ML003722065
| ML003722065 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/06/2000 |
| From: | Mccollum W Duke Energy Corp |
| To: | NRC/OCIO/IMD/RMB |
| References | |
| -RFPFR | |
| Download: ML003722065 (119) | |
Text
Duke Duke Energy Corporation Oconee Nuclear Station P r~nergy-7800 Rochester Highway Seneca, SC 29672 (864) 885-3107 OFFICE W R. McCollum, Jr.
(864) 885-3564 FAX Vice President June 6, 2000 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 2000-05 Please find attached for your use and review copies of the revision to the Oconee Nuclear Station Emergency Plan: Volume C Revision 2000-05, June, 2000.
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.
Any questions or concerns pertaining to this revision please call Mike Thorne, Emergency Planning Manager at 864-885-3210.
By copy of this letter, two copies of this revision are being provided to the
- NRC, Region II, Atlanta, Georgia.
Very truly yours, W. R.
McCollum, Jr VP, Oconee Nucld 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.
Steven Baggett Rockville, Maryland (w/o Attachments, Oconee Nuclear Station)
NRC Resident Inspector M. D. Thorne, Manager, Emergency Planning
June 6, 2000 OCONEE NUCLEAR SITE INTRASITE LETTER
SUBJECT:
Emergency Plan Implementing Procedures Volume C, Revision 2000-05 Please make the following changes to the Emergency Plan Implementing Procedures Volume C by following the below instructions.
REMOVE Cover Sheet Rev. 2000-04 Table of Contents -
Page 1 HP/0/B/1009/018 -
06/02/99)
RP/0/B/1000/001 -
04/17/00 RP/0/B/1000/019 -
05/27/99 RP/0/B/1000/020 -
12/11/98 ADD Cover Sheet Rev. 2000-05 Table of Contents -
Page 1 HP/0/B/1009/018 -
05/19/2000 RP/0/B/1000/001 -
05/30/2000 RP/0/B/1000/019 -
05/30/2000 RP/0/B/1000/020 -
05/31/2000
DUKE POWER EMERGENCY PLAN IMPLEMENTING PROCEDURES VOLUME C APPROVED:
W. W. Foster, Manager Safety Assurance 06/06/2000 Date Approved 06/06/2000 Effective Date VOLUME C REVISION 2000-05 JUNE, 2000
HP/0/B/1009/018 HP/O/B/1009/020 HP/O/B/1009/021 HP/0/B/1009/022 RP/O/B/1000/001 RP/0/B/1000/002 RP/0/B/1000/03A RP/O/B/1 000/07 RP/0/B/1000/009 RP/0/B/1000/10 RP/O/B/1000/15A RP/O/B/1000/15B RP/O/B/1000/15C RP/O/B/1000/16 RP/0/B/1000/17 RP/0/B/1000/18 RP/0/B/1000/19 RP/O/B/1000/20 VOLUME C TABLE OF CONTENTS Offsite Dose Projections - (05/19/00)
Estimating Food Chain Doses Under Post Accident Conditions - (10/09/98)
Source Term Assessment of a Gaseous Release From Non-routine Release Points - (12/01/97)
On Shift Offsite Dose Projections (06/02/99)
Emergency Classification - (05/30/00)
Control Room Emergency Coordinator Procedure - (05/03/00)
ERDS Operation (12/03/98)
Security Event - (05/15/96)
Procedure for Site Assembly - (03/21/00)
Procedure for Emergency Evacuation/Relocation of Site Personnel -(03/21/00)
Offsite Communications From The Control Room - (12/10/98)
Offsite Communications From The Technical Support Center - (12/10/98)
Offsite Communications From The Emergency Operations Facility - (12/10/98)
Medical Response - (05/27/99)
Spill Response (02/12/98)
Core Damage Assessment (09/30/97)
Technical Support Center Emergency Coordinator Procedure (05/30/00)
Emergency Operations Facility Director Procedure - (05/31/00)
Revision 2000-05 June, 2000 1
(RO*-9)
Duke Power Company (I) ID No HP/O/B/1009/018 PROCEDURE PROCESS RECORD Revision No 019
"*-i'REPARATION INFORMATION ONLY (2)
Station OCONEE NUCLEAR STATION (3)
Procedure Title Off-Site Dose Projections (4)
Prepared By Date 5/18/2000 (5)
Requires 10CFR5O.59 ev uation?
N]
Yes (New procedure or revision with major changes)
El No (Revision with minor changes) 0 No (To incorporate p
ýroved changes)
(6)
Reviewed By
/__
_(QR)
Date 0"/o'.0 Cross-Disciplinary Review By _(QR)NA AM!
Date Reactivity Mgmt. Review By
.(QR)NAA Date
/ ' 100 (7)
Additional Reviews Reviewed By Date Reviewed By Date (8)
Temporary Approval (if necessary)
By (SRO/QR)
Date By (QR)
Date
(ý9)
Approved By f*(-"*
Date iii
- ii *;
- PERFORMANCE (Co nre with control every 14 calendar days while work is being performed.)
(10)
Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copp Date (11)
Date(s) Performed Work Order Number (WO#)
COMPLETION (12)
Procedure Completion Verification El Yes El NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?
El Yes El NA Listed enclosures attached?
El Yes El NA Data sheets attached, completed, dated, and signed?
0l Yes Dl NA Charts, graphs, etc. attached, dated, identified, and marked?
El Yes El NA Procedure requirements met?
Verified By Date (13)
Procedure Completion Approved Date "14) Remarks (Attach additional pages, if necessary)
Page 1*f
- i009/4
- FST DOS
- 'JETONS Reisio 19 DESRIPION 0F 0HNE This prcdr chang is intnde t-o mak th prcdr eaie toueodlteeec s.t coptrpoga*hc is
-o longe used (Ms
)
and to0
- nopoae.
th use o
h urn offs-i 0-
-os asesmn proram (Rd s
- 5)
This chng als elmntstemna 40 metodoog.
Imlmntto of P
-0 mehdlg redee
-aua dose ca--*ulat**ns impatcl Th smao r-wrt oS the~
prcdr use enlsue to prvd 0etil of perorin St do~se proecios.
Duke Power Company Oconee Nuclear Station Off-Site Dose Projections Reference Use Procedure No.
HP/O/B/1009/018 Revision No.
019 Electronic Reference No.
OX002SD7
HP/0/B/ 1009/018 Page 2 of 6 Off-Site Dose Projections
- 1. Purpose 1.1 This procedure provides instructions to Offsite Dose Assessment personnel to:
"* Determine release status, path and magnitude,
"* Evaluate source term,
"* Project dose commitment,
"* Determine appropriate radiological protective actions and associated emergency classification.
1.2 This procedure is an Emergency Plan Implementing Procedure (EPIP). It must be forwarded to the Emergency Planning Group within three working days of approval by the responsible group. {PIP 4-0-93-0701 }
- 2. References 2.1 HP/1,2,3/A/1009/017, Operating Procedure for Post-Accident Containment Air Sampling System 2.2 HP/0/B/1009/015, Procedure for Sampling and Quantifying High Level Gaseous, Radioiodine And Particulate Radioactivity 2.3 EPA 400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 2.4 Draft NuReg-1465, Accident Source Terms for Light-Water Nuclear Power Plants 2.5 NuReg-0654, FEMA-REP-1, Rev. 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 2.6 OSC-5575, Oconee Engineering Calc File, documenting the development of NuReg-1465 Source Term and Related Data 2.7 RP/0/B/1000/001, Emergency Classification Procedure 2.8 Letter from H.B. Tucker, November 30, 1989, Re: Follow-up on McGuire Alert (March 7&8, 1989), and the definition of a release.
2.9 U.S. Nuclear Regulatory Commission Response Technical Manual (RTM-93) 2.10 HP/O/B/1009/020, Estimating Food-Chain Doses Under Post-Accident Conditions.
2.11 PIP 0-0-84-0743, Method to Quantify Radioactive Release From TDEFWP
HP/O/B/1009/018 Page 3 of 6 2.12 PIP 4-0-93-701, Distribution Of Emergency Plan Procedures
- 3. Limits And Precautions 3.1 This procedure considers all releases to be ground level releases and that meteorological data are fifteen-minute averages.
3.2 This procedure is intended for use under abnormal/emergency conditions. It may be performed in part or whole. Sections may be performed in any appropriate order and some situations may require actions NOT addressed in this procedure.
3.3 In the event of a Steam Generator Tube Leak, all airborne radioactivity release pathways (example: TDEFWPs) must be considered in the offsite dose projection. Utilizing the steam generator tube leak rate, as determined by Operations or Engineering, converting the leak rate to cubic feet per minute flow rate, and inputting the cfm flow rate and applicable RCS concentrations as a Unit Vent release will account for all activity release pathways. {PIP 0-0-94-07431 3.4 Review data, both automatic and manual, to ensure acceptability prior to use in dose assessments.
3.5 Persons communicating with the NRC (via the HPN) or with the State, should discuss only Offsite Dose information. For plant-specific questions, NRC and State representatives should be referred to the Emergency Coordinator or the EOF Director (EOFD).
3.6 IF ENF transmittal is because of EAL escalation, projected dose information (sections 11, 12, 13, and 14 is NOT required. This avoids delaying escalation transmittals.
3.7 IF an additional PAZ(s) is identified, notification must be made to the State via the ENF within 15 minutes.
3.8 Offsite Dose Assessment is NOT responsible for evaluating liquid releases. Questions regarding liquid releases should be directed to Chemistry in the OSC.
3.9 Provide enclosures and other pertinent information to Emergency Planning after drills and actual emergencies.
- 4. Procedure 4.1 Setup the Facility as applicable:
- Setup the TSC using Enclosure 5.1 as a guide as necessary.
HP/O/B/1009/018 Page 4 of 6 NOTE:
Spare computers with RD5 are located in the EOF: (1) The left side of the room, when facing the stage in the EOFD's area, and (2) The Engineering room, near the back hall.
e Setup the EOF using Enclosure 5.2 as a guide as necessary.
4.2 Evaluate RIAs and other plant conditions, by using SDS and/or contact with other groups.
4.2.1 Notify the Emergency Coordinator, or Radiological Assessment Manager, and EOFD of RIA status and significant changes.
4.2.1.1 Continue evaluating RIAs and plant conditions as required by the event scenario or as directed by the RAM.
A. Use Enclosure 5.3 (data trending sheet) as a guide as necessary.
4.3 Determine release status using criteria on Enclosure 5.4.
4.3.1 IF NOT releasing or IF a release has not been made, do not run Raddose-5 (RD5) unless specifically requested by the RAM.
4.3.1.1 Because plant conditions may require Protective Action Recommendations (PARs), with no release in progress, use.5 as necessary to select Protective Action Zones (PAZs).
NOTE:
IF automatic data is available to RD5, assessing meteorological data will serve as a verification of data used. If automatic data is not available to RD5, meteorological data must be selected and input manually.
4.3.2 IF a release is occurring, or has occurred, assess meteorological conditions using Enclosure 5.5.
4.3.3 IF a release is occurring, or has occurred, run RD5 using Enclosure 5.6 as a guide as necessary.
4.3.3.1 Obtain the RD5 "Summary Sheet" printout or display data.
4.3.3.2 Obtain the RD5 "Emergency Notification Form" (ENF/ "Green Sheet"), printout or display data.
4.3.3.3 Using Enclosure 5.4 and RD5 printouts/displays, evaluate release status to determine if release is above or below normal operating (SLC) limits.
HP/O/B/ 1009/018 Page 5 of 6 4.3.3.4 Using Enclosure 5.7 and RD5 printouts/displays, evaluate Emergency Action Levels (EALs).
4.3.3.5 Using Enclosure 5.5 and RD5 printouts/displays, evaluate PAZs.
A. RD5 PAZs should be verified with the manual procedure to ensure accuracy.
B.
Once PARs have been made, recheck meteorological conditions every 15 minutes to ensure that additional PAZs are identified as necessary.
4.3.3.6 Using Enclosure 5.8 and RD5 printouts/displays as necessary, assist in the completion of the ENF.
4.3.4 Notify the Emergency Coordinator, or the RAM and the EOFD of the results of the above evaluations.
4.4 Evaluate Field Monitoring survey results.
4.4.1 Compare Field Monitoring survey results to EAL criteria in Enclosure 5.7.
4.4.1.1 Make EAL recommendations based on step 4.4.1 evaluation.
4.4.2 Compare Field Monitoring survey results to RD5 projections 4.4.2.1 IF Field Monitoring results are higher than RD5 projections, evaluate the need to adjust RD5 input data to project dose.
4.5 IF requested by the State, supply the Self-Reading Dosimeter (SRD) Correction Factor from the RD5 Summary Report, to estimate emergency worker dose.
4.6 IF ingestion pathway dose calculations are necessary, refer to HP/O/B/1009/020, Estimating Food Chain Doses Under Post Accident Conditions, for limits, criteria, and additional information.
4.6.1 Input Field Monitoring sample data into RD5 to calculate ingestion pathway dose.
4.6.2 Communicate ingestion pathway dose calculation results to South Carolina DHEC.
HP/OB/ 1009/018 Page 6 of 6
- 5. Enclosures 5.1 TSC Setup 5.2 EOF Setup and RAM Checklist 5.3 Dose Assessment Data Trending Sheet 5.4 Release Status 5.5 Meteorology and PAZ Selection 5.6 Raddose 5 Operation 5.7 Emergency Action Levels and Protective Action Recommendations 5.8 Emergency Notification Form (ENF) Completion
.1 HP/O/B/1009/018 TSC Setup Page 1 of 1 Initial lines as applicable, depending upon accident/drill scenario. Coordinate activities with the EOF (it is not necessary to duplicate efforts with the EOF). This is only a checklist/guide for setting up the TSC.
Actual completion of this enclosure is not required. Steps may be performed in any order:
Notify Emergency Coordinator upon arrival Log name and arrival time on TSC personnel status board Boot RD5/SDS computer and start SDS
- TSC computer should boot automatically using a default User ID and Password.
- If the computer does not boot, re-start, using your network User ID and Password.
Determine release pathways (if any) using SDS and contact with other groups Use release criteria on Enclosure 5.4 to determine release status If releasing, determine if release < or > Normal Operating (SLC) Limits using RD5 Notify TSC Emergency Coordinator
___ USE RD5 results as necessary to support Emergency Notification Form (ENF) generation.
Monitor Field Team activities
- of Teams available Select meteorology and PAZs, based on Enclosure 5.5, or RD5 as required Refer to section 4.3.1.1 of the procedure
___ Communicate RD5 results to the Emergency Coordinator and to the Offsite Communicator as necessary
___ Develop 24-hour staffing schedule as needed If requested by the NRC or ERO management, staff the HPN (Health Physics Network) phone
.2 HP/O[B/1009/018 EOF Setup and RAM Checklist Page 1 of 1 Initial lines as applicable, depending upon accident/drill scenario (mandatory items in bold). The first, or duty person should sign in as the RAM until a more experienced person arrives at the EOF. This is only a checklist/guide for setting up the TSC. Actual completion of this enclosure is not required. Steps may be performed in any order:
__ Sign Attendance Log upon entry into EOF.
Notify EOF Director (EOFD) upon arrival.
__ Log name and arrival time on EOF personnel status board.
Ensure RD5 computer and SDS computers are booted. SDS could be booted on RD5 computer if necessary. Use your network User ID and Password on RD5 computer.
Contact TSC Dose Assessment Liaison. Maintain contact as necessary Ensure that turnover is completed with the TSC (ASAP). ProVide turnover sheet to EOFD.
Determine release pathways (if any) and release specifics If releasing determine if release < or > Normal Operating (SLC) Limits using RD5 Ensure that Field Team activities are monitored
- of Teams available Notify EOFD of the above results, and of changes affecting offsite rad conditions.
Ensure that the following duties are assigned (combine as needed: RAM to assume duties also):
Run RD5 Monitor SDS Assist with ENF completion Communications with TSC Monitor Field Monitoring activities Maintain Status Board Ensure Rad Assessment Mgr position is staffed.
