ML20040D249
| ML20040D249 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/19/1981 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20040D248 | List: |
| References | |
| PROC-811119-01, NUDOCS 8202010083 | |
| Download: ML20040D249 (78) | |
Text
.
'4000 SERIES h>
El1ERGEliCY PLAll Il4PLEl:EflTli!G PROCEDURES flV!1BER TITLE REV.
DATE ISSUED 4101 Unusual E0ent Actions 1
9/15/81 4102 Alert 2
10/26/81 4103 Site Area Emergency 2
10/26/81 4104 General Emergency 2
10/26/81 4201 Radiological Dose Assessment 1
8/17/81 4202 Post Accident Sampling 0
7/15/81 4203 E!1T #1-In Plant Radiological Sampling 1
9/15/81 and lionitoring 4204 El4T #2-Protective Actions for Onsite 1
9/15/81 Personnel 4205 EllT #3-Site Boundary Radiological 1
9/15/81 Sampling /llonitoring 4206 El4T #4, #5 - Offsite Radiological 1
9/15/81
(,)
Sampling and !!onitoring 4207 Radiological-Sampling During An 0
7/15/81 Emergency 4208 Aid to Affected Personnel 0
7/15/81 4209 Emergency Operations Re-Entry 0
7/15/81 4210 Emergency Recovery 0
7/15/81 4301 Communications - Radiopaging & Callback 1 9/15/81 Recorder Operations 4302 Emergency Operations Facility Ventil-0 7/15/81 lation System
^
4303 Emergency Operations facility 0
7/15/81 Emergency Diesel Generator 4304 Emeri'ncy Response Center and 1
9/15/81 Facil, ties 4306 E.O.F. Fire Detection System 0
7/15/81 O
8202gggggj$8o$5 i9/81 kD PDR.
.Page 1 of 2
4000 Series - Procedures 4501 Radioactive Materials Transport 0
7/15/81 0
^ccideat 4502 Toxic Material Release 0
7/15/81 4503 llazardous Waste and Toxic Substance 1
8/5/31-Spill Incident 4504 Personnel Emergency 0
7/15/81 4505 Atmospheres in. mediately llazardous 0
7/15/81.
to Life
'4601 Page/ Siren System Evacuation Alarm 0
7/15/81 4602 Communications Telephone Test 0
7/15/81 4603 Emergency Radiological Equipment 0
7/15/81 Maintenance and Inspection 4604 Emer0ency Call List Surveillance 0
7/15/81 4605 Emergency Operations Facility Ventil-0 7/15/81 ation System Filter Testing Annual 4606 EOF Emergency Diesel Generator 0
7/15/81 Q
Operability Test 4608 E0F Air Lock Operability Test 0
7/15/81 4609 EOF Fire Detection System Test 0
7/15/81 4610 Communications-Radiopaging and Callback 3 11/26/81 Recorder Monthly Test 4611 Station PA Speaker Inspection 0
7/15/81 4612 Waterford, State and Tri Town Radio 1
10/13/81 Test 4613 Communications-Radiopaging Daily Test 1
9/15/81 Rev. 7 11/19/81 Page 2 of 2
APPROVAL:
E.'J. Mroczka DATE:
6-18-80 Station Superintendent STATION PROCEDURE C0VER SHEET A.
IDENTIFICATION Number EPIP 4610 Rev.
3_
Title Communications-Radiopaging and Callback Recorder Monthly Drill Prepared By D. Leduc B.
REVIEW I have reviewed the above procedure and have found it to be satisfactory.
TITLE SIGNATURE DATE DEPARTMENT HEAD M
//
o 8/
y
/
/
C.
UNREVIEWED SAFETY QUESTION EVALUATION DOCUMENTATION REQUIRED:
nU (Significant change in procedure method or scope as described in FSAR)
YES [ ]
N0 p4 (If yes, document in -PORG/50RC meeting minutes)
ENVIRONMENTAL IMPACT (Adverse environmental impact)
YES [ ]
NO bd (If yes, document in MRC-/S0RC meeting minutes)
D.
40R6/50RC APPROVAL MSG /S0RC Meeting Number d/[
E.
APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effective on the dates below:
C4 de
/l'N$
llEh' I 5tatidrrSuperintendenyUnit Superintendent Approved Date Effective Date 5F-301 Rev. 3
.O U
.. ~ -... _ - -.
~ EPIP,4610 Page 1 Rev. 3 Date: 11/26/81
- O COMMUNICATIONS-RADI0 PAGING AND CALLBACK RECORDER MONTHLY DRILL' PAGE NO.
- EFFECTIVE REV.
DATE.
1
- l
- 1 3
11/26/81 2
3 11/26/81 j
3 3
11/26/81
' 4 3
11/26/81 5
3 11/26/81 6
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EPIP.4610 Page 2 Rev. 3 Date: 11/26/81
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'1.
OBJECTIVE 1.1 This procedure is provided for the monthly drill of the Millstone emergency paging system and callback recorders.
I 1.2 The drill will be condu::ted on the first Wednesday of each month at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />.
If the first Wednesday is a public holiday, the drill will be conducted on Thursday.
The daily radiopager test will be canceled on the day of the drill.
i 1.3 Unit I will perform the drill on the odd numbered months and l
Unit 2 on the even numbered months.
2.
ACCEPTANCE CRITERIA 2.1 The transmitter module lamps on the radiopager console light up after transmitting the drill message.
- 2. 2 The callback recorder phone numbers dialed respond with an audible and clear announcement drill message.
2.3 The callback recorder test messages played back are audible and clear.
O 2.4 The NNECo/NUSCo personnel on call for the emergency response have called back to acknowledge receipt of the radio drill message or individual (s) contacted.
2.5 The Towns / Agencies have called back to acknowledge receipt of the radio drill message or contacted by back up notification.
3.
REFERENCES 3.1 EPIP-4301 3.2 ACP-1.07 4.
PREREQUISITES 4.1 Notify the NNECo personnel on call for the emergency response to call-in and verify receipt of the Charlie-One Drill message.
4.2 Personnel performing drill are to be familiar with equipment operation as explained in EPIP 4301.
4.3 Notify NUSCO Chief, Radiological Assessment Branch - Berlin for O
the eveat descri tion section of the incident report.
P
EPIP 4610 Page 3-Rev. 3 Date:
11/26/81 4.4 Ensure all callback recorders are in good working order prior
]
to drill.
.5.
INITIAL CONDITIONS None 6.
PRECAUTIONS 6.1 Select the proper tape message prior to placing in radio console.
6.2 Remove the tape from paging equipment upon completion of radiopager messages.
6.3 Ensure the announcement and callback tapes are clear of any previous messages.
7.
PROCEDURE 7.1 Record Drill Announcement N TE:
Refer to EPIP 4301, Section 7.2 for callback O
recorder operation.
7.1.1 Using the incident report form previously prepared for the CHARLIE-ONE DRILL, record the drill announcement on the 10 tandom recorders located below the 3 single recorders on the top shelf.
7.1.2 Ensure the 3 single recorders located on the top shelf have the prerecorded message as follows:
"At the sound of the tone please leave your name, function and estimated time of arrival."
7.1. 3 Play back the 10 tandom recorders and verify the incident drill message was recorded.
7.1. 4 Initial data sheet upon completion.
7.2 Transmit Radio Drill Fessage 7.2.1 Ensure the paging channels are not in use.
This is indicated by the call light or busy light on the individual transmit / receive (T/R) module.
. (G)
EPIP 4610 Page 4 Rev. 3 Date:11/26/81' Q
7.2.2 Select the Level 2 (public & NNEC0/NUSCO personnel) position on the auto page module.
7.2.3 Insert the pre-recorded radiopager message for a CHARLIE-ONE DRILL.
7.2.4 Activate the push switch marked " alert" on the Auto page module.
Verify the system is activated at this time by observing the red lamp on the Auto page module.
NOTES:
To cancel auto page, push Reset switch on auto page module.
Upon activation, the console will automatically select the correct pager group tones for level. selected, and cycle the outputs through the four paging transmitters individually.
Auto page will then shut-off.
Station call letters will be sent automatically, upon sequence Q
completion.
7.2.5 Verify the four (4) transmitter module lamps on the radio console have lighted.
7.2.6 In addition to the radiopager message, Millistone will call the State Police via hot line, blue phone as a backup verification.
NOTE:
The State Police proceduies require they check State D.E.P., Governor's office and state 0.C.P. to ensure they received page.
7.2.7 Record results on data sheet.
7.3 Playback Call-in Messages NOTE:
Refer to EPIP 4301, Section 7.2 for Callback Recorder Operation.
7.3.1 After transmitting the radiopagar drill message, check for the following:
7.3.1.1 Verify individuals on call have called in to acknowledge the drill message.
O 4
EPIP 4610 Page 5 Rev.-3 Date: 11/26/81 O
NOTE:
Contact the individuals who were on-call during the drill but did not call-in and resolve the radiopager' problems with them.
{
7.3.1.2 Verify the Towns / Agencies have called in to acknowledge the drill message.
NOTE:
If local community does not respond to the radiopage, Millstone will make one call per community to alert them.
If this is unsuccessful, Millstone will call the State Police to take action giving them particular information on the stations t
attempt to alert tia community.
I For all town except Lyme, Old Lyme and Old Saybrook, call y
Montville State Police barracks via hot line, blue phone.
For Lyme, Old Lyme and Old Saybrook, call the West Brook State Police barracks number 399-6221.
7.3.1.3 Record results on data sheet.
7.4 Equipment Failure 7.4.1 Radiopager In case the radiopager system becomes inoperative, perform the following steps.
7.4.1.1 Contact the Connecticut State Police at the-Montville barracks via hot lina, blue phone.
NOTE:
The State Police procedures require they notify State D.E.P, State 0.C.P., Governor's Office and local communities.
7.4.1.2 Contact Waterford Emergency Communications Center via hot line, red phone.
EPIP 4610 -. Page 6 Rev. 3 Date: 11/26/81 -
Q-7.4.1.3
- Contact Suffolk County, Long Island, NY at 516-924-440, alternate at 516-924-5252.
7.4.1.4 Contact NUSCo/NNEco Duty Officers and 3
Directors / Managers on-call.
I 7.4.1.5 Contact Station Services Engineering.
7.4.1.6 Station Services Engineering shall contact NUSCo system test for repairs at Ext.
3800-Berlin.
- 7. 4. 2 -
Callback Recorders 7.4.2.1 In case of callback recorder failure, replace recorder with the spare recorder located on one of the last 2 lower shelves of.the recorder cabinet.
7.4.2.2 If no spare recorders are available, connect a 4
busy out plug to the telephone mounting block located on the back wall behind recorder.
The busy out plug will provide a busy signal and
(]
allow the incoming call to transfer to the next recorder in sequence.
The busy out plugs should be located in a metal file box, labeled " Busy Out Plugs", on the lower shelf of the recorder cabinet.
7.4.2.3 Bad recorders should be removed from service, tagged and placed on the bottom shelf of the cabinet.
Tag should state name of person removing recorder from service, date, time and problem with recorder.
7.4.2.4 Contact Station Services Engineering.
7.4.2.5.
Station Services Engineering shall contact NUSCo System Test for repairs at Ext.
3800-Berlin.
7.5 Data Sheets 7.5.1 Submit data sheets to the SS/SCO for signature and date.
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EPIP 4610 Page 7 Rev. 3 Date: 11/26/81
- O 7.s.2 r-erd c-gieted dete sheets to Stetion services Engineering for. filing.
