ML030230486
| ML030230486 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/13/2003 |
| From: | Watts R Rochester Gas & Electric Corp |
| To: | Clark R Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EPIP 1-0, Rev 29, EPIP 1-5, Rev 52 | |
| Download: ML030230486 (68) | |
Text
"5 *An Energy East Company ROCHESTER GAS AND ELECTRIC CORPORATION
- 89 EAST AVENUE, ROCHESTER, N Y 14649-0001
- 585 546-2700 www rge corn January 13, 2003 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Mr. Robert Clark (Mail Stop O-8-E9)
Project Directorate I-1
Subject:
Revision to Emergency Plan Implementing Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244 Gentlemen:
In accordance with 10 CFR 50.4(b)(5), enclosed are revisions to Ginna Station Emergency Plan Implementing Procedures (EPIP).
We have determined, per the requirements of 10 CFR 50.54(q), that the procedure changes do not decrease the effectiveness of our Nuclear Emergency Response Plan.
Very truly yours, Richard J. Watts Manager, Nuclear Training Department Enclosures xc: USNRC Region 1 (2 copies of letter and 2 copies of each procedure)
Resident Inspector, Ginna Station (1 copy of letter and 1 copy of each procedure)
RG&E Nuclear Safety and Licensing (1 copy of letter)
Dr. Robert C. Mecredy (2 copies of letter only)
RJW/jtw
U.S. Nuclear Regulatory Commission January 13, 2003 Page 2 of 2 PROCEDURE REVISION NUMBER EPIP 1-0 29 EPIP 1-5 52
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER r2 l EPIP 1-0 REV. NO. 29 PROCEDURE NO.
GINNA STATION EVENT EVALUATION AND CLASSIFICATION TECHNICAL REVIEW EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
THIS PROCEDURE CONTAINS 41 PAGES
EPIP 1-0 GINNA STATION EVENT EVALUATION AND CLASSIFICATION 1.0- PURPOSE:
1.1 The purpose of this procedure is to provide guidance to personnel in evaluating Ian situations which may require activation of the Nuclear Emergency Response and direct them to appropriate implementing procedures. Prompt recognition and classification is necessary to ensure the timely activation of support functions and notification of offsite organizations.
2.0 RESPONSIBILITY
2.1 The Shift Supervisor/Emergency Coordinator (SS/EC) is responsible for initiating this procedure.
2.2 Once the EOF assumes command and control of the emergency, the EOF/Recovery Manager becomes responsible for continuing this procedure.
3.0 REFERENCES
3.1 Developmental References 3.1.1 10CFR50 Appendix E 3.1.2 NUREG-0654 3.1.3 NUREG-0696 3.1.4 Nuclear Emergency Response Plan.
(NESP 3.1.5 NUMARC Methodology for Development of Emergency Action Levels 007).
3.1.6 R.E. Ginna EAL Technical Basis Revision 29 3.2 Implementing References 3.2.1 ER-SC.4, Earthquake Emergency Plan.
3.2.2 TEG-2.0, Response Spectrum Calculation.
3.2.3 TEG-2.1, Safe Shutdown Earthquake (SSE) & Operating Basis Earthquake (OBE) Exceedence Determination.
4.0 PRECAUTIONS
4.1 For emergency events involving the Emergency Operating Procedures, classification should only be made after the diagnostic steps of E-0 have been completed.
4.2 In the event that multiple "Initiating Conditions" are identified, the SS/EC shall review each condition and classify according to the highest Emergency Classification Level obtained.
4.3 During any event, the entire procedure should be reviewed for possible reclassification of the event.
4.4 See Definitions (Attachment 2) for terms used in this procedure.
4.5 Any time a current set of conditions is identified which requires an Emergency Classification, the event shall be classified and declared, even if the condition identified is quickly corrected.
4.5.1 Conditions which depend on delayed evaluation results, i.e., chemistry, RP analysis, etc., shall be classified and declared as soon as the results are known.
5.0 PREREQUISITES
or at 5.1 Entry to this procedure may be directed by various other plant procedures the discretion of the SS/EC.
6.0 ACTIONS
6.1 In the event of an abnormal condition the Control Room Personnel will:
6.1.1 Perform the immediate responses defined in the appropriate plant procedures.
wallchart 6.1.2 Identify the initiating conditions using either the guidelines of the EAL or Attachment 1 of this procedure.
6.1.3 Implement applicable Emergency Plan procedures based on Appendix guidelines.
6.1.3.1 EPIP 1-4, General Emergency 6.1.3.2 EPIP 1-3,Site Area Emergency 6.1.3.3 EPIP 1-2, Alert 6.1.3.4 EPIP 1-1, Unusual Event
6.2 Periodically re-evaluate the condition after initial classification of accident using the EAL wall chart or Attachment 1.
6.3 At the conclusion of the event, refer to EPIP 3-4, Emergency Termination and Recovery.
6.4 Any time previous initiating conditions are identified that would have warranted an Emergency Classification but they are no longer in effect at the time of identification, and do not require further evaluation or analysis, the event will be classified, but not declared.
6.4.1 Conditions which are corrected, but may require further safety evaluation or analysis, will be classified and declared.
6.4.2 The NRC will be notified any time an event is classified. This will be made by means of the NRC Emergency Notification System (ENS) phone using procedure 0-9.3 "NRC Immediate Notification".
6.4.3 The Plant Manager and Corporate Nuclear Emergency Planner (or their alternates) shall also be informed of this notification as soon as possible for notifications to Wayne County, Monroe County and New York State. For these notifications, there is no 15 minute requirement.
7.0 ATTACHMENTS
- 1. Detailed Accident Classification
- 2. Definitions
- 3. Barrier loss/potential loss
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EPIP 1-0:4 EPIP 1-0 EMERGENCY ACTION LEVELS (EALS)
INDEX 5.0 RADIOACTIVITY RELEASE/ AREA RADIATION 1.0 CRITICAL SAFETY FUNCTION STATUS TREES (CSFST) 5.1 Effluent Monitors 1.1 Sub-criticality CSFST Status Dose Projections/ Environmental Measurements 5.2 1.2 Core Cooling CSFST Status 5.3 Area Radiation Levels 1.3 Heat Sink CSFST Status 1.4 Integrity CSFST Status 6.0 ELECTRICAL FAILURES 1.5 Containment CSFST Status 6.1 Loss of AC Power Sources 6.2 Loss of DC Power Sources 2.0 REACTOR FUEL 7.0 EQUIPMENT FAILURES 2.1 Coolant Activity 7.1 Technical Specification Requirements 2.2 Failed Fuel Detectors 7.2 Safety System Failures 2.3 Containment Radiation 7.3 Loss of Indications/ Alarms/ Communication Capability 2.4 (6) Refueling Accidents 3.0 REACTOR COOLANT SYSTEM (RCS) 8.0 HAZARDS 8.1 Security Threats 3.1 RCS Leakage 8.2 Fire 3.2 Primary to Secondary Leakage 8.3 Man-Made Events 3.3 RCS Subcooling 8.4 Natural Events 4.0 CONTAINMENT 9.0 OTHER 4.1 Containment Integrity Status 4.2 Steam Generator Tube Rupture 4.3 Combustible Gas Concentrations NOTE: Changes to this attachment are required to be reflected on the EAL wall chart.
Attachment 1, Rev. 29
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EPIP 1-0:5 1.0 CRITICAL SAFETY FUNCTION STATUS TREES STATUS 1.1 Sub-criticality CSFST Status GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 1.1.3 1.1.2 1.1.1 RED path in F-0.1, RED path in F-0.1, Any failure of an automatic SUB-CRITICALITY SUB-CRITICALITY trip signal to reduce power AND Mode Applicability: range <5%
Actual or imminent entry into - (1) Power Operations AND either: - (2) Startup Manual trip is successful.
- RED path in F-0.2, CORE - (3) Hot Shutdown Mode Applicability:
COOLING - (1) Power Operations OR - (2) Startup
- RED path in F-0.3, HEAT - (3) Hot Shutdown SINK Mode Applicability
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown I Attachment 1, Rev. 29 1.2 Core Cooling CSFST Status
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( C C EPIP 1-0:6 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 1.2.2 1.2.1 RED path in F-0.2, ORANGE or RED path in CORE COOLING F-0.2, CORE COOLING AND Mode Applicability:
Functional restoration - (1) Power Operations procedures not effective - (2) Startup within 15 minutes. - (3) Hot Shutdown Mode Applicability: - (4) Hot Standby
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby 1.3 Heat Sink CSFST Status GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 1.3.1 RED path in F-0.3, HEAT SINK Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1, Rev. 29
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EPIP 1-0:7 1.4 Integrity CSFST Status GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 1.4.1 RED path on F-0.4, INTEGRITY Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby 1.5 Containment CSFST Status GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 1.5.1 RED path on F-0.5, CONTAINMENT resulting from loss of reactor coolant Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1, Rev. 29 2.0 REACTOR FUEL
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EPIP 1-0:8 2.1 Coolant Activity GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 2.1.3 2.1.2 2.1.1 Coolant sample activity Coolant sample activity Coolant sample activity:
>300 j.Ci/gm of 1-131 >300 liCi/gm of 1-131 >100% of 100/E-Bar g.Ci/gm equivalent equivalent, total specific activity AND Mode Applicability: OR Any of the following: - (1) Power Operations >1.0 liCi/gm 1-131
- RED path on F-0.4, - (2) Startup equivalent and entry into INTEGRITY - (3) Hot Shutdown conditions of Tech. Spec.
- Primary system leakage - (4) Hot Standby section 3.4.16.b.
>46 gpm Mode Applicability:
- RCS subcooling <EOP - (1) Power Operations figure MIN SUBCOOLING - (2) Startup due to RCS leakage - (3) Hot Shutdown
- Containment radiation - (4) Hot Standby monitor R-29/30 reading
>10R/hr Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1, Rev. 29
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EPIP 1-0:9 2.2 Failed Fuel Detectors GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 2.2.3 2.2.2 2.2.1 Letdown line monitor R-9 Letdown line monitor R-9 Letdown line monitor R-9
>1 OR/hr >1 OR/hr. >2R/hr AND Tave >5000 F AND Mode Applicability: Mode Applicability:
any of the following: - (1) Power Operations - (1) Power Operations
- RED path on F-0.4, - (2) Startup - (2) Startup INTEGRITY - (3) Hot Shutdown - (3) Hot Shutdown
- Primary system leakage - (4) Hot Standby
>46gpm
- RCS subcooling <EOP figure MIN SUBCOOLING due to RCS leakage
- Containment radiation monitor R-29/30 reading
>10R/hr Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1, Rev. 29
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( (9 EPIP 1-0:10 2.3 Containment Radiation GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 2.3.3 2.3.2 2.3.1 Containment radiation Containment radiation Containment radiation monitor R-29/30 reading monitor R-29/30 reading monitor R-29/30 reading
>100OR/hr >100R/hr >1 OR/hr due to RCS leakage.
