ML030520307

Emergency Plan Implementing Procedures Manual Volume C Revision 2003-02

ML030520307
Person / Time
Site:	Oconee
Issue date:	02/17/2003
From:	Rosalyn Jones Duke Power Co
To:	Document Control Desk, Office of Nuclear Security and Incident Response
References
Download: ML030520307 (75)

Text

SDuke R. A.JONES iPower Vice President A Duke Energy Company Duke Power 29672 / Oconee Nuclear Site 7800 Rochester Highway Seneca, SC 29672 864 885 3158 864 885 3564 fax February 17, 2003 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Subject:

Oconee Nuclear Station Docket Nos. 50-269, -270, -287 Emergency Plan Implementing Procedures Manual Volume C Revision 2003-02 Please find attached for your use and review copies of the revision to the Oconee Nuclear Station Emergency Plan: Volume C Revision 2003-02, February 2003.

This revision is being submitted in accordance with 10 CFR 50-54(q) and does not decrease the effectiveness of the Emergency Plan or the Emergency Plan Implementing Procedures.

K>* Any questions or concerns pertaining to this revision please call Rodney Brown, Emergency Planning Manager at 864-885-3301.

By copy of this letter, two copies of this revision are being provided to the NRC, Region II, Atlanta, Georgia.

Very y yours, R .Jones.

V , conee Nuclear Site xc: (w/2 copies of attachments)

Mr. Luis Reyes, Regional Administrator, Region II U. S. Nuclear Regulatory Commission 61 Forsyth St., SW, Suite 24T23 Atlanta, GA 30303 w/copy of attachments Mr. James R. Hall Rockville, Maryland (w/o Attachments, Oconee Nuclear Station)

NRC Resident Inspector J. R. Brown, Manager, Emergency Planning www duke-energy corn

February 17, 2003 OCONEE NUCLEAR SITE INTRASITE LETTER

SUBJECT:

Emergency Plan Implementing Procedures Volume C, Revision 2003-02 Please make the following changes to the Emergency Plan Implementing Procedures Volume C by following the below instructions.

REMOVE ADD Cover Sheet - Rev. 2003 01 Cover Sheet Rev. 2003-02 Table of Contents, Page 1 Table of Contents, Page 1 RP/0/B/1000/001 - 06/19/02 RP/0/B/1000/001 - 02/11/03 RP/0/B/1000/003A - 12/03/98 RP/0/B/1000/003A - 01/21/03 RP/0/B/1000/019 - 10/14/02 RP/0/B/1000/019 - 01/21/03

DUKE POWER EMERGENCY PLAN IMPLEMENTING PROCEDURES VOLUME C APPROVED:

W. W. Foster, Manager Safety Assurance 02/17/2003 Date Approved 02/17/2003 Effective Date VOLUME C REVISION 2003-02 February 2003

VOLUME C TABLE OF CONTENTS HP/0/B11009/018 Off-Site Dose Projections 08/29/02 HP/0/B/1009/020 Estimating Food Chain Doses Under Post Accident 10/09/98 Conditions HIP/0/B/1009/021 Source Term Assessment Of A Gaseous Release From 12/01/97 Non-Routine Release Points HP//B/I1009/022 On Shift Off-Site Dose Projections 08/15/02 RP/0/B /1000/001 Emergency Classification 02/11/03 RP/0/B/1000/002 Control Room Emergency Coordinator Procedure 08/29/02 RP/O/BI1000/003 A ERDS Operation 01/21/03 I

RP/0/B /1000/007 Security Event 08/29/02 RP/0/B /1000/009 Procedure For Site Assembly 02/19/02 RP/0/B1/1000/010 Procedure For Emergency Evacuation/Relocation Of Site 04/24/01 Personnel RP/0B/1000/015 A Offsite Communications From The Control Room 12/11/01 RP/0/B/1000/015 B Offsite Communications From The Technical Support Center 12/11/01 RP0/1B/1000/015 C Offsite Communications From The Emergency Operations 12/11/01 Facility RP/O/BI1 000/016 Medical Response 09/12/02 RP/0BI1000/017 Spill Response 11/04/02 RP/0/B/1000/018 Core Damage Assessment 09/30/97 RP/0/B/1000/019 Technical Support Center Emergency Coordinator Procedure 01/21/03 I

RP/0/B/1000/020 Emergency Operations Facility Director Procedure 12/11/02 RP/O/B/1000/021 Operations Interface (EOF) 11/04/02 RP/O/B/1000/022 Procedure For Site Fire Damage Assessment And Repair 07/16/02 RP/0/B/1000/024 Protective Action Recommendations 11/10199 RP/0/B /1000/028 Communications & Community Relations World Of 02/17/97 Energy Emergency Response Plan Revision 2003-02 February 2003 1

INIPMATION Duke Power Company PROCEDURE PROCESS RECORD (I)IDNo RP/O/B/1000/0O01 013 ONLY Revision No.

K-EPARATION (2) Station OCONEE NUCLEAR STATION (3) Procedure Title Emergency Classification (4) Prepared By Mike Thome (Signature) A z k Date 01/27/03 (5) Requires NSD 228 Applicability Determination?

[ Yes (New procedure or revision with major changes)

El No (Revision with minor changes) iZ No (To incorporate previously approved changes) 7/a (6) Reviewed By (QR) Date '," b Cross-Disciplinary Re'U By (QR)NA-4A)LDate Reactivity Mgmt Review By (QR)NA . Date Z 05 Mgmt Involvement Review By (Ops Supt) NAkhO Date Z-1 0 (7) Additional Reviews Reviewed By Date _

Reviewed By Date (8) Temporary Approval (if necessary)

By (OSM/QR) Date By (QR) Date (9) Approved By f ,L* . Date 4211 __/d,3 PERFORMANCE (Compare with control copy every 14 calendardays while work is being performed.)

(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (11) Date(s) Performed Work Order Number (WO#)

COMPLETION (12) Procedure Completion Verification:

o Unit 0 0 Unit 1 0 Unit 2 0 Unit 3 Procedure performed on what unit?

0 Yes 0 NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?

o Yes 01 NA Required enclosures attached?

03 Yes El NA Data sheets attached, completed, dated, and signed?

D Yes D NA Charts, graphs, etc. attached, dated, identified, and marked?

E0 Yes E0 NA Procedure requirements met?

Verified By Date

( Procedure Completion Approved Date

(* Remarks (Attach additionalpages)

Duke Power Company Procedure No.

Oconee Nuclear Site RP/O/B/1000/001 Revision No.

013 Emergency Classification Electronic Reference No.

Reference Use OX002WOS

RP/0/B/1000/001 Page 2 of 5 Emergency Classification NOTE: This procedure is an implementing procedure to the Oconee Nuclear Site Emergency plan and must be forwarded to Emergency Planning within seven (7) working days of approval.

1. Symptoms 1.1 This procedure describes the immediate actions to be taken to recognize and classify an emergency condition.

1.2 This procedure identifies the four emergency classifications and their corresponding Emergency Action Levels (EALs).

1.3 This procedure provides reporting requirements for non-emergency abnormal events.

1.4 The following guidance is to be used by the Emergency Coordinator/EOF Director in assessing emergency conditions:

1.4.1 The Emergency Coordinator/EOF Director shall review all applicable initiating events to ensure proper classification.

1.4.2 The BASIS Document (Volume A, Section D of the Emergency Plan) is available for review if any questions arise over proper classification.

1.4.3 IF An event occurs on more than one unit concurrently, THEN The event with the higher classification will be classified on the Emergency Notification Form.

A. Information relating to the problem(s) on the other unit(s) will be captured on the Emergency Notification Form as shown in RP/O/B/1000/015A, (Offsite Communications From The Control Room),

RP/O/B/1000/015B, (Offsite Communications From The Technical Support Center) or RP/O/B/1000/015C, (Offsite Communications From The Emergency Operations Facility).

1.4.4 IF An event occurs, AND A lower or higher plant operating mode is reached before the Classification can be made, THEN The classification shall be based on the mode that existed at the time the event occurred.

2

RP/O/B/1000/001 Page 3 of 5 1.4.5 The Fission Product Barrier Matrix is applicable only to those events that occur at Hot Shutdown or higher.

A. An event that is recognized at Cold Shutdown or lower shall not be classified using the Fission Product Barrier Matrix.

1. Reference should be made to the additional enclosures that provide Emergency Action Levels for specific events (e.g., Severe Weather, Fire, Security).

1.5 IF A transient event should occur, THEN Review the following guidance:

1.5.1 IF An Emergency Action Level (EAL) identifies a specific duration AND The Emergency Coordinator/EOF Director assessment concludes that the specified duration is exceeded or will be exceeded, (i.e.;

condition cannot be reasonably corrected before the duration elapses),

THEN Classify the event.

1.5.2 IF A plant condition exceeding EAL criteria is corrected before the specified duration time is exceeded, THEN The event is NOT classified by that EAL.

A. Review lower severity EALs for possible applicability in these cases.

NOTE: Reporting under 10CFR50.72 may be required for the following step. Such a condition could occur, for example, if a follow up evaluation of an abnormal condition uncovers evidence that the condition was more severe than earlier believed.

1.5.3 IF A plant condition exceeding EAL criteria is not recognized at the time of occurrence, but is identified well after the condition has occurred (e.g.; as a result of routine log or record review)

AND The condition no longer exists, THEN An emergency shall NOT be declared.

3

RP/O/BI1000/001 Page 4 of 5 1.5.4 IF An emergency classification was warranted, but the plant condition has been corrected prior to declaration and notification, THEN The Emergency Coordinator must consider the potential that the initiating condition (e.g.; Failure of Reactor Protection System) may have caused plant damage that warrants augmenting the on shift personnel through activation of the Emergency Response Organization.

A. IF An UnusualEvent condition exists, THEN Make the classification as required.

1. The event may be terminated in the same notification or as a separate termination notification.

B. IF An Alert, Site Area Emergency, or General Emergency condition exists, THEN Make the classification as required, AND Activate the Emergency Response Organization.

1.6 Emergency conditions shall be classified as soon as the Emergency Coordinator/EOF Director assessment determines that the Emergency Action Levels for the Initiating Condition have been exceeded.

2. Immediate Actions 2.1 Determine the operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response to the event.

2.2 IF The unit is at Hot Shutdown or higher AND The condition/event affects fission product barriers, THEN GO TO Enclosure 4.1, (Fission Product Barrier Matrix).

2.2.1 Review the criteria listed in Enclosure 4.1, (Fission Product Barrier Matrix) and make the determination if the event should be classified.

4

RPIOIB/1 000/001 Page 5 of 5 2.3 Review the listing of enclosures to determine if the event is applicable to one of the categories shown.

2.3.1 IF One or more categories are applicable to the event, 2.3.2 THEN Refer to the associated enclosures.

2.3.3 Review the EALs and determine if the event should be classified.

A. IF An EAL is applicable to the event, THEN Classify the event as required.

2.4 IF The condition requires an emergency classification, THEN GO TO RP/O/B/1000/002, (Control Room Emergency Coordinator Procedure) Subsequent Actions.

2.5 Continue to review the emergency conditions to assure the current classification continues to be applicable.

3. Enclosures Enclosures Page Number

- 4.1 Fission Product Barrier Matrix 6 4.2 System Malfunctions 7 4.3 Abnormal Rad Levels/Radiological Effluents 9 4.4 Loss Of Shutdown Functions 11 4.5 Loss of Power 13 4.6 Fires/Explosions And Security Actions 14 4.7 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety 15 4.8 Radiation Monitor Readings For Emergency Classification 18 4.9 Unexpected/Unplanned Increase In Area Monitor Readings 19 4.10 Definitions 20 4.11 Operating Modes Defined In Improved Technical Specifications 24 4.12 Instructions For Using Enclosure 4.1 25 5

Encl( e 4.1 RP/O/B/l*c/001 Fission Product Barrier Matrix Page 1 of 1 DETERMINE THE APPROPRIATE CLASSIFICATION USING THE TABLE BELOW: CIRCLE EALS CHOSEN. ADD POINTS TO CLASSIFY. (SEE NOTE BELOW')

- . . RCS BARRIERS (BD 5-7) -'FUEL CLAD BARRIERS (BD 8-9) .. . . CONTAINMENT BARRIERS (BD 10.12)

Potential Loss (4 Points) Loss (5 Points) Potential Loss (4 Points) Loss (5 Points) Potential Loss (1 Point) Loss (3 Points)

RCS Leakrate > Makeup capacity RCS Leak rate > available makeup Average of the 5 highest Average of the 5 highest CETC CETC ? 12000 F > 15 minutes Rapid unexplained containment of one HPI pump in normal capacity as indicated by a loss of CETC > 12000 F OR pressure decrease after increase 0

makeup mode (approx 160 gpm) subcooling 'a 7000 F CETCŽ> 700 F > 15 minutes with OR with Letdown isolated a valid RVLS reading 0" containment pressure or sump level not consistent with LOCA SGTR > Makeup capacity of one Valid RVLS reading of 0" Coolant activity Ž 300 tCi/ml DEI RB pressure Ž 59 psig Failure of secondary side of SG HPI pump in normal makeup OR results in a direct opening to the mode (approx. 160 gpm) with RB pressure 'a 10 psig and no environment with P/S leakage > 10 Letdown isolated. NOTE: RVLS is NOT RBCU or RBS gpm in the same SG Entry into the PTS (Pressurized I RIA 57/58 reading 1 0 R/hr valid if one or more Hours Since SD RIA57/58 R/hr Hours Since SD RIA57/58 - R/hr Failure of secondary side of SG Thermal Shock) Operation RCPs are running QR if results in a direct opening to the

---

- R 7reading1 Rhr LPI pump(s) are 0-<05 _300/150 0-<05 Ž1800/860 environment with P/S leakage 2 10 NOTE: PTS is entered under 2 RIA 58 reading Ž_1.0 R/hr running gpm in the other SG either of the following- AND

• A cooldown below 400*F @ 0 5 - < 2.0 > 80/40 05 - <2 0 >Ž400/195 Feeding SG with secondary side

> 100"F/hr. has occurred. 3RIA 57/58 reading > 1 0 Rihr failure from the affected unit 20-80 _32/16 20-80 >Ž280/130

• HPI has operated in the injection mode while NO S operating. . ...

