RC-02-0012, Transmittal of Emergency Plan Procedure Changes
| ML020370398 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 01/18/2002 |
| From: | Browne M South Carolina Electric & Gas Co |
| To: | Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| RC-02-0012 | |
| Download: ML020370398 (91) | |
Text
Melvin N. Browne Manager, NuclearLicensing & OperatingExperience 803.345.4141 January 18, 2002 RC-02-0012 A SCANA COMPANY Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 Gentlemen:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 TRANSMITTAL OF EMERGENCY PLAN PROCEDURE CHANGES In compliance with 10CFR50 Appendix E(V), South Carolina Electric & Gas Company, acting for itself and as agent for South Carolina Public Service Authority, transmits an updated Table of Contents and one controlled copy each of the following Emergency Plan Procedure Changes.
PROCEDURE REV. CHG. TITLE EPP-001 24 E Activation and Implementation of Emergency Plan EPP-051 6 A Emergency Operations Facility The effectiveness of the Virgil C. Summer Nuclear Station Radiation Emergency Plan is not decreased by these procedure changes.
Should you have any questions, please contact Mrs. Donna Railey at (803) 345-4107.
Ver truly yours, Melvin N. Browne DW R/MNB/dr Attachments c: (Without Attachment unless noted)
L. A. Reyes (With 2 Attachments)
NRC Resident Inspector RTS (0-L-99-0354)
File (810.10-2, RR 6000)
DMS (RC-02-0012) /0 SCE&G I Virgil C.Summer Nuclear Station
- P.O.Box 88 . Jenkinsville, South Carolina 29065 .T (803) 345.5209 - www.scana.com
This is an updated Table of Contents for EPP's.
Please file. Thank you.
Copy Number ) 5-7 Mail Code ,ý-ý)o
January 07,2002 VIRGIL C. SUMMER NUCLEAR STATION TABLE OF CONTENTS REPORT Document Type: PROCEDURE Series EPP%
Document Number Sheet Number Status Title EPP-001 NA A ACTIVATION AND IMPLEMENTATION OF EMERGENCY PLAN EPP-001.1 NA A NOTIFICATION OF UNUSUAL EVENT EPP-001.2 NA A ALERT EPP-001.3 NA A SITE AREA EMERGENCY EPP-001.4 NA A GENERAL EMERGENCY EPP-002 NA A COMMUNICATION AND NOTIFICATION EPP-003 NA A PLANT RADIOLOGICZAL SURVEYING EPP-005 NA A OFFSITE DOSE CALCULATIONS EPP-006 NA A TRANSPORTATION ACCIDENTS INVOLVING RADIOACTIVE MATERIAL EPP-007 NA A ENVIRONMENTAL MONITORING EPP-009 NA A ONSITE MEDICAL EPP-010 NA A PERSONNEL/VEHICLE DECONTAMINATION EPP-011 NA A PERSONNEL SEARCH AND RESCUE EPP-012 NA A ONSITE PERSONNEL ACCOUNTABILITY AND EVACUATION EPP-013 NA A FIRE EMERGENCY EPP-014 NA A TOXIC RELEASE EPP-015 NA A NATURAL EMERGENCY (EARTHQUAKE, TORNADO, HURRICANE)
EPP-017 NA A POST-RECOVERY AND RE-ENTRY EPP-020 NA A EMERGENCY PERSONNEL EXPOSURE CONTROL EPP-021 NA A ACTIVATION OF THE EARLY WARNING SIREN SYSTEM
[EWSS]
EPP-023 NA A EMERGENCY RESPONSE FACILITIES EPP-026 NA A OPERATION OF THE SIREN CONTROL SYSTEM EPP-051 NA A EMERGENCY OPERATIONS FACILITY EPP-052 NA A EMERGENCY INFORMATION PLAN EPP-102 NA A EMERGENCY PLAN TRAINING 28 record(s) Page 1 of 2
January 07, 2002 VIRGIL C. SUMMER NUCLEAR STATION TABLE OF CONTENTS REPORT Document Type: PROCEDURE Series EPP%
Document Number Sheet Number Status Title EPP-103 NA A EMERGENCY EQUIPMENT CHECKLIST EPP-104 NA A VERIFICATION OF COMMUNICATIONS OPERABILITY EPP-105 NA A CONDUCT OF DRILLS AND EXERCISES 28 record(s) Page 2 of 2
SOUTH CAROLINA ELECTRIC & GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS NUCLEAR OPERATIONS COPY NO. 1151 EMERGENCY PLAN PROCEDURE EPP-001 ACTIVATION AND IMPLEMENTATION OF EMERGENCY PLAN REVISION 24 SAFETY RELATED DIbIPLII SUPEtVISOR DATE I ZDAT7196 APPROVAL AUTHORITY DATE RECORD OF CHANGES CHANGE TYPE APPROVAL CANCELLATION CHANGE TYPE APPROVAL CANCELLATION LETTER CHANGE DATE DATE LETTER CHANGE pA'rr _ DATE
_ 2-2-4-71* F 7
__ _I_-o_-_8 INFORMATION USE Procedure may Be Performed From Memory.
User Retains Accountability For Proper Performance.
K' SAP-1 39 ATTACHMENT II PAGE 1 OF 3 REVISION 20 PROCEDURE DEVELOPMENT FORM -A ,
DATE: 1 0 PROC.# 0PP- P REV. # - CHG.=- COMM. #
&:F:fjyrheesA TITLE: aAAA ot &flKo je-L4C PldaL&
NEW PROCEDURE __ REVISION -- SAFETY RELATED v__
CHANGE: ___ PERMANENT V- QUALITY RELATED "
RESTRICTED__ FROM TO NON-SAFETY RELATED ii/. DESCRIPTION:
REASON FOR CHANGE:
Orgntr - inan A Name iii. REQUIRED REVIEWS: Check ALL selections in first 3 columns for SAPs (except for minor changes) Other Reviews:
( ) CWPS ( )ISEG ( )NOET ( ) QC C--I I )MCHS ( )MNPS ( ) MPLE ( ) GMES
)MDE ( )MNT ( )MPSE ( )GMNPO ( )DE ( )MNTS 9NPS §)QR 60f
)MHPS ( )MOD&P ( )MSPD ( )GMNSS ( )FFD ( )MQS ( )NTET ( )RC
)MMPR ( )MPO ( )SAS ( )GMSPD tHPS ( )MPR >4OPS ( )RE
)MMS ( )MOPS ( )QA ( )CHS ( )ISD ( )NL&OE ( )PSE C )TU
) MNL&OE "
-jr 59 W- DISCIPLINE SUPERVISOR AUTHORIZATION TO PROCESS PROPOSED-CHANGE Disciplini Suprvisor jDate
-V. TEMPORARY APPROVAL: V QUALIFIED REVIEWER DATE OA REVIEW DATE TELECON BY TELECON BY SHIFT SUPERVISOR DATE FINAL APPROVAL REQUIRED BY: DATE VIl. PICAP ACCEPTABLE? /.,
VI. DISCIPLINE SUPERVISOR FINAL REVIEW: C. YES NO _
N. YES NO YES.__ NO__
PSRC REVIEW REQUIRED? RESP. MGR. Date IF YES, PRIOR TO IMPLEMENTATION? YES.___ NO __ VIII. FINAL QA REVIEI (if Applicable)
TRAINING REQUIRED? YES VNO__ CA Concurrence Date IF YES, PRIOR TO IMPLEMENTATION? YES_ NO IX. APPROVAL ALTHORITY:
" /Iat SY S NO i / O""mp "rý l P/CAP AFFECTED? Date I,
COMMENTS RESOLVED P-eddA~r/ &Concurrene Date Discioline Supervisor /" Date X. PSRC REVIEW:
A. REVIEWED BY: B. PSRC COMMENTS RESOLVED:
/ /
PSRC Chairman Date Responsible Manager Date COMMENTS: YES_ NO_
PSRC Chairman Date
EPP-001, Activation and Implementation of Emergency Plan Revision 24, Change E Attachment to PDF-A, Section ii, Description and Reason for Change Page 1 of 2
==
Description:==
Attachment II, Page 4 of 17: Site Area Emergency Detection Method for a "Major Steam Line Break with Greater Than 50 Gallons per Minute Primary-to Secondary Leakage and Indication of Fuel Damage": Changed "RM-L1 High Range valid alarm and laboratory analysis dose equivalent 1-131 activity Ž 300 gCVgm in primary coolant" to "RM-L1 High Range valid alarm and primary coolant dose equivalent 1-131 activity Ž 300 giCVgm".
Reason for the Change: This change supports and clarifies the practice of the determining primary coolant dose equivalent 1-131 activity by laboratory analysis or by radiation survey on the sample line.
==
Description:==
Attachment II, Page 4 of 17: General Emergency Detection Method for a "Loss of Two of Three Fission Product Barriers with Potential Loss of the Third Barrier": Changed "Laboratory analysis dose equivalent 1-131 activity Ž 300 gCi/gm in primary coolant" to "Primary coolant dose equivalent f-131 activity
> 300 gCi/gm".
Reason for the Change: This change supports and clarifies the practice of the determining primary coolant dose equivalent 1-131 activity by laboratory analysis or by radiation survey on the sample line.
Description:
Attachment II,Page 6 of 17: Notification of Unusual Event for a "Fuel Damage Indication": Changed "Laboratory analysis which indicates dose equivalent 1-131 activity concentration Ž 30 gCi/gm in primary coolant" to "Primary coolant dose equivalent 1-131 activity Ž 30 pCi/gm".
Reason for the Change: This change supports and clarifies the practice of the determining primary coolant dose equivalent 1-131 activity by laboratory analysis or by radiation survey on the sample line.
Description:
Attachment II, Page 6 of 17: Alert Detection Method for a "Possible Fuel Damage": Changed "Laboratory analysis which indicates dose equivalent 1-131 activity concentration Ž 300 gCi/gm in primary coolant" to "Primary coolant dose equivalent 1-131 activity Ž 300 gLCVgm".
Reason for the Change: This change supports and clarifies the practice of the determining primary coolant dose equivalent 1-131 activity by laboratory analysis or by radiation survey on the sample line.
Description:
Attachment II, Page 6 of 17: Site Area Emergency Detection Method for a "Degraded Core with Possible Loss of Coolable Geometry": Changed "RM-L1 High Range off scale (>106cpm) with laboratory analysis dose equivalent 1-131 activity concentration > 300 gCi/gm in primary coolant" to "RM-L1 High Range off scale (>106 cpm) with primary coolant dose equivalent 1-131 activity Ž 300 RCi/gm".
Reason for the Change: This change supports and clarifies the practice of the determining primary coolant dose equivalent 1-131 activity by laboratory analysis or by radiation survey on the sample line.
EPP-001, Activation and Implementation of Emergency Plan Revision 24, Change E Attachment to PDF-A, Section ii, Description and Reason for Change Page 2 of 2
==
Description:==
Attachmeht II, Page 7 of 17: General Emergency Detection Method for
'Transient Requiring Operation of Shutdown Systems with Failure to Trip Which Results in Core Damage or Additional Failure of Core Cooling and Makeup Systems Which Could Lead to Core Melt": Changed "RM-L1 alarm, with laboratory analysis dose equivalent 1-131 activity concentration Ž 300 gCVgm in primary coolant" to "RM-L1 alarm, with primary coolant dose equivalent 1-131 activity Ž 300 p.Ci/gm".
Reason for the Change: This change supports and clarifies the practice of the determining primary coolant dose equivalent 1-131 activity by laboratory analysis or by radiation survey on the sample line.
Description:
Attachment II: Made various changes to the format and the wording of some sections. Format changes include providing lines next to each step for place keeping.
Reason for the Change: Feedback from users to make the attachment more usable and to provide clarification.
Description:
Attachment IIl: Removed the provision for certain TSC duty personnel to report to the TSC instead of the EOF during a security emergency. The entire ERO duty will now be instructed to report to the EOF in the event of a security emergency.
Reason for the Change: This action simplifies and clarifies the response instructions. The EOF provides a safe staging area away from the plant site. TSC and OSC personnel can be directed to respond to the plant site from the EOF as necessary and as conditions permit.
NUCLEAR OPERATIONS SAP-1 39 ATTACHMENT II COPY NO. '5q PAGE 1 OF 3 REVISION 20 PROCEDURE DEVELOPMENT FORM - A.
- i. DATE:) /12M0 PROC.# E-00 - vIRV.#Z CHG. M comm. #__
TITLE: af.yAhP aea 15 ;; 0-4 -4w C 4 a"'ýýOL EVLPMNTFRM-PRCEUE V I SAFETY RELATED NEW PROCEDURE __ REVISION QUALITY RELATED CHANGE: V. PERMANENT TO NON-SAFETY RELATED __
RESTRICTED__ FROM REASON FOR CHANGE: 41A J '-8' -5 ( 9 ()7-4 4
- 4 L140~
- nri mJ1 Nm iii. REQUIRED REVIEWS: Check ALL selections in first 3 columns for SAPs (except for minor changes)Other Reviews:
)MCHS ( )MNPS ( )MPLE ( )GMES ( )/CWPS ( )ISEG ( )NOET ( )QC q
)MDE ( )MNT ( )MPSE ( )GMNPO ( )DE ( )MNTS j> NPS PkIQR aI
)MHPS ( )MOD&P ( )MSPD ( )GMNSS ( )FFD ( )MQS ( )NTET ( )RC
)MMPR ( )MPO ( )SAS ( )GMSPD .,4HPS ( )MPR )OPS ( )RE
)MMS ( )MOPS ( )QA ( )CHS -( )ISD ( )NL&OE ()PSE ( )TU
)MNL&OE (,)50.59, B-- DISCIPLINE SUPERVISOR AUTHORIZATION TO PROCESS PROPOSED-CHAN :
Disci. " e rvisor Datj i
-V. TEMPORARY APPROVAL:
QUALIFIED REVIEWER DATE QA REVIEW DATE TELECON BY TELECON BY SHIFT SUPERVISOR DATE FINAL APPROVAL REQUIRED BY: DATE VII. PICAP ACCEPTABLE? PJ)
VL DISCIPLINE SUPERVISOR FINAL REVIEW: C. YES NO /
PSRC REVIEW REQUIRED? YES_ NO _/ S*RESP. N. YES NO - R MGR. Date IF YES, PRIOR TO IMPLEMENTATION? YES__ N VilI. FINAL QA REVIEW (if Appicable)
YES V" NO QA Concurrence Date TRAINING REQUIRED?
NO IX. APPROV.gAUTHORITY:
IF YES, PRIOR TO IMPLEMENTATION? YES_
P/CAP AFFECTED? // * ,/ ES__ NOV' Trainii gCorplet / Date COMMENTS RESOLV D: -, / /I /o o e( atelf
"ý,OsciplinoL:jervisor /Date/
X. PSRC REVIEW:
A. REVIEWED BY: /
B. PSRC COMMENTS RESOLVED: /
PSRC Chairman Date Responsible Manager Date COMMENTS: YES _ NO _ __
PSRC _ _ _ChairmanDate Chairman Date
SAP-139 NUCLEAR OPERATIONS ATTACHMENT IV PAGE 1 OF 3 COPY NO. I5__ REVISION 18 PROCEDURE DEVELOPMENT FORM - A * /
L DATE* ,zL*.-- 7 P . -CP-7 I . REV # CHGH._ %c 12, 61 /7 v SAFETY RELATED NEW PROC CHANGE__.--- PERMANENT _,'_
RESTRICTED - FROM TO QUALITY RELATED REVISION NON-SAFETY RELATED It. DESCRIPTION:
4,0-e, iL(&-7 ~ 9~
REASON FOR CHANGE:
L/ rio w 13/ Siin#Print i11. WILL THIS REVISIONJCHANGEINEW PROCEDURE: 'YES NO N/A
- 1. Result in signfcart increased persoe radiaion exposure? (ALARA review)
- 2. Result in a release of effluents to the Envirorment?
- 3. Degrade the effectiveness of the Radiation Emergeincy Plan? -
- 4. Degrade the safeguards effectiveness of the Physical Security, Safeguards Contingency of Training and Qualification Plans?
If any question I through 4 is answered "YES", refer to appropriate section of procedure for d .
REQUIRED REVIEW AND COMMENT: REQLLESTf-YEVIEW o MOPS ()MHPS ()GMNPO O TA ()ISD 6%f//1
() MMS ()MDE OGMES (QC OCHS R ,
()MOS (MNT (GMNSS (SAS )>YIPS *L~)___
() MPSE (MNL&OE OGMSPD )MNTS OPSE (). ()________ isc/1
) MCHS (MNPS k(OPS XHNPS ODE 0) . () ' /I// I/
IVF. IOCFR50OJ9 SCREENING REVIEWISAFETY EVALUATION O REQUIRED. EXEMPT PSRC SUPPORTING DOCUMENT: /-F-- " .