Mode Applicability: Mode Applicability: Mode Applicability:
- (1) Power Operations - (1) Power Operations - (1) Power Operations
- (2) Startup - (2) Startup - (2) Startup
- (3) Hot Shutdown - (3) Hot Shutdown - (3) Hot Shutdown
- (4) Hot Standby - (4) Hot Standby - (4) Hot Standby Attachment 1, Rev. 29 2.4 Refueling Accidents or Other Radiation Monitors
( ( C, EPIP 1-0:11 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 2.4.2 2.4.1 Confirmed sustained Spent fuel pool ( reactor cavity alarm on any of the during Refueling) water level following radiation cannot be restored and monitors resulting from maintained above the spent fuel an uncontrolled fuel pool low water level alarm setpoint handling process. Mode Applicability:
- R-2 Containment Area - All Monitor
- R-5 Spent Fuel Pit
- R-12 Containment Noble Gas Mode Applicability:
- All 2.4.3 Report of visual observation of irradiated fuel uncovered.
Mode Applicability:
- All Attachment 1, Rev. 29
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EPIP 1-0:12 3.0 REACTOR COOLANT SYSTEM 3.1 RCS Leakage GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 3.1.3 3.1.2 3.1.1 RVLIS cannot be maintained Primary system leakage Unidentified or pressure
>77% with no RCPs running >46gpm boundary leakage OR Mode Applicability: greater than 1Ogpm With the Reactor - (1) Power Operations OR Vessel head removed, it - (2) Startup Identified leakage greater is reported that water - (3) Hot Shutdown than 25gpm level in the Reactor - (4) Hot Standby Mode Applicability:
Vessel is dropping in an - (1) Power Operations uncontrolled manner and - (2) Startup core uncovery is likely - (3) Hot Shutdown Mode Applicability: - (4) Hot Standby
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby
- (5) Cold Shutdown
- (6) Refueling I Attachment 1, Rev. 29
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EPIP 1-0:13 3.2 Primary to Secondary Leakage GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 3.2.2 3.2.1 Unisolable release of Unisolable release of secondary side to secondary side to atmosphere atmosphere with primary (See 3.1.2 above) with primary to secondary to secondary leakage leakage greater than
>46 gpm. 0.1gpm in the affected S/G Mode Applicability: Mode Applicability:
- (1) Power Operations - (1) Power Operations
- (2) Startup - (2) Startup
- (3) Hot Shutdown - (3) Hot Shutdown
- (4) Hot Standby - (4) Hot Standby 3.2.3 Unisolable release of secondary side to atmosphere with primary to secondary leakage >0.1 gpm in the affected AND EITHER
- Coolant activity
>300 pCi/gm of 1-131 equivalent OR
- Letdown line monitor R-9
>10 R/hr Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby I Attachment 1, Rev. 29 3.3 RCS Subcoollng
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EPIP 1-0:14 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 3.3.1 RCS subcooling <EOP figure MIN SUBCOOLING due to RCS leakage Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown I_- (4) Hot Standby Attachment 1, Rev. 29
C" C 1 EPIP 1-0:15 4.0 CONTAINMENT 4.1 Containment Integrity Status GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 4.1.4 4.1.2 4.1.1 Safety injection signal due to Rapid uncontrolled Both doors open on LOCA with less than decrease in containment containment airlock minimum operable pressure following initial OR containment heat increase due to LOCA. Inability to close containment removal equipment of OR pressure relief or purge valves Loss of primary coolant which results in a radiological RECIRC SPRAY inside containment with release pathway to the CNMT FANS PUMPS containment pressure or environment PRESS OPER REQ'D sump level response not OR
< 28 psig 2 N/A consistent with LOCA Cl or CVI valve(s) not closed
_>28 psig 2 1 conditions. when required which results in
<2 2 Mode Applicability: a radiological release pathway AND - (1) Power Operations to the environment one or more of the following - (2) Startup OR fuel clad loss indicators: - (3) Hot Shutdown Rapid uncontrolled pressure
- Coolant activity >300 [tCi/gm - (4) Hot Standby decrease following initial of 1-131 equivalent (Continued on next page) increase due to steam line
- Containment radiation break.
monitor (R-29/30) reading Mode Applicability:
>10OR/hr - (1) Power Operations
- Letdown monitor R-9 reading - (2) Startup
>10R/hr - (3) Hot Shutdown
- RED path in F-0.2, CORE - (4) Hot Standby COOLING Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby (Continued on next page)
Attachment 1, Rev. 29
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( C EPIP 1-0:16 4.1 Containment Integrity Status GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 4.1.5 4.1.3 EITHER EITHER:
Rapid uncontrolled decrease Cl or CVI valve(s) not in containment pressure closed when required following initial increase due to following confirmed LOCA LOCA OR OR Loss of primary coolant inside Inability to isolate any primary containment with containment system discharging outside pressure or sump level containment response not consistent with AND LOCA conditions Radiological release pathway AND to the environment exists as a one or more of the following result.
fuel clad damage indicators: Mode Applicability:
- ORANGE or RED path in - (1) Power Operations F-0.2, CORE COOLING - (2) Startup
- RED path in F-0.3, HEAT - (3) Hot Shutdown SINK - (4) Hot Standby
- Coolant activity
>300i. Ci/gm of 1-131 equivalent
- Containment radiation monitor R-29/R-30 reading
>1 OCR/hr
- Letdown line monitor R-9 reading >10R/hr Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby (Continued on next page) I Attachment 1, Rev. 219
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EPIP 1-0:17 4.1 Containment Integrity Status GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 4.1.6 EITHER CI or CVI valve(s) not closed when required following confirmed LOCA OR Inability to isolate any primary system discharging outside containment AND Radiological release pathway to environment exists as a result AND one or more of the following fuel clad damage indicators:
- ORANGE or RED path in F-0.2, CORE COOLING
- RED path in F-0.3, HEAT SINK
- Coolant activity
>3001g Ci/gm of 1-131 equivalent
- Containment radiation monitor reading >100R/hr
- Letdown monitor R-9 reading >10R/hr Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1, Rev. 29
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EPIP 1-0:18 4.2 Steam Generator Tube Rupture with Secondary Release GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 4.2.2 4.2.1 Unisolable secondary side line Unisolable secondary side line break with S/G tube rupture as break with S/G tube rupture as identified in E-3 "Steam identified in E-3 "Steam Generator Tube Rupture". Generator Tube Rupture" AND Mode Applicability:
one or more of the following - (1) Power Operations fuel clad damage indicators: - (2) Startup
- ORANGE or RED path in - (3) Hot Shutdown
- (4) Hot Standby F-0.2, CORE COOLING
- RED path in F-0.3, HEAT SINK
- Coolant activity
>300 [tCi/gm of 1-131 equivalent
- Containment radiation monitor R-29/30 reading
>1 OOR/hr
- Letdown monitor R-9 reading >10R/hr Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1, Rev. 29
EPIP 1-0:19 4.3 Combustible Gas Concentrations GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 4.3.1
>4% hydrogen concentration in containment Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1, Rev. 29
( C I EPIP 1-0:20 5.0 RADIOACTIVITY RELEASE/ AREA RADIATION 5.1 Effluent Monitors GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 5.1.4 5.1.3 5.1.2 5.1.1 A valid reading on one or more A valid reading on one or more A valid reading on one or A valid reading on one or more of the following monitors for of the following monitors for more of the following monitors of the following monitors for
>15 minutes >15 minutes for >15 minutes >60 minutes unless sample
- R12A7 6.00E+1 g.Ci/cc - R12A7 6.00E+0 iiCi/cc - R12A7 6.OOE-1 t.Ci/cc analysis can confirm release two times
- R14A7 5.33E0 pICi/cc -
- R14A7 5.33E-1 j.Ci/cc - R14A7 5.33E-2 .iCi/cc rates release rate thanwithin are lesslimits the 60
- R15A9 1.15E+1 p.Ci/cc - R15A7 1.15E+0 1iCi/cc minute time limit.
- R15A9 1.15E+2 ICi/cc R 11
- R31/32 reading with the - R18 Offscale High with no -
- R31/32 reading with the following condition: following condition: isolation 1 ARV 1.90E+2 mR/hr 1 A RV 1.90E+1 mR/hr - R20A Offscale High 1.38E5 cpm with o fan*
1 Safety 9.51 EQ mR/hr - R20B Offscale High - 1.41 E cpm with two fans*
1 Safety 9.51 E+1 mR/hr cpm with one fan 2 Safeties 4.76E+1 mR/hr 2 Safeties 4.76E0 mR/hr - R21 Offscale High with no -7.42E6 3 Safeties 3.17E+1 mR/hr 3 Safeties 3.17E0 mR/hr isolation - 5.36E6 cpm with two-fans*
4 Safeties 2.38E+1 mR/hr 4 Safeties 2.38E0 mR/hr - R22 Offscale High with no - R13 2.34E4 cpm unless dose assessment can unless dose assessment can isolation - R14 6.0E5 cpm confirm releases at the site confirm releases at the site - R31/32 reading with the - R15 2.94E5 cpm boundary are below the bou ndary are below the following condition: - R18 3.60E5 cpm with no following within the 15 minute following within the 15 minute 1 ARV 1.90E0 mR/hr isolation limit limit 1 Safety 9.51 E-1 mR/hr - R20A 4.08E4 cpm
- 1000 mR TEDE - 100 mR TEDE 2 Safeties 4.76E-1 mR/hr - R20B 5.20E3 cpm
- 5000 mR CDE thyroid - 500 mR CDE thyroid 3 Safeties 3.17E-1 mR/hr - R21"* 5.00E4 cpm with no II - 1000 mR/hr external exposure - 100 mR/hr external exposure 4 Safeties 2.38E-1 mR/hr isolation rate rate unless dose assessment can - R22** 9.20E4 cpm with no
- 5000 mR/hr thyroid exposure - 500 mR/hr thyroid exposure confirm releases at the site isolation for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of inhalation rate for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of inhalation boundary are below - R31/32 reading 0.2 mR/hr Mode Applicability: Mode Applicability: - 10 mR TEDE or with 1 ARV or 1 Safety open.
