ML032900444
| ML032900444 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/08/2003 |
| From: | Mcintyre B Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:3004-02 PMP-2080-EPP-100, Rev 2, PMP-2080-EPP-101, Rev 4, PMP-2080-EPP-107, Rev 18 | |
| Download: ML032900444 (156) | |
Text
Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 49107 1395 INDIANA MICHIGAN POWER October 8, 2003 AEP:NRC:3004-02 10 CFR 50.4(b)(5)(iii) 10 CFR 50, Appendix E.V Docket Nos:
50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P 1-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 1 and Unit 2 TRANSMITTAL OF EMERGENCY PLAN IMPLEMENTING PROCEDURES Pursuant to 10 CFR 50.4(b)(5)(iii), Indiana Michigan Power Company, the licensee for Donald C. Cook Nuclear Plant Unit 1 and Unit 2, is transmitting PMP-2080-EPP-100, Emergency Response, Revision 2, PMP-2080-EPP-101, Emergency Classification, Revision 4, and PMP-2080-EPP-107, Notification, Revision 18. A revision summary has been included for each of the procedures being transmitted.
This letter contains no new commitments.
Should you have any questions, please contact me at (269) 697-5806.
Sincerely, Lu Aw7 Brian A. McIntyre Manager of Regulatory Affairs DB/rdw
Attachment:
Donald C. Cook Nuclear Plant Emergency Plan Implementing Procedures
U. S. Nuclear Regulatory Commission AEP:NRC:3004-02 Page 2 c:
J. L. Caldwell, NRC Region III (2)
K. D. Curry - AEP Ft. Wayne, w/o attachment J. T. King, MPSC, w/o attachment MDEQ - WBMD/HWRPS, w/o attachment NRC Resident Inspector M. A. Shuaibi - NRC Washington DC
ATTACHMENT TO AEP:NRC:3004-02 DONALD C. COOK NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES PMP-2080-EPP-100, Revision 2 PMP-2080-EPP-101, Revision 4 PMP-2080-EPP-107, Revision 18
REVISION
SUMMARY
Number.
Title:
PMP-2080-EPP-100 Revision:
2 Change:
0 Emergency Response Section or Step Change/Reason For Change
3.2.3 Change
Add Note IF accountability and /or evacuation is (are) required at classifications other than a Site Area Emergency or General Emergency, THEN Accountability is performed only ONE time for the event in progress.
Reason: Address personnel accountability and evacuation from site when Site Area Emergency or General Emergency do not exist.
3.2.4 Change
Add Note IF accountability and /or evacuation is (are) required at classifications other than a Site Area Emergency or General Emergency, THEN PA announcements may be made using the guidance in step 3.2.3. of PMP-2080-EPP-107, Notification.
The announcement may be modified as necessary to fit existing plant and ERO status.
Reason: CR 03099018 action 2 to address personnel accountability and evacuation from site when Site Area Emergency or General Emergency do not exist.
Step 3.2.6 Change: Add "or 1119" to the SAS phone extension parenthetical remark.
Reason: Identify alternate telephone extension available for use.
NOTE prior to Change: Add NOTE prior to step to caution the user not to change Step 3.2.7 Protective Action Recommendation such that protection is reduced for Areas previously addressed in previous PARs Reason: CRA03 178012-01; recommendation from OEIRIS to prevent modifying PARs for areas affected by previously-issued PARs.
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rw=U PMP-2080-EPP-100 Rev. 2 Page 1 of 21 Emergency Response Reference Effective Date: VII/61 D. A. Schroeder S. M. Partin Site Protective Services Writer Owner Cognizant Organization TABLE OF CONTENTS 1
PURPOSE AND SCOPE.
2 2
DEINITIONS AND ABBREVIATIONS..........................
2 3
DETAILS 3
9 5
REFERENCES 9 :
Data Sheet 1:
Data Sheet 2:
Figure 1:
PAR Flowchart and Map......................
10 Technical Information Sheet.......................
12 Emergency Turnover Checklist......................
14 P~rocedure Flo chart......................
18
Reference l
PMP-2080-EPP-100 l
Rev. 2 l
Page 2 of 21 Emergency Response 1
PURPOSE AND SCOPE 1.1 This procedure provides Instructions to the Shift Manager acting as the Site Emergency Coordinator (SEC), for implementing a response to an Unusual Event (UE), Alert, Site Area Emergency (SAE) and General Emergency (GE) after an emergency has been declared.
1.2 The steps in this procedure are listed in the preferred order of performance for maximum efficiency. However, the steps may be performed in a different sequence.
2 DEFINITIONS AND ABBREVIATIONS Term Meaning AOP Abnormal Operating Procedure BCSD Berrien County Sheriff Department DAP Dose Assessment Program EMD-32 Nuclear Plant Accident Notification form ENC Emergency News Center EOF Emergency Operations Facility EOP Emergency Operating Procedure ERDS Emergency Response Data System ERO Emergency Response Organization GE General Emergency JPIC Joint Public Information Center MSP Michigan State Police OSC Operations Support Center
SAE Site Area Emergency
Reference PMIP-2080-EPP-100 l
Rev. 2 Page 3 of 21 Emergency Response SAS Secondary Alarm Station SEC Site Emergency Coordinator SM Shift Manager TSC Technical Support Center UE Unusual Event NOTE:
All procedure steps are applicable to all Emergency Classification Levels EXCEPT when the applicable Emergency Classification Level(s) is(are) specified within a step. (Reference Figure 1, Procedure Flowchart.)
3 DETAILS 3.1 General 3.1.1 IF a classification upgrade is required at any time while the procedure is being performed or after it is completed, THEN return to step 3.2, Instructions, and proceed through the procedure again.
3.1.2 The Operations SM acting as the SEC shall implement this procedure until relieved of SEC duties.
3.1.3 The following actions shall not be delegated by the SEC:
Classification of the emergency.
Directing the notification of offsite officials.
Approval of PAR to offsite emergency management agencies.
3.1.4 Declaration of an emergency requires the notification of the BCSD and MSP within 15 minutes. Notification of the NRC shall follow county and state notification and in all cases be completed within one hour.
- C 1 I:
3.15 Declaration of a GE requires that a PAR be made to the state.
The PAR should be made immediately after the notification of a GE (i.e., during the same phone call).
Reference PMP-2080-EPP-100 Rev. 2 Page 4 of 21 Emergency Response 3.1.6 The ERDS for the affected Unit must be operational and transmitting data to the NRC within one hour of an ALERT or higher declaration.
3.1.7 The OSC, TSC, and the EOF are required to be activated at an ALERT classification or higher.
3.2 Instructions 3.2.1 Inform Unit 1 and Unit 2 Control Room personnel of the event classification and that the SM has assumed the position of SEC.
3.2.2 Implement or direct the implementation of PMP-2080-EPP-107, Notification.
NOTE:
IF accountability and/or evacuation is (are) required at classifications other than a Site Area Emergency or General Emergency, THEN accountability is performed only ONE time for the event in progress.
3.2.3 IF a SAE or GE has been declared, THEN notify the Security Shift Supervisor (x 2005 or 2731) to perform accountability.
- a.
WHEN evacuation is necessary, THEN inform the Security Shift Supervisor (x 2005 or 2731) to evacuate plant personnel.
- b.
WHEN evacuation of the beach is necessary, THEN direct an announcement to be made to evacuate the beach.
- c.
IF offsite agency personnel (e.g., National Guard, MSP, etc.) are stationed in the owner-controlled area, THEN determine if these personnel should be evacuated or if they will remain onsite.
Take appropriate action (e.g., evacuate, shelter, relocate onsite, issue dosimetry, etc.) as necessary to protect the offsite agency personnel.
... I.......
I-I...a,.-
Reference PMP-2080-EPP-100 Rev. 2 Page 5 of 21 Emergency Response NOTE:
IF accountability and/or evacuation is (are) required at classifications other than a Site Area Emergency or General Emergency, THEN PA announcements may be made using the guidance in Step 3.2.3 of PMP-2080-EPP-107, Notification. The announcement may be modified as necessary to fit existing plant and ERO status.
3.2.4 IF a hazard to plant personnel exists (e.g., fire, radiation or toxic gas), THEN perform one of the following steps:
- a. IF the condition is local, THEN evacuate the area by page announcement.
- b. IF the condition impacts significant portions of the plant, THEN direct the Security Shift Supervisor (x 2005 or 2731) to perform accountability in accordance with Security Post Orders and perform an evacuation.
NOTE:
The presence of an offsite dose rate may require re-classification of the event in accordance with ECC R-1, Effluent Release, PMP-2080-EPP-101, Emergency Classification.
3.2.5 IF a gaseous release of radioactive material is occurring, THEN initiate use of the DAP, to determine the magnitude of offsite dose levels. The following Emergency Plan procedures should be used as appropriate:
PMP-2080-EPP-108, Initial Dose Assessment (for use in the Control Room).
RMT-2080-EOF-001, Activation and Operation of the EOF (for use in the EOF).
3.2.6 IF additional personnel are required to respond to an Unusual Event to support the emergency response, THEN:
- ' ' '_ ,,, '-t',
:
-.,., 1,, .
- a.
Call the SAS (x1118 or 1119) and direct security to implement the Dialogic Emergency Response Notification System for an EMERGENCY.
I
.I
Reference
I PMP-2080-EPP-100 I
Rev. 2 I
Page 6 of 21 I efrnc PM-200EP1I Rv 2 I
Pg ofl
. I Emergency Response I
- b.
Direct a Control Room Operator to make the following announcement for the appropriate ERO facility(s) to be activated, over the PA system. Have the announcement broadcast twice.
"Attention all personnel. The Unusual Event is still in effect, however report to and activate the Operations Support Center/Technical Support Center/Emergency Operations Facility. All other plant personnel be prepared for further announcements."
- c.
On any touch-tone telephone:
a Dial 1646 Wait for the tone a
Repeat the above announcement twice NOTE:
DO NOT revise protective actions such that protection is reduced for areas already addressed in previously issued PARs. For example, if evacuation was recommended for Area 1 in a previous PAR, do not revise this recommendation to shelteing in Area 1 in any subsequent PAR.
3.2.7 IF a GE has been declared, THEN direct the development of a Protective Action Recommendation using the following steps:
- a.
Prior to developing a PAR consider whether the following could have an effect on the PAR:
Adverse weather conditions.
A forecast of changing weather conditions.
Release characteristics (Puff vs. Continuous).
Evacuation times.
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Reference PMP-2080-EPP-100 l
Rev. 2
-Page 7 of 21 Emergency Response
- b.
Obtain the following data:,
Wind direction
-AND-Offsite dose projection (if available) as calculated using DAP or actual offsite dose rate measurements.
- c.
Using Attachment 1, PAR Flowchart and Map, determine the appropriate PAR.
- d.
Include any deviations from the PAR flowchart, 1, based on step 3.2.7.a in the protective action recommendation that is provided to the state.
Attachment
- e.
Enter the PAR on the EMD-32 form, Nuclear Plant Accident Notification, obtained from the Emergency Kit and notify the State of Michigan of the recommendation within 15 minutes, in accordance with PMP-2080-EPP-107, Notification.
- f.
Repeat Steps 3.2.7.a through 3.2.7.e every 30 minutes or within 15 minutes of a PAR change until relieved by the incoming ERO.
3.2.8 Perform mitigating actions in accordance with appropriate plant procedures.
3.2.9 IF the PPC is inoperable, THEN:
Designate someone to complete Data Sheet 1, Technical Information Sheet, every 15 minutes.
Forward the completed copy to the TSC.
Continue this activity for the duration of the emergency or until the PPC is operable.
X -3.2.0 IF accountability results identify a missing person(s) AND the TSC and OSC are NOT activated, THEN have Security attempt to locate the missing person(s).
I Reference l
PM P-2080-EPP-100 A
Rev. 2 -
l I
Page 8 of 21 I
Emergency Response l
3.2.11 Determine if special directions to the Security Staff are required (e.g., security event, radiation release, etc.) in order to control incoming ERO and/or non-ERO plant staff.
Provide directions as necessary to control incoming personnel.
3.2.12 Upon arrival of the oncoming SEC conduct a turnover as follows:
- a.
Obtain a copy of Data Sheet 2, Emergency Turnover Checklist.
- b.
Have the oncoming SEC complete the checklist as each item is verbally addressed.
3.3 Subsequent Instructions for the SM After Being Relieved of SEC Duties 3.3.1 WHEN relieved of SEC responsibilities, THEN resume the sole function of SM.
Notify the Control Rooms that the SM has been relieved of SEC responsibilities.
3.3.2 Direct the continued implementation of the appropriate Emergency Operating Procedure (EOP) and/or Abnormal Operating Procedure (AOP) to return the unit to a safe condition.
3.3.3 Inform the TSC of changes in plant condition and equipment status.
3.3.4 Inform the TSC of mitigating actions to be taken or any that have been completed.
3.3.5 Direct plant announcements and sounding of the Nuclear Emergency Alarm, if required, for any change in classification made by the TSC or EOF.
3.3.6 IF additional personnel are required, THEN request assistance from the TSC.
'.' :3.37 Assemble all documentation associated with the emergency and forward it to the Emergency Planning Coordinator. This documentation should include:
[
Reference PMP-2080-EPP-100
- Rev. 2 Emergency Response s
.=
s
'Page 9 of 2 Complete notification forms Copies of pertinent log entries Copy of the Condition Report if generated Other documentation deemed appropriate by the Shift Manager 4
4.1 FINAL CONDITIONS The emergency has been terminated and the plant has entered the recovery phase.
5 REFERENCES 5.1 Use
References:
5.1.1 PMP-2080-EPP-101, Emergency Classification 5.1.2 PMP-2080-EPP-107, Notification 5.1.3 PMP-2080-EPP-108, Initial Dose Assessment 5.1.4 RMT-2080-EOF-001, Activation and Operation of the EOF.
5.2 Writing
References:
5.2.1 Source
References:
- a.
Cook Nuclear Plant Emergency Plan 5.2.2 General References
- a.
Michigan Emergency Preparedness Plan
- b. NRC Regulatory Issue Summary, RIS-2002-21
" 7
Reference PMP-2080-EPP.100 Rev. 2 Page 10 of 21 Emergency Response AttchmebtJ.
PAR Flowchart and Map Pages
~~~~~~~~~~~~~~~~~~10
-11 Evaluate A6CUsI
'o otential
-3ffsite Dosf R e 348.75 11.25 33.75 56.25
,/Projected or Actual Dose at Site Boundary >I
- rem TEDE or >5 rem Thyroid CDE 7
3.75 I
101.25 25 '
Evaluate beyond 10 mile radius to determine extent of area with dose rates I rem TEDE or 2 5 rem Thyroid CDE 236.25 No No 146.25 168.75 191.25 Yes Default PAR Sectors Areas A, B & C to miles I and 2 B,C & Dto5miles 1,2and3 C,D&Eto5miles 1,2and3 DE, &Fto S miles I, 2 and 3 E,F&Gto5miles 1,2and3 F,G&Hto5 miles 1 and3 G,H&Jto5miles land3 H, &Kto5miles Iand3 J, K & L to 5 miles I and 3 K. L & M to 5 miles I and 3 L, M& NtoS miles I
M,N&Pto5miles I
N, P & Q to miles 1
P, Q& R to 5 miles I
QR&Ato5miles I i RA&Bto 5miles I and 2 Deermine affected aras as follows:
A.
Direction wind is blowing from (in Degrees)
B.
Using diagram above, locate sector opposite direction identified In A C.
Downwind sectors (sector identified In B plus 2 adjacent sectors)
D.
Convert downwind sectors to areas using the Sectors to Areas table.
E. PAR is: Eveauate areas (from D)
Reference PMP-2080-EPP-100 Rev. 2 Page 11 of 21 Emergency Response Pages:
Attachmnent PAR Flowcha rt and Map 1
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-Reference PMP2O80-EPP-100 Rev. 2 l
Page 12 of 21 Emergency Response lData Sheet Technical Information Sheet Pages:
12 - 13 Unit No:
5
' fDate::
Time:
Data Taken By:
Data Reviewed By:
- NOTE:
~.. 1 When redundant indication exists, record most severe condition.
I
. 72.~'
- 3..
4.S Containment Temp.
Cont, H2 Concentration RWST-Level Source Range
-OF CPM
- 5.
Intermediate Range AMPS
- 6.
Containment Pressure PSIG
- 7.
Containment Sump Level
- 8.
Containment Level
- 9.
Containment High Range Radiation Level Upper/Lower R/HR 9.
10..
'.11.
-12.
13.
14.
15.
ICTS Pnips I-RHR Spray Flow SI Flow BIT Flow Accum Pressure
- RHR Injection Flow RCP Status East ON / OFF East GPM North GPM LP1 GPM LP1 PSIG East GPM LP1 ON / OFF LP2 GPM LP2 PSIG LP2 ON / OFF West ON / OFF West GPM South GPM LP3 GPM LP3 PSIG West _
GPM LP3 ON / OFF LP4 GPM LP4 PSIG LP4 ON / OFF 16.
17.
18.
19.
20.
.21.
RCS Pressure Charging Flow PZR Liquid Temp.
PZR Steam Temp.
PZR Level PRT Temp.,
PSIG GPM
°F OF
°OF 22.
23.
24.
25.
26.
27.
PRT Level PRT Pressure PZR Cycling Htrs PZR Backup Htrs Letdown Flow Saturation Margin PSIG ON / OFF ON / OFF
________GPM OF
Reference.
I PMP-2080-EPP-100 I
Rev. 2 1
Page 13 of 21 Emergency Response Data Sheet 1 Technical Information Sheet Pages NSSS LOOP PARAMETERS Loop 1 Loop 2 Loop 3 Loop 4 28.
29.
30.
31.
32.
33.
1 34.
35.
36.
1i 37.
1 38.
Wide Range T Hot Wide Range T Cold S / G Pressure S / G N. R. Level S / G W.R. Level Steam Flow (pph x 106)
Feed Flow (pph x 106)
Aux. Feed Flow (pph x 103)
MSIV Status CST Level Steam Dump OF OF PSIG OPEN / CLOSE ATMOS / COND
°F
°F PSIG OPEN / CLOSE Ft OF OF PSIG OPEN / CLOSE OF OF PSIG OPEN / CLOSE EQUIPMENT STATUS 39.
40.
41.
42.
43.
44.
45.
46.
47.
48 East ESW West ESW East CCW West CCW East CTS West CTS North SI South SI East RHR West RHR AVAILABLE / UNAVAILABLE I
I
=_____
I
=_____
49.
50.
51.
52.
53.
54.
55.
56.
57.
East CCP West CCP TDAFP EMDAFP WMDAFP AB Diesel CD Diesel Normal Res.
12 EP AVAILABLE / UNAVAILABLE
~
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=_____
I
=_____
/
Reference PMP-2080-EPP-100 Rev. 2 - r Page 14 of 21 Emergency Response Data Sheet 2 1Pages Emergency Turnover, Checklist14-7
- 1.
Emergency Classification Time Declared Unusual Event Alert Site Area Emergency General Emergency
- 2.
Have notifications been completed?
- a. Berrien County:
yes / no / in progress
- b. Michigan:
yes / no I in progress
- c. NRC:
yes no / in progress
- d. NGG Personnel:
yes / no / in progress
- 3.
Protective Actions:
- a. Local area evacuation yes / no
- b. Site evacuation yes I no
- c. Accountability yes I no
- d. Site closed to visitors yes I no
- e. Offsite protective action recommended:
- Evacuation:
yes no areas:
Shelter:
yes i-no areas:
Time:
Time:
Time:
Time:
Time:
Time:
Time:
Time:
Time:
Time:
I_ I
Reference PMP-208WEPP-100 Rev. 2 Page 15 of 21 Emergency Response Data Sheet 2 l
Emergency Turnover Checklist ge
- 4.
Plant Operational Status
- a. Reactor trip: yes I no time:
Trip signal:
- b. ESF Status:
- c. EOP Status:
- r
- 5.
Plant Status
- a. Chronology of Events Time Event
.. Current Plant Conditions
- b. Current Plant Conditions I ,
I...
. 6..
Reference PMP-2080-EPP-100 Rev. 2 Page 16 of 21 Emergency Response Pages:
Data Sheet 2 Emergency Turnover Checklist14-7
- c. Potential for Plant Degradation
- d. Mitigating Actions Taken or Underway
- 6.
Plant Radiological Conditions
- a. Inplant/Onsite Radiological Conditions 7
.1 -1.-.
.. . i.:
- :,.
Reference PMP-2080-EPP-100 Rev. 2 l
Page 17 of 21 Emergency Response Pages:
Data Sheet 2 Emergency Turnover Checklist14-7 X X V
. - L~~~~~~~~14 1
- b. Potential for Offsite Release of Radioactivity
____ Airborne Water
- 7.
Injured or Contaminated Personnel:
Name Employer Status 1.
... -.1 7 :
i
. I. .
Reference PMP-2080-EPP-100 Rev. 2 Page 18 of 21 Emergency Response Figure 1 Procedure Flowchart gs 18 -21 Emergency delcared Per PMP-2080-EPP-101 Notify Unit 1 and 2 Control Rooms of event classification 3.2.3 3.2.3.a 3.2.3.b Yes Yes No NNO I
.I I
Reference PMP-2080-EPP-100
_'Rev. 2 Page 19 of 21 Emergency Response Figure 1 Procedure Flowchart Pages2 18 -21 NV 11 : A. -
- I ? -.W.
1.
Reference PMP-2080-EPP-100
Rev. 2 Page 20 of 21 Emergency Response Figure 1 Procedure Flowchart Pages:
I
~~~~~~~~~~~~~18-2
Reference PMP-2080-EPP-100 Rev. 2 Page 21 of 21 Emergency Response Figure 1 Procedure Flowchart W
3.3.3 and 3.3.4 Inform TSC of plant changes and mitigating actions planned or completed 3.3.5 Direct announcements as necessary for upgrades 3.3.6 equest assistance from TSC as t
~necessary I...
.~
~
I I
REVISION
SUMMARY
Number:
Title:
PMP-2080-EPP-101 Revision:
4 Change:
0 Emergency Classification X
Section or Step Change/Reason For Change Section 2 Change: Added new fuel vault and N-train battery rooms/chargers to list of vital areas. Added additional description of 4kVswitchgear room (D/G 4kV switchgear rooms) CR-02268025.
Reason: Bring definition of vital area in line with the Security definition.
Step 3.1.1 Change: New step to describe actions needed if EAL has been exceeded for >15 minutes.
Reason: To inform the user what to do in this situation, i.e., classify the event if the condition still exists, or do NOT classify but still make NRC notification. This is per the guidance of NUREG-1022 and PMP-7030-001-001, Prompt Notification. pg.
Change: Rephrased "2X rad monitor high alarm setpoint" to "Rad 15 and 20 R-1 UE monitor 2X high alarm setpoint."
Reason: Clarification; ease of reading., pg.
Change: Added "RCS Integrity CSFST" to EAL 2.4, Potential Loss 10 and 11 column; added "Heat Sink CSFST" to EAL 2.5, Potential Loss column; added "Containment CSDST" to EAL 3.4, Potential Loss column.
Reason: For clarity and human factors; provides detail on which RED path is affected on CSFST.
Attachment I Change: Added Loss of Alarms to list of ECCs.
Reason: Corrected omission.
Change: Added a reference to NRC commitment #7991 to EAL basis for fuel clad barrier 1.3, Primary Coolant Activity.
Reason: Comply with format.
Change: Replaced the reference to the hot shutdown panel with 'outside the control room' in the note at the end of the basis for EAL H-3, Control Room Evacuation, for SAE. CR 03048023.
Reason: Ability to shut down from more than one location.
Change: Deleted reference to commitment 5572 in ECC H-5 basis for UE and Alert.
Reason: Commitment is closed.
-~~~~~~~0 fw T a' W~~y 'c Office Inf
,'afon
< P ForFo m.ackii O ly-otP srt f or This is a fiee-form as called out in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. IOa.
Page o0 offa
.-, -- i
REVISION
SUMMARY
Number:
Title:
PMP-2080-EPP-101 1Fmprorpnev Claqiflation Revision:
4 Change:
0 Section or Step Change/Reason For Change,
Change: Replaced the reference to a specific event termination procedure Termination/Reco with a general description of the event termination procedure in very Criteria for the basis for N-1 through N-7 UE and Alert. CR 02284029 N-l to N-7 UE and Reason: Reduce the number of future procedure changes due to number Alert
~~~changes.
[
hs is a free-form as called out in PMP-20 I O-PRC-002, Procedure Correction, I
Change,'and'Review; Rev. 1a.