Assist with "risk" perspectives Communicate with SCDHEC and NRC (via HPN)
(if/as necessary)
(if/as requested)
Ensure that meteorology and PAZs are determined, based on Enclosure 5.5, or RD5, as required (Refer to section 4.3.1.1 of this procedure)
Ensure that RD5 is runlbeing run (approximately every 15 minutes) to project dose and to support Emergency Notification Form (ENF) generation, if a release is in progress.
Communicate RD5 results to EOFD, and Offsite Communicator (as necessary, assist News Group in putting doses into "risk" perspective)
Ensure that Offsite Dose status board and PAZ maps in EOFD's area are maintained (as necessary)
Develop 24-hour staffing schedule (as necessary)
(
Enclo.
5.3 HP/OJB/IL.,,018 Page 1 of 2 Dose Assessment Data Trending Sheet Unit:
Date:
TURN ON TIME:--_
CODE: I PARAMETER: *,
Normal BKG$
EROENV AVERAGE Upper WIND Lower SPEED River EROENV AVERAGE Upper 1
WIND Lower 1
DIRECTION River (Procedure)
Stability Class EROENV Average A Temnp:
Ave.Precipitation P0162 **
Ambient Temp °C Or RB01 Ambient Temp TF RB01 Pen Room Filters (PRV) to Unit U.S.*
Vent (OFF)
U.S.*
1.:;L1:
lH(.; E:s V X.\\I V,[..I:.:._
EROPROC partic RIA-47 1,000-15,000 iodine RIA-48 50-5,000 low gas RIA-49 100-1,000 high gas RIA-49A Offscale low EROAREA hi hi gas RIA-57
-1R/hr EROAREA hi hi gas RIA 58
- 1R/hr EROENV Ave Vent Flow nfm
~ 65,000 cfm U.S.*
EROPROC partic RIA-43 50-1000 iodine RIA-44 5-50 "l
ow gas RIA-45 20-100 high gas RIA-46 Offseale low EROAREA hi hi gas RIA-56
- 1.5 R/h
Enclo HP/O/B/I,,O018 Page 2 of 2 Dose Assessment Data Trending Sheet TURN ON TIME:--_
CODE: 4 PARAMETER: 4 Normal BKG_
EROAREA Main Stm RIA-16 0.01-0.09 EROAREA Main Stm RIA-17 0.01-0.09 EROPROC Aux Multi RIA-32 20-100 EROPROC Contr Rm RIA-39 20-60 t
CSAE RIA-40 100-2,000 SFP Gas RIA-41 20-75 TURN ON TIME:---_
CODE: I PARAMETER:,
Normal BKG,__
EROAREA Contr Rm Area RIA-1
<1 mR/hr RB Canal Wall RIA-3 1-15 mR/hr RB Entrance RIA-4 1-15 mR/hr SFP Bid Wall 1-10 mR/hr RIA-6 Hot Machine Shop RIA-7
<1 mR/hr Pri Chin Hot Lab RIA-8
<1 mR/hr Pri Sample Area RIA-10
<1 mr/hr Aux Bid Hall 3 floor (796')
<1 mr/hr RIA-1.1 Chem Addn Area
<1 mr/hr Aux B 2,nd fl 783' RIA-12 Waste Panel Area
<1 mr/hr Aux B I" fl 771' RIA-13 HPI Rm Corridor RIA-15 1-10 mR/hr
- EROECCS RB Spray ON/OFF U.S.*
(OFF)
At top of SDS screen, select "Point List," then select "By Point ID." Then type in, P0162, as the requested point.
UNIT SPECIFIC SCREENS - Be sure you're on the correct Unit in SDS.
5.3
.4 Release Status HP/O/B/1009/018 Page 1 of 1
- 1. Determine release status using the following criteria:
NOTE:
- Dose projection values are NOT required for the Emergency Notification Form unless the release is above normal operating limits.
1.1 No Release - no potential release of activity generated by the event.
1.2 Potential Release - this item is on the Emergency Notification Form, but should be selected only if specifically instructed to do so by the RAM.
NOTE:
Dose rates are assumed to be at the Site Boundary (one mile from site).
1.3 Release Within Normal Operating Limits -activity generated by the event currently or previously released within normal operating limits (Total Effective Dose Equivalent
< 5.704E-2 mrem/hr; Committed Dose Equivalent - thyroid < 1.711 E-1 mrem/hr).
Events:
Reactor Building pressure > 1 psig with increased activity in Reactor Building
"* OTSG Tube Leak with Main Steam Relief Valve release, or increased Unit Vent activity
"* Increased Unit Vent Activity
"* Field Team Activity 1.4 Release Above Normal Operating (SLC) Limits - activity generated by the event currently or previously released above normal operating limits (Total Effective Dose Equivalent
> 5.704E-2 mrem/hr; Committed Dose Equivalent - thyroid > 1.71 1E-1 mrem/hr).
.5 Meteorology and PAZ Selection
- 1.
Assess Meteorology and Protective Action Zones (PAZs) as follows:
HP/0/B/ 1009/018 Page 1 of 4 NOTE:
Actual, average meteorological data should be used unless it is more appropriate to use forecast data, as provided by a meteorologist.
1.1 Using section 2 hierarchy below, record the following on Enclosure 5.3, or other form such as the "Drill/Event Log" NOTE:
The sources of data are listed in order of preference in the flowchart in section 2 below.
"* Time meteorological data taken.
"* Wind speed in miles per hour.
"* Direction from which the wind is blowing in degrees from North (North = 0).
"* Temperature gradient in degrees centigrade (AT0C).
Stability class based on AT.
1.2 Determine the PAZs using section 3 below.
.5 Meteorology and PAZ Selection
- 2. Select Meteorology By Using the Flowchart Below:
HP/O/B/ 1009/018 Page 2 of 4 METEOROLOGICAL DATA (All data is 15 min average except NWS.)
National Weather Service (NWS) phone number is (864) 879-1085.
TIME 1000 to 1600 hrs TIME AT°C DATA SOURCE PRIORITY wind speed sources 1) lower; 2) river; 3) upper(0.5); 4) NWS x 0.5 wind direction sources 1) upper; 2) lower; 3) river; 4) NWS AT°C sources 1) tower; 2) Assume -0.26'C DATA SOURCE PRIORITY wind speed 1) lower; 2) upper x 0.5; 3) Assume 1 mph nd wind direction 1) upper; 2) lower; 3) assume 0-360' AT°C 1) tower; 2) Assume > +2.0 1
- wind speed 1) Assume 1 mph wind direction 1) Assume 0-360' AT°C 1) Assume > +2.0
- Based on experiment I Stability Class
<-0.95
-0.94 to -0.85
-0.84 to -0.75
-0.74 to -0.25
-0.24 to +0.75
+0.76 to +2.0
> +2.0 A
B C
D E
F G
NOTE:
- Conversion formulas for the meteorological data obtained from NWS are:
(1.15) x (knots) =mph S
(1.8 x C) + 32 =F S.
t
.5 Meteorology and PAZ Selection HP/0/B/ 1009/018 Page 3 of 4
- 3. Determine PAZ by completing one of the options under Daytime or Nightime, using meteorological data selected above.
3.1 Daytime (1000-1600 hrs):
"* Wind speed > 5 mph for tower or river wind direction; use the table below.
"* Wind speed < 5 mph for tower or river wind direction. Assume PAZs AG, Al, B 1, C1, D1, El, and Fl are affected. Then use the table below to determine additional PAZ.
"* For NWS wind direction. Assume all PAZs are affected (AO, Al through Fl, A2 through F2).
3.2 Nighttime (1600-1000 hrs.):
"* IF river wind direction is between 210°-70, use Option A (Daytime).
IF river wind direction is between 70'-210, or is unavailable, assume all PAZs are affected (AG, A1 through F1, A2 through F2).
Protective Action Zones Wind Direction 0-2 miles; 2-5 miles; 5-10 miles 14.10-270 AO, C1, D1, El, C2, D2, E2 27.10-420 AG, Cl, D1, El, D2, E2 42.1 0-660 AO, D1, El, D2, E2 66.10-850 AO, D1, El, D2, E2, F2 85.1-104° AO, D1, El, F1, D2, E2, F2 104.10-1290 AO, El, F1, E2, F2 129.10-1560 AO, A1 El, F1, A2, E2, F2 156.10-1750 AO, A1 El, Fl, A2, F2 175.10-1810 AG, Al, Fl, A2, F2 181.10-2190 AG, Al, B1, Fl, A2, B2, F2 219.1°-2550 AG, Al, Bl, A2, B2, 255.10-2710 AO, Al, B1, Cl, A2, B2, C2 271.10-2970 AO, B1, C1, B2, C2 297.10-3120 AO, B1, C1, B2, C2, D2 312.10-3450 AO, B1, Cl, Dl, B2, C2, D2 345.10-140 AG, C1, Dl, C2, D2
.5 Meteorology and PAZ Selection HP/O/B/1009/018 Page 4 of 4 3.3 Identify the PAZs selected in step 3.1 or 3.2 on the table below 3.3.1 Recommend sheltering for the remainder of the 10-mile EPZ anytime that zones are recommended for evacuation.
NOTE:
Default Protective Action Recommendations (PARs)upon initial declaration of a General Emergency are to Evacuate the 2-mile radius around the plant and out to 5-miles downwind.
3.3.2 Recommend the "default" PARs upon initial declaration of a General Emergency, unless Dose Assessment or Field Monitoring indicate that additional PAZs should be evacuated.
CAUTION:
Once a zone has been added to the list of affected zones,- it shall NOT be removed except under the direction of the RAM.
I 3.3.3 IF a General Emergency has been declared and protective action recommendations have been made, recheck meteorological conditions every 15 minutes to ensure that additional PAZs are identified as required.
3.3.3.1 IF additional zones need to be added to the list of PAZs, notify the Emergency Coordinator, or RAM, or EOF Director.
The State must be notified (via the ENF) within 15 minutes of additions to PAZs.
NOTE:
Default PARs for "Severe Core Damage" (Condition 3 failed fuel) are to Evacuate the 5 mile radius around the plant and out to 10-miles downwind of the plant.
3.3.4 IF Severe core damage (Condition 3 failed fuel per RP/0/B/1000/18, Core Damage Assessment) conditions exist, recommend the associated "default" PARs, unless Dose Assessment or Field Monitoring indicate that additional PAZs should be evacuated. SAM G may be in effect at this point.
I PICKENS COUNTY I
OCONEE COUNTY 0-2 2-5 5-10 0-2 2-5 5-10 miles miles miles miles miles miles AO Al BIB2 C2 AO D1 E
F1 D2 E2 F2 EVACUATE SHELTER
.6 HP/O/B/1009/018 Raddose 5 Operation Page 1 of 4
- 1. Operate Raddose 5 (RD5) as follows:
1.1 Choose the RD5 icon.
1.2 If no icon is available, go to "Start", "Programs", "Raddose-V".
1.2.1 If RD5 is not available, load it by going to "Start", "Run", and typing in,
\\\\charf01\\das\\raddose\\prod\\setup.exe 1.2.1.1 Follow the computer prompts to complete RD5 installation.
NOTE:
Proper "Configuration" is required in order to transfer RD5 files between the TSC and EOF.
1.3 Ensure the proper "Configuration" message displays for the facility, "TSC" for TSC and "EOF" for EOF.
1.3.1 Revise "Configuration" if necessary, by selecting "File" at the DAS desktop.
1.3.2 Select "DAS Configuration" and choose appropriate configuration for facility, 1.3.3 Reboot RD5 for "Configuration" changes to take effect.
1.4 Choose the affected ONS Unit.
NOTE:
Accident Mode uses "live" data when in "Automatic". Drill Mode uses simulated data which must be input manually.
1.5 Select "Accident" or "Drill".
1.6 Select "Automatic" data to use "archived" data, OR, select "Manual" data for manual entry of data.
1.7 Select "Begin new incident" to begin a new scenario, OR, to use previously-generated dose assessments, go to step 1.12.
1.8 Enter reactor trip date and time.
1.8.1 IF the reactor did NOT trip and shutdown is NOT in progress, use the current date and time for reactor trip specifics.
1.8.2 IF the reactor did NOT trip and shutdown IS in progress, use the time and date that descent in power began as the reactor trip time and date.
1.9 Enter the release date and time (estimated or known).
1.10 Enter operator initials and either "Accept" or "Cancel".
.6 Raddose 5 Operation HP/O/B/1009/018 Page 2 of 4 1.11 Go to step 1.13 1.12 If previous TSC or EOF files are to be used, select "Continue Previous Incident."
NOTE:
After selecting "Network Data", select the location from which you want to take data.
1.12.1 Select either "Local Data" to use data from the local hard drive, OR "Network Data" to use data from the TSC or EOF.
NOTE:
Any "Automatic" data may be manually overwritten if necessary.
1.13 Enter meteorological data either manually or automatically.
1.13.1 If data is entered manually, select "F9" to accept -wind speed and wind direction data, or "esc" to abort.
1.13.2 Select "Accept" when meteorological data has been entered.
1.14 Enter Source Term data either manually or automatically.
NOTE:
e "Accident Type" and "NG Method" must be manually selected.
- IF more than one release path is used, the "Accident Type" must be the same for each path used, to ensure consistent nuclide "mix".
1.14.1 Select "Accident Type" for each applicable release path in a time step:
NOTE:
- Guidance provided in NRC document, RTM-93, indicates that between normal operating temperature (Core Exit Thermocouple readings between <650'F and -700'F; and fuel cladding temperatures <1200'F), the GAP activity is not assumed to have been released, therefore, "normal coolant" should be assumed.
o If time permits, consult with TSC Nuclear Engineering or Operations prior to use of GAP release or Core Melt accident types.
LOCA - Loss of coolant (normal coolant) - leaks released into containment with fission products normally found in coolant.
LOCAG - Loss of coolant with GAP release - coolant containing radionuclides from the fuel pin GAP leaks into containment after fuel cladding has failed (e.g., core being uncovered, fuel pin heat up, and/or if mechanical fuel pin damage has occurred).
.6 HP/O/B/1009/018 Raddose 5 Operation Page 3 of 4
"* LOCAM - Loss of coolant core melt - coolant containing radionuclides expected to be released from a core that is partially melted leaks into containment.
"* SGTR - Steam generator tube rupture (normal coolant) - steam generator tube rupture accidents with fission products normally found in coolant.
SGTRG - Steam generator tube rupture GAP release - steam generator tube rupture accidents that release fission products in the fuel pin gap after fuel cladding has failed (e.g., core uncovery or fuel pin heat up and/or after mechanical fuel pin damage has occurred).
SGTRM - Steam generator tube rupture core melt - steam generator tube rupture accidents that release fission products expected to be released from a core that is partially melted.
LOCO - LOCA outside containment (normal coolant) - leaks released directly to outside environment (e.g., Auxiliary Building) with radionuclides normally found in reactor coolant.
LOCOG - LOCA outside containment gap release - leaks released directly to outside environment (e.g., Auxiliary Building) with radionuclides from the fuel pin gap after fuel cladding has failed (e.g., core uncovery of fuel pin heat up and/or after mechanical fuel pin damage has occurred).
LOCOM - LOCA outside containment core melt - leaks released directly to outside environment (e.g., Auxiliary Building) with radionuclides expected to be released from a core that is partially melted.
"* FUEL - Fuel handling gap release - fuel pin fission products (GAP activity) released from fuel during refueling, or Spent Fuel Pool accident.
1.14.2 Enter monitor reading and flow rate data as required.
1.14.2.1 "Accept" data, or overwrite data if necessary 1.14.3 Select "Emergency Classification".
1.14.4 Select "Perform Calculations".
1.14.4.1 Select "Continue" and "Go to Report Menu".
NOTE:
IF a printer is not available, the RD5 "Summary Report" screen and the "Green Form" may be displayed on-screen, from which information may be manually recorded.