8.
RESTORATION 8.1 Reset acknowledge lamps on radio pager transmit modules.
8.2 Erase recorder drill ~ announcement ar.d call-in tapes.
8.3 Record the original announcement message in recorders.
8.4 Reset callback recorders to ANS-REC.
9.
FORMS 9.1 Unit 1 data sheet, EPIP Form 4610-1 DL:jf O
db O
p
- 4000 SERIES EMERGFi!CY PLAtl IMPLEMEll!IllG FORMS NUf1BER TITLE REV.
DATE ISSUED 4101-1 Unusual Event Checklist 0
7/15/81 Shift Supervisor / Designee
'4101-2 Unusual Event Checklist 1
9/15/81 Shift Technical Advisor /SSSA 4101-3 Unusual Event Checklist 0
7/15/81 Duty Officer
' 4102-1 Alert Emergency 1
9/15/81 Shift Supervisor / Manager of Control Room OPS 4102-2 Alert Emergency 1
9/15/81 Shift fechnical Advisor /SSSA 4102-3 A' ort Emergency 0
7/15/81 Duty Officer / Manager of TSC 4102-4 Alert Emergency 0
7/15/81 Director of Station Emergency Operations 4102-5 Alert Emergency 0
7/15/81 Manager of Radiological Consequence Assessment 4102-6 Alert Emergency 0
7/15/81 Manager of Public Information 4102-7 Alert Emergency 1
9/15/81 Manager of External Communication 4102-8 Alert Emergency 0
7/15/81 l
Manager of Security 4102-9 Alert Emergency 2
10/26/81 Manager of On-Site Resources 4102-10 Alert Emergency 0
7/15/81 Manager of Engineering Support 4103-1 Site Area Emergency 0
7/15/81 Shift Supervisor / Manager of Control Room OPS l
4103-2 Site Area Emergency 1
9/15/01 Shift Technical Advisor /SSSA Rev. 5 11/19/81 o
! O Page 1 of 5 w
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4000 SERIES - f0Rt1S-0 7/15/81 4103-3 Site Emergency Outy Officer / Manager of TSC 4103-4 Site Area Emergency 0
7/15/81 Director of Station Emergency Operations 4103-5 Site Area Emergency 0
7/15/81 Manager of Radiological Consequence Assessment 4103-6 Site Area Emergency 0
7/15/81 l
Manager of Public Information l
4103-7 Site Area Emergency 1
9/15/81 Manager of' External Communication 4103-8 Site Area Emergency 0
7/15/81 Manager of Security 4103-9 Site Emergency 2
10/26/81 Manager of On-Site Resources 1
1 f
4103-10 Site Area Emergency 0
7/15/81 Manager of Engineering Support 4104-1 General Emergency 1
9/15/81 Shift Supervisor / Manger of Control Room OPS 4104-2 General Emergency 1
9/15/81 Shift Technical Advisor /SSSA 4104-3 General Emergency 0
7/15/81 Duty Officer / Manager of TSC 4104-4 General Emergency 0
7/15/81 Director of Station Emergency Operations 4104-5 General Emergency 0
7/15/81 Manager of Radiological Consequence Assessment 4104-6 General Emergency 0
7/15/81 Manager of Public Information 4104-7 General Emergericy 1
9/15/81 Manager of External Communication O
aev s 11/19/81 Page 2 of 5
^
^
1000 SERIES - FORMS
- p 4104-8 General Emergency
- O 7/15/81 V
Manager of Security 4104-9 General Emergency 2'
10/26/81-Manager of On-Site Resources 4104-10 General Emergency 0
7/15/81 Manager of-Engineering Support 4201-1 Worksheet #1 !!oble Gas Release Rate 0
7/15/81 4201-2~
Worksheet #2 Iodine-131' Release Rate 0
7/15/81 4201-3 Worksheet #3 lieteorological Data 0
7/15/81 4201-4 Worksheet #4 floble Gas Dose 0
7/15/81 4201 Worksheet #5 Thyroid Dose 0
7/15/81 4201-6 Worksheet #G Doses Vs. Distance 0
7/15/81 1
4201-7 Dose Calculation Data Sheet 0
7/15/81 4201-8 Air Sample Activity Concentrations Worksheet 0 7/15/81 0
4201-9 Radiation Dose Rate Worksheet 0
7/15/81 4203-1 EMT #1 Worksheet 0
7/15/81 4204-1 EMT #2 Worksheet 0
7/15/81 4205-1 EMT #3 Data Sheet 0
-7/15/81-4205 Air Sample Work Sheet 0
7/15/81 4206-1 Offsite EMT Data-Sheet 0
7/15/81 4206-2 Air Sample Work Sheet
'O
- 15/81 4208-1 First Aid Kits 0
7/15/81 i
4208-2 Basket & Stretchers 0
7/15/81 4208-3 Personnel Contamination Form 0
7/15/81 4209-1 Emergency Re-Entry Checklist 0
7/15/81 Rev. 5 11/19/81 Page 3 of 5
. s.
4000 SERIES - FORl15
(]
4601-1 Page/ Siren System Evacuation Alarm Test 0
7/15/81 4602-1 Telephone Communications Test 0
7/15/81 4603-1 Emergency Operations facility 0
7/15/81 Radiological Kits 4603-2 Emergency Operations facility 0
7/15/81 Access Road 4603-3 Unit 1 Control Room Emergency 0
7/15/81 4603-4 Unit 1 Technical Support Center 0
7/15/81 Radiological Equipment Checklist 4603-5 CPF Assembly Area - Radiological Kit 0
7/15/81 4603-6 First Aid Emergency Rescue Kits and 0
7/15/81 Emergency Dosimetry 4603-7 Ambulance Kit Inventory 0
7/15/81 4603-8 Emegency Equipment Inventory List 0
7/15/81 4603-9 Acid Spill Kits 0
7/15/81 4605-1 Emergency Operations Facility 0
7/15/81 Ventilation System Filter Test 4606-1 EOFEDG Operability Test 0
7/15/81 4608-1 E.0.F. Air Lock OP Test 0
7/?5/81 4609-1 E.0.F. Fire Detection Test 0
7/15/81 4610-1 Unit 1/ Unit 2 Data Sheet 3
11/26/81 4610-2 Unit 2 Data Sheet Cancelled 9/1/81 (50RC 81-38) 4611-1 PA Speaker Inspection Form 0
7/15/81 4612-1
'Tri-Town Radio Test-Unit 1 Control Room 0
7/15/81 4612-2 Tri-Town Radio Test-E0F 0
7/15/81 4612-3 State Police Radio Test 0
7/15/81 l
Rev. 5 11/19/81 q
Page 4 of 5 v
~
4000 Sr. RIES - FOI'!!S 4612-4 Waterford Police Radio Test 0
7/15/81 4613-1 Radiopage - Daily Test Log Sheet 1
11/24/81 h
O Rev. 5 11/19/81 O
Page 5 of 5
. ~., - +_-
" " " ~ ' ' " '
Unit 1/ Unit 2 (circle one)
SORC.u ro. no.
Pace 1 Or 4 Data Sheet pj /f7
/
E F FECTivE DA TE DATE FORM APPRQv{Dfjh-evfn/
H-26 4/
H-/29/
/JV/
6C SCHEDULT ME'
~~ APP. MODE FREQUENCY TEST AUTHORIZED BY DATE (55/5CO)
ACCEPTANCE CRITERIA MET:
ACCEPTED BY DATE (55)
YES NO APPROVED BY (DEPT. NEAD)
DATE SURVEILLANCE MAINTENANCE RESTORATlON
- 5) STEM AllGNMENT ACCEPTANCE CRITERI A 2.1 The transmitter module lamps on radiopager console light up after transmitter drill message.
2.2 The callback recorder phone numbers dialed respond with an audible and clear announcement drill message.
2.3 The callback recorder drill messages played back are audible and clear.
2.4 The NNECo/NUSCo personnel on call have called back to acknowledge the drill message or individual (s) contacted.
2.5 Towns /Acencies called back to acknowledge drill message or contacted by backup notification.
IN ACCORDANCE WITH REFERENCE PROCEDURE INITIAL p
- 1. PREREQUlslTES/INITI AL CONDITIONS COMPLETED V
- 2. PRECAUTICH5 NOTED
- 3. DATA:
7.1 Record / Verify Drill Announcement Message Initial
- Remarks Top 3 Single recorders itemaining 10 tandom recorders 7.2.5 Four Acknowledge Lamps Lighted Yes No,
- Remarks 1.
Chapel Hill 2.
South MTN 3.
Talcott MTN 4.
Goose Hill 5.
Millstone 7.2.6 Back Up Verification Initial Call State Police via Hot Line, blue phone i o EPIP Form 4610-1 Rev. 3 Date:
11/26/81 Page 1 of 4
(_
7.3.1.1 NUSCo/NNECO Callback Forms Call-In See Note Yes No
" Remarks O.
1.
Unit 10uty Officer SF-102 2.
Unit 2 Duty Officer SF-102 3.
NUSCo Duty Officer SF-123 4.
Nuclear Plant Public Affairs Duty Officer SF-124 5.
Director of Site Emerge,cy Operations SF-125 6.
Manager On-Site Resources SF-125 7.
Manager Site Engineering SF-125 8.
Manager of External Communications SF-125 9.
Manager of Radiological Assmt.
SF-125 10.
Unit 1 SS bO 11.
Unit 1 SCO 12.
Unit 1 R0 13.
Unit 1 EO _ Unit-1 Operations OPS Form 2,01-2 14.
Unit 1 PE0 15.
Unit 1 PE0
~
16.
Unit 2 SS 17.
Unit 2 SCO 18.
Unit 2 R0 19.
Unit 2 PE0 Unit-2 Operations On Call Schedule 20.
Unit 2 PE0 21.
Unit 2 PE0 O
EPIP Form 4610-1 Rev. 3 Date: 11/26/81 Page 2 of 4
O 7.3.1.1 NuSCo,NNeC0 Caiibeck rorms
.Caii-in See Note Yes N_o
" Remarks 22.
EMT No. 1 23.
EMT No. 2 24.
EMT No. 3 25.
EMT No. 4 26.
EMT No. 6 On Call Schedule 28.
EMT No. 7 29.
EMT No. 8 L
30.
EMT No. 9 31.
EMT No. 10 Note:
If "No" is checked for call-in, contact individuals to resolve problems.
7.3.1.2 Towns / Agencies Callback Call-in See Note Phone Numbers Yes No
- Remarks 1.
Groton City 445-2451 2.
Groton Town 445-2497 3.
Ledyard 464-7271 4.
Lyme 434-7733 or 434-7397 5.
East Lyme - Waterford Hot Line 6.
Old Lyme 339-7981 7.
Montville 848-9292 8.
New London-Waterford Hot Line 9.
Oid Saybrook 388-4675 10.
Waterford Waterford Hot Line 1o EPIP Form 4610-1 Rev. 3 Date: 11/26/81
-()))
7.3.1.2 Towns / Agencies Callback Call-in See Note Phone Numbers Yes No
- Remarks 11.
Fishers Island-516-924-4400 or 12.
Plum Island 516-924-5252 13.
Yaphank 1$.
State Police-Westboro--339-6221 15.
State Police-Montville-State 16.
State Police-Hartford
_ Police 17.
Office of Civil Preparedness Hotline 18.