Page3 of
=WIR PMP-2080.EPP.101 Rev. 4 Page 1 of 112 Emergency Classification Reference Effective Date: TA £/O3 C. J. Graffenius S. M. Partin Site Protective Services Writer Owner Cognizant Organization TABLE OF CONTENTS 1
PURPOSE AND SCOPE.........................................
2 2
DEFINITIONS AND ABBREVIATIONS........................................
2 3
DETAILS.........................................
6 4
FINAL CO NDITIONS.........................................
7 5
REFERENCES.........................................
7 : : :
Emergency C6ndition Categories...........................................
9 Critical NUREG 0737 Parameters..........................................
22 Basis For Emergency Action Levels (Commitment: 6489)................. 23 7.,
.I
- :1..
I
Reference PMP-2080.EPP.101 Rev. 4 Page 2 of 112 Emergency Classification 1
PURPOSE AND SCOPE NOTE:
The operator aids located in the control rooms, simulator, Technical Support Center and Emergency Operations Facility are updated when changes are made to this procedure.
1.1 To ensure correct and timely classification of abnormal events into one of four emergency classification levels if appropriate. Attachments may be used as operator aids in a format different than the procedure provided the content remains the same.
2 DEFINITIONS AND ABBREVIATIONS Term Meaning Alert Events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.
Control Placing all local controls in position necessary for operation from remote panels and the shift supervisor has determined that the systems for controlling reactivity, RCS inventory, RCS temperature, and the heat sink functions have been established.
Critical Safety Subcriticality, core cooling, heat sink, pressure-temperature-Function (CSF) stress (RCS integrity), containment, and RCS inventory as monitored in accordance with the Emergency Operating Procedures.
Critical Safety The method by which the level of challenge to each CSF is Function Status determined in accordance with the Emergency Operating Tree (CSFST)
Procedures.
Emergency Action A pre-determined, site-specific, observable threshold for a Level (EAL) plant Initiating Condition that places the plant in a given emergency class. An EAL can be an instrument reading; an equipment status indicator, a measurable parameter (onsite or offsite); a discrete, observable event; results of analyses; entry into specific emergency operating procedures; or another phenomenon which, if it occurs, indicates entry into a particular emergency class.
Emergency A grouping of Initiation Conditions, recognizable to the Site Condition Category Emergency Coordinator, applying to the same area of (ECC) concern and that can logically lead to escalating the
__ emergency class.
Emergency These are taken from 10 CFR 50- Appendix E. They are in
Reference I
PMP-2080.EPP.101
-l Rev. 4 Page 3 of 112 I
Emergency Classification Term Meaning Classification Level escalating order. (Notification of) Unusual Event (UE),
(ECL)
Alert, Site Area Emergency (SAE), and General Emergency (GE).
Explosion A rapid, violent, uncontained combustion or catastrophic failure of pressurized equipment that potentially imparts significant energy to nearby structures or equipment.
Fission Product One of the three principal barriers to uncontrolled release of Barrier radionuclides, i.e., fuel clad, reactor coolant system (RCS),
and the containment building (CNTMT).
General Emergency Events are in progress or have occurred which involve actual (GE) or imminent substantial core degradation or melting with potential for loss of containment integrity. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.
Initiating Condition One of a predetermined subset of nuclear power plant (IC) conditions where either the potential exists for a radiological emergency, or such an emergency has occurred.
Loss (of a fission Severe challenge to a fission product barrier sufficient to product barrier) consider that barrier incapable of containing fission products.
Normal Charging The normal charging flow path through the volume control Mode system including design and alternate flow paths, and flow to reactor coolant pump seals.
Potential Loss (of a Challenge to a fission product barrier sufficient to consider fission product the barrier degraded in its ability to contain fission products.
barrier)
Protected Area The fenced area which requires a Cook security badge for unescorted access.
Recognition Alogical and convenient grouping of ECCs used to quickly Category eliminate non-applicable ICs from consideration during Emergency Classification.
Safe Shutdown Area Selected areas within the Protected Area that may be occupied for the security or safe shutdown of the units.
The safe shutdown areas are:
Control rooms Central alarm station Containment buildings in Modes 5 and 6 The following are Safe Shutdown areas, if a Control Room must be evacuated:
Diesel Generator rooms 4 kV rooms Vicinity of all Local Shutdown Stations
Reference PMP-2080.EPP.101 Rev. 4 Page 4 of 112 Emergency Classification Term Meaning 4
Safe Shutdown Equipment Selected components deemed necessary to place and maintain a unit in Hot Shutdown with capability to establish and maintain Cold Shutdown as described in Safe-Shutdown Capability Assessment, Proposed Modifications and Evaluations (AEPSC), Rev. 1 1986. In brief, the safe shutdown equipment can be described as:
RCS makeup path from the Refueling Water Storage Tank (RWST) via the Centrifugal Charging Pumps (CCPs) and Boron Injection Tank (BIT) injection lines.
Secondary Heat Sink consisting of:
Condensate Storage Tank (CST) all three Auxiliary Feed Water (AFW) pumps Associated AFW valves Steam Generators (SGs)
SG Main Steam Isolation Valves (MSIVs)
Component Cooling Water (CCW) system.
Essential Service Water (ESW) system including alternate supply to AFW.
Residual Heat Removal (RHR) system.
Diesel Generators and the emergency AC buses.
CRIDs and most CRID-powered instrumentation.
DC distribution system including batteries and battery chargers.
- All Local Shutdown Stations.
Site Area Events are in progress or have occurred which involve actual Emergency (SAE) or likely major failures of plant functions needed for protection of the public. Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels except near the site boundary.
Toxic Exposure to the worker in excess of limits specified in 29 CFR 1910.1000. in practice, this should be considered-for
.________________.concentrations which are capable of incapacitating the worker.
Transient A condition (1) beyond the expected steady-state fluctuations in temperature, pressure, power level, or water level, (2) beyond the normal manipulations of the Control Room operating crew, and (3) that would be expected to require actuation of fast-acting automatic control or protection system to bring the reactor to a new safe, steady-state condition.
o,.
Reference PMP-2080.EPP.101 l
Rev. 4 l
Page 5 of 112l Emergency Classification Term Meaning Uncontrolled A change that is not the result of a planned evolution.
Unisolable A leak that cannot be isolated from the control room.
Unplanned Any activity is unplanned if it is not being performed in accordance with the plan of the day, the outage schedule, the preventative maintenance schedule, a job order, or an approved procedure. In addition, the activity can be considered "unplanned" if resultant conditions exceed expected or authorized limits (e.g., a planned waste gas release should be considered unplanned" if release conditions do not conform to values specified in the discharge
_ _ _ permit).
Unusual Event (UE)
Unusual events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety system occurs.
Valid Readings are assumed valid unless circumstances cause the reading to be suspect. Verification can be obtained by a) an instrument channel check, or b) indications on related or redundant indicators, or c) by direct observation by plant personnel. Implicit in this definition is the need for timely assessment, i.e., within 15 minutes.
Vital Area Selected areas within the Protected Area that contain equipment necessary for the security or safe shutdown of the units. The vital areas are:
- Control rooms Control room and auxiliary cable vaults
- , Containment buildings Diesel Generator rooms Auxiliary feedwater pump rooms Essential service water pump rooms and switchgear Spent fuel pool area and new fuel vault 4 kV switchgear rooms (D/G 4kV switchgear rooms)
UPS battery and inverter rooms Central alarm station N-Train battery rooms and N-Train battery chargers I
. I-7, I;,.
D I
, I, I ~
Reference PMP-2080.EPP.101 Rev. 4 Page 6 of 112 Emergency Classification 3
DETAILS 3.1 Using Attachment 1, determine which Recognition Category applies to the abnormal conditions.
NOTE:
It is likely that an event will have to be classified using more than one Recognition Category.
3.1.1 Classify the event within 15 minutes of when the classification criteria (EAL threshold value) exists.
- a. IF the classification criteria is NOT recognized within 15 minutes AND the condition still exists, THEN classify the event.
- b. IF the classification criteria is NOT recognized with 15 minutes AND the condition no longer exists, THEN do NOT classify the event.
Make notifications in accordance with PMP-7030001-001, Prompt NRC Notification.
3.1.2 Review ALL appropriate Initiating Conditions within the selected Recognition Categories starting in the left-most applicable column.
3.1.3 Determine whether the threshold values for Emergency Classification have been exceeded.
- a. may be needed in making a determination of emergency classification under ECC S-6: Loss of Alarms or Indications.
- b. The appropriate basis pages (Attachment 3) may also be used if clarification is needed in making proper determination of emergency classification in any of the Recognition Categories.
I 3.1.4 The Initiating Conditions in Attachment 1 that are marked with an I do NOT have the entire EAL description listed in Attachment 1. In order to properly classify an event, the basis pages in Attachment 3 must be reviewed to insure the full description of the EAL is considered when making the classification. The page numbers listed in the Initiating
. ~ ^
fCondition boxes in Attachment I refer to the appropriate section of the basis pages, Attachment 3.
Reference l
PMP-2080.EPP.101 l
Rev. 4 l
Page 7 of 112 Emergency Classification 3.1.5 If the threshold value has been. exceeded, the higher Emergency Classification Levels within the associated ECC must be checked to ensure the highest ECL has been determined.
3.2 The Emergency Classification Level is the highest ECL determined in step 3.1 as appropriate - OR - any higher Emergency Classification Level as determined by Site Emergency Coordinator (SEC) judgement as described in Attachment 1 and.
3.3 The SEC shall evaluate plant conditions at least every 15 minutes to determine if conditions have deteriorated to the point that the Emergency Classification Level should be upgraded to a higher level until the event is terminated. The need to upgrade to a higher level could be indicated by:
0 S
Critical Safety Function Status Trees Additional radiation monitor alarms a
Reports from plant personnel 4
FINAL CONDITIONS 4.1 Event Classified 5
REFERENCES 5.1 Use
References:
5.1.1 None 5.2 Writing
References:
5.2.1 Source
References:
- a.
NUMARC/NESP-007, Rev. 2, Emergency Action Levels"
- b.
NUMARC/NESP-007, Rev. 4, Emergency Action Levels" "Methodology for Development of "Methodology for Development of
- c.
Regulatory Analysis: "Revision of Regulatory Guide 1.101 to Accept the Guidance in NUMARC/NESP-007, Rev. 2 as an Alternative Methodology for the Development of Emergency Action Levels"
Reference PMP-2080.EPP.101
. I Rev. 4 - I Page 8 of 112 Emergency Classification
- d.
NUMARC letter: "Methodology for the Development of Emergency Action Levels," NUMARC/NESP-007, Revision 2, Questions and Answers, June 1993 from Thomas E. Tipton, to NUMARC Administrative Points of Contact 5.2.2 General References
- a.
Donald C. Cook Nuclear Plant Emergency Plan
Reference PMP-2080.EPP. 101 Rev. 4 Page 9 of 112 Emergency CLASSWICATION l
Emergency Condition Categories Pages:
9 - 21 Page 10 10 11 12 13 13 13 13 14 14 14 14 14 14 14 15 15 15 16 16 16 16 17 17 17 17 17 18 19 20 21 21 21 20 20 Emergency Condition Category Fuel Clad Barrier Loss/Potential Loss Table RCS Barrier Loss/Potential Loss Table Containment Barrier Loss/Potential Loss Table ECC H-1 ECC H-2 ECC H-3 ECC H4 ECC H-5 ECC N-1 ECC N-2 ECC N-3 ECC N-4 ECC N-5 ECC N-6 ECC N-7 ECC R-1 ECC R-2 ECC R-3 ECC S-1 ECC S-2 ECC S-3 ECC S-5 ECC S-6 ECC S-7 ECC S-8 ECC S-9 ECC S-10 ECC H H-5 ECC N N-7 ECC R R-3 ECC C-3 ECC C4 ECC C-5 ECC C-6 ECC C-7 SEC Judgement Security Events Control Room Evacuation Fire Toxic or Flammable Gases Seismic Activity Tornado/High Wind Visible Structural Damage Vehicle Collision Main'Turbine Rotating Component Failure Plant Flooding Unanticipated Explosion Radioactive Effluent Release Increasing In-Plant Radiation Level Loss of Water Level in Any Area Holding Irradiated Fuel Failure of Reactor Protection System Loss of AC Power (Modes 1-4)
Loss of DC Power (Modes 1-4)
Loss of Systems Needed to Achieve/Maintain Hot Shutdown Loss of Alarms Fuel Clad Degradation Excessive RCS Leakage Tech Spec Compliance Loss of Communication Systems (Modes 1-4)
Hazards and Other Conditions (Modes 5, 6)
Natural/Destructive Phenomena (Modes 5, 6)
Abnormal Radiation Levels/Effluents (Modes 5, 6)
Cold ShutdownlRefueling/Defueled - Loss of AC Power (Modes 5, 6)
Cold Shutdown/Refueling - Inability toMaintain Cold Shutdown Cold Shutdown/Refueling - Fuel Clad Degradation (Modes 5, 6)
Cold Shutdown/Refueling - Loss of Communications (Modes 5, 6)
Cold Shutdown/Refueling - Loss of DC Power (Modes 5, 6)
I
11 j Reference I
PMP-2080.EPP.101 I Rev. 4 l Page 10 of 112 Emergency CLASSIFICATION Pages:
Emergency Condition Categories 9age21 I I FISSION PRODUCT BARRIER MATRIX - Mode 1-4 GENERAL EMERGENCY SIE AREA EMERGENCY ALERT UNUSUAL EVENT Loss of TWO Fission Product Any TWO of the Following:
Loss or Potential Loss of Either Fuel Loss or Potential Loss of Containment Barriers AND Potential Loss I1. Loss or Potential Loss of Fuel Clad.
Clad or RCS Barrier.
Barrier.
of Third Barrier.
- 2.
Loss or Potential Loss of RCS-.
- 3.
Loss of Contaimnent Barrier.
- 1. FUEL CLAD BARRIER LOSS(L)
POTENTIAL LOSS (P)
.1 Core Cooling CSFST Core Cooling CSFST - RED Core Exit Thermocouples > 72' OR RVLIS Level < 46% (Narrow Range)
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ H e a t S in k C S F S T - R E D
.2 Containment Radiadon
> 200 R/hr.
None
.3 Primary Coolant Activity
>300 uCi/cc 1-131 dose equivalent None OR Core Damage > 5.0% clad failure V
- 2. RCS BARRIER LOSS (L)
POTENTIAL LOSS (P)
.1 RCS Leak Rat (unisolable)
> available makeup capacity as indicated by complete
> capacity of one centrifugal charging pump in normal charging loss of RCS subcooling.
line up.
.2 Steam Generator Leakage Entry into OHP 4023.E-3, SGTR Ruptured SG with leak > capacity of one charging pump in AND normal charging line up.
Non-isolable secondary-line break results in a Prolonged (> 30 minutes) radioactive release to the environment from the affected SO.'
.3 Containment Radiation
> 10 R/hr None
.4 RCS Integrity CSFST None RCS Integrity CSFST - RED
.5 Heat Sink CSFST None Heat Sink CSFST - RED
'Does not include a release through the condenser air ejectors or the gland steam condenser vents for the purpose of declaration of a SITE AREA EMERGENCY.
l
FISSION PRODUCT BARRIER MATRIX - Mode 1-4 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Loss of TWO Fission Product Any TWO of the Following:
Loss or Potential Loss of Either Fuel Loss or Potential Loss of Containment Barriers AND Potential Loss
- 1. Loss or Potential Loss of Fuel Clad.
Clad or RCS Barrier.
Barrier.
of Third Barrier,
- 2.
Loss or Potential Loss of RCS.
- 3.
Loss of Containment Barrier.
- 3. CONTAINMENT BARRIER LOSS (L)
POTENTIAL LOSS (P)
.1 Containment Radiatidn None
> 1000 R/hr.
_Core damage > 20% clad failure.
.2 Containment Integrity Unisolable breach of containment.
None OR Rapid unexplained containment pressure or sump level drop following pressure rise caused by a LOCA.
OR Containment pressure/sump level NOT performing as expected for conditions.
OR Entry into ECA-1.2, LOCA Outside Containment.
.3 SG Secondary Side Release la. Primary to secondary leak rate > Tech. Spec. limit.
(p34)
None AND
- b. Secondary line break OUTSIDE Containment results in release
(>30 min.) to the environment.
- 2. Release of secondary coolant from the affected SG to the environment with alert alarm on any SG PORV rad monitor.'
E
.4 Containment CSFST None Containment CSFST - RED
.5 Containment Hydrogen None
>4.0%
Containment Hydrogen >.0.5%AND any Hydrogen Control equipment
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~inoperable.
.6 ContainmcnM Pressure Control None BOTH CTS trains OR BOTH containment air recirc fans inoperable OR fail to auto start on their containment pressure serpoint OR containment pressure
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~>
12 psig.
.7 Core Exit Thermocouples None Core Cooling CSFST - RED AND l___________________________________
Restoradon procedures not effective within 15 minutes.
'Does not include a release through the condenser air ejectors or the gland steam condenser vents for the purpose of declaration of a SITE AREA EMERGENCY.
I
Reference PMP-2080.EPP.101 Rev. 4 Page 12 of 112 Emergency CLASSIFICATION I
~~~~~~~~~~~~~Pages:
Attachment I Emergency Condition Categories 9
P 2
-~~~~~~~~~~~~~~~~~~~~~~~~~~
2 SEC Judgement: SEC Judgement may be used to determine that a Fission Product Barrier is LOST or POTENTIALLY LOST based on factors other tlian tbose listed in Attachment 1. Examples may include, but are not limited to, events such as loose parts in the core or loss of all ECCS pumps.
Once a barrier has been lost, the symptoms may disappear. SEC judgement may be used to determine whether to carry the barrier as lost. If the ability to monitor a barrier is lost or degraded, SEC judgement must be used to determine barrier status.
If escalation to Site Area Emergency or General Emergency is expected within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> based on current trends, then IMMINENT barrier degradation should be assumed and the SEC should make the appropriate classification.
GENERAL EMERGENCY I
SITE AREA EMERGENCY ALERT UNUSUAL EVENT SEC Judgement All Modes H-1 SEC Judgement (p.46)
H-1 SEC Judgement (p.45)
H-1 SEC Judgement (p.44)
H-1 SEC Judgement (p.42)
Conditions indicateactual or imminent substantial Conditions indicate likely or actual major failures Conditions indicate that plant safety systems may Conditions indicate a potential degradation of the core damage with potential loss of containment or of plant functions needed to protect the public.
be degraded and additional personnel are needed level of safety of the plant.
the potential exists for an uncontrolled radioactive for additional monitoring.
release that may exceed EPA limits at the site boundary..-.
i EAL.'s in these tables are NOT complete. Refer to referenced basis page (Attachment 3) for complete description.
Reference T--
PMP-2080.EPP.101 I Rev. 4-7Page 13 of 112 Emergency CLASSIFICATION.
I.
Pages:
Attachment I Emergency Condition Categories 9 - 21 INITIATING CONDITIONS - Mode 1-4 GENERAL EMERGENCY STE AREA EMERGENCY ALERT UNUSUALEVENT HAZARSAND OTHER CONDImONS H-I'Security (,50)
H-2 Security (p.49)
H-2 Security (p.48)
H-2 Security (p.47)
Securiy Event resulting in toss of abity Security event in a Vital Area.
Security Event in the Protected Area.
Security Event that potentially degrades level of to reach and maintain Mode I. I.Intrusion by hostile force.
I.Intrusion by hostile force.
plant safety.
OR OR I.Bomb in Protected Area/outside vital area.
I.Loss of physical control of Control Room 2.Loss of control of Vital Area 2.Civil disturbance within Protected Area.
OR OR, (NOT Control Room).
2.Credible bomb threat.
2.Ldss of physical control of remote SD capability.
OR OR 3.Confirmed bomb in Vital Area.
3.Credible attack threat.
OR 4.Hostage/extortion potentially affecting plant operations.
H-3 CR Evacuation (p.52)
H-3 CR Evacuation (p.51)
Control Room evacuated AND control not Control Room evacuation initiated.
established in 1 minutes.
H4 Fire (p.55)
Ho Fire (p.54)
Fire OR explosion affecting plant operations.
Fire n Protected Area NOT extinguished E w ithin 15 m inutes of detection.
H-5 Toxic Gas (p.58)
H-5 Toxic Gas (p.56)
Toxic OR flammable gas release that Toxic OR flammable gas release threatens lives OR affects ability to affecting plant operation.
ach eve~and~ maintain M ode_.
______________achieve and m aintain M ode 5.
I I. I w
I II r INITIATING CONDITIONS - Mode 1-4 GENERALE EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT NATURAL/DESTRUCTIVE PHENOMENA N-I Seismic (p.62)
N-1 Seismic (p.60)
Seismic event indicated by:
Seismic event indicated by:
I.Seismic instrument activated I.Seismic instrument activated OR OR 2.Ground motion detected by Control Room crew 2.Ground motion detected by Control Room crew.
AND I.Visble major damage in vital area.
OR 2.Plant Trip.
N-2 Tornado/wind (p.62)
N-2 Tornado/wind (p.60)
I.Tornado strike in Vital Area I.Tornado strike within Protected Area.
- 2. >90 mph wind for > 15 minutes.
N-3 Structural (p.62)
Visible damage to a structure containing systems required m achirequired to achieve and maintain Mode 5.
N4 Vehicle Collision (p.62)
N4 Vehicle Collision (p.60)
Vehicle collision affecting Vital Area.
Vehicle collision affecting systems or structures within the Protected Area.
N-5 MT Failure (p.62)
N-5 MT Failure(p.60)
Main turbine generated missile penetrates Vital Area.
Main turbine rotating component failure causes visible dam age or dam ages generator seals, N-6 Flooding (p.62)
Flooding in Vital Area affects safety related equipment.ffectssafetyrelated_________
N-7 Explosion (p.60)
Unanticipated explosion within Protected Area causes visible damage to permanent structures or equipm ent.
Reference PMP-2080.EPP.101 Rev. 4 Page 15 of 112 Emergency CLASSIFICATION Emergency Condition Categories Pages:
9 -21 INITIATING CONDITIONS - Mode 1-4
- -i GENERAL TEMERGENCY l
SITE AREA EMERGENCY ALERT UNUSUAL EVENT ADNO1MAi,. RADIATION LEVELS/EFFLUENTS R-1 Effluent release (p.70)
R-1 Effluent release (p.68)
R-1 Effluent release (p.66)
R-1 Effluent release (p.64)
Site boundary dose> I REM TEDE or S REM CDE Site boundary dose > 100 mrem TEDE Unplanned Rad release > 200X ODCM limits Unplanned Rad release > 2X ODCM limits for to thyroid based on:
or 500 mrem CDEto thyroid based on:
for > 15 min. based on:
> 60 minutes based on:
I.Survey results I.Survey results OR OR 1.200X rad monitor high alarm setpoint.
I.Rad monitor 2X high alarm setpoint.
2.Dose assessment 2.Dose assessment OR OR OR OR 2.Gas or liquid sample results.
2.Gas or liquid sample results.
3,Effluent monitor readings > 15 minutes 3.Effluent monitor readings > 15 minutes.
R-2 Plant Rad level (p.73)
R-2 Plant Rad level(p.72)
Rad levels that impede plant operations based Unexpected reading on Area Monitor 1000X on:
the 24 hr average.
- 1. > 15 mR/hr in Control Rm(s) /CAS OR
- 2. > 100 mR/hr at remote S/D areas.
R-3 Loss of level (p.77)
R-3 Loss of level (p.75)
Major damage to irradiated fuel or loss of Uncontrolled lowering in refueling cavity, SFP level that has or will uncover fuel outside of or Transfer Canal indicated by:
the reactor vessel based on:
I.Visual observation of levels.
1.1nability to maintain > 643'4" in SFP or Transfer Canal OR with irradiated fuel present 2.Rad monitor alarms OR OR 2.1nability to maintain > 643'4" in the refueling cavity 3.Level < 632'4" SFP or Transfer Canal.
with irradiated fuel in containment.
X,
.1
Reference lPM7 P-2080.EPP.101 I Rev. 4 l Page 16 of 112 Emergency CLASSIFICATION Emergency Condition Categories Pages:
9 - 21 INITIATING CONDITIONS - Mode 1-4 GENERAL EMERGENCY l
SE ERGECY RGENCY ALERT UNUSUAL EVENT SYSTEM MALFUNCTIONS S-1 RPSfailure (p.81)
S-1 RPS failure (p.80)
S-1 RPS failure (p.79)
I.Auto and manial Reactor Trip fails from Control Auto and manual Reactor Trip fails from Auto Reactor Trip fails AND manual trip Rm AND Subcriticality and Core Cooling CSFSTs Control room.
successful from Control Room.
are RED OR 2.Sabcriticality and Heat Sink CSFSTs are RED.
