ML031470264
| ML031470264 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/19/2003 |
| From: | Indiana Michigan Power Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:3054-07 | |
| Download: ML031470264 (186) | |
Text
ATTACHMENT 2 TO AEP:NRC:3054-07 IMPLEMENTING PROCEDURES PMI-2080, Revision 7 PMP-2080-EPP-100, Revision 1 PMP-2080-EPP-101, Revision 3b PMP-2080-EPP-107, Revision 17 PMP-2080-EPP-108, Revision 4 PMP-2081-EPP-105, Revision 4 RMT-2080-EOF-001, Revision 3 RMT-2080-EOF-002, Revision 1 RMT-2080-OSC-001, Revision 2 RMT-2080-TSC-001, Revision 2
REVIEW AND APPROVAL TRACKING FORM Proedure Information:
Number: PMI-2080 Rev. 7 Change: 0
Title:
Emergency Plan and Implementing Procedures Categor (Select' One"Only):
1 Correction (Full Procedure) 1 Change (Full Procedure) with Review of Change Only Ej Correction (Page Substitution) O Change (Page Substitution) with Review of Change Only O Cancellation O New Procedure or Change with Full Review O Superseded (list superseding procedures):
Associated Configuration Impact Assessments:,
Change Driver/CDI Tracking No(s).: ___ N/A RequiedlReviews:
Cross-Discipline Reviews: Programmatic Reviews:
X Chemistry 1 Training 1 ALARA 1 Reactivity Mgmt Team 3 Maintenance 1 Work Control 13 Component Engineering 1 SPS (Safety & Health) 1 NDM 13 Design Engineering 1 Surveillance Section l Operations 13 E1 Emerg Oper Proc Grp 1 System Engineering 1 PA/PV 1 1 Environmental 1 SOMS Administrator 1 Reg Affairs 13 ISI/IST Coordinator 1 3 RP 13 None Required l Performance Assurance 13 None Required Z Cognizant Org Review: Date: / I_
E Technical Review: - Date: / /
Concurrence:i>- u'i',00'4" < l'0t-S'-0$ 'S+'f5 1 Ops Director Concurrence: N/A Date: II Package Check: "
Updated Revision Summary attached? 1 Yes 10 CFR 50.59 Requirements complete? Tracking No.:2003-0361-00 l Yes 1 N/A Implementation Plan developed? (Ref. Step 3.4.17) l Yes O N/A Package Complete: Date: / I Approv Ils:--X3--fw0R 0PI PORC Review Required: 3 Yes 1 No Mtg. No.:_ _
Administrative Hold Status: 13 Released F1 Reissued Z N/A CR No.:_
Approval Authority Review/Approval: Date: _ I_-
Expiration Date/Ending Activity Effective Date: / /
Periodic Review: " Tj Periodic Review conducted? (Data Sheet 5 Complete) 13 Yes 3 No Flow-up Actions:^'j Commitment Database update requested in accordance with PMP-7100-CMP-001? F-1 Yes [O N/A NDM notified of new records or changes to records that could affect record retention? 13 Yes 1 N/A ofr IformtionFor Form rac iice g Oly- Part of This form is derived from the information in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. 10a, Data Sheet 1, z Review and Approval Tracking Form. Page _ of
REVIEW AND APPROVAL TRACKING FORM Number: PAMI-2080 Rev. 7 . Change:. 0
Title:
Emer*tencvPlan andlmplemenltiflProcedures E Correction (Full Procedure) 0 Change (Full Procedure) with Review of Change Only
] Correction (Page Substitution) .0 Change (Page Substitution) with Review of Change Only El Cancellation . New Procedure or Change with Full Review o Superseded (list superseding procedures):
Change Driver/CD1 Trackdng No(s).: - ON/A 54TRiPe,!gI 11 19 R., V l N` ;. VEg Rm63 Cross-Discipline Reviews: Programmatic Reviews:
X Chemistry 0 Training ALARA Reactivity Mgmt Team 0 Maintenance Ol Work Control - Component Engineering -f SPS (Safety & Health)
El NDM O - 0 Design Engineering . Surveillance Section 0 Operations E__ _ Emerg Oper Proc Grp E System Engineering I1-El PA/PV _ 0 Environmental O SOMS Administrator O Reg Affairs El ISIJIST Coordinator .
0 RP E None Required El Performance Assurance .. None Required :' .
I Cognizant Org Review: <A Date: q 11100
[ T p echnicalRview:n. / Date: 1 I,;11_
.El Ops Director Concuffence: N/A : - Date: _
tJa3EA:gS1Z'Xg~~~~~~~~~~~~~~~~~~~~~~~~
Updated Revision Summary attached? r 14 f 'r ,n i_,r _
10 CER 50.59 Requiremenis complete?
Implementation Plan developed?
- _ .- . tR
- T oe L:
I#,1,,14 4xca
.q1 16
.S, 0 Yes Commitment Database update requested in accordance with PMP-7100-CMP001? -
NDM notified of new records or changes to records that could affect record retention? El Yes I This form is derived from the Information in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. 10a, Data Sheet 1, Review and Approval Tracking Form. . Page ( of__
REVISION
SUMMARY
Number: PMI-2080 Revision: 7 Change: 0
Title:
Emer2enc v Plan Implementing Procedures Section or Step Change/Reason For Change Marginal Markings not used due to the nature of the changes (table).
The Implementation Plan for this revision is the Implementation Plan for Revision 18 of the Emergency Plan.
Step 5.2.1 Change: Added reference to the Emergency Plan Reason: The Emergency Plan -is the governing document for this procedure. Change: The following changes were made to the staffing requirements table based on NRC approval of Revision 18 of the Emergency Plan:
On Shift Column Changed Core and Thermal Hyd on shift person to STA, added 1* for manning column. Moved Unit Supervisors to Plant Operations.
Electrical Maintenance - added 1 I&C Maintenance - deleted 1 Radiological Waste - deleted 1 Protective actions - added 1 Plant Operations - moved Unit Supervisor to Plant Operations On site (out of plant) - deleted 1 In plant surveys - deleted 1 60 Minute Column Added PET-Ops/Training - 1 AEO - added 1 RP Technicians (protective actions) - deleted 2 Reason: 30 minutes response column requirements were deleted with the approval of Revision 18 to the Emergency Plan. Change: Deleted the '30 minutes' and the ** from the table header.
Reason: 30 minutes response column requirements were deleted with the approval of Revision 18 to the Emergency Plan.
~~ ~ OfficeA Inomto orFr rcin ny otPr fFr This is a free-form as called out in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. 10a. Page _ of _
REVISION
SUMMARY
Number: PMI-2080 Revision: 7 Change: 0
Title:
Emergenc y Plan Implementing Procedures Section or Step Change/Reason For Change Attachment 1 Change: Deleted the *** from the Offsite surveys RP Technician.
Reason: 30 minutes response column requirements were deleted with the approval of Revision 18 to the Emergency Plan.
Attachment 1 Change: Changed the total on site personnel to 23.
Reason: 30 minutes response column requirements were deleted with the approval of Revision 18 to the Emergency Plan.
Attachment 1 Change: Replaced the ** note reference to 30 minute staffing requirements with the note for personnel performing other functions.
Reason: 30 minutes response column requirements were deleted with the approval of Revision 18 to the Emergency Plan. Change: Added the third note (***) to explain the I&C and Electrician requirements.
Reason: 30 minutes response column requirements were deleted with the approval of Revision 18 to the Emergency Plan.
Change:
Reason:
00 OffieIformation k o FoTrackin Oni-Not Part of Form' -. <v This is a free-form as called out in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. 10a. Page _ of
ELEMORC PMI-2080 Rev. 7 Page 1 of 9 Emergency Plan and Implementing Procedures Information Effective Date: /
B. K. Molloy S. M. Partin Emergency Planning Writer Owner Cognizant Organization TABLE OF CONTENTS 1 PURPOSE AND SCOPE .2 2 DEFINITIONS AND ABBREVIATIONS. 2 3 DETAILS. 2 4 FINAL CONDITIONS. 5 5 REFERENCES. 6 : Emergency Plan Staffing Requirements .......................................... 7 Figure 1: Cook Plant Emergency Preparedness Advisory Committee ................. 9
Information I PMI-2080 I Rev. 7 1 Pa e 2 of 9 Emergency Plan and Implementing Procedures 1 PURPOSE AND SCOPE 1.1 To establish the administrative controls for protecting the health and safety of the general public and Nuclear Generation Group (NGG) personnel during radiological emergencies at the Donald C. Cook Nuclear Plant.
1.2 To provide the assignment of supervisory responsibilities for the implementation of these administrative controls.
1.3 To detail the minimum on-shift Emergency Plan staffing requirement.
2 DEFINITIONS AND ABBREVIATIONS Term Meaning EPAC Emergency Preparedness Advisory Committee EPM Emergency Planning Manager ERO Emergency Response Organization NGG Nuclear Generation Group NRC Nuclear Regulatory Commission On-Shift Personnel Personnel are on-site at all times.
PORC Plant Operations Review Committee 3 DETAILS 3.1 An Emergency Plan and Emergency Plan Procedures shall be developed for all areas of emergency planning as identified in 10 CFR 50, Appendix E.
3.1.1 Those areas covered by the Emergency Plan shall include, but are not limited to the following:
- a. Organization
- b. Assessment actions
Information I PMI-2080 I Rev. 7 l Page 3 of 9 Emergency Plan and Implementing Procedures
- c. Activation of emergency organizations
- d. Notification procedures
- e. Emergency facilities and equipment
- f. Training
- g. Maintaining emergency preparedness
- h. Recovery 3.2 An Emergency Response Organization (ERO) shall be established, with trained and equipped personnel, to respond to actual or potential radiological emergencies at the Cook Nuclear Plant.
3.3 The Donald C. Cook Emergency Plan and Emergency Plan Procedures shall meet the standards as set forth in 10 CFR 50.47(b), and ANSI N18.7 - 1976/ANSI 3.2, Section 5.3.9.3. As a minimum the Emergency Plan and, as appropriate, Emergency Plan Procedures, shall address the following as specified in 10 CFR 50.47.
3.3.1 Assignment of responsibilities to NGG, the State of Michigan and Berrien County shall be documented.
3.3.2 The responsibilities of on-shift personnel.
3.3.3 Shift staffing requirements to ensure that an adequate accident response capability exists at all times. The capability to augment on-shift capabilities in a timely manner shall also be specified. Attachment 1, Emergency Plan Staffing Requirements, contains the minimum staffing requirements.
3.3.4 Arrangements for requesting and effectively utilizing off-site resources.
3.3.5 A standard emergency classification and action level scheme which shall be coordinated with state and county response plans.
3.3.6 Procedures for notification of state and county response organizations as well as NGG emergency response personnel.
3.3.7 Communications capabilities which facilitate prompt communications among principal response organizations and to the public.
3.3.8 Methods for the dissemination of information to the general public on a periodic basis prior to an emergency.
Information T PMI-2080 _ Rev. 7 l Page 4 of 9 Emergency Plan and Implementing Procedures 3.3.9 Requirements for the provision and maintenance of emergency response facilities.
3.3.10 Methods, systems and equipment for assessing and monitoring actual or potential off-site consequences of a radiological emergency.
3.3.11 A range of protective actions and guidelines for the choice of appropriate off-site protective actions consistent with federal guidance.
3.3.12 Methods shall be established for controlling the radiological exposure of emergency workers.
3.3.13 Arrangements for medical services for contaminated injured individuals.
3.3.14 General plans for recovery and re-entry.
3.3.15 Guidance concerning periodic drills and exercises.
3.3.16 Provisions for radiological emergency response training for those who may be called upon to assist in an emergency.