V. TEMPORARY APPROVAL:
QUALIFIED REVIEWER DATE QA REVIEW DATE_
TELECON BY TELECON BY SHIFT SUPERVISOR DATE __ FINAL APPROVAL REQUIRED BY: DA VII. PICAPAC VL DISCIPUNE SUPERVSOR FAL REVIEW: C. YEs__= NO-- t N. YES__/ NO i.Date N. YES v" NO PSRC REVIEW PRIOR TO IMPLEMENTATION? YES-__ NO YESjLCO TRAIINGREQURED /VUL FINAL QIA REVIEW (As ApAcable)
QA Concurrence Date IF YES, PRIOR TO PROCEDURE IMPLEMENTATION? YESaZNO P/CAP AFFECTED? YES m DL APPO I T pi id De COMMENTS RESOLVED:
ýProce pp Condcurrence Date X. PSRC REVIEW:
A. REVIEWED BY: B. PSRC COMMENTS RESOLVED:
I l PSRC Chairman Date Respons=ble Manager Date COMMENTS: YES_ NO__
PSRC Chairman Date
EPP-001, Activation and Implementation of Emergency Plan Revision 24, Change C Addendum to PDF-A,Section II Description and Reason for Changes Page 1 of 2 Change
Description:
Changed reference 2.9 from SAP-1122 to SAP-1131.
Reason for Change:
To update the reference to the new procedure for the CER Program.
Change
Description:
Added section 5.3, Undeclared and Misclassified Events and supporting reference 2.10, NUREG-1 022, Event Reporting Guidelines 10CFR50.72 and 50.73. Section 5.3 is designated Commitment #CO1.
Reason for Change:
To provide guidance to the user for actions to take when it is discovered that an event or condition had existed which met the criteria for Emergency Plan activation but no emergency had been declared and the basis for the emergency classification no longer exists.
==
Description:==
Deleted Definition 3.1.5, EWSS Inoperable which is Commitment #NO1.
Reason for Change:
The Detection Method for an EAL in which this definition was used was deleted in a previous revision and does not appear elsewhere in this procedure.
==
Description:==
Attachment I Page 10 of 17: Detection Method for Emergency Action Levels (EAL) 231 and 331: Changed the detection method for EAL 231 to "An automatic reactor trip fails when required, and, a manual reactor trip from either MCB handswitch is successful" and changed detection method for EAL 331 to "Entry into EOP-13.0 from EOP-1.0, Step 1".
Reason for Change:
Revision 24 has nearly identical detection methods for Site Area Emergency and General Emergency indicating any Site Area Emergency from an ATWS would also warrant a General Emergency classification.
EPP-001, Activation and Implementation of Emergency Plan Revision 24, Change C Addendum to PDF-A,Section II Description and Reason for Changes Page 2 of 2
==
Description:==
Attachment II Page 16 of 17: Added the following note to each of the Security related EALs, "See EPP-001 Attachment III for additional guidance".
Reason for Change:
To remind the user of the location of additional guidance for actions to take in a Security event.
==
Description:==
Attachment II Page 17 of 17: Corrected typographical error in the detection method for the first Alert EAL.
Reason for Change:
Correct typographical error.
==
Description:==
Section 5.2.C: Removed the reference to declaring the emergency classification by using EIS.
Reason for Change:
Declaring an emergency is a decision made by the IED/ED and is not dependent on the availability of EIS.
EPP-001, Activation and Implementation of Emergency Plan Revision 24, Change C Addendum to IOCFRSO.54.q Evaluation Page 1 of 5 Change
Description:
Changed reference 2.9 from SAP-1 122 to SAP-1 131.
Reason for Change:
To update the reference to the new procedure for the CER Program.
IOCFRSO.54.q Evaluation Basis:
This change does not affect sections in 10CFR50.47(b) or 10CFR50 Appendix E.
This change is administrative in nature. Procedures for evaluation of events are not mentioned in the Radiation Emergency Plan. Therefore, this change does not decrease the effectiveness of the Radiation Emergency Plan. This change does not require further revision to the Radiation Emergency Plan. This change does not require further revision to Emergency Plan Prqcedures.
Change
Description:
Added section 5.3, Undeclared and Misclassified Events and supporting reference 2.10, NUREG-1022, Event Reporting Guidelines 10CFR50.72 and 50.73. Section 5.3 is designated Commitment #CO1.
Reason for Change:
To provide guidance to the user for actions to take when it is discovered that an event or condition had existed which met the criteria for Emergency Plan activation but no emergency had been declared and the basis for the emergency classification no longer exists.
IOCFR5O.54.q Evaluation Basis:
This change affects 10CFR50.47(b)(4) and 10CFR50 Appendix E IV.C. This change provides guidance to the user for the actions to take for undeclared and misclassified events as described in NUREG-1022, Event Reporting Guidelines 10CFR50.72 and IOCFR50.73, Rev 1, section 3.1.1, Immediate Notification Requirements. This section of the NUREG states that when such a condition is discovered that a one hour report to the NRC is appropriate and that emergency declaration and termination is unnecessary. At annual training for State and local governments conducted on 9/3/98 this issue was discussed and authorizing representatives of the State and the four Risk Counties stated that they also want to be notified within one hour of when such an event is discovered.
Unclassified and misclassified events are not mentioned in the Radiation Emergency Plan. Therefore, this change does not decrease the effectiveness of the Radiation Emergency Plan. This change does not require further revision to the Radiation Emergency Plan. This change does not require further revision to Emergency Plan Procedures.
EPP-001, Activation and Implementation of Emergency Plan Revision 24, Change C Addendum to IOCFR50.54.q Evaluation Page 2 of 5
==
Description:==
Deleted Definition 3.1.5, EWSS Inoperable which is Commitment #NO1.
Reason for Change:
The Detection Method for an EAL in which this definition was used was deleted in a previous revision and does not appear elsewhere in this procedure.
10CFR50.54.q Evaluation Basis:
This change affects 10CFR50.47(b)(4) and 10CFR50 Appendix E IV.C. EWSS Inoperability is no longer used as a detection method for emergency classification. This detection method was removed from the EALs in a prior revision to this procedure and to the Radiation Emergency Plan. This revision to the Plan was approved by the NRC prior to implementation. Therefore, this change does not decrease the effectiveness of the Radiation Emergency Plan.
This change does not require further revision to the Radiation Emergency Plan.
This change does not require further revision to Emergency Plan Procedures.
==
Description:==
Attachment It Page 10 of 17: Detection Method for Emergency Action Levels (EAL) 231 and 331: Changed the detection method for EAL 231 to "An automatic reactor trip fails when required, and, a manual reactor trip from either MCB handswitch is successful" and changed detection method for EAL 331 to "Entry into EOP-13.0 from EOP-1.0, Step 1".
Reason for Change:
Revision 24 Change B has nearly identical detection methods for Site Area Emergency and General Emergency indicating any Site Area Emergency from an ATWS would also warrant a General Emergency classification.
IOCFR50.54.q Evaluation:
These changes affect 1 OCFR50.47(b)(4) and 1 OCFR50 Appendix E (IV.C). The Alert level is entered as a result of safety system degradation. This condition indicates a failure of the automatic protection system to trip the reactor. This condition is more than a potential degradation of a safety system in that a first line automatic protection system did not function in response to a plant transient and thus the plant safety has been compromised, and design limits of the fuel may have been exceeded. An Alert is indicated because conditions exist that could lead to potential loss of fuel clad or RCS integrity. Reactor protection system setpoint being exceeded, rather that limiting safety system setpoint being exceeded, is specified here because failure of the automatic protection system is the issue. For some transients, the timing of the manual reactor trip would not be critical and fuel damage could be avoided. For other events, fuel damage could occur that would warrant the increased monitoring that would occur for an
EPP-001, Activation and Implementation of Emergency Plan Revision 24, Change C Addendum to I OCFRSO.54.q Evaluation Page 3 of 5 Alert. Failure of the manual trip would escalate the event to a Site Area Emergency.
Automatic and manual scram are not considered successful if entry into EOP-1 3.0 is required due to failure of both the automatic and manual reactor trip functions (both switches). Under these conditions, the reactor is producing more heat than the maximum decay heat load for which the safety systems are designed. A Site Area Emergency is indicated because conditions exist that could lead to the loss or potential loss of both fuel clad and RCS. Again, timing and the type of event that required the reactor trip initially are important factors on the expected damage. But to simplify the classification scheme, entry into EOP-1 3.0 indicates some time may pass before reactor power is low enough to prevent fuel damage.
The General Emergency EAL 431 detection method was not changed. The General Emergency classification is more closely related to the loss of fission product barriers. This event assumes continued power generation and demonstrated evidence of fuel damage or the loss of functions needed to support core cooling which could lead to core melt. With respect to critical safety functions, this event would represent a severe challenge to both "Subcriticality" and "Core Cooling".
The above changes match the intent of the Initiating Conditions of these EALs and reduce the possibility for misclassification. Therefore, these changes do not decrease the effectiveness of the Radiation Emergency Plan. These changes do require further revision to the Radiation Emergency Plan, Table 4-1. These changes do not require further revision to implementing procedures.
EPP-001, Activation and Implementation of Emergency Plan Revision 24, Change C Addendum to IOCFR5O.54.q Evaluation Page 4 of 5
==
Description:==
i Page 16 of 17: Added the following note to each of the Security related EALs, "See EPP-001 Attachment III for additional guidance".
Reason for Change:
To remind the user of the location of additional guidance for actions to take in a Security event.
I OCFR50.54.q Evaluation These changes affect 10CFR50.47(b)(4) and 10CFR50 Appendix E (IV.C).
These changes help to insure appropriate actions are taken in a Security event and enhance emergency response. Therefore, these changes do not decrease the effectiveness of the Radiation Emergency Plan. These changes do require further revision to the Radiation Emergency Plan, Table 4-1. These changes do not require further revision to implementing procedures.
==
Description:==
Attachment il Page 17 of 17: Corrected typographical error in the detection method for the first Alert EAL.
Reason for Change:
Correct typographical error.
IOCFR5O.54.q Evaluation This change affects 10CFR50.47(b)(4) and IOCFR50 Appendix E (IV.C). This change corrects a typographical error and is administrative in nature. Therefore, this change do not decrease the effectiveness of the Radiation Emergency Plan.
This change does require further revision to the Radiation Emergency Plan, Table 4-1. This change does not require further revision to implementing procedures.
EPP-001, Activation and Implementation of Emergency Plan Revision 24, Change C Addendum to I OCFRSO.54.q Evaluation Page 5 of 5
==
Description:==
Section 5.2.C: Removed the reference to declaring the emergency classification by using EIS.
Reason for Change:
Declaring an emergency is a decision made by the IED/ED and is not dependent on the availability of EIS.
IOCFR50.54.q Evaluation This change affects IOCFR50.47(b)(4) and 10CFR50 Appendix E (IV.C). This change does not alter the Emergency Action Level scheme. This change simplifies the emergency declaration process by removing a restrictive and inappropriate statement about using EIS to declare an emergency. EIS is not mentioned in the Radiation Emergency Plan, therefore, this change do not decrease the effectiveness of the Radiation Emergency Plan. This change does require further revision to the Radiation Emergency Plan, Table 4-1. This change does not require further revision to implementing procedures.
SAP-1 39 NUCLEAR OPFRATIONS ATTACHMENT IV 61 PAGE 1 OF 3 COPY NO. REVISION 18 PROCEDURE DEVELOPMENT FORM - A DATE: - PROC.# ---/' - Cr. . REV. # _2 CHG. L COMM. #
TITLE: 'I, /A-4fA .14 7 .Ln -22t:
427 eA/ jiI Z2MC'f ,I, - 1 {n7Z- L-*A_
NEW PROC CHANGE ._ PERMANENT SAFETY RELATED REVISION RESTRICTED FROM TO QUALITY RELATED NON-SAFETY RELATED REASON FOR CHANGE:
Originator soy"Pin III. WILL THIS REVISIOwCHANGE/NEW PROCEDURE: YES NO N/A
- 1. Result in significant increased personnel radiation exposure? (ALARA review)
- 2. Result in a release of effluents to the Environment?
- 3. Degrade the effectiveness of the Radiation Emergency Plan?
4- Degrade the safeguards effectiveness of the Physical SecUrity, Safeguards Contingency -_
of Training and Quaflication Plans?
If any question I through 4 Is answered 'YES", refer to approprdate section of procedure 1r direction.
REQUIRED REVIEW AND COMMENT: REQUESTED REVIEWS
() MOPS OMHPS ()GMNPO ()QA (TU 1)ISD (,K leJfl,_5 /I(
0 MMS OMDE ()GMES ()QC CHS ()RC O ,
C)MQS (MNT ()GMNSS (SFADC(WAPS ('&L)
() MSCE ()MNL&OE ()PMSPD ()MNTS ()SCE ().. ()________ ' - D C) MCHS OMNPS OPS (j0IPS (DE O.... (0 :* , /
Q REQUIRED7 EXEMPT [] PSRC SUPPORTING DOCUMENT-W/_Concurrence Ipine SudrX W,/
P V. TEMPORARY APPROVAL:
QUALIFIED REVIEWER_______ DATE 6/2.- A REVIEW_______ DATE _
TELECON BY__ TELECON BY SHIFT SUPERVISOR DATE FINAL APPROVAL REQUIRED BY: DATE VIL P/CAP ACCEPTABLE?
Vl. DISCIPLINE SUPERVISOR FINAL REVIEW: C. YES NO_
NO L-" N. YES__ NO___ /
PSRC REVIEW PRIOR TO IMPLEMENTATION? YES RESP. MGR. Date YES NO__ VII. FINAL OA REVIEW ( pcable)
TRAINING REQUIRED?
we I IF YES, PRIOR TO PROCEDURE IMPLEMENTATION? YES_ NO___ QA Concurrence Date
" , ' DL APPROVAL AUrTHORrrY':
P/CAP AFFECTED? YES/ A "X"I APV O COMMENTS RESOLVED/ Trfi pieted. Date Procedure ApprovaLComrnee Date X. PSRC REVIEW:
A- REVIEWED BY: B. PSRC COMMENTS RESOLVED:
I /
PSRC Chairman Dale Responsbe Manager Date COMMENTS: YES NO _
PSRC Chairman Dale
EPP-001 REVISION 24, CHANGE B
SUMMARY
OF CHANGES A. Reference 2.9, EPP-025, "Use of the ERON System" was deleted. The ERON System is no longer in use. The ERON System was used only for recording results of radio-pager drills and has been replaced by another system. It was not used for communicating with the Emergency Response Organization or offsite agencies. Therefore, there is no decrease in the level of effectiveness-of the Radiation Emergency Plan.
B. Step 4.3 was revised to remove all reference to the ERON System. (See A. above for justification.)
C. Attachment I, page 2 of 2, item 11. E was deleted.. This item described an Initiating Condition that is being revised to delete the referenced condition. The new 11. E was revised to better reflect the condition described in the referenced Initiating Condition. (See E. below for justification.)
D. Attachment II, page 1 of 17, The Initiating Condition and Detection Methods for the Notification of Unusual Event was revised. NRC approval for the revision was granted per letter dated July 11, 1997. The new Initiating Condition and Detection Methods were taken from NUMARC/NESP-007 which is approved by the NRC for use. Therefore, there is no decrease in the level of effectiveness of the Radiation Emergency Plan.
E. Attachment II, page 16 of 17, The Initiating Condition and Detection Methods for the Notification of Unusual Event was revised. NRC approval for the revision was granted per letter dated July 11, 1997. The new Initiating Condition and Detection Methods were taken from NUMARC/NESP-007 which is approved by the NRC for use. Therefore, there is no decrease in the level of effectiveness of the Radiation Emergency Plan.
SAP-139 NUCLEAR OPERATIONS ATTACHMENT IV 15"q PAGE 1 OF 3 COPYNO. REVISION 17 PROCEDURE DEVELOPMENT FORM -A I. DATE: .--- 7. PROC. # ' / - REV. # CHG. COMM. #
TITLE:
NEW PROC -- CHANGE ;7PERMANENT7 SAFETY RELATED REVISION RESTRICTED __ FROM TO QUALITY RELATED NON-SAFETY RELATED
- 11. DESCRIPTION: 4 4 £ ( 4 4A 6 7 REASON FOR CHANGE: 7 *4. ~ (~2 Originator Sign/Print Ill. WILL THIS REVISION/CHANGE/NEW PROCEDURE: *YES NO N/A
- 1. Result in significant increased personnel radiation exposure? (ALARA review)
- 2. Result ina release of effluents to the Environment?
- 3. Degradethe effectiveness of the Radiation Emergency Plan? ,
- 4. Degradethe safeguards effectiveness ofthe Physical Security, Safeguards Contingency or Training and Qualification Plans?
IIf any question I through 4 is answered 'YES', refer to appropriate section of procedure for direction.
REQ IRED REVIEW AND COMMENT: REQUESTED REVIEWS: /
01(!QR1(A) ONL&OE Wctsi- NPO C ___ ~ e L
,(OQA '(,1s -.(,)NTS (wNPS C')RPS -CGMNSS
(*SCE GMES C))_-///A
___ C . "% L .* =--7
()QC ()TU ODE 0- _ ) _iscipWXUpervisor .M.)_ I Date IV. 10CFR5O.59 SCREENING REVIEW/SAFETY EVALUATION o REQUIRED M-1.EMPT 3 PSRC SUPPORTING DOCUMENT: _d_____-__.____ _ D s.,,?o nulm.m e V. TEMPORARY APPROVAL:
QUALIFIED REVIEWER DATE QA REVIEW DATE TELECON BY TELECON BY SHIFT SUPERVISOR DATE / FINAL APPROVAL REQUIRED BY: DATE VI. DISCIPUNE SUPERVISOR FINAL REVIEW: VII. PICAPACCEPTABLE?