1.14.4.2 Select "Print Summary Report".
.6 HP/0/B/1009/018 Raddose 5 Operation Page 4 of 4 1.14.4.3 Select "Return to Output Menu" and "Return to Main Menu".
1.14.5 Select "Perform Forecast".
NOTE:
If "General Emergency" was selected, PAZs based solely on the General Emergency default may be displayed, or if dose warrants, PAZs based on dose may be displayed as desired.
Dose PAZs and General Emergency PAZs from 5 to 10 miles from the plant may be different. PAZs should be verified to the manual procedure.
1.14.5.1 Select "Continue" and "Go to Report Menu".
1.14.5.2 Select "Print Green Form".
1.14.5.3 Select "Return to Output Menu" and "Return to Main Menu".
1.14.6 Continue with offsite dose projections as required to evaluate dose to the public and to support ENF transmittal.
NOTE:
IF initial TSC offsite dose projections indicate that releases likely will not affect Emergency Classification, and IF time does not permit (ex: initial stages of TSC activation, etc), the requirement to run RD5 every 15 minutes may be relaxed.
1.14.6.1 Because of the meteorological model in RD5, data should be collected to support RD5 projections every 15 minutes if "Manual" mode is used.
1.14.6.2 If "Automatic" mode is used, RD5 should be run approximately every 15 minutes.
1.14.7 Determine approximate dose to the public beyond the 10-mile EPZ by going to the RD5 "Output Menu" and selecting "Display Point-of-Interest Doses".
1.14.7.1 Follow screen prompts to calculate dose rate at the point of interest.
1.14.7.2 Relate the dose rate to known distances at or within the 10-mile EPZ to distances beyond the 10-mile EPZ.
1.14.7.3 Note the approximate direction of the plume and the approximate distance at which PAG doses are exceeded.
.7 HP/O/B/1009/018 Emergency Action Levels and Protective Page 1 of 2 Action Recommendations
- 1. Determine Emergency Action Levels (EALs):
1.1 IF any of doses described below are projected at the Site Boundary (one mile from plant) make the associated EAL recommendation to the RAM.
IF the projected doserate at the Site Boundary > 1. 14E-1 mrem/hr TEDE OR'
> 3.42E-1 mrem/hr committed dose equivalent (thyroid), then recommend an Unusual Event (bases: > 2 times SLC limits).
- IF the projected doserate at the Site Boundary > 1. 14El mrem/hr TEDE OR > 3.42E1 mrem/hr committed dose equivalent (thyroid) then recommend an Alert (bases: > 200 times SLC limits).
IF the projected dose at the Site Boundary > 100 mrem TEDE OR
> 500 mrem committed dose equivalent (thyroid), then recommend a Site Area Emergency (bases: one tenth of PAG limit).
IF the projected dose at the Site Boundary >1000 mrem TEDE OR
> 5000 mrem committed dose equivalent (thyroid), then recommend a General Emergency (bases: PAG limit).
1.2 IF Field Monitoring Teams at the Site Boundary detect any of the doserates described below, make the associated EAL recommendation:
" IF the dose rate at the Site Boundary > 100 mrem/hr TEDE OR
> 500 mremL/hr (3.84E-7 gCi/ml 1-131 equivalent) Committed Dose Equivalent (thyroid) and either is expected to last for more than one hour, recommend a Site Area Emergency (bases: one tenth of PAG limit).
" IF the dose rate at the Site Boundary > 1000 mrem/hr TEDE OR
> 5000 mrem/hr (3.84E-6 tCi/ml 1-131 equivalent) Committed Dose Equivalent (thyroid) and either is expected to last for more than one hour, recommend a General Emergency (bases: PAG limit).
.7 HP/0/B/1009/018 Emergency Action Levels and Protective Page 2 of 2 Action Recommendations
- 2. Determine Protective Action Recommendations (PARs):
2.1 Recommend no protective action, for doses:
S< 1 Rem Total Effective Dose Equivalent OR, S< 5 Rem Committed Dose Equivalent (Thyroid) 2.2 Recommend Evacuation of Population in PAZs identified on Enclosure 5.5 and sheltering of remaining PAZs in the 10-mile EPZ, for doses:
> 1 Rem Total Effective Dose Equivalent (TEDE) OR, 0 > 5 Rem Committed Dose Equivalent (CDE Thyroid).
2.3 Notify the EOFD and State Offsite Dose personnel that the area beyond the 10-mile EPZ has exceeded the Protective Action Guide (PAG) doses, for the following doses:
> 5 Rem Committed Dose Equivalent (CDE Thyroid).
2.3.1 Provide the EOFD and State Offsite Dose personnel with the approximate direction of the plume and the approximate distance at which PAG doses are exceeded.
.8 HP/O/B/1009/018 Emergency Notification Form Completion Page 1 of 2 Example
- 1. Supply information to complete the ENF as follows:
NOTE:
"Offsite Communicators" should actually complete the Emergency Notification Form (ENF) using radiological information supplied by Offsite Dose Assessment.
1.1 At line 10, indicate appropriate box, according to Enclosure 5.4 (procedure section 4.3).
1.1.1 IF release status is "None", go to ENF line 14 (step 1.6 of this enclosure).
1.2 At line 11, indicate that the release is:
"* "Ground Level",
"* "Airborne", and
"* Provide the release "Start time" and "Start date".
"* IF release has stopped, provide the release "Stop time" and "Stop date".
1.3 At line 12, indicate that the release magnitude is in "Curies per sec."
1.3.1 Indicate if the release is "Above" or "Below" normal operating limits, using.4 and RD5 data (procedure section 4.3.3.3).
1.3.2 Supply "Noble Gases," "Particulates," and "lodines" curies per second values from RD5 data.
1.4 At line 13, IF releases < normal operating limits, go to ENF line 14 (step 1.6 of this enclosure).
1.5 IF releases > normal operating limits, indicate if the projection is "New" or "Unchanged" and provide "Projection Time" from RD5 data.
1.5.1 Provide "Estimated Duration" from RD5 data.
1.5.2 Provide "TEDE mrem" and "Thyroid CDE mrem" values from RD5.
1.6 At line 14, supply "Meteorological Data", either from SDS or from RD5.
1.7 At line 15, supply Offsite Dose related "Protective Action Recommendations" as determined from Enclosure 5.5 or RD5 data (procedure section 4.3.3.5).
.8 HPI/B/1/1009/018 Emergency Notification Form Completion Page 2 of 2 Example I-. A. ]THIS IS A DRILL R. E ACT1UAL EMERGENCY [J1 INITIAL, []Pý OUD.W-14P MESSAGE NUMBERý
- 2. SITE:
Oconee UNITz I REPORTED BY;___________________
- 3. TRANSMITITALTIMEWVTS:
I___ I CONFIRMATION PHONE NUMBER,_______
(Eastem)
- ninddtyy
- 4. AUTHENTICATION (9 Roqulro*~__________________
(Number)
(Codeword)
- 5. EMERGENCY CLASSIFICATION:ý A []3 NOTIF=TA1ON OF UNUSUAL EVENT B. E7] ALERT C. nI SITE AREA EMERGENCY 0a C] O3ENERAL EMERGENCY
&. M EmergncyDedwradion At o Tenikna~onAL TIMEOATE_,_-(iI, jj Q!.qNem 16)
(Eutwm)
MmA 4(
yy 7-EMERGENCY DESeRJPTIONSIREAARKS:
- 9. REACTOR STATUS; (E] SHUTDOWN:
TIMEIDATE:
[~____.%POWER 1a-emr(ERncymem~s (Eastern) mmn dd
'yy A.0Li 0NE (Gotlwtm 14)
S. [n POTENTLkL (Go to Item 14)
- 0. fIS OCCURRING D. f]HAS OCCURRE0 TYPE OF RELEAS~E D ELEVATEI'3 S GROUN LEVPL L1] AVRB()RNE
$TARTEiO:
12-0 mCf STOPPED:
Tkne (Eastern)
Date Twne (Eastern)
Date CE] LiUQIO STARTED:
1.STOPPED.
j rkne (Eastern)
IDabe oe (Eastern)
Date RELEASE MAGNITUDE- 0 Curi~s Por Soc 0I Gurlos NORMAL OPERATIiNO UMITS 0] BELOW n ABOVE JW]tIOLE GASES 2.56E400
]IGODINES I-8IE-01
-13.
ESTIMATE OF PROJECTED C)FFSITE DOSE: f]NEW
[]U?4CHANGED PROJECTION TIME12:i5 TEDE (M'newm)
Thyroid% COE (""M~)(Es" SITE BOUNDARY 1,48E+01 2-48E+02 2 MILES ZWE400 497E+01 E$TflAATEQD DURATION 1,25 KRS.
6 MILES 3-03E~.01 6-79E+00 10 MILES O.X3E+00 O.OOE+00
ý14. M5TEOftOI.GICAI. DAT& Ak WiND DIRECTION (VrOi) 20Z0 do" SPEED) (rii0h).
[JSTASIL1Y CLASS 8
BD PRECI~PITATION ("ap) 0,VW1 aim r
15, RAMtýWtJ F~DPv I ECtr AC I RM' A. 0 NO RECOWMENOED PAOTeCThJE ACTIONS 8,[7 EVACUATE
- 0. C3OTHER
- 16. APPROFD BY:____________
____'-EDT:___
ft~arne)(Todoe (Eastunl) mmn dd yy ht Items 8-14 hame not changed. onty items 1-7 and 15-16 are required to be competesd
" Infornian may not bo avs~bIe on initial nottilcalion
May 10, 2000 MEMORANDUM TO FILE OCONEE NUCLEAR SITE
SUBJECT:
Volume A, Oconee Emergency Plan Revision 2000-02 The following revisions were made to the Oconee Nuclear Site Emergency Plan. This revision does not decrease the effectiveness of the plan as evidenced by the following:
Title page revised for current revision number and date (Revision 2000-02, May, 2000)
List of Effective Pages, page 1 thru 6 Record of changes, page 4, added revision 2000-02 Purpose/Scope/Planning Basis Description of change:
Page 1-5, Rev. 2000-02, New Map Reason for change:
Page 1-5 reflects new revision number Map has been reprinted to show new siren locations.
Section B Description of change:
Page B-2 & B8 B Changed specific managers titles to appointed by Station Manager B Changed Mechanical Systems to Engineer Manager Reason for change:
B Titles change within the organization and this eliminates further changes in the Emergency Plan.
B Mechanical Systems position has been changed to Engineer Manager Section C Description of change:
Corrected typo Reason for change:
To correct the word available I
Appendix 5 Description of change:
Page 1 & 2 - Changed dates to reflect updated Letters of Agreement for # 8, 14, 15, 16, 19, 20, & 23 Reason for change:
Page 1 & 2 - Dates on Agreement Letters 8, 14, 15, 16, 19, 20 & 23 have changed.
Appendix 6 Description of change:
Page 3 - Deleted 36A Reason for change: 36A is no longer a valid copy. The Emergency Planning Manager uses Volume 10A Michael D. Thorne Emergency Planning Manager Oconee Nuclear Site 3
Section D Description of change:
Page 14 - Added statement Reactor Coolant System (RCS) Leakage as defined in RCS Operational Leakage in the Technical Specifications Basis B 3.4.13.
Page 31 - Deleted auxiliary bridge from #2.
Page 71 - Added statement: This EAL applies to structures required to maintain safe operations or to establish or maintain cold shutdown.
Reason for change:
Page 14 - For clarity Page 31 - Auxiliary fuel bridges have been removed from the reactor building.
Page 71 - The basis explanation was expanded to contain statements from the initiating conditions, added clarity.
Section H Description of change:
Page 3, H.5.a - Changed (H-19) to (H-18)
Page 7 - Identification of Emergency kits - deleted H-18 Reason for change:
Page 3 - typo Page 7 - Incorrect Figure numbers Section J Description of change:
Page 2 - Inserted after pathway, and beyond it if necessary. Added statement: If dose projections show that PAGs have been exceeded at 10 miles, the dose assessment code and in-field measurementswhen available, shall be used to calculate doses at various distances down wind to determine how far from the site PAG levels are exceeded. The Radiological Assessment Manager shall forward the results to the EOF Director who will communicate this information to the offsite authorities.
ReasciAi for change:
Page 2,- This change is necessary because Duke Power will address recommendations for protective actions beyond the 10-mile Emergency Planning Zone (EPZ), if warranted.
Section M Description of change:
Page 2-M.3 should be M.2 Reason for change Page 2 - Correction in numbering sequence 2
NFORMTION ONLY
,RO-97, D tDke Power Company PROCEDURE PROCESS RECORD (1) ID No RP/0/B/1000/001 Revision No 008
'--PREPARATION (2)
Station (3)
Procedure Title OCONEE NUCLEAR STATION Emergency Classification (4)
Prepared By Robert Taylor (Signature)
Date 05/24/00 (5)
Requires 10CFR50.59 evaluation?
El Yes (New procedure or revision with major changes)
E3 No (Revision with minor changes)
El No (To incorpo ate previously approved changes)
(6)
Reviewed By (QR)
Date.
35, -O6 Cross-Disciplinary ev*ew By (QR)NA Date
_____,_-6___-
Reactivity Mgmt. Review By (QR)NA Date (7)
Additional Reviews Reviewed By Date Reviewed By D3ate (8)
Temporary Approval (if necessary)
By (SRO/QR)
Date By (QR)
Date (9)
Approved By Date 9-200__
PERFORMANCE (Compare with control copy every 14 calendar days 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:
El Unit 0 El Unit 1 El Unit 2 El Unit 3 Procedure performed on what unit?
El Yes El NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?
El Yes El NA Listed enclosures attached?
El Yes El NA Data sheets attached, completed, dated, and signed?
El Yes El NA Charts, graphs, etc. attached, dated, identified, and marked?
El Yes El NA Procedure requirements met?
Verified By Date Procedure Completion Approved Date (14)
Remarks (Attach additional pages, if necessary)
C)
Duke Power Company Oconee Nuclear Site Emergency Classification Reference Use Procedure No.
RP/O/B/1000/001 Revision No.
008 Electronic Reference No.
OXOO2WOS J ____________________________________________________________
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 three (3) 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 THEN An event occurs on more than one unit concurrently, 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/0/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 AND THEN An event occurs, A lower or higher plant operating mode is reached before the Classification can be made, The classification shall be based on the mode that existed at the time the event occurred.
1.4.5 The Fission Product Barrier Matrix is applicable only to those events that occur at Hot Shutdown or higher.
2 I
1.5 IF THEN RP/0/B/1000/001 Page 3 of 5 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).
A transient event should occur, Review the following guidance:
1.5.1 IF AND THEN 1.5.2 IF THEN An Emergency Action Level (EAL) identifies a specific duration 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),
Classify the event.
A plant condition exceeding EAL criteria is corrected before the specified duration time is exceeded, 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 AND THEN 1.5.4 IF THEN 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)
The condition no longer exists, An emergency shall NOT be declared.
An emergency classification was warranted, but the plant condition has been corrected prior to declaration and notification, 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.
3
RP/0/B/1000/001 Page 4 of 5 A.
IF THEN An Unusual Event condition exists, Make the classification as required.
- 1. The event may be terminated in the same notification or as a separate termination notification.
B.
IF THEN AND An Alert, Site Area Emergency, or General Emergency condition exists, Make the classification as required, 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 AND THEN 2.2.1 The unit is at Hot Shutdown or higher The condition/event affects fission product barriers, GOTO Enclosure 4.1, (Fission Product Barrier Matrix).
Review the criteria listed in Enclosure 4. 1, (Fission Product Barrier Matrix) and make the determination if the event should be classified.
2.3 Review the listing of enclosures to determine if the event is applicable to one of the categories shown.
2.3.1 IF THEN One or more categories are applicable to the event, Refer to the associated enclosures.
2.3.2 Review the EALs and determine if the event should be classified.
A. IF THEN An EAL is applicable to the event, Classify the event as required.
4
RP/0/B/1000/001 Page 5 of 5 2.4 IF The condition requires an emergency classification, THEN GOTO RP/O/B/1000/002, (Control Room Emergency Coordinator Procedure).