3.3.17 Responsibilities for plan and procedure development review, revision and distribution.
3.4 The Donald C. Cook Emergency Plan shall provide for agreements of assistance with off-site fire departments.
3.5 Changes may be made to the Donald C. Cook Emergency Plan without NRC approval only if such changes do not decrease the effectiveness of the plan and the plan as changed, continues to meet the standards of 10 CFR 50.47(b), (d), and the requirements for 10 CFR 50, Appendix E (10 CFR 50.54(q)).
3.5.1 The EPM shall determine the extent of change and if a request for NRC approval is required.
3.5.2 All changes to the Emergency Plan shall be made available to the NRC for purposes of information and emergency preparedness.
3.6 The Emergency Plan and Emergency Plan Procedures shall provide for a program that ensures the capability to accurately determine the airborne iodine concentration in areas in the plant where personnel may be present during an emergency. This program shall include training of personnel in accordance with TPD-600-EPT, procedures for monitoring, and provisions for maintenance of sampling and analysis equipment.
Information PMI-2080 I Rev. 7 I Page of 9 Emergency Plan and Implementing Procedures I
3.7 Emergency Plan records shall be prepared and retained as authorized in PMI-2030.
3.8 The Site Vice President's responsibility for the following plant emergency planning duties is delegated to the EPM:
3.8.1 Maintaining the Emergency Plan procedures, facilities and training.
3.8.2 Interfacing with state and local agencies on Emergency Planning issues.
3.9 An EPAC shall be established to create scenarios for and conduct Emergency Plan drills and exercises.
3.9.1 The EPAC is responsible for the evaluation of those drills and exercises and making recommendations for improvements to the EPM.
3.9.2 The EPAC shall meet on an as-needed basis or at the request of the EPM or the Emergency Planning Coordinators.
3.9.3 The committee shall be organized as illustrated in Figure 1, Cook Plant Emergency Preparedness Advisory Committee. The EPAC members shall be chosen by the EPM.
3.10 Plant line management is responsible for supporting the Emergency Plan program and activities.
3.11 The Site Vice President, or designee, will review the critiques of all emergency drills and exercises.
3.12 The PORC will review changes to the Emergency Plan.
3.13 The EPM or designee will review the Emergency Plan Procedures annually.
3.14 The EPM will review proposed changes to facilities and equipment affecting the ERO's functional capabilities.
3.15 The Senior Vice President - NGG, or his designee, is responsible for reviewing all changes to the Emergency Plan.
4 FINAL CONDITIONS None
Information l PMI-2080 Rev. 7 Page 6 of 9 Emergency Plan and Implementing Procedures 5 REFERENCES 5.1 Use
References:
5.1.1 ANSI N18.7 - 1976, Administrative Controls and Quality Assurance for the Operations Phase of Nuclear Power Plants.
5.1.2 10 CFR 50, Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities.
5.1.3 TPD-600-EPT, Emergency Plan Training Program Description 5.1.4 PMI-2030, Nuclear Document Management 5.2 Writing
References:
5.2.1 Source
References:
- b. 10 CFR 50.48(b), Fire Protection
- c. AEP:NRC:9264 5.2.2 General References
- a. Regulatory Guide 1.33, Quality Assurance Program Requirements (Operation)
- b. Unit 1 Operating License, Section 2.1, Iodine Monitoring
- c. Unit 2 Operating License, Section 2.11, Iodine Monitoring
Information PMI-2080 I Rev. 7 Page 7 of 9 Emergency Plan and Implementing Procedures Attachment 1 Emergency Plan Staffing Requirements Pages 7 - 8 Personnel filling the following position must have all of their ERO qualifications up to date.
(Emergency Plan initial training, annual requalification, drill participation within 2 years.)
Table 1 Functional Area On-Shift No. ERO Position 60 min. No.
Plant System Eng Shift Technical Advisor STA 1 Core and Thermal Unit Supervisor 2 (1 per PET-Ops/Training 1 Hydraulics unit)
Electrical PET Maintenance 1 Engineer Mechanical Assistant OSC 1 Manager Repair and Corrective Actions Mechanical Maintenance Mechanic 1** Mechanic 1 Electrical Maintenance Electrical 2*** Electrical 1 I&C Maintenance I&C Technician 1 I&C Technician 1 Radiological Waste AEO 1 Rescue and First Aid Fire Brigade 2** Local Support Protective Actions RP Technicians 2** RP Technicians 4 Fire Protection Fire Brigade Per ATR Local Support Access Control and Security Per Sec. Security Per Accountability Plan Sec.
Plan Plant Operations Shift Manager 1 Work Control SRO 1 Reactor Operators 4*
AEOs 4*
Emergency Direction Shift Manager 1** Site Emergency 1 and Control Coordinator Notification/ AEOs 2 MSP Comm. 2 Communication BCSD Comm.
Radiological Accident Assessment and Support
- a. Direction and Control Emergency Director 1
- b. Offsite dose Reactor Operator 1** Environmental 1 Assessment Assessment Director
- f. Chemistry Chemistry Technician 2 Chemistry Technician 1
Information l PMI-2080 I Rev. 7 _ Page 8 of 9 Emergency Plan and Implementing Procedures Attachment I Emergency Plan Staffing Requirements Pages 7 - 8 Total Onsite (excluding Fire Protection and Security) are 23.
Staffing composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-shift personnel provided immediate action is taken to restore the shift staffing composition to within the minimum requirements of the table in this attachment.
If staffing requirements are not restored within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, a condition report must be written to document the discrepancy.
- Two per operating unit. During an emergency, the unaffected unit staffing is 1 SRO, 1 RO, and 1 AEO.
- May be filled by personnel performing other functions.
Information PMI-2080 Rev. 7 l Page 9 of 9 Emergency Plan and Implementing Procedures Figure 1 Cook Plant Emergency Preparedness Advisory Page 9 1 ~~~~~~~~Committee Pg EMERGENCY PLANNING MANAGER
- 1*
RADIATION CHEMISTRY r
SITE PROTECTIVE OPERATIONS PROTECTION ADVISOR SERVICES ADVISOR ADVISOR ADVISOR I
EMERGENCY PLANNING - n COORDINATORS (4) SIMULATOR FACILITY INSTRUCTORS CONTROLLERS
REVIEW AND APPROVAL TRACKING FORM Procedure__~~~~~~
Information.. ->L<-_ - --- ' ~ -1 Wfmt* .
1T ..v ~ T ___ ._,-"
Number: PiMlP-2080-EPP-100 Rev. 1 Change: 0
Title:
Emergencv Response Catcory (Select One 0y
[i Correction (Full Procedure) l C'hange (Full Procedure) with Review of Change Only Li Correction (Page Substitution) l C_hange (Page Substitution) with Review of Change Only O Cancellation Li Nrew Procedure or Change with Full Review L Supersede.d (list superseding procedures):
Associ3- ration ImpatW ~ -~ ~ _ i*
Change Driver/CDI Tracking No(s).: lg N/A Reqluired Reqired Revlew;s:
Rie~; s , - . ,>. _W . I-' a -
_>. K-! - ~'~-lr - ri- t Cross-Discipline Reviews: Programmatic Reviews:
l Chemistry Z Training O ALARA L Reactivity Mgmt Team O Maintenance E Work Control L Component Engineering O SPS (Safety & Health) l NDM LI _ Design Engineering E] Surveillance Section
[I1 Operations L _ Emerg Oper Proc Grp L System Engineering El PAIPV L V?is E Environmental O L Reg Affairs l l I/ST Coordinator i t.,_
L RP L None Required El Performance Assurance Z None Required 3 Cognizant Org Review: Date: >/ 3 /tC5 3 Technical Review: . Date: /i I..]
Concurrence:. . - -: .;r... z..
El Ops Director Concurrence: N/A Date: / _
Package Check: -- - -
Updated Revision Summary attached? l Yes 10 CFR 50.59 Requirements complete? Tracking No.: 2003-0062-00 _ 1, Yes L N/A Implementation Plan developed? ,. v Step 3.4.17) i Yes MN/A I Package Complete: _ _ __ _ D Date:/2 4!vd c3
.~~~~~4. ___,_ . _ 7§ Approva : - ,. "2- <,"-.
PORC Review Required: 3 Yes a No Mtg. No.:iji1 Y Administrative Hold Status: L R sed [ .eissued 3 N/A CR No.:_
Approval Authority Review/Approva r- 1/4e Date:2 __1L.1k3 Expiration Date/Ending Activity A Effective Date: 2 l.X' 0,j Periodic Review..
Periodic Review conducted? (Data Sheet 5 Complete) l Yes Z No FolloW-up Actions: .; ..
Commitment Database update requested in accordance with PMP-7100-CMP-001?
NDM notified of new records or changes to records that could affect record retention? L 0 Yes Yes 1
] N/A N/A I
Office Inf rmatlon o orm Tracing 6rfly - Not Part of Form
.... :.< ,;.; ^,¢ 5
v This form is derived from the information in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. 10, Data Sheet 1.
z _ Review and Approval Tracking Form. Page of .3
REVISION SUMiMARY Number: PMP-2080-EPP-100 Revision: 1 Change: 0
Title:
Emergency Response Nv 4tI 4 6 .. A .A Section or Step I Change/Reason For Change Step 3.2.3.b Change: Changed step to read 'direct an announcement to be made to evacuate the beach.' after THEN.
Reason: The recorded announcement capability for the beach evacuation system is not functional and obsolete. The change allows the control room to make an announcement using the beach PA system.
Section 3.2 Change: Added step 3.2.3.c to address off site agency personnel located on company property.
Reason: To ensure protective actions are addressed for off site agency personnel.
Step 3.2.6.b Change: Deleted the second 'Attention all personnel' frm the announcement.
Reason: Eliminate redundancy.
Step 3.2.6.c Change: Deleted bullet to press ## to access the PA system.
Reason: Pressing ## is not necessary.
Step 3.2.7 Change: Moved step 3.2.7.b to 3.2.7.d and added '3.2.7.a' to the step to describe a step reference and added 'that is provided to the state' to the end of the step. Also renumbered sub-steps in 3.2.7 to reflect the change in order.
Reason: To correctly describe the order the steps should be performed in and to clarify the step.
Step 3.2.7.c (old Change: Added title of Flowchart.
d) Reason: Conform to format. Correction: k Step 3.2.7.e Change: Added EMD-32 as the form number, changed inform' to
'notify' and added the reference to PMP-2080-EPP-107 at the end of the step.
Reason: Conform to format and clarify step. Correction: k, r Section 3.2 Change: Added new Step 3.2.11 and renumbered remaining step in Section 3.2.
Reason: To prompt the SM to consider incoming plant personnel and any special instructions that may be necessary for their protection.
__lOfice Iiformation Foi`Foini.i' inj Only- Not Part6f Form -
This is a free-form as called out in PMP-2010-PRC-002, Procedure Correction, Change, and Rview, Rev. 10. Page J of3
REVISION SUIMIARY Number: PMP-2080-EPP-100 Revision: I Change: 0
Title:
Emergency Response Section or Sten Change/Reason For Change Section 3.3 Change: Added new Step 3.3.5 and renumbered remaining steps in Section 3.3.
Reason: To ensure that the control room makes the necessary announcements when classification responsibility resides with the TSC or EOF.
Attachment 1 Change: Replace Attachment 1 with the PAR Attachment from RMT-2080-EOF-001.
Reason: Make PAR development consistent between procedures.
Data Sheet 1 Change: Deleted 'RCS PARAMETER' above the list of parameters.
Reason: Not all parameters were RCS parameters.
Data Sheet 1 Change: Deleted asterisks from all parameters in the data sheet.
Reason: Not necessary for the Data Sheet to be filled out by a control room operator. Allows flexibility for the SM.
Data Sheet 1 Change: Added Containment High Range Radiation Levels to the list of parameters.