I.Prolonged loss of all AC (A and D -T buses)
Loss of all AC (A and D - T buses) for AC power supply to T buses reduced to a Loss of ALL OFF-SITE power (Auxiliary. Reserve and AND Core Cooling CSFST - ORANGE.
> 15 minutes.
single source for > 15 minutes.
69kv Transformers) to the T Buses for > 15 minutes.
OR 2.Loss of all AC (A and D - T buses) expected to last for > 4 hrs.
Loss of ALL vital DC buses AB AND CD for
> 15 minutes (bus volts C 220v)
Loss of ability to achieve or maintain hot shutdown based on entry into:
.OHP 4023.FR-H., Response to Loss of Secondary Heat Sink OR 2.OHP 4023.FR-C.I. Responise to Inadequate Core Cooling.
INITIATING CONDITIONS - Mode 1-4 GENERAL 7EMERGENCY SITE AEA EMERGENCY ALERT UNUSUAL EVENT SYSTEM MALFUNCTIONS S-6 Loss of Alarms (p.95)
S-6 Loss of Alarms (p.92)
S-6 Loss of Alarms (p.90)
Loss of ability to monitor alarms during a Unplanned loss of most or all Safety System 1.Unplanned loss of Safety System annunciators or transient indicated by:
annunciators or Attachment 2 indicators for indicators or Attachment 2 parameters for > 15 I.Loss of Safety System annunciator pariel(s) for
> 15 minutes with transient in progress or minutes.
> 15 minutes.
compensatory indicators unavailable and AND AND additional monitoring is required.
2.Additional monitoring required.
2.Loss of Attachment 2 Critical AND Parameters for > 15 minutes.
3.Compensatory indications for lost annunciators are AND available.
3.Compensatory indications not available (PPC, SPDS).
S-7 Degraded Clad (p.97)
L.RCS activity > 1.0 uCI/gram 1-131 dose equivalent for > 48 hrs.
OR 2.RCS activity > 100/E uCi/gram.
S-8 RCS Leakage (p.98)
RCS leakage exceeds 10 gpm pressure boundary leakage, SG tube leakage or unidentified leakage OR > 25 gpm identified leakage.
S-9 Tech Spec (p.99)
Unit not in required mode within LCO time limits.
S-10 Loss of Comm. (p.100)
Unplanned loss of all on or off-site communications
INTIATING CONDITIONS - Mode 5 & 6 and Defueled GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT HAZARDS AN OTHER CONDMONS H-2 Security (,50).
H-2 Security (p.49)
H-2 Security (p.48)
H-2 Security (p.4 7)
Security Event resulting in loss of Security event in a Vital Area.
Security Event in the Protected Area.
Security Event that potentially degrades ability to reach/ maintain Mode S.
- 1. Intrusion by hostile Force.
- 1. Intrusion by hostile force.
level of plant safety.
OR OR
- 1. Bomb in Protected Area.
- 1. Loss of physical control of Control Room
- 2. Loss of control of Vital Area
- 2. Civil disturbance within Protected Area.
OR OR (NOT Control Room).
- 2. Credible bomb threat.
- 3. Confirmed bomb in Vital Area.
- 3. Credible attack threat.
- 4. Hostage/extortion potentially affecting plant operations.
H-3 CR Evacuation (p.52)
H-3 CR Evacuation (p.51)
Control Room evacuated AND control not Control Room evacuation initiated.
established within 15 minutes.
H4 Fire (p.55)
H4 Fire (p.54)
Fire OR explosion affecting plant operations.
Fire in Protected Area NOT extinguished within
~~ ~~~~~~~~ ~~~~~~~~~~~~1 15 m inutes.
H-5 Toxic Gas (p.58)
H-5 Toxic Gas (p.56)
Toxic OR flammable gas release that Toxic OR flammable gas release affecting threatens lives OR affects ability to achieve plant operation.
and maintain Mode 5.
Reference PMP-2080.EPP.101 Rev. 4 Page 19 of 112 Emergency CLASSIFICATION Attachment Emergency Condition Categories Pages I
INITIATING CONDITIONS - Mode 5 & 6 and Defueled GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT NATUR/DESTRUCTIVE PHENOMENA N-1 Seismic(p.62)
N-1 Seismic (p.60)
Seismic event indicated by:
Seismic event indicated by:
I.Seismic instrument activated.
OR I.Seismic instrument activated.
2.Ground motion detected by Control Room crew.
OR AND 2.Ground motion detected by Control Room crew.
a.Visble major damage in vital area.
OR b.Plant Trip.
N-2 Tornado/wind (p.62)
N-2 Tornado/wind(p.60)
I.Tornado strike in Vital Area I.Tornado strike in Protected Area.
OR 2.>90mphwindfor >15 minutes.
N-3 Structural (p.62)
Visible damage to a structure containing systems required to achieve and maintain Mode 5.
N-4 Vehicle Collision (p.62)
N4 Vehicle Collision(p.60)
Vehicle collision affecting Vital Area.
Vehicle collision affects systems or structures in the Protected Area.
N-5 MT Failure (p.62)
N-5 MT Failure (p.60)
Main turbine generated missile penetrates Vital Area.
Main turbine rotating component failure causes visible damage or damages generator seals.
N-6 Flooding (p.62)
F looding in V ital A rea affects safety related equip.
N-7 Explosion (p.60)
Unanticipated explosion within Protected Area causes visible dam age to perm anent structures or equipm ent.
Reference I
PMP-2080.EPP.101 I Rev. 4 l Page 20 of 112 Emergency CLASSIFICATION w
w~~~~~~~~~~~~~~~~~~Pgs I
Emergency Condition Categories Pages:
1;'.
~~~~~~~~~~~~~~~~~~~9
- 21 i
INITIATING CONDITIONS - Mode 5 & 6 and Defueled ee I
GENERALIEMERGENCY I
STE AREA EMERGENCY I
ALERT I
UNUSUAL EVENT ABNORMALAIATION LEVELS/EFFLUENTS R-1 Effluent release (p*70)
R-1 Efuent release (p.68)
R-1 Effluent release (p.66)
R-1 Effluent release (p.64)
Site boundary dose > I EM TEDE Site boundary dose > 100 mrem TEDE Unplanned Rad release >200X ODCM limits for Unplanned Rad release >2X ODCM limits for
.or 5 REM CDE lo thyroid based on:
or 500 mrem CDE to thyroid based on:
> 15 minutes based on:
> 60 minutes based on:
I.Survey results OR I.Survey results 1.200X rad monitor high alarm setpoint.
- 1. Rad monitor 2X high alarm setpoint.
2.Dose assessment OR OR OR OR 2.Dose assessment 2.Gas or liquid sample results.
2.Gas or liquid sample results.
3.Effluent monitor readings > 15 minutes.
OR 3.Effluent monitor readings > 15 minutes.
R-2 Plant Rad level (p.73)
R-2 Plant Rad level (p.72)
Rad levels that impede plant operations based on:
Unexpected reading on Area Monitor 1000X the 24 hr average.
- 2. > 100 mR/hr at remote S/D areas.
R-3 Loss of level (p.77)
R-3 Loss of level (p.75)
Major damage to irradiated fuel or loss of Uncontrolled lowering in refueling cavity.
level that has or will uncover fuel outside of SFP or Transfer Canal indicated by:
the reactor vessel based on:
I.Visual observation of levels, lIlnability to maintain > 643'4-in SFP or Transfer OR Canal with irradiated fuel present.
2.Rad monitor alarms OR OR 2.1nability to maintain > 643'4' in the refueling cavity 3.Level < 632'4" SFP or Transfer Canal.
with irradiated fuel in containment.
l
.. ]
I r i
I I
I I
I i
.I I
Reference PMP-2080.EPP.101 Rev. 4 Page 21 of 112 Emergency CLASSIFICATION Emergency Condition Categories 9 - 21
- ENS, INITIATING CONDITIONS - Mode 5 & 6 and Defueled rGENERAL4 EMERGENCY SITIE AEA EMERGENCY ALERT UNUSUAL EVENT COLD SI UTDOWN/REFUELING SYSTEM MALFUNCTIONS C-3 Loss of AC(p.103)
C-3 Loss of AC (p.101)
Loss of ALL AC power to A and D T-buses for Loss of ALL OFF-SITE power (Auxiliary,
> 15 minutes.
Reserve amd 69kv transformers) to the T buses for > 15 minutes.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ M o d e 5,6 a n d d e fu e le d M o d e 5,6 C-4 Loss of Water Level In the Reactor Vessel C4 Inability to Maintain a Unit in that has or will Uncover Fuel in the Reactor Cold Shutdown (p.105)
- Vessel (p.107) 1I.Loss of shutdown cooling as evidenced by entry I.Loss of shutdown cooling as evidenced by entry into OHP into OHP 4022.017.001, 'Loss of RHR Cooling" 4022.017.001, Lass of RHR Cooling-AND 4022.017.00 : "Loss of R ooliAND 2.Temperature rise that either:
2.Core uncovery as indicated by:
- a. Exceeds T/S cold shutdown limit of 200"F.
- a. RVLIS NR < 46% -
- b. Results in an UNCONTROLLED RCS
- b. Reactor Vessel Water Level <614 feet temperature rise approaching the cold shutdown T/S limit of 200"F Mode 5,6 Mode 5,6 C-S Degraded Clad (p.108)
.RCS activity > L.0RCi/grams 1-131 dose equivalent for > 48 hrs.
OR 2.RCS activity > 100/E uCi/gram.
Mode 5,6 C-6 Loss of Comm. (p.109)
Unplanned loss of all on or off-site communications, Mode 5,6 C-7 Loss of DC power (p.111)
Unplanned loss of ALL vital DC buses AB AND CD for > 15 minutes (bus volts <220v)
Modes 5,6
Reference PMP-2080.EPP.101 Rev. 4 Page 22 of 112 Emergency CLASSIFICATION Critical NUREG 0737 Parameters Page:
22 PARAMETERS INSTUMENTATION Neutron Flux - (Gammametrics)
NRI-21, 23 Reactor Coolant Pressure (Wide Range)
NPS-121, 122 Reactor Coolant Outlet Temperature THO (Wide Range)
NTR-110, 130 ReactorCoolant OutletTemperature TCOLD (Wide Range)
NTR-210, 230 Incore Thermocouples (Core Exit Thermocouples)
T/S 1-65 Reactor Coolant System Subcooling Margin Monitor SUBCOOL MAR Reactor Coolant Inventory System (Reactor Vessel Level Indication)
NH-i 10, 111, 120, 121, 130, 131 Pressurizer-Water Level NLP-151, 152, 153 Charging Pump Flow IFI-51, 52, 53, 54 Charging Pump Breaker Status 1E, 1W, 2E, 2W Control Room Position Indicating Lights for Breakers Safety Injection-Pump Breaker Status iN, 1S, 2N, 2S Control Room Position Indication Lights for Breakers Safety Injection Flow IFI-260 - 266 Refueling Water Storage Tank Water Level ILS-950, 951 Containment Water Level NLA-320, NLT-321 Containment Pressure (Wide Range)
PPA-310, 312 Containment Pressure (Narrow Range)
PPP-300, 301, 302, 303 Containment Hydrogen Monitoring ESR-1 thru 9 Containment-Isolation Valve Position Monitoring Control Room Position Indicating Lights Containment Area Radiation Monitor (High Range)
Unit 1 VRA-1310, 1410, Unit 2-2310, 2410 Steam Line Pressure MPP-210, 211, 212, 220, 221, 222, 230, 231, 232, 240, 241, 242 Steam Genera-tor Water Level (Wide Range)
BLI-110, 120, 130, 140 Steam Generator Water Level (Narrow Range)
BLP-110, 111, 112, 120, 121, 122, 130, 131, 132, 140, 141, 142 Auxiliary Feedwater Flow Rate FFI-210, 220, 230, 240 Condensate Storage Tank Level CLI-113, 114, CLR-110, 111
Reference PMP-2080.EPP.101 Rev. 4 l
Page 23 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 -112 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION FUEL CLAD BARRIER 1.1: CRITICAL SAFETY FUNCTION STATUS TREES MODE APPLICABILITY Modes 1, 2, 3, 4 EAL THRESHOLD VALUE LOSS:
Core Cooling Critical Safety Function Status Tree - RED POTENTIAL LOSS:
Core Exit Thermocouples > 7520
-OR-RVLIS level < 46% (Narrow Range)
-OR-Heat Sink Critical Safety Function Status Tree - RED.
BASIS (References)
LOSS - The core cooling critical safety function RED path indicates significant superheating and core uncovery and is considered to indicate a loss of the fuel clad barrier. One of the indicators of the core cooling critical safety function red is when the core exit thermocouple temperature is equal to or greater than 1200 degrees Fahrenheit.
POTENTIAL LOSS - Core exit thermocouple temperature equal to or greater than 752 degrees Fahrenheit or RVLIS level <46 % (Narrow Range) corresponds to a loss of subcooling and is indicative of a potential loss of the fuel clad barrier. The Heat Sink Critical Safety Function - RED path indicates that the heat sink is under extreme challenge and is indicative of a potential loss of the fuel clad barrier.
DEVIATION FROM NUMARC:
None
Reference PMP-2080.EPP.101 Rev. 4 Page 24 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
- (Commitment
- 6489) 23 - 112 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION FUEL CLAD BARRIER 1.2 - CONTAINMENT RADIATION MODE APPLICABILITY 1,2,3,4 EAL THRESHOLD VALUE LOSS:
Containment area radiation greater than 200 R/hr.
POTENTIAL LOSS:
None BASIS (References)
LOSS - The 200 R/hr value is based on a reasonable assessment of a single number representing the expected monitor reading on the upper containment area radiation monitors VRA 131011410 (Unit 1) or VRA 2310/2410 (Unit 2). This represents the expected reading for loss of coolant accidents with fuel failure in the range between 2 and 5 % (depending on core inventory which will vary with the time after reactor shutdown).
The 200 R/hr value was determined on the basis of the D. C. Cook Core Damage Assessment Methodology, taking into account that the radiation levels resulting from the release of noble gases from failed fuel will vary as a function of core shutdown time. Typically, these curves show that for noble gases the containment radiation monitors will read 1325 R/hr after 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of core shutdown, and assuming 100% fuel cladding damage based on noble gas release only. This would correspond to 200 R/hour for 5 % cladding damage and noble gas release 90 minutes after the reactor is shut down.
The reading is based on noble gas reading alone, and does not include the instantaneous release and dispersal of the reactor coolant iodine inventory associated with a concentration of 300 microcuries per gram 1-131 equivalent into the containment atmosphere as suggested by Revision 2 of NUREG/NESP 007. The addition of the iodine activity from the reactor coolant would result in higher monitor readings, thus' making the 200 R/hr value a conservative threshold value.
This assumption is appropriate since it is consistent with the current dose assessment methodology of the Donald C. Cook Nuclear Plant, an ice condenser containment plant.
POTENTIAL LOSS - None DEVIATION FROM NUMARC:
Calculation of radiation monitor reading is based on dispersal of noble gases only (iodine inventory not included) from the reactor coolant.
Reference PMP-2080.EPP.101 Rev. 4 Page 25 of 112 Emergency CLASSIFICATION Attachmnt 3 1
Basis For Emergency Action Levels Pages:
I -
(Commitment: 6489) 23 - 112 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION FUEL CLAD BARRIER 1.3: PRIMARY COOLANT ACTIVITY MODE APPLICABILITY Modes 1, 2, 3, 4 EAL THRESHOLD VALUE LOSS:
Reactor Coolant System activity level greater than 300 microcuries per cc 1-131 dose equivalent.
-OR-Assessment of core damage greater than 5% clad failure.
(NRC commitment #7991)
POTENTIAL LOSS:
None BASIS (References)
LOSS - 300 microcuires per cc 1-131 dose equivalent corresponds to a value which is cited in Revision 2 of NUMARC/NESP 007 as being well above that expected for iodine spikes and corresponding to 2 to 5 % fuel clad damage. This amount of cladding damage indicates significant clad heating and thus the Fuel Clad Barrier is considered lost. This value will be determined from Cook Nuclear Plant procedure PMP 2081 EPP. 105, "Core Damage Assessment".
Assessment may be performed by authorized shift personnel prior to TSC activation or the TSC after TSC has been activated.
POTENTIAL LOSS - None DEVIATION FROM NUMARC: None I
Reference PMP-2080EPP.101 Rev. 4 Page 26 of 112 Emergency CLASSIFICATION Atacmnt3Basis For Emergency Action Levels Pages:
Attachmen 3 (Commitment: 6489) 23 - 112 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION RCS BARRIER 2.1: RCS LEAK RATE MODE APPLICABILITY Modes 1, 2, 3, 4 EAL THRESHOLD VALUES:
LOSS:
UNISOLABLE RCS leak rate greater than available makeup capacity as indicated by a complete loss of RCS subcooling.
POTENTIAL LOSS:
UNISOLABLE RCS leakage greater than capacity of one centrifugal charging pump in normal charging lineup.
BASIS (References)
UNISOLABLE - A leak that cannot be isolated from the control room.
NORMAL CHARGING LINEUP - The normal charging flow path through the volume control system including design and alternate flow paths, and flow to reactor coolant pump seals.
LOSS - Leakage that results in complete loss of subcooling is a fundamental indication that the inventory control systems are inadequate for maintaining RCS pressure and inventory.
POTENTIAL LOSS - Unisolable leakage in excess of the capacity of one centrifugal charging pump in the normal charging mode is considered to be the inability to maintain normal liquid inventory in the RCS and assures that any event that results in a significant inventory loss or shrinkage will result in an ALERT classification.
This leak is NOT isolable from the control room OR an attempt for isolation from the control room has been made and was unsuccessful. An attempt for isolation should be made prior to the accident classification. If isolable upon identification, this initiating condition is not applicable.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101X Rev. 4 l
Page 27 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 -112 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION RCS BARRIER 2.2: STEAM GENERATOR LEAKAGE MODE APPLICABILITY Modes 1, 2, 3, 4 EAL THRESHOLD VALUE LOSS:
Entry into OHP-4023.E-3, "Steam Generator Tube Rupture" AND a non-isolable secondary line break resulting in a prolonged release ( > 30 minutes) radioactive release to the environment from the affected steam generator.
POTENTIAL LOSS:
Ruptured steam generator with primary to secondary leak rate greater than capacity of one charging pump in normal charging mode.
BASIS (References)
NORMAL CHARGING MODE - The normal charging flow path through volume control system including design and alternate flow paths, and flow to reactor coolant pump seals.
LOSS - This is intended to address the full spectrum of steam generator tube rupture events and addresses the direct release of radioactive material to the environment. Dose assessment is required when there is indication that the fuel matrix/clad is potentially lost. This EAL encompasses steam breaks, feed breaks, and stuck open safety or relief valves. The assumed break flow termination time period in our steam generator tube rupture dose consequence analysis is 30 minutes; therefore, 30 minutes is used to define prolonged.
POTENTIAL LOSS - Unisolable leakage in excess of the capacity of one centrifugal charging pump in the normal charging mode is considered to be the inability to maintain normal liquid inventory in the RCS and assures that any event that results in a significant inventory loss or shrinkage will result in an ALERT classification.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.0X1 Rev. 4 Page 28 of 112 Emergency CLASSIFICATION
--I Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 - 112 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION RCS BARRIER 2.3:
CONTAINMENT RADIATION MODE APPLICABILITY Modes 1, 2, 3, 4 EAL THRESHOLD VALUE LOSS:
Containment radiation greater than 10 R/hr.
POTENTIAL LOSS:
None BASIS (References)
LOSS - A value of 10 R/hr as indicated on VRA 1310/1410 (Unit 1) and VRA02310/2410 (Unit 2) was chosen because it is above the ambient background radiation and represents a detectable radiation level above allowed Technical Specification radiochemistry limits but less than the 2-5 % fuel clad damage used in the fuel clad fission product barrier threshold value.
The 10 R/hr value was determined on the basis of the Donald C. Cook Core Damage Assessment methodology, taking into account that the radiation levels resulting from noble gases released from the coolant will vary as a function of core shutdown time. The reading is based on noble gas reading alone approximately 90 minutes after reactor shutdown. This assumption is consistent with the current core damage assessment methodology for the Donald C. Cook Nuclear Plant.
The use of noble gases alone for a EAL threshold is conservative since if iodine or other radioactive materials were present, the doses would be higher. The use of a value reflecting a plant shutdown of one hour was selected as a reasonable reflection of the phenomena being considered without concern about setting the threshold too high or too low. The actual fission product barrier threshold will be declared at any time the value indicated is exceeded.
POTENTIAL LOSS - None DEVIATION FROM NUMARC:
Calculation of radiation monitor reading is based on dispersal of noble gases only (iodine inventory not included) from the reactor coolant.
Reference PMP-2080.EPP.101 Rev. 4 Page 29 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
23-112 (Commitment: 6489) 2 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION RCS BARRIER 2.4: RCS INTEGRITY CSFST MODE APPLICABILITY 1, 2, 3,4 EAL THRESHOLD VALTJUE LOSS: None POTENTIAL LOSS:
RCS Integrity Critical Safety Function Status Tree - RED BASIS (References)
LOSS - None POTENTIAL LOSS -
The RCS Integrity Critical Safety Function RED indicates an extreme challenge to the safety function and a potential loss of the RCS barrier.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101 Rev. 4 Page 30 of 112 Emergency CLASSifICATION Attachmet 3.Basis For Emergency Action Levels Pages: (Commitment: 6489) 23 - 112 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION RCS BARRIER 2.5: HEAT SINK. CSFST MODE APPLICABILITY 1,2,3,4 EAL ThRESHOLD VALUES LOSS: None POTENTIAL LOSS:
Heat Sink Critical Safety Function Status Tree - RED BASIS (References)
LOSS - None POTENTIAL LOSS -
The Heat Sink Critical Safety Function - RED path indicates that the heat sink is under extreme challenge and is indicative of a potential loss of the RCS barrier.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101 Rev. 4 Page 31 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 - 112 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION CONTAINMENT BARRIER 3.1 - CONTAINMENT RADIATION MODE APPLICABILITY 1,2,3,4 EAL THRESHOLD VALUE LOSS:
None POTENTIAL LOSS:
Containment Radiation greater than 1000 R/hr.
-OR-Assessment of core damage greater than 20% clad failure BASIS (References)
LOSS - None POTENTIAL LOSS - The 1000 R/hr value is based on a reasonable assessment of a single number representing the expected monitor reading on the upper containment high range area radiation monitors VRA 1310/1410 (Unit 1) or VRA 2310/2410 (Unit 2). The reading represents the expected reading for loss of coolant accidents with 20% fuel clad damage.
The 1000 R/hr value was determinedlon the basis of the Donald C. Cook Core Damage Assessment Methodology, taking into account that the radiation levels resulting from the release of noble gases from failed fuel will vary as a function of core shutdown time. As with the RCS and Fuel Clad barriers containment radiation EALs, this reading is based on release of noble gases only, approximately 90 minutes after shutdown.
DEVIATION FROM NUMARC; Calculation of radiation monitor reading is based on dispersal of noble gases only (iodine inventory not included) from the reactor coolant.
Reference PMP-2080.EPP.101 Rev. 4 X
Page 32 of 112 Emergency CLASSIFICATION Atchment 3 l
Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 - 112 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION CONTAINMENT BARRIER 3.2:
CONTAINMENT INTEGRITY MODE APPLICABILITY 1,2,3,4 EAL THRESHOLD VALUES LOSS:
- 1. UNISOLABLE breach or bypass of containment
-OR-
-OR-
- 3. Pressure/Sump level NOT performing consistent with expected conditions
-OR-
- 4. Entry into ECA-1.2, LOCA OUTSIDE CONTAINMENT" POTENTIAL LOSS:
None BASIS (References)
UNISOLABLE - A breach that cannot be isolated from the control room.
LOSS - An unisolable breach of containment includes any open unisolable containment penetration. A breach of containment has occurred if an inboard and outboard pair of isolation valves fails to close on an automatic activation signal or from a manual action in the control room and opens a release path to the environment. Plant procedure OHP 4023.E1-,
Reactor Trip or Safety Injection," provides lists of containment isolation valves required to close on high or HI HI containment pressure.
The breach is considered unisolable if it cannot be isolated from the control room or an attempt for isolation was made from the control room and was unsuccessful. An attempt for isolation should be made prior to accident classification. If isolable upon identification this initiating condition is not applicable.
The rapid pressure drop following an initial pressure rise indicates a failed containment. Failure of containment pressure to elevate or containment sump level to rise is also indicative of containment bypass or a loss of containment scenario. ECA-L.2 is entered when there is evidence of excessive auxiliary building radiation while a loss of reactor or secondary coolant is occurring.