Governor's Office 19.
State D.E.P.
Note:
For Towns / Agencies who did not call-in, refer to note under Section 7.3.1.2 of procedure for instructions.
()
7.4 Equipment Failure Initial or N/A
- Remarks Report all equipment failure to NUSCo System Test for repairs at extension 3800 - Berlin 8.
Restoration Initial 8.1 Reset acknowledge lamps on radiopager transmit module 8.2 Erase recorder drill Announcement and call-in tapes 8.3 Record the original Announcement Message 8.4 Reset callback recorders to ANS-REC
- Remarks - Under this column indicate action taken if acceptance criteria is not met.
O'-
EPIP Form 4610-1 Rev. 3 Date: ll /26/81 Page 4 of 4
m..
. _ ~ - - - - - - - - - - ____. _ ___ __- -_ _ _-
Approved By:
Data: //-19f/
SORC Mtg. No. cF/-#[
v,y
/
Radiopager
(
Daily Test Log Sheet MONTH Date Time Name c r le one)
Uns$t.
Remarks / Corrective Action l
0
(']'
Reviewed By:
/
/
SS/SCO Date NOTE:
Forward to main office for filing EPIP Form 4613-1 when completed.
Rev. 1 l
Date: 1 o/24/81 11 f 1 Page
h j-.1 500 UNIT 1 El:LRGLHCY PROCEDURES
.q NUMBER TITLE REV.
DATE-ISSUED OP 501/2501L Emergency Plan Procedure-CANCELLED 7/15/81 Replaced by'0P 501 OP 2501, ACP 1.15,
~
4000 Series OP 501 Incident Assessment and Classification 2 11/27/81 Unit 1
" OP 502A' Anticipated Transient without Scram 3
4/3/81 OP 5028 Emergency Plant Shutdown 2
6/10/81 OP 503A Loss of 345KV Transmission 5
2/27/81 OP 503B Loss of All Station AC Power 3
1/24/81 0P 503C Loss of Off-Site and On-Site AC 0
7/20/81 Power OP 504' Recirculation System Failures 7
8/24/79 OP 505/2511 Emergency Procedure Fire-6 4/31/81 OP 506 Loss of Coolant 2
4/14/81 OP 507A Potential Loss of Vacuum 1
7/15/81 OP 5078 Rapid Loss of Vacuum' l'
10/17/81 OP 508 Fuel Cladding Failure 3
10/23/81 0? 509 Excessive Radioactivity Levels 5
4/3/81 OP SilA Plant Shutdown from Outside the 3
'2/27/81 Control Room with Initial Phase Performed in Control Room OP 5118 Plant Shutdown from Outside the 3
2/27/81
, Control Room OP SllC Plant Shutdown from Outside the 4
2/27/81 Control Room with Initial Phase Performed in Control Room, Isolation Condenser Unavailable OP 5110 Plant Shutdown from outside the 4
2/27/81 c
Control Room Isolation Condenser Unavailable Rev. 75 11/19/81 Page 1 of 2
-500 OVERALL INDEX' f
~].
Rapid & Total Loss of Instrument Air 3
11/7/79
(
OP 513 Primary Containment liigh Pressure 7
12/12/80 l
OP 514A flatural Occurrences 8
8/5/81 i
OP 514B Freezing Temperatures Emergency 3
1/10/78 OP 514C Procedure - llatural Occurrences 1
10/17/81
/
OP 515 Chemical ltonitoring 7
1/24/81 OP 516A Loss of feedwater
-5 2/27/81 i,
OP 516B fluclear Steam System Rupture 2
1/1/80 OP 516C Control Rod Drive flydraulic System 2
'9/8/80 Rupture i
OP 516D Isolation Condenser System Rupture 3
4/4/80 OP 516E Reactor Clean-Up. System Rupture 3
1/2/80 OP 516F Loss of feedwater when Operating 2
8/15/79 p
at 40% Rated Power with the Isola-
.V tion Condenser Out of Service 0P 517 Auto Pressure Relier Valve Stuck Open 4
4/15/81' OP 518 Inadvertent Criticality 3
9/10/81 OP 519 Dropped Fuel Bundle 3
8/5/81 OP 520 Inadvertent Removal of Irradiated 0
11/14/76 l'
Parts or Compo'nents from the Reactor Vessel or Fuel Pool t
OP 521 Loss of Water Inventory in Reactor 2
10/23/81 Cavity or Fuel Pool OP 522
-Detonation in the Off-Gas System 0
12/22/77 A
. L).
Rev. 75 11/19/81 Page 2 of 2 L
APPROVAL:
E. J. Mroczka DATE:
6-18-80 Station Superintendent STATION PROCEDURE COVER SHEET g
A.
IDENTIFICATION.
Number OP 501 Rev.
2_
Title INCIDENT ASSESSMENT AND CLASSIFICATION - UNIT 1 Prepare ~d By A. G. Cheatham B.
REVIEW I have reviewed the above procedure _and have found it to be satisfactory.
TITLE SIGNATURE DATE DEPARTMENT HEAD h /T
// " //- //
O/S. Ass s mn:r-A/
- b/
h - n-e i 7-i C.
UNREVIEWED SAFETY QUESTION EVALUATION DOCUMENTATION REQUIRED:
-(Significant change in procedure method or scope as described in FSAR)
YES [ ]
NO [M O
cir ves. documeat in eoac/soac meetino tautes)
ENVIRONMENTAL IMPACT (Adverse environmental impact)
YES [ ]
N0 [X]
(If yes, document in PORC/50RC meeting minutes)
D.
PORC/SORC APPROVAL gg PORC/50RC Meeting Number
/~ N'
//[8 E.
APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and' effective on the dates below:
bd y d fk
/L v%
/t., p. rp
/(-L7di Station Superiqtyndent/ Unit Superintendent Approved Date ETfective Date SF-301 Rev. 3 t
v P
OP 501 Page l' t.
Rev. 2 Date:
11/27/8'1 i o' Incident Assessment and Classification,- Unit 1 Page No.
Eff. Rev.
Date-4 1
2 11/27/81 i
2 2
11/27/81 3
2 11/27/81 4
2 11/27/81 i
5 2
11/27/81 6
2 11/27/81 7
2 11/27/81
}
8 2
11/27/81 9
2 11/27/81 10 2
11/27/81 11 2
11/27/81
+
12 2
11/27/81 13 2
11/27/81 14 2
11/27/81 15' 2
11/27/81
-0 L
OP 501 Page 2
'Rev. 2 Date:
11/27/81 Q
1.
OBJECTIVE This procedure provides guidance for the assessment of initiating events and conditions in order to accurately and efficiently classify emergencies.
2.
DISCUSSION 2.1 A categorizatitn of Emergency Action Levels (EAL's) by severity and emergency classification is provided in Table 1,
" Incident Classification".
2.2 The authority and responsibility for the assessment, classification and declaration of emergencies initially resides with the Shift Supervisor of the affected Unit until he is relieved as the Director of Station Emergency Operations by the Station, Unit or Station Services Superintendent.
2.3 Emergencies are classified as to the relative hazard associated with the event.
This procedure enables the operator to determine two things:
(1) the NRC emergency classification of Q
an event and (2) the State Incident Class of the event.
2.4 Incidents are classified by referring to the matrix in Table 1 and finding in the INCIDENT DESCRIPTION column the words that best describe the type of incident that has occurred.
To the right of the general incident description, specific descriptions for various emergency class events are listed.
By matching the specific descriptions to the actual incident which has occurred the NRC emergency classification can be determined by the column heading.
2.5 If the incident is in the UNUSUAL EVENT column, it is then determined whether the State Class Code is ECHO or DELTA.
The State Class Code is listed below the incident.
If the incident is in the ALERT column, the State Class Code is always CHARLIE-0NE.
If the incident is in the SITE AREA EMERGENCY column, tne State Class Code is a! ways CHARLIE-TWO.
If the incident is in the GENERAL EMERGENCY column, it is determined whether the State Class Code i: BRAVO or ALPHA.
The O
State Class Code is listed below the incident.
t
OP 501 Page 3 Rev. 2 Date:.11/27/81 Q
3.
SYMPTOMS 3.1 Events are in progress or have occurred which indicate an actual or potential degradation of the level of. safety of the plant.
Table 1 describes various types of events. Symptoms are provided which offer guidance to the Shift Supervisor or Director of Station Emergency Operations in the classification of an incident.
3.2 The Shift Supervisor may have been referred to this' procedure by one of the Unit Emergency Procedures.
4.
AUTOMATIC ACTION None 5.
IMMEDIATE ACTION 5.1 Shift Supervisor of the Affected Unit.
5.1.1 Evaluate conditions, instrument readings and alarms with the assistance of other licensed operators and Q
Plant Equipment Operators.
Contact the Shift Technical Advisor for assistance.
5.1. 2 Carry out the immediate actions of the applicable emergency procedures.
5.1. 3 Refer to the matrix in Table 1 and determine the NRC emergency classification and State emergency classification.
5.1.4 If the incident ic not described in the matrix, make a determination of the NRC emergency classification by using the definitions at the beginning of the Table.
Then determine the State Class Code.
For an Jnusual Event (ECHO or DELTA) use the below definitions:
ECHO - Unusual event without radioactive releases DELTA - Unusual event with radioactive releases O
1
OP 501 Page 4 Rev. 2 Date:
11/27/81
(]
Determine the State Class Code for a General Emergency (BRAVO or ALPHA) using the below definitions:
BRAVO - General emergency without major breach
'in containment integrity, and the estimated site
-boundary dose is greater than 1 Rem whole body and 5 Rem thyroid.
4 ALPHA - General emergency with major-breach in containment integrity, and the estimated site boundary dose is greater than 5 Pem whole body and 25 Rem thyroid.
NOTE:
The State Class Code for an ALERT is CHARLIE-0NE and for a Site Area Emergency it is CHARLIE-TWO.'
5.1.5 Use the State Class Code determined in the above steps to make the notifications specified in the 4100 series EPIPs.
Always use it whenever discussing the
]
incident severity with Corporate, State cr local officials.
NOTE:
The State Class Code is used in the State and local emergency plans to determine what protective actions to implement and when to man emergency operating centers.
5.1.5 Use the emergency classification determined above and refer to the appropriate EPIP for the next actions to be taken.
Emergency Classification EPIP UNUSUAL EVENT 4101 ALERT 4102 SITE AREA EMERGENCY 4103 GENERAL EMERGENCY 4104 6.
SUBSEQUENT ACTION 6.1 As conditions change, consider escalation or de-escalation of O
the emergency classification and State Class Code using the
OP 501 Page 5 Rev. 2 Date:
11/27/81 O
Eat's ene uieence containee in this proceaure ena enniicebie o
Emergency Operating Procedures.
7.
FIGURES Table 1 - Incident Classification - Unit 1.
- A JEL:jf O
Io s
~
-a_
,q)
I
~f NRC CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY DEFINITION Events in progress or Events in progress or Events in progress or Events in progress or have occurred which have occurred which hace occurred which have occurred which indicate a potential involve an actual or involve actual or involve actual or im-degradation of the potential substantial likely major failures minent substantial I
level of safety of the degradation of the of plant functions core degradation or plant.
level of safety of the needed for protection melting with potential f
plant.
of the public.
for loss of contain-ment inteqrity.