Reason: This is a parameter that is used for classification and is needed by the TSC and EOF.
Data Sheet 1 Change: Changed RHR Injection Flow units to GPM from psig.
Reason: Flow is measured in GPM. Correction: h Data Sheet 1 Change: Corrected typo on Steam flow, feed flow and Aux. feed flow units to correct scientific notation units. (added superscript)
Reason: Corrected typo. Correction: h Data Sheet 1 Change: Re-aligned the parameters on the page.
Reason: Improve readability. Correction: k Data Sheet I Change: Deleted note at bottom of Data Sheet that required data to be taken by a control room operator.
Reason: Allow flexibility for the SM Figure 1 Change: Modified procedure flowchart as required for the procedure changes.
Reason: Make flowchart correct.
This is a free-form as calie:d out in PMP-2010-PRC-002, Proccdurc Correction, Change, and Review, Rev. 10. Page of ___
IC:RKARmic PMIP-2080-EPP-100 Rev. 1 Page 1 of 21 Emergency Response Reference Effective Date: .2/'I 3 B. K. Molloy 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 .................................... 3 4 FiNAL CONDITIONS ............................... 8 5 REFERENCES .......................................................................................... 8 : PAR Flowchart and Map ...................... 10 Data Sheet 1: Technical Information Sheet ...................... 12 Data Sheet 2: Emergency Turnover Checklist ...................... 14 Figure 1: Procedure Flowchart ...................... 18
Reference PMP-2080-EPP-100 I Rev. 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 PAR Protective Action Recommendation PPC Plant Process Computer SAE Site Area Emergency
Reference PMP-2080-EP ORev. 1 e3o 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 DETALS 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.
3.1.5 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. 1 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 I 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.
3.2.3 IF a SAE or GE has been declared, THEN notify the Security Shift Supervisor (x 2005 or 2731) to perforni 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.
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.
Reference l PMP-2080-EPP-100 1 Rev. I Page 5 of 21 Emergency Response 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-EOF001, Activation and Operation of the EOF
,1 (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:
- a. Call the SAS (x 118) and direct security to implement the Dialogic Emergency Response Notification System for an EMERGENCY.
- 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/TechnicalSupport CenterlEmergenay QperationsFacilitv All other plant personnel be prepared for further announcements."
- c. On any touch-tone telephone:
Dial 1646 Wait for the tone Repeat the above announcement twice
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.
- b. Obtain the following data:
. Wind direction
- AND -
Offsite dose projection (if available) as calculated using DAP or actual offsite dose rate measurements.
- d. Include any deviations from the PAR flowchart, Attachment 1, based on step 3.2.7.a in the protective action recommendation that is provided to the state.
- 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.
3.2.10 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).
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.
Reference _ PMP-2080-EPP-100 Rev. 1 r Page 8 of 21 Emergency Response 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.
3.3.7 Assemble all documentation associated with the emergency and forward it to the Emergency Planning Coordinator. This documentation should include:
- Complete notification forms
- Copies of pertinent log entries
- Copy of the Condition Report if generated Other documentation deemed appropriate by the Shift Manager 4 FINAL CONDITIONS 4.1 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
Referee IPMP-2080-EPP-100 -Rev. Page 9 of21 Emergency Response 5.2.2 General References
- a. Michigan Emergency Preparedness Plan
- b. NRC Regulatory Issue Summary, RIS-2002-21
Rcfcrence _ PMP-2080-EPP-100 Rev. 1 l Page 1 of 21 Emergency Response PAR Flowchart and Map Pages:
10 -11
- 0. R&,,Atpmiles I I R.A&Dto5mifes i I and2
Reference I PMP-2080-EPP-100 I Rev. 1 l Page 11 of 21 Emergency Response Attachment PAR Flowchart and Map Pa10-11 C emru r;gh Schoof High School 10 miles
- .f]C / / ~~~Br fntOWr1 R j 2 \
f New tZ_ .Vlft~ak___e _ mie
,_ , __rws
-/ ] N,IewEufflo,~ Tbrrf Oas 1 A
- - . - * -oo - i*- Bertr h hoo
Reference PMP-2080-EPP-100 I Rev. 1 Page 12 of 21 Emergency Responsc Data Sheet I Technical Infornation Sheet Pages:
Unit No: Date: Time: ,
Data Taken By: Data Reviewed By:
NOTE: When redundant indication exists, record most severe condition.
I. Containment Temp. OF 5. Intermediate Range AMPS
- 2. Cont. H2 Concentration 6. Containment Pressure PSIG
- 4. Source Range CPM 8. Containment Level
- 9. Containment High Range Radiation Level Upper/Lower / R/HR
- 9. CTS Pumps East ON / OFF West ON / OFF
- 10. RHR Spray Flow East GPM West GPM
- 11. SI Flow North GPM South GPM
- 12. BIT Flow LP GPM LP2 GPM LP3 GPM LP4 GPM
- 14. RHR Injection Flow East GPM West GPM
- 18. PZR Liquid Temp. OF 24. PZR Cycling Htrs ON / OFF
- 19. PZR Steam Temp. OF 0 25. PZR Backup Htrs ON / OFF
=_ _ _ _
- 20. PZR Level 26. Letdown Flow GPM
- 21. PRT Temp. OF 27. Saturation Margin OF
Reference I PMP-2080-EPP-100 l-Rev. 1 I Page 13 of 21 Emergency Response Data Sheet Technical Information Sheet I Pages:
NSSS LOOP PARAMETERS Loop 1 Loop 2 Loop 3 Loop 4
- 28. Wide Range T Hot OF OF OF OF
- 29. Wide Range T Cold OF OF OF OF
- 31. S G N. R. Level
- 32. S / G W .R. Level
- 33. Steam Flow (pph x 106)
- 34. Feed Flow (pph x 106)
- 35. Aux. Feed Flow (pph x 103)
- 36. MSIV Status OPEN / CLOSE OPEN / CLOSE OPEN / CLOSE OPEN / CLOSE
- 37. CST Level Ft
- 38. Steam Dump ATMOS t COND EQUIPMENT STATUS AVAILABLE / lJNAVAILABLE
- 39. East ESW AVAILABLE / UNAVAILABLE
- 49. East CCP
- 42. West CCW =____ I
- 52. EMDAFP
- 43. East CTS I _____
- 53. WMDAFP = I =~~
- 45. North SI = ~~I /
- 55. CD Diesel
- 46. Soutlh SI 56. Normal Res. _
- 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 Time:
- b. Michigan: yes / no / in progress Time:
- c. NRC: yes / no / in progress Time:
- d. NGG Personnel: yes I no / in progress Time:
- 3. Protective Actions:
- a. Local area evacuation yes / no Time:
- b. Site evacuation yes / no Time:
- c. Accountability yes / no Time:
- d. Site closed to visitors yes / no Time:
- e. Offsite protective action recommended:
. Evacuation: yes / no areas: Time:
. Shelter: yes / no areas:' Time:
Referene PMIP-2080-EPP-100 I Rev. 1 L Pge 15o 21 Emergency Response Data Sheet 2 Emergency Turnover Checklist Pages:
14 - 17
- 4. Plant Operational Status
- a. Reactor trip: yes / no time: ______ Trip signal:
- b. ESF Status:
- c. EOP Status:
- 5. Plant Status
- a. Chronology of Events Time Event
- b. Current Plant Conditions
Reference _ PMP-2080-EPP-100 r Rev. 1 I Page 16 of 21 Emergency Response Data Sheet 2 Emergency Turnover Checklist Pages:
- c. Potential for Plant Degradation
- d. Mitigating Actions Taken or Underway
- 6. Plant Radiological Conditions
- a. Inplant/Onsite Radiological Conditions
Reference-PMP-2080-EPP-100 ReV. age 17 of 21 Emergency Response Data Sheet 2 Emergency Tumover Checklist P 1 1 ~~~~~~~~~~~14
- 7
- b. Potential for Offsite Release of Radioactivity Airborne Water
- 7. Injured or Contaminated Personnel:
Name Employer Status
Reference I PMP-2080-EPP-100 Re. age 18 of 21.
I ~~ ~~~-Emergency Response 1iur Procedure Flowchart Pages:
Figure I 1 18 -21 Emergency delcared Per PMP-2080-EPP-1O1 II ,
3.2.3 3.2.3.a 3.2.3.b y%<. Yes No No 3.2.4.b
Reference I PMP-2080-EPP-100 Rev. 1 Page 19 of 21 Emergency Responsc Figure Procedure Flowchart Pages:
Figure 1 I I - 21 I
Reference I PMP-2080-EPP-100 I Rev. 1 Page 20 of 21 Emergency Response Figure I Procedure Flowchart Pages:
I 1- ~ -21
~~~~~~~~18
Reference PMP-2080-EPP Rev. ge 21 of 2T Emergency Response Figure_I Procedure Flowchart Pages:
Figure 1 18 - 21 3.3.3 and 3.3.4 r
Inform TSC of plant changes and mitigating actions planned or completed 3.3.5 Direct announcements as necessary or upgrades I.
3.3.6 r
equest assistance rrom TSC as necessary
REVIEW AND APPROVAL TRACKING FORM Number: PMEP-2080-EPP-101 Rev. 3b Change: 0
Title:
Ernergency! Clasfcto
'61fi~~~~~~~~~~~~~*
0"7"Correction (Full Procedure) El c'hange (Full Procedure) with Review of Change Only El Correction (Page Substitution) El c.hange (Page Substitution) with Review of Chang-e Only El Cancellation El 'lew Procedure or Change with FuIl Review El Superseded (list superseding procedures):
Change Driver/CDI Tracking No(s).:____________________ D N/A ki'de aqZM 8'-' '5V_ 'K Cross-Discipline Reviews: Programmatic Reviews:
ElChemistry El Training, ED ALARA El Performance Assurance ElMaintenance ElWork Control ElBus. Services Proc Grp ElReactivity Mgmt Team ElNDM EElComponent Engineering ElSPS (Safety & Health)
ElOperations El_____ lDesign Engineering - lSurveillance Section ElPA/PV El_____ El Emerg Oper Proc Grp ElSystem Engineering El Reg Affairs E_____ El Environmnental E ______
El RP 0None Required El IS1/IST Coordinator 0None Required El Cognizant Org Review: ____________________ Date: /
0 Technical Review: c 4"_ Date: 1(1 / 1576 ElC OpNgroc r e ce / ae El OwneMr Concurrence: N/A Date: / /
Updated Revision Summary attached?0 Yes 10 CFR 50.59 Requirements complete? Tracking No.:____________ EYes 0N/A Implementation Plan developed? (Ref. Stp 34 18) El Ys ON/A Package Complete: ae i/*Qj _
PORC Review Required: Yes LI No Mtg. No.:39IL?i2 C 4'C4 Administrative Hold Status: El Released 6J,tesred 0N/A CR No.:______
Approval Authority Review/Approval: Date: IL2i ioi Expiration Date/Ending Activity Effective Date: a/7 /0/
Periodic Review conducted? (Data Sheet 5 Complete) El Yes 0No ICommitment Database Updated?
NDM notified of new records or changes to records that could affect record refention?
ElYes El Yes 0 N/A 0 N/A
/ This form is derived from the information in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. 9, Data Sheet 1, Review and Approval Tracking Form. Page- of _
REVISION
SUMMARY
Number: PMIP-2080-EPP-101 Revision: 3b Change: 0
Title:
Emer2enev Classification Two corrections are being made due to changes in 10CFR50.72 and a change in the UFSAR.
Section or Step Change/Reason For Change Attachment 3, Change: Added 'dose consequence' between 'rupture' and 'analysis' in Basis for SG tube the paragraph labled 'LOSS' - second to last line.
leakage Correction Criteria - r Reason: License Amendments 256 and 239 (UCR 1264) implemented a new analysis method for SG overfill during a SG tube rupture.