POTENTIAL LOSS - None
Reference PMP-2080.EPP.101 Rev. 4 Page 33 of 112 Emergency CLASSIFICATION l
Basis For Emergency Action Levels Pages:
I
~(Commitment: 6489) 23 - 112 DEVIATION EROM NUMARC:
i A.:
s
- v
--- ^
None
Reference PMP-2080.EPP.101 Rev. 4 Page 34 of 112 Emergency CLASSIFICATION l
Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 -112
.~ ~
~Comtet 649 23 11 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION CONTAINMENT BARRIER 3.3 - STEAM GENERATOR SECONDARY SIDE RELEASE MODE APPLICABILITY 1,2,3,4 EAL THRESHOLD VALUE LOSS:
la.
Primary to secondary leakage rate greater than technical specification limit.
AND
- b.
Secondary line break outside containment results in release (> 30 minutes) to the environment.
- 2.
Release of secondary coolant from the associated steam generator to the environment is occurring with an alert alarm on any SG PORV radiation monitor.
POTENTIAL LOSS:
None BASIS (References)
NORMAL CHARGING LINEUP - The normal charging flow path through the volume control system including design and alternate flow paths, and flow to reactor coolant pump seals.
LOSS - Secondary side release paths to the environment include atmospheric relief valves and main steam safety valves. Site Area Emergency declaration will be based on evidence of elevated RCS activity as indicated by SG PORV radiation monitor alert alarm. The SG PORV radiation monitor alert alarm setpoint corresponds to SAE site boundary dose rate.
For smaller breaks, not exceeding the capacity of one charging pump in the NORMAL CHARGING MODE, an UNUSUAL EVENT classification Will result if the ruptured steam generator is isolated.
For largerbreaks, if the steam generator remains unisolated, this EAL will be a discriminator for'SITE AREA AND GENERAL EMERGENCIES. 'Me threshold for Site Area Emergency is based on elevated RCS activity indicated by an alert alarmon a SG PORV radiation monitor.
Reference PMP-2080.EPP.101
-Rev.
4 Page 35 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 -112 Z
If the MSIV on the affected SG is stuck open, the classification is not upgraded to a Site Area Emergency unless there are other complicating factors present. Any complicating factors present should be considered in order to determine if the tube rupture should be classified as a Site Area Emergency. These factors may include, but are not limited to, elevated RCS activity (300 plc/cc 1-131 dose equivalent indicates significant failed fuel, > 1%), or significant unisolable steam leakage downstream of the MSIV.
SEC judgement should be used when evaluating the steam leak size and any other complicating factors that are not specifically addressed in the EAL, when making the determination to classify the tube rupture as a Site Area Emergency.
POTENTIAL LOSS None DEVIATION FROM NUMARC:
NUMARC does not use the elevated RCS activity as discriminator for Site Area Emergency.
Reference PMP-2080.EPP.101-Rev. 4 l
Page 36 of 112 Emergency CLASSIFICATION 1
Basis For Emergency Action Levels Pages:
ffi (Commitment: 6489)23-112 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION CONTAINMENT BARRIER 3.4 - CONTAINMENT CRITICAL SAFETY FUNCTION STATUS TREE MODE APPLICABILITY 1,2, 3,4 EAL THRESHOLD VALUE LOSS:
None POTENTIAL LOSS:
Containment critical safety function status tree - RED BASIS (References)
LOSS - None POTENTIAL LOSS - The RED path indicates an extreme challenge to the containment and represents a potential loss of containment.
In addition to a containment isolation system, the Cook Nuclear Plant design includes an ice condenser system, containment air recirculation hydrogen skimmer fans, containment spray system, and an RHR system. The lower containment high pressure setpoint is 1.1 psig at which a partial containment isolation will occur and the containment air recirculation fans are automatically started after a short time delay. Containment spray is automatically started when containment pressure reaches its HI HI pressure of 2.9 psig. RHR spray will be initiated if both containment spray trains are not running and 50 minutes has elapsed since the reactor trip. This 12 psig value is also the containment pressure which indicates Containment Critical Safety Function Status Tree - RED, this EAL indicates the potential of the containment exceeding its design pressure of 12 psig, hence the potential of loss of containment.
DEVIATION FROM NUMARC: None I.
I
Reference PMP-2080.EPP.101
-Rev. 4 Page 37 of 112 Emergency CLASSIFICATION 4
Basis For Emergency Action Levels l
Pages:
(Commitment: 6489)23-112 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION CONTAINMENT BARRIER 3.5:
CONTAINMENT HYDROGEN MODE APPLICABILITY 1,2, 3,4 EAL THRESHOLD VALUES LOSS:
Initiating conditions for LOSS included under initiating conditions for loss of FPB 3.2, CONTAINMENT INTEGRITY.
POTENTIAL LOSS:
- 1. Hydrogen greater than 4.0%
-OR-
- 2. Containment hydrogen concentration greater than 0.5% AND any hydrogen control equipment (Containment air recirculation/hydrogen skimmer systems, electric hydrogen recombiner OR igniters) inoperable.
BASIS (References)
LOSS - None POTENTIAL LOSS - Cook Nuclear Plant is a Westinghouse plant with an ice condenser containment.
Due to its smaller volume than comparable plants with dry containments, it relies more heavily on engineered safety features for overpressure protection than do dry containments. Overpressure may be caused by buildup of steam or noncondensibles in containment, or the consequences associated with ignition of hydrogen gas in the containment.
The potential for loss of containment may be caused by the accumulation of hydrogen gas and the inability of at least one train of required safety components required for the control of hydrogen gas to be inoperable. A 0.5% or greater volume percent is indicative that significant hydrogen gas has formed in containment, and control measures are warranted. Equipment to limit accumulation of hydrogen includes the containment air recirculation fans and the containment air recirculation/hydrogen skimmer system. Failure of this equipment is indicative of accumulating percentages of hydrogen until 4 volume percent, the lower flammability limit for hydrogen gas is exceeded.. Above this percentage,
'the hydrogen igniters are the principal equipment relied on to reduce hydrogen gas concentration to below 4 percent.
Reference PMP-2080.EPP.101 Rev. 4 Page 38 of 112 Emergency CLASSIFICATION J
Basis For Emergency Action Levels Pages:
Attachment (Commitment: 6489) 23 -112 DEVIATION FROM NUMARC:
A threshold value has been added for hydrogen concentration greater than 0.5 % and key hydrogen control equipment inoperable.
Reference PMP-2080.EPP.101 Rev. 4 Page 39 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
A m(Commitment: 6489) 23 - 112 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION CONTAINMENT BARRIER 3.6 - CONTAINMNT PRESSURE CONTROL MODE APPLICABILITY 1,2,3,4 EAL THRESHOLD VALUES LOSS:
Initiating conditions for LOSS included under initiating conditions for loss of FPB 3.3, CONTAINMENT INTEGRITY.
POTENTIAL LOSS:
- 1. Both containment spray systems both inoperable OR fail to automatically actuate on HI-HI containment pressure.
-OR-
- 2. Both containment air recirculation fans inoperable OR fail to automatically actuate on HI containment pressure.
-OR-
- 3. Containment pressure exceeds 12 psig.
BASIS (References)
LOSS - None POTENTIAL LOSS - Cook Nuclear Plant is a Westinghouse plant with an ice condenser containment.
Due to its smaller volume than comparable plants with dry containments, it relies more heavily on engineered safety features for overpressure protection than do dry containments. Overpressure may be caused by buildup of steam or noncondensibles in containment, or the consequences associated with ignition of hydrogen gas in the containment.
Containment pressure control is achieved through the Containment Spray system and the Containment Air Recirculation/hydrogen skimmer system. Total failure of both these systems'may allow steam to build up within containment, and, unabated, this steam buildup may cause the internal' containment
' pressure buildup to exceed the design pressure of 12 psig. Studies have shown that the containment can withstand pressures well above this value.
Both the recirculation fans and the containment spray pumps are actuated atuomatically following
'receipt of a HI or HI HI containment pressure signal, respectively. However, rapid startup of these systems is not required, since the ice condenser will serve as a passive steam pressure reduction device until the ice has melted. Therefore, if these systems should fail, it is permissible to start both these
Reference PMP-2080.EPP.101 Rev. 4 Page 40 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
23 112 (Commitment: 6489) 2 1
systems manually without being overly concerned about the potential loss of containment due to overpressure. However, the failure of automatic startup of redundant equipment is considered symptomatic of potentially degraded key safety equipment. Thus the potential loss categorization will remain until it can be determined that the failure to start automatically was not symptomatic of major system degradation.
DEVIATION FROM NUMARC:
None.
Reference PMP-2080.EPP.101-Rev. 4 Page 41 of 112 Emergency CLASSIFICATION Atchment 3 Basis For Emergency Action'Levels Pages:
(Commitment: 6489)23-112 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION CONTAINMENT BARRIER 3.7 - CORE EXIT THERMOCOUPLES MODE APPLICABILITY 1,2,3,4 EAL THRESHOLD VALUES LOSS:
None POTENTIAL LOSS:
Core Cooling Critical Safety Function Status Tree - RED
-AND-Restoration procedures not effective within 15 minutes.
BASIS (References)
LOSS - None POTENTIAL LOSS - The conditions in this EAL represent inminent fuel melt sequence which, if not corrected could lead to vessel failure and an increased potential for containment failure. Severe accident analysis has concluded that functional restoration procedures can arrest core damage within the reactor vessel in many core damage cenarios, and that the likelihood of containment failure is small for these events. Whether or not the procedures will be effective should be apparent within 15 minutes of taking action as directed by the procedure. The SEC should make the declaration as soon as it is determined that the procedure appears to be ineffective.
The core cooling status tree - RED is indicative that major fuel damage has occurred, and radioactive release can be expected. The conditions which indicate this condition are either 1) core exit thermocouples greater than 1200 degrees F or core exit thermocouples greater than 752 degrees F and RVLIS (Reactor Vessel Level Indication System) narrow range less than 46% with no reactor coolant pump running. This represents a more conservative position than recommended in Revision 2 of NUMARC/NESP 007, but is taken to be consistent with the guidance afforded by the Westinghouse Owners Group as to the indication of when core cooling may be considered to be lost.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101 Rev. 4 Page 42 of 112 Emergency CLASSIFICATION
.1 Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H-i: UNUSUAL EVENT - SEC JIUDGEMENT INITIATING CONDITION Other conditions existing which in the judgement of the Site Emergency Coordinator (SEC) warrant declaration of an Unusual Event.
MODE APPLICABILITY All EAL THRESHOLD VALUE In the judgement of the SEC, conditions indicate a potential degradation of the level of safety of the plant.
BASIS (References)
This ECC is intended to address unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of an emergency because conditions exist which are believed by the SEC to fall under the Unusual Event emergency class.
From a broad perspective, one area that may warrant SEC judgement is related to likely or actual breakdown of site specific event mitigating actions. Examples to consider include inadequate emergency response procedures, transient response either unexpected or not understood, failure or unavailability of emergency systems during an accident in excess of that assumed in accident analyses, or insufficient availability of equipment and/or support personnel.
Specific examples of actual events that may require SEC judgement for Unusual Event declaration are listed here for consideration. However, this list is by no means all inclusive and is not intended to limit the discretion of the SEC.
Aircraft crash on -site but, outside the protected area.
Train derailment on-site but, outside the protected area.
Near-site explosion which may adversely affect normal site activities but, doesn't directly affect activities required to maintain safe operation of the plant.
a Near-site releases of toxic or flammable gas which may adversely affect normal site activities but, doesn't directly affect activities required to maintain safe' operation of the plant.
. i
. I
Reference PMP-2080.EPP.101 Rev. 4 Page 43 of 112 Emergency CLASSIFICATION
' ' Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 - 112 It is also intended that the SEC's judgement not be limited by any lists of events as defined here. This list is provided solely as examples for consideration' and it is recognized that actual events may not always follow a pre-conceived description.
TERMEIATIONIRECOVERY CRITERIA The condition which caused the declaration to be made no longer exists, or in the SEC's judgement, the condition will not cause a degradation of the level of safety of the plant.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.11 Rev. 4 l
Page 44 of 112 Emergency CLASSIFICATION Basis For. Emergency Action Levels Pages:
(Commitment: 6489)
-23
-112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H-i: ALERT - SEC JUDGEMENT INITIATING CONDITION Other conditions existing which in the judgement of the Site Emergency Coordinator (SEC) warrant declaration of an Alert.
MODE APPLICABILITY All EAL THRESHOLD VALUE In the judgement of the SEC:
- 1. conditions indicate that plant safety systems may be degraded,
-AND-
- 2. increased monitoring of plant functions is needed.
BASIS (References)
This ECC is intended to address unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of an emergency because conditions exist which are believed by the SEC to fall under the Alert emergency class.
TEPINIATION/RECOVERY CRITERIA The condition which caused the declaration to be made no longer exists, or in the SEC's judgement, the condition will not cause a degradation of the level of safety of the plant.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101,l Rev. 4 Page 45 of 112 Emergency CLASSIFICATION Attahen 3Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H-1: SITE AREA EMERGENCY - SEC JUDGEMENT INITIATING CONDITION Other conditions existing which in the judgement of the Site Emergency Coordinator (SEC) warrant declaration of a Site Area Emergency.
MODE APPLICABILITY All EAL THRESHOLD VALUE In the judgement of the SEC:
Conditions indicate likely or actual major failures of plant functions needed for the protection of the public.
BASIS (References)
This ECC is intended to address unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of an emergency because conditions exist which are believed by the SEC to fall under the Site Area Emergency, emergency classification.
TERMINATIONRECOVERY CRITERIA The condition which caused the declaration to be made no longer exists, or in the SEC's judgement, the condition no longer indicates likely or actual major failures of plant functions needed for the protection of the public health and safety.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.11 Rev. 4 Page 46 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
(C jm t 6489)23-112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H-i: GENERAL EMERGENCY - SEC JUDGEMENT INITIATING CONDITION Other conditions existing which in the judgement of the Site Emergency Coordinator (SEC) warrant declaration of a General Emergency.
MODE APPLICABILITY All EAL THRESHOLD VALUE In the judgement of the SEC:
- 1. Condition indicate an actual or imminent substantial core degradation with potential loss of affected unit's containment.
-OR-
- 2. Potential exists for an uncontrolled radioactive release that may exceed EPA limits at the site boundary.
BASIS (References)
The ECC is intended to address unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of an emergency because conditions exist which are believed by the SEC to fall under the General Emergency, emergency classification.
TERMINIATIONIRECOVERY CRITERIA In the SEC's judgement, a General Emergency no longer exists and entry into recovery procedures is appropriate. The affected unit has achieved a cold shutdown.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101 Rev. 4 Page 47 of 112 Ein&gency CLASSIFICATION Basis For'Emergency Action Levels Pages.
Afiachmen 3 (Commitment-609) 23 - 112 L} ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H-2: UNUSUAL EVENT - SECURITY EVENTS INITIATING CONDITION Confirmed Security Event which indicates a potential degradation in the level of safety of the plant.
MODE APPLICABILITY All EAL THRESHOLD VALUE
- 1. Bomb device discovered within the protected area and outside the vital area.
-OR-
- 2. Credible bomb threat.
-OR-
- 3. Credible attack threat.
-OR-
- 4. Hostage/Extortion incident potentially affecting plant operations.
BASIS (References)
This EAL is based on the Modified Amended Security Plan (MASP). Security events which do not represent at least a potential degradation in the level of safety of the Plant, are reported under 10 CFR 73.71 or in some cases, under 10 CFR 50.72. The plant protected area boundary is the area within the security isolation zone as defined in the Modified Amended Security Plan. Bomb devices discovered within the plant vital area would result in EAL escalation.
TERMINIATION/RECOVERY CRITERIA The hazard to the level of safety of the plant no longer exists.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101 Rev. 4 Page 48 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
Attacment (Commitment: 6489) 23 - 112
-ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H-2: ALERT - SECURITY EVENTS INITIATING CONDITION Security Event in a Plant Protected Area.
MODE APPLICABILITY All EAL THRESHOLD VALUE
- 1. Intrusion into protected area by a hostile force.
-OR-
- 2. Civil disturbance within the protected area.
BASIS (References)
This class of security events represent an escalated threat to plant safety above that contained in the Unusual Event. Intrusion into a vital area by a hostile force will escalate this event to a Site Area Emergency.
TERMINIATION/RECOVERY CRITERIA Challenge to the safety of the plant no longer exists.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101 Rev. 4 Page 49 of ll2 Emergency CLASSIFICATION
--1 Basis For Emergency Action Levels Pages:
It (Commitment: 6489) 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H-2: SITE AREA EMERGENCY - SECURITY EVENTS INITIATING CONDITION Security event in a plant vital area.
MODE APPLICABILITY All EAL THRESHOLD VALUE
- 1. Intrusion into any vital area by a hostile force.
-OR-
- 2. A security event which results in the loss of control of any vital area (other than the control room).
-OR-
- 3. A confirmed bomb device discovered in a vital area.
BASIS (References)
This class of security events represents an escalated threat to plant safety above that contained in the Alert IC in that a hostile force has progressed from the protected area to a vital area.
TERMNUITION/RECOVERY CRITERIA The condition causing the event has been eliminated.
DEVIATION FROM NUMARC: None
Reference l
PMP-2080.EPP.101 Rev. 4 l
Page 50 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
23-112 I
~(Commitment: 6489)
-1 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H-2: GENERAL EMERGENCY - SECURITY EVENTS INITIATING CONDITION Security Event resulting in loss of ability to reach and maintain cold shutdown.
MODE APPLICABILITY All EAL THRESHOLD VALUE
- 1. Loss of physical control of the control room due to a security event.
-OR-
- 2. Loss of physical control of a unit's remote shutdown capability due to a security event.
BASIS (References)
This Initiating Condition encompasses conditions under which a hostile force has taken physical control of either the control room or all remote shutdown capabilities resulting in a loss of physical control of the facility. This EAL is an escalation of the Site Area Emergency declaration for a hostile force intrusion into a vital area.
TERMINIATION/RECOVERY CRITERIA The security threat has been eliminated and cold shutdown can be maintained.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.1O1 Rev. 4 Page 51 of 112 Emergency CLASSIFICATION Attchment 3 l
Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H-3: ALERT - CONTROL ROOM EVACUATION INITIATING CONDITION Control room evacuation has been initiated.
MODE APPLICABILITY All EAL THRESHOLD VALUE Control room evacuation has been initiated.
BASIS (References)
CONTROL - Placing all local controls in position necessary for operation from remote panels and the shift supervisor has determined that the systems for controlling reactivity, RCS inventory, RCS temperature, and the heat sink functions have been established.
Evacuation of the control room represents a potential for substantial degradation in the level of safety of the plant and, therefore, requires an ALERT declaration. Additional support, monitoring, and direction is required and accomplished by activation of the Technical Support Center at the Alert classification level. Inability to establish plant CONTROL from outside the control room will escalate the event to a Site Area Emergency.
Cook Nuclear Plant has separate control rooms for each unit. The Cook Nuclear Plant procedure governing control room evacuation afid establishing plant control outside the control room is (01-for Unit 1, 02-for Unit 2) OHP 4025.001.001, 'Emergency Remote Shutdown".
TERMINATION/RECOVERY CRITERIA Control of the plant has been reestablished from the control room.
DEVIATION FROM NUMARC: None
..1
Reference PMP-2080.EPP.101 Rev. 4 Page 52 of 112 Emergency CLASSIFICATION T
Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 -112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H-3: SITE AREA EMERGENCY - CONTROL ROOM EVACUATION INITIATING CONDIITON Control room evacuation has been initiated and plant CONTROL cannot be established.
MODE APPLICABILITY All EAL THRESHOLD VALUE The following conditions exist:
- 1.
Control Room evacuation has been initiated.
-AND-
- 2.
CONTROL of any one of the following processes is not established within 15 minutes:
Reactivity RCS inventory RCS temperature SG heat sink BASIS (References)
CONTROL - Placing all local control switches in local control necessary for operation from remote panel and the shift supervisor has determined that the systems for controlling reactivity, RCS inventory, RCS temperature, and the heat sink functions have been established.
Cook Nuclear Plant has separate control rooms for each unit. The Cook Nuclear Plant procedure governing control room evacuation and establishing plant control outside the control room is (01-for Unit 1, 02-for Unit 2) OHP 4025.001.001, Emergency Remote Shutdown",.
- The 15 minute time for CONTROL being established outside of the control room is taken from Revision 2 of NUMARC/NESP 007.
TERMINIATION/RECOVERY CRITERIA-Control of the plant has been reestablished from the control room.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101 Rev. 4 l
Page 53 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
.3.1-(Commitment: 6489) 23 112
- The inability to establish control of RCS inventory, RCS temperature, reactivity and heat sink functions outside of the control room within 15 minutes requires the declaration of a site area emergency.
I
. A -..
I. w
Reference PMP-2080.EPP.101
,Rev. 4 T-Page 54 of 112 Emergency CLASSIFICATION 1-Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 -112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H4: UNUSUAL EVENT - FIRE INITIATING CONDITION Fire in protected area boundary not extinguished within 15 minutes of detection.
MODE APPLICABILITY All EAL THRESHOLD VALUE Fire within the protected area boundary not extinguished within 15 minutes of detection.
BASIS (References)
The purpose of this EAL is to address only fires which are potentially significant precursors to safety system damage. This excludes such items as fires within office buildings, waste basket fires, and other small fires of no consequence. This EAL applies to buildings and areas contiguous to plant vital areas or other significant buildings and areas. The intent is not to include buildings (or warehouses) that are not contiguous or immediately adjacent to areas where safety system performance would be adversely affected or there could be an uncontrolled release of radioactive material.
Areas of concern at the Cook Nuclear Plant for this initiating condition (H-i: UNUSUAL EVENT) include the protected area. The radioactive material building (RMB) is not included since it is outside the protected area, and not required to safely shutdown the plant. In the unlikely event that a fire were to occur where 100% of the RMB contained radioactive material were released, it could result in an offsite dose of 2.5 rem. If a fire or explosion were to occur that could result in an offsite radioactive release, the SEC would initially declare as unusual event under the classification requirements of H-S, SEC judgment. The classification could be escalated in accordance with the requirement of R-1, if field measurements show large offsite releases have actually occurred.
TERMINIATIONRECO VERY CRITERIA Fire Extinguished.
DEVIATION FROM NUMARC: None
-Rv
-F ag 55o Reference PMP-2080.EPP.101 Rev. 4 Page 55 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
ttachment 3
)
Basis (Commitment: 6489)23-112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H14:; ALERT - FIRE OR EXPLOSION AFFECTING OPERABILITY OF SAFETY EQUIPMENT INITIATING CONDITION Fire or explosion affecting OPERABILITY of plant safety systems required to establish or maintain safe shutdown.
MODE APPLICABILITY All EAL THRESHOLD VALUE
- 1.
Fire or explosion that affects the OPERABILITY of systems required for the current operating mode OR for safe shutdown.
-OR-
- 2.
Fire or explosion that causes visible damage to any of the following structures: containments, auxiliary buildings, essential service water system enclosures, auxiliary feedwater pump rooms, refueling water storage tank, or condensate storage tank.
BASIS (References)
EXPLOSION - A rapid, violent, uncontained combustion or catastrophic failure of pressurized equipment that potentially imparts significant energy to nearby structures or equipment.
If a fire affects operability of only one of two redundant systems, then this EAL is not applicable.
The purpose of this EAL is to address only fires which are potentially significant precursors to safety system damage. This excludes such items as fires within office buildings, waste basket fires, and other small fires of no consequence. This EAL applies to building and areas contiguous to plant vital areas or other significant buildings and areas. The intent is not to include buildings (or warehouses) that are not contiguous or immediately adjacent to areas where the safety system performance would be adversely affected.
Only explosions of significant force to cause damage (deformation, scorching) to structures or equipment required for safe operation should be considered.
TERMINIATION/RECOVERY CRITERIA Plant capability to operate safety no longer affected by the event.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101 Rev. 4 Page 56 of 112 Emergency CLASSIFICATION - f Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 -112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H-5: UNUSUAL EVENT - TOXIC OR FLAMMABLE GASES INITIATING CONDITION Release of toxic or flammable gases deemed detrimental to safe operation of the plant.
MODE APPLICABILITY All NOTE:
1 or 2 OHP-4021-028-014, Operation of the Control Room Air Conditioning and Pressurization/Cleanup Filter System contains instructions for control room isolation in the event of a toxic gas release.
EAL THRESHOLD VALUE
- 1.
Release of toxic or flammable gases within or near site boundary that may affect normal operation of the plant.
-OR-
- 2.
Report by local, county, or state officials of potential evacuation of site personnel based on offsite event.
BASIS (References)
TOXIC - Exposure to the worker in excess of limits specified in 29 CFR 1910.1000. in practice, this should be considered for concentrations which are capable of incapacitating the worker.