- 3. Subsequent Actions 3.1 Continue to review the emergency conditions to assure the current classification continues to be applicable.
- 4. 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 1 18 4.9 Unexpected/Unplanned Increase In Area Monitor Readings 19 4.10 Definitions 20 4.11 Operating Modes Defined In Improved Technical Specifications 23 4.12 Instructions For Using Enclosure 4.1 24 5
EncloQ_.: 4.1 Fission Product Barrier Matrix DETERMINE THE APPROPRIATE CLASSIFICATION USING THE TABLE 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 (I 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 > 1200' F > 15 minutes Rapid unexplained containment of one HPI pump in normal capacity as indicated by a loss of CETC 2! 12000 F OR pressure decrease after increase makeup mode (approx. 160 gpm) subcooling
> 7000 F CETC > 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 > 300 pCi/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 > 10 psig and no environment with P/S leakage > 10 Letdown isolated.
RBCU or RBS gpm in the same SG Entry into the TSOR (Thermal I RIA 57/58 reading _> 1.0 R/hr Hours Since SD RIA57/58 R/hr Hours Since SD RIA57/58 - R/hr Failure of secondary side of SG Shock) operating range results in a direct opening to the 2 RIA 57 reading 2! 1.6 R/hr 0 - < 0.5
>300/150 0 - < 0.5 2! 1800/860 environment with P/S leakage _ 10 2 RIA 58 reading _> 1.0 R/hr gpm in the other SG 0.5 - < 2.0
Ž80/40 0.5 - < 2.0
_400/195 AND 3RIA 57/58 reading >1.0 R/hr Feeding SG with secondary side e 1failure from the affected unit 2.0- 8.0
Ž32/16 2.0- 8.0
> 280/130 HPI Forced Cooling RCS pressure spike > 2750 psig Hydrogen concentration > 9%
Containment isolation is incomplete and a release path to the environment exists Emergency Coordinator/EOF Emergency Coordinator/EOF Emergency Coordinator/EOF Emergency Coordinator/EOF Director Emergency Coordinator/EOF Emergency Coordinator/EOF Director judgment Director judgment Director judgment judgment Director judgment Director judgment UNUSUAL EVENT (1-3 Total Points)
ALERT (4-6 Total Points)
SITE AREA EMERGENCY (7-10 Total Points)
GENERAL EMERGENCY (11-13 Total Points)
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 barriers 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 barrier and potential loss of either third barrier 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 RP/0/B/10b,_, 01 Page 1 of 1 CIRCLE EALS CHOSEN. ADD POINTS TO CLASSIFY. (SEE NOTE BELOW)
Encd(
4.2 Systems M...anctions UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY
- 1.
KCS LEAK*AGE tlBU 14)
OPERATING MODE:
I, 2, 3, 4 A.
Unidentified leakage _> 10 gpin B.
Pressure boundary leakage >_ 10 gptn C.
Identified leakage Ž! 25 gpm
- 2.
UNPLANNED LOSS OF MOST OR ALL SAFETY SYSTEM ANNUNCIATION/
INDICATION IN CONTROL ROOM FOR > 15 MINUTES (BD 15)
OPERATING MODE:
1, 2,3,4 A. I Unplanned loss of> 50% of the following annunciators on one unit for > 15 minutes:
Units 1 & 3 I SAI-9, 14-16, and 18 3 SAI-9, 14-16, and 18 A.2 Loss of annunciators or indicators requires additional personnel (beyond normal shift complemnent) to safely operate the unit
- 3.
INABILITY TO REACH REQUIRED SHUTDOWN WITHIN LIMITS (BD 16)
OPERATING MODE: 1,2,3,4 A.
Required operating mode not reached within TS LCO action statement time (CONTINUED)
- 1.
UNVPLANNE LOSS OF MIST OR ALL SAFETY SYSTEM ANNUNCIATION/
INDICATION IN CONTROL ROOM (BD 19)
OPERATING MODE: 1, 2,3,4 A. I Unplanned loss of> 50% of the following annunciators on one unit for > 15 minutes:
Units I & 3 I SAI-9, 14-16, and 18 3 SAI-9, 14-16, and 18 Unit 2 2 SAI-9, 14-16 AND A.2 Loss of annunciators/indicators requires additional personnel (beyond normal shift complement) to safely operate the unit AND A.3.1 Significant plant transient in progress OR A.3.2 Loss of the OAC and ALL PAM indications (END)
- 1.
INABILITY TO MONITOR A SIGNIFICANT TRANSIENT IN PROGRESS (BD 21)
OPERATING MODE: 1, 2,3,4 A. 1 Unpanned loss of> 50% of the following annunciators on one unit for > 15 minutes:
Units I & 3 I SAI-9, 14-16, and 18 3 SA1-9, 14-16, and 18 Unit 2 2 SAI-9, 14-16 AND A.2 A significant transient is in progress AND A.3 Loss of the OAC and ALL PAM indications AND A.4 Inability to directly monitor any one of the following functions:
I.
- 2.
- 3.
- 4.
- 5.
6.
Suberiticality Core Cooling Heat Sink RCS Integrity Containment Integrity RCS Inventory (END) 7 RP/O/B/I1(
Page 1 of 2
)1 AND Unit 2 2 SAI-9, 14-16 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
(
Encl(
4.2 Systems
-i.
4nctions 8
RP/0/B/1 -(
Page 2 of ý-
UNUSUAL EVENT ALERT SITE AREA EMERGENCY 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 FTS lines, Offsite Radio System, AT&T line) affecting ability to communicate with offsite authorities.
- 5. FUEL CLAD DEGRADATION (BD 18)
OPERATING MODE: All:
A.
DEI - >5¶Ci/ml (END)
INITIAL NOTIFICATION REQUIREMENTS:
SEE EMERGENCY TELEPHONE DIRECTORY NOTIFY 1,2,3,4
EnclosL - 4.3 Abnormal Rad Levels/Radiological Effluent UNUSUAL EVENT ALERT SITE AREA EMERGENCY J
GENERAL EMERGENCY I
ANY UNPLANNED RELEASE OF GASEOUS OR LIQUID RADIOACTIVITY TO THE ENVIRONMENT THAT EXCEEDS TWO TIMES THE SLC LIMITS FOR 60 MINUTES OR LONGER (BD 23)
OPERATING MODE: All A.
Valid indication on radiation monitor RIA 33 of 2 4.06E+06 cpm for > 60 minutes (See Note I)
B.
Valid indication on radiation monitor RIA 45 of 2! 1.33E+06 cpm for> 60 minutes (See Note 1)
C.
Liquid effluent being released exceeds two times SLC 16.11.1 for> 60 minutes as determined by Chemistry Procedure 1).
Gaseous effluent being released exceeds two times SLC 16.11.2 for > 60 minutes as determined by RP Procedure (CONTINUED)
I. ANY UNPLANNED RELEASE OF GASEOUS OR LIQUID RADIOACTIVITY TO THE ENVIRONMENT THAT EXCEEDS 200 TIMES RADIOLOGICAL TECHNICAL SPECIFICATIONS FOR 15 MINUTES OR LONGER (BD 28)
OPERATING MODE: All A.
Valid indication on RIA 46 of > 2.98E+04 cpm for >15 minutes (See Note I)
B. I RIA 33 HIGH Alarm AND B.2 Liquid effluent being released exceeds 200 times the level of SLC 16.11.1 for > 15 minutes as determined by Chemistry Procedure C.
Gaseous effluent being released exceeds 200 times the level of SLC 16.11.2 for >15 minutes as determined by RP Procedure
- 2.
RELEASE OF RADIOACTIVE MATERIAL OR INCREASES IN RADIATION LEVELS THAT IMPEDES OPERATION OF SYSTEMS REQUIRED TO MAINTAIN SAFE OPERATION OR TO ESTABLISH OR MAINTAIN COLD SHUTDOWN (BD 30)
OPERATING MODE: All A.
Valid radiation reading >_ 15 mRad/hr in CR, CAS, or, Radwaste CR B.
Unplanned/unexpected valid area monitor readings exceed limits stated in Enclosure 4.9 (CONTINUED)
I.
BOUNDARY DOSE RESULTING FROM ACTUAL/IMMINENT RELEASE OF GASEOUS ACTIVITY (BD 32)
OPERATING MODE: All A.
Valid reading on RIA 46 of > 2.98E+05 cpm for>15 minutes (See Note 2)
B.
Valid reading on RIA 57 or 58 as shown on.8 (See Note 2)
C.
Dose calculations result in a dose projection at the site boundary of:
> 100 mnRem TEDE or 500 mRem CDE adult thyroid D.
Field survey results indicate site boundary dose rates exceeding _ 100 mRad/hr expected to continue for more than one hour OR D.I Analyses of field survey samples indicate adult thyroid dose commitment of > 500 mRem CDE (3.84 E"7 pCi/ml) for one hour of inhalation NOTE 2: If actual Dose Assessment cannot be completed within 15 minutes, then the valid radiation monitor reading should be used for emergency classification.
(CONTINUED)
- 1. BOUNDARY DOSEr RESUL rTING FROM ACTUAL/ IMMINENT RELEASE OF GASEOUS ACTIVITY (BD 36)
OPERATING MODE: All A.
Valid reading on RIA 46 of 2.98E+06 cpm for >15 minutes (See Note 3)
B.
Valid reading on RIA 57 or 58 as shown on.8 (See Note 3)
C.
Dose calculations result in a dose projection at the site boundary of:
C.I
> 5000 mRem CDE adult thyroid D.
Field survey results indicate site boundary dose rates exceeding >1000 mRad/hr expected to continue for more than one hour OR D. I Analyses of field survey samples indicate adult thyroid dose commitment of 2 5000 mRem CDE for one hour of inhalation NOTE 3: If actual Dose Assessment cannot be completed within 15 minutes, then the valid radiation monitor reading should be used for emergency classification.
(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 1 NOTIFY 1, 2,3,4 Assumplions used for calculation ot vent monitors RIA 45 & 46:
Average annual meteorology (1.672 E-6 sec/m'), -emi-lcevalcd Vent ilnw rate 65,M(S) clmt (average daily ltow rne)
No credit is taken for vent filtration One hour release duration for atJnsual Event, 15 mtinute duration lor Alert, Site Area Emergency, General Emergency General Enwrgencr PAGs are I rem TEDE and 5 rem CDE: Sim Area Emergency determination is based on 10% of the General Emnergenciy PAGs Calculations for moinitor readings are based on whole body dose Standard ODCM guidance together with NUMARC guidance indicates that cittuent releases are based tin Technical Specification releases RP/0/BI /10 Page 1 of 2 J1 NOTE 1: If monitor reading is sustained for the time period indicated in the EAL AND the required assessments (procedure calculations) cannot be completed within this period, declaration must be made on the valid Radiation Monitor reading.
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
7.
(
.3 Abnormal Rad Levels/Radiological Effluent RP/O/B/1000/001 Page 2 of 2 UNUSUAL EVENT
[
ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 2
UNEXPECTED INCREASE IN PLANT
- 3.
MAJOR DAMAGE TO IRRADIATED
- 2.
LOSS OF WATER LEVEL IN THE RADIATION OR AIRBORNE FUEL OR LOSS OF WATER LEVEL REACTOR VESSEL THAT HAS OR CONCENTRATION (BD 25)
THAT HAS OR WILL RESULT IN THE 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 A. I Failure of heat sink causes loss of Cold core Shutdown condition A.
Valid RIA 3, 6, 41, OR 49 HIGH Alarm B.
Uncontrolled water 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.
I R/hr radiation reading at one foot away from C
Report of visual observation of irradiated fuel makeup a damaged storage cask located at the ISFSI uncovered B. I Failure of heat sink causes loss of Cold Shutdown condition 1).
Valid area monitor readings exceeds limits I).
Operators determine water level drop in either siated 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 (END) makeup (END)
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 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 10
Enclok., 4.4 Loss of Shutdown Functions RP/O/B/ 10K1 1I Page 1 of 2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY j
GENERAL EMERGENCY
- i.
FAILURE OF RPS TO COMPLETE OR INITIATE A Rx SCRAM (BD 39)
OPERATING MODE 1, 2, 3 A. I Valid reactor trip signal received or required WITHOUT automatic scram AND A. 1.1 DSS has inserted Control Rod Groups 5,6,7 OR A. 1.2 Manual trip from the Control Room is successful and reactor power is less than 5% and decreasing
- 2.
INABILITY TO MAINTAIN PLANT IN COLD SHUTDOWN (BD 41)
OPERATING MODE:
5,6 A. I Loss of LPI and/or LPSW AND A.2 Inability to maintain RCS temperature below 200' F as indicated by either of the following:
A.2. I RCS temperature at the LPI Pump Suction OR A.2.2 Visual observation (END)
- 1.
FAILURE OF RPS TO COMPLETE OR INITIATE A Rx SCRAM (BD 42)
OPERATING MODE: 1, 2 A. I Valid reactor trip signal received or required WITHOUT automatic scram AND A.2 DSS has NOT inserted Control Rod Groups 5, 6, 7 AND A.3 Manual trip from the Control Room was NOT successful in reducing reactor power to less than 5% and decreasing
- 2.
COMPLETE LOSS OF FUNCTION NEEDED TO ACHIEVE OR MAINTAIN HOT SHUTDOWN (BD 43)
OPERATING MODE: 1, 2,3,4 A.
Average of the 5 highest CETCs _>1200' F shown on ICCM B.
Unable to maintain reactor subcritical C.
SSF feeding SG per EOP (CONTINUED)
- 1.
FAILURE OF RPS TO COMPLETE AUTOMATIC SCRAM AND MANUAL SCRAM NOT SUCCESSFUL WITH INDICATION OF CORE DAMAGE (BD 45)
OPERATING MODE: 1, 2 A. I Valid Rx trip signal received or required WITHOUT automatic scram AND A.2 Manual trip from the Control Room was NOT successful in reducing reactor power to < 5%
and decreasing AND A.3 Average of the 5 highest CETCs >1200' F on ICCM (END) 11 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
Enclos. c 4.4 Loss of Shutdown Functions I
RP/O/B/10,, O01 Page 2 of 2 12 UNUSUAL EVENT ALERT SITE AREA EMERGENCY
]GENERAL EMERGENCY
- 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 A. I Failure of heat sink causes loss of Cold Shutdown conditions AND A.2 LT-5 indicates 0 inches after initiation of RCS Makeup B. I Failure of heat sink causes loss of Cold Shutdown conditions AND B.2 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
/
(
Enclos*_
4.5 Loss of Power RP/O/B/100i.l Page 1 of 1 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY
- 1.
LOSS OF ALI, 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 FOR GREATER LOSS OF ALL ONSITE AC POWER TO LOSS OF ALL ONSITE AC POWER TO POWER AND ONSITE AC POWER THAN 15 MINUTES (BD 47)
ESSENTIAL BUSSES (BD 49)
ESSENTIAL BUSSES (BD 51)
(BD 54)
OPERATING MODE: All OPERATING MODE: 5,6 OPERATING MODE: 1,2,3,4 OPERATING MODE: 1, 2,3,4 Defueled A. I Loss of all offsite AC power to both the Red A. I MFB I and 2 de-energized A. I MFB I and 2 de-energized and Yellow Busses for> 15 minutes A. I MFB I and 2 de-energized AND AND AND AND A.2 Failure to restore power to at least one MFB A.2 SSF fails to maintain Hot Shutdown A.2 Failure to restore power to at least one MFB within 15 minutes from the time of loss of A.2 Unit auxiliaries are being supplied from within 15 minutes from the time of loss of both both offsite and onsite AC power Keowee or CT5 offsite and onsite AC power AND
- 2.
UNPLANNED LOSS OF REQUIRED DC
- 2.
AC POWER CAPABILITY TO
- 2.