Previously, the SG overfill analysis was the same as the dose consequence analysis. The correction clarifies that the basis for the classification is related to the still valid dose consequence analysis.
Attachment 3, Change: In the fourth line under BASIS, changed 'one' to 'four'.
Basis for Tech Correction Criteria- m Spec time liCnoit exceeded. Reason: 10CFR50.72, Non-emergency reporting section was changed to require a four hour report in the event that a Tech Spec shutdown was required. This is correctly referenced in PMP-7030-001-001, Rev. 6 which has had a 50.59 screening performed on it.
Change:
Reason:
Change:
Reason:
ffi'rmayii'l, w Fa'6 m &Ting"11i a-+b'tfi riA .E This is a free-form as called out in PMP-2010-PRC-002, Procedure Correction, c Change, and Review, Rev. 9. Page - of -
CItK PMP-2080.EPP.101 Rev. 3b Page 1 of 114 Emergency Classification Reference EffectiveDate:,/7/1 B. K. Molloy P.E. Holland Site Protective Services Writer Owner Cognizant Organization TABLE OF CONTENTS 1 PlURPOSE AND SCOPE ......................................... 2 2 DEFINITIONS AND ABBREVIATIONS ......................................... 2 3 DETAILS ......................................... 6 4 FINAL CONDITIONS ......................................... 7 5 REFERENCES ......................................... 7 : Emergency Condition Categories .8 : Critical NUREG 0737 Paraeters .21 : Basis For Emergency Action Levels (Commitment: 6489) ................. 22
Reference PMP-2080.EPP.101 Rev. 3b l Page2 of 114 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 abnornal 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), c6ntainment, 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 Tree determined in accordance with the Emergency Operating (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
Reference I PMP-2080.EPP.101 I Rev. 3b I Page 3 of 114l Emergency Classification Term Meaning emergency class.
Emergency These are taken from 10 CFR 50- Appendix E. They are in 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 A logical 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
. 4KV rooms
Reference I PMP-2080.EPP.101 Rev. 3b I Page4 of 114 Emergency Classification Term Meaning
- Vicinity of all Local Shutdown Stations Safe Shutdown Selected components deemed necessary to place and maintain Equipment 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 systems
Reference PMP-2080.EPP.101 l Rev. 3b I Page 5 of 114 Emergency Classification Term Meaning.
to bring the reactor to a new safe, steady-state condition.
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
- 4 Kv switchgear rooms and security power supply room
- UPS battery and inverter rooms
- Central alarm station
Reference PMP-2080.EPP.101 I Rev. 3b Page 6 of 114 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 Review ALL appropriate Initiating Conditions within the selected Recognition Categories starting in the left-most applicable column.
3.1.2 Determine whether the threshold values for Emergency Classification have been exceeded.
- a. Attachment 2 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.
3.1.3 The Initiating Conditions in Attachment 1 that are marked with an E 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 Condition boxes in Attachment 1 refer to the appropriate section of the basis pages, Attachment 3.
3.1.4 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 Attachment 3.
Reference l PMP-2080.EPP.101 I Rev. 3b Pane 7 of 114 Emergency Classification 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:
- Critical Safety Function Status Trees
- Additional radiation monitor alarms
- 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, "Methodology for Development of Emergency Action Levels"
- b. NUMARC/NESP-007, Rev. 4, "Methodology for Development of Emergency Action Levels'
- 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'
- 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
Page Emergency Condition Category 9 Fuel Clad Barrier Loss/Potential Loss Table 9 RCS Barrier Loss/Potential Loss Table 10 Containment Barrier Loss/Potential Loss Table 11 ECC H-1 SEC Judgement 12 ECC H-2 Security Events 12 ECC H-3 Control Room Evacuation 12 ECC H-4 Fire 12 ECC H-5 Toxic or Flammable Gases 13 ECC N-1 Seismic Activity 13 ECC N-2 Tornado/High Wind 13 ECC N-3 Visible Structural Damage 13 ECC N-4 Vehicle Collision 13 ECC N-5 Main Turbine Rotating Component Failure 13 ECC N-6 Plant Flooding 13 ECC N-7 Unanticipated Explosion 14 ECC R-1 Radioactive Effluent Release 14 ECC R-2 Increasing In-Plant Radiation Level 14 ECC R-3 Loss of Water Level in Any Area Holding Irradiated Fuel 15 ECC S-1 Failure of Reactor Protection System 15 ECC S-2 Loss of AC Power (Modes 1-4) 15 ECC S-3 Loss of DC Power (Modes 1-4) 15 ECC S-5 Loss of Systems Needed to Achieve/Maintain Hot Shutdown 16 ECC S-7 Fuel Clad Degradation 16 ECC S-8 Excessive RCS Leakage 16 ECC S-9 Tech Spec Compliance 16 ECC S-10 Loss of Communication Systems (Modes 1-4) 17 ECC H H-5 Hazards and Other Conditions (Modes 5, 6) 18 ECC N N-7 Natural/Destructive Phenomena (Modes 5, 6) 19 ECC R R-3 Abnormal Radiation Levels/Effluents (Modes 5, 6) 20 ECC C-3 Cold Shutdown/Refueling/Defueled - Loss of AC Power (Modes 5, 6) 20 ECC C-4 Cold Shutdown/Refueling - Inability to Maintain Cold Shutdown 20 ECC C-5 Cold Shutdown/Refueling - Fuel Clad Degradation (Modes 5, 6) 20 ECC C-6 Cold Shutdown/Refueling - Loss of Communications (Modes 5, 6) 20 ECC C-7 Cold Shutdown/Refueling - Loss of DC Power (Modes 5, 6)
Reference I PMP-2080.EPP.101 l Rev. 3b Pa e 11 of 114 Emergency CLASSIFICATION Attachment Emergency Condition Categories 8 - 20 SEC Judgement: SEC Judgement may be used to determine that a Fission Product Barrier is LOST or POTENTIALLY LOST based on factors other than those 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 SITE AREA EMERGENCY ALERT UNUSUAL EVENT SEC Judgenent - All Modes 11-1 SEC Judgenent (p.46) H-1 SEC Judgement (p.45) 11-1 SEC Judgement (p.44). H-1 SEC Judgement (p.42)
Conditions indicate actual 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 danage 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.
£ EAL's in tese tables are NOT complete. Refer to referenced basis page (Attachment 3) for complete description.
- 'p >*!
'*,- J:
FISSION PRODUCT BARRIER MATRIX - Mode 1- 4 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Loss of TWO Fission Product Any TWO of the Followiig: 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. -
- 1. FUEL CLAD BARRIER LOSS (L) POTENTIAL LOSS (P)
.1 Core Cooling CSFST RED Core Exit Thermocouples > 752-OR RVLIS Level < 46% (Narrow Range)
.2 Containment Radiation > 200 Rlhr. None
.3 Primary Coolant Activity >300 uCi/cc 1-131 dose equivalent None OR Core Damage > 5.0% clad failure
- 2. RCS BARRIER LOSS (L) POTENTIALLOSS P)
.1 RCS Leak Rate (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 OIIP 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 SG.
.3 Containient Radiation > 10 Rlhr None
.4 RCS Integrity CSPST None RED
.5 lIeat Sink CSFST None RED Does not include a release through the condenser sir ejectors or the gland steam condenser vents for the purpose of declaration of a SITE AREA EMERGENCY.
1.3 FISSION PRODUCT BARRIER MATRIX - Mode 1-4 GENE RAL EIERGENCY Loss of TWO Fission Product SITE AREA EMERGENCY rALERT I UNUSUAL E ENT 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.
- 13. Loss of Containrent Barrier.
- 3. CONTAINMENT BARRIER LOSS (L) POTENTIAL LOSS (P)
.1 Containment Radiation None > 1000 R/hr.
.Core _ dam age > 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 S Secondary Side Release la. Primary to secondary leak rate > Tech. Spec. limit. (p35) None AND
- b. Secondary line break OUTSIDE Containment results In release
(>30 min.) to the environment.
- 2. Release of secondary coolant from the affected SC to the -
environment with ilert alarm on any SG PORV rad monitor.' E
.4 Containment CSFST None RED
.5 Contaitiment lydrogen None >4.0%
OR Containment lydrogen >0.5% AND any lydrogen Control equipment
.6 Containmenit Pressure Control Noneioerbe inoperable.
.6 Contanmeiit Cntrol Pessure Noe BOTH CTS trains OR 130Tl containent air recirc fans inoperable OR fail to auto start on teir containment pressuire setpolnt OR containment pressure
.7 Core Exit Termocouples None Core Cooling CSFST - RED
_oe o s tnotei gnl dnear l etes t r m uhhcconesdeirneeet rosv nt o t e Resto ra to n pro cedur s not effe ctiv e with in 15 minutes.
Does not include a release through the condenser air ejectors or the gland steam condenser vents for the prpose of declaration of a SITE AREA EMERGENCY.~
Reference _ IMP-2080.EPP.101 Rev. 3b Page 12 of 114 Emergency CLASSIFICATION Attachment 1 Emergency Condition Categories Pages:
INITIATING CONDITIONS - Mode 1- 4 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT IIAZARDS AND OTIIER CONDITIONS 11-2 Security (p.50) H-2 Security (p.4 9) 11-2 Security (p. 4 8) II-2 Security (p. 47 )
Security Event resulting in loss of ability Security event in a Vital Atea. Security Event in the Protected Area. Security Event that potentially degrades level of to reach and maintain Mode 5. I.lntrusion 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.Loss of physical control of remote SD capability. OR OR 3.Confirmed bomb in Vital Area. 3.Credible attack threat.
OR 4.1Hostage/extortion potentially affecting plant operations.
11-3 CR Evacuation (p.52) 11-3 CRL Evacuation (p.51)
Control Room evacuated AND control not Control Room evacuation initiated, established in 15 minutes. S 11-4 Fire (p.55) H-4 Fire (p.5 4 )
Fire OR explosion affecting plant operations. Fire in Protected Area NOT extinguished
. within 15 minutes of detection.
11-5 Toxic Gas (p.58) 11-5 Toxic Gas (p.56)
Toxic OR flammable gas release that Toxic OR flammable gas release threatens lives OR affects ability to affecting plant operation.
achieve and maintain Mode 5. E
Reference PMP-2080.EPP.101 b Page 13 of 114 Emergency CLASSIFICATION Attachment 1 Emergency Condition Categories 8 -20 INITIATING CONDITIONS - Mode 1- 4 GENERAL EMERGENCY I SITE AREA EMERGENCY ALERT lUNUSUAL EVENT l NATURAL/DESTRUCTIVE PIENOMENA N-1 Seismic (p. 62) N-1 Seismic (p.60)
Seismic event Indicated by: Seismic event indicated by:
I .Scismic 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. E N-2 Tornadolwind (p.62) N-2 Tornado/vind (p.6 0)
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 to achieve and maintain Mode 5.
N-4 Vehicle Collision (p.62) N-4 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 Faillre(p.60)
Main turbine generated missie penetrates Vital Area. Main turbine rotating component failure causes
__ ___ __ visible damage or damages generator seals.
N-6 Flooding (p.62)
Flooding in Vital Area affects safety related equipment.
N-7 Explosloii (p.60)
Unanticipated explosion within Protected Area causes visible damage to permanent structures or I_equipment.