ECt10 or DELTA riiARLIE ONE CilARLIE TWO BRAVO or ALPitA STATE CLASS i
(
l INCIDENT EMERGENCY ACTION LEVELS DESCRIPTION 1
(
I. Natural Pheno-Direct observation
(
menon (earth-or quake, tornado, notification by j
hurricane, external agencies flood) or j
seismic hionitors greater than 0.079 or sustained wind
(
-~
speed greater than 75 mph (measured at
(
the 142 ft. elevation)
F 5 ECD 0 e
r.;_
d E -
1 1
l c
E u
=
- =.=..:=-......
~
j h
f;RC CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY I fjC I DO,'T DtSCRIPTION II. Physical Fire lasting more than Fire having high poten-liazards 10 minutes in an area tial of or affecting (Fire, that has some potential safety systems.
Explosion, to adversely affect
- 1. Fire alarm from NA NA toxic or systems important to areas which could flaa.mable gas sa fe ty, affect safety release)
- 1. Fire alarms as related equipment appropriate e
or
- 2. Fire pump start CHARLIE-0NE o
alarms ECHO Direct observation of Direct observation of other hazards which unanticipated signifi-cculd endanger the cant hazard which has facility (e.g. onsite a relatively high plane crash, train degree of potential for
~
derailn'ent, explosion, affecting reactor onsite toxic or flam-safety and/or signifi-NA NA mable gas release.
cant release. (i.e.,
aircraf t crash, ex-plosion damaging plant
(
ECl10 structures, uncontrol-led entry of toxic or flammable gases onsite) i? %
~
CilARLIE-0NE
.,k M
'.)
=
3 c 1 s
_=.;_
NRC CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Dd'CI DENT 5CRIPTION It III. Security Notification by Notification by Notification by Notification by Threa t/
Security of a security Security of an ongoing Security of the.
Security of loss of Compromise threat.
security compromise.
imminent loss of physical control of the g
physical control of station due t'oA p
i station.
security incident.
m ECHO CilARLIE-0NE CilARLI E-TWO BRAVO IV. Loss of AC loss of offsite Loss of offsite power Loss of offsite power g;
Station power or_ total loss of and loss of all onsite and loss of AC power O
Services onsite AC power AC power.
for more than 15_
g l
Power capability.
- 1. 4-KV bus trips and minutes.
=
l (ACorDC)
- 1. 4-XV bus trips and RSST undervoltage
- 1. 4-KV bus trips an'd n
reserve Station alanns RSST undervoltage c-I Service transformer and alanns NA f3 (RSST) undervoltage
- 2. Gas turbine and and C
alarms diesels not ready
- 2. Gas turbines and 2
or-for auto start diesels not ready 9
. Gas tuFbine and alarms.
for auto start.
d diesels not ready 8
for auto start alarms.
ECHO CHARLIE-0NE C.HARLIE-TWO DC Loss of all onsite Loss of all onsite DC DC power.
power for more than NA
- 1. Battery trouble 15 minutes.
NA 5'l alarms.
E Battery trouble
{g alarms.
CliARLIE-0NE CilARLIE-TWO ay oo "o
Cti i
A i
NRC CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY
~
Dd'CIDENTdCP.lPTION I'
V..
Plant Safety ECCS initiated with or Protection discharge to vessel System
- 1. ECCS pump running
(
Functions annunciator and~
(
- 2. a. DryweTl pressure NA NA NA greater than 2 psig er
- b. Reacto7 water level less than 79" above the core ECil0 Failure of a primary system safety relief valve to close
- 1. Relief va Ne dis-
~
charge high temper-NA NA NA ature alarm or
- 2. Torus later high temperature alarm
{
or-
- 3. Relief valve open g g indication
- (
or
- 4. Acoustic monitor alarm ECHO EI gk
'4 W
?
-~-
. -.... -. ~. - -.
=.._.
-_=.
()
(
NRC CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY IfTIDENT Dd5CRIPTION V..
Plant Safety Loss of engineered Loss of functions or Protection safety feature or fire needed for plant cold El System protection system shutdown Functions function requiring
- 1. Operation beyond
{
(contd.)
shutdown by Technical the action state-Specifications ments in the Tech-(W
- 1. Determine by nical Specifications NA NA Technical Specifi-for systems required cation LC0's.
for cold shutdown.
O e
{[
(CHARLIE-0NE) gc,;g Failure of reactor protection system to g
initiate and complete t
a reactor scram which brings the reactor p
subcritical.
E
- 1. Reactor scram alarm p
i:
with continued indication of power level.
(CHARLIE-0NE)
.Q Loss of all alarms All alarms (annunci-and annuciators ators) lost and signi-
- 1. Direct observation ficant abnormal transients in progress.
m:
1 (CHARLIE-ONE)
(CHARLIE-TWO)
NA
'il di 6
N w.
8d
[
= _ _. ___.
. m.. %
____s
.1 NRC CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY I!jCIDENT 0:SCRIPTION V. Plant Safety Evacuation of control Evacuation of Control
~or Protection room anticipated or room and control of System required with control shutdown systems not Functions of shutdown systems established from local (contd.)
from local stations stations in 15 minutes.
F NA
- 1. Control room fire
- 1. Direct observation NA occurs
=
or
- 2. ControT room area y
radiation monitor CHARLIE-TWO E
alarm f.
_[_
CHARLIE-0NE
~
9 VI. Release of High radiation level 3
Radioactivity /
or high airborne con-r High Radiction
'tamination which indi-cates a severe E
Levels degradation in the NA control of radioactive NA NA g
material.
~
For example: Fuel handling accident with release of radioactivity to the reactor building CHARLIE-0NE.
gG N
~
~s e
i..
a-l.
lis l
l a
1
~
$o
%)
(
~
m >
.t r.u.5-E:E -
. v.-
- -. : 7~..
w I
EMERGENCY ACTION LEVEL b kbk.
IO!:
l VI. Relea:e of Fuel handling accident Major damage to spent Radioactivity /
with release of radio-fuel.
liigh Radiation activity to the reactor
- 1. Area radiation NA g
y Levels (contd.)
building.
monitor on refueling NA
- 1. Iligh range refueling floor reads greater p.
floor area radiation than 1000 mr/hr.
monitor alarm and or
- 2. Direct E~bservation ContinuEiis air of fuel handling h
monitor alarm accident.
g m
and 5
- 2. Direct observation of fuel Iindling p
accident.
'y' CHARLIE-TWO CHARLIE-0NE Instantaneous radio-Radiological effluents Actual or estimated Radiation monitors R
logical effluent greater than,10, times releases corresponding detect levels corres-R Technical Specification technical specification to greater than 5_0 ponding to 1 t0 5 rem E
0 limit exceede'd.
instantaneous limits mr/hr_ whole body dose shole body dose or 5 to
- 1. Liquid effluent for more than 1_5_
at ti.e site boundary, 25 rem thyroid close at 5
monitor alarm minu tes, or 250 mr/hr thyroid the site boundary.
- 1. Stack radiation dose.
- 1. Unit I stack gas O
or Stacii RMS alarm muni tor alarm.
- 1. Stack gas monitor monitor greater than and or between ex104 cps 7x105 cps
- er
. 2. Analyses indicate
- 2. LiquiiT~ effluent and 7x10b cps offscale
- 5'@
limit was exceeded.
radiation monitor or-or alarm.
- 2. EMT's detect levels
?. EMT's ifetect levels 5m DELTA of:
of:
"S (cont.)
(cont'd)
CllARLIE-0NE
'If necessary, dispatch EMT#1 to determine I-131 concentrations a c-and whole body dose ran 55 at the site boundary.
Q 3-
=
o
1
/ %
f h'
ij d
NRC CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY I
_i t
If;CICEtiT j
DESCRIPTION Main steam line break Steamline break outside II. Primary i
- 1. Steam flow mismatch containment without of Fission NA alarm isolation.
j System / Loss and
- 1. Steam flow mismatch Product
- 2. Steam tunnel high alarm Boundary temperature alarm and NA Ei (195 )
Steam tunnel high 8'
m and temperature alarm
- 3. Steam line high (200 )
[
r radiation alarm and (3xN)
- 2. Main steam isolation E!
valve position indi-O C
cation - open.
~
and 5l
- 3. Steam line high rad-n,
e $
C iation alorm (7xN)
CHARLIE-0NE CilARLIE-TWO 4
n Abnormal coolant a
temperature and/or NA NA NA g
pressure
=
Primary pressure greater than 1125
- cc psig S'
or
~
- 2. Primary temp. less than Technical Speci-fication Limits b --
f{I ECtt0 Dy b
o
'4
[
N t
NRC CLASS UNUSUAL LVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY f
EMERGENCY ACTION LEVEL 6$bN"TEPTION VII. Primary Exceeding the primary Primary coolant leak Loss of coolant LOCA and failure i
System / Loss system leak rate Tech-rate exceeding 50 gpm accident (LOCA) to isolate containment i
of Fission nical Specifications
- 1. Total dryuell leakage 1. High drywell or potential to l
Product
- 1. Total drywel', leakage greater than 50 gpm pressure (2 psi) rupture containment.
- ! [
- 1. LOCA (as in site l2 %
or Boundary greater than 25 gpm p
er leve
")
a
- 2. Unide ified leakage and 2.a. Drywell pressure greater than 2.5 gpm ECCS pump running remains normal t
8 or ECHO
- b. Isolation valve
%f
- r open light CHARLIE-0NE CHARLIE-TWO indication P
nr
- c. Drywill pressure 3$y exceeded 62 psig BRAVO 2
9'
~
Significant loss of 8j containment integrity requiring shutdown by h
h Technical Specifications gw f
- 1. Loss of drywell NA NA NA integrity as deter-l nined by lechnical t
l Specification LC0's 5'E :
or
<"E
- 2. Equipiiiint f ailure re-su'. ting in inabili.ty
"~;
to isolate cc.itain-ment penetrations.
l EC!:0 U
ES:
[
,DE 2
b
I NRC CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EMERGENCY ACTION LEVEL
[*j{hi{I0'l 111. Primary Sudden fuel damage Severe loss of fuel Degraded core with Any potential core Sys te:a/ Loss indication cladding possible loss of relt situation of Fission
- 1. Air ejector RMS trip
- 1. Offgas air ejector coolable geometry
- 1. LOCA
[
monitor greater than
- 1. Core less than P/3 and y
j, Boundary ECHO lx105 mr/hr covered alarm.
- a. Partial failure of p
[
d Product ECCS as indicated j
m or (cont.)
by pump and valve t
2, Chemistry sampling status indicators
(
yields an 1-131 dose l
CilARLIE-TWO or
=
equivalent greater
~
R
- b. Failure to shut-than 300 uCi/ml in down as indicated 5
l primary coolant by neutron moni tor y
or n
CilARLIE-0NE
- 2. Total loss of long g
term cooling as in-e dicated by pump and {
valve status indica-2 tors for the ECCS 9
and shutdown cooling d
systems.
i BRAVO O
p
.g
~-
4 G2 m
7 i
O2 L
Unit 2 2500 EMERGEllCY PROCEDURES Itt0EX O
riunBeR TI1te Rev.