This initiating condition is based on release in concentrations within the site boundary that will affect the health and safety of plant personnel or affect safe operation of the plant.
The potential for the degradation in the level of safety of the plant through the affect of toxic OR flammable gas on the health of personnel or operation of the plant is to be considered for declaration of the UNUSUAL EVENT. The source of the toxic or flammable gas could be from inside or outside the site.
Although carbon dioxide (C02) concentrations can be lethal, it is not considered a toxic gas for the purpose of classification unless access is required and cannot be made in an area where equipment needed for the safe shutdown of the plant is maintained.
TERMINIATION/RECOVERY CRITERIA
Reference PMP-2080.EPP.101 Rev. 4 Page 57 of 112 Emergency CLASSIFICATION Attachmnent 3 l
- - Basis For Emergency Action Levels Pages:
(Commitment: 6489)23-112
- The release of toxic material is terminated and the operational impact of the release has been eliminated.
DEVIATION FROM NUMARC: None a
S f
g s
t
\\.
- 0
, f
?
f
Reference PMP-2080.EPP.101 Rev. 4 Page 58 of 112 Emergency CLASSIVICATION Basis For Emergency Action Levels Pages:
Attachmn 3 (Commitment: 6489) 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H-5: ALERT - TOXIC OR FLAMMABLE GASES IN1TIATING CONDITION Release of toxic of flammable gases within a facility, structure which jeopardizes operation of systems required to maintain safe operations or to establish or maintain cold shutdown.
MODE APPLICABILITY All NOTE:
1 or 2 OHP-4021-028-014, Operation of the Control Room Air Conditioning and Pressurization/Cleanup Filter System contains instructions for control room isolation in the event of a toxic gas release.
I EAL THRESHOLD VALUE
- 1.
Report or detection of toxic gases within a facility structure in concentrations that will be life threatening to plant personnel.
-OR-
- 2.
Report or detection of flammable gases within a facility structure in concentrations that will affect the safe operation of the plant.
BASIS (References)
TOXIC - Exposure to the worker in excess of limits specified in 29 CFR 1910.1000. In practice, this should be considered for concentrations which are capable of incapacitating the worker.
This EAL is based on gases that have entered plant structures that will affect the safe operation of the plant. These structures include buildings and areas contiguous to plant vital areas and other significant buildings or area. The intent of this EAL is not to include buildings that are not contiguous or immediately adjacent to plant vital areas. The source of the toxic or flammable gas could be from inside or outside the site.
The source of the release is not of immediate concern for these threshold values. The concern is for the health and safety of plant personnel and their ability to maintain the plant in a safe operating
-condition.
-This EAL is reached whenever the shift manager determines that protective gear is required to be worn
-by plant personnel required to safely operate the unit.
Reference.
PMP-2080.EPP. 101 Rev. 4 Page 59 of 112 Emergency CLASSIfICATION Basis For Emergency Action Levels Pages:
2-1 (Commitment: 6489) 23 112 Although carbon dioxide (C02) concentrations can be lethal, it is not considered a toxic gas for the purpose of classification unless access is required and cannot be made in an area where equipment needed for the safe shutdown of the plant is maintained.
TERMINIATION/RECOVERY CRITERIA Plant operations are no longer affected.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101 Rev. 4 Page 60 of 112
'Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION N-1 to N-7:
UNUSUAL EVENT - NATURAL OR DESTRUCTIVE PHENOMENA INSIDE THE PROTECTED AREA INITIATING CONDITION Natural or destructive phenomena inside protected area.
MODE APPLICABILITY All EAL THRESHOLD VALUE
- 1.
CONFIRMED seismic event as indicated by seismic instrument activation or based on ground motion felt at the nuclear plant and recognized as an earthquake based on consensus of control room operators on duty at the time.
-OR-
- 2.
Report of a tornado strike within the protected area.
-OR-
- 3.
Vehicle collision affecting structures or systems within the protected area.
-OR-
- 4.
Main turbine rotating component failure causing visible damage or damage to the generator seals.
-OR-
- 5.
Report by plant personnel of an unanticipated explosion within the protected area boundary resulting in visible damage to permanent structures or equipment.
BASIS (References)
These threshold values are natural or destructive phenomena which represent potential degradation of the level of safety of the plant. The affects of the phenomena should also be evaluated on a system or component basis in relation to the Technical Specifications and evaluated for further classification via either site emergency coordinator (SEC) judgement or plant procedures as appropriate.
Threshold Value 1 - Seismic events at the lowest instrument activation, 0.02g (or based on ground motion felt at the nuclear plant and recognized as an earthquake based on consensus of control room operators on duty at the time) may cause damage to systems and represent a potential degradation of the level of safety of the plant. A confirnation call to the National Earthquake Center will confirm that an earthquake has occurred and mayprovide an estimate of the magnitude of the earthquake'in the vicinity of Cook Nuclear Plant. Further information regarding anticipated actions may be found in plant procedures OHP 4022.001.007, "Earthquake.
Reference PMP-2080.EPP.101
-Rev. 4
-T Page 61 of 112 Emergency CLASSIFICATION
, Basis For Emergency-Action Levels Pages:
(Commitment: 6489) 23 -112 A call to one of the following may be used to verify/confirm a seismic event. National Earthquake Center (phone number (303) 273-8500 or 1-800-525-7848), Local television stations, or, University monitoring stations.
Threshold Value 2 - Any report that a tornado has touched down within the protected area.
Threshold Value 3 - A collision of any vehicle on land, from the air, or on water (plane, train, barge, etc.) which affects structures or equipment within the protected area may potentially damage plant structures containing functions and systems required for safe shutdown of the plant. If the crash is confirmed to affect a plant vital area, the event may be escalated to Alert.
Threshold Value 4 - Failure of the rotating components has the potential for leakage of flammable fluids (oil and hydrogen) into the turbine building.
Threshold Value 5 - Only those explosions of sufficient force to damage permanent structures or equipment within the protected area should be considered. As used here an explosion is a rapid, violent, unconfined combustion, or a catastrophic failure of pressurized equipment, that potentially imparts significant energy to near-by structures and materials. No attempt is made in the EAL to assess the actual magnitude of the damage. The occurrence of the explosion with reports of evidence of damage (e.g., deformation, scorching) is sufficient for declaration. The SEC also needs to consider any security aspects of the explosion, if applicable.
TERMINIATION/RECOVERY CRITERIA No further hazard exists, and damage assessment is complete, and termination is allowed in accordance with the requirements of the event tennination procedure.
DEVIATION FROM NUMARC:
A separate ECC category name was established for these "Natural or Destructive Phenomena". They are included in the Hazards And Other Conditions' Category in NUMARC/NESP 007.
Reference' PMP-2080.EPP.11 Rev. 4 Page 62 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
23-112 I
~~(Commiten:6489) 2-12 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION N-1 to N-7: ALERT - NATURAL OR DESTRUCTIVE PHENOMENA INSIDE A VITAL AREA INITIATING CONDITION Natural or destructive phenomena inside vital areas.
MODE APPLICABILITY All EAL THRESHOLD VALUE
- 1.
CONFIRMED seismic event as indicated by seismic instrument activation or based on ground motion felt at the nuclear plant and recognized as an earthquake based on consensus of control room operators on duty at the time AND which causes visible major damage to structures, systems, and components in the vital area or causes a plant trip to occur.
-OR-
- 2.
Report of a tornado strike in a plant vital area or SUSTAINED high wind (> 15 min.) greater than 90 miles per hour.
-OR-
- 3.
Report of visible structural damage to a structure containing systems required to establish and maintain cold shutdown.
-OR-
- 4.
Vehicle collision affecting a vital area.
-OR-
- 5.
Turbine failure generated missiles penetrating a vital area.
-OR-
- 6.
Flooding in a vital area affecting safety related equipment.
BASIS (References)
These threshold values are natural or destructive phenomena which represent actual or potential substantial degradation of the level of safety of the plant. The affects of the phenomena should also be evaluated on a system or component basis in relation to the Technical Specifications and evaluated for further classification via either Site Emergency Coordinator (SEC) judgement or plant procedures as appropriate.
Threshold Value 1 - Seismic events at the lowest instrument activation (0.02g ground acceleration) or ground motion felt at the nuclear plant and recognized as an earthquake based on consensus.of control room operators.on duty at the time. The effect of the earthquake has significantly affected plant operations (up to and including manual or automatic plant trip) or has caused visible damage that has the potentia for major degradation of systems required to maintain the plant in a safe'shutdown condition. A call to the National Earthquake Center will confirm that an earthquake has occurred and may provide an estimate of the magnitude of the earthquake in the vicinity of the Cook Nuclear Plant.
Reference PMP-2080.EPP.101 Rev. 4 Page 63 of 112 Emergency CLASSIFICATION
-]
Basis For' Emergency Action Levels -
Pages:
(Commitment: 6489) 23 -112 Operator walkdowns of plant systems, structures and components will be performed to assess potential damage levels.
A call to one of the following maybe used to verify/confirm a seismic event: National Earthquake Center (phone number (303) 273-8500 or 1-800-525-7848), local television stations, or university monitoring stations.
Threshold Value 2 - A tornado strike must include an affect on systems or components that affects the operability or integrity of the system or structure within a vital area. The threshold value of 90 mph is the FSAR design basis wind load.
Threshold Value 3 - Should be used in conjunction with investigation of threshold values 1 and 2, or on a stand alone basis. A detailed description or assessment of damage is not intended to meet the intent of this threshold value. The list of critical structures is the same as that included under H4 ALERT (containments, auxiliary buildings, ESW system enclosures, auxiliary feedwater pump rooms, refueling water storage tank, condensate storage tank).
Threshold Value 4 - A collision by any vehicle on land, from the air, or on water (plane, train, barge, etc.) which affects structures or equipment within a vital area.
Threshold Value 5 - This threshold value addresses the threat to safety equipment imposed by missiles generated by main turbine rotating component failures. This includes all areas classified as vital areas of the plant.
Threshold Value 6 - Flooding in vital areas which affect OPERABILITY of safety related systems or components. The source of the flooding need not be known.
The word "OPERABLITY" refers to the definition in the Technical Specifications where required redundant safety equipment will be made inoperable. The only types of floods anticipated to trigger this threshold are major catastrophic pipe ruptures in the plant that have not been previously evaluated or floods caused by severe external phenomena such as seiches.
TERMIATION/RECOVERY CRITERIA No further hazard exists, damage assessment is complete, and termination is allowed in accordance with the requirements of the event termination procedure.
DEVIATION FROM NUMARC:
A separate ECC category name was established for these "Natural or Destructive Phenomena." They
-are included in the "Hazards And Other Conditions" category in NUMARC/NESP 007.
.:The EAL for earthquakes does not include a real time seismic instrumentation reading. Cook Nuclear Plant seismic instrumentation does not provide indication of the level of earthquake as an Operations Basis Earthquake (OBE) or Design Basis Earthquake (DBE). This EAL is written using the operator
'assessment method specified in NUMARC/NESP 007.
Reference-PMP-2080.EPP.101 Rev. 4 Page 64 of 112 Emergency CLASSIFICATION Attachment 3
Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 -112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION R-1: UNUSUAL EVENT - RADIOACTIVE EFFLUENT RELEASE INITIATING CONDITION Unplanned release of gaseous or liquid radioactivity, to the environment that exceeds two times the ODCM release limits for 60 minutes or longer.
MODE APPLICABILITY All NOTE:
The term "one or more of the following monitors" in the EAL means that the total of all monitors is to be considered when classifying an event.
[Commitment 5116]
EAL THRESHOLD VALUE
- 1.
A valid reading on one or more of the following monitors that exceeds 2 times the high alarm setpoint for 60 minutes of longer.
VRS-1500/2500 (Noble Gas)
SRA-180012800 (Noble Gas)
SRA-1900/2900 (Noble Gas)
R-20 R-28
-OR-
- 2.
A VALID radiation monitor reading 2 times the high alarm setpoint for any monitored release pathway for > 60 minutes.
-OR-
- 3.
Confirmed sample analyses for gaseous or liquid releases indicates concentrations or release rates exceeding 2 times the ODCM maximum instantaneous release limit for > 60 minutes.
BASIS (References)
VALID -'Readings are assumed valid unless circumstances cause the reading to be suspect.
Verification can be obtained by a) an instrument channel check, or b) indications on related or redundant indicators, or c) by direct observation by plant personnel. Implicit in this definition is the need for timely assessment, i.e., within 15 minutes.
Reference I
PMP-2080.EPP.101 l
Rev. 4 l
Page 65 of 112 Emergency CLASSIFICATION l
Basis For Emergency Action Levels Pages:
Attachmen 3 (Commitment: 6489) 23 - 112 UNPLANNED - Means the release occurred without a discharge permit or the conditions specified on the discharge permit have been exceeded.
Environmental release limits for effluent radiation monitor alarms are calculated using methods specified in the offsite dose calculation manual (ODCM). An UNPLANNED release in excess of two times the ODCM release limit for 60 minutes, or longer, represents an uncontrolled situation, and hence, a potential degradation in the level of safety. Although the final integrated dose is very low in the Unusual Event emergency class, the degradation in plant control implied by the fact that the release cannot be terminated in 60 minutes is the primary concern.
Declaration of an Unusual Event should be made as soon as it is determined that the release duration has or will likely exceed 60 minutes. A dose assessment should be performed to ensure that a higher classification is not warranted. If the monitor reading(s) is sustained for longer than 60 minutes and the required assessments cannot be completed within this period, then the declaration must be made based on the valid reading.
Radioactive gaseous release pathways are monitored by either the unit vent monitor (VRS-150012500),
the gland steam condenser exhaust effluent monitors (SRA-1800/2800), the steam jet air ejector vent effluent monitors (SRA-1900/2900), or the steam generator relief monitors. The first three monitors are included in threshold 1. Steam generator relief monitors are excluded. The reason is that radioactive gas release via the steam generator PORVs and safety valves is believed to be a pathway that could not, under normal operating conditions, lead to release of radioactive gases to the environment in sufficient amounts so as to cause exceeding the technical specification limits. The steam generator relief monitors are included as an EAL threshold in the site area emergency classification for abnormal release of radioactive materials.
With the exception of possible releases from the essential water system (monitored by R-20 and R-28) release of radioactive liquids to the environment are planned and controlled. Before a batch of radioactive liquid is released to the environment, the sample is analyzed. If the radioactivity of the sample is within acceptable limits, the liquid will be released, monitored, and recorded. The alarm on the monitor is set in accordance with ODCM limits. To cover the potential that something may go wrong with the liquid release process, threshold 2 addresses any valid radiation monitor reading.
TERMINIATION/RECOVERY CRITERIA The source of the release is determined and isolated (terminated). Environmental field team samples have been taken and the environmental impact assessment is in progress.
DEVIATION FROM NUMARC:
Example EALs from NUMARC/NESP 007 numbers 3 and 4 (i.e., perimeter radiation monitoring and real time dose assessment) were not used because Cook Nuclear Plant does not have those capabilities.
The initiating condition is stated in terms of exceeding ODCM limits rather than exceeding radiological technical specifications.
Reference PMP-2080.EPP.101 Rev. 4 l-Page 66 of 112 Emergency CLASSIFICATION
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(Commitment: 6489)23-112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION R-1: ALERT - RADIOACTIVE EFFLUENT RELEASE INITIATING CONDITION Any unplanned release of gaseous or liquid radioactivity to the environment, greater than 200 times ODCM release limits, which lasts for 15 minutes or longer.
MODE APPLICABILITY All NOTE:
The term "one or more of the following monitors" in the EAL means that the total of all monitors is to be considered when classifying an event.
[Commitment 5116]
EAL THRESHOLD VALUE
- 1.
A valid reading on one or more of the following monitors which is greater than 200 times high alarm setpoint for > 15 minutes.
VRS-1500/2500 (Noble Gas)
SRA-1800/2800 (Noble Gas)
SRA-1900/2900 (Noble Gas)
R-20 R-28
-OR-
- 2.
A valid radiation monitor reading indicating 200 times the high alarm setpoint for any monitored release pathway for > 15 minutes.
-OR-
- 3.
Confirmed sample analyses for gaseous or liquid releases indicates concentrations or release rates exceeding 200 times the ODCM maximum instantaneous release limit for > 15 minutes.
BASIS (References)
VALID - Readings are assumed valid unless circumstances cause the reading to be suspect.
Verification can be obtained by a) an instrument channel check or b) indications on related or redundant indicators, or c) by direct observation by plant personnel. Implicit in this definition is the need for timely assessment, i.e., within 15 minutes.
UNPLANNED - Means the release occurred without a discharge permit or the conditions specified on the discharge permit have been exceeded.
Reference PMP-2080.EPP. 101 Rev. 4 l
Page 67 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels, Pages:
I (Commitment: 6489) 23 - 112 This event escalates from the Unusual Event by escalating the magnitude of the release by a factor of 100. Prorating the 500 mR/yr criterion for both time (8766 hr/yr and the 200 multiplier, the associated site boundary dose rate would be 10 mR/hr. The required release duration was reduced to 15 minutes in recognition of the increased severity.
Declaration of an Alert should be made as soon as it is determined that the release duration has or will likely exceed 15 minutes. A dose assessment should be performed to ensure that a higher classification is not warranted. If the monitor reading(s) is sustained for longer than 15 minutes and the required assessments cannot be completed within this period, then the declaration must be made based on the valid reading.
Further information on the basis of EAL threshold 1 cited above may be found in the basis document for the Unusual Event associated with R-1.
TERMNIATION/RECOVERY CRITERIA The source of the release is determined and isolated (terminated). Environmental field team samples have been taken and the environmental impact assessment is in progress.
DEVIATION FROM NUMARC:
Example EALs from NUMARC/NESP 007 numbers 3 and 4 (i.e., perimeter radiation monitoring and real time dose assessment) were not used because Cook Nuclear Plant does not have those capabilities.
The initiating condition is stated in terms of exceeding ODCM limits rather than exceeding radiological technical specifications.
Reference H
HHHHHHHHHHHHHHH H
HHHHHHH HHHHHHHHHHHHHHHHHH l
Rev. 4 lPage 68 of 112
~~Emergency CLASSIFICATION Attachmnt 3 l
Basis.For Emergency Action Levels l
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I
~(Commitment: 6489) 23 - 112-ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION R-1: SITE AREA EMERGENCY - RADIOACTIVE EFFLUENT RELEASE INITIATING CONDITION Site boundary dose resulting from an actual or imminent release of gaseous radioactivity exceeds 100 mrem TEDE or 500 mrem thyroid CDE for the actual or projected duration of the release.
MODE APPLICABILITY All NOTE:
The term "one or more of the following monitors" in the EAL means that the total of all monitors is to be considered when classifying an event.
[Commitment 5116]
EAL THRESHOLD VALUE
- 1.
Field survey results indicate site boundary dose rates exceeding 100 mR/hr -y or a CDE thyroid exceeding 500 mrem for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of inhalation at the site boundary.
-OR-
- 2.
A valid dose assessment indicates greater than 100 mrem TEDE or 500 mrem CDE thyroid at the site boundary.
-OR-
- 3.
A valid reading on one or more of the following monitors (noble gas channels) that exceeds or is expected to exceed the value shown indicates that the release may have exceeded the above criterion and indicates the need to assess the release in accordance with appropriate plant procedures.
VRS-1500/2500 > 1.07 E-1 gci/cc (Unit Vent)
VRS-180012800 > 7.90 EOpIci/cc (Steam Packing Exhauster)
SRA-1900/2900 > 1.95 E+3 Itci/cc (Air Ejector)
MRA-1600/2600 > 1.00 E+2 gLci/cc (SG PORV) 1700/2700 NOTE: The above monitor readings are based on an assumed hour event duration If the monitor reading(s) is sustained for longer than 15 minutes and the required assessments cannot be completed within this period, then the declaration must be based on the valid monitor reading. The monitor, ranges should be selected in accordance with guidance in PMP 2081 EPP. 106.
BASIS (References)
VALID - Readings are assumed valid unless circumstances cause the reading to be suspect. Radiation readings can be confirmed by redundant instrumentation, local readings, or grab samples.
Reference l
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Rev. 4 lPage 69 of 112 Emergenc CLASSIFICATION Attachrent 3
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Basis For Emergency Action Levels l
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~(Commitment: 6489) 23 -1 The 100 mrem integrated dose in this initiating condition, is based on the 10 CFR 20 annual average population exposure. This value also provides a desirable gradient (one order of magnitude) between the Alert, Site Area Emergency and General Emergency classes. The 500 mrem CDE thyroid dose is consistent with the 1.5 ratio of the EPA Protective Action Guidelines for Total Effective Dose Equivalent and Committed Dose Equivalent to the thyroid.
A release duration of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is assumed. For analysis of longer or shorter duration releases, the 100 mrem/hr TEDE and 500 mrem/hr CDE thyroid dose rates should be adjusted accordingly.
The releases on the monitors in threshold #3 above are calculated using the Cook Nuclear Plant Dose Assessment Program (DAP) and are based on average plant meteorology, the assumption that the release is one hour duration, and a site boundary dose of 100 mrem/hour. Details may be found in AEP Radiological Support Section calculation RS-C-283. Analysis of gaseous releases shorter or longer duration or different meteorologic conditions is performed during the dose assessment. If the monitor release is sustained for greater than 15 minutes and the dose assessment cannot be completed in this time period, then emergency classification will be solely on whether the monitor readings are valid and whether they exceed the values cited in threshold #3 above.
TERMINIATIONIRECOVERY CRITERIA The source of the release has been determined and isolated (terminated) Environmental field samples have been taken and environmental impact assessment is in progress.
DEVIATION FROM NUMARC:
NUMARC/NESP 007 example EAL number 2 (i.e., perimeter radiation monitoring system) was not used because Cook Nuclear Plant does not have that capability.
Reference PMP-2080.EPP.101 Rev. 4 Page 70 of 112 Emergency CLASSIVICATION
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(Commitment: 6489) 23 -112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION R-1: GENERAL EMERGENCY - RADIOACTIVE EFFLUENT RELEASE INITIATING CONDITION Site boundary dose resulting from an actual or imminent release of gaseous radioactivity exceeds 1000 mrem TEDE or 5000 mrem CDE thyroid for the actual or projected duration of the release.
MODE APPLICABILITY All NOTE:
The term "one or more of the following monitors" in the EAL means that the total of all monitors is to be considered when classifying an event.
[Commitment 51161 EAL THRESHOLD VALUE
- 1.
Field survey results indicate site boundary dose rates exceeding 1000 mRlhr y
- y or a CDE thyroid exceeding 5000 mrem for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of inhalation at the site boundary.
-OR-
- 2.
A valid dose assessment indicates greater than 1000 mrem TEDE or 5000 mrem CDE thyroid at the site boundary.
-OR-
- 3.
A valid reading on one or more of the following monitors (noble gas channels) that exceeds or is expected to exceed the value shown indicates that the release may have exceeded the above criterion and indicates the need to assess the release in accordance with the appropriate plant procedures.
VRS-1500/2500 > 1.07 E+0 pci/cc (Unit Vent)
SRA-1800/2800 > 1.57 E+2 pci/cc (Steam Packing Exhauster)
SRA-1900/2900 > 5.78 E+3 pci/cc (Air Ejector)
NOTE: The above monitor readings are based on an assumed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> event duration. If the monitor reading(s) is sustained for longer than 15 minutes and the required assessments cannot be completed within this period, then the declaration must be based on the valid monitor reading. The monitor ranges should be selected in accordance with guidance in PMP 2081 EPP. 106.
BASIS (References)
VALID - Readings are assumed valid unless circumstances cause the reading to be suspect.
Verification can be obtained by a) an instrument hannel check, or b) indications on related or redundant indicators, or c) by direct observation by plant personnel. Implicit in this definition is the need for timely assessment, i.e., within 15 minutes.
Reference PMP-2080.EPP.101 Rev. 4 T-Page 71 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 - 112 The 1000 mrem TEDE and 5000 mrem CDE thyroid values are based on the EPA protective action guidance which indicates that public protective actions are indicated if those values are exceeded. This is consistent with the emergency class description for a General Emergency.
A release duration of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has been assumed for analysis if longer or shorter duration, releases, the 1000 mrem/hr TEDE and 5000 mrem/hr thyroid CDE dose rates should be adjusted accordingly.
The release on the monitors in threshold #3 above are calculated using the Cook Nuclear Plant Dose Assessment Program (DAP) and are based on average plant meteorology, the assumption that the release is one hour duration, and a site boundary dose of 1000 mrem. Details may be found in AEP Radiological Support Section calculation RS-C-283. Analysis of gaseous releases shorter or longer duration or different meteorologic conditions is performed during the dose assessment. If the monitor release is sustained for greater than 15 minutes and the dose assessment cannot be completed in this time period, then emergency classification will be solely on whether the monitor readings are valid and whether they exceed the values cited in threshold #3 above.