- All -All - 10 mR/hr external exposure Mode Applicability:
rate - All within the 15 minute limit Mode Applicability:
-All During containment purge R-21 and R-22 have no remote indications in the Control Room or on PPCS. MCB annunciators Attachment 1, Rev. 29 AA-2 or K-27 may indicate a possible release; however, local observation must be performed.
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EPIP 1-0:21 5.2 Dose Projections/ Environmental Measurements/Release Rates GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 5.2.5 5.2.4 5.2.2 5.2.1 Dose projections or field Dose projections or field Confirmed sample Confirmed sample surveys resulting from actual surveys resulting from actual analysis for gaseous or analysis for gaseous or or imminent release which or imminent release which liquid release rates in liquid release rates in indicate doses/dose rates in indicate dose rates in excess excess of two hundred excess of two times release excess of 1OOOmR/hr external of IOOmR/hr external exposure times release rate limits for rate limits for >60 min exposure rate at the Site rate at the Site Boundary or >15 min Mode Applicability:
Boundary or beyond beyond Mode Applicability: - All OR OR - All Dose projections or field Dose projections or field 5.2.3 surveys resulting from actual surveys resulting from actual Dose projections or field or imminent release which or imminent release which surveys resulting from actual indicate >50OOmR/hr thyroid indicate >5OOmR/hr thyroid or imminent release which exposure dose rate at the Site exposure dose rate at the Site indicate >10mRihr external Boundary or beyond Boundary or beyond exposure rate at the Site OR OR Boundary or beyond Dose projections or field Dose projections or field OR surveys resulting from actual surveys resulting from actual Dose projections or field or imminent release which or imminent release which surveys resulting from actual indicate >10OOmR TEDE dose indicate >1OOmR TEDE dose or imminent release which at the Site Boundary at the Site Boundary indicate >1OmR TEDE dose or beyond or beyond the Site Boundary or beyond OR OR Dose projections or field Dose projections or field Mode Applicability:
surveys indicate >5000mR surveys resulting from actual - All CDE thyroid dose at the Site or imminent release which Boundary or beyond. indicate >500mR CDE thyroid dose at the Site Boundary or Mode Applicability: beyond.
-All Mode Applicability:
-All Attachment 1, Rev. 29
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EPIP 1-0:22 5.3 Area Radiation Levels GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 5.3.2 5.3.1 Sustained area radiation Any sustained direct area levels > 15 mR/hr in radiation monitor readings either Control Room > 100 times alarm or OR off-scale high resulting from Central Alarm Station and an uncontrolled process.
Secondary Alarm Station Mode Applicability:
Mode Applicability: - All
- All 5.3.3 Sustained abnormal area radiation levels > 8 R/hr within any of the following areas:
- Containment
- Auxiliary Building
- Turbine Building
- Emergency Diesel Bldg.
- Screen house
- Standby Auxiliary Feedwater Building AND Access is required to establish or maintain Cold Shutdown Mode Applicability:
- All Attachment 1, Rev. 29
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EPIP 1-0:23 6.1 Loss of AC Power Sources GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 6.1.5 6.1.4 6.1.2 6.1.1 Loss of all safeguards Loss of both trains of AC Loss of both trains of AC Loss of ability to supply bus AC power busses for greater busses for greater than 15 power to the safeguard AND EITHER: than 15 minutes minutes trains from offsite circuits power restoration to any Mode Applicability: Mode Applicability: 751 and 767 for greater than safeguards train is not likely in - (1) Power Operations - (5) Cold Shutdown 15 minutes 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> - (2) Startup - (6) Refueling Mode Applicability:
OR - (3) Hot Shutdown - (D) Defueled - All Actual or imminent entry into - (4) Hot Standby 6.1.3 ORANGE or RED path Available safeguards train on F-0.2, CORE AC power reduced to COOLING only one of the following Mode Applicability: sources for >15 minutes.
- (1) Power Operations - EDG 1A (14/18)
- (2) Startup - EDG 1B (16/17)
- (3) Hot Shutdown - Station Auxiliary
- (4) Hot Standby Transformer 12A
- Station Auxiliary Transformer 12B Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1, Rev. 29
C C EPIP 1-0:24 6.2 Loss of DC Power Sources GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 6.2.2 6.2.1
<108vdc bus voltage <108vdc bus voltage indications on 125vdc indications on 125vdc batteries 1A AND 1B for >15 batteries 1A AND 1B for minutes. >15 minutes.
Mode Applicability: Mode Applicability:
- (1) Power Operations - (5) Cold Shutdown
- (2) Startup - (6) Refueling
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1, Rev. 29
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EPIP 1-0:25 7.0 EQUIPMENT FAILURES 7.1 Technical Specification Requirements GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 7.1.1 Plant is not brought to the required operating mode within Technical Specifications LCO Required Action Completion Time Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1, Rev. 29
(7 C C EPIP 1-0:26 7.2 Safety Failures or Control Room Evacuation GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 7.2.5 7.2.2 7.2.1 Entry into AP-CR.1 "Control Turbine failure generated Report of main turbine failure Room Inaccessability" missiles results in any visible resulting in casing AND structural damage to plant penetration or damage to Control of core cooling vital equipment. turbine seals or generator cannot be established Mode Applicabilitv seals per AP-CR.1 "Control - (1) Power Operations Mode Applicability:
Room Inaccessibility" - (2) Startup - (1) Power Operations within 20 minutes - (3) Hot Shutdown - (2) Startup Mode Applicability: - (4) Hot Standby - (3) Hot Shutdown
- (1) Power Operations 7.2.3 - (4) Hot Standby
- (2) Startup Entry into AP-CR.1 "Control
- (3) Hot Shutdown Room Inaccessability"
- (4) Hot Standby Mode Applicability:
- (5) Cold Shutdown - (1) Power Operations
- (6) Refueling - (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby
- (5) Cold Shutdown
- (6) Refueling 7.2.4 Reactor coolant temperature cannot be maintained <200'F Mode Applicability:
- (5) Cold Shutdown
- (6) Refueling Attachment 1, Rev. 29
( V EPIP 1-0:27 7.3 Loss of IndIcations/Communication Capability GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 7.3.4 7.3.3 7.3.1 Loss of annunciators or Unplanned loss of annunciators Unplanned loss of annunciators indications on any of the or indications on any of the or indications on any of the following Control Room Panels following Control Room Panels following Control Room Panels
-A for greater than 15 minutes for greater than 15 minutes
-AA -A -A
-B -AA -AA
-C -B -B
-D -C -C
-E -D -D
-F -E -E
-G -F -F AND -G -G Complete loss of ability AND AND to monitor any critical increased surveillance is increased surveillance is safety function status required for safe plant required for safe plant AND operation operation A plant transient in AND EITHER Mode Applicability:
progress - A plant transient in - (1) Power Operations Mode Applicability: progress - (2) Startup
- (1) Power Operations OR - (3) Hot Shutdown
- (2) Startup - PPCS is unavailable - (4) Hot Standby
- (3) Hot Shutdown Mode Applicability: 7.3.2
- (4) Hot Standby - (1) Power Operations Loss of all communications
- (2) Startup capability affecting the
- (3) Hot Shutdown ability to either:
- (4) Hot Standby - perform routine operations OR
- Notify offsite agencies or personnel Mode Applicability:
-All Attachment 1, Rev. 29
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f, EPIP 1-0:28 8.0 HAZARDS 8.1 Security Threats GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 8.1.4 8.1.3 8.1.2 8.1.1 Security event which Intrusion into plant security Intrusion into plant Protected Bomb device or other indication results in: vital area by an adversary Area by an adversary of attempted sabotage
- Loss of plant control OR OR discovered within plant from the control room Any security event which Any security event which Protected Area OR represents actual or likely represents an actual or OR
- Loss of remote failures of plant systems substantial degradation of the Notification of any credible site shutdown capability needed to protect the public level of safety of the plant. specific security threat by the Mode Applicability: Mode Applicability: Mode Applicability: Security Shift Supervisor
-All - -All - All or outside agency (NRC, military or law enforcement Mode Applicability:
- All Attachment 1, Rev. 29
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9, EPIP 1-0:29 8.2 Fire or Explosion GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 8.2.2 8.2.1 Fire or explosion in any of the Confirmed fire in any of the following plant areas which following plant areas not results in extinguished within 15 minutes EITHER of control room notification visible damage to plant - Intermediate Building equipment or structures - TSC needed for safe shutdown - Service Building OR - Contaminated Storage Loss of a safety system Building
- Intermediate Building - Control Building
- TSC - Containment Building
- Service Building - Auxiliary Building
- Contaminated Storage - Turbine Building Building - Emergency Diesel
- Control Building Building
- Containment Building - Standby Auxiliary
- Auxiliary Building Feedwater Building
- Turbine Building - Screen House
- Emergency Diesel Mode Applicability:
Building - All
- Standby Auxiliary Feedwater Building
- Screen House Mode Applicability:
-All Attachment 1, Rev. 29
( C ii EPIP 1-0:30 8.3 Man-Made Events GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 8.3.4 8.3.1 Vehicle crash or projectile Vehicle crash into or impact which precludes projectile which impacts personnel access to or plant structures or systems damages equipment in the within Protected Area following plant vital areas Boundary
- Control Building Mode Applicability:
- Containment Building - All
- Auxiliary Building 8.3.2
- Intermediate Building Report by plant personnel of
- Emergency Diesel Building an explosion within Protected
- Standby Auxiliary Area Boundary resulting in Feedwater Building visible damage to permanent
- Screen House structures or equipment Mode Applicability: Mode Applicability:
- All - All 8.3.5 8.3.3 Report or detection of toxic or Report or detection of toxic or flammable gases within the flammable gases that could following plant areas, in enter or have entered within concentrations that will be life the Protected Area Boundary threatening to plant personnel in amounts that could affect or precludes access to the health of plant personnel or equipment needed for safe safe plant operation plant operations OR
- Control Building Report by local, county or
- Containment Building state officials for potential
- Auxiliary Building evacuation of site personnel
- Intermediate Building based on offsite event
- Emergency Diesel Building Mode Applicability:
- Standby Auxiliary - All Feedwater Building
- Screen House Mode Applicability:
-All Attachment 1, Rev. 29
( (I EPIP 1-0:31 8.4 Natural Events GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 8.4.4 8.4.1 Earthquake felt in plant by Earthquake felt in plant by any plant operations personnel any plant operations personnel AND AND Confirmation of earthquake of Confirmation of earthquake of an intensity greater than 0.08g an intensity greater than O.Olg per ER-SC.4 "Earthquake per ER-SC.4 "Earthquake Emergency Plan" Emergency Plan" Mode Applicability: Mode Applicability:
- All - All 8.4.5 8.4.2 Sustained winds >75mph Report by plant personnel of OR tornado striking within plant Tornado strikes one of the Protected Area Boundary following plant vital areas Mode Applicability:
- Control Building - All
- Containment Building (Continued on next page)
- Auxiliary Building