Reference I PMP-2080.EPP.101 Rev. 3b Page 14 of 114 Emergency CLASSIFICATION Pages:
Attachment 1 1 Emergency Condition Categories S - 20 INITIATING CONDITIONS - Mode 1- 4 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT ABNORMAL RADIATION LEVELSIEFFLUENTS R-1 Effluent release (p.71) R-1 Efrluent release (p.69) R-1 Effluenit release (p.67) R-1 Effuent release (p.65)
Site boundary dose > I REM TEDE or 5 REM CDE Site boumdary dose > 100 mrem TEDE Unplanned Rad release >200X ODCM limits Unplanned Rad release >2X ODCM limits for to thyroid based on: or 500 mrem CDE to thyroid based on: for > 15 min. based on: > 60 minutes based on:
I.Survey results I.Survey results OR OR 1.200X rad nionitor high alarm setpoint. 1.2X rad monitor high aann setpoint.
2.Dose assessment 2.Dose assessment OR OR OR OR 2.Gas or liquid sample results. 2.Gas or liquid sample results.
3.Emuent monitor readings > 15 minutes 3.Effluent monitor readings > 15 minutes.
R-2 Plant Rad level (p.74) R-2 Plant Rad level(p.73)
Rad levels that Impede plant operations based Unexpected reading on Area Monitor IOOOX 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.78) R-3 Loss of level (p.76)
Major damage to rradiated fuel or loss of Uncontrolled lowering in refueling cavity, SP level that has or will uncover fuel outside of or Transfer Canal indicated by:
the reactor vessel based on:
I.Visual observation of levels. I.lnability 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 rfueling cavity 3.Level < 632'4' SFP or Transfer Canal. with irradiated fuel in containment.
Reference I PMP-2080.EPP.101 I Rev. 3b Page 15 of 114 Emergency CLASSIFICATION Attachment 1 Emergency Condition Categories Pages:
INITIATING CONDITIONS - Mode 1-4 I GENERAL EMERGENCY I SITE AREA EMERGENCY I ALERT l UNUSUALEVENT l SYSTEM MALFUNCTIONS S-I RPS failure (p.83) S-I RPS failure (p.82) S-l RPS failure (p.80)
I .Auto and manual Reactor Trip fails from Control Auto and manual Reactor Trip fails from Auto Reactor Trip fails AND manual trip Rm AND Suberiticality and Core Cooling CSFSTs Control room. successful from Control Room.
are RED OR 2.Subcriticality and Ileat Sink CSr'STs are RED.
S-2 Loss or AC (p.88) S-2 Loss of AC (p.87) S-2 Loss of AC (p.86) S-2 Loss of AC (p.85)
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 irs.
Loss of ALL vital DC buses AD AND CD for
> 15 minutes (bus volts < 220v)
S-5 Loss of Ilot SD sys (p.91)
Loss of ability to achieve or maintain hot shutdown based on entiy into:
I.OIIP 4023.FR-H. 1, Response to Loss of Secondary leat Sink OR 2.011P 4023.FR-C.1, Response to Inadequate Core Cooling.
(7 Reference I PMP-2080.EPP.101 Rev. 3b Page 16 of 114 Emergency CLASSIFICATION Attachment 1 l Emergency Condition Categories Pages:
INITIATING CONDITIONS - Mode 1-4 GENERAL EMERGENCY SITE AREA EMERGENCY 'ALERT UNUSUAL EVENT SYSTEM MALFUNCTIONS S-6 Loss of Alarms (p.97) S-6 Loss or Alarms (p.94) S-6 Loss or Alarms (p.92)
Loss of ability to monitor alarms during a Unplanned loss of most or all Safety System ILUnplanned 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 panel(s) for > 15 minutes with transient in progress or minutes.
> 15 minutes. compensatory tndicators 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). Z S-7 Degrade(d Clad (p.99) l.RCS activity > 1.0 uCI/gram 1-131 dose equivalent for > 48 hrs.
OR 2.RCS activity > 100/1 uCi/gram.
S-8 RCS Leakage (p.100)
RCS leakage exceeds 10 gpm pressure boundary leakage, SG tube leakage or unidentified leakage OR > 25 gpm dentified leakage.
S-9 Tecli Spec (p. 101)
Unit not in required mode within LCO time linits.
S-10 Loss of Conini. (p.102)
Unplanned loss of all on or off-site communications
I:- . .-
- Rcference I PMP-2080.EPP.101 I Rev. 3b Page 17 of 114 Emergency CLASSIFICATION Attachment 1 Emergency Condition Categories 8 - 20 INTIATING CONDITIONS - Mode 5 & 6 and Defueled GENEIAL EMERGENCY I SITE AREA EMERGENCY ALERT UNUSUAL EVENT IIAZARDS AND OTIIER CONDITIONS 11-2 Security (p.50) 11-2 Security (p.49) H-2 Security (p.48) II-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 5. 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.
- 2. Loss of physical control of remote SD OR OR capability. 3. Confirmed bomb in Vital Area. 3. Credible attack threat.
- 4. Hostage/extortion potentially affecting plant uperations.
11-3 CR Evacuation (p.52) H-3 CR Evacuation (p.51)
Control Room evacuated AND control not Control Room evacuation initiated.
established within 15 minutes.
E 11-4 Fire (p.55) 11-4 Fire (p.54)
Fire OR explosion affecting plant operations. Fire in Protected Area NOT extinguished within
. 15 minutes.
H-5 Toxic Gas (p.58) 11-5 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 Rev. 3b IPMP-2080.EPP.1l Page 18 of 114 Emergency CLASSIFICATION Pages:
Attachment 1 1 Emergency Condition Categories 8 - 20 INITIATING CONDITIONS - Mode 5 & 6 and Defueled I GENERAL EMERGENCY I SITE AREA EMERGENCY I ALERT l UNUSUAL EVENT =
NATURAL/DESTRUCTIVE PHENOMENA N-1 Seismlc(p.62) N-1 Selsmic (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.
- 2. > 90 mph wind for > 15 minutes.
N-3 Structtiral (p.62)
Visible damage to a structure containing systems required to achieve and maintain Mode 5.
N-4 Vehicle Collision (p.62) N-4 Vehicle Collision(p.60)
Vehicle collision affecting Vital Atea. Vehicle collision affects systems or structures
.__________________________________________ in the Protected Area.
N-S IT 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)
Flooding in Vital Area affects safety related equip.
N-7 Explosion (p. 6 0)
Unanticipated explosion within Protected Area catises visible damage to permanent structures or equipmeit.
t-W ..
Reference I PMP-2080.EPP.101 I Rev. 3b Page 19 of 114 Emergency CLASSIFICATION Attachment 1 l Emergency Condition Categories Pages:
INITIATING CONDITIONS - Mode 5 & 6 and Defueled GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT ABNORMAL RADIATION LEVELS/EFFLUENTS R-1 Erfitent release (p.71) R-1 Effluent release (p.69) R-1 Effluent release (p.67) R-1 Eriluent release (p. 6 5 )
Site boundary dose > I REM 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 to thyroid based on: or 500 mnrem CDE to thyroid based on: > 5 minutes based on: > 60 minutes based on:
I.Survey results OR I.Survey results 1.200X rad monitor high alarm setpoint. 1.2X rad monitor 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.74) R-2 Plant Rad level (p.73)
Rad levels that impede plant operations based on: Unexpected reading on Area Monitor IOOOX the 24 hr average.
- 2. > 100 nfhr at remote S/D areas.
R-3 Loss of level (p.78) R-3 Loss of level (p.76)
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. lInability to maintain > 643'4" In SFP or Transfer OR Canal with irradiated fuel present, 2.Rad monitor alarms OR OR 2,lnability to maintain > 643'4' in the refueling cavity 3.Level < 63i-4' SFP or Transfer Canal. with irradiated fuel in containment.
F-. .. /.
Reference l PMP-2080.EPP.101 I Rev. 3 Page 20 of 114
'Emergency CLASSIFICATION Pages:
Attachment 1 1 Emergency Condition Categories 18 - 20 INITIATING CONDITIONS - Mode 5 & 6 and Defueled GENERAL EMERGENCY I SITE AREA EMERGENCY ALERT UNUSUAL EVENT COLD SIIUTDOWN/REFUELING SYSTEM MALFUNCTIONS C-3 Loss or AC(p.105) C-3 Loss of AC (p.103)
Loss of ALL AC power to A and D T-buses for Loss of ALL OFF-SITE power (Auxiliary,
> 15 minutes. Reserve and 69kv transformers) to the T buses for > 15 minutes.
Mode 5,6 and defueled - Mode 5,6 C-4 Loss of Water Level n the Reactor Vessel C-4 Inability to Maintain a Unit in that has or will Uncover Fuel in the Reactor . Cold Shutdown (p.10 7 )
Vessel (p.109) I.Loss of shutdown cooling as evidenced by entry I.Loss of shutdown cooling as evidenced by entry into OIIP Into OIIP 4022.017.001. Loss of RIIR Cooling' 4022.017.001, 'Loss of RHR Cooling' AND AND 2.Temperature rise that either:
2.Core uncovery as indicated by: a. Exceeds TIS cold shutdown limit of 200 F.
- 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-5 Degraded Clad (p.110)
I.RCS activity > 1.0"lCi/grams 1-131 dose equivalent for > 48 hrs.
. 2.RCS activity > 00/E uCllgram.
Mode 5,6 C-6 Loss of Comm. (p.111)
Unplanned loss of all on or off-site communications.
Mode 5,6 C-7 Loss of DC power (p.113)
Unplanned loss of ALL vital DC buses AB AND CD for > 15 minutes (bus volts <220v)
Modes 5,6
fe-Reference PMP-2080.EPP.101 Rev. 3b Page 21 of 114 Emergency CLASSIFICATION Attachment 2 Critical NUREG 0737 Parameters Page:
21 PARAMETERS INSTRUMENTATION Neutron Flux - (Gammametrics) NRI-21, 23 Reactor Coolant Pressure (Wide Range) NPS-121, 122 Reactor Coolant Outlet Temperature THOT (Wide Range) NTR-110, 130 Reactor Coolant Outlet Temperature 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) NLI-110, 111, 120, 121, 130, 131 Pressurizer Water Level NLP-151, 152, 153 Charging Pump Flow IFI-51, 52, 53, 54 Charging Pump Breaker Status lE, 1W, 2E, 2W Control Room Position Indicating Lights for Breakers Safety Injection Pump Breaker Status 1N, 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 Liglts 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 Generator 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 I PMP-2080.EPP.101 I Rev. 3b IPae 22 of 114 Emergency CLASSIFICATION
--3 Iacunen 1 Basis For Emergency Action Levels Pages:
Attachment 3 (Commitment: 6489) 1 22 - 114 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 > 752°
-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 I PMP-2080.EPP.101 I Rev. 3b I Page 23 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
ent!-1 3 (Commitment: 6489) 22 - 114 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 Rlhr.
POTENTIAL LOSS:
None BASIS (References)
LOSS - The 200 Rlhr value is based on a reasonable assessment of a single number representing the expected monitor reading on the upper contaimnent area radiation monitors VRA 1310/1410 (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 contaimnent radiation monitors will read 1325 Rlhr 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:
Reference I PMP-2080.EPP.101 I Rev. 3b IPae 24 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
(Commitment: 6489) 1 22 -114 Calculation of radiation monitor reading is based on dispersal of noble gases only (iodine inventory not included) from the reactor coolant.
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.