C. YES__ NO /
PSRC REVIEW PRIOR TO IMPLEMENT .ON? YES__ NO NL&OE Date N. YES_ NO /
TRAINING REQUIRED? YES I NO N. -- RESP. MGR- Date IF YES, PRIOR TO PROCEDURE IMPLEMENTATION? YES__ N0 VIIL 7lNbAlIEW) (AsApliabile)
P/CAPAFFECTED?
COMMENTS RES YES 0 F r QA Concurrence
- 2-taUzj'7Date p uDate ID. APPROVpAýUTHORITY:
TRAININGCOMPL Approval/Concurrence Date r Discip4L *ervisor 1Date X. PSRCREVIEW:
A. REVIEWED BY: B. PSRC COMMENTS RESOLVED:
I /
PSRCChairman Date Responsible Manager Date COMMENTS: YES__ NO I PSRC Chairman Date
EPP-0O01 PAGE i REVISION 24 TABLE OF CONTENTS SECTION PAGE Chg 1.0 PURPOSE AND SCOPE 1 ID
2.0 REFERENCES
1 3.0 DEFINITIONS 1 4.0 CONDITIONS AND PREREQUISITES 3 5.0 PROCEDURE 4 6.0 RECORDS 5 IChgC Chg 7.0 REVISION
SUMMARY
5 A ATTACHMENTS Attachment I - Emergency Action Level Cross Reference Guide Attachment II - Emergency Action Levels Attachment III- Considerations for a Security Emergency Chg A
EPP-001 REVISION 24 1.0 PURPOSE AND SCOPE 1.1 To define the Emergency Action Levels (EALs) that will activate and implement the Emergency Plan and to provide a means of classifying the emergency.
1.2 Changes and revisions to this procedure must ensure compliance with the requirements of 10CFR50.54.q. and 10CFR50 Appendix B. A 10CFR50.59 Chg review is not required. -D
2.0 REFERENCES
2.1 Virgil C. Summer Nuclear Station FSAR, Appendix 13A, "South Carolina Electric and Gas Company Virgil C. Summer Nuclear Station Radiation Emergency Plan".
2.2 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.
2.3 1 OCFR50, Appendix E.
2.4 1 0CFR50.54 (x) and (y), Applicability of License Conditions and Technical Specifications in an Emergency.
2.5 EPP-001.1, Notification of Unusual Event.
2.6 EPP-001.2, Alert.
2.7 EPP-001.3, Site Area Emergency.
2.8 EPP-001.4, General Emergency.
2.9 SAP-1 131, Electronic Processing of Condition Evaluation Reports. Chg B and C 2.10 NUREG-1022, Event Reporting Guidelines 10CFR50.72 and 50.73. Chg C 3.0 DEFINITIONS 3.1 Definitions 3.1.1 Notification of Unusual Event - Off normal events which could indicate a potential degradation of the level of safety of the plant.
3.1.2 Alert - Events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant.
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EPP-001 REVISION 24 3.1.3 Site Area Emergency - Events which involve actual or likely major failures of plant functions needed for protection of the public.
3.1.4 General Emergency - Events which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Chg C 3.2 Abbreviations 3.2.1 EAL - Emergency Action Level 3.2.2 NUE - Notification of Unusual Event 3.2.3 lED - Interim Emergency Director 3.2.4 ED - Emergency Director 3.2.5 EPP - Emergency Plan Procedure 3.2.6 EOP - Emergency Operating Procedure 3.2.7 TEDE - Total Effective Dose Equivalent 3.2.8 CDE- Committed Dose Equivalent 2 of 5
EPP-001 REVISION 24 4.0 CONDITIONS AND PREREQUISITES 4.1 The Emergency Plan shall be implemented whenever an "Initiating Condition" (as identified in Attachment II) has occurred.
NOTE 4.2 The implementation of any specific Emergency Plan Procedure (except this procedure) does not necessarily implement the Emergency Plan, but may do so at the discretion of the IED/ED. For example: a small chlorine leak would implement the toxic release procedure but not necessitate implementation of the Emergency Plan, whereas a large release with the potential of affecting the level of safety of the plant would implement the toxic release procedure and the Emergency Plan due to the declaration of a NUE.
4.2 The "Initiating Condition" and "Detection Method" shall be used to determine the applicable EAL. The Detection Methods are intended to be a guide for the proper classification of an emergency. The judgment of the IED/ED may take precedence in determining if the Initiating Condition has been met or exceeded.
4.3 The 3 digit number in parenthesis associated with EALs on Attachment I1is B the Emergency Information System (EIS) Emergency Type Code. I Chg.
NOTE 4.4 When the plant is in a security related event, deviation from the Chg.
A guidance in the Emergency Plan Procedures is allowed when the safety of plant personnel and/or plant equipment must be considered. See Attachment III for additional guidance.
4.4 The Duty Shift Supervisor must concur with any actions that depart from a license condition or technical specification in an emergency when such actions are immediately needed to protect the public health and safety (Reference 2.4).
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EPP-001 REVISION 24 4.5 Attachment I provides a cross reference for the EAL Classification and should only be used as a guide to locate the "Initiating Condition" in Attachment II, Emergency Action Levels.
5.0 PROCEDURE 5.1 Upon recognition of an abnormal plant or site condition, the observer shall notify the Duty Shift Supervisor of the potential emergency plan condition.
NOTE 5.2 When the TSC is activated, the ED is responsible for determining the appropriate EAL and emergency classification.
5.2 The IED/ED shall:
A. Using Attachment I for guidance, locate the appropriate initiating condition and turn to the referenced page in Attachment II.
B. Determine the EAL by comparing the verified plant parameters or conditions to the detection method for each emergency condition.
C. Declare the appropriate emergency classification. Perform additional Chg actions in accordance with the EOPs and the appropriate EPPs. C Notification of Unusual Event - EPP-001.1 Alert - EPP-001.2 Site Area Emergency - EPP-001.3 General Emergency - EPP-001.4 5.3 Undeclared or Misclassified Events C01--> A. When it is discovered that an event or condition had existed which met the criteria for Emergency Plan activation but no emergency had been declared and the basis for the emergency classification no longer exists, the IED/ED shall insure that an ENS notification to the NRC and ESSX Chg C
notification to the State and local governments is made within one hour of the discovery of the undeclared or misclassified event. No "after-the-fact" emergency declaration is necessary.
4 of 5
EPP-001 REVISION 24 6.0 RECORDS 6.1 There are no records generated by this procedure.
7.0 REVISION
SUMMARY
7.1 Include use of Emergency Type Codes in EIS in step 4.3.
7.2 Include use of Emergency Type Codes in EIS in step 5.2.C.
7.3 Incorporate Change A.
7.4 Addition of SAP-1122.
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EPP-O01 ATTACHMENT I PAGE 1 OF 2 REVISION 24 EMERGENCY ACTION LEVEL CROSS REFERENCE GUIDE NOTE: This Attachment is not to be used for Event Classification. Refer to Attachment Ii.
INITIATING EVENT/TOPIC REFERENCE PAGE IN ATTACHMENT II 1 Reactor Coolant System A. Reactor Coolant Leakage I B. Loss-of-Coolant Accident (LOCA) 1 C. Pressurizer or Steam Generator Safety or Relief Valve Fails to Reseat 2 D. Loss of Fission Product Barriers 4 E. Primary to Secondary Leakage 3,4 F. Major Steam Line Break with Primary to Secondary Leak 4
- 2. Secondary System A. Major Steam Line Break 4 B. Steam Generator Safety or Relief Valve Fails to Reseat 2 C. Secondary System Depressurization 5 D. Loss of Feedwater and Condensate System 5 E. Failure of Emergency Feedwater System 5, 8 F. Turbine-Generator Rotating Component Failure 5
- 3. Fuel A. Fuel Damage 1,2,4,6,7 B. Fuel Handling Accident 6 C. Loss of Fission Product Barriers 4 D. Loss of Coolable Geometry 1, 2, 6
- 4. Engineered Safety Feature A. Failure of the Reactor Protection System 7 B. Operation of Shutdown Systems with Failure to Trip 7
- 5. Station Power A. Loss of Offsite Power 3, 8 B. Loss of Onsite AC Power 8 C. Loss of Onsite DC Power 8
- 6. Containment A. Loss of Containment Integrity 4
- 7. Radiological Effluents 9,10 A. Liquid or Gaseous Effluent Exceeds Technical Specification 9 B. High Radiation Levels 9,10 C. Radiation Levels Detected/Projected at the Exclusion Area Boundary
EPP-001 ATTACHMENT I PAGE 2 OF 2 REVISION 24 EMERGENCY ACTION LEVEL CROSS REFERENCE GUIDE NOTE: This Attachment is not to be used for Event Classification. Refer to Attachment II INITIATING EVENT/TOPIC REFERENCE PAGE IN ATTACHMENT II
- 8. Fire A. Fire Lasting More Than 15 Minutes 11 B. Fire Effecting Safety Trains, Systems or Functions 11
- 9. Security A. Security Threats, Attempted Entry or Sabotage 12
- 10. Natural Phenomenon A. Natural Events Onsite or Near Site 13 (Earthquake, Tornado, or Hurricane)
B. Other Hazards Onsite or Near Site 14 (Aircraft Crash, Train Derailment, Explosion or Toxic/Flammable Gas Release)
- 11. Other A. Emergency Director Discretion Based On Other Plant Conditions 15 B. Inability to Reach Required Shutdown Within Technical Specification Limits 15 C. Loss of Function for Plant Cold or Hot Shutdown 16 D. Control Room Evacuation 16 Cg E. Loss of Communications Capability 16s F. Loss of RHR 1,17
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EPP-001 ATTACHMENT II PAGE 1 OF 17 REVISION 24 EMERGENCY ACTION LEVELS REACTOR COOLANT SYSTEM
-r r ----------. . 1 NOTIFICATION OF UNUSUAL EVENT ALERT SITE1 AHEA EMEH(3lNUY ULNERHALEMHRHGNUY ALER SITE- ARAEEREC INITIATING CONDITION (101) INITIATING CONDITION (201) INITIATING CONDITION (301) INITIATING CONDITION (401)
RCS LEAKAGE REACTOR COOLANT LEAKAGE RATE KNOWN LOSS-OF-COOLANT ACCIDENT SMALL OR LARGE LOSS OF COOLING EXCEEDS 50 GALLONS PER MINUTE GREATER THAN CHARGING PUMP CAPACITY ACCIDENT WITH FAILURE OF EMERGENCY CORE COOLING SYSTEM TO PERFORM, LEADING TO SEVERE CORE DEGRADATION OR MELT.
Chi 13 Detection Method: Detection Method: Detection Method: Detection Method:
EITHER 1 OR 2: Excessive Makeup to the Volume Control Tank. All of the following (1 - 7) OR 8: Items I - 7 OR 8 under Site Area Emergency and (Only applicable in Modes 1 through 4.) EITHER 1 OR 2:
- 1. Pressurizer low pressure reactor trip,
- 1. Unidentified or Pressure Boundary Leakage 2. Pressurizer low pressure safety Injection 1. Indications that safety Injection and RHR greater than 10 gpm. signal, pumps are not running (no AMPS).
- 4. Reactor Building sump level above zero,
- 2. Identified Leakage greater than 25 gpm. 5. RBCU Drain Flow High, 2. Flow indication for safety injection and RHR
- 6. RM-A2, RM-G7, RM-G18 high alarm, pumps reading zero.
- 7. Reactor Building temperature >120°F.
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EPP-001 ATTACHMENT II PAGE 2 OF 17 REVISION 24 EMERGENCY ACTION LEVELS RIFAc.TOR C.OOLANT SYSTEM NOTIFICATION OF UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY INITIATING CONDITION (102) INITIATING CONDITION (4021 SMALL LOSS OF COOLING ACCIDENT WITH FAILURE OF A PRESSURIZER OR STEAM INITIALLY SUCCESSFUL EMERGENCY CORE GENERATOR SAFETY OR RELIEF VALVE TO COOLING SYSTEM, FOLLOWED BY RESEAT (EXCEEDING NORMAL WEEPAGE) SUBSEQUENT FAILURE OF REACTOR BUILDING HEAT REMOVAL SYSTEMS THAT COULD LEAD TO CORE MELT Detection Method:
Detection Method:
All of the following (1 - 5):
Pressurizer or Steam Generator Safety or Relief Valve opens and then fails to reseat as indicated
- 1. Pressurizer low pressure reactor trip, by EITHER 1 OR 2 OR 3:
AND
- 1. Valid open indication of Pressurizer Relief OR Safety Valve OR valid Acoustical Monitor indication. 2. Pressurizer low pressure safety injection signal, OR AND
- 2. Visual OR audible indication at vent stacks of 3, RHR flow indicators show zero flow for greater open Stearn Generator Safety or Relief Valve. than 30 minutes after shift to RHR, OR AND
- 3. Excess feedwater flow to and steam flow from affected Steam Generator. 4. RCS temperature rising, AND
- 5. Reactor Building Spray and Reactor Building Cooling Units fail to function.
_____________________ L I
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EPP-001 ATTACHMENT II PAGE 3 OF 17 REVISION 24 EMERGENCY ACTION LEVELS REACTOR COOLANT SYSTEM NOTIFICATION OF UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY INITIATING CONDITION (202) I INITIATING CONDITION (302) I INITIATING CONDITION (103)
EXCEEDING TECHNICAL SPECIFICATION RAPID GROSS FAILURE OF ONE STEAM RAPID FAILURE OF SEVERAL STEAM GENERATOR TUBE WITH LOSS OF OFFSITE GENERATOR TUBES (SEVERAL HUNDRED PRIMARY TO SECONDARY LEAK RATE LIMIT POWER GALLONS PER MINUTE PRIMARY-TO SECONDARY LEAK RATE) WITH LOSS OF OFFSITE POWER Detection Method: Detection Method: Detection Method:
Primary to Secondary Leak Rate Exceeds T.S. All of the following (1 - 5): All of the following (1 - 3):
3.4.6.2 Limits:
- 1. Pressurizer low pressure alarm AND reactor 1. Entry into EOP-4.0,
- 1. >1 gpm Total for > 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. trip,
- 2. > 500 gpd any one Steam Generator for AND
> 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. AND
- 2. Loss of 115KV and 230KV Emergency
- 2. Pressurizer low level alarm, Safeguards Power Potential Lights, AND AND
- 3. RM-A9, G19A, G-19B, OF G19C valid high 3. Lifting of Steam Generator Power Operated alarm supported by laboratory analysis, Relief Valves or Safety Valves.
AND
- 4. Pressurizer low pressure safety injection signal, AND
INITIATING CONDITION (203)
RAPID FAILURE OF SEVERAL STEAM GENERATOR TUBES (e.g., SEVERAL HUNDRED GALLONS PER MINUTE PRIMARY TO-SECONDARY LEAK RATE)
Detection Method:
S.....
Ent Int Into EOP-4 0
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EPP-001 ATTACHMENT II PAGE 4 OF 17 REVISION 24 EMERGENCY ACTION LEVELS REACTOR COOLANT SYSTEM NOTIFICATION OF UNUSUAL EVENT I ALERT I I
SITE AREA EMERGENCY I GENERAL EMERGENCY INITIATING CONDITION (204) INITIATING CONDITION (3031 I INITIATING CONDITION (403)
MAJOR STEAM LINE BREAK WITH GREATER LOSS OF TWO OF THREE FISSION MAJOR STEAM LINE BREAK (o.g., GREATER THAN 6 INCHES EQUIVALENT DIAMETER) THAN 50 GALLONS PER MINUTE PRIMARY PRODUCT BARRIERS WITH POTENTIAL TO-SECONDARY LEAKAGE AND INDICATION LOSS OF THE THIRD BARRIER (e.g., LOSS WITH A SIGNIFICANT PRIMARY-TO OF FUEL DAMAGE. OF FUEL INTEGRITY AND PRIMARY SECONDARY LEAK RATE.
COOLANT BOUNDARY AND HIGH POTENTIAL FOR RADIOACTIVITY RELEASE FROM CONTAINMENT)
Detection Method: Detection Method: Detection Method; All of the following (1 - 3): All of the following (1 - 4): EITHER 1 2 OR 3:
1, All of the following rapidly decreasing: 1. All of the following rapidly decreasing: 1. Primary coolant dose equivalent 1-131
- a. Tavg activity > 300 pCi/gm AND LOCA in
- a. Tavg b. PZR pressure progress AND Reactor Building
- b. PZR pressure c. PZR level, pressure _>30 psig for at least 2 minutes
- c. PZR level, AND Ch(
OR E AND 2. High alarms on RM-A9 and laboratory analysis of secondary coolant activity 2. Primary coolant dose equivalent 1-131
- 2. High alarms on either RM-L3, _10, OR A9, supporting 50 gpm leakage, activity > 300 pCi/gm AND breech of containment integrity AND AND and EITHER a OR b:
Chg
- 3. EITHER a OR b: 3. RM-L1 High Range valid alarm and a. RCS leakage greater than Technical primary coolant dose equivalent 1-131 E Specification allowable.
- a. For break inside RB: activity > 300 VCi/gm, High-i RB pressure AND safety injection OR actuation. AN__
- b. RCS pressure > 2335 psig.