- Intermediate Building
- Emergency Diesel Building
- Standby Auxiliary Feedwater Building
- Screen House Mode Applicability:
-All (Continued on next page)
Attachment 1, Rev. 29
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EPIP 1-0:32 8.4 Natural Events GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 8.4.6 8.4.3 Any natural event which results Deer Creek flooding over in a report of visible structural entrance road bridge handrail damage or assessment by OR control room personnel of Lake level >252 ft actual damage to equipment OR needed for safe plant operation Screen House Suction in any of the following plant Bay water level <19 feet or areas:
- 17.5 feet by manual level
- Control Building measurement
- Containment Building Mode Applicability:
- Auxiliary Building - All
- Intermediate Building Emergency Diesel Building
- Standby Auxiliary Feedwater Building
-Screen House Mode Applicability:
- All 8.4.7 Flood water accumulating on screen house operating floor OR Lake level >253 ft OR Screen House Suction Bay water level
- 16 feet or
- 14.5 feet by manual level measurement Mode Applicability:
-All Attachment 1, Rev. 29
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EPIP 1-0:33 9.0 OTHER GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT PROCEED TO EPIP 1-4 PROCEED TO EPIP 1-3 PROCEED TO EPIP 1-2 PROCEED TO EPIP 1-1 9.1.7 9.1.5 9.1.3 9.1.1 In the opinion of the Shift In the opinion of the Shift Any event, which in the Any event, which in the Supervisor or Emergency Supervisor or Emergency opinion of the Shift opinion 'of the Shift Supervisor Coordinator, events are in Coordinator, events are in Supervisor or Emergency or Emergency Coordinator, progress which indicate progress which indicate actual Coordinator, that could cause that could lead to or has led to actual or imminent core or likely failures of plant or has caused actual a potential degradation of the damage and the potential systems needed to protect the substantial degradation of the level of safety of the plant for a large release of public. Any releases are not level of safety of the plant Mode Applicability:
radioactive material in expected to result in Mode Applicability: - All excess of EPA PAGs exposures which exceed - All 9.1.2 outside the site boundary EPA PAGs 9.1.4 Any event, which in the Mode Applicability: Mode Applicability: Any event, which in the opinion of the Shift
- All - All opinion of the Shift Supervisor Supervisor or Emergency 9.1.8 9.1.6 or Emergency Coordinator, Coordinator, that could lead Any event, which in the Any event, which in the that could lead or has led to a to or has led to a potential loss opinion of the Shift opinion of the Shift Supervisor loss or potential loss of either of containment (Attachment 3)
Supervisor or Emergency or Emergency Coordinator, fuel clad or RCS barrier Mode Applicability:
Coordinator, that could or has that could or has led to either: (Attachment 3) - (1) Power Operations led to a loss of any two fission - Loss or potential loss of Mode Applicability: - (2) Startup product barriers and loss or both fuel clad and RCS - (1) Power Operations - (3) Hot Shutdown potential loss of the third barrier (Attachment 3) - (2) Startup - (4) Hot Standby (Attachment 3) OR - (3) Hot Shutdown Mode Applicability: - Loss or potential loss of - (4) Hot Standby
- (1) Power Operations either fuel clad and RCS
- (2) Startup barrier in conjunction
- (3) Hot Shutdown with a loss of containment
- (4) Hot Standby (Attachment 3)
Mode Applicability:
- (1) Power Operations
- (2) Startup
- (3) Hot Shutdown
- (4) Hot Standby Attachment 1, Rev. 29
ATTACHMENT 2 DEFINITIONS Actuate To put into operation; to move into action; commonly used to refer to automated, multi-faceted operations. "Actuate ECCS".
Adversary As applied to security EALs, an individual whose intent is to commit sabotage, disrupt station operations or otherwise commit a crime on station property.
Adverse Meteorology - Low wind speed and low dispersion of effluents.
Alert - Events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant.
Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.
Available - The state or condition of being ready and able to be used (placed into operation) to accomplish the stated (or implied) action or function. As applied to a system, this requires the operability of necessary support systems (electrical power supplies, cooling water, lubrication, etc).
Can/Cannot be - The current value or status of an identified parameter relative to that determined specified can/cannot be ascertained using all available indications (direct and indirect, singly or in combination).
Can/Cannot be - The value of the identified parameter(s) is/is not able to be kept maintained above/below specified limits. This determination includes making an above/below evaluation that considers both current and future system performance in relation to the current value or trend of the parameter(s). Neither implies that the parameter must actually exceed the limit before the action is taken nor that the action must be taken before the limit is reached.
Can/Cannot be - The value of the identified parameter(s) is/is not able to be returned to restored above/below above/below specified limits after having passed those limits. This determination includes making an evaluation that considers both current and future systems performances in relation to the current value and trend of the parameter(s). Does not imply any specific time interval but does not permit prolonged operation beyond a limit without taking the specified action.
As applied to loss of electrical power sources (ex.:power cannot be restored to any vital bus in <4 hrs) the specified power source cannot be returned to service within the specified time. This determination includes making an evaluation that considers both current and future restoration capabilities. Implies that the declaration should be made as soon as the determination is made that the power source cannot be restored within the specified time.
Classified Identify an EAL that corresponds to plant conditions
Close - To position a valve or damper so as to prevent flow of the process fluid.
- To make an electrical connection to supply power Confirm/Confirmation - To validate, through visual observation or physical inspection, that an assumed condition is as expected or required, without taking action to alter the "as found" configuration.
Control - Take action, as necessary, to maintain the value of a specified parameter within applicable limits; to fix or adjust the time, amount, or rate of; to regulate or restrict.
Core Failure
- Fission product release to containment atmosphere that results in a reading of > 1000 REM/HR on containment area monitor R-2, R-29 or R-30.
- Use of the New York State Radiological Emergency Data Form in Declared procedure EPIP 1-5 to notify offsite agencies of a classified event.
Decrease - To become progressively less in size, amount, number, or intensity.
Discharge - Removal of a fluid/gas from a volume or system.
ECCS - High and low pressure safety injection
- Accumulators Enter - To go into.
Establish - To perform action necessary to meet a stated condition. "Establish communication with the Control Room."
Evacuate - To remove the contents of; to remove personnel from an area.
Exceeds - To go beyond a stated or implied limit, measure, or degree.
Exist - To have being with respect to understood limitations or conditions.
Facility - The Protected Area of the plant. The area within the security fence Failed Fuel - An increase in primary coolant activity reflected by an unexplained increase on failed fuel monitor (R-9) which exceeds its high alarm setpoint. If R-9 reading unavailable or unreliable, the failed fuel condition would be verified by a primary sample analysis.
Failure - A state of inability to perform a normal function.
Fire - The observance of flames or if any doubt exists due to excessive smoke, inaccessible location, a fire should be assumed to be present.
General Emergency - Events are in progress or have occurred which involve actual or imminent substantial core degradation or melting with potential loss of containment integrity. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.
Hazards - Aircraft crash, explosion, missiles, toxic gas, flammable gas, or turbine blade failures.
If - Logic term which indicates that taking the action prescribed is contingent upon the current existence of the stated condition(s). If the identified conditions do not exist, the prescribed action is not to be taken and execution of operator actions must proceed promptly in accordance with subsequent instructions.
Increase - To become progressively greater in size, amount, number or intensity.
Indicate - To point out or point to; to display the value of a process variable; to be a sign or symbol.
Initiate - The act of placing equipment or a system into service, either manually or automatically. Activation of a function or protective feature (i.e. initiate a manual trip).
Injection - The act of forcing a fluid into a volume or vessel.
Inoperable - Not able to perform it's intended function.
Intrusion - The act of entering without authorization.
LOCA - Entry into E-1.
Loss - Failure of operability or lack of access to.
Loss of all - Total loss of wind speed, wind direction and temperature from the Meteorological primary weather tower onsite and of wind direction and wind speed Indications from the back up weather tower located at Station 13A (accessible using EPIP 2-2), and all off-site sources available to the on-shift RP Tech.
Loss of Secondary - Entry into E-1.
Coolant Maintain - Take action, as necessary, to keep the value of the specified parameter within the applicable limits.
Monitor - Observe and evaluate at a frequency sufficient to remain apprised of the value, trend, and rate of change of the specified parameter.
Notify - To give notice of or report the occurrence of; to make known to; to inform specified personnel; to advise; to communicate; to contact; to relay.
OBE - Operating Basis Earthquake. An earthquake having 0.08g peak ground acceleration.
Open - To position a valve or damper so as to allow flow of the process fluid.
To break an electrical connection which removes a power supply from
. an electrical device.
To make available for entry or passage by turning back, removing, or
- clearing away.
Operable - Able to perform it's intended function.
Perform - To carry out an action; to accomplish; to affect; to reach an objective.
Periodically - As plant conditions change.
Plant Building - Turbine Building, Serv. Building, Containment, Aux. Building, Standby Aux. Feed Building or the Screen House, Contaminated Storage Building or Upper Radwaste Storage Building.
Primary System - The pipes, valves, and other equipment which connect directly to the reactor vessel or reactor coolant system such that a reduction in reactor coolant system pressure will effect a decrease in the steam or water pressure being discharged through an unisolated break in the system.
Radiation Monitor - Any permanent or temporary area or process monitor.
Remove - To change the location or position of.
Report . To describe as being in a specific state.
Require - To demand as necessary or essential.
Restore - Take the appropriate action required to return the value of an identified parameter to within applicable limits.
- Describes an increase in a parameter as the result of an operator or Rise automatic system.
Safe Shutdown - Minimum equipment required by Appendix "R" procedures.
Equipment Sample - To perform an analysis on a specified media to determine its properties.
SGTR . Entry into E-3.
Shutdown - To perform operations necessary to cause equipment to cease or suspend operation; to stop. "Shutdown unnecessary equipment."
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 result in exposure levels which exceed EPA Protective Action Guideline exposure levels except near the site boundary.
Sustained Prolonged. Not intermittent or of transitory nature.