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
FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION RCS BARRIER 2.1: RCS LEAK RATE MODE APPLICABILITY Modes 1, 2, 3, 4 EAL THRESHOLD VALIES:
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 altemate 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 inabiity 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 I PMP-2080.EPP.101 I Rev. 3b I Page 27 of 114 Emergency CLASSIFICATION Attachment 3 l Basis For Emergency Action Levels Pages:
I (Commitnent: 6489) 22 - 114 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 I PMP-2080.EPP.101 l Rev. 3b I Page 28 of 114 Emergency CLASSIFICATION Attachment 3 l Basis For Emergency Action Levels Pages:
(Commitment: 6489) 1 22 - 114 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION RCS BARRIER 2.3: CONTAINIENT 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. 3b I Page 29 of 114 Emergency CLASSIFICATION Attachmnent 3 Basis For Emergency Action Levels Pages:
(Commitment: 6489) I 22 - 114 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION RCS BARRIER 2.4: RCS INTEGRITY CSFST MODE APPLICABILITY 1,2,3,4 EAL THRESHOLD VALUUE 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. 3b Page 30 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
(Commitment: 6489) 22 - 114 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 I PMP-2080.EPP.101 I Rev. 3b I Page 31 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
I I (Comitment: 6489) 1 22-114 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 determined on 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 contaimnent 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 I PMP-2080.EPP.101 I Rev. 3b I Page 32 of 114 Emergency CLASSIFICATION Attachmnent 3 l Basis For Emergency Action Levels Pages:
I ~ (Commitment: 6489) 22 - 114 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.E-0, "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-1.2 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 I PMP-2080.EPP.101 I Rev. 3b I Page 33 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
(Commitment: 6489) 22 - 114 DEVIATION FROM NUMARC: None
Reference I PMP-2080.EPP.101 I Rev. 3b I Page 34 of 114 Emergency CLASSIFICATION Attachmnent 3 t Basis For Emergency Action Levels Pages:
I (Commitment: 6489) 22 - 114 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION CONTTAINMENT 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 larger breaks, if the steam generator remains unisolated, this EAL will be a discriminator for SITE AREA AND GENERAL EMERGENCIES. The threshold for Site Area Emergency is based on elevated RCS activity indicated by an alert alarm on a SG PORV radiation monitor.
Reference I PMP-2080.EPP.101 I Rev. 3b I Page 35 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
Attachmen 3 l(Commitment: 6489) l 22 - 114 v 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 Pc/cc I-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 I PMP-2080.EPP.101 l Rev. 3b I Page 36 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
I l (Commitment: 6489) 22 - 114 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION CON'TAINMENT BARRIER 3.4 - CONTAINMENT CRITICAL SAFETY FUNCTION STATUS TREE MODE APPLICABILITY 1, 2, 3,4 EAL THRESHOLD VALUE LOSS:
None POTENTLAL 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
Reference I PMP-2080.EPP.101 I Rev. 3b I Page 37 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
Attachment 3 (ComIitment: 6489) 22 - 114 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION CONTAINMENT BARRIER 3.5: CONTAINMENT HYtDROGEN 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 I PMP-2080.EPP.101 I Rev. 3b I Page 38 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
I (Commitment: 6489) l 22 - 114 DEVIATION FROM NUMARC:
A threshold value has been added for hydrogen concentration greater than 0.5% and key hydrogen control equipment inoperable.
JI
Reference PMP-2080.EPP.101 I Rev. 3b I Page 39 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
(Commitment: 6489) 22- 114 FISSION PRODUCT BARRIER NAME, LOSS/POTENTIAL LOSS, & DESCRIPTION CONTAINMENT BARRIER 3.6 - CONTAINMENT 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 contaimnents, it relies more heavily on engineered safety features for overpressure protection than do dry containrnents. 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
Reference I PMP-2080.EPP.101 I Rev. 3b I Page 40 of 114 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
Attachment 3 I ~ (Commitment: 6489) 22 -114 until the ice has melted. Therefore, if these systems should fail, it is pernissible to start both these 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 symptouiatic of major system degradation.
DEVIATION FROM NUMARC:
None.
Reference I PMP-2080.EPP.101 - Rev. 3b I Page 41 of 114 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
Attachment I (Commitment: 6489) 22 - 114 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 scenarios, 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 thernocouples greater than 752 degrees F and RVLIS (Reactor Vessel Level Indication System) -narrow range less than 46% with no reactor coolant punp running. This represents a mrore 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 I PMP-2080.EPP.101 Rev. 3b Page 42 of 114 Emergency CLASSIFICATION Ataln 3Basis For Emergency Action Levels Pages:
Attachment3 (Commitnent: 6489) - 22 - 114 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H-1: UNUSUAL EVENT - SEC JUDGEMENT 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.
- 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.
Reference PMP-2080.EPP.101 Rev. 3b I Page43 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
[ Attachment 3 (Commitment: 6489) I 22 - 114 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.
TERMINLTION/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 I Rev. 3b P2ge 44 of 114 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
Attachment 3 (Commitment: 6489) 22 - 114 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H-1: 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.
TERMINIATION/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 PIP-2080.EPP.101 I Rev. 3b I Pace 4 Of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
Attachment 3 (Commitment: 6489) .22 - 114 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.
TERMINIATION/RECOVERY 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 7 PMP-2080.EPP.101 Rev. 3b Page 46 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels l Pages:
_ Attachment 3 (Commitment: 6489)22-114 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H-1: 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.
TERMINIATION/RECOVERY 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 I PMP-2080.EPP.101 I Rev. 3b Page 47 of 114 Emergency CLASSIFICATION Attc n 3Basis For Emergency Action Levels Pages:
Attachment 3 l (Commitment: 6489) l 22 - 114 D 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 I PMP-2080.EPP.101 I Rev. 3b I Page 48 of 114
[ Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
l (Commitment: 6489) 1 22 - 114 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 VALUTE
- 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 I PMP-2080.EPP.101 I Rev. 3b I Page 49 of 114 Emergency CLASSIFICATION Attachrnent 3 Basis For Emergency Action Levels Pages:
Attachment 3 (Commitment: 6489) 1 22 - 114 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.
TERMINIATION/RECOVERY CRITERIA The condition causing the event has been eliminated.
DEVIATION FROM NUMARC: None'
Reference I PMP-2080.EPP.101 l Rev. 3b I Paoe 50 of 114 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
Attachment 3 (Commitment: 6489) 22 - 114 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.
TERMNIATION/RECOVERY CRITERIA The security threat has been eliminated and cold shutdown can be maintained.
DEV7IATION FROM NUMARC: None
Reference PMP-2080.EPP.101 I Rev. 3b I Page 1 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
Attachment 3 l (Commitment: 6489) 22 - 114 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 deterrnined 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 and establishing plant control outside the control room is (01-for Unit 1, 02-for Unit 2) OHP 4025.001.001, "Emergency Remote Shutdown".
TERMINIATION/RECOVERY CRITERIA Control of the plant has been reestablished from the control room.
DEVIATION FROM NUMARC: None
Reference I PMP-2080.EPP.101 Rev. 3b I Page 2 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
i Attachment 3 (Commitment: 6489) 22 - 114 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
- 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 esiablishing 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 NUMARCINESP 007.
TERMEiIATION/RECOVERY CRITERIA Control of the plant has been reestablished from the control room.
DEVIATION FROM NUMARC: None
Reference I PMP-2080.EPP.101 I Rev. 3b I Page 53 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
(Commitment: 6489) 22 - 114
- The inability to establish control of RCS inventory, RCS temperature, reactivity and heat sink functions at the affected unit's hot shutdown panel within 15 minutes requires the declaration of a site area emergency.
Reference I PMP-2080.EPP.101 I Rev. 3b I Page 54 of 114 Emergency CLASSIFICATION Attachment 3 l Basis For Emergency Action Levels Pages:
Attachment 3 (Commitment: 6489) 1 22 - 114 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-1: 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-5, 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.
TERMINIATION/RECOVERY CRITERIA Fire Extinguished.
DEVIATION FROM NUMARC: None
Reference I PMP-2080.EPP.101 Rev. 3b I Paoe 55 of 114 Emergen'y CLASSIFICATION Basis For Emergency Action Levels Paaes:
3 (Attachment (Coniitment: 6489) 1 22 -114 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION 114: 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 V7ALUE
- 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: contairunents, 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 I PMP-2080.EPP.101 Rev. 3b I Paoe 56 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
I (Commitment: 6489) 1 22 - 114 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H-5: UNUSUAL EVTENT - TOXIC OR FLAMMABLE GASES INITIATING CONDITION Release of toxic or flamnmable 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. [Commitment 5572]
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 flamnmable 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. 3b Page 57 of 114 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
Attachment 3 (Commitment: 6489) 22 - 114 The release of toxic material is terminated and the operational impact of the release has been eliminated.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101 Rev. 3g Pane 58 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
(Commitment: 6489) 22 - 114 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION H-5: ALERT - TOXIC OR FLAMMABLE GASES INITIATING 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 OHP4021-028-014, 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. [Commitment 5572]
EAL THRESHOLD VIALUE
- 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 I PMP-2080.EPP.101 I Rev. 3b I Page 59 of 114 Emergency CLASSIFICATION Att enBasis For Emergency Action Levels Pages:
AItachmentI3 (Commitment: 6489) 22 - 114 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.
TERME\IATION/RECOVERY CRITERIA Plant operations are no longer affected.
DEVIATION FROM NUMARC: None
Reference I PMP-2080.EPP.101 I Rev. 3b I Pane 60 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
AtRachment I (Commitment: 6489) 22 - 114 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION N-1 to N-7: UNUSUAL EVENT - NATURAL OR DESTRUCTIVE PHENOMENA ISIDE THE PROTECTED AREA INITIATING CONDITION Natural or destructive phenomena inside protected area.
MODE APPLICABILITY All EAL THRESHOLD VALlUE
- 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 confirmation call to the National Earthquake Center will confirm that an earthquake has occurred ax;d may provide 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 l PMP-2080.EPP.101 I Rev. 3b I Pao,e 61 of 114 Emergency CLASSIFICATION
. Attachment 3 Basis For Emergency Action Levels Pages:
Attachment 3 8 2
! ~(Cornmitment: 6489) 1 22 -114 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 tomado 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 PMP 2081 EPP.306, De-escalation of Termination of the Emergency and Recovery".
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 I PMP-2080.EPP.101 1 Rev. 3b I Paoe 62 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
(Commitment: 6489) 22 - 114 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 potential 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 I PMP-2080.EPP.101 I Rev. 3b I Page 63 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
Attachment 3 (Commitment: 6489) 22 - 114 Operator walkdowns of plant systems, structures and components will be performed to assess potential damage levels.
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 - 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 H-4 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.
TERMINIATION/RECOVERY CRITERIA No further hazard exists, damage assessment is complete, and termination is allowed in accordance with the requirements of PMP 2081 EPP.306, "De-escalation or Termination of the Emergency and Recovery".
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
Reference I PMP-2080.EPP.101 I Rev. 3b I Page 64 of 114 Emergency CLASSIFICATION Attchn Basis For Emergency Action Levels Pages:
I (Commitment: 6489) 22'- 114 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 I Rev. 3b I Pace 5 of 114 Emergency CLASSIFICATION Attachmnent 3 Basis For Emergency Action Levels Pages:
Attachment I (Commitment: 6489) I 22 - 114 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION R-1: UNUSUAL EVENT - RADIOACTIVE EFFLUENT RELEASE INITLITING 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-1800/2800 (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 PMP-2080.EPP.101 Rev. 3b Pane 66 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
AttachmentI3 (Commitment: 6489) 22 - 114 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 concem.
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-1500/2500),
the gland steam condenser exhaust effluent monitors (SRA-180012800), 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 I PMP-2080.EPP.101 l Rev. 3b I Paoe 67 of 114 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
Attachmnent 3 (Commitnent: 6489) l 22 - 114 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 I PMP-2080.EPP.101 I Rev. 3b Page 68 of 114 Emergency CLASSIF1CATION Attachment 3 Basis For Emergency Action Levels Pages:
Attachment 3 (Commitment: 6489) 22 - 114 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 niR/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.
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 I PMP-2080.EPP.101 I Rev. 3b I Page 69 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
I (Commitment: 6489) 1 22 - 114 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 THPESHOLD VALUE
- 1. Field survey results indicate site boundary dose rates exceeding 100 mRlhr B-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 uci/cc (Unit Vent).