- b. For break outside RB: a, For break Inside RB:
safety Injection actuation due to steamlinE High-1 RB pressure AND safety injection 3. LOCA AND breech of containment integrity AP or low steamlino pressure actuation. and EITHER a OR b:
OR a. Dose equivalent 1-131 activity
>llpCi/gm in primary coolant.
- b. For break outside RB:
safety injection actuation due to OR steamline AP or low steamllne pressure.
Refer to Loss of 2 of 3 FP Barriers b. Core Exit temperaiure > 700 (Possible General Emergency).
_____________________________________________ .1.
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EPP-001 ATTACHMENT II PAGE 5 OF 17 REVISION 24 EMERGENCY ACTION LEVELS SECONDARY SYSTEM SITE AREA EMERGENCY GENERALEMERGENCY NOTIFICATION OF UNUSUAL EVENT ALERT INITIATING CONDITION (411)
INITIATING CONDITION (104) TRANSIENT INITIATED BY LOSS OF RAPID SECONDARY SYSTEM FEEDWATER AND CONDENSATE SYSTEMS DEPRESSURIZATION (PRINCIPLE HEAT REMOVAL SYSTEM)
FOLLOWED BY FAILURE OF EMERGENCY FEEDWATER SYSTEM FOR EXTENDED PERIOD. CORE MELTING POSSIBLE IN SEVERAL HOURS Detection Method:
Detection Method:
EITHER 1IOR 2:
Rapid decrease in S/G pressure resulting in a safety injection actuation. 1. a. Failure of feed and bleed of the RCS to maintain core cooling, AND
- b. Steam Generator wide range levels less INITIATING CONDITION (292) than 15% in two or more steam generators.
INITIATING CONDITION (105)
OTHER HAZARDS BEING EXPERIENCED OR OTHER HAZARDS BEING EXPERIENCED OR OR PROJECTED WHICH HAVE THE POTENTIAL PROJECTED WHICH HAVE A SIGNIFICANT FOR ENDANGERING THE FACILITY POTENTIAL FOR AFFECTING PLANT SAFETY
- 2. a. Failure of feed and bleed of the RCS to (TURBINE-GENERATOR ROTATING (TURBINE -GENERATOR FAILURE CAUSING maintain core cooling, COMPONENT FAILURE CAUSING RAPID CASING PENETRATION)
ANQ PLANT SHUTDOWN)
- b. RCS Pressure > 2335 psig due to loss Detection Method: Detection Method:
of heat sink.
All of the following ( 1 AND 2): All of the following (I AND 2):
- 1. Turbine Trip, 1. Turbine Trip, AND AND
- 2. Observation of Failure of EITHER a OR b: 2. Observation of penetration of the turbine casing
- a. Turbine Rotating Assembly.
OR U. ,.3 III*.LU 0l LAII
- 4; '
A hlly U. SIHeneat, or 1111
. . lOO9
. JE.
Lj I
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( C EPP-001 ATTACHMENT II PAGE 6 OF 17 REVISION 24 EMERGENCY ACTION LEVELS FUEL NOTIFICATION OF UNUSUAL EVENT ALERT 1 SITE AREA EMERGENCY INITIATING CONDITION (321
[
I GENERALEMERGENCY INITIATING CONDITION (106) INITIATING CONDITION (221 FUEL DAMAGE INDICATION POSSIBLE FUEL DAMAGE DEGRADED CORE WITH POSSIBLE LOSS OF COOLABLE GEOMETRY Detection Method: Detection Method: Detection Method:
All of the following (1 AND 2): All of the following (1 AN.DD2): All of the following (1 - 3):
- 1. RM-L1 High Range Alarm, 1. RM-Li High Range Alarm, 1 RM-[I1 High Range off scale (>100cpm) with primary coolant dose equivalent Chg AND AND 1-131 activity > 300 pCi/gm, E AND
- 2. Primary coolant dose equivalent 1-131 Chg 2. Primary coolant dose equivalent 1-1311 Chg activity _>30 pCi/gm. E activity > 300 pCi/gm. E 2. Core Exit Temperatures_> 700°F, AND
- 3. No indication of forced or natural circulation.
INITIATING CONDITION (222) INITIATING CONDITION (322)
FUEL HANDLING ACCIDENT WITH RELEASE MAJOR DAMAGE TO MORE THAN ONE OF RADIOACTIVITY TO REACTOR OR FUEL SPENT FUEL ASSEMBLY IN REACTOR HANDLING BUILDING BUILDING OR FUEL HANDLING BUILDING LEADING TO CLAD RUPTURE (e.g., LARGE Detection Method: OBJECT DAMAGES FUEL OR WATER LOSS BELOW FUEL LEVEL)
EITHER 1 OR 2 Detection Method:
- 1. a. In the Reactor Building:
Observation of damage to spent fuel EITHER 1 OR 2:
assembly,
- 1. a. In the Reactor Building:
AND Observation of major damage to more than one spent fuel assembly OR water
- b. RM-G5, RM-G17A, 17B high alarm. level below the tops of spent fuel assemblies, OR AND
- 2. a. In the Fuel Handling Building: b. RM-G5, G17A, G17B high alarms.
Observation of damage to spent fuel OR assembly,
- 2. a. In the Fuel Handling Building:
Observation of major damage to more AND than one spent fuel assembly OR water level below the tops of spent fuel
- b. RM-A6 high alarm, OR RM-G8 high assemblies, alarm.
AND
- b. RM-A6 or RM-G8 high alarm.
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( C EPP-001 ATTACHMENT II PAGE 7 OF 17 REVISION 24 EMERGENCY ACTION LEVELS ENGINEERED SAFETY FEATURE NOTIFICATION OF JNUSUAL EVENT ALERT I SITE AREA EMERGENCY I GENERAL EMERGENCY INITIATING CONDITION (231) INITIATING CONDITION (331 INITIATING CONDITION (4311 TRANSIENT REQUIRING OPERATION OF TRANSIENT REQUIRING OPERATION OF FAILURE OF THE REACTOR PROTECTION SHUTDOWN SYSTEMS WITH FAILURE TO SHUTDOWN SYSTEMS WITH FAILURE TO SYSTEM TO INITIATE AND COMPLETE A-TRIP TRIP (CONTINUED GENERATION, NO FUEL TRIP WHICH RESULTS IN CORE DAMAGE OR WHICH BRINGS THE REACTOR SUBCRITICAL DAMAGE EVIDENT) ADDITIONAL FAILURE OF CORE COOLING AND MAKEUP SYSTEMS WHICH COULD LEAD TO CORE MELT Detection Method: Detection Method: Detection Method:
An automatic reactor trip fails when required, Entry into EOP-13.0 from EOP-1.0, Step 1 EITHEB 1 OR 2 OR 3:
Chg AND C 1. a. Reactor remains critical after attempted trip, A manual reactor trip from either MCB handswitch Is successful. AND
- b. RM-L1 alarm, with primary coolant dose equivalent 1-131 activity Chg
_>300 p.Ci/gm. E OR
- 2. a. Reactor remains critical after attempted trip, AND
- b. Flow indicators on safety Injection system AND RHR systems show zero flow with safety Injection Initiated.
- 3. a. Reactor remains critical after attempted trip.
AND
- b. Status lights show safety injection system AND RHR pumps not running with safety Injection Initiated.
_______________________ i ______________________ I ______________________ I
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EPP-001 ATTACHMENT II PAGE 8 OF 17 REVISION 24 EMERGENCY ACTION LEVELS STATION POWER KltTIC',ATflMQ nt\ll C1 I NIH- AI EIVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY INITIATING CONDITION (241 INITIATING CONDITION (341) INITIATING CONDITION (441)
INITIATING CONDITION (107) LOSS OF OFFSITE POWER AND LOSS OF FAILURE OF OFFSITE AND ONSITE POWER TOTAL LOSS OF OFFSITE POWER OR LOSS LOSS OF OFFSITE POWER AND LOSS OF ONSITE AC POWER FOR MORE THAN ALONG WITH TOTAL LOSS OF EMERGENCY OF ONSITE AC POWER CAPABILITY ALL ONSITE AC POWER FOR MORE FEEDWATER MAKEUP CAPABILITY.
5 MINUTES 15 MINUTES Detection Method: Detection Method:
Detection Method: Detection Method:
EITHER 1 OR 2: All of the following (I - 3):
In Modes 1-6, EITHER 1 Qf 2 OR 3: EITHER 10. 2:
- 1. a. Both Diesel Generators Inoperable, 1. Both Diesel Generators inoperable
- i. Loss of 115KV AND 230KV ESF Potential 1. a. Both Diesel Generators inoperable, Lights. AND AND AND OR 2. EITHER a OR b:
- 2. Automatic actuation of both trains of OR a. Loss of 11 5KV AND 230KV ESF emergency Diesel Generators due to OR degraded or undervoltage conditions. potential lights.
- 2. a. Both Diesel Generators inoperable, 2. a. Both Diesel Generators Inoperable, OR OR AND AND
- b. Automatic actuation of both trains of
- 3. Both Diesel Generator inoperable for > 1 emergency Diesel Generators due to
- b. Automatic actuation of both trains of b. Automatic actuation of both trains of hour. degraded voltage or undervoltage emergency Diesel Generators due to emergency Diesel Generators due to conditions, degraded or undervoltage conditions. degraded or undervoltage conditions..
AND INITIATING CONDITION (242) INITIATING CONDITION (342)
LOSS OF ALL VITAL ONSITE DC POWER FOR 3. EITHER aOR b:
LOSS OF ALL ONSITE DC POWER FOR A PERIOD GREATER THAN 5 MINUTES MORE THAN 15 MINUTES
- a. Steam Driven Emergency Feedwater Detection Method: Pump falls to start AND is inoperable Detection Method: for one hour.
All of the following (1 - 3): All of the following (1 - 3):
- b. Core Exit temperatures > 7000 F.
AND AND
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EPP-001 ATTACHMENT II PAGE 9 OF 17 REVISION 24 EMERGENCY ACTION LEVELS RAfiI O11WAI*A FFFLUIENTS NOTIFICATION OF UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY INITIATING CONDITION (261) INITIATING CONDITION (461)
INITIATING CONDITION (108) INIIIAIING UUOUINIIUTIN (36 EFFLUENT MONITORS DETECT LEVELS SUSTAINED HIGH RADIATION LEVELS OR PROJECTED DOSE GREATER THAN GASEOUS EFFLUENT INSTANTANEOUS CORRESPONDING TO 1 REM TEDE RELEASE RATE TECHNICAL SPECIFICATION HIGH AIRBORNE CONTAMINATION WHICH 50 MILLIREM TEDE (WHOLE BODY)
INDICATES A SEVERE DEGRADATION IN THE (WHOLE BODY)
LIMITS EXCEEDED FOR 1 HOUR (APPENDIX B TABLE II,COLUMN 1 10CFR20) CONTROL OF RADIOACTIVE MATERIALS OR OR (e.g., INCREASE BY A FACTOR OF 1000 IN DIRECT RADIATION READINGS)
GREATER THAN 250 MILLIREM CDE 5 REM CDE (THYROID) AT THE EXCLUSION (THYROID) AT OR BEYOND THE EXCLUSION AREA BOUNDARY UNDER ACTUAL AREA BOUNDARY METEOROLOGICAL CONDITIONS.
Detection Method: Detection Method: Detection Method:
Detection Method:
EITHER 1 OR 2: Non-routine release(s) cause an alarm of RM-A3, All of the following (1 AND 2):
A4, A13, A14, or RM-G19 (or detection by other I. Unexpected valid RMG readings as follows: means) warrant an offsite dose assessment and 1, Radiation Monitor levels exceed those
- i. RM-A3 (Gas) increases > 1 x 105 cpm above specified for Site Area Emergency, bkgd iii any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. the results indicate projections exceeding the
- a. RM-G2-4, 8.13, or 16; greater than above doses at or beyond the exclusion area 2.5 R/hr OR boundary. AND OR b) RM-G7, 17A, 17B, or 18 greater than 100 R/hr OR 2. Calculation on Dose Assessment Forms
- 2. RM-A3 (Iodine) increases > 8 x 104 cpm indicates levels exceeding I Rem TEDE above bkgd in any I hour. c) RM-G1; greater than 1 R/hr.
(whole body) or 5 Rem CDE (thyroid) at the OR exclusion area boundary using radiation OR monitor readings and effluent stream flow rates (measured or assumed) for actual
- 3. RM-A4 (Gas) exceeds 4 times the high alarm Unexpected plant area Iodine or particulate meteorological conditions; or using field setpoint for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. airborne concentration greater than 1000 DAC measurements.
(as per 10CFR20 Appendix B, Table 1).
- 4. RM-A4 (Iodine) in valid high alarm for more than I hour.
Classification for gaseous radiological effluents Classification for gaseous radiological effluents Classification for gaseous radiological effluents can also be determined using EPP-005. Classification for gaseous radiological effluents can also be determined using EPP-005.
can also be determined using EPP-005.
can also be determined using EPP-005. I I
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EPP-001 ATTACHMENT II PAGE 10 OF 17 REVISION 24 EMERGENCY ACTION LEVELS DfI:Anl'i fl(r.Cl FFFi1 IIENT5R NOTIFICATION OF UNUSUAL EVENT IALERT ITIOIINOFUUV [I--ERTEllN.TnE I EFLSITE SE AREAEN EMERGENCY ER _GENERAL EMERGENCY INITIATING CONDITION (262) I INITIATING CONDITION (362)
INITIATING CONDITION (109) DOSE RATES LISTED BELOW ARE LIQUID EFFLUENT CONCENTRATIONS RADIOLOGICAL EFFLUENT RELEASE RATE EXCEEDING 10 TIMES TECHNICAL PROJECTED BASED ON GAMMA RADIATION TECHNICAL SPECIFICATIONS LIMITS MONITOR (RMG) READINGS AND/OR OTHER EXCEEDED FOR 15 MINUTES (APPENDIX B SPECIFICATION INSTANTANEOUS LIMITS PLANT PARAMETERS OR ARE MEASURED TABLE IICOLUMN 2 10CFR20) AT THE EXCLUSION AREA BOUNDARY Detection Method: Detection Method:
Detection Method:
Any of the following valid radiation monitor EITHER I OR 2 OR 3:
Any of the following liquid effluent monitors in valid High Alarm for longer than 15 mrin. AND readings for longer than 15 minutes:
- 1. Reactor Building leak rate results in isolation valve(s) fail to close: calculated dose rate at exclusion area
- 1. RM-A3 (Gas) is off scale high.
boundary greater than 50 mrem/hr whole RM-L5 OR body for 0,5 hr. or RM-L7 OR OR 500 mrem/hr whole body for 2 min.
RM-Lg. 2. RM-A3 (Iodine) is off scale high*
- 2. Radiation Monitoring Teams measure dose
- 3. RM-A4 (Gas) exceeds 40 times high alarm rates greater than 50 mrem/hr for 0.5 hr. or greater than 500 mrem/hr for 2 min. (beta +
setpoint. gamma) at one mile or greater from the plant.
- 4. RM-A4 (Iodine) exceeds 10 times high alarm setpoint. 3. Radiation Monitoring Teams measure thyroid dose rates (equivalent 1-131 concentrations)
OR greater than EITHER a or b:
- 5. RM-L5, RM-L7, or RM-L9 exceeds 10 times a. 250 mrem/hr high alarm setpoint ANQD Isolation valve(s) fail (1.3x10,7 pCI/cc) for 0.5 hr.
to close.
- b. 2500 mrem/hr 6
(1.3x10s .CI/cc) for 2 min. at one mile oi greater from the plant.
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( K K EPP-001 ATTACHMENT II PAGE 11 OF 17 REVISION 24 EMERGENCY ACTION LEVELS FIRE NOTIFICATION OF UNUSUAL EVENT ALERT SITE AREA
... Q..
. . ZA
. . .. . EMERGENCY
. J GENERAL EMERGENCY INITIATING CONDITION (110) INITIATING CONDITION (271) I I1,1I Im I#
I ' 11m %,pId UImI IUIm 101 FIRE POTENTIALLY AFFECTING SAFETY FIRE AFFECTING SAFETY TRAINS OR FIRE WITHIN THE PROTECTED AREA OR THE FUNCTIONS SWITCHYARD LASTING MORE THAN SYSTEMS.
15 MINUTES Detection Method: Detection Method:
Detection Method:
Observation of fire that could affect one or more Observation of major fire that defeats both trains EITHER 1 OR 2: of a safety system or function.
safety systems.
- 1. Observation.
OB
- 2. Fire Detection Device alarm with confirming observation.
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EPP-001 ATTACHMENT II PAGE 12 OF 17 REVISION 24 EMERGENCY ACTION LEVELS SECURITY NOfTIFICIATIOfN OF UlNtJUSAL EVENT I ALERT I SITE AREA EMERGENCY I GENERAL EMERGENCY INITIATING CONDITION (381 I INITIATING CONDITION (481)
INITIATING CONDITION (111) SECURITY THREAT RESULTING IN LOSS OF ONGOING SEVERE SECURITY THREAT SECURITY THREAT INVOLVING IMMINENT SECURITY THREAT OR ATTEMPTED ENTRY PHYSICAL CONTROL OF THE FACILITY LOSS OF PHYSICAL CONTROL OF THE OR ATTEMPTED SABOTAGE PLANT Detection Method: Detection Method:
Detection Method: Detection Method: Physical attack on the Plant has resulted in Report to ttie Control Room by Security or Security safeguards contingency event which Physical attack on the Plant involving imminent occupation of EITHER 1 OR 2:
observer. results in adversaries commandeering an area of the plant, but not impacting shutdown capability. occupancy of EITHER I OR 2:
- 1. Control Room.