Sustained Winds - The five minuted average based on a PPCS reading from the 150 foot or 250 foot Met Tower wind speed indicator.
SSE - Safe Shutdown Earthquake. An earthquake having 0.2g peak ground acceleration.
TEDE - Total Effective Dose Equivalent.
Thyroid Dose - Thyroid dose is assumed to be the same as Committed Dose Equivalent (CDE).
Trip - To de-energize a pump or fan motor; to position a breaker so as to interrupt or prevent the flow of current in the associated circuit; to manually activate a semi-automatic feature.
- To take action to cause shutdown of the reactor by opening the reactor trip breaker.
- Total loss of Condensate, Mainfeed, all Auxiliary Feedwater and Total Loss of All Standby Auxiliary Feedwater.
Feedwater Uncontrolled - An evolution lacking control but is not the result of operator action.
Unexplained - A condition where parameters/condition exist that are not normal for current plant status and are not a result of operator action.
Unmonitored - A release of radioactive material to the environment which does not Release pass through an area or process monitor.
Unplanned - Not as an expected result of deliberate action.
Until - Indicates that the associated prescribed action is to proceed only so long as the identified condition does not exist.
Unusual Event - 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.
Valid - Supported or corroborated on a sound basis.
Vent - To open an effluent (exhaust) flowpath from an enclosed volume; to reduce pressure in an enclosed volume.
Verify - To confirm a condition and take action to establish that condition if required. "Verify reactor trip, verify SI pumps running."
Vital Areas - Areas of the plant containing equipment or machinery that could affect the safe operation or shutdown of the plant.
Whole Body - Whole body dose is assumed to be the same as Total Effective Dose Dose Equivalent (TEDE).
EPIP 1-0:39 Attachment 3 BARRIER LOSS/POTENTIAL LOSS Fuel Cladding Potential Loss Loss ORANGE path in F-0.2, CORE COOLING RED path in F-0.2, CORE COOLING RED path in F-0.3, HEAT SINK Coolant activity > 300 pCi/cc of 1-131 Core Exit Thermocouple Readings > 700 OF Core Exit Thermocouple Readings > 1200 OF RVLIS <77% w/ no RCPs running Containment rad monitor reading >100 R/hr Emergency Coordinator Judgment Letdown Monitor (R-9) reading > 10 R/hr Emergency Coordinator Judgment RCS Potential Loss Loss RED path on F-0.4, INTEGRITY RCS subcooling < EOP Fig. MIN SUBCOOLING due to RCS leakage RED path on F-0.3, HEAT SINK Unisolable secondary side line break with SG tube rupture as identified in E-3 "Steam Generator Tube Rupture" Primary system leakage > 46 gpm Containment radiation monitor reading > 10 R/hr Emergency Coordinator Judgment Emergency Coordinator Judgment Page 1 of 2
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EPIP 1-0:40 Attachment 3 BARRIER LOSSIPOTENTAIL LOSS Containment I I Potential Loss Loss RED path F-0.5, CONTAINMENT Rapid uncontrolled decrease in Containment Pressure following Initial increase Either: Loss of primary coolant Inside containment with containment pressure or Core exit thermocouples >1200 OF sump level response not consistent with LOCA conditions, i.e.
OR unexpected changes occur in these parameters that are not explainable Core exit thermocouples >700 OF with RVLIS <77% (no RCPs) due to operator actions or automatic system actions.
AND Restoration procedures not effective within 15 minutes Safety injection signal due to LOCA with < the minimum containment Either:
cooling safeguards equipment operating: Cl or CVI isolation required and Cl or CVI valve(s) not closed when CNMT pressure <28 pslg: 2 CNMT Recirc Fans required OR CNMT pressure >28 psig: 2 CNMT Spray Pumps Inability to isolate any primary system discharging outside containment OR AND 2 CNMT Recirc Fans Radiological release pathway to the environment exists and 1 CNMT Spray Pump Containment pressure 60 psig and increasing Release of secondary side to atmosphere with primary to secondary leakage greater than tech spec allowable of 0.1 GPM per steam generator
>_4 % hydrogen concentration In containment Both doors open on containment airlock OR Inability to close containment pressure relief or purge valves which results in a radiological release pathway to the environment OR Cl or CVI valve(s) not closed when required which results in a radiological release pathway to the environment Containment radiation monitor reading >1000 R/hr Emergency Coordinator Judgment Emergency Coordinator Judgment A B A Page 2 ot 2
ROCHESTER GAS & ELECTRIC CORPORATION GINNA STATION I
Controlled Copy Number CJ3 Revision Number 52 Procedure Number EPIP 1-5 NOTIFICATIONS 01113 /1o3 Effective Date Category 1.0 This procedure contains 24..4_ pages
/
NOTIFICATIONS 1.0 PURPOSE The purpose of this procedure is to specify the means by which notifications are made to station personnel for all emergency action levels, to expedite the notification of selected RG&E personnel to augment the emergency response organization and notify offsite agencies.
2.0 RESPONSIBILITY 2.1 The Shift Supervisor, Emergency Coordinator or EOF/Recovery Manager is responsible for making the decision to notify offsite agencies.
2.2 Ginna Station Control Room personnel are responsible for implementing this procedure.
2.3 Community Alert Network (CAN) is responsible for activating the onsite/offsite responders.
2.4 The Corporate Nuclear Emergency Planner is responsible for maintaining the station call lists up to date on a quarterly basis.
3.0 REFERENCES
3.1 Developmental References 3.1.1 Nuclear Emergency Response Plan 3.2 Implementing References 3.2.1 EPIP 1-0, Ginna Station Event Evaluation and Classification 3.2.2 EPIP 2-1, Protective Action Recommendations (PARs) 3.2.3 0-9.3, NRC Immediate Notification 3.2.4 10 CFR 26, Fitness for Duty Programs 3.2.5 P-9, Radiation Monitoring System 3.2.6 EPIP 2-2, Obtaining Meteorological Data and Forecasts and their use in Emergency Dose Assessment 3.2.7 ER-SC.9, Security Event Plan
EPIP 1-5:2 3.2.8 EPIP 4-7, Public Information Organization Staffing 3.2.9 EPIP 5-7, Emergency Organization 4.0 PRECAUTIONS 4.1 New York State, Wayne and Monroe Counties must be notified of all Emergency Classifications within 15 minutes of a declaration.
4.2 The Licensee should notify the USNRC immediately after notification of the appropriate State and local agencies but the notification shall not be later than one hour after the time the licensee declares one of the Emergency Classes.
4.3 Attachment 4 is a specialized list of resources that are available during an emergency.
5.0 PREREQUISITES An Emergency has been declared in accordance with EPIP 1-0, Ginna Station Event Evaluation and Classification or offsite assistance has been requested by RG&E personnel.
6.0 ACTIONS 6.1 Shift Supervisor, Emergency Coordinator, EOF/Recovery Manager 6.1.1 Ensure that notifications of all emergency declarations to New York State, Wayne and Monroe Counties are made within 15 minutes of declaring an emergency, in accordance with Attachment 3.
6.1.2 The licensee should notify the USNRC immediately after notification of the appropriate State or local agencies and the notification shall not be later than one hour after the time the licensee declares one of the Emergency Classes using procedure 0-9.3 "NRC Immediate Notification".
6.1.3 If Control Room is unable to complete notifications, notify Emergency Preparedness representative.
Peter Polfleit Business 6772 Home 315-524-7101 Pager 585-527-2207 Cellular 585-315-1201 OR Frank Cordaro Business 3108 Home 315-524-2924 Pager 585-527-3650 Cellular 585-315-1277 OR
EPIP 1-5:3 Tim Laursen Business 6185 Home 585-396-1149 Pager 585-528-5982 Cellular 585-315-1854 OR Richard Watts Business 8706 Home 585-425-2644 Pager 585-527-3749 Cellular 585-315-1204 OR Jill Willoughby Business 4033 Home 585-787-9075 Pager 585-528-3295 Cellular 585-315-1205 6.1.4 Upon notification of an Unusual Event at Ginna Station, direct the control room personnel to implement section 6.2.1 of this procedure. If the event is an Alert or higher, implement section 6.2.2.
6.1.5 If additional assistance is required, refer to the NOG E-Plan phone list (in the RG&E telephone directory) in the Control Room and all Emergency Response Facilities, for phone numbers of emergency response personnel.
6.2 Control Room Personnel 6.2.1 Unusual Event - Go to Attachment 1 6.2.2 Alert Classification or Higher - Go to Attachment 2 6.2.3 When offsite assistance has been requested - Go to Attachment 5 7.0 ATTACHMENTS
- 1. Unusual Event Notifications
- 2. Alert or Higher Notifications
- 3. Instructions for New York State Radiological Emergency Data Form 3a. New York State Radiological Emergency Data Form (Part I) 3b. New York State Radiological Emergency Data Form (Part il) 3c. Instructions for Event 1 and Event 2 Printouts and Plant Status Report 3d. Event 1 Supplemental Information Form 3e. Plant Status Report (PPCS not available)
EPIP 1-5:4 7.0 ATTACHMENTS (Cont'd.)
- 4. Specialized Resource List
- 5. Notifications When Offsite Assistance Has Been Requested
- 6. Emergency Planning Contingency Notification
- 6. Management Notification Roster (This attachment is controlled by Nuclear Emergency Preparedness.
It is not included as part of the distributed procedure)
EPIP 1-5:5 Attachment 1, Rev. 52
/ Page 1 of 3 UNUSUAL EVENT NOTIFICATIONS
- 1. Report information to NEW YORK STATE, WAYNE and MONROE counties within 15 minutes of declaring the emergency via RECS Line using New York State Radiological Emergency Data Form (Part I) Attachment 3a. Fax the New York State Radiological Emergency Data Form (Part I) Attachment 3a to New York State, Wayne County, Monroe County, TSC, EOF, Survey Center and Joint Emergency News Center.
- 2. Notify USNRC immediately after the notification of the State and Counties, using procedure 0-9.3, NRC Immediate Notification
- 3. Activate the following positions by stating the following:
"We have an UNUSUAL EVENT at Ginna Station based on (Initiating Condition)
Please report to the Technical Support Center. The event was declared at hrs. We need to remind you of the Fitness for Duty Requirements.
Are you available to report for Duty at this time? If not, we are requesting that you standby so you can be notified for the next call in shift".
A TSC Manager: Report to the TSC to support the Control Room with offsite communications.