- VRS-1800/2800 > 7.90 EOp.ci/cc (Steam Packing Exhauster)
- SRA-1900/2900 > 1.95 E+3 tci/cc (Air Ejector)
- MRA-1600/2600 > 1.00 E+2 p.ci/cc (SG PORV) 1700/2700 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)
Reference PMP-2080.EPP.101 I Rev. 3b I Page 70 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
Attachment 3 (Commitment: 6489) 22 - 114 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.
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.
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 PMTP-2080.EPP.101 Rev. 3b Page 71 of 114 Emergency CLASSIFICATION Attachment 3 l Basis For Emergency Action Levels Pages:
A (Commitment: 6489) 22 - 114 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 5116]
EAL THRESHOLD VALUE
- 1. Field survey results indicate site boundary dose rates exceeding 1000 mR/hr P - 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 lici/cc (Unit Vent)
- SRA-1800/2800 > 1.57 E+2 lici/cc (Steam Packing Exhauster)
- SRA-1900/2900 > 5.78 E+3 1ici/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 ronitor 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 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. 3b I Paoe 72 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
Attachin I (Commnitment: 6489) 22 - 114 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 I hour 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 I PMP-2080.EPP.101 I Rev. 3b Page 73 of 114 Emergency CLASSIFICATION Attachment 3 l Basis For Emergency Action Levels Pages:
I - (Commitment: 6489) 22 - 114 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION R-2: UNUSUAL EVENT - RISING IN-PLANT RADIATION LEVELS INITIATING CONDITION Unexpected higher in plant radiation levels.
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.
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 mR/hr 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 impaired 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 I PMP-2080.EPP.101 l Rev. 3b I Page 75 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
I (Commitment: 6489) 1 22 - 114 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.
TERMINIATIONIRECOVERY 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 I PMP-2080.EPP.101 I Rev. 3b I Page 76 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
(Commitment: 6489) _ 22 - 114 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 observatioh 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 'h" above the top of the fuel) and low level alarm (RLA-501 644'-2 1/2h" 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 l PMP-2080.EPP.101 I Rev. 3b I Page 77 of 114 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
Attachment 3 (Commitment: 6489) 22 - 114 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 I Rev. 3b I Paoe 78 of 114 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
(Commitment: 6489) 22 - 114 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 instrumerit 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 timne available to take corrective actions, and there is little potential for substantial fuel damage. In addition, NUREG/CR-4982 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 wamed that the level drop is occurring via the spent fuel pool
Reference I PMP-2080.EPP.101 Rev. 3b I Page 79 of 114 Emergency CLASSIFICATION Attachment 3 l Basis For Emergency Action Levels Pages:
I I (Commitment: 6489) 22 - 114 low level alarm (RLA-500 at 644'9" or 24'-5 'A" above the top of the fuel) and low level alarn (RLA-501 644'-2 11" 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 1101/1201 and 2101/2202 are the upper contairmnent area radiation monitors, and are set to alarm at 54 mR/hr. 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
Reference I PMP-2080.EPP.101 I Rev. 3b I Page 80 of 114 Emergency CLASSIFICATION Atah .. . 1 Attachment 3 Basis For Emergency Action Levels I -r (Commitment: 6489)
Pages:
22 - 114 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-1: 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 TIRESHOLD 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 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.
Reference PMP-2080.EPP.101 I Rev. 3b I Page 81 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
(Commitment: 6489) 22 - 114 DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101 I Rev. 3b I Page 82 of 114 Emergency CLASSIFICATION Atachment 3 r Basis For Emergency Action Levels Pages:
i Attachment3(Commitment: 6489) 1 22 - 114 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-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 I and 2 EAL THRESHOLD VALUE An anticipated transient without scram (ATWS) was NOT terninated 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 I PMP-2080.EPP.101 I Rev. 3b Page 83 of 114 Emergency CLASSIFICATION Attachment 3 l Basis For Emergency Action Levels Pages:
I (Commitment: 6489) - 22 - 114 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-1: 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 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 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 700°F. This GE EAL equates to a Core Cooling RED condition.
Reference I PMP-2080.EPP.101 l Rev. 3b I Page 84 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
I (Commitment: 6489) 1 22 - 114 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.
TERMINIATION/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. 3b Page 85 of 114 Emergency CLASSIFICATION Attachment 3 l Basis For Emergency Action Levels Pages:
AttaIbment 3 (Comrmitment: 6489) 22 - 114 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)
- 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 reserve transformers. Backfeed through the unit auxiliary transformers is also considered an adequate source of offsite power.
TERMINIATION/RECOVERY CRITERIA A reliable power supply to ESF buses from offsite sources is re-established.
DEVIATION FROM NUMARC: None
Reference I PMP-2080.EPP.101 I Rev. 3b I Page 86 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
(Commitment: 6489) 1 22 - 114 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-101AB/TR-201AB
- TR-lO1CD/TR-201CD
- TR-1AB/TR-2AB
- TR-lCD/TR-2CD
- EDG ABIEDG 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 I PMP-2080.EPP.101 I Rev. 3b I Pace 87 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
I (Commitment: 6489) 22 - 114 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. TIlA, TIlD (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-0.0, "Loss of All AC Power", no specific time limitation is given for restoration of power to the emergency buses. Therefore, Cook 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 I PMP-2080.EPP.101 I Rev. 3b I Page 88 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
Attachment I (Commitment: 6489) 22 - 114 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. TIlA, TlD (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. TlA, T11D (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 containmnent. 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 blackout (SBO) coping category.
This IC is specified to assure that in the unlikely event of a prolonged station blackout timely recognition of the seriousness of the event occurs and that declaration of a General Emergency occurs
Reference I PMP-2080.EPP.101 I Rev. 3b Page 89 of 114 Emergency CLASSIFICATION Attachmnent 3 Basis For Emergency Action Levels Pages:
(Commitment: 6489) 22 - 114 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.
Reference I PMP-2080.EPP.101 T Rev. 3b Paoe 90 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
c men (Commitment: 6489) 22 - 114 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
Reference i PMP-2080.EPP.101 I Rev. 3b I Page 91 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
I (Commiitment: 6489) 22 -114 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-H1, "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.
TERMINIATIONIRECOVERY CRITERIA Hot Shutdown operation is capable of being maintained.
DEVIATION FROM NUMARC: None
Reference PMP-2080.EPP.101 I Rev. 3b I Pave 92 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
(Commnitment: 6489) 22 - 114 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, 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)
- Containrent Pressure (Narrow Range)
- Containmnent Hydrogen Monitoring
- Containment Isolation Valve Position Monitoring
- Containrment Area Radiation Monitors (High Range)
- Steam Line Pressure
Reference I PMP-2080.EPP.101 I Rev. 3b I Page 93 of 114 Emergency CLASSIFICATION I Attachment 3 Basis For Emergency Action Leve] Pages:
L ~~ ~~1(Commitment: 6489) 22 - 114
- 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-Alarning 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.
TERMINIATION/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 I PMP-2080.EPP.101 I Rev. 3b I Paoe 94 of 114 Emergency CLASSIFICATION
~
Attachment 3 j Basis For Emergency Action Levels Pages I ~~ ~ ~I.(Commitment: 6489) 1 22 - 114 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, and 4 EAL THRESHOLD VIALUE
- 1. Loss of one of the following:
- a. Loss of one or more safety system annunciator panels in a unit for > 15 mninutes:
- Panels 104-114, 119, 120 (Unit l)
- 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)
- Contaimnent Hydrogen Monitoring
- Containment Isolation Valve Position Monitoring
- Containment Area Radiation Monitors (High Range)
- Steam Line Pressure
Reference I PMP-2080.EPP.101 I Rev. 3b I Page 95 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
I (Commitment: 6489) 22 - 114
- 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. 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 inforrnation (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 indicate herein.
TERMINIATION/RECOVERY CRITERIA
Reference I PMP-2080.EPP.101 I Rev. 3b I Page 96 of 114 Emergency CLASSIFICATION i Attachment 3 Basis For Emergency Action Levels Pages:
I[ (Commitment: 6489) 1 22 - 114 The miniimum number of required annunciators is restored to operabilih,r and an investigation of the cause of the problem is in progress.
DEVIATION FROM NUMARC: None
Reference I PMP-2080.EPP.101 Rev. 3b Page 97 of 114_
Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
l(Commitment:
Attachmen 3 6489) l 22 - 114 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 VALULE 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
- Containment Pressure (Wide Range)
- Containment Pressure (Narrow Range)
- Containment Hydrogen Monitoring
- Containment Isolation Valve Position Monitoring
- Containment Area Radiation Monitors (High Range)
- Steam Line Pressure
Reference I PMP-2080.EPP.101 l Rev. 3b Page 98 of 114 Emergency CLASSIFICATION Attachment 3 l Basis For Emergency Action Levels Pages:
Attachment 3 (Commitment: 6489) 1 22 - 114
- 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/recorders/computer 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 I PMP-2080.EPP.101 Rev. 3b Page 99 of 114 Emergency CLASSIFICATION Attachment 3 - Basis For Emergency Action Levels Pages:
(Commitment: 6489) l 22 - 114 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-7: UNUSUAL EVENT - FUEL CLAD DEGRADATION IITIATING CONDITION Indication of Fuel Clad Degradation in Active Fuel MODE APPLICABILITY All EAL THRESHOLD VALUE
- 1. Activity > 1.0 plCilgram 1-131 dose equivalent for >48 hours in the RCS.
-OR-
- 2. RCS activity > 1001E pCi/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 I-131 levels are greater than the limits of technical specifications Figure 3.4-1, or gross radioactivity levels are > 100/E liCiIgram.
The coolant sample activity values indicate fuel clad degradation greater than technical specification allowable limits.
TERMINIATION/RECOVERY CRITERIA Technical specification 3.4.8 limit or action requirements are met.
DEVIATION FROM NUMARC:
Cook Plant does not have failed fuel monitors.
Reference P1IP-2080.EPP.101 l Rev. 3b I Page 100 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
(Commitment: 6489) 1 22 - 114 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 values 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 I PMP-2080.EPP.101 I Rev. 3b Page 101 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
(Comnitment: 6489) 22 - 114 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S-9: UNUSUAL EVENT - TECHNICAL SPECIFICATION TIME LIMIT EXPIRED INITIATING 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 camot 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 irnmediate 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 System Malfunction, Hazards, or Fission Product Barrier Degradation ICs.
TERMIATION/RECOVERY 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 I PMP-2080.EPP.101 I Rev. 3b I Panye 102 of 114 Emergency CLASSIFICATION Basis For Emergency Action Levels Pages:
(Counitment: 6489) 22 - 114 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 cormnunication capabilities:
Telephone (offsite)
Microwave transmission NRC phone State Police/Sheriff Department Emergency Radios BASIS (References)
UNPLANNED - The loss of communication js 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 coununications 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 least one form of onsite and offsite communications has been established.
DEVIATION FROM NUMARC: None
Reference I PMP-2080.EPP.101 Rev. 3b Paoe 103 of 114 Emergency CLASSIFICATION Attachment 3 l Basis For Emergency Action Levels Pages:
1(Commitment:
Attachmen 3 6489) 1 22 - 114 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 transfonner are LOST to the T-buses for > 15 minutes.
- a. Normal Auxiliary Power Source (Auxiliary Transformer)
- TR 1AB /TR 2AB
- b. Preferred Offsite Power Sources (Reserve Transformer)
- TR 101AB /TR 201AB
- 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 the reserve transformers. During outages, switchyard power may be supplied via the normal transformers aligned
Reference I PMP-2080.EPP.101 l Rev. 3b I Page 104 of 114 Emergency CLASSIFICATION Attachmnent 3 l Basis For Emergency Action Levels Pages:
Attacrnen 3 (Commitment: 6489) L 22 - 114 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
Reference I PMP-2080.EPP.101 I Rev. 3b I Page 103 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
I (Commitment: 6489) 22 - 14 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 ESSENTLAL BUSES INITATING 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 ninutes when fuel is in the reactor.