- 1. Control Room.
OR OR
- 2. Control Room Evacuation Panel Rooms.
- 2. Control Room Evacuation Panel Rooms.
Ch See EPP-001 Attachment IIIfor additional See EPP-001 Attachment III for additional C I See EPP-OO Attachment IIIfor additional See EPP-001 Attachment IIIfor additional guidance. guidance. guidance.
guidance.
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EPP-001 ATTACHMENT 11 PAGE 13 OF 17 REVISION 24 EMERGENCY ACTION LEVELS NATURAL PHENOMENON NOTIFICATION OF UNUSUAL EVENT I ALERT SITE AREA EMERGENCY [
I GENERAL EMERGENCY INITIATING CONDITION (291) INITIATING CONDITION (391)
INITIATING CONDITION (112)
SEVERE NATURAL EVENT NEAR SITE: SEVERE NATURAL PHENOMENON BEING NATURAL EVENTS:
- 1. EARTHQUAKE GREATER THAN THE EXPERIENCED OR PROJECTED WITH PLANT
- 1. EARTHQUAKE NOT INCOLD SHUTDOWN:
- 2. TORNADO ONSITE 2/3 OPERATING BASIS EARTHQUAKE LEVEL 1. EARTHQUAKE GREATER THAN
- 3. HURRICANE NEAR SITE
- 2. TORNADO STRIKING FACILITY OPERATING BASIS EARTHQUAKE LEVEL
- 3. SUSTAINED HURRICANE WINDS 2. SUSTAINED WINDS IN EXCESS OF GREATER THAN 75 MILES PER HOUR 100 MILES PER HOUR ONSITE Detection Method: Detection Method:
Detection Method:
EITHER 1 OR 2 QO3: EITHER 1 OR 2:
- 1. For Earthquake: 1. For Earthquake: 1. For Earthquake:
Seismic Event Annunciator 2/3 OBE Observation of the event (felt or heard)
Seismic Recording System Start Indication and confirmation of a seismic event thru exceeded (one or more yellow lights lit) and lasting >2 seconds and EITHER a OR b:
observation (felt or heard) in the Control confirmation of a seismic event through a. RB Foundation Seismic Switch OBE Room. observation (felt or heard) in the Control Room. exceeded.
- 2. For Tornado:
- 2. For Tornado: b. Seismic Event Annunciator OBE Observation of event in Exclusion Area.
Observation of the event within the exceeded (one or more red lights lit).
OR Protected Area or Switchyard.
- 3. For Hurricane: OR
- 2. For sustained winds in 'ecess of 100 mph Sustained winds in excess of 50 mph due to a
- 3. For Hurricane: onsite:
hurricane as measured by onsite Sustained winds In excess of 75 mph due to As measured by onsite meteorological meteorological instrumentation or the National Weather Service. a hurricane as measured by onsite instrumentation or the National Weather meteorological instrumentation or the Service.
National Weather Service.
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EPP-001 ATTACHMENT II PAGE 14 OF 17 REVISION 24 EMERGENCY ACTION LEVELS MANMADE PHENOMENON NOTIFICATION OF UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY INITIATING CONDITION (292) INITIATING CONDITION (392) I INITIATING CONDITION (113)
OTHER HAZARDS BEING EXPERIENCED OR OTHER HAZARDS BEING EXPERIENCED OR OTHER HAZARDS BEING EXPERIENCED OR PROJECTED WHICH HAVE THE POTENTIAL PROJECTED WHICH HAVE A SIGNIFICANT PROJECTED WITH PLANT NOT IN COLD FOR ENDANGERING THE FACILITY: POTENTIAL FOR AFFECTING PLANT SAFETY: SHUTDOWN:
- 1. ONSITE AIRCRAFT CRASH 1. AIRCRAFT CRASH ON FACILITY 1. AIRCRAFT CRASH INTO VITAL
- 2. ONSITE TRAIN DERAILMENT 2. MISSILE IMPACTS ON FACILITY WITH STRUCTURES,
- 3. ONSITE EXPLOSION (EXCLUDING RESULTANT MAJOR DAMAGE 2. MISSILE OR EXPLOSION IMPACT ON PLANNED ACTIVITIES) 3. KNOWN EXPLOSION AT FACILITY FACILITY RENDERING SEVERE DAMAGE
- 4. NEAR OR ONSITE TOXIC OR FLAMMABLE RESULTING IN MAJOR DAMAGE TO TO SHUTDOWN EQUIPMENT GAS RELEASE OF A MAGNITUDE THAT PLANT STRUCTURES OR EQUIPMENT 3. ENTRY OF TOXIC OR FLAMMABLE GASES THREATENS PERSONNEL 4. ENTRY INTO FACILITY ENVIRONS OF INTO VITAL AREA WHICH INVOLVE A TOXIC OR FLAMMABLE GASES IN SIGNIFICANT DEGRADATION OF PLANT CONCENTRATION WHICH EXCEED THE SAFETY LIMITS OF FLAMMABILITY OR TOXICITY Detection Method: Detection Method: Detection Method:
EITHER 1 OR 2 OR 3 QB 4: EITHER I OR 2 OR 3QR 4: EITHER 1 OR 2 OR 3:
- 1. For Aircraft Crash: 1. For Aircraft Crash: 1. Aircraft crash causing damage OR_ fire in:
Observation of event. Observation of aircraft c rash into Plant a) Reactor Building; OR structures. b) Control Room; OR OR c) Auxiliary Building; OR OB d) Fuel Handling Building; OR
- 2. For Train Derailment: e) DG Building; OR Observation of event. 2. For Missile Impact: f) Intermediate Building; OR Observation of missile impacts on Plant g) SW Intake Structures.
OR structures or components.
- 3. For Onsite Explosion: .OOR 2. For Missile or Explosion Impact:
Observation of explosion or warning from Loss of functions needed for hot shutdown (see offsite. 3. For Onsite Explosion: specific Initiating Condition for this situation).
Observation of damage by explosion. OR OR OR 3. Entry of toxic or flammable gases into:
- 4. For Onsite Toxic or Flammable Gas Release: a) Control Room; OR Observation of release or warning from offsite 4. For Onsite Toxic or Flammable Gas b) Cable spreading rooms; QR Release: c) Reactor Building; OR Observation or warning from outside the d) Switchgear room; OR Plant; detection of gasses (using portable e) Control Room Evacuation Panel Rooms; Instrumentation) which exist in OR concentrations which exceed the limits of f) Emergency Diesel Generator rooms; flammabillty or toxicity. (as detected by portable instrumentation AND which renders a train of a safety related system inoperable).
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EPP-001 ATTACHMENT II PAGE 15 OF 17 REVISION 24 EMERGENCY ACTION LEVELS OTHER NOTIFICATION OF UNUSUAL EVENT ALERT I SITE AREA EMERGENCY I GENERAL EMERGENCY INITIATING CONDITION (293) INITIATING CONDITION (393) I INITIATING CONDITION (493)
OTHER PLANT CONDITIONS EXIST THAT OTHER PLANT CONDITIONS EXIST THAT OTHER PLANT CONDITIONS EXIST THAT WARRANT ACTIVATION OF EMERGENCY WARRANT ACTIVATION OF EMERGENCY WARRANT ACTIVATION OF TECHNICAL FACILITIES AND RADIATION MONITORING FACILITIES AND RECOMMENDED SUPPORT CENTER AND PLACING TEAMS AND A PRECAUTIONARY PUBLIC PROTECTIVE MEASURES FOR THE PUBLIC EMERGENCY OPERATIONS FACILITY PERSONNEL ON STANDBY WARNING Detection Method: Detection Method:
Detection Method:
As determined by IED/ED. As determined by lED/ED.
As determined by IED/ED.
INITIATING CONDITION (114)
INABILITY TO REACH REQUIRED SHUTDOWN WITHIN TECHNICAL SPECIFICATION LIMITS Detection Method:
Same as Initiating Condition.
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EPP-001 ATTACHMENT II PAGE 16 OF 17 REVISION 24 EMERGENCY ACTION LEVELS OTHER NOTIFICATION OF UNUSUAL EVENT I ALERT SITE AREA EMERGENCY I
GENERAL EMERGENCY INITIATING CONDITION (115) INITIATING CONDITION (294) INITIATING CONDITION (394)
UNPLANNED LOSS OF ALL ONSITE OR LOSS OF ALL FUNCTIONS NEEDED FOR LOSS OF FUNCTIONS NEEDED FOR PLANT OFFSITE COMMUNICATIONS CAPABILITY. PLANT COLD SHUTDOWN HOT SHUTDOWN Detection Method: Detection Method: Detection Method:
Ch EITHER I OR 2: All of the following (1 AND 2): All of the following (1 - 4):
B
- 1. Loss of all onsite communications capability 1. RI-IR system not functional in Modes 1-4, 1. Inability to establish charging pump injection, affecting the ability to perform routine operations. (Internal telephone system, Gal AND AND Tronics system and radio system.)
- 2. Inability to reject heat to the condenser and 2. Inability t6 establish Emergency Feedwater OR atmosphere. Flow,
- 2. Loss of all offsite communications capability. AND Internal telephone system, Bell lines, Fiberoptic 3. RHR System not functional (applicable to, links, radio system. (When extraordinary Modes, 1, 2, and 3 only),
means must be used to make communications.) AND 4, Inability to reject heat to the condenser and atmosphere.
INITIATING CONDITIONS (295) INITIATING CONDITION (395)
EVACUATION OF CONTROL ROOM EVACUATION OF CONTROL ROOM AND ANTICIPATED OR REQUIRED WITH CONTROL CONTROL OF SHUTDOWN SYSTEMS NOT OF SHUTDOWN SYSTEMS ESTABLISHED ESTABLISHED FROM LOCAL STATIONS IN FROM LOCAL STATIONS 15 MINUTES.
Detection Method: Detection Method:
Same as Initiating Condition. Same as Initiating Condition.
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EPP-001 ATTACHMENT II PAGE 17 OF 17 REVISION 24 EMERGENCY ACTION LEVELS OTHER NOTIFICATION OF UNUSUAL EVENT 1 ALERT SITE AREA EMERGENCY GENERAL EMERGENCY INITIATING CONDITION (296) I INITIATING CONDITION (396)
MOST OR ALL ANNUNCIATOR ALARMS LOST MOST OR ALL ANNUNCIATORS LOST AND PLANT TRANSIENT INITIATED OR IN PROGRESS Detection Method:
Detection Method:
Ch" All of the following (1 AND 2):
Greater than 75% of the MCB annunciators inoperable. 1. Greater than 75% of the MCB Annunciators inoperable, AND
- 2. Reactor Trip or Safety Injection actuation Initiated or In progress.
INITIATING CONDITION (397}
INITIATING CONDITION (297) LOSS OF RESIDUAL HEAT REMOVAL FLOW LOSS OF RESIDUAL HEAT REMOVAL FLOW FOR MORE THAN 40 MINUTES DURING FOR MORE THAN 20 MINUTES DURING HALF-PIPE OPERATIONS WITH VESSEL HALF-PIPE OPERATIONS WITH VESSEL HEAD INSTALLED AND HIGH HEAD SAFETY HEAD INSTALLED INJECTION/CHARGING UNAVAILABLE.
Detection Method: Detection Method:
All of the following (1 - 4): All of the following (1 - 5):
- 1) Both RHR Loop A FLO LO AND RHR Loop 1) Both RHR Loop A FLO LO AND RHR Loop B FLO LO annunciators in alarm, B FLO LO annunciators in alarm, AND AN1"
- 3) Core exit temperature increasing on core 3) Core exit temperature Increasing on core exit thermocouples, exit thermocouples, AND AND
- 4) Reactor Vessel Head is in place and RCS
- 4) Reactor Vessel Head Is in place and RCS loops are practically filled, loops are partially filled.
- 5) NEITHER train of Charging/S Iis available.
_ _ __ _ _I_ _ _ _ _ _ _ _ __ _ _ _ _ _ _ I -
EPP-001 ATTACHMENT III PAGE 1 OF 8 REVISION 24 CHANGE D CONSIDERATIONS FOR A SECURITY EMERGENCY Due to the wide range of possible security emergencies, it is not feasible to develop a strategy for every possible situation. Therefore, this general guidance has been provided to help in determining appropriate response.
Scripts of plant page announcements contained in this Attachment are examples only and should be modified based on the nature of the emergency.
The Security Team Leader will notify the Control Room of a security emergency. A security emergency may be classified as an Intrusion or a Site-Specific Credible Threat. See the following considerations for each of these situations. Lines to the left of the considerations are for place keeping and are optional.
Intrusion:
CAUTION Avoid moving personnel within the Protected Area without consulting the Security Team Leader as to the safety of the personnel.
- 1. Immediately direct an Operator to install the "Ultra Dogs" on the two card reader doors that lead into the Control Room area.
- 2. Make the following plant announcement:
Attention in the Plant. Attention in the Plant.
The Station is in a Security Emergency. All personnel should remain in their current location and take cover. Do not move to another location unless advised by the Control Room or Security personnel. (Repeat announcement once.)
- 3. DO NOT sound the Radiation Emergency Alarm.
- 4. Maintain contact between the Control Room and the Security Team Leader.
The Control Room may monitor the Security frequency on a hand-held radio.
- 5. Declare the appropriate Emergency Classification when the Initiating Conditions are met.
- 6. If the ERO is needed, DO NOT activate pagers using the normal method to summon the entire ERO. After working hours, contact the ERO and instruct Chg only the Duty ERO Team to report to the Primary EOF or Backup EOF.
E Provide the access route, if appropriate (see page 8). The ERO may be contacted using the Dialogics Communicator or the Call Tree as follows:
EPP-001 ATTACHMENT III PAGE 2 OF 8 REVISION 24 CHANGE D CONSIDERATIONS FOR A SECURITY EMERGENCY a) Dialogics Communicator:
- 1) Dial the Dialogics Communicator at (70) 58716 or dial toll free 1 (877) 262-5585.
- 2) The Dialogics Communicator System will answer as follows: "This is the Remote Activation Module. Please enter your scenario activation password followed by the # sign". Enter 1234567 and press the # sign.
- 3) "To start a scenario, enter the scenario-ID.followed by the # sign or press # alone for more options". To start the scenario for sending the Duty ERO Team to the Primary EOF, enter the scenario ID 100200 fQllowed by the # sign. To start the scenario for sending the Duty ERO Team to the Backup EOF, enter the scenario ID 100201 followed by the # sign. The text for the current scenarios is as follows:
Primary EOF, Scenario ID 100200:
"The V. C. Summer Nuclear Station has received a security threat. The On-duty and only the On-duty Emergency Response Team, including the Technical Support Center, Operations Support Center and the Emergency Operations Facility staffs, shall report to the Primary Emergency Operations Facility at the Nuclear Training Center. All other Emergency Response Personnel should stand-by for further instructions".
Backup EOF, Scenario ID 100201:
"The V. C. Summer Nuclear Station has received a security threat. The On-duty and only the On-duty Emergency Response Team, including the Technical Support Center, Operations Support Center and the Emergency Operations Facility staffs, shall report to the Backup Emergency Operations Facility at the Palmetto Center. All other Emergency Response Personnel should stand-by for further instructions.
EPP-001 ATTACHMENT III PAGE 3 OF 8 REVISION 24 CHANGE D CONSIDERATIONS FOR A SECURITY EMERGENCY
- 4) After you enter the scenario ID and press the # sign you will hear, "You may change the current message. Press 1 to listen to the message. Press 2 to record a new message or Press the # sign to continue". Press 1 if no supplemental information, such as access routes to the EOF, is needed. Press 2 if supplemental information needs to be provided.
- 5) If 1 is pressed, listen to the message, then press # to continue. If 2 is pressed, record the new message. Press the # sign when completed.
- 6) "To start the scenario, press 3. To return to the Main Menu press #". Press 3. Press the # sign to exit.
Or Chg
__ b) Use the Call Tree. The current Call Tree may be found in: Public FoldersNCS/Emergency Preparedness.
- 7. The lED retains Emergency Plan duties and responsibilities until it is safe to staff the TSC.
- 8. Evacuate Non-essential personnel when it is safe to do so.
- 9. During normal working hours, consider utilizing personnel responding to the EOF to assist in making notifications.
EPP-001 ATTACHMENT III PAGE 4 OF 8 REVISION 24 CHANGE D CONSIDERATIONS FOR A SECURITY EMERGENCY Site-Specific Credible Threat:
CAUTION Avoid moving personnel inside or outside the Protected Area without consulting the Security Team Leader as to the safety of the personnel.
- 1. Declare a Notification of Unusual Event (NOUE), at a minimum, based on Security Threat, EAL #111. A higher initial classification could be made based on the nature and timing of the threat and pbotential consequences.
- 2. Implement the Radiation Emergency Plan and Emergency Plan Procedures.
State and local governments should be notified as required. Do not activate the Early Warning Siren System unless directed by the government agencies, per our procedures.