Joe Widay Business 3250 Will Report (YES/NO)
Home 585-586-2679 Pager 585-528-3977 Cellular 585-315-0343 OR Will Report (YES/NO)
Dick Marchionda Business 3699 Home 315-926-0324 Pager 585-464-4403 Cellular 585-315-0344 OR Will Report (YES/NO)
Jack St. Martin Business 3641 Home 585-586-5676 Pager 585-464-5287 Cellular 585-315-0803
EPIP 1-5:6 Attachment 1, Rev. 52 Page 2 of 3 UNUSUAL EVENT NOTIFICATIONS B. Technical Assessment Manager: Report to the TSC to support the Control Room with offsite communications.
Ron Ploof Business 3673 Will Report (YES/NO)
Home 585-381-9379 Pager 585-783-7872 Cellular 585-315-0551 OR Will Report (YES/NO)
Brian Flynn Business 3734 Home 585-293-1565 Pager 585-464-5134 Cellular 585-315-0550 OR Will Report (YES/NO)
Peter Bamford Business 3832 Home 585-924-0490 Pager 585-528-3166 Cellular 585-315-1242 C. Operations Assessment Manager: Report to the TSC to support the Control Room with offsite communications.
Terry White Business 3667 Will Report (YES/NO)
Home 585-346-2575 Pager 585-464-7382 Cellular 585-315-0345 OR Will Report (YES/NO)
Pete Sidelinger Business 3314 Home 585-671-3198 Pager 585-463-9830 OR Will Report (YES/NO)
Bill Everett Business 3812 Home 315-589-8156 Pager 585-527-7461 Cellular 585-315-0359 D. NRC Resident Inspector: Informational call only Ken Kolaczyk Business 3265 Home 585-924-5187 Pager 1-800-944-2337 (then dial personal ID# 53133)
EPIP 1-5:7 Attachment 1, Rev. 52 Page 3 of 3 UNUSUAL EVENT NOTIFICATIONS E. Notify Nuclear Emergency Preparedness:
'This is the Ginna Control Room. We have declared an Unusual Event. Can you be the Emergency Planning contact? Your duties are: (a) Inform the government officials; (b) inform Public Relations; (c) contact the PSC; and (d) contact the financial department."
Peter Polfleit Business 6772 Home 315-524-7101 Pager 585-527-2207 Cellular 585-315-1201 OR Frank Cordaro Business 3108 Home 315-524-2924 Pager 585-527-3650 Cellular 585-315-1277 OR Tim Laursen Business 6185 Home 585-396-1149 Pager 585-528-5982 Cellular 585-315-1854 OR Richard Watts Business 8706 Home 585-425-2644 Pager 585-527-3749 Cellular 585-315-1204 OR Jill Willoughby Business 4033 Home 585-787-9075 Pager 585-528-3295 Cellular 585-315-1205
- 4. Ifthe Unusual Event lasts greater than one (1) hour, report information using the New York State Radiological Emergency Data Forms (Part I) Attachment 3a to New York State, Wayne County, Monroe County, TSC, EOF, Survey Center and Joint Emergency News Center each hour from the time the previous notification was made. Fax the New York State Radiological Emergency Data Form (Part I) Attachment 3a to New York State, Wayne County, Monroe County, TSC, EOF, Survey Center and Joint Emergency News Center after each report.
EPIP 1-5:8 Attachment 2, Rev. 52 Page 1 of 2 ALERT OR HIGHER NOTIFICATIONS Contact Community Alert Network (CANs) at 9-1-800-552-4226 (or at their back-up number of 9-1-877-786-8478). Inform the CAN operator of the following information to activate the system:
- a. This is . I am the Ginna Control Room Communicator at RG&E.
(your name)
- b. My password is: Brookwood
- c. My callback number is:
- d. This is (circle one): an Actual Event a Drill
- e. This Emergency Classification declared at:
(Time from RECS form)
- f. Message to deliver (circle one):
Drill Alert Site Area Emergency General Emergency
- g. Ginna responders report to (circle one):
Normal locations Ontario Fire Department Exempt Hall
- h. My current time is: . Please start notifications now.
- 2. Report information to NEW YORK STATE, WAYNE and MONROE counties within 15 minutes of declaring the emergency via RECS Line using New York State Radiological Emergency Data Form (Part I) Attachment 3a. Fax the New York State Radiological Emergency Data Form (Part I) Attachment 3a to New York State, Wayne County, Monroe County, TSC, EOF, Survey Center and Joint Emergency News Center.
- 3. Notify Nuclear Emergency Preparedness.
. Can you be the "This is the Ginna Control Room. We have declared a Emergency Planning contact? Your duties are: (a) contact the PSC; and (b) verify actuation of the emergency response organization." (EP will refer to Attachment 6 for contingency notifications.)
Peter Polfleit Business 6772 Home 315-524-7101 Pager 585-527-2207 Cellular 585-315-1201 OR Frank Cordaro Business 3108 Home 315-524-2924 Pager 585-527-3650 Cellular 585-315-1277
EPIP 1-5:9 Attachment 2, Rev. 52 Page 2 of 2 ALERT OR HIGHER NOTIFICATIONS (Continued)
OR Tim Laursen Business 6185 Home 585-396-1149 Pager 585-528-5982 Cellular 585-315-1854 OR Richard Watts Business 8706 Home 585-425-2644 Pager 585-527-3749 Cellular 585-315-1204 OR Jill Willoughby Business 4033 Home 585-787-9075 Pager 585-528-3295 Cellular 585-315-1205
- 4. Notify USNRC immediately after the notification of the State and Counties, using procedure 0-9.3, NRC Immediate Notification
- 5. NRC Resident Inspector: Informational call only Ken Kolaczyk Business 3265 Home 585-924-5187 Pager 1-800-944-2337 (then dial personal ID# 53133)
- 6. If the Alert of higher lasts greater than 30 minutes report information using the New York State Radiological Emergency Data Forms (Part I) Attachment 3a to New York State, Wayne County, Monroe County every 30 minutes from the time the previous notification was made. Fax the New York State Radiological Emergency Data Form (Part I) Attachment 3a to New York State, Wayne County, Monroe County, TSC, EOF, Survey Center and Joint Emergency News Center after each report.
- 7. Notify Energy Operations (8944) that Ginna has an emergency and to implement procedures to increase reliability of power to Ginna.
- 8. If requested by the TSC or EOF, the Control Room will fax the Event 1 Supplemental Information Form, Attachment 3d to the TSC and EOF.
NOTE: EVENT 1 AND EVENT 2 PRINTOUTS SHOULD NOT BE TRANSMITTED BY THE CONTROL ROOM, BUT SHOULD BE FAXED BY THE TSC ADMINISTRATIVE/COMMUNICATIONS STAFF WHEN IT IS SUFFICIENTLY STAFFED TO DO SO.
- 9. Refer to Attachment 3c for Event 1 and Event 2 instructions.
EPIP 1-5:10 Attachment 3, Rev. 52 Page 1 of 5 INSTRUCTIONS FOR NEW YORK STATE RADIOLOGICAL EMERGENCY DATA FORM
- 1. The New York State Radiological Emergency Data Form, (Part I) Attachment 3a should be filled out with the assistance of the Emergency Coordinator or EOF/Recovery Manager and Radiation Protection personnel.
- 2. At the upper right hand corner of the form, number each notification form sequentially.
- 3. When information has changed from the previous notification, check the box for that item.
- 4. For training and drills/exercise, circle "B" - An Exercise. For actual events, circle "A" -' NOT An Exercise.
- 5. Fill out the form using the following instructions:
Block I Fill in the date and time that the message is transmitted. Select A or B, depending on the method the RECS will be transmitted.
WHEN THE FORM IS COMPLETED, report the information on the completed New York State Radiological Emergency Data Form (Part I),
Attachment 3a, to New York State, Wayne and Monroe Counties within 15 minutes of declaring the emergency using the RECS line.
- a. Pick up the receiver and depress "A" then "."for all call. Wait 5 seconds then depress the "Push to Talk" bar on the handset and state:
"This is Ginna Station. Please standby for roll call."
"New York State" (wait for response)
"Monroe County" (wait for response)
"Wayne County" (wait for response)
- b. Report the information by reading the statement number and the statement including the designation letter (e.g., "Item four, Classification "A" Unusual Event").
- c. Upon completion of transmitting the information perform roll call. Reset the system by depressing "A" then "#".
- d. Hang up receiver.
If the RECS line is Out Of Service (OOS) and OTHER is selected, note the method (phone) and perform the following:
Call Wayne County at 9-1-315-946-9711 (Wayne County Warning Point). Inform Wayne County 'This is a Ginna Emergency. Please hold while we connect Monroe County and New York State". Press the conference button on the telephone.
EPIP 1-5:11 Attachment Rev. 52 3,
Page 2 of 5 FORM (Cont'd.)
INSTRUCTIONS FOR NEW YORK STATE RADIOLOGICAL EMERGENCY DATA County Call Monroe County at 9-528-2222 (Monroe County Warning Point). Inform Monroe and Wayne
'This is a Ginna emergency. Press the conference button on the telephone.
Monroe Counties should now be connected Roll call: Wayne County Monroe County "Please hold while we connect New York State". Press the conference button on the telephone.
New Call New York State at 9-1-518-457-2200 (New York State Warning Point). Inform York State "This is a Ginna emergency." Press the conference button on the telephone.
Wayne County, Monroe County and New York State should all be connected.
Block 2 Circle A or B Block 3 Ginna is the facility providing the information. Nothing further is needed in this box.
Block 4 Circle the appropriate Emergency Classification. The Emergency Coordinator (TSC) or EOF/Recovery Manager (EOF) will provide this information.
Block 5 Fill in the date and time that the Emergency Classification was declared.
This will normally be in the Control Room, Emergency Coordinator's or EOF/Recovery Manager's log.
Block 6 Check effluent monitor readings against the release rate limits given in the table below. Circle the appropriate release information. For unmonitored release determination, have the Shift RP Technician or the Dose Assessment Manager assist in assessment.