DATE issue 0-501/2501 Emergency Plan Procedure CANCELLE0 7/15/81 Replaced by 0P 501, OP 2501, ACP 1.15, 4000 Series Incident Assessment and Classification 2 12/3/81 j
OP 2501
, Unit 2 2502 Emergency Shutdown (Reactor Trip) 12 11/30/81 2503 Electrical Emergency (Loss of flormal 7
9/3/81 Power) 2504 Loss of Reactor Coolant Flow 6
10/23/81 2505 Primary System Leakage 3
10/17/78 2506 Loss of-Coolant Incident 10 8/13/81 2507 Loss of Condenser Vacuum 4
2/18/81 2508 Loss of Reactor Bldg. Closed Cooling 2
2/16/77 Water 2509 Steam Line Rupture 7
10/23/81 2510 Natural Occurrences 5
8/19/80 505/2511 Emergency Procedure' Fire 6
4/31/81 2512 Loss of Instrument Air 3
10/24/78 2513 Shutdown from Outside the Control
'6 4/23/81 Room 2514 Emergency Boration 4
10/23/81 2515 Steam Generator Tube Rupture 8
9/3/81 2516 Steam Generator Chemistry 6
11/28/79 2517 Earthquake 2
6/30/77 2518 Loss m' Service Water 2
7/31/78 2519 Electrical Emergency (Loss of Main 02 1/16/81 DC Bus)
O Rev. 73 1?/1/81 Page 1 of 2
_.. _. _ _.... _. ~... _.. _.
.. _ _ _.. _.. _ _ ~. _ _ _ _ _ _ _ _.
{
-2500 OVERALL INDEX i
g '
2520' Fuel llandling Accident Inside 2
4/1/81 i
Containment 2521 Loss of'Feedwater/ Steam Generators 0
1/1/80 4
E
.I.
5 O
k Rev. 73 12/1/81 Page 2 of 2
F e
APPROVAL:
E. J. Mroczka DATE:
6-18-80 E tien Superintendent (9
STATION PROCEDURE COVER SHEET A.
IDENTIFICATION Number OP 2501 Rev.
2 Title INCIDENT ASSESSMENT AND CLASSIFICATION -UNIT 2 Prepared By A. G. Cheatham B.
REVIEW I have reviewed the above procedure and have found it to be satisfactory.
TITLE SIGNATURE DATE DEPARTMENT liEAD
^[m2
////4/f/
C.
UNREVIEWED SAFETY QUESTION EVALUATION DOCUMENTATION REQUIRED:
O (Significant change in procedure method or scope as described in FSAR)
YES [ ]
N0 [a Y-(If yes, document in PORC/S0RC meeting minutes)
ENVIRONMENTAL IMPACT (Adverse environmental impact)
YES [ ]
N0 [,::4--
(If.yes, document in PORC/SORC meeting minutes)
D.
PORC/50RC APPROVAL PORC/ SORT Meeting Number 2-8/-7Y E.
APPROVAL AND IMPLEMENTATION The attached procedure'is hereby approved, and effective on the dates below:
b br'W en
~ ill19 ?!
17 3 S/
Station'Superhitendent/ Unit S(herintendent Appr6ved Date Effecti~ve Date SF-301 Rev. 3 O
' OP 2501 Page 1
~
Rev. 2 Date: 1 2/3/81 0
INCIDENT ASSESSMENT AND CLASSIFICATION - UNIT 2 Page No Eff. Rev.
Date 1
2 12/3/81 2
2 1 2/3/81 3
2 12/3/81 4
2 12/3/81 5
2 1 2/3/81 6
2 12/3/81 7
2 12/3/81 8
2 12/3/81 9
2 12/3/81 10 2
12/3/81 i
11 2
1 2/3/81 12 2
12/3/81 0
13 2
12/3/8, 14 2
12/3/81 15 2
1 2/3/81 16 2
1 2/3/81 17 2
1 2/3/81 18 2
1 2/3/81 19 2
1 2/3/81 20 2
1 2.'3/81 21 2
12/3/81 O
r
OP 2501 Page 2 Rev. 2 Date: 12/3/81 O
V 1.
OBJECTIVE This procedure provides guidance for the assessment of initiating events and conditions in order to accurately and efficiently classify emergencies.
2.
DISCUSSION 2.1 A categorization of Emergency Action Levels (EAL's) by severity and emergency classification is provided in Table 1, " Incident Classification".
2.2 The authority and responsibility for the assessment, classification and declaration of emergencies initially resides with the Shift Supervisor of the affected Unit until he is relieved as tiie Director of Station Emergency Operations by the on-call Director.
2.3 Emergencies are classified as to the relative hazard associated with the event.
This procedure enables the operator to determine two things:
(1) the NRC emergency classification of an event, and (2) the State Incident Class for the event.
E.4 Incidents are classified by referring to the matrix in Table 1 and finding in the INCIDENT DESCRIPTION column the words that best describe the type of incident that has occurred.
To the right of the general incident description, specific descriptions for various emergency class events are listed.
By matching the specific descriptions to the actual incident which has occurred the NRC emergency classification can be determined by the column heading.
2.5 If the incident is in the UNUSUAL EVENT column, it is then determined whether the State Class Code is ECHO or DELTA.
The State Class Code is listed below the incident.
If the incident is in the ALERT column, the State Class Code is always CHARLIE-0NE.
If the incident is in the SITE AREA EMERGENCY column, the State Class Code is always CHARLIE-TWO.
If the incident is in the GENERAL EMERGENCY column, it is determined whether the State Class Code is BRAVO or ALPHA.
The State Class Code is listed below the incident.
I
OP 2501 Page 3 Rev. 2 Date:12/3/81 O
3.
svae:0Ms 3.1 Events are in progress or have occurred which indicate an actual or potential degradation of the level of safety of the plant.
Table 1 describes various types of events.
Symptoms are provided which offer guidance to the Shift Supervisor or Director of Station Emergency Operations in the classification of an incident.
3.2 The Shift Supervisor may have been referred to this procedure by one of the Unit Emergency Procedures.
4.
AUTOMATIC ACTION None 5.
IMMEDIATE ACTION 5.1 Shift Supervisor of the Affected Unit 5.1.1 Evaluate conditions, instrument readings and alarms with the assistance of other licensed operators and O
eient equipment Operetors. Contect the Shift Technical Advisor for assistance.
5.1.2 Carry out the immediate actions of the applicable emergency procedures.
5.1.3 Refer to the matrix in Table 1 and determine the NRC emergency classification and State emergency classification.
5.1.4 If the incident is not described in the Matrix, make a determination of the NRC emergency classification by using the definitions at the beginning of the table.
Then determine the State Class Code.
For an Unusual Event (ECHO or DELTA) use the below definitions:
ECHO - Unusual event without radioactive releases DELTA - Unusual event with radioactive releases O
OP 2501 Page 4 Rev. 2 Date:12/3/81 m'V Determine the State Class Code for a General Emergency (BRAVO or ALPHA) using the below definitions:
BRAVO - General emergency without major breach in containment integrity, and the estimated site boundary dose is greater than 1 Rem whole body and 5 rem thyroid.
ALPHA - General emergency with major breach in containment integrity, and the estimated site boundary dose is greater than 5 Rem whole body and 25 Rem thyroid.
NOTE:
The State Class Code for an ALERT is CHARLIE-0NE and for a SITE AREA EMERGENCY it is CHARLIE-TW0.
5.1.5 Use the State Class Code determined in the above steps to make the notifications specified in the 4100 O
V series EPIPs.
Always use it whenever discussing the incident severity with Corporate, State or local officials.
NOTE:
The State Class Code is used in the State and local emergency plans to determine what protective actions to implement and when to man emergency operating centers.
5.1.6 Ilse the emergency classification determined above and refer to the appropriate EPIP for the next actions to be taken.
Emergency Classification EPIP UNUSUAL EVENT 4101 ALERT 4102 SITE AREA EMERGENCY 4103 GENERAL EMERGENCY 4104 0
-NN-w
--p,
OP 2501 Page 5 Rev. 2 Date: 12/3/81 6.
SUBSEQUENT ACTION 6.1 As conditions change, consider ~ escalation of the emergency classification and State Class Code using the EAL's and guidance contained in this procedure and applicable Emergency Operating Procedures.
7.
FIGURES Table 1 - Incident Classification - Unit 2.
AGC:bjo O
O i
O O
O NRC CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY DEFINITION Events in progress or Events in progress or Events in progress or Events in progress or have occurred which have occurred which have occurred which have occurred which indicate a potential involve an actual or involve actual or likely involve actual or im-degradation of the level potential substantial major failures of plant minent substantial core of safety of the plant.
degradation of the functions needed for degradation or melting g
level of safety of the protection of the public with potential for loss g
plant.
of containment integrity STATE CLASS ECHO or DELTA CHARLIE ONE CHAR;_lE TWO BRAVO or ALPHA O
~
E O
C2 INCIDENT EMERGENCY ACTION LEVELS E
DESCRIPTION p
I. Natural pheno-With the potential to 3
menon (earth-affect the level of 3
quake, tornade, safety hurricane,
- 1. Direct observation 9d flood) or
- 2. NotifTcation by NA NA NA E
external agencies h
or 1
- 3. Seismic monitor
> 0.079 h
or
- 4. Sustained wind speed >75 mph 5'%
(measured at 142
?m f t. elevation)
N8
~
I ECHO
??
e gg N
M S
O O
NRC CLASS l'NUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY bbfbkION II. Physical Fire lasting >10 minutes Fire having high hazards (fire, that has potential to potential of or affect-d explosion, adversely affect safety ing safety systems.
O toxic or related systems.
- 1. Indications of flammable gas 1.a. Fire detection actual fire are release) panel alarms received -
or
- a. Fire detection
- b. Fire pump running panel alarm (s)
NA NA g
alarms or g
and
- b. Fire pump running m
- 2. Leads to investiga-alarm 5
gation shich deter-or n
mines an actual c.VisuaT confirmation E
fire is in progress.
and M
- 2. Fire is verified to 4;
ECHO be in immediate M
vicinity of safety 4
related systems a=
CHARLIE-0NE Hazards which could Unanticipated signifi-endanger the facility cant hazard having Q
(e.g. train derailment, relatively high degree explosion, onsite toxic of natential for af-or flammable gas re-fecting reactor lease) safety and/or signiff-F58 cant releases to the NA NA m
ECHO environment. (e.g.
m8 aircraft crash, ex-plosion damaging plant, etc.)
$[
l CHARLIE-0NE mm N
=
3
?
O O
O NRC CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY ObCbkION III. Security Notification by Notification by Notification by
. Notification by Threat Secu 'ity of a security Security of an ongoing Security of the im-Security of loss of threat.
security compromise.
minent loss of physica f physical control of y**
control of the station, the station.
h ECHO CHARLIE-0NE CHARLIE-TWO BRAVO Q
IV. Loss of Statior AC Loss of all tie Loss of offsite power Loss of offsite power 5
Services lines between and and 8
Power switchyard and 345 Loss of all onsite AC Loss of onsite AC NA 9
KV grid, power power for more than or
- 1. All offsite line 15 minutes l2 TotaT loss of onsite isolation breakers E open breaker indi-3 AC power capability open cations for offsite
- 1. All offsite line and lines on the 3
isolation breakers
- 2. Both diesel gener-switchyard status 9
ator trouble alarms.
panel d
open and B
or 2.a. Both diesel gen-CHARLIE-0NE
- 2. TroubTe/ disabled erators declared alarms on both inoperable diesel generators
.Q and
- b. Normal Station CHARLIE-TWO Service Trans-former unavailable f 58 ECHO
,m M
M S
I
19 G
p)
,ry q
G i
NRC. CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 0$'CIDENT It
$CRIPTION IV. Loss of Station DC Loss of all onsite Loss of all onsite Services vital DC power DC power for more than Power
- 1. Both battery trouble 15 minutes NA g
NA alarms
- 1. Both battery trouble alarms
(
CHARLIE-ONE CHARLIE-TWO V.