LOSS OF ALL VITAL DC POWER A.3 At least one of the following conditions exist:
POWER FOR GREATER THAN 15 ESSENTIAL BUSSES REDUCED TO A (BD 52)
MINUTES (BD 48)
SINGLE SOURCE FOR GREATER THAN A.3. I Restoration of power to at least one 15 MINUTES (BD 50)
OPERATING MODE:
1, 2,3,4 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 OPERATING MODE: 1, 2, 3, 4 A. I Unplanned loss of vital DC power to required OR A. I Unplanned loss of vital DC power to required DC busses as indicated by bus voltage less than A.3.2 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 ongradaion of corier loss of all but one of:
AND monitoring AND Unit Normal Transformer A.2 Failure to restore power to at least one required (END)
A.2 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 CT4 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
.i
EnclI 1.6 Fires/Explosions an,., iecurity Actions RP/0/a/ge Page I of(1 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY
- 1.
FIRES/EXPLOSIONS WITHIN THE PILANT (BD 57)
OPERATING MODE: All NOTE: Within the plant means Turbine Building, Auxiliary Building, Reactor Building, Keowee Hydro.
A.
Fire within the plant not extinguished within 15 minutes of Control Room notification or verification of a Control Room alarm B.
Unanticipated explosion within the plant resulting in visible danage to permanent structures/equipment
- 2.
CONFIRMED SECURITY THREAT INDICATES POTENTIAL DEGRADATION IN THE LEVEL OF SAFETY OF PLANT (BD 58)
OPERATING MODE: All NOTE: RP/0/B/1000/007, (Security Event), shall be used in conjunction with all security related emergency classifications.
A.
Discovery of bomb within plant protected area and outside security vital areas B.
Hostage/Extortion situation C.
Violent civil disturbance within the owner controlled area (END)
- 1.
PIRI/IEXPLOSION AFFECTING OPERABILITY OF PLANT SAFETY SYSTEMS REQUIRED TO ESTABLISH/MAINTAIN SAFE SHUTDOWN (BD 59)
OPERATING MODE: All NOTE: Only one train of a system needs to be affected or damaged in order to satisfy this condition.
A. I Fire/explosions AND A. 1. 1 Affected safety-related system parameter indications show degraded performance OR A. 1.2 Plant personnel report visible damage to permanent structures or equipment required for safe shutdown 2
SECURITY EVENT IN A PLANT PROTECTED AREA (BD 60)
OPERATING MODE: All NOTE: RP/0/B/1000/007, (Security Event),
shall be used in conjunction with all security related emergency classifications.
A.
Intrusion into plant protected area by a hostile force B.
Bomb discovered in an area containing safety related equipment (END)
- 1.
SECURITY EVENT IN A PLANT VITAL AREA (BD 61)
OPERATING MODE: All NOTE: RP/0/B/1000/007, (Security Event),
shall be used in conjunction with all security related emergency classifications A.
Intrusion into any of the following plant areas by a hostile force:
Reactor Building Auxiliary Building Keowee Hydro B.
Bomb detonated in any of the following areas:
"* Keowee Hydro
"* Keowee Datn
"* ISFSI
"* Reactor Building
"* Auxiliary Building
"* SSF (END) 1.
SECURITY EVENT RESULTING IN LOSS OF ABILITY TO REACH AND MAINTAIN COLD SHUTDOWN (BD 621 OPERATING MODE: All NOTE: RP/0/B/1000/007, (Security Event),
shall be used in conjunction with all security related emergency classifications A.
Loss of physical control of the control room due to security event B.
Loss of physical control of the Aux Shutdown panel and the SSF due to a Security Event (END) 14 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 j NOTIFY 1, 2,3,4 NOTIFY 1, 2, 3, 4
(.7 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety UNUSUAL EVENT f
ALERT SITE AREA EMERGENCY GENERAL EMERGENCY
- 1.
NATURAL AND DESTRUCTIVE PHENOMENA AFFECTING THE PROTECTED AREA (BD 64)
OPERATING MODE: All A.
Tremor felt and valid alarm on the strong motion accelerograph B
Tornado striking within Protected Area Boundary C.
Vehicle crash into plant structures/systems within the Protected Area Boundary I).
Turbine failure resulting in casing penetration or damage to turbine or generator seals (CONTINUED)
- 1.
NATURAL AND DESTRUCTIVE PHENOMENA AFFECTING THE PLANT VITAL AREA (BD 69)
OPERATING MODE: All A.
Tremor felt and seismic trigger actuates (0.05g)
B. I Tornado, high winds, missiles resulting from turbine failure, vehicle crashes, or other catastrophic event NOTE: Only one train of a safety-related system needs to be affected or damaged in order to satisfy these conditions.
2.
B. 1.1 Visible damage to permanent structures or equipment required for safe shutdown of the unit OR B. 1.2 Affected safety system parameter indications show degraded performance RELEASE OF TOXIC/FLAMMABLE GASES JEOPARDIZING SYSTEMS REQUIRED TO MAINTAIN SAFE OPERATION OR ESTABLISH MAINTAIN COLD SHUTDOWN (BD 71)
OPERATING MODE: All A.
Report/detection of toxic gases in concentrations that will be life-threatening to plant personnel B.
Report/detection of flammable gases in concentrations that will affect the safe operation of the plant:
"* Reactor Building
"* Auxiliary Building
"* Turbine Building
"* Control Room (CONTINUED)
- 1.
CONTROL ROOM EVACUATION AND PLANT CONTROL CANNOT BE ESTABLISHED (BD 75)
OPERATING MODE: All A. I Control Room evacuation has been initiated AND A.2 2.
Control of the plant cannot be established from the Aux Shutdown Panel or the SSF within 15 minutes KEOWEE HYDRO DAM FAILURE (BD 76)
OPERATING MODE: All A.
Imminent/actual dam failure includes any of the following:
"* Keowee Hydro Darn
"* Little River Dam
"* Dikes A, B, C, or D
"* Intake Canal Dike
- 3.
OTHER CONDITIONS WARRANT DECLARATION OF SITE AREA EMERGENCY (BD 77)
OPERATING MODE:
All A.
Emergency Coordinator/EOF Director judgment (END)
- 1.
OTHER CONDITIONS WARRANT DECLARATION OF GENERAL EMERGENCY (BD 78)
OPERATING MODE: All A. I Emergency Coordinator/EOF Director judgment indicates:
A. 1. 1 Actual/imminent substantial core degradation with potential for loss of containment OR A. 1.2 Potential for uncontrolled radionuclide releases that would result in a dose projection at the site boundary greater than 1000 mRem TEDE or 5000 mRem CDE Adult Thyroid (END)
RP/O/B/1000/001 Page 1 of 3 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
Ench4 1.7 Natural Disasters, Hazards and Otht. Conditions Affecting Plant Safety RP/0/B/1 Page 2 of UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY PHENOMENA AFFECTING KEOWEE HYDRO (BD 66)
OPERATING MODE: All A.
Reservoir elevation >_ 807 feet with all spillway gates open and the lake elevation continues to rise B.
Seepage readings increase or decrease greatly or seepage water is carrying a significant amount of soil particles C
New area of seepage or wetness, with large amounts of seepage water observed on dam, dam toe, or the abutments I).
Slide or other movement of the dam or abutments which could develop into a failure E.
Developing failure involving the powerhouse or appurtenant structures and the operator believes the safety of the structure is questionable
- 3.
RELEASE OF TOXIC OR FLAMMABLE GASES DEEMED DETRIMENTAL TO SAFE OPERATION OF THE PLANT (BD 67)
OPERATING MODE: All A.
Report/detection of toxic or flammable gases that could enter within the site area boundary in amounts that can affect normal operation of the plant B.
Report by local, county, state officials for potential evacuation of site personnel based on offsite event (CONTINUED)
- 3.
1 U1'*.D1*
DUILUIt'JI rLUOD (BD
/72)
OPERATING MODE: All A.
Turbine Building flood requiring use of A P/1,2,3/A/1700/10, (Uncontrolled Flooding Of Turbine Building)
- 4.
CONTROL ROOM EVACUATION HAS BEEN INITIATED (BD 73)
OPERATING MODE: All A. I Evacuation of Control Room AND A. 1. I Plant control IS established from the Aux shutdown Panel or the SSF OR A. 1.2 Plant control IS BEING established from the Aux Shutdown Panel or SSF
- 5.
OTHER CONDITIONS WARRANT CLASSIFICATION OF AN ALERT (BD 74)
OPERATING MODE: All A. I Emergency Coordinator judgment indicates that:
A. 1. 1 Plant safety may be degraded AND A. 1.2 Increased monitoring of plant functions is warranted (END) 16 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
Encl 1.7 Natural Disasters, Hazards and Othe1 Conditions Affecting Plant Safety 17
(
)I RP/0/3/1 Page 3 of 3 UNUSUAL EVENT ALERT SITE 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 TELEPHONE DIRECTORY NOTIFY 1, 2,3,4
(
Enclost.. e 4.8 Radiation Monitor Readings for Emergency Classification Rp/0/B/! I 0t, 00 1 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/in 3)
- 2.
Design basis leakage (5.6 E6 ml/hr)
- 3.
One hour release duration
- 4.
General Emergency PAGs are I 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
(
Enclos'U-e 4.9 Unexpected/Unplanned Increase In Area Monitor Readings P/a/B/I o Page I of I NOTE:
This Initiating Condition is not intended to apply to anticipated temporary increases due to planned events (e.g.; incore detector movement, radwaste container move.ment, depleted resin transfers, etc.).
UNITS 1, 2,3 MONITOR NUMBER UNUSUAL EVENT 1000x ALERT NORMAL LEVELS mRAD/HR rmRAD/HR RIA 7, Hot Machine Shop Elevation 796 150
_5000 RIA 8, Hot Chemistry Lab Elevation 796 4200
Ž> 5000 RIA 10, Primary Sample Hood Elevation 796 830
> 5000 RIA 11, Change Room Elevation 796 210
Ž> 5000 RIA 12, Chem Mix Tank Elevation 783 800
Ž> 5000 RIA 13, Waste Disposal Sink Elevation 771 650
> 5000 RIA 15, HPI Room Elevation 758 NOTE*
> 5000 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
.10 RP/O/B/1000/001 Definitions/Acronyms Page 1 of 3
- 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 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.
1.7 EXTORTION - An attempt to cause an action at the station by threat of force.
1.8 FIRE - Combustion characterized by heat and light. Sources of smoke, such as slipping drive belts or overheated electrical equipment, do NOT constitute fires. Observation of flames is preferred but is NOT required if large quantities of smoke and heat are observed.
1.9 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.
1.10 HOSTAGE - A person or object held as leverage against the station to ensure demands will be met by the station.
1.11 INTRUSION/INTRUDER - Suspected hostile individual present in a Protected Area without authorization.
1.12 INABILITY TO DIRECTLY MONITOR - Operational Aid Computer data points are unavailable or gauges/panel indications are NOT readily available to the operator.
20
.10 RP/0/B/1000/001 Definitions/Acronyms Page 2 of 3 1.13 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 MFBs were de-energized.
1.14 PROTECTED AREA - Encompasses all Owner Controlled Areas within the security perimeter fence.
1.15 REACTOR COOLANT SYSTEM (RCS) LEAKAGE - RCS Operational Leakage as defined in the Technical Specification Basis B 3.4.13.
1.16 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.
1.17 SABOTAGE - Deliberate damage, mis-alignment, or mis-operation of plant equipment witl the intent to render the equipment unavailable.
1.18 SAFETY-RELATED SYSTEMS AREA - Any area within the Protected area 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.
1.19 SIGNIFICANT TRANSIENT - An unplanned event 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 1.20 SITE AREA EMERGENCY - Events are in process or have occurred which involve actua 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.
1.21 SELECTED LICENSEE COMMITMENT (SLC) -Chapter 16 of the FSAR 1.22 SITE BOUNDARY - That area, including the Protected Area, 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).
1.23 TOXIC GAS - A gas that is dangerous to life or health by reason of inhalation or skin contact (e.g.; Chlorine).
1.24 UNCONTROLLED - Event is not the result of planned actions by the plant staff.
21
.10 RP/O/B/1000/001 Definitions/Acronyms Page 3 of 3 1.25 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.
1.26 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.
1.27 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.
1.28 VIOLENT - Force has been used in an attempt to injure site personnel or damage plant property.
1.29 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, 22
.11 Operating Modes Defined In Improved Technical Specifications RP/O/B/1000/001 Page 1 of 1 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.
23
.12 Instructions For Using Enclosure 4.1 RP/O/B/1000/001 Page 1 of 2
- 1. Instructions For Using Enclosure 4.1 - Fission Product Barrier Matrix 1.1 I 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.
24
.12 RP/O/B/I 000/001 EXAMPLE:
Instructions For Using Enclosure 4.1 Page 2 of 2 Failure to properly isolate a 'B' MS Line Rupture outside containment, results in extremely severe overcooling.
TSOR entry conditions were satisfied.
Stresses on the 'B' S/G resulted in failure of multiple S/G 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 TSOR 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 I
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.
25
R07)
INFORIMAT1CN ONLY Duke Power Company (IDNo RP/0/B/1000/019 PROCEDURE PROCESS RECORD Revision No 007 PREPARATION (2)
Station OCONEE NUCLEAR STATION (3)
Procedure Title Technical Support Center Emergency Coordinator Procedure (4)
Prepared By Rodney Brown (Signature) 9ate 05/08/2000 (5)
Requires 10CFR50.59 evaluation?
l] Yes (New procedure or revision with major changes) 0l No (Revision with minor changes)
ElNo (To incorpoate p
- ,#ously app edc ags (6)
Reviewed By (QR)
Date Cross-Disciplinary Review By (QR)NA-Date g
t20 Reactivity Mgmt. Review By (QR)NA Date (7)
Additional Reviews Reviewed By Date Reviewed By Date (8)
Temporary Approval (if necessary)
By (SRO/QR)
Date By (QR)
Date (9)
Approved By _
."h/rLk Date PERFORMANCE (Compare with control copy every 14 calendar days while work is being performed.)
(10)
Compared with Control Copy Date Compared w ith Control Copy Date Compared with Control Copy Date (11)
Datc(s) Performed Work Order Number (WO#)
COMPLETION (12)
Procedure Completion Verification:
"El Unit 0 El Unit 1 El Unit 2 El Unit 3 Procedure performed on what unit?
"El Yes El NA Check lists and/or blanks initialed. signed, dated. or filled in NA. as appropriate?
"El Yes El NA Listed enclosures attached?
El Yes El NA Data sheets attached, completed, dated, and signed?
El Yes El NA Charts. graphs, etc. attached. dated, identified, and marked?
El Yes El NA Procedure requirements met?
Verified By Date (13)
Procedure Completion Approved Date (14)
Remarks (Attach additional pages, if necessary)
Duke Power Company Oconee Nuclear Station Technical Support Center Emergency Coordinator Procedure Reference Use Procedure No.
RP/O/B/1000/019 Revision No.
007 Electronic Reference No.
OX002WPG L ___________________________________________________________
RP/O/B/1000/019 Page 2 of 20 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 three (3) 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:
e 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: 0l at left of steps may be used for procedure place keeping (I').
Major events are required to be documented in the TSC Emergency Coordinator Log.
El 2.1 Establish the Technical Support Center as operational by doing the following:
El 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.
El 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.
[] 2.1.3 Determine the following minimum staff requirements for TSC activation.
Emergency Coordinator Dose Assessment Liaison Nuclear Engineering Offsite Communicator Tech Assistant to EC NAME
RP/O/B/1000/019 Page 3 of 20 El 2.1.4 Verify that the phone system is operational or make other provisions for communications.
0l 2.1.5 Verify that the OSC is Operational.
O 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).
El 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 El 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.
El 2.5 Discuss any off-site radiological concerns with the TSC Dose Assessment Liaison.
El 2.6 Announce the following over the TSC/OSC Public Address System:
El 2.6.1 The current Emergency Classification level and plant status.
El 2.6.2 "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."