Monitor No Release Release BELOW federally Release ABOVE federally approved operating limits approved operating limits*
R-1 1 Not on Alarm
- 1 fan, monitor on Alarm and
- 1 fan and monitor -6.91 E4
<6.91 E4 cpm cpm e 2 fans, monitor on Alarm and
- 2 fans and monitor
<7.06E4 cpm >7.06E4 cpm R-1 2 Not on Alarm
- 1 fan, monitor on Alarm and
- 1 fan and monitor -3.71 E6
<3.71 E6 cpm cpm e 2 fans, monitor on Alarm and
- 2 fans and monitor
<2.68E6 cpm -2.68E6 cpm R-13 Not on Alarm On Alarm and <1.17E4 cpm On Alarm and >1.17E4 cpm R-14 Not on Alarm On Alarm and <3.05E5 cpm On Alarm and >3.05E5 cpm R-1 5 Not on Alarm On Alarm and <1.47E+05 cpm >1.47E+05 cpm
EPIP 1-5:12 Attachment 3, Rev. 52 Page 3 of 5 INSTRUCTIONS FOR NEW YORK STATE RADIOLOGICAL EMERGENCY DATA FORMS (Cont'd.)
Monitor No Release Release BELOW Release ABOVE federally approved federally approved operating limits operating limits*
R-1 8 Not on Alarm On Alarm and >1.80E+05 cpm
<1.80E+05 cpm R-20A Not on Alarm On Alarm and >2.04E+04 cpm
<2.04E+04 cpm R-20B Not on Alarm On Alarm and >2.60E+03 cpm
<2.60E+03 cpm R-21"* Not on Alarm On Alarm and >2.50E+04 cpm I <2.50E+04 cpm R-22** Not on Alarm On Alarm and >4.60E+04 cpm
<4.60E+04 cpm R-31 Not on Alarm On Alarm and >1.OOE-01 mRad/hr
<1.OOE-01 mRad/hr R-32 Not on Alarm On Alarm and >1.OOE-01 mRad/hr
<1.O0E-01 mRad/hr
- Release rate limit in procedure P-9.
Unmonitored release requiring evaluation - select this if there is an unmonitored release and it has not been quantified.
R-21 and R-22 have no remote indications in the Control Room or on PPCS. MCB annunciators AA-2 and K-27 may indicate a possible release; however, local observation must be performed.
NOTE: PROTECTIVE ACTION RECOMMENDATION5 AKt UNLY it IUINiU AT A GENERAL EMERGENCY CLASSIFICATION.
Block 7 Circle the appropriate PAR. The Emergency Coordinator and/or the EOF Recovery Manager will use EPIP 2-1, Protective Action Recommendations (PAR's). PAR's only reflect RG&E's recommendations, NOT THE ACTIONS IMPLEMENTED BY OFFSITE COUNTY OFFICIALS.
Block 8 Fill in the EAL # from EPIP 1-0 that the Emergency Classification is based on. The Emergency Coordinator and/or EOF Recovery manager can provide that information, if necessary.
If declaring an event due to ER-SC.9, include a brief explanation of the event.
Block 9 Determine plant status and circle the appropriate condition.
EPIP 1-5:13 Attachment 3, Rev. 52 Page 4 of 5 INSTRUCTIONS FOR NEW YORK STATE RADIOLOGICAL EMERGENCY DATA FORM (Cont'd.)
Block 10 Select A, Not Applicable, if the reactor is NOT SHUTDOWN or select B and fill in the date and time if the REACTOR WAS SHUTDOWN. Reactor shutdown time is the time the reactor trip breakers are opened. When the reactor trips, a red "Event" message appears next to the time in the upper right hand corner of the screen. To find the reactor trip time, click on SPDS in the upper left hand corner of the screen.
Select "normal ops" and the trip time is displayed.
Block 11 Determine wind speed preferably at 33 foot level.
NOTE: THE WIND SPEED INDICATOR AT THE 33 FOOT LEVEL IS DESIGNED TO MEASURE ONLY TO 50 MILES PER HOUR.
Obtain wind speed using the plant process computer (PPCS).
OR Ifthe PPCS is not available, use the Control Room wind speed indication on the RMS rack.
OR The Radiation Protection Shift Technician or Dose Assessment Manager will determine the weather and stability class in accordance with procedure EPIP 2-2.
Block 12 Determine wind direction preferably at 33 foot level as it was taken from PPCS and/or Control Room weather data instrumentation and fill in the wind direction and elevation.
Obtain wind direction using the plant process computer (PPCS)
OR Ifthe PPCS is not available, use the Control Room wind direction on the RMS rack.
OR The Radiation Protection Shift Technician or Dose Assessment Manager will determine the weather and stability class in accordance with procedure EPIP 2-2.
Block 13 Fill in temperatures from the 250 foot and 33 foot levels and calculate stability class. Circle the appropriate stability class (Unstable, Neutral, Stable).
Ifthe PPCS is not available, use the Control Room wind direction on the RMS rack.
OR The Radiation Protection Shift Technician or Dose Assessment Manager will determine the weather and stability class in accordance with procedure EPIP 2-2.
Block 14 If Ginna responders are responding to the Ontario Fire Department Exempt Hall, check the box to notify Wayne County to have the Ontario Fire Department open the Exempt Hall.
Fill in the name of the communicator reporting the information. Fill in the call back area code and telephone number. Return to BLOCK 1 and report information via RECS or other means, as necessary.
- 6. The communicator will initial the "prepared by" line at the bottom of the form. The Shift Supervisor, Emergency Coordinator or EOF/Recovery Manager will approve the form at the bottom prior to transmission. The communicator will ensure all forms are sent to the Corporate Nuclear Emergency Planner (CNEP) at the conclusion of the event.
EPIP 1-5:14 Attachment 3, Rev. 52 Page 5 of 5 INSTRUCTIONS FOR NEW YORK STATE RADIOLOGICAL EMERGENCY DATA FORM (Cont'd.)
- 7. Data in items 15 through 20 of the New York State Radiological Emergency Data Form (Part II), Attachment 3b, should be filled out by the TSC/EOF Dose Assessment group and transmitted by fax as information becomes available from the TSC/EOF. The form is transmitted via fax after there has been a release above release limits (see Attachment 3a, Block 6).
- 8. Fax all New York State Radiological Emergency Data Forms to the following using the instructions on the fax machine:
Wayne County 9-1-315-946-9721 Monroe County 9-256-6355 New York State 9-1-518-457-9942 TSC 3927 EOF 9-262-5788 Survey Center 3612 Engineering Support Center 3774 Joint Emergency News Center 6771
- 9. When a County or the State request to be notified only if conditions change or when the event is terminated, check with the State/County warning points to see if they agree. Ifthey all agree, note this in section 8 of the next Part I Form notification. The facility with command and control will inform the other RG&E response facilities of the status of notifications. Perform a notification when conditions change or the event is terminated.
EPIP 1-5:15 Attachment 3a, Rev. 52 Page 1 of 1 NEW YORK STATE RADIOLOGICAL EMERGENCY DATA FORM (PART I)
RECS message number "This is Ginna Station. Please stand by for roll call." "New York State" 0 "Monroe County" 0 "Wayne County" 0
- 1. Message transmitted at: 2. This is:
Date Time Via: A. RECS B. Other A. NOT an exercise B. An exercise 3 Facility providing information: C. Ginna 4 Classification:
03 check box if information has changed A. UNUSUAL EVENT C. SITE AREA EMERGENCY E. EMERGENCY TERMINATED B. ALERT D. GENERAL EMERGENCY F. RECOVERY 5 Classification Time:
o3 check box if information has changed This Emergency Classification declared at: Date Time 6 Release of Radioactive Materials due to the Classified Event.
o check box if information has changed A. No Release B. Release BELOW federally approved operating limits (technical specifications)
IJ to atmosphere E0 to water C. Release ABOVE federally approved operating limits (technical specifications) 0 to atmosphere 03 to water D. Unmonitored release requiring evaluation
- 7. Protective Action RECOMMENDATIONS: (Refer to EPIP 2-1)
O check box ifinformation has changed A. No need for Protective Actions outside the site boundary B. Evacuate the following ERPAs W1 W2 W3 W4 W5 W6 W7 M1 M2 M3 M4 M5 M6 M7 M8 M9 C. Shelter all remaining ERPAs
- 8. Brief Event
Description:
03 check box ifinformation has changed EAL #
9 Plant Status: 10. Reactor Shutdown: (subcritical) o check box ifinformation has changed 0 check box if information has changed A. Stable C. Degrading E. Cold Shutdown A. Not Applicable B. Date__ Time__
B. Improving D. Hot Shutdown
- 11. Wind Speed: 12. Wind Direction:
0 check box if information has changed 0 check box if information has changed A. Miles/hour at elevation feet From: degrees at elevation feet
- 13. Stability Class: DO NOT REPORT 14. Reported By.
0 check box if Stability Class Work Sheet information has Name changed Temperature at 250 feet OF Temperature at 33 feet _ _F Area Cede __ Number Unstable, Neutral, Stable Temperature Difference OF
-1.74 -0.65 03 Check box TO WAYNE COUNTY ONLY Unstable I Neutral I Stable Please contact the Ontario Fire Department and have them ope
-3 -2 -1 0 1 the Exempt Hall for the Ginna responders.
I_____ _ I Temperature Difference II "New York State copy?" 0"Monroe County copy?" 0"Wayne County copy?" 0 FOR RG&E USE ONLY:
Time Prepared: Time Approved: Completed form sent Prepared By: Approved By: to EP - Ginna Training_
EPIP 1-5:16 Attachment 3b, Rev. 52 Page 1 of 1 NEW YORK STATE RADIOLOGICAL EMERGENCY DATA FORM (PART II)
Telefax this data form to: 0 New York State [3 Monroe County 0 Wayne County
- 15. Message transmitted at:
Date _ Time Location/Facility Transmitted From:
- 16. General Release Information A. Release > Tech Specs started, Date Time B. Release > Tech Specs expected to end: Date Time OR 0 Unknown C. Release > Tech Specs ended: Date Time D. Reactor Shutdown: N/A OR Date Time E. Wind Speed. miles/hour at elevation feet F. Wind Direction from, degrees at elevation feet G. Stability Class: PASQUILL A B C D E F G OR Other__
- 17. Atmospheric Release Information A. Release from: 0 Ground 0 Elevated D. Noble Gas Release Rate__ Cilsec B. Iodine/Noble Gas Ratio E. Iodine Release Rate Ci/sec C. Total Release Rate Cisec F. Particulate Release Rate __ Ci/sec
- 18. Waterbome Release Information A. Volume of Release _ gal or liters C. Radionuclides in Release B. Total Concentration _ pCi/ml D. Total Activity Released
- 19. Dose Calculations (based on a release duration of __ hours)
Calculation is based on (circle one) A. Inplant Measurements B. Field Measurements C. Assumed Source Term Table below applies to (circle one) A. Atmosphere Release B Waterbome Release Dose Distance Xu/Q TEDE (rem) CDE - Child Thyroid (rem)
Site Boundary 2 Miles 5 Miles I I 10 Miles Miles 20.Field Measurements of Dose Rates or Surface Contamination/Disposition Dose Rate OR Miles/Sector OR Location OR Sampling Point Time of Reading Contamination Miles/Degrees (Include Units)
Time Prepared:
Time Approved:
FOR RG&E USE ONLY:
By: By:
Completed form sent to EP - Ginna Training,
EPIP 1-5:17 Attachment 3c, Rev. 52 Page 1 of 1 INSTRUCTIONS FOR EVENT 1 AND EVENT 2 PRINTOUTS AND PLANT STATUS REPORT
- 1. Assure the Plant Process Computer System (PPCS) is operational. If PPCS is not operational, go to step 5.