TERMINIATION/RECOVERY CRITERIA The source of the release has been determined and isolated (terminated). Environmental field samples have been taken and environmental impact assessment is in progress.
DEVIATION FROM NUMARC:
NUMARC/NESP 007 example EAL number 2 (i.e., perimeter radiation monitoring system) was not used because Cook Nuclear Plant does not have that capability.
Reference PMP-2080.EPP.101 Rev. 4 Page 72 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION R-2: UNUSUAL EVENT - RISING IN-PLANT RADIATION LEVELS INITIATING CONDITION Unexpected higher in plant radiation levels.l MODE APPLICABILITY All EAL THRESHOLD VALUE A valid unexpected reading on an area monitor 1000 times higher than the 24-hour average.
BASIS (References)
VALID - Readings are assumed valid unless circumstances cause the reading to be suspect:
Verification can be obtained by a) an instrument channel check, or b) indications on related or redundant indicators, or c) by direct observation by plant personnel. Implicit in this definition is the need for timely assessment, i.e., within 15 minutes.
This event has a long lead time relative to potential radiological release outside the site boundary, thus impact to public health and safety is very low. It represents a degradation in the control of radioactive material, and represents a potential degradation in the level of safety of the plant.
TERMINIATION/RECOVERY CRITERIA The source of the higher radiation levels has been determined and levels have decreased to below the threshold values. Radiological controls have been implemented and are effective.
DEVIATION FROM NUMARC:
NUMARC/NESP 007 AU2 example EALs numbers 1 and 2 are included under R-3, Unusual Event, "Loss of Water Level in Any Area Holding Irradiated Fuel." Example EAL number 3 was not used because Cook Nuclear plant does not have a dry storage area for irradiated spend fuel.
Reference i
PMP-2080.EPP.101 Rev. 4 Page 73 of 112 Emergency CLASSIFICATION 1
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Attachmen 3 '
(Commitment: 6489) 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION R-2: ALERT - RISING IN-PLANT RADIATION LEVELS INITIATING CONDITION Release of radioactive material or higher in-plant radiation levels within the facility that impede operation of systems required to maintain safe operation or to establish or maintain cold shutdown.
MODE APPLICABILITY All EAL THRESHOLD VALUE
- 1.
Unexpected radiation levels > 15 mRlhr in any of the following areas.
Ul Control Room U2 Control Room Central Alarm Station
-OR-
- 2.
Radiation level of > 100 mR/hr at any station required by plant procedure OHP 4025.001.001, "Emergency Remote Shutdown", and associated subtier procedures.
BASIS (References)
This IC addresses higher radiation levels that impede necessary access to operating stations, or other areas containing equipment that must be operated manually, in order to maintain safe operation or performing a safe shutdown. It is inpaired ability to operate the plant that results in the actual or potential substantial degradation of the level of safety of the plant. The cause and/or magnitude of the higher in radiation levels is not a concern of this IC. The SEC must consider the source or cause of the higher levels and determine if any other ICs may be involved. For example, a dose rate of 15 mR/hr in the'control room may be a problem in itself. However, the higher reading may also be indicative of high dose rates in the containment due to LOCA. In this latter case, an SAE or GE may be indicated based on the fission product barrier matrix ICs.
These EALs could result in declaration of an Alert at one unit due to a radioactivity release or radiation shine resulting from a major accident at the other unit. This is appropriate if the higher levels impair operations at the operating unit. This IC is not meant to apply to higher levels in the containment dome radiation. monitor as these are events which are addressed in the-fission product barrier matrix iCs, nor
..is it intended to apply to anticipated temporary' higher levels due to planned events (e.g., incore detector movement, radwaste container movement, depleted resin transfer, etc.).
Procedure OHP 4025.001.001 refers to the emergency remote shutdown procedures for the'Donald C.
Cook Nuclear Plant. The procedure provides an alternate method of achieving safe shutdown with and
Reference PMP-2080.EPP. 101 Rev. 4 Page 74 of 112 Emergency CLASSIFICATION l
7 Basis For Emergency Action Levels Pages:
-1 (Commitment: 6489) 23 - 112 without offsite power available in the event that control of plant equipment is not available from the control room or hot shutdown panel. The procedure gives priority to achieving reactor and turbine trip, establishing auxiliary feedwater for heat removal, and establishing charging for the reactor coolant pump seal injection and reactivity control. Special consideration is given to establishing primary and secondary system isolation and preventing fire induced spurious operation of plant equipment. In event that CVCS, AFW, CCW, and ESW crossties are utilized to achieve safe shutdown, special consideration is given to maintaining the opposite unit in safe configuration.
Threshold 2 refers to the specific locations throughout the plant that are necessary to man to perform the functions cited in procedure OHP 4025.001.001, and related subtier procedures.
TERMINIATION/RECOVERY CRITERIA The source of the higher radiation levels is determined and levels have dropped to below their threshold values. Radiological controls have been implemented and are effective.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101 Rev. 4 lPage 75 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
23-112 (Commitment: 6489) 2 1
ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION R-3:
UNUSUAL EVENT - LOSS OF WATER LEVEL IN ANY AREA HOLDING IRRADIATED FUEL INITIATING CONDITION An UNCONTROLLED water level drop in the reactor refueling cavity, the spent fuel pool, and/or the fuel transfer canal with all irradiated fuel assemblies covered by water.
MODE APPLICABILITY All EAL THRESHOLD VALUE
- 1.
Inability to maintain water level in the spent fuel pool and/or transfer canal at > 643' 4" with irradiated fuel present.
-OR-
- 2.
Inability to maintain refueling cavity level > 643' 4" with irradiated fuel in containment.
BASIS (References)
VALID - Readings are assumed valid unless circumstances cause the reading to be suspect.
Verification can be obtained by a) an instrument channel check, or b) indications or related or redundant indicators, or c) by direct observation by plant personnel. Implicit in this definition is the need for timely assessment, i.e., within 15 minutes.
UNCONTROLLED - A change that is not the result of a planned evolution.
The above EALs indicate events which have long lead times relative to potential for radiological release outside the site boundary, thus impact to public health and safety is very low. Classification as an Unusual Event is warranted as a precursor to a more serious event.
The level of 643' 4" refers to the water level that is 23 feet above the top of the spent fuel, the plant technical specification limit. Prior to that water level being reached, the operators will be warned that the level decrease is occurring via the spent fuel pool low level alarm (RLA-500 at 644'9" or 24'-5 1h" above the top of the fuel) and low level alarm (RLA-501 644'-2 1h" or 23'-1 1" above the top of the fuel). Local visual confirmation that the level has dropped below the technical specification limit is possible since much less water than 23 feet is needed for protection of the plant staff from excessive radiological doses. Twenty-three feet of water is required to protect members of the public from the anticipated radiological consequences of a fuel handing accident.
TERMINIATION/RECOVERY CRITERIA The cause of the loss of water inventory is identified and actions to recover water level are successful.
Reference PMP-2080.EPP.101 Rev. 4 Page 76 of 112 Emergency CLASSIFICATION Atachment 3 Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 -112 DEVIATION FROM NUMARC:
NUMARC/NESP 077 AU2 example EAL number 3 (radiation reading for irradiated spent fuel in dry storage) was not included because Cook Nuclear Plant does not have irradiated fuel in dry storage.
Reference PMP-2080.EPP.101 Rev. 4 Page 77 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages: (Commitment: 6489) 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION R-3:
ALERT - LOSS OF WATER LEVEL IN ANY AREA HOLDING IRRADIATED FUEL INITIATING CONDITION Major damage to irradiated fuel or loss of water level that has or will uncover irradiated fuel outside of the Reactor Vessel.
MODE APPLICABILITY All EAL THRESHOLD VALUE
- 1.
Report of visual observation of irradiated fuel uncovered in the spent fuel pool, transfer canal, or refueling cavity.
-OR-
- 2.
An UNPLANNED VALID alarm on one of the following radiation monitors.
VRS - 1101.1201 (Unit 1) (Upper Containment)
VRS - 2101/2201 (Unit 2) (Upper Containment)
R-5 (SFP)
Portable radiation monitors
-OR-
- 3.
Water level < 632'4" in the spent fuel pool, transfer canal or reactor cavity that will result in fuel uncovery.
BASIS (References)
UNPLANNED - Not anticipated as part of a scheduled testing, surveillance, or maintenance activity.
VALID - Readings are assumed valid unless circumstances cause the reading to be suspect.
Verification can be obtained by a) an instrument channel check, or b) indications on related or redundant indicators, or c) by direct observation by plant personnel. Implicit in this definition is the need for timely assessment, i.e., within 15 minutes.
This IC applies to spent fuel requiring water coverage and is not intended to address spent fuel which is licensed for dry storage.
There is time available to take corrective actions, and there is little potential for substantial fuel damage. In addition, NUREG/CR4982 indicates that even if corrective actions are not taken, no prompt fatalities are predicted, and that risk of injury is low. Thus, an Alert classification for this event is appropriate.
632'4" refers to the water level that is 12 feet above the top of the spent fuel pool. Prior to that water level being reached, the operators will be warned that the level drop is occurring via the spent fuel pool
Reference PMP-2080.EPP1O1 Rev. 4 Page 78 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 - 112
- low level alarm (RLA-500 at 644'9" or 24'-5 h" above the top of the fuel) and low level alarm (RLA-501 644'-2 1/2" or 23'-11 " above the top of the fuel). Local visual confirmation that the level has dropped below 632'4" is possible since 12 feet of water provides adequate radiation shielding for staff personnel from excessive radiation doses in the area of the spent fuel pool.
VRS 110111201 and 2101t2202 are the upper containment area radiation monitors, and are set to alarm at 54 mRlhr. R-5 (RCC-330) is a monitor in the spent fuel pool area. R-5 is set to alarm at 15 mRlhr.
In addition to the above radiation monitors, during refueling operations, portable area radiation monitors are located on the manipulator crane inside containment and on the spent fuel bridge crane.
These monitors are set to alarm at radiation levels equal to about twice the background radiation, and thus provide early warning of any fuel uncovery problems.
Due to the potential of high personal radiation exposure, actual observation of an irradiated fuel assembly without benefit of shielding is not considered likely. If (as indicated under threshold #1 above) this should occur, it is appropriate that an ALERT be declared.
TERMINIATION/RECOVERY CRITERIA The cause of the loss of water inventory is identified and actions to recover water level are successful.
Radiological controls have been implemented and are effective.
DEVIATION FROM NUMARC: None S
s- -
=
r::-
A:
I.
Reference PMP-2080.EPP.1O1 l
Rev. 4 Page 79 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pa 23-112 (Commitment: 6489) 2 1
ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-i: ALERT - FAILURE OF REACTOR PROTECTION SYSTEM INITIATING CONDITION Failure of Reactor Protection System (RPS) instrumentation to complete or initiate an automatic reactor trip once an RPS setpoint has been exceeded. A manual reactor trip was successful.
MODE APPLICABILITY 1, 2, and 3 EAL THRESHOLD VALUE An anticipated transient without scram (ATWS) was terminated by a manual reactor trip from the control room.
BASIS (References)
Anticipated Transient Without Scram (ATWS) - An anticipated operational occurrence followed by the failure of the reactor trip portion of the protection system. Anticipated operational occurrences are those occurrences of normal operation which are expected to occur one or more times during the life of the plant and include, but are not limited to, loss of power to all reactor coolant pumps, tripping of the turbine generator set, isolation of the main condenser, and loss of all offsite power.
Reactor Protection System Instrumentation - All equipment associated with the measurement of process variables, and generation and implementation of trip signals.
This condition indicates failure of the automatic reactor protection system to trip the reactor. This condition is more than a potential degradation of a safety system in that a front line automatic protection system did not function in response to a plant transient and thus, plant safety has been compromised, and design limits of the fuel may have been exceeded. An Alert is indicated because conditions exist that lead to potential loss of fuel clad or RCS. Reactor protection system setpoint being exceeded (rather than limiting safety system setpoint being exceeded) is specified here because failure of the automatic protection system is the issue.
A manual reactor trip is any set of actions by the reactor operator(s) in the control room which cause control rods to be rapidly inserted into the core and brings the reactor subcritical (e.g., reactor trip switches). Failure of manual trip would escalate the event to a Site Area Emergency.
TERMINIATION/RECOVERY CRITERLA Hot shutdown conditions established, an investigation as to the cause is in progress, and an assessment of any significant damage to the fuel or RCS has been completed.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101 Rev. 4 Page 80 of 112 Emergency CLASSIFICATION
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(Commitment: 6489) 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION 5-1: SITE AREA EMERGENCY - FAILURE OF REACTOR PROTECTION SYSTEM INITIATING CONDITION Failure of Reactor Protection System (RPS) instrumentation to complete or initiate an automatic reactor trip once an RPS setpoint has been exceeded. A manual reactor trip was NOT successful.
MODE APPLICABILITY 1 and 2 EAL THRESHOLD VALUE An anticipated transient without scram (ATWS) was NOT terminated by a manual reactor trip from the control room.
BASIS (References)
Anticipated Transient Without Scram (ATWS) - An anticipated operational occurrence followed by the failure of the reactor trip portion of the protection system. Anticipated operational occurrences are those occurrences of normal operation which are expected to occur one or more times during the life of the plant and include, but are not limited to, loss of power to all reactor coolant pumps, tripping of the turbine generator set, isolation of the main condenser, and loss of all offsite power.
Reactor Protection System Instrumentation - All equipment associated with the measurement of process variables, and generation and implementation of trip signals.
Automatic and manual trips are not considered successful if action away from the reactor control console was required to trip the reactor.
Under these conditions, the reactor is producing more heat than the maximum decay heat load for which the safety systems are designed. A Site Area Emergency is indicated because conditions exist that lead to imminent loss or potential loss of both fuel clad and RCS. Although this IC may be viewed as redundant to the Fission Product Barrier Degradation IC, its inclusion is necessary to better assure timely recognition and emergency response..
TERMINIATION/RECOVERY CRITERIA Hot shutdown conditions established, an investigation as to the cause is in progress, and as assessment of any significant damage to the fuel or RCS has been completed.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101:
Rev. 4 1 of 1121 Em'ergency CLASSIFICATION Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-I: GENERAL EMERGENCY - FAILURE OF REACTOR PROTECTION SYSTEM INITIATING CONDITION Failure of Reactor Protection System (RPS) to complete an automatic trip and manual trip was NOT successful and there is indication of an extreme challenge to the ability to cool the core.
MODE APPLICABILITY 1 and 2 EAL THRESHOLD VALUE
- 1.
ATSW was NOT terminated by manual reactor trip from the control room.
-AND-
- 2.
Subcriticality AND Core Cooling CSFSTs are RED.
-OR-Subcriticality AND Heat Sink CSFSTs are RED.
BASIS (References)
Anticipated Transient Without Scram (ATWS) - An anticipated operational occurrence followed by the failure of the reactor trip portion of the protection system. Anticipated operational occurrences are those occurrences of normal operation which are expected to occur one or more times during the life of the plant and include, but are not limited to, loss of power to all reactor coolant pumps, tripping of the turbine generator set, isolation of the main condenser, and loss of all offsite power.
Reactor Protection System Instrumerftation - All equipment associated with the measurement of process variables, and generation and implementation of trip signals.
Automatic and manual trips are not considered successful if action away from the reactor control console is required to trip the reactor.
Under the conditions of this IC and its associated EAL, the efforts to bring the reactor subcritical have been unsuccessful and, as a result, the reactor is producing more heat than the maximum decay heat load for which the safety systems were designed. Although there are capabilities away from the reactor control console, such as emergency boration, the continuing temperature rise indicates that these capabilities are not effective. This situation could be a precursor for a core melt sequence.
The extreme challenge to the ability to cool the core is intended to mean that the core exit temperatures are at or approaching 1200'F or that the reactor vessel water level is at approximately three feet and the core exit thermocouples are greater than 7000F. This GE EAL equates to a Core Cooling RED condition.
Reference PMP-2080.EPP.101 Rev. 4 Page 82 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
Another consideration is the inability to initially remove heat during the early stages of this sequence.
If emergency feedwater flow is insufficient to remove the amount of heat required by design from at least one steam generator, an extreme. challenge should be considered to exist. This EAL equates to a Heat Sink RED condition.
In the event either of these challenges exist at a time that the reactor has not been brought below the power associated with the safety system design (5 % power as represented by a RED condition on the subcriticality CSFST), a core melt sequence exists. In this situation, core degradation can occur rapidly. For this reason, the General Emergency declaration is intended to be anticipatory of the fission product barrier matrix declaration to permit maximum offsite intervention time.
TERMETIATION/RECOVERY CRITERIA Hot shutdown conditions established, an investigation as to the cause is in progress, and an assessment of any significant damage to the fuel or RCS has been completed.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101:
Rev. 4 Page 83 of 112 Emergency CLASSIFICATION 7 7 Basis For Emergency Action Levels Pages:
(Commitnent: 6489) 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-2: UNUSUAL EVENT - LOSS OF AC POWER INITIATING CONDITION Loss of all offsite power to essential buses for greater than 15 minutes.
MODE APPLICABILITY 1,2,3,4 EAL THRESHOLD VALUE
- 1.
ALL of the OFFSITE power sources indicated by the following list of transformers are LOST to the T-buses for > 15 minutes. NOTE: Evaluate each units' power supply separately.
- a.
Normal Auxiliary Power Source (Auxiliary Transformer)
- b.
Preferred Offsite Power Sources (Reserve Transformer)
TR OAB /TR 201AB TR 1CD TR 201CD
- c.
Emergency Offsite Power Source (69Kv Transformer)
T-12-EP-1
- 2.
At least two diesel generators per unit are supplying power to the emergency buses.
BASIS (References)
Prolonged loss of AC power reduces required redundancy and potentially degrades the level of safety of the plant by rendering the plant more vulnerable to a complete Loss of AC Power (Station Blackout). Fifteen minutes was selected as a threshold to exclude transient or momentary power losses.
Offsite power can be supplied via the 69Kv emergency feed lines or from the switchyard via the reservetransformers. Backfeed through the unit auxiliary transformers is also considered an adequate source of offsite power.
TERMINIATION/RECOVERYCRITERIA A reliable power supply to ESF buses. from offsite sources is reestablished.
DEVIATION FROM NUMARC: None
Reference PMP-208.EPP.101 Rev. 4 Page 84 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages: (Commitment: 6489) 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-2: ALERT - LOSS OF AC POWER INITIATING CONDITION AC Power capability to essential buses reduced to a single power source for greater than 15 minutes such that any additional single failure would result in a station blackout.
MODE APPLICABILITY 1,,2,3,4 EAL THRESHOLD VALUE Power to the T-buses has been degraded to a single source of AC power consisting of only one of the following transformers or diesel generators for greater than 15 minutes. NOTE: Evaluate each units' power supply separately.
TR-1O1AB/TR-201AB TR-1O1CD/TR-201CD TR-1AB/TR-2AB TR-ICD/TR-2CD EDG 1AB/EDG 2AB EDG 1CD/EDG 2CD TR-12-EP-1 BASIS (References)
In Modes 1, 2, 3, and 4, the condition indicated by this IC is the degradation of the offsite and onsite power systems such that any additional single failure would result in a station blackout. This condition could occur due to a loss of all offsite power with a concurrent failure of one emergency generator to supply power to its emergency buses or failure of emergency diesels and four of the five offsite power transformers. The subsequent loss of another single power source would escalate the event to a Site Area Emergency.
TERMINIATION/RECOVERY CRITERIA Restore power from at least one additional source.
DEVIATION FROM NUMARC: None
Reference R
PMP-2080.EPP1 Rev. 4 Page 85 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels l
s:
1 2-1 (Commitment: 6489) 23 -112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-2: SITE AREA EMERGENCY - LOSS OF AC POWER INITIATING CONDITION Loss of ALL offsite power and loss of ALL onsite AC power to essential buses.
MODE APPLICABILITY 1,2,3,4 EAL THRESHOLD VALUE
- 1.
Loss of both of the following T-buses for > 15 minutes
- a.
T11A, T1D (Unit 1)
-OR-
- b.
T21A, T21D (Unit 2)
NOTE: Evaluate each units' power supply separately.
BASIS (References)
Loss of all AC power compromises all plant safety systems requiring electric power including RHR, ECCS, Containment Heat Removal and ESW. Prolonged loss of all AC power will cause core uncovering and loss of containment integrity, thus this event can escalate to a General Emergency.
Per ECA-O.0, Loss of All AC Power", no specific time limitation is given for restoration of power to the emergency buses. Therefore, Cobk uses the NUMARC/NESP 007 generic limit of 15 minutes.
Escalation to General Emergency is via Fission Product Barrier Degradation or IC S-2A, Prolonged Loss of All Offsite Power and Prolonged Loss of All Onsite AC Power."
TERMINIATION/RECOVERY CRITERIA Cold shutdown is established or a reliable power supply to the ESF buses is established.
DEVIATION FROM NUMARC:
This EAL is specified by loss of essential pump buses rather than loss of transformers and emergency generators.
Reference PMP-2080.EPP.101 Rev. 4 l
Page 86 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
Attachment 3
(Commitment: 6489) 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-2: GENERAL EMERGENCY - LOSS OF AC POWER INITIATING CONDITION Prolonged loss of ALL offsite power and ALL onsite AC power to essential buses.
MODE APPLICABILITY 1,2,3,4 EAL THRESHOLD VALUE
- 1.
Loss of both of the following T-buses on a unit AND Core Cooling CSFST is ORANGE
- a.
Ti A, T1 iD (Unit 1)
-OR-
- b.
T21A, T21D (Unit 2)
-OR-
- 2.
Loss of both of the following T-buses that is expected to last for > 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
- a.
T1 1A, T ID (Unit 1)
-OR-
- b.
T21A, T21D (Unit 2)
NOTE: Evaluate each units' power supply separately.
BASIS (References)
PROLONGED - Restoration of at least one emergency bus within four (4) hours is not likely.
Loss of all AC power compromises all plant safety systems requiring electric power including RHR ECCS, Containment Heat Removal and ESW. Prolonged loss of all AC power could lead to loss of fuel clad, RCS, and containment. In accordance with letters AEP:NRC.0537D, dated April 14, 1989 and AEP:NRC:0537E, dated March 30, 1990, Cook Nuclear Plant falls within the four hour station
':: -, -;' 0.-blackout SBO) copingcategory.
d
.,s-IC:.
-n -n
.g this IC is specified to assure that in the unlikely event of a prolonged station blackout timely reco-gnt-.oi ion of the seriousness of the' event occurs and that declaration of a General Emergency occurs
Reference PMP-2080.EPP.101 Rev. 4 Page 87 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels (Commitment: 6489) 23--112
.as early as is appropriate, based on a reasonable assessment of the event trajectory. Although this IC may be viewed as redundant to the Fission Product Barrier Degradation IC, its inclusion is necessary to better assure timely recognition and emergency response.
The likelihood of restoring at least one emergency bus should be based on a realistic appraisal of the situation since a delay in an upgrade decision based on only a chance of mitigating the event could result in a loss of valuable time in preparing and implementing public protective actions.
TERMINIATION/RECOVERY CRITERIA Cold shutdown is established or a reliable power supply to the ESF buses is established and other initiating conditions requiring maintenance of the general alert status are not present.
DEVIATION FROM NUMARC:
This EAL is specified by loss of essential pump buses rather than loss of transformers and emergency generators.
, A t..
t E
Reference PMP-2080.EPP.101 Rev. 4 Page 88 of 112 Emergency CLASSIFICATION X
0 Basis For Emergency Action Levels Pages:
(Commitment: 6489)23-112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-3: SITE AREA EMERGENCY - LOSS OF DC POWER INITIATING CONDITION Loss of all vital DC power for greater than 15 minutes.
MODE APPLICABILITY 1, 2, 3, and 4 EAL ThRESHOLD VALUE Loss of DC buses AB AND CD as indicated by bus voltage < 220 volts DC for greater than 15 minutes.
BASIS (References)
VITAL - All 250 volt DC power.
The loss of all vital DC power compromises the ability to monitor and control plant functions required for the protection of the public and is considered a loss of these functions. A prolonged loss of control power may result in core uncovering and loss of containment integrity if there is sufficient decay heat generated by the core and sensible heat in the RCS.
The threshold value was chosen to recognize a loss of DC power at a voltage level low enough to be indicative of a severe control system problem. This value is high enough to provide reasonable assurance that the 250 volt batteries will last at least 15 minutes prior to reaching a designed minimum voltage of 210 volts.
The N Train battery supplies TDAFW control bus and the AMSAC inverter. Since these are backup systems, this bus is not included in this EAL.