...... RC!Ps -------------

were °Pe*t2.ng HPI Forced Cooling RCS pressure spike *a2750 psig Hydrogen concentration;> 9% Containment isolation is incomplete and a release path to the environment exists Emergency Coordinator/EOF Emergency Coordmator/EOF Emergency Coordmator/EOF Emergency Coordinator/EOF Director Emergency Coordinator/EOF Emergency Coordinator/EOF Director judgment Director judgment Director judgment judgment Director judgment Director judgment

-XUNUSUALEVENT (1-3 Total Points), --"-,,ALERT (4-6 Total Points) 'SITE AREA EMERGENCY (7-10 Total Points) GENERAL EMERGENCY (11-13 TotalPoints)

OPERATING MODE: 1,2,3,4 OPERATING MODE: 1, 2,3,4 OPERATING MODE: 1,2,3,4 OPERATING MODE: 1, 2,3,4

• Loss of any two bamers

+ Any potential loss of Containment

• Any potential loss or loss of the Fuel Clad

• Loss of any two barriers and potential loss of the

• Loss of one barmer and potential loss of either third bamer Any loss of containment

• Any potential loss or loss of the RCS RCS or Fuel Clad Barriers

• Loss of all three barriers Potential loss of both the RCS and Fuel Clad Barriers INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS:

SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY NOTIFY 1,2,3,4 NOTIFY 1,2,3,4 .NOTIFY 1,2,3,4 NOTIFY 1,2,3,4 NOTE: An event with multiple events could occur which would result in the conclusion that exceeding the loss or potential loss threshold is IMMINENT (i e, within 1-3 hours). In this IMMINENT LOSS situation, use judgment and classify as if the thresholds are exceeded 6

Enclj- -re 4.2 RP/O/B/I( 1001 C Systems , lunctions Page 1 ofR.

EET-,SITE ALERTA ARAEMERGENCY;_ ",GNEA EMERGENCY,

_______________________________ _____________________________%_ 4 I. RCS LEAKAGE (BD 14) 1. UNPLANNED LOSS OF MOST OR ALL 1. INABILITY TO MONITOR A SAFETY SYSTEM ANNUNCIATION/ SIGNIFICANT TRANSIENT IN OPERATING MODE: 1, 2,3,4 INDICATION IN CONTROL ROOM PROGRESS (BD 21)

(BD 19)

A. Unidentified leakage ? 10 gpm OPERATING MODE: 1,2,3,4 OPERATING MODE: 1, 2,3,4 B. Pressure boundary leakage 2: 10 gpm A.1 Unplanned loss of > 50% of the following A1 Unplannedloss of > 50% of the following annunciators on one unit for > 15 minutes.

C. Identified leakage > 25 gpm annunciators on one unit for > 15 minutes:

Units 1 & 3

1. UNPLANNED LOSS OF MOST OR ALL Units I & 3 1 SAI-9, 14-16, and 18 SAFETY SYSTEM ANNUNCIATION/ 1 SAI-9, 14-16, and 18 3 SAI-9, 14-16, and 18 INDICATION IN CONTROL ROOM 3 SA1-9, 14-16, and 18 Unit 2 FOR > 15 MINUTES (BD 15)

Unit 2 2 SA1-9, 14-16 OPERATING MODE: 1, 2,3,4 2 SA1-9, 14-16 AND AND AI Unplannedloss of > 50% of the following annunciators on one umt for > 15 minutes A.2 A significanttransientis in progress A.2 Loss of annunciators /indicators requires additional personnel (beyond normal shift Units 1 & 3 complement) to safely operate the unit AND 1 SA1-9, 14-16, and 18 3 SA1-9, 14-16, and 18 A.3 Loss of the OAC and ALL PAM indications AND Unit 2 A.3 Significantplant transientin progress AND 2 SA1-9, 14-16 AND OR A4 Inability to directly monitor any one of the following functions-A2 Loss of annunciators or indicators requires A.4 Loss of the OAC and ALL PAM additional personnel (beyond normal shift indications I. Subcriticality complement) to safely operate the unit 2 Core Cooling

3. INABILITY TO REACII REQUIRED 3 Heat Sink

4. RCS Integrity SIhUTDOWN WITIUN LIMITS (BD 16)

5. Containment Integrity 6 RCS Inventory OPERATING MODE: 1, 2,3,4 A Required operating mode not reached within TS LCO action statement time (CONTINUED) (END) (END)

INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS:

SEE EMERGENCY TELEPIIONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPIIONE DIRECTORY NOTIFY 1, 2,3,4 NOTIFY 1, 2,3,4 NOTIFY 1, 2,3,4 NOTIFY 1, 2,3,4 7

EncIl*"re 4.2 Page 2 of - '001 RP/0/B/ir 00

('UNUSUAL EVENT,-,,

Systems lunctions S '** '**, *ALERT*' "I; . ,, "', .. SIE A' AEER ENYA . - *

• GENERAL EMERGENCY-::

4. UNPLANNED LOSS OF ALL ONSITE OR OFFSITE COMMUNICATIONS (BD 17)

OPERATING MODE: All A. Loss of all onsite communications capability (ROLM system, PA system, Pager system, Onsite Radio system) affecting ability to perform Routine operations B. Loss of all onsite communications capability (Selective Signaling, NRC ETS lines, Offsite Radio System, AT&T line) affecting ability to communicate with offsite authorities.

5. FUEL CLAD DEGRADATION (lID 18)

• OPERATING MODE: Allt A. DEI - >5iCi/ml (END)

+ 4 4 INITIAL NOTIFICATION REQUIREMENTS:

SEE EMERGENCY TELEPIIONE DIRECTORY NOTIFY 1,2,3,4 8

Encle',re 4.3 RP/0/B/t/ '/001

( Abnormal Rad Lev( ,adiological Effluent Page 1 ot ,

7 A EV:, * .....

,.,'-' -ALERT,,, :J SITEAREA EMERGENCY GEA EMERGENCY I ANY UNPLANNED RELEASE OF 1. ANY UNPLANNED RELEASE OF 1. BOUNDARY DOSE RESULTING FROM 1. BOUNDARY DOSE RESULTING FROM GASEOUS OR LIQUID RADIOACTIVITY GASEOUS OR LIQUID RADIOACTIVITY ACTUAL/IMMINENT RELEASE OF ACTUAL/ IMMINENT RELEASE OF TO THE ENVIRONMENT THAT TO THE ENVIRONMENT TIAT GASEOUS ACTIVITY (BD 32) GASEOUS ACTIVITY (BD 36)

EXCEEDS TWO TIMES THE SLC EXCEEDS 200 TIMES RADIOLOGICAL LIMITS FOR 60 MINUTES OR LONGER TECHNICAL SPECIFICATIONS FOR 15 OPERATING MODE: All OPERATING MODE All (BD 23) MINUTES OR LONGER (BD 28)

A. Valid reading on RIA 46 of > 2 09E+05 cpm A. Valid reading on RIA 46 of 2 2 09E+06 cpm OPERATING MODE: All OPERATING MODE: All for >15 minutes (See Note 2) for Ž15 minutes (See Note 3)

A. Valid indication on RIA 46 of > 2 09E+04 cpm A. Valid indication on radiation monitor RIA 33 B. Valid reading on RIA 57 or 58 as shown on B. Valid reading on RIA 57 or 58 as shown on of Ž4 06E+06 cpm for > 60 minutes for >15 minutes (See Note 1) Enclosure 4.8 (See Note 2) Enclosure 4.8 (See Note 3)

(See Note 1)

B I RIA 33 HIGH Alarm C. Dose calculations result in a dose projection at C. Dose calculations result in a dose projection at B. Valid indication on radiation monitor RIA 45 of> 9.35E+05 cpm for > 60 minutes the site boundary of. the site boundary of:

AND (See Note I)

> 100 mRem TEDE or 500 mRem CDE adult Cl :1000mRemTEDE B2 Liquid effluent being released exceeds 200 thyroid C. Liquid effluent being released exceeds two times the level of SLC 16.11.1 for > 15 minutes OR times SLC 16.11.1 for > 60 minutes as as determined by Chemistry Procedure determined by Chemistry Procedure D Field survey results indicate site boundary dose C2 > 5000 mRem CDE adult thyroid C Gaseous effluent being released exceeds 200 rates exceeding >100 mRad/hr expected to D. Gaseous effluent being released exceeds two times the level of SLC 16.11.2 for >15 minutes continue for more than one hour D Field survey results indicate site boundarydose times SLC 16 11.2 for> 60 minutes as as determined by RP Procedure rates exceeding >1000 mRad/hr expected to determined by RP Procedure OR continue for more than one hour

2. RELEASE OF RADIOACTIVE DI Analyses of field survey samples indicate adult NOTE 1: If monitor reading is sustained OR MATERIAL OR INCREASES IN thyroid dose commitment of Ž 500 mRem for the time period indicated in the EAL AND the required assessments (procedure RADIATION LEVELS THAT IMPEDES CDE (3 84 E"7 p1Ci/ml) for one hour of D1 Analyses of field survey samples indicate adult OPERATION OF SYSTEMS REQUIRED inhalation calculations) cannot be completed within thyroid dose commitment ofŽ 5000 mRem TO MAINTAIN SAFE OPERATION OR this period, declaration must be made on the CDE for one hour of inhalation TO ESTABLISII OR MAINTAIN COLD valid Radiation Monitor reading.

SIIUTDOWN (BD 30) NOTE 2: If actual Dose Assessment cannot be completed within 15 minutes, then the OPERATING MODE: All valid radiation monitor reading should be NOTE 3. If actual Dose Assessment cannot used for emergency classification. be completed within 15 minutes, then the A. Valid radiation reading > 15 mRad/hr in CR, valid radiation monitor reading should be CAS, or, Radwaste CR used for emergency classification B. Unplanned/unexpected valid area monitor readings exceed limits stated in Enclosure 4.9 (CONTINUED) (CONTINUED) (END)

(CONTINUED)

INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS:

SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY NOTIFY 1,2,3,4 NOTIFY 1,2,3,4 NOTIFY 1, 2,3,4 NOTIFY 1, 2,3,4 Assumptions used for calculation of vent moritors RIA 45 & 46 1 Average annual meteorology (1 672 E-6 sec/hr), serm--levated 2 Vent flow rate 65,000 cfm (average daily flow rate) 3 No credii is taken for vent filtration 4 One hour release duration for Unusual Event, 15 mtnute duration for Alert, Site Area Emergency, General Emergency 5 General Emergency PAGs are I rein TEDE and 5 rem CDE, Site Area Emergency determination is based on 10% of the General Emergency PAGs 6 Calculations for monitor readings are based on whole body dose

7. Standard ODCM guilance together with NUMARC guilance indiates that effluent releases are based on Technical Specification releases 9

Encl*',re 4.3 RP/0/B/I( '001

( Abnormal Rad Lev& ,adiological Effluent Page 2ofk,

[-NSALEET' NSA ALERT STAREA EMERGENCYGNRLEEGNY GEEY MREC 2 UNEXPECTED INCREASE IN PLANT 2. MAJOR DAMAGE TO IRRADIATED 2. LOSS OF WATER LEVEL IN THE RADIATION OR AIRBORNE FUEL OR LOSS OF WATER LEVEL REACTOR VESSEL TIIAT HAS OR CONCENTRATION (BD 25) THAT IIAS OR WILL RESULT IN TIHE WILL UNCOVER FUEL IN THE UNCOVERING OF IRRADIATED FUEL REACTOR VESSEL (BD 35)

OPERATING MODE: All OUTSIDE THE REACTOR VESSEL (BD 31) OPERATING MODE: 5,6 A LT 5 reading 14" and decreasing with makeup not keeping up with leakage WITH fuel in the OPERATING MODE: All A1 Failure of heat sink causes loss of Cold core Shutdown conchtion A Valid RIA 3,6,41, OR 49 HIGH Alarm B. Uncontrolledwater level decrease in the SFP AND and fuel transfer canal with all irradiated fuel B HIGH Alarm for portable area monitors on the assemblies remaining covered by water main bridge or SFP bridge A.2 LT 5 indicates 0 inches after initiation of RCS C Report of visual observation of irradiated fuel makeup C 1 R/hr radiation reading at one foot away from a damaged storage cask located at the ISFSI uncovered B.1 Failure of heat sink causes loss of Cold Shutdown condition D Valid area monitor readings exceeds limits D. Operators determine water level drop in either stated in Enclosure 4 9 the SFP or fuel transfer canal will exceed AND makeup capacity such that irradiated fuel will be uncovered B 2 Either train ultrasonic level indication less than 0 inches and decreasing after initiation of RCS (NND) makeup NOTE: This Initiating Condition is also located in Enclosure 4 4., (Loss of Shutdown Functions) High radiation levels will also be seen with this condition (END)

INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS:

SEE EMERGENCY TELEPIIONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY NOTIFY 1, 2,3,4 NOTIFY,2, 3,4 NOTIFY 1, 2,3,4 10

C Encl( e 4.4 Loss of Shutdown Functions RPg/Be 1o Page I of 2

/001 UNUSUAL EVENT IAE¶> ITAE MREC GENERAL EMERGENCY ý'7<

1. FAILURE OF RPS TO COMPLETE OR 1. FAILURE OF RPS TO COMPLETE OR 1. FAILURE OF RPS 'O CUOMI'LEIT INITIATE A Rx SCRAM (BD 39) INITIATE A Rx SCRAM (BD 42) AUTOMATIC SCRAM AND MANUAL SCRAM NOT SUCCESSFUL WITH INDICATION OF CORE DAMAGE OPERATING MODE 1, 2,3 OPERATING MODE: 1, 2 (BD 45)

A.1 Valid reactor trip signal received or required A.1 Valid reactor trip signal received or required WITITOUT automatic scram WITHOUT automatic scram OPERATING MODE: 1, 2 AND A I Valid Rx trip signal received or required AND A.I.1 DSS has inserted Control Rod Groups WITHOUT automatic scram 5,6,7 A.2 DSS has NOT inserted Control Rod Groups 5, 6, 7 AND OR A 1.2 Manual trip from the Control Room is AND A.2 Manual trip from the Control Room was NOT successful and reactor power is less successful in reducing reactor power to < 5%

than 5% and decreasing and decreasing A3 Manual trip from the Control Room was NOT successful in reducing reactor power to less

2. INABILITY TO MAINTAIN PLANT IN AND than 5% and decreasing COLD SHUTDOWN (BD 41)

2. COMPLETE LOSS OF FUNCTION A.3 Average of the 5 highest CETCs 21200* F on OPERATING MODE: 5,6 NEEDED TO ACHIEVE OR MAINTAIN ICCM HOT SHUTDOWN (BD 43)

A 1 Loss of LPI and/or LPSW AND OPERATING MODE: 1, 2,3,4 A2 Inability to maintain RCS temperature A. Average of the 5 highest CETCs >1200* F below 200* F as indicated by either of the shown on ICCM (END) following B. Unable to maintain reactor subcntical A 2.1 RCS temperature at the LPI Pump Suction C SSF feeding SG per EOP OR A22 Average of the 5 highest CETCs as (CONTINUED) indicated by ICCM display OR A 2.3 Visual observation (END)

INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS.

SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY NOTIFY 1, 2,3,4 NOTIFY 1, 2,3,4 NOTIFY 1, 2,3,4 11

C EnclC .e 4.4 Loss of Shutdown Functions RP/O/B/1*,.,/001 Page 2 of 2 UNUSUAL EVENT.> - iALR SITE-AREA EMERGENCY.GNLEMREC

3. LOSS OF WATER LEVEL IN THE REACTOR VESSEL THAT HAS OR WILL UNCOVER FUEL IN THE REACTOR VESSEL (BD 44)

OPERATING MODE: 5,6 A1 Failure of heat sink causes loss of Cold Shutdown conditions AND A.2 LT-5 indicates 0 inches after initiation of RCS Makeup BI Failure of heat sink causes loss of Cold Shutdown conditions AND B2 Either train ultrasonic level indication less than 0 inches and decreasing after initiation of RCS makeup (END)

INITIAL NOTIFICATION REQUIREMENTS:

SEE EMERGENCY TELEPHONE DIRECTORY NOTIFY 1, 2, 3,4 12

C Enc( :e 4.5 Loss of Power RP/O/B/1ih( /O1 Page 1 of 1 UNUSUAL EVENT . LR. SITE AREA EMERGENCY IGENER1AL EMERGENCY

1. LOSS OF ALL OFFSITE POWER TO 1. LOSS OF ALL OFFSITE AC POWER AND 1. LOSS OF ALL OFFSITE AC POWER AND 1. PROLONGED LOSS OF ALL OFFSITE ESSENTIAL BUSSES (BD FOR 47)GREATER LOSS OF ALLBUSSES ONSITE(BD AC 49)

POWER TO LOSS OF ALLBUSSES ONSITE AC THAN 15 MINUTES ESSENTIAL ESSENTIAL (BDPOWER

51) TO POWER (BD 54)AND ONSITE AC POWER OPERATING MODE: All OPERATING MODE: 5,6 OPERATING MODE: 1,2,3,4 OPERATING MODE: 1, 2,3,4 Defueled A.1 Loss of all offsite AC power to both the Red A.1 MFB I and 2 de-energized AI MFB I and 2 de-energized and Yellow Busses for > 15 minutes AI MFB I and 2 de-energized AND AND AND* AND A2 Failure to restore power to at least one MFB A.2 SSF fails to maintain Hot Shutdown A2 Failure to restore power to at least one MFB within 15 minutes from the time of loss of A2 Unit auxiliaries are being supplied from within 15 minutes from the time of loss of both both offsite and onsite AC power AND Keowee or CTS offsite and onsite AC power

2. AC POWER CAPABILITY TO 2. LOSS OF ALL VITAL DC POWER A.3 At least one of the following conditions exist

2. UNPLANNED LOSS OF REQUIRED DC POWER FOR GREATER THAN 15 ESSENTIAL BUSSES REDUCED TO A (BD 52)

MINUTES (BD 48) MD15 SINGLE MINUTES SOURCE 50) GREATER TIIAN (BDFOR OPERATING MODE: 1,2, 3, 4 A 3.1 Restoration of power to at least one MFB within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is NOT likely OPERATING MODE: 5, 6 ORl OPERATING MODE: 1, 2,3,4 A.1 Unplannedloss of vital DC power to required A. 1 Unplannedloss of vital DC power to required DC busses as indicated by bus voltage less than A 32 Indications of continuing DC busses as indicated by bus voltage less A. AC power capability has been degraded to a 110 VDC degradation of core cooling based than 110 VDC single power source for > 15 minutes due to the on Fission Product Barrier loss of all but one of, AND monitoring AND Unit Normal Transformer A.2 Failure to restore power to at least one required (END)

A2 Failure to restore power to at least one required Unit SU Transformer DC bus within 15 minutes from the time of loss DC bus within 15 minutes from the time of loss Another Unit SU Transformer CT5 (END)

(END)

(END)

INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS:

SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY NOTIFY 1,2,3,4 NOTIFY 1, 2,3,4 NOTIFY 1,2,3,4 NOTIFY 1, 2,3,4 13

Encd -'re 4.6 RP/O/B/]/ 1001 C Fires/Explosions, .Security Actions Page 1 OVL UNUSUAL EVENTr! J ALRTALERT,,- ~.

' SITE AREA EMERGENCY G

1. FIRES/EXPLOSIONS WITInN TIlE 1. FIRE/EXPLOSION AFFECTING 1. SECURITY EVENT IN A PLANT VITAL 1. SECURITY EVENT RESULTING IN LOSS PLANT (BD 57) OPERABILITY OF PLANT SAFETY AREA (BD 61) OF ABILITY TO REACH AND SYSTEMS REQUIRED TO MAINTAIN COLD SHUTDOWN (BD 62)

ESTABLISH/MAINTAIN SAFE OPERATING MODE: All OPERATING MODE: All SHUTDOWN (BD 59) OPERATING MODE All OPERATING MODE: All NOTE: RP/0/B/1000/007, (Security Event), NOTE: RP/OIBII00/007, (Security Event),

NOTE Within the plant means shall be used in conjunction with all security shall be used in conjunction with all Turbine Building, Auxiliary Building, related emergency classifications security related emergency classifications NOTE: Only one train of a system needs to Reactor Building, Keowee Hydro. I be affected or damaged in order to satisfy this condition.

A. Fire within the plant not extinguished within A Intrusion into any of the following plant areas A Loss of physical control of the control room 15 minutes of Control Room notification or A 1 Fire/explosions by a hostile force due to security event verification of a Control Room alarm Reactor Building AND Auxiliary Building B Loss of physical control of the Aux Shutdown B. Unanticipated explosion within the plant A. 1.1 Affected safety-related system parameter Keowee Hydro panel and the SSF due to a Security Event resulting in visible damage to permanent indications show degraded performance structures/equipment OR B. Bomb detonated in any of the following areas (END)

"* Keowee Hydro

2. CONFIRMED SECURITY THREAT A 12 Plant personnel report visible damage to "* Keowee Dam INDICATES POTENTIAL permanent structures or equipment "* ISFSI DEGRADATION IN THE LEVEL OF required for safe shutdown "* Reactor Building SAFETY OF PLANT (BD 58) "* Auxiliary Building 2 SECURITY EVENT IN A PLANT "* SSF OPERATING MODE: All PROTECTED AREA (BD 60)

(END)

OPERATING MODE: All NOTE: RPIO/B/1000/007, (Security Event), shall be used in conjunction with all NOTE: RP/0/B/10001007, (Security Event),

security related emergency classifications. shall be used in conjunction with all security related emergency classifications.

A. Discovery of bomb within plant protectedarea and outside security vital areas A Intrusion into plant protected areaby a hostile B HostagelExtortionsituation force C. Violent civil disturbance within the owner B Bomb discovered in an area containing safety controlled area related equipment D CredibleSecurity threat to the site (END) (END)

INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS:

SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY. SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY NOTIFY 1, 2,3,4 NOTIFY 1, 2,3,4 1 NOTIFY 1, 2,3,4 NOTIFY 1, 2,3,4 14

Enclp r'e 4.7 RP/0/B/I( t001 C Natural Disasters, Hazards and 0L_ .-Conditions Affecting Plant Safety Page 1 of'-,

UNUSUAL EVENT . ALR '/Jj pH h%"- KGENERAL EMERGENCY--

1. NATURAL AND DESTRUCTIVE 1. NATURAL AND DESTRUCTIVE 1. CONTROL ROOM EVACUATION AND OTHER CONDITIONS WARRANT PHENOMENA AFFECTING THE PHENOMENA AFFECTING TIHE PLANT PLANT CONTROL CANNOT BE DECLARATION OF GENERAL PROTECTEDAREA (11D 64) VITAL AREA (BD 69) ESTABLISHED (B1D 75) EMERGENCY (BD 78)

OPERATING MODE: All OPERATING MODE: All OPERATING MODE: All OPERATING MODE: All A. Tremor felt and seismic trigger actuates (0 05g)

A.1 Control Room evacuation has been initiated AI Emergency Coordinator/EOF Director A Tremor felt and valid alarm on the strong B.1 Tornado, high winds, missiles resulting from turbine failure, vehicle crashes, or other judgment indicates motion accelerograph AND catastrophic event AND A 11 Actual/imminent substantial core B Tornado striking within ProtectedArea A2 Control of the plant cannot be estabhshed from degradation with potential for loss of Boundary the Aux Shutdown Panel or the SSF within 15 NOTE- Only one train of a safety-related system containment minutes needs to be affected or damaged in order to C. Vehicle crash into plant structures/systems satisfy these conditions. OR within the ProtectedArea Boundary 2. KEOWEE IIYDRO DAM FAILURE (BD 76) A.1.2 Potential for uncontrolled D Turbine failure resulting in casing penetration B I I Visible damage to permanent radionuclide releases that would or damage to turbine or generator seals structures or equipment required for OPERATING MODE: All result in a dose projection at the safe shutdown of the unit site boundary greater than 1000 mRem OR A Imminent/actual dam failure includes any of TEDE or 5000 mRem CDE Adult Thyroid (CONTINUED) the following B.I.2 Affected safety system parameter "* Keowee Hydro Dam indications show degraded " Little River Dam (END) performance "* DikesA, B,C, orD

"* Intake Canal Dike

2. RELEASE OF TOXIC/FLAMMABLE GASES JEOPARDIZING SYSTEMS 3. OTHER CONDITIONS WARRANT REQUIRED TO MAINTAIN SAFE DECLARATION OF SITE AREA OPERATION OR ESTABLISH EMERGENCY (BD 77)

MAINTAIN COLD SHUTDOWN (BD 71)

OPERATING MODE: All OPERATING MODE: All A. Report/detection of toxic gases in concentrations that will be life-threatening to A. Emergency Coordinator/EOF Director plant personnel judgment B Report/detection of flammable gases in (END) concentrations that will affect the safe operation of the plant.