El 2.6.3 "Personnel should assume that areas are contaminated until surveyed by RP."
El 2.6.4 "No eating, drinking, or smoking until the TSC and OSC are cleared by RP."
RP/O/B/1000/019 Page 4 of 20 El 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 (name)
I am the Emergency Coordinator.
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 was 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 (name)
I am the Emergency Coordinator.
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.
El 2.8 Contact the State Director Emergency Planning at the SEOC.
NAME TELEPHONE NUMBERS SDEP 1(803) 737-8564 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 1(864) 898-5943 Pickens CDEP
RP/O/B/1000/019 Page 5 of 20 51 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/0/B/ 1000/019 Page 6 of 20 0J 2.10 Review emergency classification and verify that it meets the criteria of RP/0/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.
E-C. IF THEN Condition B at Keowee exists, Notify the Area Hydro Manager (refer to Section 6 of the Emergency Telephone Directory, Keowee Hydro Project Dam/Dike Notification).
El D. Discuss classification with SDEP and CDEP NAME TELEPHONE NUMBERS SDEP Oconee CDEP Pickens CDEP 1(803) 737-8564 1(864) 638-4200 1(864) 898-5943 (Unusual Event Classification guidance continued on next page)
RP/O/B/1000/019 Page 7 of 20 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.
- 1. Notify Emergency Planning that the Unusual Event has been terminated.
0
- 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 8 of 20 0 2.10.2 IF An Alert Classification exists, THEN Initiate the following actions:
"U A. Notify counties/state within 15 minutes of event classification "U B. 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 U C. Notify NRC of change in classification U D. Start ERDS (TSC NRC Communicator - RP/0/B/1000/003A, ERDS Operation)
U E.
Discuss change in classification with the State Director of Emergency Preparedness (SDEP) and County Directors of Emergency Preparedness (CDEP)
NAME SDEP TELEPHONE NUMBERS 1(803) 737-8564
- 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 F. IF THEN Condition B at Keowee exists, Notify the Area Hydro Manager (refer to Section 6 of the Emergency Telephone Directory, Keowee Hydro Project Dam/Dike Notification).
(Step 2.10.3, Site Area Emergency Classification on next page)
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}
RP/O/B/ 1000/019 Page 9 of 20 LI 2.10.3 IF A Site Area Emergency Classification exists, THEN Initiate the following actions:
LI A. Notify counties/state within 15 minutes of event classification LI 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.
LI 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 LI D. Notify NRC of change in classification LI E.
Start ERDS (TSC NRC Communicator - RP/0/B/1000/003A, ERDS Operation)
LI F.
Discuss change in classification with SDEP and CDEP NAME TELEPHONE NUMBERS SDEP 1(803) 737-8564
- 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 LI G. IF Condition A, Dam Failure (Keowee or Jocassee) exists, THEN REFER TO Step 3.1.
RP/O/B/1000/019 Page 10 of 20 El H. IF Condition B at Keowee exists, THEN Notify the Area Hydro Manager (refer to Section 6 of the Emergency Telephone Directory, Keowee Hydro Project Dam/Dike Notification).
(Step 2.10.4, General Emergency Classification, on next page)
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}
RP/O/B/1000/019 Page 11 of 20 2.10.4 IF A General Emergency Classification exists, THEN Initiate the following actions:
El 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/0/B/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) 737-8564
- 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
RP/O/B/1000/019 Page 12 of 20 0 H. IF Condition A, Dam Failure (Keowee or Jocassee) exists, THEN REFER TO Step 3.1.
111.
IF THEN Condition B at Keowee exists, Notify the Area Hydro Manager (refer to Section 6 of the Emergency Telephone Directory, Keowee Hydro Project Dam/Dike Notification).
(Step 2.11 on next page)
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}
RP/O/B/ 1000/019 Page 13 of 20 0] 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 30minutes should be used to complete turnover after the EOF is declared Operational. (1}
LI 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 Initial Emergency Classification Time Time
"* Initiating Condition/Unit affected
"* 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 Airborne Liquid __
Is occurring __ Has occurred Time Normal Operating Limits:
Below __
Above Protective Action Recommendations Site Evacuation NO Time of evacuation Last Message Number YES If yes, location Next Message due at
RP/0/B/1000/019 Page 14 of 20 2.11.2 Emergency Coordinator turnover to EOF Director complete.
EOF Activated Time LI 2.11.3 Request NRC Communicator to notify the NRC EOC that the EOF is activated.
- 3. Subsequent Actions 3.1 IF THEN Condition A, Dam Failure (Keowee or Jocassee) exists, Perform the following actions:
0I 3.1.1 Notify the Duke Power System Coordinator (System Operations Center) and provide information related to the event. Refer to Section 6 of the Emergency Telephone Directory.
0I 3.1.2 Relocate Keowee personnel to the Operational Support Center if events occur where their safety could be affected.
0I 3.1.3 Notify the Duke Power System Coordinator if Keowee personnel are relocated to the OSC.
NOTE:
A loss of offsite communications capabilities (Selective Signaling and the WAN) could 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 trough Bad Creek should be started AS SOON AS POSSIBLE.
LI 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.
LI 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 15 of 20 EJ 3.1.7 Ensure Operations has dispatched operators to the SSF and established communications.
0 3.2 Periodically evaluate with TSC personnel the need to conduct evacuation. Log the status of this action on the TSC Status Board.
NOTE:
9 Twenty-four (24) hour staffing must be accomplished prior to personnel being evacuated from the site. RP/0/B/ 1000/010, (Procedure for Emergency Evacuation/Relocation of Site Personnel).
- 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/1000/019 Page 16 of 20 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.
"El A. Request OSC to verify operability of the Control Room Ventilation System per AP/1,3/A/1700/018, (Abnormal Release of Radioactivity).
"O B. 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.
El 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
RP/O/B/1000/019 Page 17 of 20 El 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.
Li 3.5 IF An NRC team is enroute, THEN Perform the following steps:
Li 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.
Li 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.4 (NRC Site Team Response Form).
Li 3.5.3 Notify OSC Manager and request RP Manager and Security to implement actions required to process NRC Site Team.
Li 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.
RP/O/B/1000/019 Page 18 of 20 E] 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) l 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 THEN Offsite fire apparatus is needed to provide water to the Spent Fuel Pool, 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).
[1 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/O/B/1000/019 Page 19 of 20 El 3.11 IF THEN Plant conditions require a decision to implement 10CFR50.54(x),
Perform the following steps:
El 3.11.1 Obtain approval of a Licensed Senior Reactor Operator prior to taking any action.
0l 3.11.2 Document decision and actions taken in the Reactor Operator Log Book.
0l 3.11.3 Document decision and actions taken in the TSC Emergency Coordinator Log.
NOTE:
NRC must be notified of any 10CFR50.54(x) decisions and actions within one (1) hour.
El 3.11.4 Request TSC NRC Communicator to report decision and actions taken to the NRC.
NOTE:
10CFR50.72 requires NRC notification for specific plant conditions.
El 3.12 IF THEN Plant conditions require NRC notification under 10CFR50.72, Request the TSC NRC Communicator to provide this notification using the guidance in OMP 1-14, (Notifications).
NOTE:
10CFR50.54(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 I0CFR50.54(x) actions by a Licensed Senior Operator.
Implementation of Oconee Severe Accident Guidelines (OSAG) requires the use of 10CFR50.54 (x) and (y) provisions.
RP/0/B/1000/019 Page 20 of 20 El 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/A/I 102/023, (Operation Of Containment Hydrogen Recombiner System).
3.13.2 Request the Operations Superintendent to have Operations personnel refer to OP/0/A/1 104/019 (Control Room Ventilation System).
El 3.14 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.
3.14.1 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.
3.15 Emergency Planning Section shall be responsible for completing all Procedure Process Records of Emergency Plan Implementing procedures initiated by the TSC.
- 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
.1 Operations Shift Manager To TSC Emergency Coordinator Turnover Sheet EMERGENCY CLASSIFICATION RP/O/B/1000/019 Page 1 of 2 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
.1 Operations Shift Manager To TSC Emergency Coordinator Turnover Sheet Classification Procedure in Use:
RP/0/B/1000/002 Control Room Emergency Coordinator Procedure Is RP/0/B/1000/003A, ERDS Operation, in use?
Yes No __
Is RP/0/B/1000/007, (Security), in use?
Is RP/O/B/1000/016, (Medical), in use?
Is RP/0/B/1000/0 17, (Spill Response), in use?
Is RP/0/B/1000/022, (Fire/Flood), in use?
Yes No Yes No Yes No Yes No RP/O/B/ 1000/019 Page 2 of 2 If Yes, Unit No. __
Step No. __
If Yes, Step No. __
If Yes, Step No. __
If Yes, Step No. __
If Yes, Step No. __
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 Emergency Coordinator/TSC Time:
Time:
CDEP EC EOF EOFD FTS2000 LEC NRC EOC OSC PAR SCC SDEP SEOC SWP TSC.2 Emergency Preparedness Acronyms County Director of Emergency Preparedness Emergency Coordinator Emergency Operations Facility Emergency Operation, Facility Director NRC Emergency Telephone Communications System Law Enforcement Center Nuclear Regulatory Commission Emergency Operations Center Operational Support Center Protective Action Recommendation State/County Communicator State Director of Emergency Preparedness State Emergency Operations Center State Warning Point Technical Support Center RP/O/B/ 1000/019 Page 1 of 1
Enclosure
(
TSC Personnel Log DATE:
PRIMARY RELIEF POSITION NAME SOCIAL SECURITY TIME SHIFT NAME SOCIAL SECURITY SHIFT IN AT SCHEDULE SCHEDULE (Last, First, MI)
EMPLOYEE ID TSC
(
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 RP/O/B/1000/019 Page 1 of 2
(
Enclosure -.
TSC Personnel Log RP/O/B/1000/019 Page 2 of 2 PRIMARY I
RELIEF POSITION NAME SOCIAL SECURITY TIME SHIFT NAME SOCIAL SECURITY SHIFT (Last, First, MI)
IN AT SCHEDULE (Last, First, MI)
SCHEDULE EMPLOYEE ID TSC EMPLOYEE ID TSC/OSC Liaison Support Engineering Manager NRC Communicator (ENS)
Dose Assessors Emergency Planning Community R elations (W O E)...................................
Local I/T
.4 RP/O/B/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
.5 RP/O/B/1000/019 Emergency Classification Termination Page 1 of 1 Criteria IF The following guidelines applicable to the present emergency condition have been met or addressed, THEN An emergency condition may be considered resolved when:
El 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.
0l 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.
Date/Initial/Time El 1.13 Emergency terminated. Request the TSC Offsite Communicator to complete an Emergency Notification Form for a Termination Message using guidance in RP/0/B/1000/015B, (Offsite Communications From The Technical Support Center), and provide information to offsite agencies.
0 Return to Step 2.10.1.E. I
.6 RP/O/B/1000/019 Alternate TSC/OSC Activation Page 1 of 2 S1.
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/0/B/1000/25 (OSC Manager Procedure).
El 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) 0l 1.3.2 TSC Logkeeper El 1.3.3 Emergency Planning (if available) 0 1.4 Return to Step 2.2 of this procedure and complete turnover with the OSM.
El 1.4.1 Report to the Alternate TSC with remaining support personnel after completion of turnover.
.6 RP/0/B/1000/019 Alternate TSC/OSC Activation Page 2 of 2
- 2. Activation of the Alternate TSC/OSC 11 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 El 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.
El 2.7 Return to Step 3.4.2 of this procedure after reporting to the Alternate TSC.
.7 References RP/O/B/1000/019 Page 1 of 1 PIP 0-98-04996 PIP 0-99-00743 I.
2.
(R(06-97)
INFOWT14 OL Duke Power Company PROCEDURE PROCESS RECORD (I) ID) No RI/0/B/1000/020 Rcvision No 004 "rIREPARATION (2)
Station (3)
Procedure Title OCONEE NUCLEAR STATION Emergency Operations Facility Director Procedui re (4)
Prepared By Rodney Brown (Signature) t (5)
Re uires IOCFR50.59 evaluation?
L7'Yes (New procedure or revision with major changes)
El No (Revision with minor changes) 11 No (To incorporate pr uyap a
(6)
Reviewed By
,tjia./'
._=
(QR)
Cross-Disciplinary Review By (QR)NA,21!
Reactivity Mgmt. Review By (QR)NA (7)
Additional Reviews Reviewed By Reviewed By Date 05/16/2000 Date Date Date Date Date Temporary Approval (if necessary)
By (SRO/QR)
Date By (QR)
Date (9)
Approved By.
Date 0-0 0 PERFORMANCE (Compare with control copy every 14 calendar days 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:
El Unit 0 E] Unit 1 0l Unit 2 El Unit 3 Procedure performed on what unit?
0l Yes Dl NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?
El Yes 0l NA Listed enclosures attached?
LI Yes Dl NA Data sheets attached, completed, dated, and signed?
El Yes 11 NA Charts, graphs, etc. attached, dated, identified, and marked?
E0 Yes Dl NA Procedure requirements met?
Verified By Date (13)
Procedure Completion Approved Date (14) Remarks (Attach additional pages, if necessary)
Emergencv 0mrations Facifitv Director Procedure Z"
Duke Power Company Oconee Nuclear Site Emergency Operations Facility Director Procedure Reference Use Procedure No.
RP/I/B/1000/020 Revision No.
004 Electronic Reference No.
OX002WPH
RP/O/B/1000/020 Page 2 of 7 Emergency Operations Facility Director Procedure NOTE:
This procedure is an implementing procedure to the Oconee Nuclear Site Emergency Plan and must be forwarded to Emergency Planning within three (3) working days of approval.
- 1. Symptoms 1.1 Conditions exist where events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant and activation of the Emergency Response Organization has been initiated.
- 2. Immediate Actions NOTE:
e Place Keeping Aids: LI at left of steps may be used for procedure place keeping (I2).
Major events are required to be documented in the EOF Director's log.
- The EOF must be operational within 75 minutes of an Alert or higher classification.
Turnover may or may not have occurred. Turnover should occur with the TSC at a time that will not decrease the effectiveness of communications with the offsite agencies.
- Enclosure 3.4, (Emergency Preparedness Acronyms) contains a list of abbreviations.
EL 2.1 Sign in on the EOF Personnel Status Board.
L0 2.2 Initiate a log of major activities and decisions.
El 2.3 Assure EOFD PA system has been turned on in the telephone room.
El 2.4 Turn switch to "ALL CALL" for announcements to all rooms.
2.4.1 Select individual room if only one room is to receive announcement.
L0 2.5 Notify the Emergency Coordinator in the TSC of arrival and establish an open phone line. Dial 66-3921 OR 66-3704 on the 624-4350 line (
Reference:
Emergency Telephone Directory, page 14).
{5}
LI 2.6 Assure access control has been established.
0I 2.7 Make EOF announcement concerning fitness-for-duty.
"Any one who has consumed alcohol within the past five (5) hours, notify either the EOF Director or the appropriate EOF Manager."
RP/O/B/1000/020 Page 3 of 7 0] 2.8 Declare the EOF operational when the following positions are filled, and they have contacted their counterpart in the TSC.
2.8.1 Ensure that the following names are listed on the EOF Personnel Status Board.
NAME EOF Director Offsite Communications Manager State/County Communicator Radiological Assessment Manager Operations Interface Manager Access Control Security Guard L 2.8.2 EOF Operational Time:
_{3}
0I 2.9 Contact the Emergency Coordinator at the TSC and inform him that the EOF is operational and will commence gathering plant status information.
NOTE:
The following individuals will exchange information. Three separate enclosures will be provided to the EOF Director. These enclosures are a part of RP/O/B/1000/021, (Operations Interface (EOF)), RP/0/B/1000/015C, (Offsite Communications From The Emergency Operations Facility) and RP Manual Section 11.3, (Off-Site Dose Assessment And Data Evaluation)
TSC EOF Dose Assessment Liaison Radiological Assessment Manager Offsite Communicator State/County Communicator EOF Liaison Operations Interface Manager
RP/O/B/1000/020 Page 4 of 7 NOTE:
e EOF Managers will inform the EOFD when information is received.