TERMINIATION/RECOVERY CRITERIA Power is restored to at least one 250 volt DC bus and an investigation as to the cause is underway.
DEVIATION FROM NUMARC: None
. w
-Reference
-:PMP-2080.EPP. 101
-l
-Rev. 4 Page 89 of 112 Emergency CLASSIFICATION Attachent 3
- l asis or E-mergency Action Levels l
Pages:
^
(Commitmenit: 6489) l 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-5: SITE AREA EMERGENCY -. LOSS OF SYSTEMS NEEDED TO ACHIEVE OR MAINTAIN HOT SHUTDOWN INITIATING CONDITION Complete loss of function needed to achieve or maintain Hot Shutdown.
MODE APPLICABILITY 1, 2, 3, and 4 EAL THRESHOLD VALUE Entry into one of the following procedures has occurred:
OHP 4023.FR-HI, "Response to Loss of Secondary Heat Sink"
-OR-OHP 4023.FR-C1, "Response to Inadequate Core Cooling" BASIS (References)
This EAL addresses complete loss of functions, including ultimate heat sink and reactivity control, required for hot shutdown with the reactor at pressure and temperature. Under these conditions, there is an actual major failure of a system intended for protection of the public. Thus, declaration of a Site Area Emergency is warranted. Escalation to General Emergency would be via Abnormal Rad Levels/Radiological Effluent, Site Emergency Coordinator Judgement, or Fission Product Barrier Degradation ICs.
TERMINIATION/RECOVERY CRITERIA Hot Shutdown operation is capable of being maintained.
DEVIATION FROM NUMARC: None I.-..I,4 I
I.
..- I,,
Reference PMP-2080.EPP.101 Rev. 4 Page 90 of 112 Emergency CLASSIFICATION Attachmnt 3 l -
Basis For Emergency Action Levels Pages:
(Commitment: 6489)23-112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-6: UNUSUAL EVENT - LOSS OF ALARMS OR INDICATION INITIATING CONDITION Unplanned loss of safety system annunciators and/or indications in the Control Room for greater than 15 minutes.
MODE APPLICABILITY 1, 2, 3, and 4 EAL THRESHOLD VALUE I 1.
Loss of one of the following:
- a.
Loss of one or more safety system annunciator panels in a unit for > 15 minutes:
Panels 104-114, 119, 120 (Unit 1)
Panels 204-214, 219, 220 (Unit 2)
- b.
A known loss of indications associated with the following parameters for > 15 minutes (See Attachment 2):
Neutron Flux - Gammametrics)
Reactor'Coolant Pressure (Wide Range)
Reactor Coolant Outlet Temperature Thot (Wide Range)
Reactor Coolant Outlet Temperature Tcold (Wide Range)
Incore Thermocouples (Core Exit Thermocouples)
Reactor Coolant System Subcooling Margin Monitor Reactor Coolant Inventory System (Reactor Vessel Level Indication)
Pressurizer Water Level Charging Pump Flow Charging Pump Breaker Status Safety Injection Pump Breaker Status Safety Injection Flow
- . Refueling Water Storage Tank Water Level Containment Water Level
.-' -. -' -- 0:.
--; Containment Pressure (Wide Range)
- Conta
- ment Pressure (Narrow Range)
- -Containment Hydrogen Monitoring Containment Isolation Valve Position Monitoring Containment Area Radiation Monitors (High Range)
Stea Line-Pressure
Reference PMP-2080.EPP.101 Rev. 4 Page 91 of 112 Emergency CLASSIVICATION l
- Basis For Emergency Action Levels Pages
(Commitment: 6489) 23 - 112 Steam Generator Water Level (Wide Range)
Steam Generator Water Level (Narrow Range)
Auxiliary Feedwater Flow Rate Condensate Storage Tank Level
-AND
- 2.
In the opinion of the Shift Supervisor, the loss of annunciators or indications requires additional surveillance to safely operate the unit.
-AND-
- 3.
Annunciator/Indicator loss does not result from PLANNED action.
-AND-
- 4.
Compensatory Non-Alarming Indications for the above annunciator panels are available.
BASIS (References)
Compensatory Non-Alarming Indication - Computer-based information (SPDS, plant process computer, etc.) which could be monitored by control room operators.
PLANNED - Loss of annunciators or indicators that is the result of scheduled maintenance or testing.
This EAL is intended to recognize the difficulty associated with operating the plant safely without major groups of safety annunciators or indications. Compensatory non-alarming indications may include local process indications, or control room indicators/recorders/computer points in the event of an annunciator-system-only failure. Two types of failures are considered; the failure of redundant panels of indications important to safety, and the loss from all sources of any of the key safety indications as to the status of the nuclear steam supply system.
PLANNED maintenance or surveillance activities associated with annunciators or indicators are excluded from the EALs indicated herein.
TE INATION/RECOVERY CRITERIA The minimum number of required annunciators are restored to operability and an investigation of the cause of the problem is in progress.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101 Rev. 4 Page92 of 112 Emergency CLASSIVICATION Attachmen:
3 1
Basis For Emergency Action Levels Pages:
AIac~unent 3 (Commitment: 6489) 23 - 112 A ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-6: ALERT - LOSS OF ALARMS OR INDICATION INITIATING CONDITION Unplanned loss of most or all safety system annunciators or indications in the Control Room with either (1) a significant transient in progress, or (2) compensatory non-alarming indicators are unavailable.
MODE APPLICABILITY 1,2,3, and4 EAL THRESHOLD VALUE
- 1.
Loss of one of the following:
- a.
Loss of one or more safety system annunciator panels in a unit for > 15 minutes:
Panels 104-114, 119, 120 (Unit 1)
Panels 204-214, 219, 220 (Unit 2)
- b.
A known loss of indications associated with the following parameters for 15 minutes (See Attachment 2):
Neutron Flux - Gammametrics)
Reactor Coolant Pressure (Wide Range)
Reactor Coolant Outlet Temperature Thot (Wide Range)
Reactor Coolant Outlet Temperature Tcold (Wide Range)
Incore Thermocouples (Core Exit Thermocouples)
Reactor Coolant System Subcooling Margin Monitor Reactor Coolant Inventory System (Reactor Vessel Level Indication)
Pressurizer Water Level Charging Pump Flow Charging Pump Breaker Status Safety Injection Pump Breaker Status Safety Injection Flow Refueling Water Storage Tank Water Level Containment Water Level.
Containment Pressure (Wide Range)
Containment Pressure (Narrow Range)
Containment Hydrogen Monitoring
.*: Containment Isolation Valve Position Monitoring Containment Area Radiation Monitors (High Range)
Reference:
PMP-2080.EPP.11 Rev. 4 Page 93 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels s:
I 2.1 (Commitment: 49 23 -112-Steam Line Pressure
-SteamGenerator Water Level (Wide Range)
Steam Generator Water Level (Narrow Range)
Auxiliary Feedwater Flow Rate Condensate Storage Tank Level
-AND
- 2.
In the opinion of the Shift Supervisor, the loss of annunciators or indications requires additional surveillance to safely operate the unit.
-AND-
- 3.
Annunciator/Indicator loss does not result from PLANNED action.
-AND-
- 4.
Either
- a.
A significant transient is in progress,
-OR-
- b.
Compensatory Non-Alarming Indications from the plant process computer or safety parameter display system are NOT available.
BASIS (References)
Compensatory Non-Alarming Indication - Computer based information (SPDS, plant process computer, etc.) which could be monitored by control room operators.
PLANNED - Loss of annunciators or indicators that is the result of scheduled maintenance or testing.
This EAL is intended to recognize the difficulty associated with operating the plant safety without major groups of safety annunciators or indications. Compensatory non-alarming indications may include local process indicators, or control room indicators/recorders/computer points in the event of an annunciator-system-only failure.
Examples of significant transients include: 1) reactor trips, 2) unanticipated power changes of greater than 10%, and 3) valid ESF actuations.
PLANNED maintenance or surveillance activities associated with annunciators or indicators are
-excluded from the EALs indicateherein.
TERMINIATION/RECOVERY CRITERIA
Reference PMP-2080.EPP.101 Rev. 4 Page 94 of 112 Emergency CLASSIFICATION Basis For EmergencyAction Levels Pages:
AttacIunen 3 -(Commitment: 6489) 23 -112 The minimum number of required annunciators is restored to operability and an investigation of the cause of the problem is in progress.
DEVIATION FROM NUMARC: None S
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Reference PMP-2080.EPP.101 Rev. 4 Page 95 of 112 Emergency CLASSIFICATION Attch n 3Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-6: SITE AREA EMERGENCY - LOSS OF ALARMS OR INDICATION INITIATING CONDITION Inability to monitor a significant transient in progress.
MODE APPLICABILITY 1,2, 3, and 4 EAL THRESHOLD VALUE Loss of one of the following:
- 1.
Loss of one or more safety system annunciator panels in a unit for > 15 minutes:
Panels 104-114, 119, 120 (Unit 1)
Panels 204-214, 219, 220 (Unit 2)
- 2.
A known loss of indications associated with the following parameters (See Attachment 2) for
> 15 minutes which in the opinion of the Shift Supervisor significantly affects the ability to safely operate or shutdown the unit.
Neutron Flux - Gammametrics)
Reactor Coolant Pressure (Wide Range)
Reactor Coolant Outlet Temperature Thot (Wide Range)
Reactor Coolant Outlet Temperature Tcold (Wide Range)
Incore Thermocouples (Core Exit Thermocouples)
Reactor Coolant System Subcooling Margin Monitor Reactor Coolant Inventory System (Reactor Vessel Level Indication)
Pressurizer Water Level Charging Pump Flow Charging Pump Breaker Status Safety Injection Pump Breaker Status Safety Injection Flow Refueling Water Storage Tank Water Level Containment Water Level Contanmen t
Pres esure (Wie Range)-
Containment Pressure (Narrow Rane)
- -ontainent Hydrogen Monitoring
,,t*,At' Containment Isolation Valve Position Monitoring Containment Area Radiation Monitors (High Range)
Steam Line Pressure
Reference PMP-2080.EPP.1O1 Rev. 4 Page 96 of 112 Emergency CLASSlVICATION.
Basis. For Emergency -Action Levels l
'es:
Attamen Basis (Commitment: 6489)23-112 Steam Generator Water Level (Wide Range)
Steam Generator Water Level (Narrow Range)
Auxiliary Feedwater Flow Rate Condensate Storage Tank Level
-AND-
- 3.
Compensatory Non-Alarming Indications from the plant process computer or safety parameter display system are NOT available.
-AND
- 4.
A significant transient is in progress.
BASIS (References)
Compensatory Non-Alarming Indication - Computer based information (SPDS, plant process computer, etc.) which could be monitored by control room operators.
This EAL is intended to recognize the difficulty associated with operating the plant safely without major groups of safety annunciators or indications. Compensatory non-alarming indications may include local process indications, or control room indicators/recordersfcomputer points in the event of an annunciator-system-only failure. A significant transient is not intended to be strictly defined, however, the following examples are provided: 1) reactor trips; 2) unanticipated power changes of
> 10%, and 3) valid ESF actuations. NUREG 0737 instruments are included in this EAL to provide a redundant means for monitoring the plant should annunicators become unavailable. To prevent overclassifying an event to a Site Area Emergency, Shfit Supervisor discretion has been provided for.
This allows the Shift Supervisor to decide if the specific indications which are unavailable are needed to monitor the transient in progress.
TERMINIATION/RECOVERY CRITERIA Transient is terminated and ability to monitor plant parameters is restored.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101 Rev. 4 Page 97 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
'Attachment 3 2-1 (Commitment: 6489)23-112
..ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-7: UNUSUAL EVENT - FUEL CLAD DEGRADATION INITIATING CONDITION Indication of Fuel Clad Degradation in Active Fuel MODE APPLICABILITY All EAL THRESHOLD VALUE
- 1.
Activity> 1.0.LCigraxn1-131 dose equivalent for >48 hours in the RCS.
-OR-
- 2.
RCS activity > 100/E Ci/gram BASIS (References)
This IC is included as an Unusual Event because it is considered to be a potential degradation in the level of safety of the plant and a potential precursor of more serious problems.
Per Cook Technical Specification 3.4.8, "Reactor Coolant System Activity', fuel clad degradation is indicated if dose equivalent I-131 levels are greater than 1 pCi/gram for greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, dose equivalent 1-131 levels are greater than the limits of technical specifications Figure 3.4-1, or gross radioactivity levels are > 100/E gCi/gram.
The coolant sample activity values indicate fuel clad degradation greater than technical specification allowable limits.
TERM1NIATIONIRECOVERY CRITERIA Technical specification 3.4.8 limit or action requirements are met.
DEVIATION FROM NUMARC:
Cook Plant does not have failed fuel monitors.
Reference PMP-2080.EPP.1O1 Rev. 4 Page 98 of 112 Emergency CLASSIfICATION Attc n 3Basis For Emergency Action Levels Pages:
Attahmen 3 l
(Commitment: 6489) 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-8: UNUSUAL EVENT - ESCESSIVE RCS LEAKAGE INITIATING CONDITION Reactor Coolant System Leakage MODE APPLICABILITY 1,2, 3,4 EAL THRESHOLD VALUE Reactor coolant system leakage exceeds one of the following values:
- 1.
Pressure boundary leakage > 10 gpm
-OR-
- 2.
SG tube leakage > 10 gpm
-OR-
- 3.
Identified leakage >25 gpm
-OR-
- 4.
Unidentified leakage > 10 gpm BASIS (References)
This IC is included as an Unusual Event because it may be a precursor of more serious conditions and as a result, is considered to be a potential degradation of the level of safety of the plant. The 10 gpm value for unidentified or pressure boundary leakage was selected because it is observable with normal control room indications. Lesser valbes must generally be determined through time-consuming surveillance test (e.g., mass balances). The generic EAL for identified leakage is set at a higher value (25 gpm) due to the lesser significance of identified leakage in comparison to unidentified or pressure boundary leakage.
Only operating modes in which there is fuel in the reactor coolant system and the system is pressurized are specified.
TERMINIATION/RECOVERY CRITERIA Leakage is isolated OR Cold Shutdown (Mode 5) is established.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101 Rev. 4 Page 99 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
23-112 (Commitment: 6489) 2 1
ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-9: UNUSUAL EVENT - TECHNICAL SPECIFICATION TIME LIMIT EXPIRED INITATING CONDITION Inability to reach required shutdown within Technical Specification time limits.
MODE APPLICABILITY 1,2,3,4 EAL THRESHOLD VALUE Unit is NOT placed in required MODE within Technical Specification LCO action time limit.
BASIS (References)
Limiting Conditions of Operation (LCOs) require the plant to be brought to a required shutdown mode when the technical specification required configuration cannot be restored. Depending on the circumstances, this may or may not be an emergency or precursor to a more severe condition. In any case, the initiation of plant shutdown required by the site technical specification requires a four hour report under 10 CFR 50.72 (b) Non-emergency events. The plant is within its safety envelope when being shutdown within the allowable action statement time in the technical specifications. An immediate Notification of an Unusual Event is required when the plant is not brought to the required operating mode within the allowable action statement time in the technical specifications. Declaration of an Unusual Event is based on the time at which the LCO-specified action statement time period elapses under the site technical specifications and is not related to how long a condition may have existed. Other required technical specification shutdowns that involve precursors to more serious events are addressed by other Systeni Malfunction, Hazards, or Fission Product Barrier Degradation ICs.
TERMINIATIONIRECOVERY CRITERIA Unit has reached cold shutdown (Mode 5) or other mode as specified in the limiting condition for operation action statement.
-OR-Unit has been placed in a Mode where the LCO no longer applies.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101
-l Rev. 4 Page 100 of 112 Emergency CLASSIFICATION 1
Basis For Emergency Action Levels Pages (Commitment: 6489)23-112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-10: UNUSUAL EVENT - LOSS OF COMMUNICATION SYSTEMS INITIATING CONDITION Unplanned loss of all onsite or offsite communications.
MODE APPLICABILITY 1,2,3,4 EAL THRESHOLD VALUE
- 1.
UNPLANNED loss of ALL onsite electronic communication capabilities:
Telephone Page System Radios
-OR-
- 2.
UNPLANNED loss of ALL offsite electronic communication capabilities:
Telephone (offsite)
Microwave transmission NRC phone State Police/Sheriff Department Emergency Radios BASIS (References)
UNPLANNED - The loss of communication is not a result o planned testing, maintenance or surveillance activities.
The purpose of this IC and its associated generic EALs is to recognize a loss of communications capability that either defeats the plant operations staff ability to perform routine tasks or the ability to communicate problems with offsite authorities. The loss of offsite communications capability is expected to be significantly more comprehensive than that addressed by 10 CFR 50.72. The loss of offsite communications capability is' applicable when no direct means is available to communicate with or makes notifications to the load dispatcher or state and federal authorities.
-TERMINIATION/RECOVERY CRITERIA At [east one form of onsite and offsite communications has been established.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101 Rev. 4 Page 101 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
Basis (Commitment: 6489) 23 -112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION C-3 UNUSUAL EVENT - LOSS OF AC POWER ALL OFFSITE POWER TO ESSENTIAL BUSES FOR GREATER THAN 15 MINUTES INITIATING CONDITION Loss of all offsite power to essential buses for greater than 15 minutes.
MODE APPLICABILITY 5, 6 EAL THRESHOLD VALUE
- 1.
ALL of the following OFFSITE power sources indicated by the following list of transformer are LOST to the T-buses for > 15 minutes.
- a.
Normal Auxiliary Power Source (Auxiliary Transformer)
- b.
Preferred Offsite Power Sources (Reserve Transformer)
TR 11AB / TR 201AB TR 101CD / TR 201CD
- c.
Emergency Offsite Power Source (69Kv Transformer)
T-12-EP-1
-AND-
- 2.
At lease one diesel generator per unit is supplying power to the emergency buses.
BASIS (References)
Prolonged loss of AC power reduces required redundancy and potentially degrades the level of safety of the plant by rendering the plant more vulnerable to a complete Loss of AC Power (Station Blackout). Fifteen minutes was selected as a threshold to exclude transient or momentary power losses.
Offsite power can be supplied via the 69Kv emergency feed lines or from the switchyard via te reserve transformers. During outages, swichyard power may be supplied via the normal transformers
Reference PMP-2080.EPP.101 Rev. 4 Page 102 of 112
.'Emergency CLASSIFICATION
-- Basis For Efergency Action Levels-Pages:
(Commitment: 6489) 23 - 112 aligned for "backfeed". During outages, the backfeed alignment should be -considered equivalent to reserve feed for the purpose of emergency classification level determinations.
TERMINIATION/RECOVERY CRITERIA A reliable power supply to ESF buses from offsite sources is re-established.
DEVIATION FROM NUMARC: None I:
i!.,.
Reference PMP-2080.EPP.101 Rev. 4 Page 103 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages.
(23-112 (Commitment: 6489) 2 1
ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION C-3 ALERT - LOSS OF AC POWER ALL OFFSITE POWER AND LOSS OF ALL ONSITE AC POWER TO ESSENTIAL BUSES INITIATING CONDITION Loss of ALL offsite power and loss of ALL onsite AC power to essential buses.
MODE APPLICABILITY 5, 6 or defueled EAL THRESHOLD VALUE
- 1.
Loss of both of the following T-buses for > 15 minutes when fuel is in the reactor.
- a.
T1 IA, T1 ID (Unit 1)
-OR-
- b.
T21A, T21D (Unit 2)
- 2.
Loss of power to all the following buses when defueled Ti IA, TI1 iD, T21A, T2ID BASIS (References)
In Modes 5 and 6, loss of all AC power compromises all plant safety systems requiring electric power including RHR, ECCS, Containment Heat Removal, Spent Fuel Heat Removal, and ESW. When in cold shutdown, refueling, or defueled mode the event can be classified as an Alert, because of the significantly reduced decay heat, lower temperature and pressure. An Alert is declared in these modes due to the less severe threat to the protection of the health and safety of the public because of the much longer time available to restore power and decay heat removal systems. Fifteen minutes was selected as a threshold to exclude transient or momentary power losses. Escalating to Site Area Emergency, if appropriate, is by Abnormal Rad Levels/Radiological Effluent, or SEC Judgement ICs.
When a unit is defueled, power from an essential bus on either unit will emergency power to required plant safety systems.
STERMINIATION/RECOVERY CRITERIA Restore power to at least one T-bus.
EVIATION FROM NUMARC:
be sufficient to provide
Reference PMP-2080.EPP.101.7l Rev. 4 l
Page 104 of 112
- Emergency CLASSIFICATION n 3 Basis For Emergency Action Levels Pages:
Attahmen 3 (Commitment: 6489) 23 - 112 finis EAL is specified by loss of essential pump buses rather than loss of transformers and emergency generators.
I I
I -
k - -I. -
I..
Reference PMP-2080.EPP.101 Rev. 4 Page 105 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels, Pages.
2 (Commitment: 6489) 23 - 12 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRITION C-4: ALERT - INABILITY TO MAINTAIN A UNIT IN COLD SHUTDOWN INITIATING CONDITION Inability to maintain plant in Cold Shutdown.
MODE APPLICABILITY 5, 6 EAL THRESHOLD VALUE
- 1.
Loss of shutdown cooling'as evidenced by entry into OHP 4022.017.001, "Loss of RHR Cooling."
-AND
- 2.
Temperature increase that either
- a.
exceeds Technical Specification cold shutdown limit of 200 0F
-OR-
- b.
results in an UNCONTROLLED increase in RCS temperature rise approaching the cold shutdown technical specification limit of 200'F.
BASIS (References)
UNCONTROLLED - means a temperature increase that is not the result of a planned evolution. It is included to preclude the declaration of an emergency for circumstances where decay head removal is intentionally removed from service and is controlled within the requirements of the technical specifications.
The threshold value indicates a substantial degradation in the level of safety of the plant by indicating a potential complete loss of the ability to removal decay heat in the Cold Shutdown and Refueling modes.
NRC concerns expressed in Generic Letter 88-17, "Loss of Decay Heat Removal" are the basis for the threshold value as an anticipatory sequence leading to core uncovery and clad damage.
The threshold related'to-an uncontrolled temperature rise is necessary to preserve the anticipatory philosophy of NUREG-0654 for events starting rom temperatures much lower than 20OF. The inability to reach cold shutdown is to 'include instances where decay heat removal capability is lost prior to reaching the c tolwd shut n mode.
-- TERMINIATION/RECOVERY CRITERIA,
Reference PMP-2080.EPP.101
- Rev. 4
-Page 106 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
(Commitment: 6489) 23 - 112 Cold shutdown conditions have been established and can be maintained.
DEVIATION FROM NUMARC None.
Reference PMP-2080.EPP.101 Rev. 4 lPage 107 of 112 E mergency CLASSIFICATION Basis For Emergency Action Levels Pages:
(Commitment: 6489)23-112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION CA: SITE AREA EMERGENCY - INABILITY TO MAINTAIN A UNIT IN COLD SHUTDOWN INITIATING CONDITION LOSS of water level in the reactor vessel that has or will uncover fuel in the reactor vessel.
MODE APPLICABILITY 5, 6 EAL THRESHOLD VALUE Loss of reactor vessel water level as indicated by:
- 1.
LOSS of shutdown cooling as evidenced by entry into OHP 4022.017.001, "Loss of RHR Cooling."
-AND
- 2.
Core uncovery as indicated by:
- a.
RVLIS NR < 46% -
-OR-
- b.
Reactor Vessel Water Level < 614' BASIS (References)
LOSS - Inability to restore RHR operability (e.g., restart the RHR pumps) when required.
The threshold values indicate that severe core damage can occur and RCS integrity may not be assured and thus indicate failures of functions needed for the protection of the public.
These conditions address prolonged boiling as a result of loss of decay heat removal.
TERMINIATION/RECOVERY CRITERIA Restoration of lost core inventory is in progress, level is above the top of the active fuel, and decay heat removal capability has been restored.
DEVIATION FROM NUMARC:-
--None.
TT-D Reference PMP-2080.EPP.101 7_^^^
Rev. 4 l
Page 108 of 112 Emergency CLASSIFICATION Attachment 3
I Basis For Emergency Action Levels Pages:
-Attahmen 3
-(Commitment:
6489) 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION C-5: UNUSUAL EVENT - FUEL CLAD DEGRADATION INITIATING CONDITION Fuel clad degradation.
MODE APPLICABILITY 5,6 EAL THRESHOLD VALUE
- 1.
(Site-specific) radiation monitor readings indicating fuel clad degradation greater than Technical Specification allowable limits.
- 2.
RCS sample activity value indicating fuel clad degradation greater than Technical Specification allowable limits.