"* Reactor Building

"* Auxiliary Building

"* Turbine Building

"* Control Room (CONTINUED)

INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS:

SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPIHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY NOTIFY 1, 2,3,4 NOTIFY 1, 2,3,4 1 NOTIFY 1, 2,3,4 NOTIFY I, 2,3,4 15

Enclj re 4.7 RP/0/B/1( /001 C UNUSUAL EVENT 7`7 Natural Disasters, Hazards and ALERT Conditions Affecting Plant Safety I

Page 2 of'--

GENERAL EEGNY

-EAEAEMERGENCY',ý

______________________3/4::i RT~j~ ~SITEAREEMERENC

2. NATURAL AND DESTRUCTIVE 3. TURBINE BUILDING FLOOD (BD 72)

PHENOMENA AFFECTING KEOWEE IIYDRO (BD 66)

OPERATING MODE: All OPERATING MODE: All A. Turbine Building flood requiring use of A. Reservoir elevation Z:807 feet with all spillway AP/1,2,3/A11700/10, (Turbine Building Flood) gates open and the lake elevation continues to rise 4. CONTROL ROOM EVACUATION IIAS BEEN INITIATED (BD 73)

B Seepage readings increase or decrease greatly or seepage water is carrying a significant amount of soil particles OPERATING MODE: All C New area of seepage or wetness, with large A. 1 Evacuation of Control Room amounts of seepage water observed on dam, AND ONE OF THE FOLLOWING:

dam toe, or the abutments AND D. Slide or other movement of the dam or abutments which could develop into a failure A.1.1 Plant control IS established from the Aux E. Developing failure involving the powerhouse or shutdown Panel or the SSF OR appurtenant structures and the operator believes the safety of the structure is questionable A 1.2 Plant control IS BEING established from the Aux Shutdown Panel or SSF

3. RELEASE OF TOXIC OR FLAMMABLE

5. OTHER CONDITIONS WARRANT GASES DEEMED DETRIMENTAL TO SAFE OPERATION OF TIlE PLANT CLASSIFICATION OF AN ALERT (BD 74)

(BD 67)

OPERATING MODE: All OPERATING MODE: All A. Report/detection of toxic or flammable gases A I Emergency Coordinator judgment indicates that could enter within the site area boundary that:

in amounts that can affect normal operation of the plant A. 1.1 Plant safety may be degraded B Report by local, county, state officials for AND potential evacuation of site personnel based on A.I 2 Increased monitoring of plant functions offsite event is warranted (END)

(CONTINUED)

INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS, INITIAL NOTIFICATION REQUIREMENTS: INITIAL NOTIFICATION REQUIREMENTS:

SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPHONE DIRECTORY SEE EMERGENCY TELEPIIONE DIRECTORY NOTIFY 1, 2,3,4 NOTIFY 1, 2,3,4 NOTIFY 1, 2,3,4 NOTIFY 1,2,3,4 16

Encl, RP/0/ag/e(" '001 (7 Natural Disasters, Hazards and O. Conditions Affecting Plant Safety Page 3 of,-*

" UNUSUALEVENT., STE AREA EMERGENCY ,GENERAL EMERGENCY"'

4 OTHER CONDITIONS EXIST WHICH WARRANT DECLARATION OF AN UNUSUAL EVENT (BD 68)

OPERATING MODE: All A. Emergency Coordinator determines potential degradation of level of safety has occurred (END)

INITIAL NOTIFICATION REQUIREMENTS:

SEE EMERGENCY TELEPhIONE DIRECTORY NOTIFY 1, 2,3,4 17

EnclC e 4.8 Rp/0/B/l*,,d/001 C Radiation Monitor Readings for Emergency Classification Page 1 of 1 NOTE: IF Actual Dose Assessment cannot be completed within 15 minutes.

THEN The valid monitor reading should be used for Emergency Classification.

All RIA values are considered GREATER THAN or EQUAL TO HOURS SINCE RIA'57 R/hr-. RIA 58 R/hr*

REACTOR TRIPPED Site Area Emergency General Emergency Site Area Emergency General Emergency 0.0 - < 0.5 5.9E+003 5.9E+004 2.6E+003 2.6E+004 0.5 - < 1.0 2.6E+003 2.6E+004 1.1E+003 1.1E+004 1.0 - < 1.5 1.9E+003 1.9E+004 8.6E+002 8.6E+003 1.5 - < 2.0 1.9E+003 1.9E+004 8.5E+002 8.5E+003 2.0 - < 2.5 1.4E+003 1.4E+004 6.3E+002 6.3E+003 2.5 - < 3.0 1.2E+003 1.2E+004 5.7E+002 5.7E+003 3.0 - < 3.5 1.1E+003 1.1E+004 5.2E+002 5.2E+003 3.5 - < 4.0 1.OE+003 1.OE+004 4.8E+002 4.8E+003 4.0 - < 8.0 1.OE+003 1.OE+004 4.4E+002 4.4E+003

• RIA 58 is partially shielded Assumptions used for calculation of high range in-containment monitors RIA 57 and 58:

1. Average annual meteorology (7.308 E6 sec/m 3)

2. Design basis leakage (5.6 E6 mulhr)

3. One hour release duration

4. General Emergency PAGs are 1 rem TEDE and 5 rem CDE; Site Area Emergency determination is based on 10% of the General Emergency PAGs

5. Calculations for monitor readings are based on CDE because thyroid dose is limiting

6. No credit is taken for filtration

7. LOCA conditions are limiting and provide the more conservative reading 18

RP/0/B/I,/001 C Unexpected/Unplanned Enc(

Increase 7e 4.9 In Area Monitor Readings Page 1 of 1 NOTE: This Initiating Condition is not intended to apply to anticipated temporary increases due to planned events (e.g.; incore detector movement, radwaste container movement, depleted resin transfers, etc.).

UNITS 1, 2,3 MONITOR NUMBER UNUSUAL EVENT 1000x ALERT NORMAL LEVELS mRAD/HR mRAD/HR RIA 7, Hot Machine Shop Elevation 796 150 >5000 RIA 8, Hot Chemistry Lab Elevation 796 4200 Ž5000 RIA 10, Primary Sample Hood Elevation 796 830 Ž5000 RIA 11, Change Room Elevation 796 210 Ž5000 RIA 12, Chem Mix Tank Elevation 783 800 >5000 RIA 13, Waste Disposal Sink Elevation 771 650 Ž5000 RIA 15, HPI Room Elevation 758 NOTE* Ž5000 NOTE: RIA 15 normal readings are approximately 9 mRad/hr on a daily basis. Applying 1000x normal readings would put this monitor greater than 5000 mRad/hr just for an Unusual Event. For this reason, an Unusual Event will NOT be declared for a reading less than 5000 mRad/hr.

19

Enclosure 4.10 RP/O/B/1000/001 Definitions/Acronyms Page 1 of 4

1. List of Definitions and Acronyms NOTE: Definitions are italicized throughout procedure for easy recognition.

1.1 ALERT - Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.

1.2 BOMB - A fused explosive device 1.3 CONDITION A - Failure is Imminent or Has Occurred - A failure at the dam has occurred or is about to occur and minutes to days may be allowed to respond dependent upon the proximity to the dam.

1.4 CONDITION B - Potentially Hazardous Situation is Developing - A situation where failure may develop, but preplanned actions taken during certain events (such as major floods, earthquakes, evidence of piping) may prevent or mitigate failure.

1.5 CIVIL DISTURBANCE - A group of ten (10) or more people violently protesting station operations or activities at the site.

1.6 CREDIBLE THREAT - The determination of what is a credible threat to the site will be the responsibility of Security Manager/designee in consultation with the OSM. The determination of "credible" is made through use of information found in the Oconee Nuclear Station Safeguards Contingency Plan and Security implementing procedures.

1.7 EXPLOSION - A rapid, violent, unconfined combustion, or a catastrophic failure of pressurized equipment that imparts energy of sufficient force to potentially damage permanent structures, systems, or components. A sudden failure of a pressurized pipe/line could fit this definition. This definition includes MS line rupture and FW line ruptures.

1.8 EXTORTION - An attempt to cause an action at the station by threat of force.

1.9 FIRE - Combustion characterized by heat and light. Sources of smoke, such as slipping drive belts or overheated electrical equipment, do NOT constitutefires. Observation of flames is preferred but is NOT required if large quantities of smoke and heat are observed.

1.10 GENERAL EMERGENCY - Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Releases can be reasonably expected to exceed EPA Protective Action Guidelines exposure levels outside the Exclusion Area Boundary.

20

Enclosure 4.10 RP/O/B/1000/001 Definitions/Acronyms Page 2 of 4 1.11 HOSTAGE - A person or object held as leverage against the station to ensure demands will be met by the station.

1.12 INTRUSION/INTRUDER - Suspected hostile individual present in a ProtectedArea without authorization.

1.13 INABILITY TO DIRECTLY MONITOR - Operational Aid Computer data points are unavailable or gauges/panel indications are NOT readily available to the operator.

1.14 LOSS OF POWER - Emergency Action Levels (EALs) apply to the ability of electrical energy to perform its intended function, reach its intended equipment. Ex. - If both MFBs, are energized but all 4160v switchgear is not available, the electrical energy can not reach the motors intended. The result to the plant is the same as if both MIFBs were de-energized.

1.15 PROTECTED AREA - Encompasses all Owner Controlled Areas within the security perimeter fence.

1.16 REACTOR COOLANT SYSTEM (RCS) LEAKAGE - RCS Operational Leakage as defined in the Technical Specification Basis B 3.4.13:

RCS leakage includes leakage from connected systems up to and including the second normally closed valve for systems which do not penetrate containment and the outermost isolation valve for systems which penetrate containment.

A. Identified LEAKAGE LEAKAGE to the containment from specifically known and located sources, but does not include pressure boundary LEAKAGE or controlled reactor coolant pump (RCP) seal leakoff (a normal function not considered LEAKAGE).

LEAKAGE, such as that from pump seals, gaskets, or valve packing (except RCP seal water injection or leakoff), that is captured and conducted to collection systems or a sump or collecting tank; LEAKAGE through a steam generator (SG) to the Secondary System- Primary to secondary LEAKAGE must be included in the total calculated for identified LEAKAGE.

B. Unidentified LEAKAGE All LEAKAGE (except RCP seal water injection or leakoff) that is not identified LEAKAGE.

C. Pressure Boundary LEAKAGE LEAKAGE (except SG LEAKAGE) through a nonisolable fault in an RCS component body, pipe wall, or vessel wall.

1.17 RUPTURED (As relates to Steam Generator) - Existence of Primary to Secondary leakage of a magnitude sufficient to require or cause a reactor trip and safety injection.

1.18 SABOTAGE - Deliberate damage, mis-alignment, or mis-operation of plant equipment with the intent to render the equipment unavailable.

21

Enclosure 4.10 RP/O/B/1000/001 Definitions/Acronyms Page 3 of 4 1.19 SAFETY-RELATED SYSTEMS AREA - Any area within the Protectedarea which contains equipment, systems, components, or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation.

1.20 SIGNIFICANT PLANT TRANSIENT - An unplannedevent involving one or more of the following:

(1) Automatic turbine runback>25% thermal reactor power (2) Electrical load rejection >25% full electrical load (3) Reactor Trip (4) Safety Injection System Activation 1.21 SITE AREA EMERGENCY - Events are in process or have occurred which involve actual or likely major failures of plant functions needed for the protection of the public. Any releases are NOT expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels outside the Exclusion Area Boundary.

1.22 SELECTED LICENSEE COMMITMENT (SLC) -Chapter 16 of the FSAR 1.23 SITE BOUNDARY - That area, including the ProtectedArea, in which DPC has the authority to control all activities including exclusion or removal of personnel and property (1 mile radius from the center of Unit 2).

1.24 TOXIC GAS - A gas that is dangerous to life or health by reason of inhalation or skin contact (e.g.; Chlorine).

1.25 UNCONTROLLED - Event is not the result of planned actions by the plant staff.

1.26 UNPLANNED - An event or action is UNPLANNED if it is not the expected result of normal operations, testing, or maintenance. Events that result in corrective or mitigative actions being taken in accordance with abnormal or emergency procedures are UNPLANNED.

1.27 UNUSUAL EVENT - Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.

1.28 VALID - An indication or report or condition is considered to be VALID when it is conclusively verified by: (1) an instrument channel check; or, (2) indications on related or redundant instrumentation; or, (3) by direct observation by plant personnel such that doubt related to the instrument's operability, the condition's existence, or the report's accuracy is removed. Implicit with this definition is the need for timely assessment.

1.29 VIOLENT - Force has been used in an attempt to injure site personnel or damage plant property.

22

Enclosure 4.10 RP/O/B/1000/001 Definitions/Acronyms Page 4 of 4 1.30 VISIBLE DAMAGE -Damage to equipment or structure that is readily observable without measurements, testing, or analyses. Damage is sufficient to cause concern regarding the continued operability or reliability of affected safety structure, system, or component.

Example damage: deformation due to heat or impact, denting, penetration, rupture.

23

Enclosure 4.11 RP/0/B/1000/001 Operating Modes Defined In Improved Page 1 of 1 Technical Specifications MODES REACTIVITY  % RATED AVERAGE CONDITION THERMAL REACTOR COOLANT MODE TITLE POWER (a) TEMPERATURE (Keff) (OF) 1 Power Operation >0.99 >5 NA 2 Startup >0.99 <5 NA 3 Hot Standby <0.99 NA >250 4 Hot Shutdown (b) < 0.99 NA 250 > T > 200 5 Cold Shutdown (b) < 0.99 NA < 200 6 Refueling (c) NA NA NA (a) Excluding decay heat.

(b) All reactor vessel head closure bolts fully tensioned.

(c) One or more reactor vessel head closure bolts less than fully tensioned.