NOTE: OBTAIN EVENT I AND EVENT 2 PRINTOUTS FROM THE COMPUTER ANALYST IF THAT POSITION IS STAFFED, OTHERWISE PERFORM THE FOLLOWING STEP.
- 2. From the top menu:
Select "Emergency Plan Menu".
Select "Group Event 1".
Select "Report".
Select "File" then "Print" or select the printer icon.
From the top menu:
Select "Emergency Plan Menu".
Select "Group Event 2".
Select "Report".
Select "File" then "Print" or select the printer icon.
Place printout in the Event 1 & 2 group trend log book NOTE: EVENT 1 AND EVENT 2 GROUP TREND (GTLOG) SHOULD BE PRINTED EVERY 15 MINUTES.
- 3. Verify with the TSC computer analyst that the PPCX (plant computer data) is being transmitted to New York State, Wayne County and Monroe County via computer modem. If the PPCX (plant computer data) to offsite agencies is unavailable, perform step 2 and fax the printout to New York State, Wayne County and Monroe County.
- 4. If the PPCS is unavailable, the Plant Status Report (Attachment 3e) must be completed by the Control Room and faxed to the TSC for distribution to New York State, Wayne County, Monroe County and EOF.
- 5. When completing Attachment 3e, if the parameter is measurable (e.g. pressurizer level) use the numerical value. When the parameter is not measurable, the condition of any deviation from normal should be noted (e.g.
core circulation - forced or natural).
EPIP 1-5:18 Attachment 3d, Rev. 52 Page 1 of 1 EVENT 1 SUPPLEMENTAL INFORMATION FORM 61 Aux Feedwater System Inservice _ Standby OOS Inservice Standby 00S 62 Safety Injection System Inservice _ Standby 00S 63 Diesel Generators Inservice _ Standby 00S 64 Containment Fan Cooler System Inservice _ Standby 00S 65 Service Water System Inservice _ Standby 00S 66 Post Accident Charcoal Filters Inservice _ Standby 00S 67 Containment Spray Pumps Inservice _ Standby 00S 68 Component Cooling System A_
V B v 69 DC System 70 NaOH Tank Level Time Completed:
Completed By:
(7 Q EPIP 1-5:19 Attachment 3e, Rev. 52 PLANT STATUS REPORT (PPCS NOT AVAILABLE) r_ ye;* UI Plant Parameters Plant Parameters Radiation Monitoring Auxiliary Feedwater Inservice R-1 Control Room TIME System Standby mRem/hr Reactor Shutdown YES/NO OS Inservice R-2 Containment PSIG Safety Injection Standby mRem/hr RCS Pressure DOS Inservice R-9 Letdown
% Diesel Generators __ Standby mRem/hr PRZR Level COS Inservice R-10 "A"Containment Iodine Service Water System Standby CPM Core Circulation Forced/Natural 00S OF Cnmt Fan Coolers System Inservice R-1 1 Containment Particulate
_ _ Standby CPM Subcooled
_ OOS
% Post Acc. Charcoal Filter Damper Damper R-12 Containment Gas CPM "A" SIG Level Open I Closed
% Cnmt. Spray Inservice R-1 0 "B" Plant Vent Iodine "B" S/G Level CPM
_ Standby Cnmt. Spray Inservice Pumps Standby COS Comp. Cooling System Inservice R-13 Plant Vent Particulate Standby CPM "A" S/G Pressure PSIG _
COS
/ Volts R-14 Plant Vent Gas CPM "B" S/G Pressure PSIG D.C. System Safeguard Train B (16/17) NaOH Tank Level % R-29 Containment High Range EDG/Turbine/Offsite % R30 ContainmentHighRan eR/hr Offsite Power Available/Unavailable RWST Level % R-30 Containment High Range R~hr
% R-1 5 Air Ejector Gas CPM Cnmt Pressure PSIG B A. Tank Level FT Wind Speed *R-12A SPING Containment Sump "A" Level MPH Gas pCVcc Sump "B" Level IN Wind Direction (From) Degrees *R1 4A SPING Plant Vent Gas
_______________pCVcc OF *R-1 5A SPING Air Ejector Gas pCVcc RCS Temp OF Temperature 33 FT OF R-31 Steam Line "A" mRem/hr RVLIS % Temperature 250 FT R-32 Steam Line "B" mRem/hr CET OF I
.rI',. ip1
,i_;, .A..,.^ f,, kHa I,-l,*,4 df Date R/hr = Roentgen/Hour Completed radiation monitors R-1 2 and R1 4 onTime Completed By pCVcc =Microcuries/Cubic Centimeter scale.
mRem/hr = millirem/Hour
EPIP 1-5:20 Attachment 4, Rev. 52 Page 1 of 1 SPECIALIZED RESOURCE LIST Department Of Energy
- 1. Radiation Assistance Program 631-344-2200 Brookhaven Group Office Other 9-722-2122
- 1. Plant Protection Department Kodak Park
- 2. National Weather Service (Buffalo) 9-1-800-462-7751 9-1-415-846-3453
- 3. Helgeson Nuclear Services Inc 9-1-800-321-0614
- 4. Institute of Nuclear Power Operations 9-1-203-677-7305
- 5. American Nuclear Insurers Phone 9-1-613-991-7000
- 6. Emergency Preparedness Canada 9-1-613-996-0995 Fax
EPIP 1-5:21 Attachment 5, Rev. 52 Page 1 of 3 NOTIFICATIONS WHEN OFFSITE ASSISTANCE HAS BEEN REQUESTED
- 1. When offsite assistance has been requested activate:
Security Nuclear Management Emergency Planning Examples of initiating events that could require offsite assistance are:
- Fire
- Medical Emergency
- Security Event
- HAZMAT Incident
- Natural Events (such as flooding, earthquakes or severe weather)
- 2. Security Contact Security at 3210, so that they can make preparations for the arrival of the emergency vehicles and personnel.
- 3. Nuclear Management Notify the following individuals:
"This is the Ginna Control Room. We have requested offsite assistance from Can you be the Nuclear Management contact for this event? Your duties are (a) act as the RG&E lead for this event and (b) act as the liaison between the Control Room and the corporation."
Nuclear Management (One person required to respond)
Joe Widay Business 3250 Available (YES/NO)
Home 585-586-2679 Pager 585-528-3977 Cellular 585-315-0343 OR Robert Popp Business 3645 Available (YES/NO)
Home 585-671-6818 Pager 585-527-7881 Cellular 585-315-0351 OR John Smith Business 3525 Available (YES/NO)
Home: 315-524-5340 Pager 585-463-9716 Cellular 585-315-0353 OR Bob Mecredy Business 3494 Available (YES/NO)
Home 585-381-6430 Pager 585-783-4900 Cellular: 585-315-0813
EPIP 1-5:22 Attachment 5, Rev. 52 Page 2 of 3 NOTIFICATIONS WHEN OFFSITE ASSISTANCE HAS BEEN REQUESTED (Cont'd.)
The nuclear management representative may call other nuclear managers or members of the Ginna leadership team.
- 4. Emergency Planning j -
Notify the following individuals:
"This is the Ginna Control Room. We have requested offsite assistance from . Can you be the Emergency Planning contact for this event? Your duties are (a) activate Public Relations and (b) act as the liaison between the Control Room and government agencies.
is acting as the Nuclear Management lead for this event. He can be reached at__
Nuclear Emergency Preparedness (One person required to respond)
Peter Polfleit Business 6772 Home 315-524-7101 Pager 585-527-2207 Cellular 585-315-1201 OR Frank Cordaro Business 3108 Home 315-524-2924 Pager 585-527-3650 Cellular 585-315-1277 OR Tim Laursen Business 6185 Home 585-396-1149 Pager 585-528-5982 Cellular 585-315-1854 OR Richard Watts Business 8706 Home 585-425-2644 Pager 585-527-3749 Cellular 585-315-1204 OR Jill Willoughby Business 4033 Home 585-787-9075 Pager 585-528-3295 Cellular 585-315-1205 The Emergency Planning representative will call the duty public information officer (PIO) via the ECC at 771-2233, and inform them of the event. The duty PIO will determine if a media announcement is warranted. The Emergency Planning representative will also contact Wayne County, Monroe County and New York State officials to brief them on offsite resources being used
EPIP 1-5:23 Attachment 5, Rev. 52 Page 3 of 3 NOTIFICATIONS WHEN OFFSITE ASSISTANCE HAS BEEN REQUESTED
- 5. Contact the NRC resident inspector Ken Kolaczyk Business 3265 Home 585-924-5187 Pager 1-800-944-2337 (then dial personal ID# 53133)
EPIP 1-5:24 Attachment 6, Rev. 52 Page 1 of 1 EMERGENCY PLANNING CONTINGENCY NOTIFICATION
- 1. Ensure verification of the Community Alert Network System or Group Page for one hour response positions. If the pagers do not activate or notifications are not completed, begin manual notification process.
- 2. Notify other Nuclear Emergency Preparedness staff members to request their assistance with contingency notifications.
- 3. The following one hour response positions should be filled by contacting a minimum of one responder for each position by individual page or by home, office or cellular phone number. Refer to EPIP 4-7, Public Information Organization Staffing, and EPIP 5-7, Emergency Organization.
- TSC Emergency Coordinator
- Operations Assessment Manager
- Technical Assessment Manager
- Communicator
- TSC Dose Assessment Manager
- RP/Chemistry Manager
- Maintenance Assessment Manager
- Survey Center Manager
- EOF Recovery Manager
- Nuclear Operations Manager
- Engineering Manager
- EOF Dose Assessment Manager
- News Center Manager
- 4. Inform the responder of the current emergency classification and instruct them to report to the appropriate emergency duty location immediately. Inform them of the fitness for duty requirements.