- 3. TSC/OSC staffing and other personnel decisions are made based on the nature of the threat and the timing of the threat. These decisions are independent of the NOUE activities.
Evacuate plant personnel if the information about the threat indicates that time is available. The ERO Duty Team is directed to report to the EOF or Backup EOF as described below. The EOF or Backup EOF is used as a staging area for TSC and OSC personnel. The lED may contact the EOF or Chg Backup EOF to direct specific TSC and OSC personnel to come to the plant E site, as necessary. The TSC and OSC should not be fully manned until the threat is resolved.
- 4. Make one of the following plant announcements:
TAKE COVER:
Attention in the Plant. Attention in the Plant.
The Station is in a Security Emergency. All personnel should remain in their current location and take cover. Do not move to another location unless advised by the Control Room or Security personnel.
EPP-001 ATTACHMENT III PAGE 5 OF 8 REVISION 24 CHANGE D CONSIDERATIONS FOR A SECURITY EMERGENCY EVACUATE:
Attention in the Plant. Attention in the Plant.
The Station is in a Security Emergency. All non-essential and off-duty ERO personnel evacuate the site. All Duty ERO personnel report to the EOF.
(Provide the exit route, if appropriate. See Page 8)
Sound the Radiation Emergency Alarm.
Repeat the Plant Announcement.
- 5. The Duty Emergency Director should evaluate assuming emergency duties Chg from the IED without a staffed and activated TSC. The Duty Emergency E Director should only assume emergency duties from the lED if the Duty Emergency Director is located in the TSC.
- 6. Maintain contact between the Control Room and the Security Team Leader.
The Control Room may monitor the Security frequency on a hand-held radio.
- 7. Reactor and plant operational decisions should be as directed by Management.
- 8. After working hours, contact the ERO and instruct only the Duty ERO Team to report to the Primary EOF or Backup EOF. Provide the access route, if Chg appropriate (see page 8). The ERO may be contacted using the Dialogics E Communicator or the Call Tree as follows:
a) Dialogics Communicator:
- 1) Dial the Dialogics Communicator at (70) 58716 or dial toll free 1 (877) 262-5585.
- 2) The Dialogics Communicator System will answer as follows. "This is the Remote Activation Module. Please enter your scenario activation password followed by the # sign". Enter 1234567 and press the # sign.
EPP-001 ATTACHMENT III PAGE 6 OF 8 REVISION 24 CHANGE D CONSIDERATIONS FOR A SECURITY EMERGENCY
- 3) "To start a scenario, enter the scenario ID followed by the # sign or press # alone for more options". To start the scenario for sending the Duty ERO Team to the Primary EOF, enter the scenario ID 100200 followed by the # sign. To start the scenario for sending the Duty ERO Team to the Backup EOF, enter the scenario ID 100201 followed by the # sign. The text for the current scenarios is as follows:
Primary EOF, Scenario ID 100200:
"The V. C. Summer Nuclear Station has received a security threat. The On-duty and only the On-duty Emergency Response Team, including the Technical Support Center, Operations Support Center and the Emergency Operations Facility staffs, shall report to the Primary Emergency Operations Facility at the Nuclear Training Center. All other Emergency Response Personnel should stand-by for further instructions".
Backup EOF, Scenario ID 100201:
"The V. C. Summer Nuclear Station has received a security threat. The On-duty and only the On-duty Emergency Response Team, including the Technical Support Center, Operations Support Center and the Emergency Operations Facility staffs, shall report to the Backup Emergency Operations Facility at the Palmetto Center. All other Emergency Response Personnel should stand-by for further instructions.
__ 4) After you enter the scenario ID and press the # sign you will hear, "You may change the current message. Press 1 to listen to the message. Press 2 to record a new message or Press the # sign to continue". Press 1 if no supplemental instructions, such as access routes to the EOF, are needed. Press 2 if supplemental information needs to be provided.
- 5) If 1 is pressed, listen to the message, then press # to continue. If 2 is pressed, record the new message. Press the # sign when completed.
- 6) "To start the scenario, press 3. To return to the Main Menu press #". Press 3. Press the # sign to exit.
EPP-001 ATTACHMENT III PAGE 7 OF 8 REVISION 24 CHANGE D CONSIDERATIONS FOR A SECURITY EMERGENCY Or b) Use the Call Tree. The current Call Tree may be found in: Public Chg FoldersNCS/Emergency Preparedness. E
- 9. Notify Security of the intended routes and direct them to ensure gates are open, as appropriate.
EPP-O01 ATTACHMENT III PAGE 8 OF 8 REVISION 24 CHANGE D CONSIDERATIONS FOR A SECURITY EMERGENCY Access/Exit Routes:
As dictated by the events, select one of the below Basic Routes and the closest open bridge(s) to access/exit the plant and the EOF.
Three Basic Routes:
- 1. Normal Route via Highway 215.
- 2. Northern Route via the dirt road over the Fairfield Pumped Storage dam.
- 3. Southern Route via the dirt road from the south end of the plant access road to Parr.
Bridges Across the Broad River:
- 1. Pinner Bridge, Highway 213.
- 2. Highway 34 Bridge, located near the junction of Highway 34 and Highway 215, in the northern section of the 10-mile EPZ.
- 3. 1-20 Bridge, located in Columbia, west of the junction of 1-20 and Monticello Rd. (Highway 215).
SOUTH CAROLINA ELECTRIC & GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS NUCLEAR OPERATIONS COPY NO.251L EMERGENCY PLAN PROCEDURE EPP-051 EMERGENCY OPERATIONS FACILITY REVISION 6 7IAT /
-2/1i/0 /
DATE RECORD OF CHANGES CHANGE TYPE APPROVAL CANCELLATION CHANGE TYPE APPROVAL CANCELLATION iAh LETTER CHANGE 10 DATE DATE LETTER CHANGE DATE DATE INFORMATION USE Procedure May Be Performed From Memory.
User Retains Accountability For Proper Performance.
NUCLEAR OPERATIONS SAP-139 yyy*, r\ L'Ž ATTACHMENT II PAGE 1 OF 3 REVISION 20 PROCEDURE DEVELOPMENT FORM - A DATE: //-;O-O/ PROC.A EP)O-o0/ REV.#.*, CHG.,_. COMM._#
TITLE: -c. e.t,,,-c,
/*--I "
NEW PROCEDURE __ REVISION SAFETY RELATED _
CHANGE: / PERMANENT L.- QUALITY RELATED -
RESTRICTED - FROM TO NON-SAFETY RELATED 3J- h .,,d , -ha 4#4zk",.,74--A..
REASON FOR CHANGE: I/ "rVe- v,,
a..)
tr 0 v -d--- U Oo7 14"Leo &7 iiL REQUIRED EVIEWS: Check ALL selections in firt 3 columns for SAPs (except for minor chanoes) Other Reviews:
)MCHS ( )MNPS ( )MPLE ( )GMES ( )CWPS ( )ISEG ( )NOET ( )QC
( )MDE ( )MNT ( )MPSE { )GMNPO ( )DE ( )MNTS (-.4NPS (,,QR
)MHPS ()MOD&P ()MSPD ()GMNSS ()fFD ( )MQS ( )NTET ( )RC C)
)MMPR ()MPO ()SAS ()GMSPD (..4kHPS ( ) MPR ((-OS )RE (}
)MMS ()MOPS ()QA ()CHS ()ISD ( )NL&OE ()PSE ( )TU MNL&OE / ^)50.59 W-- DISCIPLINE SUPERVISOR AUTHORIZATION TO PROCESS PROPOSED-CHANGES:/
j /1-30-01 R ineSuevisor Date V. TEMPORARY APPROVAL:
QUALIFIED REVIEWER DATE QA REVIEW DATE TELECON BY TELECON BY SHIFT SUPERVISOR DATE FINAL APPROVAL REQUIRED BY: DATE VIL PICAP ACCEPTABLE?
VI. DISCIPLINE SUPERVISOR FINAL REVIEW: C. YES. NO _ _ /
NL&OE Date YES NO N. YES__ NO0_ !Date PSRC REVIEW REQUIRED? -- 'RESP. MGR.
IF YES. PRIOR TO IMPLEMENTATION? YES___ NO Vil FINAL QA REVIEW If Applicable)
I TRAINING REQUIRED? YESZ NO_ QA Concurrence Date IX. APPROVAL AUTHORITY:
IF YES. PRIOR TO IMPLEMENTATION? YES___ NO AFFECTED? ES__ NO TraPP X/CAP Completed :PTDate COMMENTS RESOLVE / I p//vIConcur*ence Date Discioli u~oeiisor Date X. PSRC REViEW A. REVIEWED BY: B. PSRC COMMENTS RESOLVED: !
/
PSRC Chairman Date Responsible Manager Date COMMENTS: YES _ NO_
PSRC Chairman Date
EPP-051 PAGE i REVISION 6 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE 1 2.0 SCOPE 1
3.0 REFERENCES
1 4.0 DEFINITIONS 2 5.0 CONDITIONS AND PREREQUISITES 2 6.0 PROCEDURE 3 7.0 RECORDS 8 8.0 REVISION
SUMMARY
8 ATTACHMENTS ATTACHMENT I EOF Staff General Guidance and Expectations ATTACHMENT I-A Offsite Emergency Coordinator ATTACHMENT I-B EOF Plant Status Advisor ATTACHMENT I-C Emergency Planning Representative ATTACHMENT I-D Technical Support Coordinator ATTACHMENT I-E General Services Coordinator ATTACHMENT I-F Media Coordinator ATTACHMENT I-G Emergency Control Officer ATTACHMENT I-H Offsite Radiological Monitoring Coordinator ATTACHMENT I-I Security Coordinator (with Medical, Fire, and Security Emergency Information)
ATTACHMENT I-J EOF Communicator ATTACHMENT I-K Field Team Driver ATTACHMENT I-L EOF Plant Status Communicator ATTACHMENT I-M EOF Major Events Logger ATTACHMENT I-N Lead Technical Briefer ATTACHMENT II Emergency Operations Facility Manning Chart
EPP-051 REVISION 6 1.0 PURPOSE 1.1 This procedure describes the functional capabilities of the V. C. Summer Nuclear Station Emergency Operations Facility (EOF).
1.2 This procedure describes the action necessary to activate the EOF and the Backup EOF.
2.0 SCOPE 2.1 Changes and revisions to this procedure must ensure compliance with the requirements of 10CFR50.54.q. A 10CFR50.59 review is not required.
3.0 REFERENCES
3.1 NUREG-0696, Functional Criteria for Emergency Response Facilities.
3.2 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.
3.3 EP-1 00, Virgil C. Summer Nuclear Station Radiation Emergency Plan.
3.4 EPP-001, Activation and Implementation of Emergency Plan.
3.5 EPP-001.1, Notification of Unusual Event.
3.6 EPP-001.2, Alert.
3.7 EPP-001.3, Site Area Emergency.
3.8 EPP-001.4, General Emergency.
3.9 EPP-002, Communication and Notification.
3.10 EPP-005, Offsite Dose Calculations.
3.11 EPP-007, Environmental Monitoring.
3.12 EPP-009, On-site Medical.
3.13 EPP-013, Fire Emergency.
3.14 EPP-014, Toxic Release.
3.15 EPP-015, Natural Emergency (Earthquake, Tomado, Hurricane).
3.16 EPP-021, Activation of the Early Warning Siren System (EWSS).
PAGE 1 OF 10
EPP-051 REVISION 6 3.17 EPP-052, Emergency Information Plan.
3.18 HPP-1003, Radiological Emergency Operations of Health Physics Personnel at the NTC.
3.19 SPP-114, Security Force Responsibilities During Emergencies.
3.20 SAP-1 131, Electronic Processing of Condition Evaluation Reports.
4.0 DEFINITIONS 4.1 Definitions 4.1.1 Backup EOF - An alternate Emergency Response Facility (ERF) to locate the Offsite Emergency Response Organization (ERO), located on the 11 th Floor of the Corporate Offices in Columbia, S. C.
4.1.2 EOF - The primary ERF to locate the Offsite ERO, located in the basement of the Nuclear Training Center.
4.1.3 ESSX Telephone -Telephone lines which are used to notify the State and Counties simultaneously and are programmed in the Bell South Telephone system.
4.1.4 Facility Activation - Minimum regulatory staffing requirements have been met and the facility is prepared to provide its support function as determined by its facility manager.
4.1.5 Key Personnel - Positions located in the EOF Command Center, listed in Section 6.1.2.
4.1.6 Minimum Staff - Personnel who must be available in an ERF for facility activation.
5.0 CONDITIONS AND PREREQUISITES 5.1 The EOF is required to be activated within about one hour of the declaration of a Site Area Emergency or General Emergency, but it may be activated at lower classifications.
5.2 The Backup EOF will be activated when the EOF must be evacuated or is not available to support offsite emergency operations.
5.3 The lED, using available information, will determine which offsite facility will be activated - either EOF or Backup EOF.
PAGE 2 OF 10
EPP-051 REVISION 6 5.4 The Offsite ERO, located in t&e EOF will provide:
A. Technical expertise in engineering.
B. Environmental monitoring.
C. Radiological assessment.
D. Logistical support such as transportation, food, communications, materials, supplies, and-other needed services.
E. Focal point for the news media, NRC, and other federal, State, and local officials that are dispatched to the near site area.
5.5 The EOF will evaluate and coordinate all V. C. Summer Nuclear Station emergency related activities and will provide infornnation and recommendations to federal, State, and local authorities responding to radiological emergencies.
5.6 All communications to the State, except for those made by EOF Communicators, should be done using 748-8010.
6.0 PROCEDURE 6.1 EOF Emergency Response Personnel 6.1.1 Attachment I provides guidance and expectations for EOF staff.
6.1.2 The following Key Personnel are located in the EOF. A checklist of specific position responsibilities is provided in the indicated attachments.
Blocks are provided beside responsibilities that are normally performed once. The blocks can be checked when the item is performed.
A. Offsite Emergency Coordinator (OEC) - Attachment I-A B. EOF Plant Status Advisor - Attachment I-B C. EP Representative - Attachment I-C D. Technical Support Coordinator - Attachment I-D E. General Services Coordinator - Attachment I-E F. Media Coordinator - Attachment I-F G. Emergency Control Officer (ECO) - Attachment I-G H. Offsite Radiological Monitoring Coordinator (ORMC)
Attachment I-H PAGE 3 OF 10
EPP-051 REVISION 6
- 1. Security Coordinator - Attachment I-I J. EOF Communicators - Attachment I-J 6.1.3 Key Personnel in the EOF shall maintain a log of their activities to include projects, decisions and their basis, etc.
6.1.4 When a member of the Offsite ERO in the Command Center must leave the facility, he/she shall designate and brief an interim substitute before leaving and receive a briefing-upon returning.
6.1.5 The OEC communicates with the ED by a dedicated phone line to the TSC.
6.1.6 When the OEC is fully apprised of the emergency situation, minimum staff is available and facilities are ready, the OEC shall declare that the EOF is activated and inform the TSC.
6.1.7 The OEC shall routinely brief the EOF organization on the status of emergency support operations.
6.1.8 Requests for manpower, equipment, or material are made by the ED or his designee to the OEC at the EOF. The OEC confers with the appropriate members of the Offsite ERO in order to fulfill the request.
6.1.9 The NRC Site Team will be located in the EOF at a Site Area Emergency or General Emergency classification to provide assistance and enhance information exchange between SCE&G and federal agencies.
6.2 Communications Center 6.2.1 The Communications Center, used by the EOF Communicators, is located in close proximity to the Command Center.
6.2.2 The Communications Center contains an SCE&G telephone extension, ESSX telephone, radio communications, and facsimile machine.
PAGE 4 OF 10
EPP-051 REVISION 6 6.2.3 After activation of the EOF, the EOF Communicator, with the approval and direction of the OEC, provides plant status updates, as required, to offsite authorities. The EOF Communicator will obtain the Emergency Notification Form from the EP Representative. If using the Emergency Information System (EIS), the Emergency Preparedness Representative will fax the approved Emergency Notification Form to the State and local governments. The EOF Communicators will verify receipt via a telephone call to each location in accordance with EPP-002. If not using EIS, the EOF Communicators will read the Emergency Notification Form to the State and counties and-then Fax the form to them.
6.2.4 The EOF Communicator logs all communications to offsite agencies involving the EOF. Further descriptions of EOF communications are included in EPP-002, Communication and Notification, and Attachment I-J ofthis procedure.
6.3 Technical Support 6.3.1 The Technical Support Coordinator shall:
A. Provide input to the General Services Coordinator in regard to facilities needed in the EOF to support technical support activities.
B. Direct, coordinate, and approve engineering and design activities.
C. Ensure Engineering Design and Design Review activities are controlled in support of short term mitigation requests.
Communicate on going actions to the ERO.
D. Define, initiate, and coordinate plans to support long term recovery efforts.
6.3.2 The Technical Support Staff shall:
A. Analyze plant problems, determine alternatives, and design and coordinate the installation of short-term modifications as requested by the TSC Technical Support Supervisor and the Technical Support Coordinator.
B. Analyze system operations problems, determine alternatives, and develop emergency procedures.
C. Assist the TSC in analyzing conditions and provide guidance to station personnel on protection of the reactor core.
PAGE 5 OF 10
EPP-051 REVISION 6 6.4 General Services 6.4.1 The General Services Area provides space for personnel activated and supervised by the General Services Coordinator.