24

Enclosure 4.12 RP/0/B/1000/001 Instructions For Using Enclosure 4.1 Page 1 of 2

1. Instructions For Using Enclosure 4.1 - Fission Product Barrier Matrix 1.1 If the unit was at Hot S/D or above, (Modes 1, 2, 3, or 4) and one or more fission product barriers have been affected, refer to Enclosure 4.1, (Fission Product Barrier Matrix) and review the criteria listed to determine if the event should be classified.

1.1.1 For each Fission Product Barrier, review the associated EALs to determine if there is a Loss or Potential Loss of that barrier. Circle any that apply.

NOTE: An event with multiple events could occur which would result in the conclusion that exceeding the loss or potential loss thresholds is imminent (i.e. within 1-3 hours). In this situation, use judgement and classify as if the thresholds are exceeded.

1.2 Three possible outcomes exist for each barrier. No challenge, potential loss, or loss.

Use the worst case for each barrier and the classification table at the bottom of the page to determine appropriate classification.

1.3 The numbers in parentheses out beside the label for each column can be used to assist in determining the classification. If no EAL is met for a given barrier, that barrier will have 0 points. The points for the columns are as follows:

Barrier Failure Points RCS Potential Loss 4 Loss 5 Fuel Clad Potential Loss 4 Loss 5 Containment Potential Loss 1 Loss 3 1.3.1 To determine the classification, add the highest point value for each barrier to determine a total for all barriers. Compare this total point value with the numbers in parentheses beside each classification to see which one applies.

1.3.2 Finally as a verification of your decision, look below the Emergency Classification you selected. The loss and/or potential loss EALs selected for each barrier should be described by one of the bullet statements.

<-I 25

Enclosure 4.12 RP/0/B/1000/001 Instructions For Using Enclosure 4.1 Page 2 of 2 EXAMPLE: Failure to properly isolate a 'B' MS Line Rupture outside containment, results in extremely severe overcooling.

PTS entry conditions were satisfied.

Stresses on the 'B' SIG resulted in failure of multiple SIG tubes.

RCS leakage through the S/G exceeds available makeup capacity as indicated by loss of subcooling margin.

Barrier EAL Failure Points RCS SGTR > Makeup capacity of one HPI pump in Potential Loss 4 normal makeup mode with letdown isolated Entry into PTS operating range Potential Loss 4 RCS leak rate > available makeup capacity as Loss 5 indicated by a loss of subcooling Fuel Clad No EALs met and no justification for No 0 classification on judgment Challenge Containment Failure of secondary side of SG results in a Loss 3 direct opening to the environment RCS 5 + Fuel 0 + Containment 3 = Total 8 A. Even though two Potential Loss EALs and one Loss EAL are met for the RCS barrier, credit is only taken for the worst case (highest point value) EAL, so the points from this barrier equal 5.

B. No EAL is satisfied for the Fuel Clad Barrier so the points for this barrier equal 0.

C. One Loss EAL is met for the Containment Barrier so the points for this barrier equal 3.

D. When the total points are calculated the result is 8, therefore the classification would be a Site Area Emergency.

E. Look in the box below "Site Area Emergency". You have identified a loss of two barriers. This agrees with one of the bullet statements.

The classification is correct.

26

- D V03"4-0) Duke Power Company (1)IDNo. RP/OiB1I000/003A INFORMATION PROCEDURE PROCESS RECORD Revision No. 006 (2"ýARATION

/ONLY (2) Station OCONEE NUCLEAR STATION (3) Procedure Title Procedure for ERDS Operation (4) Prepared By Ray Waterman (Signature) . Date 01/13/03 (5) Requires NSD228 Applicability Determination? 6(

0 Yes (New procedure or revision with major changes)

[] No (Revision with minor changes)

EJ No- (To incorporate previously approved changes)

(6) ReviewedBy " .. A 2?Zc t (QR) Date /-/ 0-O3 Cross-Disciplinary Review By (QR)NA Z ate I- 0(-3 Reactivity Mgmt Review By .(QR)NA Date 1- / 6--'2 Mgmt Involvement Review By (Ops Supt) NA Date (7) Additional Reviews Reviewed By Date Reviewed By Date (8) Temporary Approval (ffnecessary)

By .(OSM!QR) Date "_

By (QR) Date (9) Approved By Lill,) 9-W , Date otI ,.ZLLLL PERFORMANCE (Compare with controlcopy every 14 calendardays while work is beingperformed.)

(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (11) Date(s) Performed Work Order Number (WO#)

COMPLETION (12) Procedure Completion Verification:

0 Unit 0 0 Unit 1 0 Unit 2 0 Unit 3 Procedure performed on what unit?

0 Yes El NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?

13 Yes El NA Required enclosures attached?

0 Yes NA Data sheets attached, completed, dated, and signed?

N

-I Yes 1l NA Charts, graphs, etc. attached, dated, identified, and marked?

El Yes 0 NA Procedure requirements met?

Verified By Date Procedure Completion Approved Date (14) Remarks (Atach additionalpages)

Duke Power Company Procedure No.

Oconee Nuclear Site RP/O/B/1000/003A Revision No.

ERDS Operation 006 Electronic Reference No.

Reference Use OXOO2WOV

RPI/O/B1 000/003A Page 2 of 11 ERDS Operation NOTE: This procedure is an implementing procedure to the Oconee Nuclear Site Emergency Plan and must be forwarded to Emergency Planning within seven (7) worlkng days of approval.

1. Symptoms An Alert, Site Area Emergency, or General Emergency has been declared and ERDS is required to provide data to the NRC. ERDS is to be started within one (1) hour of the emergency declaration.

2. Immediate Actions NOTE: Lines left of procedure steps are used to indicate place in the procedure. Check marks are acceptable in these blanks.

2.1 Determine which unit is affected and start the applicable ERDS computer.

S2.1.1 ERDS Operation Started By:

2.1.2 IF Unit 1 ERDS Computer is required to be started, THEN GOTO Step 3.1.

2.1.3 IF Unit 2 ERDS Computer is required to be started, THEN GOTO Step 3.2.

2.1.4 IF Unit 3 ERDS Computer is required to be started, THEN GOTO Step 3.3.

2.1.5 IF Multiple unit ERDS Computers are required to be started, THEN Refer to the steps identified above for the affected unit(s).

RP/O/B/1000/003A Page 3 of 11

3. Subsequent Actions 3.1 Unit 1 ERDS Operation NOTE: 9 Computers in the TSC and OAC room (located outside Unit 1&2 CR) can be used to activate ERDS.

0 ERDS can only be activated by an SRO or the NRC TSC Communicator. These individuals must change the Security Level for the computer. (Step 3.1.4) 3.1.1 IF The computer was logged onto the network, THEN GOTO Step 3.1.3.

3.1.2 IF The computer and CRT are OFF, THEN Turn the computer and CRT ON by depressing the white power switch.

3.1.3 Click on Unit 1 ERDS Activation Icon NOTE: SDS Security Levels can only be changed with computers assigned access to the USER ID and PASSWORD listed below.

3.1.4 Type CSL in the Turn-on Code Area, OR select Change Security Level (first option) from the pull-down Main Menu and the Admin Menu options list

__A. Select the Change Security Level button.

B. Select the OK button.

__C. Enter the applicable USER ID and PASSWORD:

USER ID PASSWORD ERDS ERDSADM 3.1.5 Verify that the Unit 1 OAC MMI (Operational Aid Computer Man Machine Interface) is selected by ensuring that the bottom right hand corner of the display indicates Oconee 1.

3.1.6 Type ERDS in the Turn-On Code Area, OR select the ERDS Display from the OAC MMlI by selecting ERDS from the pull-down Main Menu and the General Sub-Menu.

RP /OJIBI1OOO/OO3A Page 4 of 11 3.1.7 Verify that the ERDS display, under the STATUS column, indicates the following:

MODEM Disconnected ERDS COMPUTER Terminated COMMUNICATOR TASK Inactive NOTE: Status Column will display: Connect - Connected - Transmitting 3.1.8 Select the ACTIVATE Target Area with the mouse, OR press the F1 Keyboard Key to initiate ERDS transmission from the OAC MMI.

A. Record the Date and Time Unit 1 ERDS transmission was initiated below:

Date Time Initials 3.1.9 Verify that the Communication Task status, under the STATUS column, displays the following: LINK REQUESTED.

3.1.10 Verify that the ERDS Computer status, under the STATUS column, displays the following: ACCEPTED.

3.1.11 IF ERDS does not connect with the NRC after five attempts, THEN Notify the NRC using the ENS Phone Line.

A. Record the Date and Time of this notification.

Date Time Initials 3.1.12 IF Instructed by the NRC to restart ERDS transmission, THEN Select the RECONNECT Target Area with the mouse, OR press the F3 Keyboard Key to reconnect ERDS to the NRC from the OAC MMI.

A. Record the Date and Time Unit 1 ERDS transmission was reconnected below:

Date Time Initials 3.1.13 IF Multiple ERDS Computers are required to be started, THEN GOTO Step 2.1.5 of this procedure.

3.1.14 IF Muliple ERDS Computers are not required to be started, THEN GOTO Step 3.4 of this procedure.

RP/O/B/1000/003A Page 5 of 11 3.2 Unit 2 ERDS Operation NOTE: Computers in the TSC and OAC room (located outside Unit 1&2 CR) can be used to activate ERDS.

ERDS can only be activated by an SRO or the NRC TSC Communicator. These individuals must change the Security Level for the computer. (Step 3.2.4) 3.2.1 IF The computer was logged onto the network, THEN GOTO Step 3.2.3.

3.2.2 IF The computer and CRT are OFF, THEN Turn the computer and CRT ON by depressing the white power switch.

3.2.3 Click on Unit 2 ERDS Activation Icon NOTE: SDS Security Levels can only be changed with computers assigned access to the USER ID and PASSWORD listed below.

3.2.4 Type CSL in the Turn-On Code Area, OR select Change Security Level (first option) from the pull down Main Menu and the Admin Menu options list.

A. Select the Change Security Level button B. Select the OK Button C. Enter the applicable USER ID and PASSWORD:

USER ID PASSWORD ERDS ERDSADM 3.2.5 Verify that the Unit 2 OAC MMI (Operational Aid Computer Man Machine Interface) is selected by ensuring that the bottom right hand corner of the display indicates Oconee 2.

3.2.6 Type ERDS in the Turn-On Code Area, OR select the ERDS Display, from the OAC MMI, by selecting ERDS from the pull-down Main Menu and the General Sub-Menu.

RP/0/B/1000/003A Page 6 of 11 3.2.7 Verify that the ERDS display, under the STATUS column, indicates the following:

MODEM Disconnected ERDS COMPUTER Terminated COMMUNICATOR TASK Inactive NOTE: Status Column will display: Connect - Connected - Transmitting 3.2.8 Select the ACTIVATE Target Area with the mouse, OR press the Fl Keyboard Key to initiate ERDS transmission from the OAC MMI.

A. Record the Date and Time Unit 2 ERDS transmission was initiated below:

Date Time Initials 3.2.9 Verify that the Communication Task status, under the STATUS column, displays the following: LINK REQUESTED.

3.2.10 Verify that the ERDS Computer status, under the STATUS column, displays the following: ACCEPTED.

3.2.11 IF ERDS does not connect with the NRC after five attempts, THEN Notify the NRC using the ENS phone line.

A. Record the Date and Time of this notification.

Date Time Initials 3.2.12 IF Instructed by the NRC to restart ERDS transmission, THEN Select the RECONNECT Target Area with the mouse, OR press the F3 Keyboard Key to reconnect ERDS to the NRC from the OAC MMI.

A. Record the Date and Time Unit 1 ERDS transmission was reconnected below:

Date Time Initials 3.2.13 IF Multiple ERDS Computers are required to be started, THEN GOTO Step 2.1.5 of this procedure.

3.2.14 IF Multiple ERDS Computers are not required to be started, THEN: GOTO Step 3.5 of this procedure.

RP/O/B/1000/003A Page 7 of 11 3.3 Unit 3 ERDS Operation NOTE: Computers in the OAC room, TSC or OSC (located outside U3 CR) can be used to activate ERDS.

ERDS can only be activated by an SRO or the NRC TSC Communicator. These individuals must change the Security Level for the computer. (Step 3.3.4) 3.3.1 IF The Computer was logged onto the network, THEN GOTO Step 3.3.3.

3.3.2 IF The computer and CRT are OFF, THEN Turn the computer and CRT ON by depressing the white power switch.

3.3.3 Click on Unit 3 ERDS Activation Icon.

NOTE: SDS Security Levels can only be changed with computers assigned access to the USER ID and PASSWORD listed below.

3.3.4 Type CSL in the Turn-On Code Area, OR select Change Security Level (first option) from the pull down Main Menu and the Admin Menu options list.

A. Select the Change Security Level button B. Select the OK Button C. Enter the applicable USER ID and PASSWORD:

USER ID PASSWORD ERDS ERDSADM 3.3.5 Verify that the Unit 3 OAC MMI (Operational Aid Computer Man Machine Interface) is selected by ensuring that the bottom right hand comer of the display indicates Oconee 3.

3.3.6 Type ERDS in the Turn-On Code Area, OR select the ERDS Display, from the OAC MMI by selecting ERDS from the pull-down Main Menu and the General Sub-Menu.

RP/O/B/1000/003A Page 8 of 11 3.3.7 Verify that the ERDS display, under the STATUS column, indicates the following:

MODEM Disconnected ERDS COMPUTER Terminated COMMUNICATOR TASK Inactive I NOTE: Status Column will display: Connect - Connected - Transmitting 3.3.8 Select the ACTIVATE Target Area with the mouse, OR press the Fl Keyboard Key to initiate ERDS transmission from the OAC MMI.