BASIS (References)
This IC is included as a UE because it is considered to be a potential degradation in the level of safety of the plant and a potential precursor of more serious problems. EAL #1 addresses site-specific radiation monitor readings that provide indication of fuel clad integrity. EAL #2. addresses coolant samples exceeding coolant technical specification for iodine spike.
TERMINIATION/RECOVERY CRITERIA DEVIATION FROM NUMARC:
Cook Plant does not have failed fuel monitors.
':, r...,...
Reference PMP-2080.EPP.1O1 Rev. 4 Page 109 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
Attachment:
3(Commitment: 6489 23 - 112 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION C-6: UNUSUAL EVENT - UNPLANNED LOSS OFALL ONSITE OR OFFSITE COMMUNICATION CAPABILITIES INITIATING CONDITION Unplanned loss of all onsite or offsite communications.
MODE APPLICABILITY 5, 6 EAL THRESHOLD VALUE
- 4.
UNPLANNED loss of ALL onsite electronic communication capabilities:
Telephone Page System Radios
-OR-
- 5.
UNPLANNED loss of ALL offsite electronic communication capabilities:
Telephone (offsite)
Microwave transmission NRC phone State Police/Sheriff Department Emergency Radios BASIS (References)
UNPLANNED - The loss of communication is not a result of planned testing, maintenance or surveillance activities.
The purpose of this IC and its associated generic EALs is to recognize a loss of communications capability that either defeats the plant operations staff ability to perform routine tasks or the ability to communicate problems with offsite authorities. The loss of offsite communications capability is expected to be significantly more comprehensive than that addressed by 10 CFR 50.72-' The loss of offsite communications capability 'is'applicable when no direct means is available to communicate, with or makes notifications to the load dispatcher or state and federal authorities.
TERMINIATION/RECOVERY CRITERIA At lease one formof onsite and offsite communications has been established.
Reference -
l
-PMP-2080.EPP.O1 Rev. 4 Page 110 of 112
- Emergency CLASSIFICATION l I-SBasis For Emergency Action Levels Pages:
(Commitment: 6489) 23 - 112 DEVIATION FROM NUMARC:
.Jo None
Reference PMP-2080.EPP.101 Rev. 4 Page II1 of 112 Emergency CLASSIFICATION' Basis For Emergency Action Levels23-112 (Commitment: 6489) 2
.1 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION C-7 UNUSUAL EVENT - UNPLANNED LOSS OF DC POWER FOR GREATER THAN 15 MINUTES INITIATING CONDITION Unplanned loss of required DC power during cold shutdown or refueling mode for greater than 15 minutes.
MODE APPLICABILITY 5,6 EAL THRESHOLD VALUE UNPLANNED loss of 250 volt DC buses AB AND CD as indicated by bus voltage < 220 volts DC for greater than 15 minutes.
BASIS (References)
The purpose of this IC and its associated generic EAL is to recognize a loss of DC power compromising the ability to monitor and control the removal of decay heat during Cold Shutdown or Refueling operations. This EAL is intended to be anticipatory in as much as the operating crew may not have necessary indication and control equipment needed to respond to the loss.
The threshold value was chosen to recognize a loss of DC power at a voltage level low enough to be indicative of a severe control'system problem. This value is high enough to provide reasonable assurance that the 250 volt batteries will last at least 15 minutes prior to reaching a designed minimum voltage of 210 volts.
UNPLANNED is included in this IC and EAL to preclude the declaration of an emergency as a result of planned maintenance activities. Routinely, plants will perform maintenance on a train related basis during shutdown periods. It is intended that the loss of the operating (operable) train is to be considered. If this loss results in the inability to maintain cold shutdown, the escalation to Alert will be per C-4, "Inability to Maintain Plant in Cold Shutdown with Irradiated Fuel in the Reactor Vessel."
Plant Specific Information DC systems are not shared between Cook Units 1 and 2.
Reference PMP-2080.EPP.101 Rev.
Page 112 of 112 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages.23-112 (Commitment: 6489) 2 1
Tile Cook 250 VDC system includes three major battery groups for each unit.
Station or Plant Battery Train A (supplies 250 Bus CD)
Station or Plant Battery Train B (supplies 250 Bus AB)
N Train Battery The N train battery supplies TDAFW control bus and the AMSAC inverter. Since these are backup systems, this bus is not included in this EAL-The above symptoms include equipment which may be used to monitor and control the removal of decay heat during Cold Shutdown or Refueling operations (i.e., annunciators, PZ PORVs, steam dumps, SG PORVs).
TERMINIATION/RECOVERY CRITERIA Power is restored to at least one 250 volt DC bus and an investigation as to the cause is underway.
DEVIATION FROM NUMARC: None 1
7
.R 2.
REVISION
SUMMARY
Number:
Title:
PMP-2080-EPP-107 Revision:
18 Change:
0 NOTIFICATIONS Section or Step Change/Reason For Change
3.2.3 Change
Add Note IF accountability and /or evacuation is (are) required at classifications other than a Site Area Emergency or General Emergency, THEN PA announcements may be made using the guidance in step 3.2.3.
Reason: CR 03099018 action 2 to address personnel accountability and evacuation from site when Site Area Emergency or General Emergency do not exist.
3.2.3 Change
Add "Note Directions to activate the ERO facilities are only given ONE time for the event in progress" and remove bullet with same statement from 3.2.3.
Reason: CR 03099018 action 2 to address personnel accountability and evacuation from site when Site Area Emergency or General Emergency do not exist.
3.2.3 and 3.2.3.c Change: Add "Note Accountability is performed only ONE time for the event in progress", and remove bullet with same statement from
3.2.3. Reason
CR 03099018 action 2 to address personnel accountability and evacuation from site when Site Area Emergency or General Emergency do not exist.
3.2.3 Change
Add "Note Announcements may be modified as necessary to fit existing plant and ERO status."
Reason: CR 03099018 action 2 to address personnel accountability and evacuation from site when Site Area Emergency or General Emergency do not exist.
3.2.3 Change
Add bulleted item IF ERO Facility activation is desirable at other than Alert, Site Area Emergency, or General Emergency Classification, THEN announce the following "Attention all personneL Activate the Name of Facility(ies) to be activated All other personnel continue with your work and be prepared for future announcements.".
Reason: CR 03099018 action 2 to address personnel accountability and evacuation from site when Site Area Emergency or General
- ad -
s-Emergency do not exist.
. ~ ~~~
~
.~
I I
'Juice Inlormation iior term 1 raciQug Unly,- kNOt 1'art 01 t orni This is a free-form as called out in PMP-20 1O-PRC-002, Procedure Correction, Change, and Review, Rev. lOa.
Page i. of 3
REVISION
SUMMARY
Number:
Title:
PMP-2080-EPP-107 Revision:
18 Change:
0 NOTIFICATIONS Section or Step Change/Reason For Change
3.2.3 Change
Add bulleted item IF evacuation of areas of the plant, or evacuation of the plant site is desirable at other than Alert, Site Area Emergency, or General Emergency Classification, THEN announce the following "Attention all personnel. Evacuate the Area(s) of the plant to be evacuated
. All other personnel continue with your work and be prepared for future announcements.".
Reason: CR 03099018 action 2 to address personnel accountability and evacuation from site when Site Area Emergency or General Emergency do not exist.
3.2.3 Change
Add bulleted item IF Personnel Accountability is desirable at other than Site Area Emergency, or General Emergency Classification, THEN notify the Security Shift Supervisor to perform accountability.
Reason: CR 03099018 action 2 to address personnel accountability and evacuation from site when Site Area Emergency or General Emergency do not exist.
3.2.3 Change
Delete sentence "Modify the announcements in steps 3.2.3.a, 3.2.3.b, and 3.2.3.c as necessary to ensure that:"
Reason: CR 03099018 action 2 to address personnel accountability and evacuation from site when Site Area Emergency or General Emergency do not exist.
3.2.10 Bullet Change: Delete word "Offsite".
Reason: "Offsite" is not included in the title for Data Sheet 1.
Change: Pages block numbering from 10 - 11 to 11-12 on both pages of.
Reason: Correct pagination.
This is-a free-form as called out in PMP-20 IlO-PRC-002, Procedure Correction, hange, and Review, Rev..
.Oa.
Page of
EVOKE l
PMP-2080-EPP-107 Rev. 18 Page 1 of 15 Notification Reference Effective Date: q,
D. A. Schroeder S. M. Partin Site Protective Services Writer Owner Cognizant Organization TABLE OF CONTENTS 1
PURPOS E
AND SCOPE.
2 2
DEFINITIONS ANI ABBREVIATIONS........................................
2 3
DETAILS...................................................................................
3 4
FINAL CONDITIONS.......................................
8 5
REFE N ES.....................................................................................................................
8 :
Drills and Exercises.................................................................................... 10 :
Communication System Tests...........................
11 Data Sheet 1:
Shift Manager Initial Notification List...........................
13 Data Sheet 2:
Plant Status.......
14
Reference I
PMP-2080-EPP-107 I
Rev. 18 l
Page 2 of 15 Notification 1
PURPOSE AND SCOPE 1.1 This procedure specifies the actions for notification of offsite personnel and activation of plant emergency response personnel for emergency conditions, drills, exercises and communication system tests.
1.2 The steps in this procedure are listed in the preferred order of performance for maximum efficiency. However, the steps may be performed in a different sequence.
2 DEFINITIONS AND ABBREVIATIONS Term Meaning Drill/Exercise An Emergency Response Organization (ERO) test that uses the Dialogic pager system to page ERO members in order to activate the Emergency Response Facilities.
EMD-32 Nuclear Plant Accident Notification form Emergency An actual plant condition that requires an Emergency Plan classification.
ENC Emergency News Center EOF Emergency Operations Facility ERO Emergency Response Organization JPIC Joint Public Information Center MSP Michigan State Police OSC Operations Support Center PA Public Address PAR Protective Action Recommendation SAS Secondary Alarm Station SEC Site Emergency Coordinator SM Shift Manager TSC Technical Support Center
Reference PMP-2080-EPP-107 Rev. 18 Page 3 of 151 Notification j
Turnover A Dialogic Emergency Response Organization pager activation that signals a change in the on-duty team.
l 3
DETAILS 3.1 General 3.1.1 The SM shall assume the duties of the SEC and initiate this procedure.
3.1.2 IF an Emergency Classification upgrade is required, THEN re-perform section 3.2 of this procedure.
Activation of ERO pagers is only required once.
NOTE:
The SEC may implement this procedure in full or partially at any time should the need for additional personnel be recognized.
3.2 Actions ICAUTION:
Do not use the 911 r 007 code for drills, exercises or training.l NOTE:
SEC judgement will be used to determine which of the following codes will be used. The 007,code will be used if it is determined to be unsafe to report to the plant site.
3.2.1 IF an Alert, Site Area Emergency, or a General Emergency has been declared or an Unusual Event has been declared and ERO facility staffing is desired, THEN determine where the ERO should respond.
Code '911' will direct ERO responders to their respective facilities in the TSC, OSC, EOF, ENC/JPIC.
Code '007' will direct all ERO responders reporting from offsite to the Buchanan Office Building. The EOF will activate and the back-up TSC will be manned. Personnel will remain in Buchanan pending further instructions by the SEC.
Reference PMP-2080-EPP-107 Rev. 18 Page 4 of 15 1~~
I I
Notification I
3.2.2 IF a pager code was identified in step 3.2.1, THEN call the SAS at extension 1118 or 1119 and direct Security to implement the Dialogic Emergency Response Organization pager system for the selected response code.
- a.
IF conditions at the plant are such that personnel reporting to the plant would be at risk (e.g., security event, radiation release, toxic spill, etc.), THEN direct Security to close access to the plant until the SEC determines that the condition no longer exists.
NOTE:
IF accountability and/or evacuation is (are) required at classifications other than a Site Area Emergency or General Emergency, THEN PA announcements may be made using the guidance in Step 3.2.3.
F NOTE:
Directions to activate the ERO facilities are only given ONE time for the
[
event in progress.
NOTE:
Accountability is performed only ONE time for the event in progress.
NOTE:
Announcements may be modified as necessary to fit existing plant and ERO status.
3.2.3 Direct a Control Room Operator to perform ONE of the following, depending on the current classification. Include a brief description of the incident. Have the announcement broadcast twice.
IF ERO Facility activation is desirable at other than Alert, Site Area Emergency or General Emergency Classification, THEN announce the following:
I "Attention all personnel. Activate the Name of Facilitv(ies) to be activated All other personnel continue with your work and be prepared for future announcements."
IF evacuation of areas of the plant or evacuation of the plant site is desirable at other than Alert, Site Area Emergency or General Emergency Classification, THEN announce the following:
I
~..
..... I..... l..... -;...
I 1 V-
Reference PMP-2080-EPP-107 Rev. 18 Page 5 of 15 Notification "Attention all personnel. Evacuate the Area(s) of the plant ot be evauated
. All other personnel continue with your work and be prepared for future announcements."
IF Personnel Accountability is desirable at other than Site Area Emergency or General Emergency Classification, THEN notify the Security Shift Supervisor to perform accountability.
IF an Unusual Event exists, THEN perform step 3.2.3.a.
IF an Alert exists, THEN perform step 3.2.3.b.
IF a Site Area Emergency or General Emergency exists, THEN perform step 3.2.3.c.
Other contingencies are addressed as determined by the SEC (e.g.,
security concerns, radiation release, etc.).
- a.
FOR AN UNUSUAL EVENT:
"Attention all personnel. An Unusual Event has been declared due to (brief description)_. Continue with your work and be prepared for future announcements."
- b.
FOR AN ALERT:
"Attention all personnel. An Alert has been declared due to (brief descript Activate the Operations Support Center, Technical Support Center, Emergency Operations Facility and the Emergency News Center. All other personnel stand by for further announcements."
- c.
FOR A SITE AREA EMERGENCY OR GENERAL EMERGENCY:
lNOTE:
a Accountability is performed only ONE time for the event in progress.
I I~~~~~~~~~~~~~~~~~~~~~~~
1-1.
Sound the Nuclear Emergency Alarm from the Control Room and broadcast the following:
~~
I
Reference PMP-2080-EPP-107 Rev. 18 Page 6 of 15 Notification "Attention all personnel. A (Site Area Emergency or General Emergency) has been declared due to (brief description)
. Activate the Technical Support Center, Operations Support Center, Emergency Operations Facility, and Joint Public Information Center. All other personnel report for accountability."
- 2. Actuate the Unit 1 and Unit 2 Containment Evacuation Alarm.
3.2.4 On any touch-tone telephone, dial 1646 to access the Training Center and Buchanan Office Building PA and repeat the announcement that was made in step 3.2.3 twice.
3.2.5 Within 15 minutes of the classification of any emergency perform the following:
- a.
Complete a Nuclear Plant Accident Notification form, EMD-32a, (from Emergency Kit or DAP printout).
NOTE:
The MSP operator may request that a different phone number be used after initial contact is made.
- b.
Contact:
Michigan State Police (MSP) at 8-1-517-336-6250 using the MSP bridge phone (extension 1088) in the back of the Control Room.
Berrien'County Sheriff's Department at 8-1-269-983-3911. IF the automated system answers, THEN dial 7200.
- c.
Document phone calls on Data Sheet 1, Shift Manager Initial Notification List.
- d.
Provide the information from the Nuclear Plant Accident Notification form, verbally to the MSP and the Berrien County Sheriff's Department.
- e.
Request a call back from the MSP and Berrien County Sheriff's Department.
- f.
Inform the MSP that the Nuclear Plant Accident Notification form will be faxed.
Reference PMP-2080-EPP-107 l
Rev. 18 T
Page 7 of 15 Notification 3.2.6 Fax Nuclear Plant Accident Notification form, to the MSP: Fax number 8-1-517-336-6257.
NOTE:
If BROADCAST is pushed on the fax machine all of the locations listed in step 3.2.7 will receive the fax. If BROADCAST is NOT used then each of the locations will have to be individually faxed at the numbers listed in step 3.2.7.
3.2.7 IF an Alert, Site Area Emergency or General Emergency exists, THEN make follow-up notifications to the below listed facilities by faxing:
EMD-32a, Nuclear Plant Accident Notification, within 15 minutes of a change of classification or Protective Action Recommendation.
EMD-32b, Nuclear Plant Event Technical Data, every 30 minutes there after until relieved by the EOF or as directed by the MSP.
Michigan State Police 8-1-517-336-6257 State Emergency Operations Center 8-1-517-333-4987 Emergency Operations Facility 8-284-2942 Emergency News Center/JPIC 8-284-5892 Visitors' Center 2906 or 2907 3.2.8 IF a General Emergency exists and a PAR is made based on dose assessment, THEN within 15 minutes of the General Emergency classification or PAR change:
Complete an EMD-32a and EMD-32b form and make notifications as directed in step 3.2.5 and fax the forms to the parties listed in step 3.2.7.
3.2.9 For all classifications, including classification upgrades, the Shift Manager or designee shall:
- a.
Provide the information on Data Sheet 2, Plant Status, to the NRC as soon as possible after the State and County have been notified, and within one hour of classification.
Make the notification in accordance with the instructions in PMP-7030-001-001, Prompt NRC Notification.
Reference I
PMP-2080-EPP-107 l
Rev. 18 l
Page 8 of 15 Notificatiout 3.2.10 IF an emergency classification is upgraded or the PAR changes, THEN verbally inform the MSP, Berrien County Sheriffs Department and the NRC.
Document phone calls to MSP and Berrien County Sheriff's Department, on Data Sheet 1, Shift Manager Initial Notification List.
3.2.11 Inform the Security Shift Supervisor of the time of the Emergency Classification.
- a.
Direct the Security Shift Supervisor to assume the responsibility of the Security Director.
- b.
Direct the Security Shift Supervisor to notify the personnel listed in Section 5 of the ERO Phone Directory of the Emergency Classification.
3.3 Drills, Exercises and Communication System Tests 3.3.1 IF a Drill or Exercise is being conducted, THEN perform the applicable portions of Attachment 1.
3.3.2 IF a Communication System Test is being conducted, THEN perform the applicable portions of Attachment 2.
4 FINAL CONDITIONS 4.1 Emergency is closed-out.
4.2 Drill is completed.
4.3 Communication System Test is completed.
5 REFERENCES 5.1 Use
References:
5.1.1
'Emergency Response Organization ERO Phone Directory.
5.1.2 ;- PMP-7030-001-O01, Prompt NRC Notification
- 5. 2 Writing
References:
5.2.1 Source
References:
Reference PMP-2080-EPP-107 l
Rev. 18 Page 9of 15 Notificatin
- a. NUREG 0654 FEMA REP-1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants (Rev. 1).
- b.
Cook Nuclear Plant Emergency Plan.
5.2.2 General References
- a.
None.
I I.
o -
. 1, ;,,.
I
Reference PMP-2080-EPP-107 I
Rev. 18 Page 10 of 15 Notification Drills and Exercises Page:
10 1
DRILLS AND EXERCISES 1.1 IF an Alert, Site Area Emergency, or a General Emergency has been declared, THEN the Simulator Shift Manager calls the SAS at extension 41-1118 and directs Security to implement the Dialogic Emergency Response Organization pager system for an announced or unannounced drill as directed by the controller. The drill or exercise controller may provide alternate instructions for contacting Security as dictated by the drill scenario.
1.2 The Simulator Shift Manager requests that the Shift Manager have a control room staff member page the plant using the Plant PA system, and make an announcement in accordance with the drill controller's instructions.
1.3 The Simulator Shift Manager directs the Simulator control room staff to sound the Nuclear Emergency Alarm and the Containment Evacuation Alarm in the SIMULATOR for a Site Area Emergency or General Emergency.
1.4 The Simulator Shift Manager directs the Simulator unaffected control room staff to page the Training Building and Buchanan Office Building by dialing 41-1646 on the plant phone system, and make an announcement in accordance with the drill controller's instructions.
Reference PMP-2080-EPP-107 Rev. 18 Page 11 of 15 Notification Communication System Tests lges COMMUNICATION SYSTEM TESTS 1.1 Nuclear Emergency Alarm Test and ERO Turnover/Notification Process Test 1.1.1 Operating shift shall perform the following tests every Tuesday at approximately 1000 or at a time approved by the Shift Manager:
Call the SAS at extension 1118 to direct Security to activate the Dialogic Emergency Response Organization pagers for a Turnover.
1.1.2 Test Nuclear Emergency Alarm Announce:
"This is a test. The following is a test of the Nuclear Emergency Alarm and ERO turnover notification."
Sound the Nuclear Emergency Alarm (NEA) for 8 to 10 seconds and then reset by pushing "OVERIDE' button.
Announce:
"The test of the Nuclear Emergency Alarm is complete. Oncoming duty ERO personnel should call Dialogic when the ERO pager activates."
Acceptance Criteria:
NEA alarm is heard in the Control Room.
Print Name/Signature Date
Reference PMP-2080-EPP-107 I
Rev. 18 l
Page 12 of 15 Notification Communication System Tests Pages:
11 - 12 1.1.3 Perform test of the Training Building and Buchanan Office Building Public Address System.
Dial 1646 and announce the following:
"This is a test of the Training Building and Buchanan Office Building Public Address System and ERO turnover notification.
Oncoming duty ERO personnel should call Dialogic when the ERO pager activates. Test is complete."
Acceptance Criteria: (only required to be verified during normal work days).
Emergency Planning personnel report that PA system test is heard in the Training Building and Buchanan Office Building.
Print Name/Signature Date 1.1.4 Perform the test of the Beach PA system monthly, between May S and October 31St.
a Station an AEO within range of the Beach PA system speakers.
Make the following announcement using the Beach PA system microphone; a
"This is a test of the Beach Public Address System. Test complete."
Acceptance Criteria:
Announcement is heard by the AEO stationed for the test.
Print Name1Signature
F X.. -. -
M....
-...- 6:
w i
...
Date
~~.
I
Reference T
PMP-2080-EPP-107 --
l Rev. 18 Pg 3 f1 Notification Data Sheet Shift Manager Initial Notification List
[
ae ON-SITE PHONE NUMBER CONTACT ESTABLISHED INITIALS I NOTIFICATION TIME Security (SAS) for 1118 or 1119
/
Dialogic Activation Training and 1646
._/
Buchanan Office PA Announcement OFF-SITE PHONE NUMBER CONTACT NOTIFICATION ESTABLISHED CLOSEOUT INITIALS / TIME INITIALS I DATE Berrien County Sheriff's 8-1-269-983-3911
'_ /
I Department REQUEST CALL BCSD Person Contacted:
BACK VERIFICATION Time Call Back Received:
Michigan State 8-1-517-336-6250
/
Police REQUEST CALL MSP Person Contacted:
BACK VERIFICATION Time Call Back Received:
NRC Operations 8-1-301-816-5100 Red Phone or'Commercial Center -
8-1-301-951-0550 8-1-301-415-0553 NRC Person Contacted:__
Continuous contact will be required for an Alert, Site Area Emergency, or General Emergency
Reference PMP-2080-EPP-107
'Rev. 18 Page 14 of 15 Notification 2
Plant Status
~~~~~~~~Pages:
Data Sheet2 1
Plant Status
- 15 NOTE:
This Data Sheet is not required to be sent to the NRC unless asked for by the NRC. It is to be used as a guide for the communicator talking to the NRC.
Time of NRC Notification:
Reactivity Control All Control rods inserted?
Yes No
- of rods out
- Reactor Subcritical?
Yes No
- Emergency Boration initiated?
Yes No Adequate Shutdown Margin?
Yes No RCS Inventory Control - Check all that apply for the current plant conditions Inventory makeup controlled by: (Identify all pumps injecting into RCS)
CVCS - Normal Charging Charging Pumps via BIT (High Head SI)
Safety injection pumps (Intermediate Head SI)
Ather RCS Pressure Control
- Pressurizer PORVs Closed?
Yes No Pressurizer Safeties Closed?
Yes No
Reference PMP-2080-EPP-107 Rev. 18 Page 15 of 15 Notification
'Pages:
Data Sheet 2 Plant Status14-5 RCS Heat Transport Control - Check all that apply for the current plant conditions Forced Circulation by RCP Natural Circulation Feed and Bleed Decay Heat Removal System (RHR)
RCS Heat Sink (available or in operation) - Check all that apply for the current plant conditions SIG - Condenser Dump Valves S/G - Atmospheric Dump Valves S/G - Safety Valves RCS - Feed/Bleed Decay Heat Removal System (RHR)
S/G Inventory Control - Check all that apply for the current plant conditions Main Feedwater Aux. Feedwater Other:
Containment Control Ice Condenser Doors OPEN?
Yes No Containment Sprays ON?
Yes No
- Hydrogen Recombiners/Igniters ON?
Yes No
- Containment Isolation Valves fail to CLOSE?
Yes No
- Phase A Actuation?
Yes No