Plant Safety ECCS initiated with E
or Protection discharge to vessel C
System
- 1. SIAS annunciation Functions and 4
l 2.a. Pressurizer NA NA NA n
pressure <l600 E
psia y
or n
- b. Coiitainment y
pressure : 5 3
PS19 ECHO Loss of all alarms All alarms (annunci-or annunciators for ators) lost and signi-NA greater than 15 ficant abnormal trans-NA I
minutes.
ient in progress
- 1. Direct observation
- 1. Direct observation CHARLIE-ONE CHARLIE-TWO F%
?~
~g EW L'
R
i O
O o
NRC CLASS UNUSUAL EVENT AtERT SITE AREA EMERGENCY GENERAL EMERGENCY ItjCIDENT DtSCRIPTION V. Plant Safety Failure of a reactor
- f
'or Protection coolant system safety y
System or relief valve to Functions close (cont.)
- 1. High temperature NA NA NA
{
alarms (> l80 F) k4 on discharge piping from relief / safety g
valves g
and g
w 2.a. Quench tank level, o
temperature and/or pressure increasing
{
F
- b. Acoiiiitic monitor E
n alarms 4
q ECl10 f
Evacuation of control Evacuation of control 1
room anticipated or room and control of required with control minimum shutdown h
NA of shutdown systems systet.1s not established NA from local stations.
from local stations in g
- 1. Control Room 15 minutes.
Chlorine Alarm
- 1. Direct observation or
- 2. ConFol Room Fire xo E"
l or CHARLIE-TWO
- 3. ConWol Room ARM Q
alarm.
CliARLIE-0NE g
t'8 i
M k
e i
O O
O i
l ALERT SITE AREA EMERGENCY GENERAL EMERGENCY NRC CLASS UNUSUAL EVENT IUQIDENT DESCRIPTION V. Plant Safety Loss of functions need-or Protection ed for plant cold d
System shutdown Functions
- 1. Operation beyond the P
(cont.)
action statements in
{
1 Technical Specifica-tions for systems Q'
=
required for cold shutdown.
yl E
Loss of engineered
-CHARLIE-0NE
-e safety reature or fire o
protection system function requiring Failure of reactor pro-NA NA h
m shutdown by technical tection system to M
specification initiate and complete
- 1. As determined by a reactor trip which y
technical specifica-brings the reactor d
tion LC0's.
subcri tical.
sa
^
- 1. Core mimic display ECHO indicates a signi-ficant number of I P control element assemblies remain-g ing out of core, coincident with a reactor trip alarm.
Temperature (Tavg) yo or primary system m
pressure remaining yg high or rising.
CHAf! LIE-0NE oo C
mm s-is
O f
f )
C V
V NRC CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY bN ION VI. Release of Instantaneous radio-Radiological effluents Actual or estimated Radiation monitors Radioactivity /
logical effluent tech-greater than 10 times releases corrcsponding detect leveis corres-5!
High Radiation nical specification technical specification to creater than 50 ponding to 1-5 rem F
Levels limit exceeded.
instantaneous limits mr/hr whole body dose whole body dose or 5-25 1.a. MP2 stack monitor for more than 15 rate rem thyroid dose at alarm minu tes.
or the site boundary.
or
- 1. Stack radiation 250 mr/hr thyroid E
- b. Liqiifd Effluent monitor or liquid
- 1. Unit #1 stack gas
- 1. Unit #1 stack gas O
R monitor heater Monitor Alarm effluent radiation moni or between than 7xl cps or l $
and monitor alarms 4x]
cos and 7x1 cp:
offscale *
- 2. Analysir indicates
~
P limit was exceeded or or CHARLIE-ONE-
- 2. Unit #2 stuck gas
- 2. Unit #2 stack gas 3
DELTA monitor greater monitor offscale*
than lxlCS cps or Z!
but still ce scale
- 3. Unit #2 stack inter-9 or im high range d
- 3. Unit #2 stack inter-monitor greater im high range than 2 R/Hr monitor greater than or 100 mr/br and less
- 4. Atmospheric steam than 2000 mr/hr cump measurement or_
result greater than
- 4. Atmospheric steam 400 mr/hr dump measurement or result greater than no 20 mr/hr but less (cont.)
than 400 mr/hr
- N
- If necessary, dispatch yo or
~
EMT#1 to determine 6
I-131 concentrations (cont.)
and whole body dose rate at the site 5'8 boundary.
T5 s
N b
t 2
O O
O NRC CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL' EMERGENCY
!' CIDENT DE5CRIPTION
- 5. Containment post
- 5. Containment post VI, Release of accident area monitor accident area monitor Radioactivi ty/
between 10 R/Hr and greater than 80 P/Hr.
-4 High Radiation Levels (cont'd) 80 R/Hr
- 6. EMT's detect 7cvels E
or anywhere offsite of: 6'
- 6. EMT's detect levels dose rates greater V
anywhere offsite of:
than 1 rem /hr.
- a. dose rates greater or than 50 mrem /hr Iodine-I31 concen-M
-or trations greater Es
- b. Iodin !131 concen-than 1x10-5 uCi/cc.
g?
trations greater than 5x10-7 uCi/cc.
C2 4
1 CHARLIE-TWO BRAVO 5;
w Radiation Monitors detect levels corres-F; ponding to greater than EI 5 rem whole body or 25 23 2
rem thyroid at the site NA boundary.
- 1. Unit I stack gas
())
monitor offscale*
or
- 2. Unit 2 stack gas in-l; terim high range i
monitor greater than 23 c3 10 R/hr o
63 or I!d
- 3. Unit 2 stack gas monitor offscale*
E i
l
'~
(cont'd)
??
Q5 7
3 N
(~)
n r
V (y
,/
V NRC CLASS tlNUsuAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY INCIDENT DESCRIPTION or l
VI. Release of
- 4. Atmoipheric steam Radioactivity /
dumps measurement High Radiation result greater than Levels (cont'd) 2000 mR/hr h
E
- 5. Containment post i.
accident area monitor m j
greater than 400 R/hr i
or EMT'i~ detect levels
=
anywhere offsite of 5
dose rates greater g
thar.1 Rem /hr or j
I-131 concentrations greater than 5 x 10-5 r
NA NA NA uCi/cc.
p
- If necessary, dispatch
]
EMT#1 to determine 9
I-131 concentrations d
and whole body dose rate at the site bound-ary.
l w to o ALPHA
[N
- ~S E' 2 EW hE e
E l
q I
)'s T a.
U I(aE gn ay n ReZ9'.nO n%"e 1
O t.
yC3 YC oG N
E
.R EM E
AN LAR E
N EG YC N
E GR EM E
A A
E N
S r
g
- af o
n
- ido i
l nda l
r e0d eonrl a o
l0a o
vcigoi t
a0e e
errai rc1 r l ehdt een is nc nt ro afnl nrieoaam f aa E ooh rcm soh mN T
i b we dn u
t r 0 R
rirrn os o
t r veeeo E
aineh vni oi E
L aosti nt s noe I
i A
d i
taam itt s L aht ancli r ti ae R rga i a pd a nnemA ins onal oori H hhieniUra C m gt C g
mt od iraaia Hot ctr1 2
TN E
VE AN L
AU SU N
U
)
/nd yo' tit O
it n N
f vao O
oiic S
I td(
S TT eca A
NP saR s L
EI ao l
C DR eih e IC l d gv C
CS eaie R
NE RRHL N
ID I
V i
l
3
/
g O
O o
NRC CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY I
INGIDE'4T DESCRIPTION Fuel handling accident Major damage to spent
' ' VI.. Release of with release of radio-fuel in containment or High Radiation activity to containment fuel. handling building Radioactivity /
Levels (cont'd) or fuel handling 1.a. Containment ARM i
NA building greater than 1000
'NA 1.a. Containment AR14 mr/hr.
n d
W alarm or l
- b. Spent fuel ARM E
or C
l l
- b. Containment air greater than 1000 monitor alarm mr/hr.
l and Ci or i
- c. Spent Fuel Pool
- 2. Direct observation n
ARM Alarm of fuel handling
{
or accident.
w
- d. Spent Fuel Pool.
n Air Monitor Alarm y
and
- .3 e
- 2. Direct observation of s "
fuel handling acci-
{
dent.
h CHARLIE-ONE CHARLIE-TWO VII. Secondary Unplanned depressuriza-Steam line break with Steamline break with h
System tion of secondary side significant primary to significant primary to failure of steam generators.
secondary leakage.
secondary leakage and NA
- 1. Steam generator A. Break Inside indication of fuel me 2"
pressure less than Containment damage.
500 psia.
- 1. Steam generator LO?S I
pressure low alarm pressure low alarm ECHO and and (cont.)
(cont.)
o, Ww 4
R
O O
O NRC CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL' EMERGENCY OkCkhTION VII. Secondary (See previous page)
- 2. Containment high 2.a. Air ejector System pressure / tempera ture radiation monitor Failure alam alarm y>
(cont.)
and or
- 3. Containment area or
- b. Blowdo'wn radiation NA lQ atmosphere radiation monitor alarm monitor alarm and and
- 4. Main steam isolation
- 3. Letdown radiation signal monitor alarm
.~
B. Break Outside
~
of Containment CHARLIE-TWO
- 1. Steam generator p
pressure low alarm 3
w and
- 2. VCT low level alarm n
~
and nM'
- 3. Main steam isolation signal.
y Q
CHARLIE-0NE O,
NS
?~
N8:
.~
C C
- (
~
~
R 1.'g
O O
O NRC CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY irrIDENT DESCRIPTION VIII. Primary Suddenly exceeding Reactor coolant leak LOCA of coolant acci-LOCA and failure to System / Loss either primary to rate greater than the dent (LOCA) isolate containment or of Fission secondary leak rate capacity of I charging
- 1. Low pressurizer potential to rupture E
Product technical specification pump pressure alarm containment.
(h
~
Bour.dary or primary system leak
- 1. Containment atmos-and
- 1. Low ~ pressurizer br
~
rate technical speci-phere radiation
- 2. Containment ARM pressure alarm (3
i fication.
monitors alarm alarm and W
l. Primary to secondary and and
- 2. Low pressurizer C
leak in either steam
- 2. Pressurizer level
- 3. Air particulate level alarm S
generator greater program calls for monitor alarms and i'i than 0.5 gpm additional charging
- 3. Containment ARM o
or pump (s) to start.
alarms 5
~
- 2. Prindry unidentified and 12 leakage greater than CHARLIE-0NE CHARLIE-TWO 4.a. Containment 9
1 gpm pressure remains R
normal II or
- 3. IdentiTied leakage or 5
=
greater than 10 gpm.
- b. IsoTation valve open light ECHO indication
,O or
- c. Containment hydrogen concen-tration greater i
than 4%
or e
- c. Containment E"
pressure exceeded y
54 psig.
~
BRAVO E
I*
N I
t' E
1
e O
O
~
NRC CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY bkhCkfhION VIII. Primary Rapid failure of many Rapid failure of many System / Loss steam generator tubes steam generator tubes of Fission (e.g. several hundred with loss of offsite E
Product gpm primary to second-power.