6.4.2 General Services personnel arrange for, or provide, the administrative, logistic, communications, and personnel support for emergency operations.
6.4.3 Telephones and a telecopief-are available to the General Services personnel for use during an emergency.
6.5 Security Area 6.5.1 The Security Coordinator is normally located in EOF Room 142. When local government representatives respond to the EOF, the Security Coordinator will relocate to the Command Center.
6.5.2 Security personnel activated and supervised by the Security Coordinator will provide access control and other security related services at the EOF.
6.6 Media Area 6.6.1 Personnel supervised by the Media Coordinator are provided with working space in the EOF.
S6.6.2 Telephones and a telecopier are available for use in the preparation of coordinated and accurate information for the News Media.
6.6.3 Operations in the EOF and News Media Area are described in EPP-052, Emergency Information Plan.
6.7 Offsite Radiological Monitoring Area 6.7.1 The Offsite Radiological Monitoring Coordinator's staff operates from both the EOF and Environmental Laboratory at the NTC.
6.7.2 Offsite Radiological Monitoring personnel acquire data reflecting radiological conditions outside the Protected Area.
6.7.3 Communications will be established with onsite radiological assessment personnel to obtain offsite radioactive release information.
6.7.4 Telephones and radio equipment are available for communicating with both onsite and offsite radiological monitoring activities.
PAGE 6 OF 10
EPP-051 REVISION 6 6.7.5 Dose assessment equipment and supplies are available to determine and predict offsite dose projections to the general public.
6.7.6 Offsite Radiological Monitoring personnel communicate and coordinate with S. C. Department of Health and Environmental Control (DHEC) throughout the emergency on monitoring activities.
6.7.7 Implement the guidelines specified in HPP-1 003 to set up and operate the Dose Assessment Area of the EOF.
6.8 Activation of the EOF:
6.8.1 The OEC is notified of an emergency by the Shift Communicator in accordance with EPP-002, Communication and Notification.
NOTE The EOF is not normally activated during an NUE.
6.8.2 Upon declaration of a Notification of Unusual Event (NUE):
A. The OEC shall notify the ECO.
B. If deemed necessary by the OEC or ECO, or requested by the lED or ED, all portions of the Offsite ERO may be activated.
C. When notified, the Media Coordinator may implement the applicable sections of EPP-052, Emergency Information Plan.
6.8.3 Upon declaration of an Alert, Site Area Emergency, or General Emergency:
A. When activated, the Offsite ERO shall respond to the appropriate facility.
B. The OEC shall notify the ECO of the emergency condition.
C. The Media Coordinator will implement EPP-052, Emergency Information Plan.
D. The ORMC, Security Coordinator, General Services Coordinator, and Technical Support Coordinator will ensure notification of other support personnel to staff the EOF.
E. Attachment II, Emergency Operations Facility Manning Chart, is used to record Minimum and Essential manning in the EOF.
PAGE 7 OF 10
EPP-051 REVISION 6 6.9 Evacuation of the EOF:
NOTE If the airborne radiation levels exceed 10CFR20, Appendix B, Table 1 limits, or the general area radiation levels exceed 100 mr/hr in the EOF, the EOF will be evacuated to the Backup EOF or a location designated by the OEC.
6.9.1 If the EOF must be evacuated and the Backup EOF activated, the OEC shall:
A. Dispatch Communicator(s) to set up the Backup EOF immediately.
B. Notify the ED and determine time of turnover of operations for emergency during the transition to the-Backup EOF.
C. Notify the Media Coordinator to inform him of the activation of the Backup EOF.
D. Notify Palmetto Center Security of intent to activate the Backup EOF.
E. Notify the State and Local Governments and inform them of the interim transfer of responsibility for emergency operations to the TSC.
F. Announce to the EOF the evacuation and the route to be taken to the Backup EOF.
G. Ensure the Communicators turn communications over to the TSC during the transition to the Backup EOF.
H. Ensure Offsite Radiological Monitoring and Dose Assessment activities are transferred to the TSC. Dispatch personnel from the EOF to the TSC to perform this function.
7.0 RECORDS 7.1 Forward all written material or copies of written material generated because of an emergency to the Emergency Services Unit (ESU). The ESU will insure appropriate written material is included in the applicable Condition Evaluation Report.
8.0 REVISION
SUMMARY
8.1 Incorporated Changes A and B.
PAGE 8 OF 10
EPP-051 REVISION 6 8.2 Added section 2.0 Scope and renumbered the remainder of the text.
8.3 Section 5.3, Technical Support function, and Attachment I-D, Technical Support Coordinator item 4: Reworded to better reflect responsibilities of this function.
8.4 Added Section 5.8.3.E and Attachment II, Emergency Operations Facility Manning Chart to provide an improved method to ensure Minimum and Essential manning is met in the EOF.
8.5 Attachment I, EOF Staff General Guidance and Expectations: Changed Item 1 from EIS login procedure to completing the EOF Manning Chart to provide an improved method to ensure Minimum and Essential manning is met in the EOF.
8.6 Attachment I, EOF Staff General Guidance and Expectations: Added step to item 3, EIS login procedure, todescribe action if EIS terminal is a PC. Some EIS terminals have been replaced with PCs.
8.7 Attachment 1, EOF Staff General Guidance and Expectations Added guidance in step 5 for receiving emergency messages during briefings. Reason for Change is due to Training feedback.
8.8 Attachment I-A, Offsite Emergency Coordinator: Added a note to remind the OEC to include personnel outside the EOF Command Center in OEC Briefings, as necessary. Reason for the change is PIP C-01-0458 CA #11.
8.9 Attachment I-A, Offsite Emergency Coordinator Deleted previous step 1 .b to Notify the Emergency Control Officer. The Reason for Change is the Step is unnecessary.
8.10 Attachment I-A, Offsite Emergency Coordinator: Revised item 2.a to include EPP-009, 013, 014, 015 to remind OECs to check if these procedures are in use prior to EOF Activation.
8.11 Attachment I-A, Offsite Emergency Coordinator: Revised item 4.a to delete the last sentence concerning not maintaining Status Boards if EIS is operating because EOF Status Boards are more effective than EIS in keeping the EOF staff and the NRC up to date.
8.12 Attachment I-A, Offsite Emergency Coordinator: Added the protocol for validating offsite dose assessments to item 4.f. See Drill action item PIP C-00 0430, CA #5.
8.13 Attachment I-C, Emergency Preparedness Representative: Changed item 1.b to Emergency Operations Facility Manning Chart to provide an improved method to ensure Minimum and Essential manning is met in the EOF.
PAGE 9 OF 10
EPP-051 REVISION 6 8.14 Attachment I-C, Emergency Preparedness Representative: Revised item 1 .d to delete the last sentence concerning not maintaining Status Boards if EIS is operating because EOF Status Boards are more effective than EIS in keeping the EOF staff and the NRC up to date.
8.15 Attachment I-C, Emergency Preparedness Representative: Revised item 2.b to delete the last sentence concerning not giving approved Emergency Notification Forms (ENF) to the EOF Lead Communicator if EIS is operating. This action must take place whether the ENF is-developed on EIS or developed manually.
8.16 Attachment I-H, Offsite Rad. Monitoring Coordinator: Added the protocol for validating offsite dose assessments to item 2.e. This is due to a Drill action item.
8.17 Attachment I-H, Offsite Rad. Monitoring Coordinator. Revised item 2.f to describe the process to access RMS and Met data on a PC. HP EIS workstations have been replaced with PCs.
8.18 Attachment I-I, Security Coordinator: Added step 1.d to monitor the completion of the EOF Manning Chart. This change is due to a Drill action item.
8.19 Attachment I-K, Field Team Driver, Attachment I-L, EOF Plant Status Communicator, Attachment I-M, EOF Major Events Logger, Attachment I-N, Lead Technical Briefer: Deleted Item 1 .c on each attachment, step to log into EIS since EIS is no longer used to log people into the EOF.
8.20 Attachment I-M, EOF Major Events Logger: Added new step 1 .c to synchronize clocks with the plant computer. This change is due to a Drill action item.
8.21 Added Attachment II, Emergency Operations Facility Manning Chart to provide an improved method to ensure Minimum and Essential manning is met in the EOF.
PAGE 10 OF 10
EPP-051 ATTACHMENT I PAGE 1 OF 1 REVISION 6 EOF STAFF GENERAL GUIDANCE AND EXPECTATIONS
- 1. Print your name on the EOF Manning Chart next to your position.
- 2. Ensure all necessary equipment for your position is in place.
"* Test telephone.
"* Adequate supplies are available (pens, pencils, paper, etc.).
"* Procedures are available.
"* Position Checklist is available.
"* Adequate staffing in your functional area.
- 3. Upon arrival, get update on the plant status. Possible sources of information:
"* ED Briefing
"* OEC Briefing
"* Plant Computer
"* Dose Assessment Computer
"* Status Boards
"* Counterpart in TSC
"* EIS To log into EIS if your terminal is a PC, perform the following:
At the Logon Information Window, type EIS for User Name, type EIS for Password, and select the EIS Domain. Select OK. Then using the mouse, double click on the EIS001 icon.
- 4. Maintain a log of all major actions, projects, decisions and their bases, etc. throughout the emergency.
- 5. Personnel are to be attentive during Emergency Director and Offsite Emergency Coordinator Briefings. If your phone rings during a Briefing, answer the phone and tell the caller you are in a briefing and ask the caller if he/she has a Critical Emergency Message. Critical Emergency Messages are messages informing you of:
"* Loss of Safety Systems or Components
"* Offsite Radiological Releases
"* Security Intrusion
"* Medical Emergency
"* Fire Emergency If the message is not critical, tell the caller to call back or write down the number and call back when the briefing is completed. Do not leave the phone off the hook because this prevents others from calling if they should have critical information.
If you decide the message is a Critical Emergency Message that warrants interrupting the Briefing, stand up and raise your hand to get the attention of the Offsite Emergency Coordinator and say you have a Critical Emergency Message.
The Off site Emergency Coordinator tells the listeners to standby. The Offsite Emergency Coordinator evaluates the new information and returns to or reschedules the briefing.
- 6. If you leave the Command Center for any reason, ensure someone is briefed as a designated alternate. Receive an update upon your return.
EPP-051 ATTACHMENT I -A PAGE 1 OF 4 REVISION 6 OFFSITE EMERGENCY COORDINATOR Major Tasks Specific Actions 4-
- 1. Initial Notification from Plant a. Discuss:
- 1. Emergency Classification and Facility Activation.
- 2. Release in Progress.
- 3. Notification Status.
- 4. Protective Action Recommendations (PARs).
should be activated about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1. Emergency classification:
after Site Area Emergency or Initiating Conditions.
General Emergency is declared) Detection Method.
E-12. Plant Status. .
E] 3. Releases: Yes/No TDEFP Running: Yes/No PORVs, Safeties: Yes/No Normal Plant releases: Yes/No Other. Yes/No El 4. Priorities:
"* TSC
"= EOF El 5. Equipment status.
El 6. Injuries (EPP-009): Yes/No Victim(s)_
E] 7. Fire (EPP-01 3) Yes/No E] 8. Toxic Release (EPP-01 4) Yes/No
[] 9. Natural Emergency (EPP-015) Yes/No El10. Notification status.
E]l 1.Protective Action Recommendations.
Ell 2. Early Warning Siren System Recommendation. (SAE/GE)
El 3. Site Evacuation/Accountability. (SAE/GE) 1El14. Offsite Emergency Services requested (ambulance, fire department, law enforcement). Yes/No
- b. Ensure minimum staffing as follows:
El Offsite Emergency Coordinator (1)
El Offsite Dose Assessment Person (1)
El Offsite Rad Monitoring Personnel (4)
El c. Verify habitability of EOF and News Media Area.
El d. Coordinate time of EOF activation.
El e. Ensure EOF Communicators coordinate assumption of communications.
El f. Ensure the Media Coordinator has initiated the activation of the News Media Area.
E] g. Inform the ECO of EOF activation time.
EPP-051 ATTACHMENT I -A PAGE 2 OF 4 REVISION 6 OFFSITE EMERGENCY COORDINATOR Major Task Specific Actions Note Ensure personnel outside the EOF Command Center are included in OEC Briefings, as necessary, or are otherwise informend-of the content of the briefings.
1 The EOF is activated as of hrs. My name is I am the OEC. The ECO is. The ED in the TSC is
- 2. Remind staff:
0 To maintain log of activities.
a If they leave Command Center, someone is to be briefed and assume their duties. Receive an update upon their return.
- 3. Plant priorities.
- 4. EOF priorities.
Fl b. Direct the EOF Communicators to notify the offsite agencies of the EOF activation.
- 4. Once EOF is activated El a. Initiate status boards. Ensure status boards are maintained current.
COl E b. Provide periodic briefings of the EOF, to include the E--
following information: (unless already covered in the ED briefing).
"*EAL
"*Priorities
"*Plant Status
"*Releases
"*PARs
"*Offsite Interface El c. Ensure periodic habitability check. If Zone C-1 must be evacuated or sheltered, ensure the News Media Area is considered.
- d. Continually review priorities.
- f. Review/Approve Emergency Notification Forms.
EPP-051 ATTACHMENT I -A PAGE 3 OF 4 REVISION 6 OFFSITE EMERGENCY COORDINATOR Major Task Specific Actions
- g. The following protocol should be used to ensure dose assessment results are adequately reviewed prior to approving Forms and informing the State and local government officials:
- 1. Evaluation of dose projections should not delay the Emergency Notification Process. It is acceptable to communicate dose data on follow-up Notifications. Due to time constraints for adequate assessment of dose projections and development of the General Emergency Notification, it is preferred to send out the Initial General Emergency Notification with minimum PAR and send a follow-up message immediately after proper assessment of dose data. If Tradiation monitor readings provide sufficient data for assessment, it is not appropriate to wait for field monitoring data to become available to confirm the need to expand PARs.
- 2. The EOF has a maximum of 15 minutes from the time dose data is available to evaluate the dose data and determine PARs.
- 3. The ORMC will post the dose projection results in mRem with no scientific notation for the EOF staff to evaluate.
- 4. The ORMC will explain the results, including the inputs and basis.
- 5. The EOF staff will discuss and validate the results. This should include a determination and validation of the potential release pathways based on events in progress and a determination and validation of the release rate based on changes to plant parameter data.
- 6. The results are approved or rejected by the OEC.
- h. Approve press releases in ECO's absence.
E i. Dispatch County Liaison personnel to the County EOCs, as necessary.
L j. EOF log is maintained by the Tech Support Coordinator on EIS or manually.
E k. EOF manning completed.
I. Fairfield Pumped Storage Facility evacuation (SAE/GE).
- m. Authorize Radiation Dose limit extensions, as necessary.
EPP-051 ATTACHMENT I -A PAGE 4 OF 4 REVISION 6 OFFSITE EMERGENCY COORDINATOR
- n. Approval of revisions of plant procedures affecting offsite activities only.
El a. Dispatch Communicator(s) to set up the Backup EOF
El b. Notqjýy the ED of evacuation.
El c. Notify the Media Coordinator of Backup EOF activation.
El d. Announce to the EOF the evacuation and the route to be taken to the Backup EOF.
El e. Notify the State and local governments.
El f. Ensure the Communicators turn communications over to the TSC (interim).
El g. Ensure Radiological Monitoring and Dose Assessment activities are transferred to the TSC. Dispatch personnel from the EOF to the TSC to perform this function.
EPP-051 ATTACHMENT I-B PAGE 1 OF 1 REVISION 6 EOF PLANT STATUS ADVISOR Major Tasks Specific Actions
- 1. EAL Changes a. Continually monitor plant conditions and compare with EAL table in EPP-001 for change in EAL in support of TSC.
- 2. Technical Input a. Provide technical input to the OEC and/or EOF personnel on plant status. --
EPP-051 ATTACHMENT I-C PAGE 1 OF 2 REVISION 6 EMERGENCY PLANNING REPRESENTATIVE Major Tasks Specific Actions
- b. Ensure the Emergency Operations Facility Manning Chart, Attachment Il is completed.
E] c. Ensure equipment and supplies are available.
[] d. Ensure status boards are being initiated and maintained.
- e. Ensure ED Log is.being received from the TSC and distributed in the EOF. If usiig-EIS, this step is not necessary.
C02-- 2. Notification Forms a. Complete Emergency Notification Forms at the required frequencies and submit to the OEC for review and approval.
- b. Give approved Emergency Notification Forms to the Lead Communicator for transmittal to State and counties.
- 3. Emergency Plan and Procedures a. Provide guidance on implementation of EPPs.
- 4. EAL changes. a. Ensure Plant Status Advisor and OEC are reviewing plant EPP-001 conditions for EAL change.
EPP-001.1 - EPP-001.4
- b. Ensure notifications are made if EAL changes.
- b. Provide input on PARs.
- c. Communicate with the State and local governments on PARs, as necessary.
EPP-051 ATTACHMENT I-C PAGE 2 OF 2 REVISION 6 EMERGENCY PLANNING REPRESENTATIVE Major Tasks Specific Actions
- 6. EWSS Activation a. Ensure authorization for siren activation is requested at Site Area EPP-021 Emergency and General Emergency.
- b. Communicate with State and local governments on siren aetivation, as necessary.