- Turnover with the TSC 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}
0l 2.10 Contact Emergency Coordinator to conduct turnover using the information prepared by the EOF Managers.
Present emergency classification Time Initial emergency classification Time Initiating Condition/Unit affected:
Present status of affected unit(s), including significant pieces of 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 __
Airborne __
Liquid __
Is occurring __ Has occurred __ Time __
Normal operating limits: Below __
Above __
Protective Action Recommendations:
Site Evacuation NO YES If yes, where Time of evacuation Last message number Next message due at El 2.10.1 Request Emergency Coordinator to provide periodic updates to the EOFD concerning plant status.
0l 2.10.2 Inform the Emergency Coordinator that the EOFD will provide dose assessment and field monitoring data on a periodic basis.
El 2.10.3 Record EOF Activation Time:
RP/O/B/1000/020 Page 5 of 7 NOTE:
TSC remains responsible for all Offsite Notifications required by Title JIl (Hazardous Materials Spills).
0] 2.11 Announce to all EOF personnel that the EOF is activated. Provide time of activation and name of EOF Director.
NOTE:
For all drills, precede messages with "This is a drill."
Example message:
"May I have your attention please. The EOF is activated as of (time) hours. This is (Name).
I am the EOF Director and have taken responsibility for emergency management from the Emergency Coordinator in the Technical Support Center.
The plant status is..........
0 2.12 Determine that the EOF Managers understand they are responsible for each of the following actions:
NAME EOF Director Emergency Classification Protective Action Recommendations
+
Approval of news releases.
NOTE:
News releases may be approved by Public Spokesperson if the news releases only contain information already approved by the EOFD on the notification form.
Offsite Communications Manager Notification to offsite agencies.
Contact for offsite agency support (i.e.; medical, fire, law enforcement)
Operations Interface Manager Emergency classification recommendation Plant status Step 2.12 Continued to the next page.
RP/O/B/1000/020 Page 6 of 7 Radiological Assessment Manager
+
Dose Calculations Field Monitoring HPN Communication
+
TSC radio to the EOF operational NOTE:
The following two managers do not have to be in place in a required time frame. Sign off Step 2.12 when the first four managers are identified. Continuation to Step 2.13 should commence while completing this step.
News Director Interface with news media.
Update of company officers.
Update Industry groups. This includes INPO.
Provide technical briefers to the SC Emergency Operations Center (SEOC), Pickens Emergency Operations Center (PEOC) and Oconee Emergency Operations Center (OEOC), and the Joint Information Center (JIC). (Note: JIC is in the EOF).
Commodities & Facilities Manager Update of Duke Power Insurance Department Access Control Responsible for any actions relating to Security
- Facility equipment repair
- Assure 24 hr. Staffing for EOF positions 0l 2.13 Notify SEPD and Oconee and Pickens CEPD that the EOF has assumed turnover from the TSC. This duty may be assigned to the following positions:
+ EOF Logkeeper
- Emergency Planning Manager 2.13.1 Contact SEPD after each message is transmitted to provide additional information/follow-up.
0l 2.14 Verify with the News Director that the Senior Vice president, Nuclear Generation, has been notified of the emergency status.
E0 2.15 Make an announcement over the EOF PA system requesting persons who are medical first responders or EMT's to register that information with the C&F Manager.
El 2.16 EOF Director may approve entry of personnel to the Emergency Operations Facility if the individual's training is not current. Each case would be decided on its own merits.
Document decision in the EOF Director's log.
RP/O/B/1000/020 Page 7 of 7 0I 2.17 Hold round-table discussions with EOF managers every. hour. (Secure timer from procedures cart.)
0] 2.18 Keep EOF personnel updated on changing plant conditions after each round-table discussion. This duty may be assigned to the EOF Logkeeper.
L0 2.19 REFER TO Enclosure 3.1, (Emergency Classification Tracking Sheet).
Enclosures 3.1 Emergency Classification Tracking Sheet 3.2 Emergency Classification Termination/Reduction Flowchart 3.3 Recovery Guidelines 3.4 Emergency Preparedness Acronyms 3.5 References 3.
.1 Emergency Classification Tracking Sheet RP/O/B/1000/020 Page 1 of 16
- 1. Emergency Classification Tracking Review emergency classification and verify it meets the criteria of RP/0/B/1000/001, (Emergency Classification). Discuss changing plant conditions with Emergency Coordinator. Discuss classification prior to making recommendation.
0] 1.1 IF THEN 0 1.2 IF THEN 0 1.3 IF THEN A General Emergency is/or should be classified, GO TO Step 4.0 of this Enclosure, (Enclosure 3.1, Emergency Classification Tracking Sheet).
A Site Area Emergency is/or should be classified, GO TO Step 3.0 of this Enclosure, (Enclosure 3.1, Emergency Classification Tracking Sheet).
An Alert is/or should be classified, GO TO Step 2.0 of this Enclosure, (Enclosure 3.1-, Emergency Classification Tracking Sheet).
- 2. Alert NOTE:
If Steps 2.1 and 2.2 are verified to have been completed by the Emergency Coordinator then they may be marked COMPLETE on this procedure.
0I 2.1 Discuss need to change classification with the Emergency Coordinator. Determine the following:
+
Have any medical emergencies occurred? Status? Transported offsite? Where?
SNOTE:
World Of Energy personnel must be evacuated if non-essential site personnel are evacuated.
Status of non-essential personnel evacuation Have any chemical spills occurred? If yes, what?
Has fire brigade responded to any fires? Has offsite fire department responded?
Has a Condition B been determined for a Keowee Hydro Project Dam/Dike?
{2)
Dl 2.2 Declare an Alert. Notify Offsite Communications Manager to complete an Emergency Notification Form in accordance with RP/O/B/1000/015C, (Offsite Communications From the Emergency Operations Facility), get it approved, and fax to the offsite agencies. (The Alert is officially declared when the Emergency Action Levels for the initiating condition have been exceeded.)
2.2.1 Time of declaration:
.1 RP/O/B/1000/020 Emergency Classification Tracking Sheet Page 2 of 16 NOTE:
Message form transmission must begin within 15 minutes of declaration.
0 Condition B for Keowee Hydro Project Dams/Dikes also requires notification of the Georgia Emergency Management Agency and National Weather Service. Remind the EOF Communications Manager to notify these agencies in addition to and after SC State, Oconee County, and Pickens County.
{2}
0I 2.3 When the message form is completed and the form has been sent, contact the SEPD at the SEOC. This is in addition to contact by the State/County Communicator.
NAME Telephone Numbers SEPD 8-1(803)737-8564 EL 2.3.1 IF the SEOC has NOT been activated, THEN Contact the County Emergency Preparedness Directors (CEPD) to discuss plant status.
Oconee CEPD 8-1(864)638-4200 Pickens CEPD 8-1(864)898-5943 LI 2.3.2 IF Condition B at Keowee exists, THEN Notify the Area Hydro Manager (Refer to Section 6 of the Emergency Telephone Directory, Keowee Hydro Project Dam/Dike Notification).
{2}
L0 2.4 Notify Emergency Coordinator of change in classification. Request Emergency Coordinator to notify the NRC EOC regarding current emergency classification.
NOTE:
Announcements should be made approximately every 30 minutes. Provide current plant status also.
LI 2.5 Announce the emergency class and the time of classification to EOF personnel.
NOTE:
C&F will manage the staffing sheets and route to the EOF Director.
LI 2.6 Evaluate the need for 24-hour staffing and instruct managers to prepare for it if needed.
Telephone numbers and staffing sheets are located in the procedures cart.
.1 RP/0/B/1000/020 Emergency Classification Tracking Sheet Page 3 of 16 0l 2.7 Review emergency classification to determine if it is current and meets the criteria of RP/O/B/1000/001, (Emergency Classification).
El 2.7.1 IF the emergency classification remains as an Alert, THEN have the Offsite Communications Manager continue updating the state and counties by message form every 60 minutes.
El 2.7.2 Keep EOF personnel informed concerning plant conditions.
El El El 2.7.3 2.7.4 2.7.5 0l2.8 IF THEN 02.9 IF THEN El 2.10 IF THEN Keep EC aware of offsite conditions.
Log actions in the EOF Director's log.
Remain in this step until plant conditions dictate a change in emergency classification.
A Site Area Emergency is determined, GO TO Step 3.0 of this Enclosure, (Enclosure 3.1, Emergency Classification Tracking Sheet).
A General Emergency is determined, GO TO Step 4.0 of this Enclosure, (Enclosure 3.1, Emergency Classification Tracking Sheet).
The termination criteria of Enclosure 3.2, (Emergency Classification Termination Criteria) has been met, GO TO Step 5.0 of this Enclosure, (Enclosure 3.1, Emergency Classification Tracking Sheet).
.1 Emergency Classification Tracking Sheet RP/0/B/ 1000/020 Page 4 of 16
- 3. Site Area Emergency NOTE:
If Steps 3.1 and 3.2 are verified to have been completed by the Emergency Coordinator then they may be marked COMPLETE on this procedure.
E0 3.1 Discuss need to change classifications with the Emergency Coordinator. Determine the following:
Have any medical emergencies occurred? Status? Transported offsite? Where?
NOTE:
World Of Energy personnel must be evacuated if non-essential site personnel are evacuated.
- Status of non-essential personnel evacuation?
- Have any chemical spills occurred? If yes, what?
+ Has fire brigade responded to any fires? Have offsite fire department responded?
+ Has dam failure for Keowee or Jocassee occurred? Actions taken?
+
Has a Condition B been determined for a Keowee Hydro Project Dam/Dike?
{2)
El 3.2 Declare a Site Area Emergency. Notify Offsite Communications Manager to complete an Emergency Notification Form in accordance with RP/0/B/1000/015C, (Offsite Communications From the Emergency Operations Facility), get it approved, and fax to the offsite agencies. (The Site Area Emergency is officially declared when the Emergency Action Levels for the initiating condition have been exceeded.)
Time of declaration:
3.2.1
.1 Emergency Classification Tracking Sheet 0I3.3 IF THEN RPIO/B1 000/020 Page 5 of 16 Condition A, Dam Failure (Keowee or Jocassee) exists, 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):
Move residents living downstream of the Keowee Hydro Project dams to higher ground.
+
Prohibit traffic flow across bridges identified on your inundation maps until the danger has passed 0I 3.4 When message form has been sent, contact SEPD. This is in addition to contact by the State/County Communicator.
NAME SEPD Telephone Numbers 8-1(803)737-8564 LI 3.4.1 IF the SEOC has NOT been activated, THEN Contact the County Emergency Preparedness Directors (CEPD) to discuss plant status.
Oconee CEPD 8-1(864)638-4200 8-1(864)898-5943 Pickens CEPD
[1 3.4.2 IF THEN Condition B at Keowee exists, Notify the Area Hydro Manager (Refer to Section 6 of the Emergency Telephone Directory, Keowee Hydro Project Dam/Dike Notification).
{2}
Li 3.5 Notify Emergency Coordinator of change in classification. Request Emergency Coordinator to notify the NRC EOC regarding current emergency classification.
NOTE:
Announcements should be made approximately every 30 minutes. Provide current plant status also.
0i 3.6 Announce the emergency class AND the time of classification to EOF personnel.
NOTE:
e Message form transmission must begin within 15 minutes of declaration.
- Condition B for Keowee Hydro Project Dams/Dikes also requires notification of the Georgia Emergency Management Agency and National Weather Service. Remind the EOF Communications Manager to notify these agencies in addition to and after SC State, Oconee County, and Pickens County.
{2}
RP/0/B/ 1000/020 Page 6 of 16 Fire apparatus is needed to provide water to the spent fuel pool, Contact the Oconee CEPD to provide sufficient fire apparatus (at least three pumper trucks of 1000 gpm, or greater, capacity) to Oconee Nuclear Site (If available, Keowee Ebenezer, Corinth Shiloh and Keowee Key Rural Volunteer Fire Departments should be requested to provide support). Provide instructions concerning entry to the site.
A loss of offsite communications capabilities (Selective Signaling and the WAN) could 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 stated AS SOON AS POSSIBLE.
LI 3.8 IF A Condition A, Keowee Dam failure, exists, THEN Request Commodities & Facilities to notify Telecommunications Group in Charlotte to begin rerouting the Oconee Fiber Optic Network. Refer them to Selective Signaling Section of the Emergency Telephone Directory (page 9).
DI 3.9 Request Radiological Assessment Manager to provide information regarding potential sectors that would be affected should emergency be upgraded to a General Emergency.
NOTE:
C&F will manager the staffing sheets and route to the EOF Director.
LI 3.10 Evaluate the need for 24-hour staffing and instruct managers to prepare for it if needed.
Telephone numbers and staffing sheets are available in the emergency procedures cart.
EL 3.11 Review emergency classification to determine if it is current and meets the criteria of RP/0/B/1000/001, (Emergency Classification).
El 3.11.1 IF the emergency classification remains as a Site Area Emergency, THEN have the Offsite Communications Manager continue updating the counties by message form every 60 minutes.
LI 3.11.2 Keep EOF personnel informed concerning plant conditions.
LI 3.11.3 Keep EC aware of offsite conditions.
[] 3.11.4 Log actions in the EOF Director's log.
LI 3.11.5 Remain in this step until plant conditions dictate a change in emergency classification.
LI 3.12 IF THEN A General Emergency is determined, GO TO Step 4.0 of this enclosure, (Enclosure 3.1, Emergency Classification Tracking Sheet).
0I3.7 IF THEN.1 Emergency Classification Tracking Sheet NOTE:
.1 RP/0/B/1000/020 Emergency Classification Tracking Sheet Page 7 of 16 IF the termination criteria of Enclosure 3.2, (Emergency Classification Termination Criteria) has been met, THEN GO TO Step 5.0 of this enclosure, (Enclosure 3.1, Emergency Classification Tracking Sheet).
0I 3.14 IF the reduction criteria of Enclosure 3.2, (Emergency Classification Termination Criteria) has been met, THEN REFER TO Step 3.17.
0I 3.15 Notify Offsite Communications Manager to complete a message form in accordance with RP/O/B/ 1000/01 5C, (Offsite Communications From The Emergency Operations Facility),
get it approved, and send it to the offsite agencies.
01 3.16 When message form has been sent, contact SEPD to discuss emergency classification reduction. This is in addition to contact by the State/County Communicator.
NAME SEPD Telephone Numbers 8-1(803)737-8564 3.16.1 IF the SEOC has NOT been activated, THEN Contact the County Emergency Preparedness Directors (CEPD) to discuss plant status.
8-1(864)638-4200 8-1(864)898-5943
[] 3.17 Consider the present working copy procedure as being completed since the classification is reduced to an Alert. Obtain a new working copy of RP/0/B/1000/020, (Emergency Operations Facility Director Procedure) from the Procedures Cart and GOTO Enclosure 3.1, (Emergency Classification Tracking Sheet) Step 2.1.
Pickens CEPD LI 3.13 Oconee CEPD
.1 RP/O/B/1000/020 Emergency Classification Tracking Sheet Page 8 of 16
- 4. General Emergency NOTE:
If Steps 4.1 AND 4.2 are verified to have been completed by the Emergency Coordinator then they may be marked COMPLETE on this procedure.
Li 4.1 Discuss changing plant conditions AND emergency classification with Emergency Coordinator prior to making recommendation. Determine the following:
Have any medical emergencies occurred? Status? Transported offsite? Where?
NOTE:
World Of Energy personnel must be evacuated if non-essential site personnel are evacuated.
- Status of non-essential personnel evacuation?
Have any chemical spills occurred? If yes, what?
Has fire brigade responded to any fires? Have offsite fire departments responded?
+
Has dam failure at Keowee or Jocassee occurred? Actions taken?