Boundary ary leak rate)
- 1. Air ejector N'A O
(cont.)
NA
- 1. Air ejector radia-radiation monitor tion monitor alarm alarm and and E-
- 2. Pressurizer low level 2. Sustained depressur-C alarm ization of pressur-and izer ti
- 3. Volume control tank and e3 (VCT) low level
- 3. Low voltage or open E
alarm breaker indication 7,
and for all offsite
- s
- 4. Auto start of addi-lines.
Fs tional charging pump.
CHARLIE-TWO Es
=
CHARLIE-0NE Rapid gross failure of Q
steam generator tube (s)
Q with loss of offsite power
- 1. Air ejector monitor alarm and g'Q 2.a. Switchyard status Ng panel indicates
~
breakers open for all offsite lines or (c5iit. )
s'? i a"n S'*
i t
?
f
\\
O O
O HRC CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY bbC P ION i_
VIII. Primary 2.b. Reserve station (See previous page)
System / Loss services trans-of Fission NA former fails as NA g
to indicated by Product i
Boundry i
trouble alarm and (cont.)
direct observation h
CHARLIE-ONE Sudden fuel damage Severe loss of fuel Degraded core with Any potential core h
indication cladding greater than possible loss of cool-melt situation o
- 1. Letdown system rad-1% fuel failure able geometry 1.a. LOCA
=
iation monitor alarm
- 1. Chemistry Dept.
- 1. Subcooling monitor and and' Reactor Coolant sampling indicates less than or equal
- b. Partial failure of P
Analysis indicates dose equivalent to zero ECCS or failure M
>l uCi/ml dose equi-Iodine - 131 greater and to shutdown 2
valent Iodine 131.
than 300 uCi/ml in
- 2. Incore thermo-couple or
~
primary coolant.
greater than 700 F.
2.a. TBtal loss of 9
ECHO feedwater O
CHARLIE-ONE CHARLIE-TWO and
- b. Failure of auxili-ary feedwater h
and
- c. Failure of ECCS BRAVO Abnormal coolant temp-erature and/or pressure NA NA NA og 3u
- 1. Tc greater than
- m 549 alarm or (con t. )
l n
_,~4 m
e
a.
O (vD u'
0'-
NRC CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 1
~
D$b n,,-INTION l
t VI'I. Primary
- 2. Pressurizer pressure 1
System / Loss greater than 2350 of Fission psia for greater than NA NA NA g
1 Et
.{-
Droduct 2 '1ours.
~
Soundary o r_
hr (cont.)
- 3. Pressurizer pressure greater than 2400
=
psia 0
4 91 o
t
- 4. Pressurizer pressure
=
j less than 2225 psia for greater than 2
,q hours.
8
. t i
Significant loss of l
containment integrity L-requiring shutdown by l, j -
technical specification NA NA NA g
1
=j
- 1. Equipment failure 1
resulting in inability A
to isolate contain-g'%#
l l
ment penetrations or l
- 2. Loss oT containment integrity as deter-m mined by technical specification LC0's.
P.N I
1.
NGm e%3 t
e l
1
Unit 2 7.500 LMERGliiCY PROCEDURES ItiOEX O
fiuMBER.
Titte aev.
0A1e ISSUE 0 501/2501 Emergency Plan Procedure CAtlCELLED - 7/15/81 Replaced by OP 501, OP 2501, ACP 1.15, 4000 Series OP'2501 Incident Assessment and Classification 1 9/24/81
-Unit 2 2502 Emergency Shutdcwo ("eactor Trip) 12 11/30/81 25'03 Electrical Emergency (Loss of !!ormal 7
9/3/81 Power) 2.504 Loss of Reactor Coolant Flow 6
10/23/81 2505 Primary System Leakage 3
10/17/78 2506
-Loss-of-Coolant Incident 10 8/13/81 2507 Loss of Condenser Vacuum 4
2/18/81 2508 Loss of Reactor Bldg. Closed Cooling 2
2/16/77 Water 2509 Steam Line Rupture 7
10/23/81-2510 Natural Occurrences 5
8/19/80 505/2511 Emergency Procedure Fire 6
-4/31/81 2512 Loss of Instrument Air 3
10/24/78 2513 Shutdown from Outside the Control 6
4/23/81 Room 2514 Emergency Boration 4
'10/23/81 2515 Steam Generator Tube Rupture 8
9/3/81' 2516 Steam Generator Chemistry 6
11/28/79 2517 Earthquake 2
6/30/77 2518 Loss of Service Water 2
7/31/78
-2519 Electrical Ecargency (Loss of Main 02 1/16/81 OC Bus)
O Rev. 72 11/19/81 Page 1 of 2
2500 OVERALL II;DEX 2520 Fuel llandling Accident Inside 2
4/1/81 c""' ia* "'
O-2521 Loss of feedwater/ Steam Generators 0
1/1/80' i
~
i O
1 l
l O
Rev. 72 11/19/81 Page 2 of 2
APPROVAL:
E. J. Mroczka LATE: 6-18-80 Station Superintendent STATION PROCEDURE COVER SHEET A.
IDENU FICATION Number SP 2502 Rev.
12 Title EMERGENCY SHUTDOWN (REACTOR TRIP)
Prepared By A. Weber B.
REVIEW I have reviewed the above procedure and have found it to be satisfactory.
TITLE SIGNATURE DATE A7,Nma
//I2/f/
DEPARTMENT HEAD C.
UNREVIEWED SAFETY QUESTION EVALUATION DOCUMENTATION REQUIRED:
(Significant' change in procedure method or scope es described in FSAR)
YES [ ]
NO R l
(Ifyes,documentinPORC/50RCmeetingminutes) l ENVIRONMENTAL IMPACT (Adverse environmental impact)
YES [ ]
NO M (If yes, document in PORC/SORC meeting minutes) l D.
PORC/SORC APPROVAL l
PORC/60RC-Neeting Number 2 7 2.
1 E.
APPROVAL AND IMPLEMENTATION l
The attached procedure is hereby approved, and effective on the dates below:
O
/IflE / h
//[M hl l
Station Superintendent /U Mt Superintendent Approved Date Effective Date i
SF-301 l
Rev. 3 M
l LJ
SP 2502 Page 1 Rev. 12 Date: 11/30/81 s,
EMERGENCY SHUTDOWN (REACTOR TRIP)
.i Page No.
Effective Revision Date l
1 12 11/30/81
>I 2
12 11/30/81
,l 3
12 11/30/81 i
4 12 11/30/81 5
12 11/30/81' 6
12 11/30/81 7
12 11/30/81 8
12 11/30/81 9
12 11/30/81 10 12 11/30/81 4,,
11 12 11/3a/81 12 12 11/30/81 13 12 11/30/81 f
b i
Y l
l t
SP 2502 Page 2 Rev. 12 Date: 11/30/81 1.
OBJECTIVE 1.1 To provide a procedure to bring the plant to a hot standby condition after an emergency shutdown has been initiated automatically or manually by operator action.
2.
DISCUSSION 2.1 Any shutdown of the plant accomplished by rapid insertion of the control elements (also called " Reactor Trip" or " Scram") is considered an emergency shutdown.
Emergency shutdown will be automatically initiated by the Reactor Protection System (RPS) whenever certain continuously monitored parameters surpass a predetermined setpoint.
Emergency shutdown can also be initiated manually by operator action if unstable plant conditions warrant such action.
The operator is alerted to unstable plant conditions by several "Pretrip" alarms.
Additional 11y, due to the fail safe nature of the RPS, a malfunction of the system can also cause an emergency shutdown.
A reactor trip occurring early in core life or after a prolonged plant shutdown leaves little decay heat to be removed.
This creates the possibility of overcooling the reactor coolant by the rapid insertion of feedwater (or addition of too much feedwater) to the steam generators following a reactor trip.
This cooling could result in a reduction of shutdown margin.
To help avoid this rapid over feed of water, the feedwater regulating valves to the steam generators wil.1 automatically ramp down to a 5% open position i
l and will then transfer to manual control.
I j
Auxiliary feed water may initiate after a reactor trip.
Low l
steam generator (either) water level will initiate the logic and pump start / valve opening will occur after a three-minute twenty-five second time delay.
If RCS cooldown is excessive, auto-auxiliary feed water should be reset when steam generator (both) water levels have returned above setpoint to allow throttling of feed water flow.
t w
i SP 2502 Page 3 Rev. 12 Date: 11/30/81 l
Whenever possible. key system parameterc should ha restored and
.u oiton.eu at..s...u i 1.u t a i
...u 3. one, i i.m., e.. s u. 4 n.
a pressure / level at 2250 PSIA /40%, 1C at 532 F., etc.) After an emergency shutdown, the reactor may not be restarted until all 1
l administrative requirements of ACP 1.07 have been met.
,1 3.
SYMPTOMS OF EMERGENCY SHUTDOWN q
NOTE:
All symptoms may not initially be present.
Any single or 1
multiple symptom which provides an indication of a reactor I
trip will require implementation of this procedure.
3.1 Major Symptoms i
3.1.1 Control element assembly (CEA) lower electrical 4
3 limit lights on as indicated on core matrix.
(C04) j 3.1.2 CEA position indication shows all CEA's on the
{
bottom as indicated by position step indicators and l
metrascope.
i 3.1.3 Reactor power indicators and recorders show rapid i
decrease in reactor power. (C00 i
v
(
3.1.4 "Reator Trip" annunciator alarm (red alarm light)
(C04).
3.1.5 Annunciator drops verifying reactor trip circuit breakers (TCB's) (8) have tripped.
(C04) 3.1.6 Green indicating lights illuminated for TCB's (8)
(C04).
3.2 Other Symptoms i
3.2.1 Any one or more of the following annunciator alarms (red alarm lights) on panel C04.
Approximate Trip Set Point 1.
Steam Generator Low Level 36.0%
2.
Steam Generator Low Pressure 500 PSIA 3.
Reactor Coolant Low Flow 4 Pump Operatiun 91.7%
4.
Pressurizer High Pressure 2400 PSIA v
j SP 2502 Page 4 Rev. 12 Date: 11/30/8 l
I 5.
Thermal Margin / Low Pressure Variable 6.
Nuclear Instrumentation High Power Q Power +
9.6%
7.
Turbine Trip, Low Hydraulic Fluid Pressure 500 PSIG i
8.
Local Power Density Refer to Limit 9.
Containnient Pressure High 4.75 PSIG 10.
Reactor Coolant Pump Underspeed 829 R.P.M.
3.2.2 The reactor has been manually tripped due to one of the following:
3.2.2.1 Tavg decreased below 515*F. for greater than 15 minutes, i
3.2.2.2 Either steam generator level increase above 90%.
3.2.2.3 Reactor startup rate exceeded 2.5 DPM.
y 3.2.2.4 Pressurizer level decreased below 20% after
'i a dropped CEA occurrence (OP 2391).
3.2.2.5 Total loss of instrument air (E.P. 2512).
4.
IMMEDIATE ACTIONS 4.1 Ensure the reactor has tripped by depressing the four (4) reactor trip pushbuttons (C04).
4.1.1 Verify reactor power is decreasing (C04).
l 4.1.2 Verify all CEA's are fully inserted (C04).
j 4.2 Ensure the turbine has tripped by depressing the turbine trip button on the EHC insert panel (C07).
4.2.1 Verify all steam admission valves indicated closed l
(C07).