- c. Coordinate with the TSC on the siren-activation, as necessary.
- 7. State and Local Communications a. Communicate with State and local government EOCs as necessary. -.
- 8. NRC Site Team Interface a. Upon arrival and after initial briefing by the ECO, introduce NRC Site Team members to their counterparts and direct them to their work locations.
EPP-051 ATTACHMENT I-D PAGE 1 OF 1 REVISION 6 TECHNICAL SUPPORT COORDINATOR Major Tasks Specific Actions
- 1. Staff a. Essential staffing for Technical Support personnel:
E] Assistant Technical Support Coordinator (1)
[I Systems Engineer (1)
El Plant Status Communicator (1)
LI Major Events Data Logger (1)
- 2. NSSS Supplier & Ml a. Establish communications with Westinghouse and Architect/Engineer Architect/Engineer as necessary.
- 1. Access the EOF Log from the Master Menu or the Main Menu.
- 2. Press PF1 to activate the Function Menu.
- 3. Using the arrow keys select the NEW EVENT option.
Press RETURN.
- 4. Enter the text of the new event in the displayed window.
Note that there is no "Word Wrap" function.
- 5. Press PF1 to activate the Function Menu of the New Event window and select SAVE. Press RETURN.
- 6. Verify the Declaration Date and Time is correct or overstrike to input the correct date and time.
Press RETURN.
- 4. Technical Support Activities a. Direct, coordinate and approve engineering and design activities.
- b. Ensure Engineering Design and Design Review activities are controlled in support of short term mitigation requests.
Communicate ongoing actions to the ERO.
- c. Analyze plant problems, determine alternatives, and design and coordinate the installation of short-term modifications as requested by the TSC Technical Support Supervisor.
- d. Define, initiate, and coordinate plans to support long term
'recovery efforts.
- e. Assist the TSC in analyzing conditions and provide guidance to station personnel on protection of the reactor core.
- f. Call in additional Technical Support personnel, as needed.
EPP-051 ATTACHMENT I-E PAGE 1 OF 1 REVISION 6 GENERAL SERVICES COORDINATOR Major Tasks Specific Actions
- 1. General Services Staff M a. Ensure adequate General Services personnel are located in work area.
- a. Provide for general office support to include word processing,
- 2. Support Services and Supplies reproduction, etc., when required.
- b. Provide additional telephones, when required.
- c. Function as purchasing agent with responsibility for contract negotiation/adminiLtration and material control.
- a. Administer the petty cash fund and expense account.
- e. Handle payroll matters, if required.
- f. Provide for food deliveries, for operation of additional meal support, and for trash disposal.
- g. Arrange for motel, airline, and office space, if required.
- h. Coordinate the manpower request needs of the recovery operation.
- i. Provide vehicles and transportation for recovery operations.
EPP-051 ATTACHMENT I-F PAGE 1 OF 1 REVISION 6 MEDIA COORDINATOR Major Tasks Specific Actions I
- 1. Initial notification from Plant ria. Discuss plant conditions for initial media statement.
- b. Implement EPP-052, Emergency Information Plan, for Alert, Site Area,.and General Emergency.
- 2. Press releases and conferences a. Prepare and issue official press releases as approved by the ECO or his designated alternate.
- b. Assist the ECO in preparing for Press Briefings.
EPP-051 ATTACHMENT I-G PAGE 1 OF 1 REVISION 6 EMERGENCY CONTROL OFFICER Major Tasks Specific Actions
- 1. Manage SCE&G's overall response a. Verify through the OEC:
to emergencies 1. Emergency Response Facilities are activated and staffed.
- 2. Notifications are being made to offsite authorities.
- 3. PARs given to State and local governments.
- 4. Status of the Plant and Releases.
- 2. Ensure effective liaison with a. Verify Technical Support Coordinator has established Westinghouse, Architect/Engineer, communication with Westinghouse, Architect/Engineer, other services and equipment and other contractors.
contractors
- 3. Activate additional Corporate a. Approve purchase requisitions, as required.
resources, as required
- b. Authorize any additional Corporate resources, as required.
- 4. Approve press releases a. Approve press releases to be released by the Media Coordinator.
- 5. Company Spokesperson a. Speak for SCE&G while the emergency exists.
- b. Ensure factual information is given to the public in consistent, accurate, understandable manner.
- c. Explain plant conditions and Company actions in non-technical language during news conferences.
- d. Put dose estimates from radioactive releases into perspective by equating to exposure from common material.
- e. Reveal names of injured personnel only after next of kin has been notified.
- 6. Communications with State Officials a. Communicate with State Officials on issues when required.
- b. Discuss the Protective Action Recommendations with State Officials when required.
- c. When a Site Area Emergency or a General Emergency is CHG declared, call the SEOC to discuss the circumstances for the A declaration with the State Operations Officer or his designee.
- 7. Recovery Organization a. Determine if a Recovery Organization is required.
- b. Determine the scope and functions of the Recovery Organization.
- 8. NRC incidence Response Team a. Brief NRC Site Team upon arrival.
EPP-051 ATTACHMENT I-H PAGE 1 OF 2 REVISION 6 OFFSITE RADIOLOGICAL MONITORING COORDINATOR Major Tasks Specific Actions
- 1. EOF Activation a. Ensure minimum staffing as follows F Dose Assessment Person F1 4 - Offsite Rad Monitoring Persons (may include 2 Field Team Drivers) jj b. Ensure EOF and News Media Area habitability and advise OEC as necessary.
- 2. Radiological Monitoring Task a. Conduct radiation surveys and sampling of the environment in areas outside of the Protected Area.
- b. Coordinate offsite surveys with local, State, and Federal survey teams.
- c. Retrieve the TLDs located offsite and determine cumulative population doses.
- d. Report data to the Radiological Assessment Supervisor in TSC and to the OEC.
- e. Provide technical assistance in the evaluation of offsite and onsite radiological conditions including dose projections.
The following protocol should be used to ensure dose assessment results are adequately reviewed prior to informing the State and local government officials:
- 1. The Offsite Rad. Monitoring Coordinator will post the dose projection results in mRem with no scientific notation.
- 2. The Offsite Rad. Monitoring Coordinator will explain the results to the EOF Staff, including the inputs and basis.
- 3. The EOF staff will discuss and validate the results.
This should include a determination and validation of the potential release pathways based on events in progress and determination and validation of the release rate based on changes to plant parameter data.
- 4. The results are approved or rejected by the OEC.
- f. Access plant RMS and Meteorological data as follows:
- 1) Using the mouse, double click on the PID icon.
- 2) Using the mouse, highlight the desired selection on the VCS Plant PID menu and click Execute. Note the selections on the menu are listed alphabetically by TOC Name.
- For Met Data, use EARMET.
- For RMS Data, use RMLEMG.
EPP-051 ATTACHMENT I-H PAGE 2 OF 2 REVISION 6 OFFSITE RADIOLOGICAL MONITORING COORDINATOR Major Tasks Specific Actions
- 3. Input on Protective Action i a. Provide input to the OEC on Protective Action Recommendations Recommendations, when required.
- 4. Ongoing EOF Functions a. Periodically conduct radiological surveillances to assure habitability of the EOF and News Media Areas and advise the OEC, as necessary.
- b. Coordinate radiological assistance with State and Federal agencies as well as with private contractors.
- c. Arrange support for.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day offsite radiation monitoring supportwhen required.
- d. Authorize KI administration to emergency response personnel, as necessary.
- 5. Use of the Backup EOF (either a. The ORMC reports to the Backup EOF. The EOF Dose initially or following evacuation of Assessor and the Field Team Dispatcher report to the Rad the Primary EOF) Assessment Supervisor in the TSC. EOF Count Room and habitability personnel report to the OSC.
EPP-051 ATTACHMENT I-I PAGE 1 OF 4 REVISION 6 SECURITY COORDINATOR Major Tasks Specific Actions i
[] b. Establish security and access control at the EOF.
- c. Ensure EOF emergency response personnel meet Fitness For Duty requirements.
El d. Monitor the completion of Attachment 1I,Emergency Operations Facility Manning Chart, as follows:
- 1. Periodically monitor as personnel fill in their names.
2.Obtain the names of State and Local Government Liaison personnel from the EP Representative.
3.Inform the OEC when Minimum Staffing is met.
- 4. Inform the OEC when Essential Staffing is met.
5.Provide a copy of the completed Attachment II to the OEC and post the original.
- 2. EOF Operations a. Interface with Local Law Enforcement, when required.
- c. Provide information to EOF staff relating to screening access requirements. Coordinate with offsite organizations, Station Security and Training, as required, to expedite prompt Station access for contractors, vendors, etc.
- d. Obtain information on medical, fire, and security emergencies from Security Supervisor and provide to EOF staff (see pages 2 through 4 of this attachment).
EPP-051 ATTACHMENT I-I PAGE 2 OF 4 REVISION 6 MEDICAL EMERGENCY INFORMATION
- 1. Name of Victim:
(Not to be divulged until next of kin have been POSITIVELY notified.)
- 2. Position/Job
Title:
- 3. Age, Sex:
- 4. What was injured person doing at the time of the accident?
- 5. Medical Condition? Where taken and by whom?
- 6. If a fatality, what was the cause of death? (fall, heat, explosion, etc.)
- 7. Was radiation/contamination involved?
"-8. Have accidents such as this previously occurred?
".9. Why/How did the accident take place?
NOTES:
- The Security Coordinator is not responsible for obtaining this information. The ECO should obtain this information from any available source.
None of the above information is mandatory.
EPP-051 ATTACHMENT I-I PAGE 3 OF 4 REVISION 6 FIRE EMERGENCY INFORMATION
- 1. What type of fire? How was it started?
- 2. What was the extent of the damage?
- 3. Were there any injuries? (Refer to Medical) YES or NO
- 4. What time did the fire start? Has it been extinguished?
- 5. Was offsite assistance required? Who?
- 6. Will the fire complicate recovery from the emergency?
NOTES:
- The Security Coordinator is not responsible for obtaining this information. The ECO should obtain this information from any available source.
None of the above information is mandatory.
EPP-051 ATTACHMENT I-I PAGE 4 OF 4 REVISION 6 SECURITY EMERGENCY INFORMATION
- 1. How many perpetrators were there?
- 2. What was the age/sex of perpetrators?
- 3. Have perpetrators been captured?
.4. How did the perpetrators breech security? (How did they get in?)
ý5. Was damage sustained? Where? How?
- 6. Were explosives involved?
- 7. Were injuries sustained by perpetrators/plant personnel? (See Medical for response.) YES or NO
- 8. Were shots fired? By whom? How many? What was hit?
- 9. Refuse to answer questions specific to our Security Plan such as:
What type of Security Force do we have? (i.e., How armed? How many?)
How did Security fail? What will be done to ensure it doesn't fail again?
NOTES:
- Do not divulge this information if Safeguards information is involved.
None of the above information is mandatory.
EPP-051 ATTACHMENT I-J PAGE 1 OF 2 REVISION 6 EOF COMMUNICATORS Major Tasks Specific Actions i
EIb. Obtain a key from Security personnel at the NTC and unlock rooms and cabinets.
If reporting to the Backup EOF, retrieve the supply carts from the Communicator and Storage Room adjacent to Room 1109 and follow the instructions on the carts to setup the Backup EOF.
Dic. Set up the EOF or BEck Up EOF..
I--d. Notify the OEC when the EOF is set-up.
- 2. Communications ri a. Coordinate with TSC Communicators on assuming responsibility for offsite notification and inform the OEC when the responsibility has been assumed.
- b. Ensure all Initial Notifications have been completed and faxed to the appropriate offsite authority in accordance with EPP-002.
NOTE For all Emergency Notification Forms the Communicators should make 8 copies and distribute as follows:
- a. ECO
- b. OEC CHG
- c. EP Representative A
- d. 5 copies on the back table for State and Federal Government Representatives use
- c. If the Emergency Classification is upgraded, ensure initial notifications are made to the State and Counties within 15 minutes of declaration.
- d. Ensure follow-up notifications are completed at least hourly and as conditions change and are faxed to the appropriate authorities.
Li e. Ensure Fairfield Pumped Storage is notified of the emergency in an Alert condition and/or notified to evacuate in a Site Area Emergency or a General Emergency.
- f. Ensure OEC is informed as notifications are completed.
El g. Ensure Early Warning Siren Authorization is requested per EPP 021. Notify TSC Communicators that EWSS Activation Authorization has been requested and fax EPP-021, Attachment I,to the TSC.
EPP-051 ATTACHMENT I-J PAGE 2 OF 2 REVISION 6 EOF COMMUNICATORS Major Tasks Specific Actions i
ED i. Ensure INPO is notified within one working day.
E] j. Ensure the American Nuclear Insurer's Notification is completed in accordance with EPP-002.
El k. -Ensure termination messages are made to all authorities upon termination of an event.
3- EOF turnover E] a. When the EOF is manned and activated, assume all notifications per EPP-002 (excluding requests for emergency services, NRC commdnication, and receiving authorization to activate EWSS).
El b. Ensure a thorough turnover briefing is performed prior to the EOF assuming responsibilities for notifications.
- c. Ensure the TSC Communicator transmits and reviews updated information to and from the EOF as applicable.
El d. Ensure the transfer of responsibility is documented.
- e. Ensure that all completed pages of the ED Log Book are faxed to the EOF. If using EIS, this step is not necessary.
EPP-051 ATTACHMENT I-K PAGE 1 OF 1 t REVISION 6 FIELD TEAM DRIVER Major Tasks Specific Actions
- 1. Manning a. When notified to report, proceed to the EOF. Field team drivers also report to the EOF if the BEOF is used.
- b. Notify the Offsite Rad Monitoring Coordinator or Field Team Dispatcher that you have arrived.
- c. Obtain dosimetry.
- 2. Duties a. Follow directions of.the environmental monitoring personnel for emergency kit and vehicle checkout and monitoring activities.
- b. Remind the environmental monitoring person on your team of the radio check required every 15 minutes.
- c. Periodically check dose and report results to rider. Team dispatcher will inform you when/if you reach your dose limits and must be pulled from field operations.
- d. Put vehicle ventilation on recirculation when traversing plume to reduce dose.
- e. Extra Field Team Drivers may be called upon to be Sample Runners between the EOF and the Field Teams.
EPP-051 ATTACHMENT I-L PAGE 1 OF 1 REVISION 6 EOF PLANT STATUS COMMUNICATOR Major Tasks Specific Actions
+
- b. Notify the Technical Support Coordinator that you have arrived.
- a. Establish communications with the Control Room and the
- 2. Duties TSC Plant Status Communicators as follows:
- 1. 'All-phones on hook.
- 2. TSC presses talk button on handset.
- 3. All lift handset.
- 4. If any parties drop off, call must be reinitiated.
- b. Keep the EOF staff informed of changing plant conditions.
- c. Use judgment to convey critical plant information to the EOF staff in a timely manner with the appropriate degree of emphasis and urgency. Interrupt the OEC, if appropriate.
EPP-051 ATTACHMENT I-M PAGE 1 OF 1 REVISION 6 EOF MAJOR EVENTS LOGGER Major Tasks Specific Actions I 1. Manning a. When notified to report, proceed to the EOF or Backup EOF as required.
- b. Notify-the Technical Support Coordinator that you have arrived.
- c. Synchronize the EOF digital clock with the Plant Computer.
- 2. Duties a. Sequentially log major events on the Status Board.
- b. Sources of information:
"* ED and OEC Briefings.
"* Listening to EOF staff.
"* EIS.
"* Directions from EOF staff to log specific items.
EPP-051 ATTACHMENT I-N PAGE 1 OF 1 REVISION 6 LEAD TECHNICAL BRIEFER Major Tasks Specific Actions
- b. Notify the Media Coordinator that you have arrived.
- 2. Duties a. Assist the ECO, Media Coordinator, and JIC personnel in preparing Press Releases and Press Briefings by providing an understanding of plant systems and operations. Strive to put technical information in terms the public can understand.
- b. Attend all Press Briefings with the ECO. CHG I A
- c. Do not talk to representatives of the Media unless directed to by the JIC Coordinator or the Media Coordinator.
- d. If approached by the Media directly, politely but firmly decline to answer questions and state that all information is being released through the JIC. Suggest they contact the JIC Coordinator.
- e. When talking to the Media do not speculate.
EPP-051 ATTACHMENT II PAGE 1 OF 1 REVISION 6 EMERGENCY OPERATIONS FACILITY MANNING CHART Team:_ Date:
Minimum Staffing (Time Met: _ )
Offsite Emergency Coordinator:
Offsite Dose Assessor:
Offsite Radiological Monitor:
Offsite Radiological Monitor:
Field Team Driver:
Field Team Driver:
Essential Staffing (Time Met:_)
Emergency Control Officer:
Security Coordinator:
Lead Communicator:
EOF Communicator:
Emergency Preparedness Rep.:
Offsite Rad. Monitoring Coordinator:
Field Team Dispatcher:
Technical Support Coordinator:
TS Engineer, Assistant:
TS Engineer, Systems:
Plant Status Communicator:
Major Events Logger:
Plant Status Advisor:
General Services Coordinator:
Media Coordinator:
Lead Technical Briefer:
State/Local Government Liaisons SC Emergency Operations Center:
Fairfield County:
Newberry County:
Lexington County:
Richland County:
Others Comments