A. Record the Date and Time Unit 3 ERDS transmission was initiated below:

Date Time Initials 3.3.9 Verify that the Communication Task status, under the STATUS column, displays the following: LINK REQUESTED.

3.3.10 Verify that the ERDS Computer status, under the STATUS column, displays the following: ACCEPTED.

3.3.11 IF ERDS does not connect with the NRC after five attempts, THEN Notify the NRC using the ENS phone line.

A. Record the Date and Time of this notification.

Date Time Initials 3.3.12 IF Instructed by the NRC to restart ERDS transmission, THEN Select the RECONNECT Target Area with the mouse, OR press the F3 Keyboard Key to reconnect ERDS to the NRC from the OAC MMI.

A. Record the Date and Time Unit 3 ERDS transmission was reconnected below:

Date Time Initials 3.3.13 IF Multiple ERDS Computers are required to be started, THEN GOTO Step 2.1.5 of this procedure.

3.3.14 IF Multiple ERDS Computers are not required to be stared THEN GOTO Step 3.6 of this procedure.

RP/O/B/1000/003A Page 9 of 11 3.4 Stop Unit 1 ERDS data transmission after the event has terminated.

3.4.1 Reset the Security Level by performing the following steps; A. Press the Fl keyboard day to return to the Unit Overview display B. Type CSL C. Select the Change Security Level button D. Select the OK button E. Enter the applicable USER ID and PASSWORD:

USER ID PASSWORD ERDS ERDSADM 3.4.2 Select the TERMINATE Tartet Area OR the F2 Key to stop the ERDS transmission from the OAC MMI.

3.4.3 Record the Date and Time Unit 1 ERDS Computer transmission was stopped below.

Date Time 3.4.4 Close the SDS session by selecting EXIT from the pull-down Main Menu.

3.4.5 Shutdown the ERDS Computer as follows:

A. Select File from the Menu Bar B. Select Shutdown from the listed options C. Select the Shutdown button from the Pop-Up Menu D. Select the OK button NOTE: The Shutdown process must be completed before performing this step.

3.4.6 Turn the Computer OFF by pressing the power switch in.

3.4.7 Turn the CRT Monitor OFF by pressing the power switch in.

RPIO/B/1000/003A Page 10 of 11 3.5 Stop Unit 2 ERDS data transmission after the event has terminated.

3.5.1 Reset the Security Level by performing the following steps; A. Press the F1 keyboard day to return to the Unit Overview display B. Type CSL C. Select the Change Security Level button D. Select the OK button E. Enter the applicable USER ID and PASSWORD:

USER ID PASSWORD ERDS ERDSADM 3.5.2 Select the TERMINATE Tartet Area OR the F2 Key to stop the ERDS transmission from the OAC MMI.

3.5.3 Record the Date and Time Unit 2 ERDS Computer transmission was stopped below.

Date Time 3.5.4 Close the SDS session by selecting EXIT from the pull-down Main Menu.

3.5.5 Shutdown the ERDS Computer as follows:

A. Select File from the Menu Bar B. Select Shutdown from the listed options C. Select the Shutdown button from the Pop-Up Menu D. Select the OK button NOTE: The Shutdown process must be completed before performing this step.

3.5.6 Turn the Computer OFF by pressing the power switch in.

3.5.7 Turn the CRT Monitor OFF by pressing the power switchown the ERDS Computer as follows:

RP/O/B/1000/003A Page 11 of 11 3.6 Stop Unit 3 ERDS data transmission after the event has terminated.

3.6.1 Reset the Security Level by performing the following steps; A. Press the F1 keyboard key to return to the Unit Overview display B. Type CSL C. Select the Change Security Level button D. Select the OK button E. Enter the applicable USER ID and PASSWORD:

USER ID PASSWORD ERDS ERDSADM 3.6.2 Select the TERMINATE Tartet Area OR the F2 Key to stop the ERDS transmission from the OAC MMI.

3.6.3 Record the Date and Time Unit 3 ERDS Computer transmission was stopped below.

Date Time 3.6.4 Close the SDS session by selecting EXIT from the pull-down Main Menu.

3.6.5 Shutdown the ERDS Computer as follows:

A. Select File from the Menu Bar B. Select Shutdown from the listed options C. Select the Shutdown button from the Pop-Up Menu D. Select the OK button NOTE: The Shutdown process must be completed before performing this step.

3.6.6 Turn the Computer OFF by pressing the power switch in.

3.6.7 Turn the CRT Monitor OFF by pressing the power switch in

INFRMATION MCIPD_713 aR04-01)

PROCEDURE Duke Power Company PROCESS RECORD (1 IDNo RPIOJBI10001019 ReisionNo. 013 ONLY PARATION Station OCONEE NUCLEAR STATION (3) Procedure Title Technical Support Center Emergency Coordinator Procedure (4) Prepared By Ray Waterman (Signature)

• Date 01/21/03 (5) Requires NSD 228 Applicability Determination?0 E] Yes (New procedure or revision with major changes)

[ No (Revision with minor changes) 0 No (To incorporate previously approved changes)

(6) Reviewed By W. R 3 -1 .- (QR) Date 1/-29-03 Cross-Disciplinary Review By (QR)NAtf 7-_Date 2- 0'-)o Reactivity Mgmt Review By (QR)NA NO/OPDate 1--29-03 Mgmt Involvement Review By (Ops Supt) NA Date (7) Additional Reviews Reviewed By Date Reviewed By Date (8) Temporary Approval (if necessary)

By (OSM/QR) Date By QR) Date (9) Approved By 9L 3 gt.ir- Date PERFORMANCE (Compare with control copy every 14 calendardays while work is beingperformed.)

(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy_ Date (11) Date(s) Performed Work Order Number (WO#)

COMPLETION (12) Procedure Completion Verification:

o Unit 0 0 Unit 1 0 Unit 2 0 Unit 3 Procedure performed on what unit?

o Yes 0 NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?

0 Yes 01 NA Required enclosures attached?

o Yes D NA Data sheets attached, completed, dated, and signed?

01 Yes 03 NA Charts, graphs, etc. attached, dated, identified, and marked?

03 Yes El NA Procedure requirements met?

Verified By Date "1 ' Procedure Completion Approved Date

, Remarks (Attach additionalpages)

Duke Power Company Procedure No.

Oconee Nuclear Station RP/0/B/1000/019 Revision No.

Technical Support Center Emergency Coordinator 013 Procedure Electronic Reference No.

Reference Use OX002WPG

RP/O/BI1000/019 Page 2 of 21 Technical Support Center Emergency Coordinator Procedure NOTE: This procedure is an implementing procedure to the Oconee Nuclear Site Emergency Plan and must be forwarded to Emergency Planning within seven (7) working days of approval.

1. Symptoms 1.1 Conditions exist where events are in progress or have occurred which indicate a potential degradation in the level of safety of the plant and activation of the Emergency Response Organization has been initiated.

2. Immediate Actions NOTE: 9 Enclosure 4.2 contains listing of abbreviations/acronyms.

"* Actions in Sections 2.0 and 3.0 are NOT required to be followed in any particular sequence.

"* Place keeping aids: Li at left of steps may be used for procedure place keeping (2I).

Major events are required to be documented in the TSC Emergency Coordinator Log.

0i 2.1 Establish the Technical Support Center as operational by doing the following:

Li 2.1.1 Use the attached Enclosure 4.3, (TSC Personnel Log Sheets) for sign-in by all personnel reporting to the TSC. Assign responsibility to the TSC Log Keeper.

0i 2.1.2 Ensure Names are also listed on the TSC Personnel Status Board in the TSC NOTE: The TSC must assume turnover from the Control Room within 75 minutes of the initiating Emergency Classification time.

Li 2.1.3 Determine the following minimum staff requirements for TSC activation.

NAME Emergency Coordinator Dose Assessment Liaison Nuclear Engineering Offsite Communicator Tech Assistant to EC

RP/0/B/1000/019 Page 3 of 21

[] 2.1.4 Verify that the phone system is operational or make other provisions for communications.

El 2.1.5 Verify that the OSC is Operational.

El 2.1.6 Verify that a log of TSC actions and activities has been started.

El 2.1.7 IF Activation of the Alternate TSC is required prior to completion of turnover with the OSM.

THEN REFER TO Step 1.0 of Enclosure 4.6, (Alternate TSC/OSC Activation).

0l 2.2 Receive turnover from the Operations Shift Manager using Enclosure 4.1, (Operations Shift Manager To TSC Emergency Coordinator Turnover Sheet)

TSC and OSC Activated Time 0l 2.3 Determine the status of Site Accountability from the TSC Offsite Communicator.

El 2.3.1 Request the TSC/OSC Liaison to have a Search & Rescue Team dispatched from the OSC if personnel within the Protected Area have not been accounted for by their group.

0l 2.4 Verify that the electronic status board is set up and that someone is available to maintain it.

0l 2.5 Discuss any off-site radiological concerns with the TSC Dose Assessment Liaison.

RP/O/B/1000/019 Page 4 of 21 0l 2.6 Activate the TSC/OSC Public Address (PA) System {7}

0l 2.6.1 Flip the power switch UP on the PA system amplifier located inside the communications cabinet.

0l 2.6.2 Depress the microphone switch and hold in position while making PA announcements.

El 2.6.3 Announce the following information over the TSC/OSC PA System:

El A. The current Emergency Classification level and plant status.

El B. TSC/OSC activation time {7}

El C. "Anyone who has consumed alcohol within the past five (5) hours notify either the Emergency Coordinator in the TSC or the OSC Manager in the OSC."

"ElD. "Personnel should assume that areas are contaminated until surveyed by "ElE. "No eating or drinking, until the TSC and OSC are cleared by RP."

RP/OJB0/1000/019 Page 5 of 21 0] 2.7 Turn office page over ride switch ON, and dial 70 on the Emergency Coordinator's phone.

2.7.1 Announce the following information over the Plant Public Address System:

Drill Message:

Attention all site personnel. This is I am the Emergency Coordinator.

(name)

This is a drill. This is a drill.

You have been assembled as a part of an emergency exercise. The simulated emergency conditions are If this were a real emergency, you would be asked to remain assembled waiting on further information, or given instructions to leave the site in accordance with our site evacuation plan. At this time, however, we will continue with the emergency exercise and you may now return to your normal work assignments. I repeat.... you may now return to your normal work assignments.

Thank you for your participation.

Emergency Message:

Attention all site personnel. This is I am the Emergency Coordinator.

(name)

This is an emergency message.

At the present time we have a(n) emergency classification. The plant status is as follows Please remain at your site assembly location until you receive further instructions.

Information will be provided to you as conditions change.

RP/O/B/10001019 Page 6 of 21 0 2.8 Contact the State Director Emergency Planning at the SEOC.

NAME TELEPHONE NUMBERS SDEP 1(803) 737-8500 2.8.1 Inform the TSC Offsite Communicator whenever the SEOC is activated.

2.8.2 IF The SEOC has not been activated, THEN Contact the County Directors of Emergency Planning (CDEP) to discuss plant status.

Oconee CDEP 1(864) 638-4200 Pickens CDEP 1(864) 898-5943 0] 2.9 Perform the following concurrently.

"* Use Step 2.10 for emergency classification.

"* Use Step 2.11 for turnover to the EOF Director.

"* Use steps in 3.0 for tasks that must continue regardless of emergency classification.

(Step 2.10 on next page)

RP/O/B/1000/019 Page 7 of 21 El 2.10 Review emergency classification and verify that it meets the criteria of RP/O/B/1000/001 (Emergency Classification).

"* Discuss changing plant conditions with the Superintendent of Operations.

"* Discuss emergency classification prior to making recommendations.

El 2.10.1 IF An Unusual Event Classification exists, THEN Initiate the following actions:

El A. Notify counties/state within 15 minutes of event classification.

NOTE:

• Remind the TSC NRC Communicator to complete the NRC Event Notification Worksheet and Plant Status Sheet prior to contacting the NRC.

• NRC should be notified immediately after notification of Offsite Agencies but NOT later than one (1) hour after declaration of the emergency.

El B. Notify NRC of event classification NOTE: Condition B for Keowee Hydro Project Dams/Dikes also requires notification of the Georgia Emergency Management Agency and National weather service. Remind the TSC Offsite Communicator to notify these agencies in addition to and after SC State, Oconee County, and Pickens County.

ElC. IF Condition B at Keowee exists, THEN Notify Hydro Central (refer to Section 6 of the Emergency Telephone Directory, Keowee Hydro Project Danm/Dike Notification). {4}

El D. Discuss classification with SDEP and CDEP NAME TELEPHONE NUMBERS SDEP 1(803) 737-8500 Oconee CDEP 1(864) 638-4200 Pickens CDEP 1(864) 898-5943 (Unusual Event Classification guidance continued on next page)

RP/O/B/1000/019 Page 8 of 21 5 E. IF An Unusual Event classification is being terminated THEN REFER TO Enclosure 4.5, (Emergency Classification Termination Criteria) of this procedure for termination guidance.

NOTE: The EP Section shall develop a written report, for signature by Site Vice President, to the State Emergency Preparedness Agency, Oconee County EPD, and Pickens County EPD within 24 working hours of the event termination.