Has a Condition B been determined for a Keowee Hydro Project Dam/Dike?
{ 21 NOTE:
9 The General Emergency is officially declared at this time.
0 Protective Action recommendations are the sole responsibility of the EOF Director. Use input from other managers. Continually review plant status for change in Protective Action Recommendations. Review the requirements of RP/O/B/1000/024, (Protective Action Recommendations).
0i 4.2 Declare a General Emergency. Initial protective action recommendation is to evacuate 2 mile radius and 5 miles downwind.
Time of Declaration:
4.2.1
.1 Emergency Classification Tracking Sheet RP/0/B/ 1000/020 Page 9 of 16 NOTE:
9 Message form transmission must begin within 15 minutes of declaration.
0 Condition B for Keowee Hydro Project Dams/Dikes also requires notification of the Georgia Emergency Management Agency and National Weather Service. Remind the EOF Communications Manager to notify these agencies in addition to and after SC State, Oconee County, and Pickens County.
{2}
El 4.2.2 Notify Offsite Communications Manager to begin completing a message form in accordance with RP/O/B/1000/015C, (Offsite Communications From The Emergency Operations Facility).
A. Request Radiological Assessment Manager to determine the exact sectors to be evacuated and sheltered using HP/O/B/1009/018, (Offsite Dose Projections).
B.
Provide the following protective action recommendations for use by the offsite communicator to complete the emergency notification form.
PICKENS COUNTY OCONEE COUNTY AO Al B1 C1 A2 B2 C2 AO D1 El F1 D2 E2 F2 EVACUATE SHELTER I
I I
I I I C. IF THEN Condition A, Dam Failure (Keowee or Jocassee) exists, 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):
+
Move residents living downstream of the Keowee Hydro Project dams to higher ground.
Prohibit traffic flow across bridges identified on your inundation maps until the danger has passed.
.1 Emergency Classification Tracking Sheet RP/OB/ 1000/020 Page 10 of 16 0I 4.3 When message form is completed and the form has been sent, contact SEPD. This is in addition to contact by the State/County Communicator.
Protective Action Recommendation: Read from the approved emergency notification form the protective action recommendations. Provide any known information concerning conditions that would make evacuation dangerous.
El 4.3.1 IF the State Emergency Operations Center has been activated, THEN contact the SEPD.
NAME Telephone Numbers 8-1(803)737-8564 SEPD LI 4.3.2 IF the State Emergency Operations Center has NOT been activated, THEN contact the CEPD.
Oconee CEPD 8-1(864)638-4200 8-1(864)898-5943 Pickens CEPD Li 4.3.3 Request SEPD or CEPD to call back after a decision has been made on actual protective actions recommended by the State and Counties for the plume exposure pathway population.
A. Record below the actions that have been taken by SEPD or CEPD:
B.
Information received from:
El 4.4 Notify the Emergency Coordinator of the change in classification AND the current protective action recommendations. Request Emergency Coordinator to notify the NRC EOC of the change in emergency classification AND the protective action recommendations.
NOTE:
Announcements should be made approximately every 30 minutes. Provide current plant status also.
El 4.5 Announce the emergency class AND the time of classification to EOF personnel. Provide the current protective action recommendations.
Time:
RP/0/B/ 1000/020 Page I Iof 16 Condition B at Keowee exists, Notify the Area Hydro Manager (Refer to Section 6 of the Emergency Telephone Directory, Keowee Hydro Project Dam/Dike Notification).
{2}
0i4.6 IF THEN 0i4.7 IF THEN 0I 4.8 Evaluate plant status.
0 4.8.1 IF emergency classification remains as a General Emergency, THEN have Offsite Communications Manager continue updating the counties by message form every 60 minutes.
0 4.8.2 Keep EOF personnel informed concerning plant conditions.
LI 4.8.3 Keep EC aware of offsite conditions.
Li 4.8.4 Log actions in the EOF Director's log.
[] 4.8.5 Remain in this step until plant conditions dictate a change in protective action OR emergency classification.
LI 4.8.6 IF Additional protective action recommendations are required by RP/0/B/1000/024, (Protective Action Recommendations),
THEN GO TO Step 4.9.
El A. Additional PAR Determination Time:
{4}
LI 4.8.7 IF The termination criteria of Enclosure 3.2, (Emergency Classification Termination Criteria) are met, THEN GO TO Step 5.0 of this Enclosure, (Enclosure 3.1, Emergency Classification Tracking Sheet).
NOTE:
Transmission of a change in protective action recommendations must begin within 15 minutes of determination.
0i 4.9 Notify Offsite Communications Manager to complete a message form in accordance with RP/0/B/1000/015C, (Offsite Communications From The Emergency Operations Facility) providing the additional protective action recommendations, get it approved, and send it to the offsite agencies..1 Emergency Classification Tracking Sheet Fire apparatus is needed to provide water to the Spent Fuel Pool, Contact the Oconee CEPD to provide sufficient fire apparatus (at least three pumper trucks of 1000 gpm, or greater, capacity) to Oconee Nuclear Site (If available, Keowee Ebenezer, Corinth Shiloh and Keowee Key Rural Volunteer Fire Departments should be requested to provide support). Provide instructions concerning entry to the site.
.1 RP/O/B/1000/020 Emergency Classification Tracking Sheet Page 12 of 16 E0 4.10 When the message form has been sent, contact SEPD. This is in addition to contact by the State/County Communicator.
Protective Action Recommendation: Read from the approved emergency notification form the protective action recommendations. Provide any known information concerning conditions that would make evacuation dangerous.
El 4.10.1 IF the State Emergency Operations Center has been activated, THEN contact the SEPD.
NAME Telephone Numbers S EPD 8-1 (803)737-8564 El 4.10.2 IF the State Emergency Operations Center has NOT been activated, THEN contact the CEPD.
Oconee CEPD _8-1 864)638-4200 Pickens CEPD 8-1 (864)898-5943 El 4.10.3 Request SEPD or CEPD to call back after a decision has been made on actual protective actions recommended by the State and Counties for the plume exposure pathway population.
A. Record below the actions that have been taken by SEPD or CEPD:
B.
Information received from: "Time:
EL 4.11 Notify the Emergency Coordinator of the change in protective action recommendations.
4.11.1 Request Emergency Coordinator to notify the NRC EOC of the change in protective action recommendations.
El 4.12 Announce the current protective action recommendation AND plant status to EOF personnel.
.1 Emergency Classification Tracking Sheet RP/O/B/ 1000/020 Page 13 of 16 0l 4.13 Evaluate Plant status.
4.13.1 IF emergency classification remains as a General Emergency, THEN have the Offsite Communications Manager continue updating the counties by message form every 60 minutes.
Li 4.13.2 Keep EOF personnel informed concerning plant conditions.
[] 4.13.3 Keep EC aware of offsite conditions.
El 4.13.4 Log actions in the EOF Director's log.
[] 4.13.5 Remain in this step until plant conditions dictate a change in protective action OR emergency classification.
[] 4.13.6 IF Additional protective action recommendations are required by RP/0/B/1000/024, (Protective Action Recommendations),
THEN GO TO Step 4.14.
El A. Additional PAR Determination Time:
{4}
LI 4.13.7 IF The termination criteria of Enclosure 3.2, (Emergency Classification Termination Criteria) are met, THEN GO TO Step 5.0 of this Enclosure, (Enclosure 3.1, Emergency Classification Tracking Sheet).
NOTE:
Transmission of a change in protective action recommendations must begin within 15 minutes of determination.
El 4.14 Notify Offsite Communications Manager to complete a message form in accordance with RP/0/B/1000/015C, (Offsite Communications From The Emergency Operations Facility) providing the additional protective action recommendations, get it approved, and send it to the offsite agencies.
.1 Emergency Classification Tracking Sheet RP/O/B/ 1000/020 Page 14 of 16 EL 4.15 When the message form has been sent, contact SEPD. This is in addition to contact by the State/County Communicator.
Protective Action Recommendation: Read from the approved emergency notification form the protective action recommendations. Provide any known information concerning conditions that would make evacuation dangerous.
LI 4.15.1 IF the State Emergency Operations Center has been activated, THEN contact the SEPD.
NAME SEPD Telephone Numbers 8-1(803)737-8564 0I 4.15.2 IF the State Emergency Operations Center has NOT been activated, THEN contact the CEPD.
Oconee CEPD______________
Pickens CEPD 8-1(864)638-4200 8-1(864)898-5943 LI 4.15.3 Request SEPD or CEPD to call back after a decision has been made on actual protective actions recommended by the State and Counties for the plume exposure pathway population.
A. Record below the actions that have been taken by SEPD or CEPD:
B.
Information received from:
Time:
El 4.16 Notify the Emergency Coordinator of the change in protective action recommendations.
4.16.1 Request Emergency Coordinator to notify the NRC EOC of the change in protective action recommendations.
NOTE:
Announcements should be made approximately every 30 minutes. Provide current plant status also.
LI 4.17 Announce the current protective action recommendation AND plant status to EOF personnel.
.1 Emergency Classification Tracking Sheet RP/O/B/ 1000/020 Page 15 of 16 NOTE:
C&F will manage the staffing sheets and route to the EOF Director.
0I 4.18 Evaluate the need for 24-hour staffing and instruct managers to prepare for it if needed.
Telephone numbers and staffing sheets are available in the emergency procedures cart.
0 4.19 WHEN termination criteria are met, GO TO Step 5.0 of Enclosure 3.1 (Emergency Classification Tracking Sheet).
- 5. Termination 0115.1 IF THEN 0 5.2 IF THEN Terminating from an Alert or Site Area Emergency, GO TO Step 5.3.
In a General Emergency, Discuss with the NRC Director of Site Operation& (NRCDSO) and the SEPD that the termination criteria have been met.
5.2.1 Secure agreement from the two directors to terminate the event.
5.2.2 Document names and time decision made below.
NAME SEPD NRCDSO Telephone Numbers 8-1(803)737-8564 (In person in EOF)
Time El 5.3 Request Offsite Communications Manager to complete message form and send it in accordance with RP/0/B/1000/015C, (Offsite Communications From The Emergency Operations Facility) to terminate the emergency.
0115.4 IF THEN terminating from an Alert or a Site Area Emergency, notify the following agencies.
NAME SEPD Telephone Numbers 8-1(803)737-8564 5.4.1 IF the SEOC has NOT been activated, THEN contact the County Directors of Emergency Planning (CEPD).
Oconee CEPD Pickens CEPD_____________
8-1(864)638-4200 8-1(864)898-5943
.1 Emergency Classification Tracking Sheet 05.5 IF THEN RP/O/B/1000/020 Page 16 of 16 terminating from an emergency involving dam failure (Keowee or Jocassee),
discuss termination with the Hydro Emergency Operations Facility in Charlotte.
0l 5.6 Establish Recovery Organizations if needed.
5.6.1 GO TO Enclosure 3.3, (Recovery Guidelines).
5.6.2 IF Recovery Organizations are NOT required, THEN GO TO Step 5.7.
0l 5.7 Request Emergency Planning to provide a copy of the License Event Report (LER) to state and county agencies at the time it is sent to the NRC.
.2 Emergency Classification Termination Criteria RP/O/B/1000/020 Page 1 of 2
.2 Emergency Classification Termination Criteria RP/O/B/1000/020 Page 2 of 2 TERMINATE THE CURRENT CLASSIFICATION AND DECLARE THE PLANT IN RECOVERY NO CONTINUE WITH THE CURRENT CLASSIFICATION UNTIL A RECOVERY CAN BE DECLARED TABLE 1 RECOVERY CONDITIONS NO NEW EVACUATION OR SHELTERING PROTECTIVE ACTIONS ARE ANTICIPATED CONTAINMENT PRESSURE IS LESS THAN DESIGN PRESSURE CONTAINMENT HYDROGEN LEVELS ARE BEING MAINTAINED WITHIN LIMITS LONG TERM CORE/DEBRIS COOLING HAS BEEN ESTABLISHED THE RISKS FROM RECRITICALITY ARE ACCEPTABLY LOW RADIATION PROTECTION IS MONITORING ACCESS TO RADIOLOGICALLY HAZARDOUS AREAS OFF-SITE CONDITIONS DO NOT LIMIT PLANT ACCESS THE NEWS DIRECTOR, NRC OFFICIALS, AND STATE REPRESENTATIVES HAVE BEEN CONSULTED TO DETERMINE THE AFFECTS OF TERMINATION ON THEIR ACTIVITIES THE RECOVERY ORGANIZATION IS READY TO ASSUME CONTROL OF RECOVERY OPERATIONS
.3 RP/0/B/1000/020 Recovery Guidelines Page 1 of 2
- 1. Recovery Guidelines The Recovery Manger shall be responsible for the following:
0l 1.1 Make a PA announcement as follows:
"Agreement has been reached between Duke, the State of South Carolina and the NRC that the General Emergency classification is terminated. Recovery Operations are being initiated at the site. Actions are underway to determine when people who have been evacuated from their homes can return. As this information is made available, it will be released to the public."
El 1.2 Establish a Recovery Organization to handle offsite consequences.
1.2.1 The offsite recovery organization will stay at the EOF and work with the counties and state if radiological conditions exist beyond the ONS site boundary.
1.2.2 The onsite recovery organization will be established by the Emergency Coordinator.
El 1.3 Make the following assignments:
Recovery Manager Radiological Assessment Manager Field Monitoring Coordinator Emergency Planning Manager Commodities & Facilities Manager El 1.4 Assure staffing for long-term operation.
NOTE:
Once recovery has been determined, the emergency notification message forms are no longer used.
El 1.5 Contact the SEPD to discuss work in progress at the EOF and determine communication channels and notifications expected.
[E 1.6 Discuss with each manager the activities they have in progress.
.3 RP/0/B/1000/020 Recovery Guidelines Page 2 of 2
[] 1.7 Radiological Assessment Responsibilities 1.7.1 Provide ingestion pathway dose assessments 1.7.2 Provide ongoing communications with DHEC Nuclear Emergency Planning 1.7.3 Evaluate environmental concentrations within the radiological footprint 1.7.4 Provide technical assistance to Joint Information Center 1.7.5 Help plan for reactor building purge as needed Ei 1.8 Emergency Planning Responsibilities 1.8.1 Communications to the State and County Emergency Directors 1.8.2 Review information being released through the news medium El 1.9 Commodities & Facilities Manger Responsibilities 1.9.1 Assure ANI (insurance) is set up for public inquiry 1.9.2 Provide services as required El 1.10 Joint Information Center Responsibilities 1.10.1 Providing news releases 1.10.2 Work with media/public to reduce rumors 0l 1.11 Responsibilities of the Site's Outage Manager 1.11.1 Provide Recovery Manager with updates on work in progress at the site El 1.12 Keep the Emergency Operations Facility activated and staffed until consensus is reached by Duke and State of South Carolina there is no basis for continuous staffing.
El 1.12.1 Record time and date that Emergency Operations Facility/Joint Information Center were closed.
A. EOF/JIC Closed Time/Date
.4 Emergency Preparedness Acronyms RP/O/B/ 1000/020 Page 1 of 1 BSHWM CEPD DHEC EC EOF EOFD EPA FAX FEOC FTS-2000 LEC NEP NRCDSO NRC EOC OSC PAR SCC SEPD SEOC SWP TSC Bureau of Solid and Hazardous Waste Management County Emergency Preparedness Director/Division Department of Health and Environmental Control Emergency Coordinator Emergency Operations Facility Emergency Operations Facility Director Emergency Preparedness Agency Facsimile Forward Emergency Operations Center (Clemson)
NRC Emergency Telephone Communication System Law Enforcement Center Nuclear Emergency Planning (BSHWM)
Nuclear Regulatory Commission Director of Site Operations Nuclear Regulatory Commission Emergency Operations Center Operational Support Center Protective Action Recommendations State/County Communicator State Emergency Preparedness Director/Division State Emergency Operations Center (Columbia)
State Warning Point Technical Support Center
.5 RP/O/B/1000/020 References Page 1 of 1