1 4.2.2 Verify generator pegawatts indicate zero or negative (C07).
v 1
l L
m
SP 2502 Page 5 Rev. 12 Data: 11/30/81 4.3 Ensure the generator ACB's (15G-8T-2 and 15G-9T-2) are open by simultaneously depressing both emergency trip pushbuttons (C07).
4.4 Verify the transfer of 6.9KV and 4.16KV buses to the reserve station service transformer (RSST) (C08).
4.5 Ensure main feedwater flow decreasing (C05).
4.5.1 Verify the main feedwater regulating valves are ramping to the 5% open position (C05).
4.5.2 If the feed pumps are in manual speed control, ramp feed pump speed to minimum (C05).
4.5.3 If two feed pumps are running, trip one pump (C05).
CAUTION:
ENSURE THAT THE FEE 0 WATER FLOW RATE IS CONTROLLED 50 THAT THE PRESSURIZER LEVEL AND PRESSURIZER PRESSURE CONTROLLERS ARE ABLE TO MAINTAIN THOSE PARAMETERS WITHIN NORMAL LIMITS.
DO NOT ALLOW AN RCS C00LDOWN RATE IN EXCESS OF 100 F/ HOUR.
AVOID OVERFILLING THE STEAM GENERATORS TO v
. PREVENT POSSIBLE DAMAGE TO THE MAIN STEAM l
LINES, ATMOSPHERIC DUMP VALVES, MAIN STEAM ISOLATION VALVES OR THE STEMt DUMP VALVES.
4.6 If the main feed pumps have tripped and/or are not available, l
start the electric and/or steam driven auxiliary feed pumps (005).
NOTE:
The electric driven auxiliary feed pumps will automatically start and auxiliary feed ragulating 8
valves open fully if steam generator level falls below 12%.
Pump start / valve opening is delayed for 3 ll, l
minutes,*25 seconds after the initiating signal.
l, 4.6.1 Adjust feedwater flow to at least 300 GPM per steam ll generator (600 GPM if only one steam generator is l
available) to return steam generator water level to 70-80% (C05).
l NOTE:
If auxiliary feedwater was automatically l
lc-
i i
I SP 2502 Pag? 6 Rev. 12 Date: 11/30/31 initiated, maunual control of pumps and v
reg. valves can be obtained by positioning the aut aux-feed han,dswitches (2) to Reset (C05).
i 4.6.2 Whenever all feedwater flow has been lost for greater than 5 minutes, limit feedwater flow to 600 GPM if steam generator temperature is greater than 212 F.
and level is below the feedwater sparger (< 45%).
However, cooling of the core is to take precedence
{
over water hammer considerations.
Therefore, when considered nccessary feedwater flow shall be increased as required to ensure adequate core cooling.
4.7 Trip all operating heater drain pumps and open heater drain pump subcooling valve (2-HD106) (C05).
(
4.8 Trip all but one condensate pump (C05).
t l
l 5.
SUBSEQUENT ACTIONS y
i 5.1 Refer to OP 2501 " Incident Assessment and Classification" to determine the applicable incident classification and to determine which Emergency Plan Implementing Procedure (EPIP) is to be initiated.
- 5. ? Monitor Primary System Temperature 5.2.1 Verify that steam dump and bypass valves are i
functioning to reach and maintain a no-load TAVG of 532 F. (C04-C05).
S.2.2 If the main steam isolation valves have closed or the rain condensar is not available, use the l
atmospheric dump valves to maintain TAVG at 532 F.
l (Curresponds to 900 PSIA secondary pressure).
(C05) 5.3 Monitor steam generator water level and adjust flow to maintain level betweer. 70% and 80%. (C05) 5.3.1 Whenever all feedwater flow has been lost for greater i
than five (5) minutes, limit feedwater flow to 600 g
GPM if steam generator temperature is greater than
SP 2502 Page 7 Rev. 12 Date: 11/30/81 212'F. and level is below the feedwater sparger
( 45%).
However, cooling of the core is to take precedence over the above water hammer considerations.
Therefore, when considered necessary, feedwater flow shall be initiated up to
~
the maximum rate to ensure adequate core cooling even with the above conditions.
5.3.2 Monitor condensate tank level.
If low level is indicated, respond per the applicable sections of OP 2319B, Condensate Storage and Transfer. (C05).
4 5.2.3 If all feedwater is lost to both steam generators or if for any reason both steam generators become inoperable, refer to E0P 2521, Loss of Feedwater/ Steam Generators.
5.4 If using the auxiliary feed pumps to supply the steam generators, secure the normal hydrazine feed pumps, open valves 2MS-15A and 2MS-15B and then start the suxiliary chemical feed pumps.
CAUTION:
IF ALL CONDENSATE PUMPS MUST EE SECURED, REMOVE STEAM FROM THE TURBINE BUILDING PRIOR TO SECURING THE PUMPS BY CLOSING BOTH MAIN STEAM ISOLATION VALVES.
ENSURE STEAM DUMP VALVES ARE BEING USED TO CONTROL TAVG AND THEN BREAK CONDENSER VACUUM.
5.5 Monitor pressurizer level decreasing to reach the no load programmed level of 40% 15%.
Switch to manual control if necessary, and maintain level between 40% and 50%. (C02/3).
5.6 Use manual control of pressurizer sprays and heaters if l
necessary to return primary system pressure to normal (2250 PSIA) (CO2/3).
5.6.1 If pressurizer pressure control is lost, commence a cooldown per OP 2207, Plant Cooldown and attempt to maintain T 50*F. subcooled.
H 5.6.2 If saturation conditions are approached, (less than 20'F. subcooled - use Subcooled Margin Monitor or i
y Figure 6.2).
Observe reactor coolant pump parameters
r SP 2502 Page 8 Rev. 12 Date: 11/30/81 for indication of void formation. Void formation D
would be indicated by the following:
5.6.2.1 Pump current:
less than 400 amps 5.6.2.2 Steam Generator P: 10 psid (2 pumps) 20 psid (3 pumps) 5.6.2.3 RCS T:
greter than 5 F.
5.6.2.4 RCP Vibration alarms present. (C03).
5.6.3 If voiding is indicated and a low pressureizer pressure SIAS is not present, do not secure RCP's unless at least one of the following conditions exist:
5.6.3.1 One RCP per loop will continue to operatore (C03) or, 5.6.3.2 The RCP's are not providing forced flow as indicated by low steam generator P
( 3 psid), low RCP current ( 100 amps) and high reactor vessel % (T
-T 10 F) (C03)
H C
or, 5.6.3.3 RBCCW to the RCP's has been secured and cannot be restored and pump temperatures l
exceed alarm limts. (CO3) j
~
5.7 If the pressurizer power operated relief valves have lifted and primary pressure has decreased below 2350 psia, attempt to reset the acoustic PORV valve position monitor and monitor quench tank parameters and discharge pipe temperatures to verify the relief valves have reseated (C03/RC05E).
5.8 If the pressurizer power operated relief valves appear to be stuck open, close the affected PORV's isolation valve (2-RC-403 or 2-RC-405).
Maintain the stuck open PORV's isolation valve closed (2-RC-403 or 2-RC-405) (C03).
5.9 If steam generator safety valves had lifted, verify that they have. reseated. (CO3)
CUATION:
CERTAIN TWO RCP COMBINATIONS WILL RESULT IN l
INEFFECTIVE PRESSURIZER SPRAY CAPABILITIES AND POTENTIAL " HARDNESS" 0F PRESSURE RESPONSE.
TO ENSURE w
t SP 2502 Page 9 Rev. 12 Date: 11/30/81 EFFECTIVE SPRAY (AND MINIMIZE THE NEED FOR AUXILIARY SPRAY), ATTEMPT TO RUN A,B OR B,0 MIEN TWO PUMP OPERATION IS DESIRED / REQUIRED.
IF ONE OF THESE TWO l
PUMP COMBINATIONS CANNOT BE MAINTAINED, MINIMIZE RCS l
TEMPERATURE AND PRESSURIZER LEVEL CHANGES.
I INCREASING LEVEL WILL CAUSE A PRESSURE RESPONSE SIMILAR TO THAT RESULTING IN OPERATION WITH A"HARD" BUBBLE.
5.10 Unless a low pressurizer pressure safety injection initiation has occurred, ensure at least one reactor coolant pump (RCP) per loop is running.
5.11 Record all relay actions on rear of C08, open 15G-2X1-4, (visually verify stabs open) reset the relays, and then reclose 15G-8T-2 and 15G-9T-2. (C08) 5.12 Secure secondary plant equipment not necessary in maintaining a hot shutdown condition.
5.13 Verify main turbine motor suction pump running and manually start lift pumps and turning gear motor to ensure safe coast down of main turbine generator (C07).
NOTE:
Lift pumps and turning gear will auto start if Step 5.12 is omitted.
5.14 Determine cause of reactor trip and correct.
i 5.15.1 If cause of trip was low condenser vacuum, refer to Emergency Procedure 2507 " Loss of Condenser Vacuum."
5.15.2 If cause of trip was high containment pressure, refer to Emergency Procedure 2506 " Loss of Coolant Incident" or 2509 " Steam Line Rupture."
5.15.3 If cause of trip cannot be corrected without plant cooldown, initiate plant operating procedure 2205
" Plant Shutdown."
5.16 Fill out Station Form SF-1001 (Plant Incident Report) and notify higher supervision in accordance with ACP 1.07.
5.17 As soon as conditions permit, reset the turbine as follows:
l 5.17.1 Reset and close the reactor protective sy; tem switchgear breakers. (C04)
SP 2502 Page 10 Rev. 12 Date:
11/30/81 5.17.2 Reset the turbine and verify the intermediate stop valves (4) stroke to the full open position. (C07) 5.17.3 If the intermediate stop valves do not open, EHC pressure can be increased to provide additional force per the following:
5.17.3.1 Loosen the lock nut,on the pressure compensator at the pump.
5.17.3.2 Note original EHC pressure.
NOTE:
The pump discharge relief valves are set at approximately 2000 PSIG.
5.17.3.3 Turn the compensator clockwise until pressure equals 1900 PSIG.
5.17.3.4 After the valves open or if the extra pressure does not open the valves return the pressure to its original value.
5.17.4 After the intermediate stop valves open, the turbine may be tripped. (C07) 5.18 If condenser vacuum is'being maintained, monitor turbine steam seal header pressure and adjust as necessary to maintain 4 PSIG on the header. (C07) 5.19 Notify Chemistry to perform an isotopic analysis for Iodine within a 2 to 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> period from the time of the trip if I
1 reactor power was greater than 15% at the time of the trip.
5.20 Monitor wide range power instrumentation.
If the count rate for any channel decreases below.5 CPS and the channel is l
required to meet Technical Specification minimum channnel requirements, reconnect the B-10 detector by depressing the B-10 off pushbutton.
5.21 Monitor system voltage and if necessary, request CONVEX to adjustsystemvoltagetoensureadequateinhousevoltage.
(C08) 6.
FIGURES i
V
SP 2502 Pag 2 11 Rev. 12 Date: 11/30/31 6.1 Break Identification Chart
~
6.2 Saturation Curve AW/PC:sjr v
v 1
.. f
DREAK IDE!!TIflCATIO!! CilaRT SP 2502 Rev. 12*
Pag' e :12 e
Dat 11/30/01 8
e Per Level Changing and v
Pzr. Press. Rapidly Occreasing N
6
,e Steam Generator Pressure f
s l
Normal Abnormally Low In One'
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