El 1. Notify Emergency Planning that the Unusual Event has been terminated.

5 2. Emergency Planning shall hold a critique following termination of the Unusual Event.

(Step 2.10.2, Alert Classification on next page)

RP/O/B/1000/019 Page 9 of 21 0 2.10.2 IF An Alert Classification exists, THEN Initiate the following actions:

"ElA. Notify counties/state within 15 minutes of event classification "ElB. Follow Up Notifications (updates) are required a minimum of every 60 minutes

• Significant changes in plant status should be communicated to offsite agencies as they occur "ElC. Notify NRC of change in classification

"[1D. Start ERDS (TSC NRC Communicator - RP/O/B/1000/003A, ERDS Operation)

"ElE. Discuss change in classification with the State Director of Emergency Preparedness (SDEP) and County Directors of Emergency Preparedness (CDEP)

NAME TELEPHONE NUMBERS SDEP 1(803) 737-8500

1. IF The SEOC has not been activated, THEN Contact the CDEP to discuss plant status.

Oconee CDEP 1(864) 638-4200 Pickens CDEP 1(864) 898-5943 NOTE: Condition B for Keowee Hydro Project Dams/Dikes also requires notification of the Georgia Emergency Management Agency and National Weather Service. Remind the TSC Offsite Communicator to notify these agencies in addition to and after SC State, Oconee County, and Pickens County. {2}

5 F. IF Condition B at Keowee exists, THEN Notify Hydro Central (refer to Section 6 of the Emergency Telephone Directory, Keowee Hydro Project Dam/Dike Notification). {4}

(Step 2.10.3, Site Area Emergency Classification on next page)

RP/O/B/1000/019 Page 10 of 21 El 2.10.3 IF A Site Area Emergency Classification exists, THEN Initiate the following actions:

0 A. Notify counties/state within 15 minutes of event classification El B. IF Condition A, Dam Failure (Keowee or Jocassee) exists, THEN Make the following protective action recommendations to Oconee County and Pickens County for imminent/actual dam failure and include on the Emergency Notification Form under Section 15 (B) and (D):

1. Move residents living downstream of the Keowee Hydro Project dams to higher ground.

2. Prohibit traffic flow across bridges identified on your inundation maps until the danger has passed.

0] C. Follow Up Notifications (updates) are required a minimum of every 60 minutes

1. Significant changes in plant status should be communicated to offsite agencies as they occur 0 D. Notify NRC of change in classification 0 E. Start ERDS (TSC NRC Communicator - RP/O/B/1000/003A, ERDS Operation)

El F. Discuss change in classification with SDEP and CDEP NAME TELEPHONE NUMBERS SDEP 1(803) 737-8500

1. IF The SEOC has not been activated, THEN Contact the CDEP to discuss plant status.

Oconee CDEP 1(864) 638-4200 Pickens CDEP _1(864) 898-5943 0] G. IF Condition A, Dam Failure (Keowee or Jocassee) exists, THEN REFER TO Step 3.1.

RP/OJB/10001019 Page 11 of 21 NOTE: Condition B for Keowee Hydro Project Dams/Dikes also requires notification of the Georgia Emergency Management Agency and National Weather Service. Remind the TSC Offsite Communicator to notify these agencies in addition to and after SC State, Oconee County, and Pickens County. {2}

0-H. IF Condition B at Keowee exists, THEN Notify Hydro Central (refer to Section 6 of the Emergency Telephone Directory, Keowee Hydro Project Dam/Dike Notification). {4}

(Step 2.10.4, General Emergency Classification, on next page)

RP/0/B/1000/019 Page 12 of 21 2.10.4 IF A General Emergency Classification exists, THEN Initiate the following actions:

Ol A. Evacuate 2 mile radius and 5 miles downwind unless conditions make evacuation dangerous. Shelter all sectors not evacuated. Request the TSC Dose Assessment Liaison to determine the actual sectors affected.

El B. IF Condition A, Dam Failure (Keowee or Jocassee) exists, THEN Make the following protective action recommendations to Oconee County and Pickens County for imminent/actual dam failure and include on the Emergency Notification Form under Section 15B and D:

1. Move residents living downstream of the Keowee Hydro Project dams to higher ground.

2. Prohibit traffic flow across bridges identified on your inundation maps until the danger has passed.

El C. Notify counties/state within 15 minutes of event classification El D. Follow Up Notifications (updates) are required a minimum of every 60 minutes

1. Significant changes in plant status should be communicated to offsite agencies as they occur El E. Notify NRC of change in classification El F. Start ERDS (TSC NRC Communicator - RP/0IB/1000/003A, ERDS Operation)

El G. Discuss change in classification and Protective Action Recommendations with SDEP and/or CDEP. Provide any known information concerning conditions that would make evacuation dangerous.

NAME TELEPHONE NUMBERS SDEP 1(803) 737-8500

1. IF The SEOC has not been activated, THEN Contact the CDEP to discuss plant status.

Oconee CDEP 1(864) 638-4200 Pickens CDEP P1(864) 898-5943

RP/O/B/1000/019 Page 13 of 21 El H. IF Condition A, Dam Failure (Keowee or Jocassee) exists, THEN REFER TO Step 3.1.

NOTE: Condition B for Keowee Hydro Project Dams/Dikes also requires notification of the Georgia Emergency Management Agency and National Weather Service. Remind the TSC Offsite Communicator to notify these agencies in addition to and after SC State, Oconee County, and Pickens County. {2}

0I. IF Condition B at Keowee exists, THEN Notify Hydro Central (refer to Section 6 of the Emergency Telephone Directory, Keowee Hydro Project Dam/Dike Notification). {4}

(Step 2.11 on next page)

RP/O/B/1000/019 Page 14 of 21 0l 2.11 When notified by the EOF Director that the Emergency Operations Facility (EOF) is operational, notify the following TSC personnel to exchange information with their counterpart in the EOF.

TSC Dose Assessment Liaison TSC Offsite Communicator Control Room/EOF Liaison (Operations Network)

NOTE: EOF Director will notify the Emergency Coordinator when the information has been received and establish a time for turnover. Turnover should be initiated as soon as possible. A goal of 30 minutes should be used to complete turnover after the EOF is declared Operational. {1}

El 2.11.1 Obtain the current copy of the Emergency Notification Form and plant status.

The EOF Director shall provide to the Emergency Coordinator the information he has been provided with in the following areas:

"* Present Emergency Classification Time Initial Emergency Classification Time

"* Initiating Condition/Unit affected 0 Present status of affected unit(s), including significant equipment out of service Improving Stable - Degrading -

"* Status of unaffected unit(s):

Unit 1 shutdown at or at  % power Unit 2 shutdown at or at  % power Unit 3 shutdown at or at  % power

"* Emergency Releases: NO YES {7}

Airborne __- Liquid _ Is occurring _ Has occurred Time Normal Operating Limits: Below _ Above Protective Action Recommendations

"* Site Evacuation NO _ YES _ If yes, location Time of evacuation a Last Message Number LNNext Message due at

RP/O/B/1000/019 Page 15 of 21 El 2.11.2 Emergency Coordinator turnover to EOF Director complete.

EOF Activated Time El 2.11.3 Request NRC Communicator to notify the NRC EOC that the EOF is activated.

El 2.11.4 Make announcement to TSC/OSC that EOF is activated. {6 }

3. Subsequent Actions 3.1 IF Condition A, Dam Failure (Keowee or Jocassee) exists, THEN Perform the following actions:

0l 3.1.1 Notify Hydro Central and provide information related to the event. Refer to Section 6 of the Emergency Telephone Directory. {4}

El 3.1.2 Relocate Keowee personnel to the Operational Support Center if events occur where their safety could be affected.

El 3.1.3 Notify Hydro Central if Keowee personnel are relocated to the OSC. {4}

NOTE: A loss of offsite communications capabilities (Selective Signaling and the WAN) could K..- occur within 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after Keowee Hydro Dam failure. Rerouting of the Fiber Optic Network through Bad Creek should be started AS SOON AS POSSIBLE.

El 3.1.4 IF The EOF is NOT activated, THEN Notify Telecommunications Group in Charlotte to begin rerouting the Oconee Fiber Optic Network. Refer to Selective Signaling Section of the Emergency Telephone Directory (page 9).

El 3.1.5 Notify Security to alert personnel at the Security Track/Firing Range and Warehouse #5 to relocate to work areas inside the plant.

El 3.1.6 Relocate personnel at the following locations to the World of Energy/Operations Training Center:

NOTE: Plant access road to the Oconee Complex could be impassable within 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> if the Keowee Hydro Dam fails. A loss of the Little River Dam or Dikes A-D will take longer to affect this road.

Oconee Complex Oconee Garage Oconee Maintenance Training Facility

RP/O/B/1000/019 Page 16 of 21 El 3.1.7 Ensure Operations has dispatched operators to the SSF and established communications.

El 3.2 Periodically evaluate with TSC personnel the need to conduct evacuation. Log the status of this action on the TSC Status Board.

NOTE:

• Twenty-four (24) hour staffing must be accomplished prior to personnel being evacuated from the site. RP/O/B/I000/0 10, (Procedure for Emergency Evacuation/Relocation of Site Personnel).

0 Determine if personnel with special radiological exposure limits need to be evacuated (e.g.; declared pregnant women, personnel with radio-pharmaceutical limitations).

3.2.1 Consider the following for making Site Evacuation decisions:

"* Alert - determined by actual plant conditions

"* Site Area Emergency - consider evacuation/relocation of non-essential site personnel. World of Energy personnel should be evacuated at the same time as non essential personnel.

• General Emergency - evacuate all non-essential personnel. Notify the EOF Director to evacuate the World of Energy.

• Notify the EOF anytime personnel are relocated on site or evacuated from the site.

RP/O/B/IO00If19 Page 17 of 21 WARNING: Use of the Outside Air Booster Fans during a Security Event may introduce incapacitating agents into the Control Room. {5)

El 3.3 Periodically evaluate the need to operate the outside air booster fans (Control Room Pressurization and Filter System - CRVS) with TSC personnel. Log status of this system on the TSC Status Board.

NOTE: 9 Outside air booster fans are used to provide positive pressure in the Control Room/TSC/OSC to prevent smoke, toxic gas, or radioactivity from entering the area as required by NUREG 0737, Control Room Habitability.

• Chlorine Monitor Alarm will either stop the outside air booster fans OR will not allow them to start.

El 3.3.1 IF Smoke/toxic gas in the Turbine Building or Auxiliary Building is expected to reach the Control Room, THEN Instruct the Control Room to turn ON the outside air booster fans.

Fans On Time "El A. Request OSC to verify operability of the Control Room Ventilation System per AP/1,3/A/1700/018, (Abnormal Release of Radioactivity).

3.3.2 IF RIA-39 is in Alarm THEN Verify that the Control Room has turned on the outside air booster fans.

"ElA. Request OSC to verify operability of the Control Room Ventilation System per AP/1,3/A/1700/018, (Abnormal Release of Radioactivity).

"ElB. Request backup air sample from the OSC to verify RIA alarm El C. IF Air sample determines that RIA-39 alarm is not valid, THEN Secure outside air booster fans.

RP/0/B/1000/019 Page 18 of 21

[0 D. IF Air sample determines that RIA-39 alarm is valid, THEN Isolate the source of airborne contamination to the Control Room/TSC/OSC El E. IF Dose levels in the Control Room/TSC/OSC are being increased by the addition of outside filtered air, THEN Secure outside air booster fans.

Fans Off Time 0l 3.4 Periodically evaluate the need to activate the Alternate TSC and/or OSC.

3.4.1 IF Activation of the Alternate TSC and/or OSC is required, THEN REFER TO Step 2.0 of Enclosure 4.6, (Alternate TSC/OSC Activation).

3.4.2 Notify the EOF Director once relocation to the Alternate TSC is completed.

NOTE: The NRC will send a response team to the site at a Site Area or General Emergency Classification.

El 3.5 IF An NRC team is enroute, THEN Perform the following steps:

El 3.5.1 Notify Alternate Emergency Coordinator to report to the TSC for an update on plant conditions.

A. Record Alternate Emergency Coordinator's name on Enclosure 4.4 (NRC Site Team Response Form).

B. Brief Alternate Emergency Coordinator on current plant conditions.

El 3.5.2 Provide Enclosure 4.4 (NRC Site Team Response Form), to the TSC NRC Communicator.

A. Instruct TSC NRC Communicator to complete Steps 1.2 - 1.5 of Enclosure 4.4 (NRC Site Team Response Form).

El 3.5.3 Notify OSC Manager and request RP Manager and Security to implement actions required to process NRC Site Team.

RP/0B/1000/019 Page 19 of 21 0 3.6 Provide periodic updates to the EOFD concerning plant status. Request the EOFD to provide dose assessment and field monitoring data to the TSC on a periodic basis.

3.6.1 IF Failed Fuel Condition Three (3) has been determined, THEN Immediately notify the EOFD.

A. Failed Fuel Condition Three (3) requires additional Protective Action Recommendations.

0l 3.7 Authorize exposure greater than normal operating limits for planned equipment repair missions and/or emergency lifesaving missions.

3.7.1 Approval may be either verbal or written.

3.7.2 This authority may be delegated to the RP Manager in the OSC.

El 3.8 Update TSC and OSC personnel approximately every 30 minutes on the Emergency Classification and plant status via the TSC/OSC public address system. (Timer is available in the Emergency Procedures Cart)

El 3.9 Establish twenty-four (24) hour staffing and have the Managers prepare as needed.

3.9.1 TSC Personnel Log Sheets (Enclosure 4.3) are to be used for this purpose.

NOTE: Long term use of the SFP as a makeup source will deplete the SFP inventory.

Engineering has evaluated and approved the following method for refilling of the SFP with filtered lake water.

El 3.10 IF Offsite fire apparatus is needed to provide water to the Spent Fuel Pool, THEN Request the EOFD to contact the Oconee CDEP to provide sufficient fire apparatus (at least 3 pumper trucks of 1000 gpm, or greater capacity) to Oconee Nuclear Site (If available, Keowee Ebenezer, Corinth Shiloh, or Keowee Key Rural Volunteer Fire Departments should be requested to provide support).

El 3.10.1 Provide the OSC Manager with the following information and request support from the OSC:

Fire apparatus is being dispatched from Oconee County to provide water to the Spent Fuel Pool

• Request Security Liaison to have Security Officers meet the fire apparatus at the determined site entrance

• Request Maintenance Manager to initiate MP/0/A/3009/012A (Emergency Plan For Refilling Spent Fuel Pool).

RP/OIB/1000/019 Page 20 of 21 NOTE: IOCFR50.54(x) allows for reasonable actions that depart from a License Condition or Technical Specification to be performed in an emergency when this action is immediately needed to protect the health and safety of the public and no action consistent with the License Condition or Technical Specification that can provide adequate or equivalent protection is immediately apparent.

10CFR50.54(y) requires approval of any 10CFR50.54(x) actions by a Licensed Senior Operator.

Implementation of Oconee Severe Accident Guidelines (OSAG) requires the use of 10CFR50.54 (x) and (y) provisions.

0l 3.11 IF Plant conditions require a decision to implement 10CFR50.54(x),

THEN Perform the following steps:

EJ 3.11.1 Obtain approval of a Licensed Senior Reactor Operator prior to taking any action.

El 3.11.2 Document decision and actions taken in the affected units log.

El 3.11.3 Document decision and actions taken in the Control Room Emergency Coordinator Log.

NOTE: NRC must be notified of any 10CFR5O.54(x) decisions and actions within one (1) hour.

El 3.11.4 Request Control Room/TSC NRC Communicator to report decision and actions taken to the NRC.

NOTE: 10CFR50.72 requires NRC notification for specific plant conditions.

Dl 3.12 IF Plant conditions require NRC notification under 10CFR50.72, THEN Request the Control Room/TSC NRC Communicator to provide this notification using the guidance in OMP 1-14, (Notifications).

RPIO/B/1000/O19 Page 21 of 21 0 3.13 IF A LOCA exists inside containment, THEN Initiate the following actions:

3.13.1 Request the Operations Superintendent to have Operations personnel refer to OP/1,2,3/AI1 102/023, (Operation Of Containment Hydrogen Recombiner System).

3.13.2 Request the Operations Superintendent to have Operations personnel refer to OP/0/A11104/019 (Control Room Ventilation System) to verify proper operation of the Control Room Ventilation System. {3}

0l 3.14 Announce SAMG transition to TSC/OSC/EOF personnel so proper signage can be displayed with current plant conditions. {6}

0 3.15 Establish a Recovery Organization (Section M of the ONS Emergency Plan, Volume A, located in the Operations Shift Manager's office) once the emergency has been terminated.

3.15.1 Request the OSC Manager to review Section M of the Emergency Plan (Volume 17A is located in Unit 3 Control Room) to begin preparation for recovery.

3.16 Emergency Planning Section shall be responsible for completing all Procedure Process Records of Emergency Plan Implementing procedures initiated by the TSC.

0 3.17 Ensure TSC is returned to ready condition for next drill or actual event.

El 3.17.1 Ensure TSC PA override switch is put in off position. {8}

4. Enclosures 4.1 Operations Shift Manager to TSC Emergency Coordinator Turnover Sheet 4.2 Emergency Preparedness Acronyms 4.3 TSC Personnel Log 4.4 NRC Site Team Response Form 4.5 Emergency Classification Termination Criteria 4.6 Alternate TSC/OSC Activation 4.7 References

Enclosure 4.1 RP/OJB/1000!019 Operations Shift Manager To TSC Emergency Page 1 of 2 Coordinator Turnover Sheet EMERGENCY CLASSIFICATION TIME DECLARED DESCRIPTION OF EVENT Unit One Status:

Reactor Power RCS Pressure RCS Temperature Auxiliaries Being Supplied Power From ES Channels Actuated MAJOR EQUIPMENT OUT OF SERVICE JOBS IN PROGRESS Unit Two Status:

Reactor Power RCS Pressure RCS Temperature Auxiliaries Being Supplied Power From ES Channels Actuated MAJOR EQUIPMENT OUT OF SERVICE JOBS IN PROGRESS Unit Three Status:

Reactor Power RCS Pressure RCS Temperature Auxiliaries Being Supplied Power From ES Channels Actuated MAJOR EQUIPMENT OUT OF SERVICE JOBS IN PROGRESS

Enclosure 4.1 RP/OIB/1o00/O19 Operations Shift Manager To TSC Emergency Page 2 of 2 Coordinator Turnover Sheet

> Classification Procedure in Use:

RP/O/BI1000/002 Control Room Emergency Coordinator Procedure Is RP/O/B/1000/003A, ERDS Operation, in use? Yes _ No If Yes, Unit No.

Step No.

Is RP/O/B/1000/007, (Security), in use? Yes _ No _ If Yes, Step No. __

Is RP/O/B/1000/016, (Medical), in use? Yes _ No _ If Yes, Step No.

Is RP/0/B/1000/017, (Spill Response), in use? Yes __ No _ If Yes, Step No.

Is RP/0/B/1000/022, (Fire/Flood), in use? Yes __ No __ If Yes, Step No.

Is RP/O/B/1000/29, (Fire Brigade) in use? Yes _ No _ If Yes, Step No. __

Is Step 5.4 of OMP 1-18 (Implementation Standard During Abnormal And Emergency Events) in use?* Yes _ No

• If yes, implementation of emergency worker exposure limits must be announced over Public Address System. {31 IF Condition A, Dam Failure, has been declared for Keowee Hydro Project, THEN provide the following information to the TSC Emergency Coordinator:

• Status of Offsite Agency Notifications

• Recommendations made to offsite agencies

• Status of relocation of site personnel What is the status of Site Assembly? (This question is only applicable for those times that the Emergency Response Organization is activated after hours, holidays, or weekends.)

Next message due to Offsite Agencies at Time:

Operations Shift Manager/CR Time:

Emergency Coordinator/TSC Time:

Enclosure 4.2 RP/O/B/ l000/019 Emergency Preparedness Acronyms Page 1 of 1 CDEP County Director of Emergency Preparedness EC Emergency Coordinator EOF Emergency Operations Facility EOFD Emergency Operation, Facility Director ETS Emergency Telephone System LEC Law Enforcement Center NRC Nuclear Regulatory Commission EOC Emergency Operations Center OSC Operational Support Center PAR Protective Action Recommendation SCC State/County Communicator SDEP State Director of Emergency Preparedness SEOC State Emergency Operations Center SWP State Warning Point TSC Technical Support Center

Enlo(*'.3 RP/C )00/019 TSC Pers~o'mel Log Page 1 of 2 DATE:

PRIMARY RELIEF POSITION NAME SOCIAL SECURITY TIME SHIFT NAME SOCIAL SECURITY SHIFT IN AT SCHEDULE ( SCHEDULE (Last, First, MI) EMPLOYEE ID TSC (Last, First, MI) EMPLOYEE ID Emergency Coordinator**

Offsite Communicator**

Dose Assessment Liaison*

Nuclear Engineering**

Tech Assist to EC (Mech Engineer)**

Operations Superintendent TSC/OSC Liaison

• 45 Minute Responder

• • 75 Minute Responder

Enclos( '.3 RP/O17 )00/019 TSC Perso ixel Log Page 2 of 2 PRIMARY I RELIEF POSITION NAME (Last, First, MI)

SOCIAL SECURITY EMPLOYEE ID 1 TIME IN AT TSC SHIFT SCHEDULE NAME (Last, First, MI)

SOCIAL SECURITY EMPLOYEE ID SHIFT SCHEDULE TSC/OSC Liaison Support Engineering Manager NRC Communicator (ENS)

Dose Assessors Engineering Mgr.

Assistant Operations Superintendent Assistant Emergency Planning Community Relations (WOE)

Local I/T

Enclosure 4.4 RP/O/BI 1000/019 NRC Site Team Response Form Page 1 of 1

1. NRC Site Team Response Form 1.1 Alternate Emergency Coordinator (name) 1.2 NRC Site Team Personnel Information:

NAME SOCIAL SECURITY NUMBER 1.3 Estimated Time of Arrival (ETA):

1.4 Mode of Transportation:

Access Gate (Circle One): Hwy 130 - Main Station/WOE Entrance (Gate 1)

Hwy 183 - Intake Owner Controlled Area (OCA) Gate (Gate 3)

Hwy 183 - Complex/Branch OCA Gate (Gate 4) 1.5 Telecopy this form to the OSC and Security using Speed Dial Code 031 or One-Touch Dial Code 31.

1.6 GET and BBA Requirements Waived:

RP Manager Date

Enclosure 4.5 RP/O0/BII000/19 Emergency Classification Termination Page 1 of 1 Criteria SIF The following guidelines applicable to the present emergency condition have been met or addressed, THEN An emergency condition may be considered resolved when:

0l 1.1 Existing conditions no longer meet the existing emergency classification criteria and it appears unlikely that conditions will deteriorate further.

El 1.2 Radiation levels in affected in-plant areas are stable or decreasing to below acceptable levels.

El 1.3 Releases of radioactive material to the environment greater than Technical Specifications are under control or have ceased.

El 1.4 The potential for an uncontrolled release of radioactive material is at an acceptably low level.

El 1.5 Containment pressure is within Technical Specification requirements.

El 1.6 Long-term core cooling is available.

El 1.7 The shutdown margin for the core has been verified.

El 1.8 A fire, flood, earthquake, or similar emergency condition is controlled or has ceased.

El 1.9 Offsite power is available per Technical Specification requirements.

El 1.10 All emergency action level notifications have been completed.

El 1.11 The Area Hydro Manager has been notified of termination of Condition B for Keowee Hydro Project.

El 1.12 The Regulatory Compliance Section has evaluated plant status with respect to Technical Specifications and recommends Emergency Classification termination.

El 1.13 Emergency terminated. Request the TSC Offsite Communicator to complete an Emergency Notification Form for a Termination Message using guidance in RP/O/B/1000/015B, (Offsite Communications From The Technical Support Center), and provide information to offsite agencies.

Date/Time of Termination: I Emergency Coordinator Initials:

0 Return to Step 2.10.1.E.I

Enclosure 4.6 RP/0/B/1000/019 Alternate TSC/OSC Activation Page 1 of 2

1. Activation of the Alternate TSC prior to completion of turnover with the OSM 0l 1.1 Request OSC Manager/SPOC Supervisor to initiate steps to setup the Alternate TSC located in RP/O/B/1000/25 (OSC Manager Procedure).

5 1.2 Request TSC Logkeeper (or designee) to announce over the plant PA that the Alternate TSC is being activated.

0 1.3 Relocate TSC personnel, except for the following, to the Alternate TSC, Room 316 of the Oconee Office Building:

El 1.3.1 TSC Offsite Communicator (1)

El 1.3.2 TSC Logkeeper El 1.3.3 Emergency Planning (if available) 0l 1.4 Return to Step 2.2 of this procedure and complete turnover with the OSM.

0l 1.4.1 Report to the Alternate TSC with remaining support personnel after completion of turnover.

Enclosure 4.6 RP/O/B/1000/019 Alternate TSC/OSC Activation Page 2 of 2

2. Activation of the Alternate TSC/OSC 0l 2.1 Direct the TSC/OSC Liaison to inform the OSC Manager of the need to relocate the following emergency response facilities:

TSC OSC TSC and OSC El 2.2 Provide guidance on best available route to personnel being relocated to the Alternate TSC.

2.2.1 IF A radiological release is in progress, THEN Direct the TSC/OSC Liaison to request RP to determine the best available route to the Alternate TSC.

El 2.3 Direct the following TSC personnel to report to the Alternate TSC to assist with setup of the facility and establish communications with the TSC:

(1) TSC Offsite Communicator (1) Dose Assessor Ops Superintendent Assistant TSC/OSC Liaison Technical Assistant 0l 2.4 Direct the TSC NRC Communicator to inform the NRC that the Alternate TSC is being activated.

0l 2.5 Direct the remaining TSC personnel to report to the Alternate TSC.

El 2.6 Inform the EOF Director that the Alternate TSC is being activated and that TSC personnel, including the Emergency Coordinator, are enroute to that facility.

0l 2.7 Return to Step 3.4.2 of this procedure after reporting to the Alternate TSC.

Enclosure 4.7 RP/O/B/1000/019 References Page 1 of 1

1. PIP 0-98-04996

2. PIP 0-99-00743

3. PIP 0-01-01395

4. PIP 0-01-03460

5. PIP 0-01-03696

6. PIP 0-02-00264

7. PIP 0-02-03705

8. PIP 0-02-7089