- a. T1lA, T11D (Unit 1)
-OR-
- b. T21A, T21D (Unit 2)
- 2. Loss of power to all the following buses when defueled T11A, TlD, T21A, T21D 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 he'at 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 be sufficient to provide emergency power to required plant safety systems.
TERMINIATION/RECOVERY CRITERIA Restore power to at least one T-bus.
DEVIATION FROM NUMARC:
Reference I PMP-2080.EPP.101 I Rev. 3b I Page 106 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
I (Commitment: 6489) _ 22 - 114 This EAL is specified by loss of essential pump buses rather than loss of transformers and emergency generators.
Refserence I PMP-2080.EPP.101 I Rev. 3b I Pa e 107 of 114 Reerc Emergency CLASSIFICATION Attachment 3 l Basis For Emergency Action Levels Pages:
Attachment (Commitment: 6489) 1 22 - 114 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION C4: 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°F
-OR-
- b. results in an UNCONTROLLED increase in RCS temperature rise approaching the cold shutdown techriical 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 from temperatures much lower than 200°F. The inability to reach cold shutdown is to include instances where decay heat removal capability is lost prior to reaching the cold shutdown mode.
Reference I PMP-2080.EPP.101 i Rev. 3b I Page 108 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
I c -I (Commitment: 6489) e 22-- 114 TElRMINIATION/RECOVERY CRITERIA Cold shutdown conditions have been established and can be maintained.
DEVIATION FROM NUMARC None.
Reference PMP-2080.EPP.101 Rev. 3b Page 109 of 114 Emergencv CLASSIFICATION Attachment 3 l Basis For Emergency Action Levels l Pages:
(Commitment: 6489) 22 -114 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION C-4: 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:
-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 functiohs 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.
Reference PMP-2080.EPP.101 I Rev. 3b I Page 110 of 114 Emergency CLASSIFICATION i Attachment 3 I
Basis For Emergency Action Levels (Commitment: 6489)
Pages:
22 - 114 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.
Reference PMP-2080.EPP.101 I Rev. 3b Page 111 of 114 Emergency CLASSIFICATION Attachment 3 Basis For Emergency Action Levels Pages:
(Commitnent: 6489) 22 - 114 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 form of onsite and offsite communications has been established.
Reference I PMP-2080.EPP.101 I Rev. 3b I Page 112 of 114 Emergency CLASSIFICATION Attachment 3 l Basis For Emergency Action Levels Pages:
l (Commitment: 6489) 1 22 - 114 DEVIATION FROM NUMARC: None
Reference I PMP-2080.EPP.101 I Rev. 3b I Page 113 of 114 Emergency CLASSIFICATION Attachmnent 3 l Basis For Emergency Action Levels Pages:
(Commitment: 6489) 22 - 114 ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION C-7 UNTUSUAL 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 I PMP-2080.EPP.101 I Rev. 3b I Page 114 of 114 Emergency CLASSIFICATION i Attachment 3 Basis For Emergency Action Levels Pages:
I ~~~~~~~~(Comimitment: 6489) 1 22 - 114 The 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 Refieling 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
REVIEW AND APPROVAL TRACKING FORM LI- UCLtJUF iniormation: , -, +, t t
=
$l- '_ -' --
Number: PMP-2080-EPP-107 _ Rev. 17 Change: 0
Title:
Notiication Category (Sel&ct .Oe6vmnK & ,-
E Correction (Full Procedure) 3 Change (Full Procedure) with Review of Change Only l Correction (Page Substitution) El Change (Page Substitution) with Review of Change Only El Cancellation [l New Procedure or Change with Full Review El Superseded (list superseding procedures):
Ass"iated
-' Coiif' aex 6n fq_ija_c-
- . - #q MPp
'v, ax Change Driver/CDT Trackinp No(s): Rl N/A Required Reylewss. : .'-l Cross-Discipline Reviews: Programmatic Reviews:
El Chemistry 0 Training El ALARA El Reactivity Mgmt Team El Maintenance El Work Control El Component Engineering El SPS (Safety & Health)
EUNDM _ El Design Engineering E Surveillance Section 0 Operations El El Emerg Oper Proc Grp El System Enginecring E PAtPV E El Environmental El El Reg Affairs E El ISI/TST Coordinator El E RP E None Required El Performance Assurance 0 None Required 3 Cognizant Org Review:
z Technical Review:
Concurrence: I. -
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Updated Revision Summary attached? 0 Yes 10 CFR 50.59 Requirements complete? Tracking No.:_2003-0061-00 0 Yes E N/A Implementation Plan developed? (Ref. Step 3.4.17) El Yes ON/A Package Complete: Wm Date: L_/Jq/ 03 Approvas-_`1= M^
PORC Review Required: 3 Yes El No Mtg. No.: 9 r, &1 Administrative Hold Status: E Rel sed l Reissued Z N/A CR No.:_
Approval Authority Review/Approval: . ** __ Date: 2 124 103 Expiration Date/Ending Activity // i N Effective Date: j28/ 0t Periodic,Revie'w: :_ir ;s , =
Periodic Pview condrcted? (Data Sheet 5 EI Yes IFollow-up Actions: -- - -
Commitment Database update requested in accordance with PMP-7100-CMP-001?
NDM notified of new records or changes to records that could affect record retention? l Yes O NA Ii
> I r *+ T'Tc-rac ing ni5, - Not .Pait &CFi-This form is derived from thc information in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. 10, Data Sheet I, /
Revicw and Approval Tracking Form. Page _ of
REVISION SIIARY Number: PMP-2080-EPP-107 Revision: 17 Change: 0
Title:
Notification Section or Step Change/Reason For Change All No marginal markings used.
Section 1 Change: Added Step 1.2 to allow steps to be performed out of the written sequence.
Reason: Allow flexibility for the SM/SEC to address unforeseen circumstances.
Section 2 Change: Added abbreviations for ERO, EOF, TSC, OSC, JPIC, ENC, SAS to list.
Reason: Comply with format. Correction: k Section 2 Change: Combined the definitions of Drill and Exercise. Deleted information about phone calls from definition.
Reason: Terms are used interchangeably. Phone call information was incorrect.
Section 3.2 Change: Added Caution prior to step 3.2.1 warning that 911 or 007 codes shall not be used for drills, exercises or training.
Reason: Clarify when to use the codes.
Step 3.2.1 Change: Added 'or an Unusual Event has been declared and ERO facility staffing is desired'.
Reason: Clarify when the ERO is paged.
Step 3.2.1 Change: Added ENC/ to first bullet.
Reason: Correct an omission.
Step 3.2.1 Change: Added 'reporting from off site' to first line of second bullet.
Reason: Clarify who goes to Buchanan.
Step 3.2.2 Change: Added the conditional at the beginning of the step.
Reason: Clarify when to call security.
Step 3.2.2.a Change: Added step to address potentially unsafe conditions for personnel reporting to the plant.
Reason: Enhance the procedure.
Step 3.2.3 Change: Renumbered and clarified step to make the actions easier to understand added guidance for modifying the announcements.
Reason: Clarified actions.
L____ o ffice Inf6rmation ForForm.Tracking O N thPari of 1orm l
This is a free-Form as called out in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. 10. Page L _o l
REVISION SUMIARY Number: PMP-2080-EPP-107 Revision: 17 Change: 0
Title:
Notification Section or Step Change/Reason For Change Step 3.2.3 Change: Deleted one of the 'Attention all personnel' phrases from each of the announcements.
Reason: Eliminate redundancy.
Step 3.2.3.c Change: Added action to sound the Containnent Evacuation alarm.
Reason: To help ensure that all personnel on site are notified.
Step 3.2.5.a Change: Added 'a' before Nuclear Accident...
Reason: Grammar. Correction: a Step 3.2.5.b Change: Added Note prior to first bullet and changed area code for the
- county.
I i ,
Reason- Clarifying information on what the MSP may do., Phone number change.
Step 3.2.5.b Change: Added conditional statement to the end of the second bullet to provide phone directions.
Reason: The county EOC may not answer directly.
Step 3.2.5.d and f Change: Added 'the' before Nuclear Accident...
Reason: Grammar. Correction: a Step 3.2.7 Change: Added 'or as directed by the MSP' to end of second bullet.
Reason: The MSP may provide other guidance for faxing.
Step 3.2.8 Change: Added new step 3.2.8. Renumbered remaining steps in section 3.2.
Reason: To clarify when the EMD-32a and EMD-32b forms must be sent to the state.
Step 3.2.10 (old Change: Added 'or the PAR changes' to the first line.
step 3.2.9) Reason: To include all requirements for notification.
Attachment I Change: Replaced EXERCISE, DRILL with the correct terms:
Step 1.1 Announced or Unannounced Drill.
Reason: Correct terms.
- 4A.'.;A .. sg t--..Sr -
- '--ffice TIfforation or formy- ItTr- - Pt f F rm N t.Prt :.
This is a free-form as called out in PMP-2010-PRC-002, Procedure Correction, Change, and Revicw. Rev. 10. Page 1 of
REVISION
SUMMARY
Number: PMP-2080-EPP-107 Revision: 17 Change: 0
Title:
Notification Section or Step Change/Reason For Change Attachment 1 Change: Added 'and the Containment Evacuation Alarm' after Nuclear Step 1.3 Emergency Alarm.
Reason: Make drills consistent with real requirements.
Attachment 2 Change: Deleted one of the phrases 'This is a test' from announcement.
Step 1.1.2 Reason: Eliminate redundancy.
Attachment 2 Change: Added 'when the ERO pager activates' to the second Step 1.1.2 announcement.
Reason: To clarify when to call dialogic. Change: Added 'when the ERO pager activates' to the second Step 1.1.3 , announcement.
Reason: To clarify when to call dialogic. Change: Deleted one of the phrases 'This is a test' from announcement.
Step 1.1.3 Reason: Eliminate redundancy. Change: Rewrote entire step to reflect the new method for testing the Step 1.1.4 Beach Evacuation system.
Reason: Taped announcement capability does not exist. PA announcement will be made by operators.
Data Sheet 1 Change: Changed the area code for the Berrien County Sheriff.
Reason: Phone number change. Correction: e Data Sheet 2 Change: Added a note to the beginning of the DS stating that the DS does not have to be sent to the NRC unless the NRC requests it.
Reason: Clarify the use of the DS.
Data Sheet 2 Change: Added 'Yes No' to shutdown margin item. Added question marks after items asking for a yes/no answer.
Reason: Clarify requirements.
Data Sheet 2 Change: Added 'Heat' to 'RCS Transport Control'.
Reason: Clarify the title of the section.
'- ' nfornation For1 nOfice eigWdiig Only =NoVPart of Form , - - -
Thts is a free-form as called out in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. 10. Page Q off
REVISION SUMiMIARY Number: PiNIP-2080-EPP-107 Revision: 17 Change: 0
Title:
Notification Section or Step Change/Reason For Change Data Sheet 2 Change: Under 'RCS Heat Sink' changed 'Containment' to 'RCS'.
Reason: Containment is incorrect.
Data Sheet 2 Change: Added directions and blanks for checking equipment/methods available based on plant conditions.
Reason: Clarify DS requirements.
-> : -~ 'Office nformation For Form Trink OxiW t Part f F i This is a free-forTn as called out in PMP-2010-PRC-002, Procedure Correction, - 7 Change, and Review, Rev. 10. Page < of j
ruc"trip l PIMP-2080-EPP-107 Rev. 17 Page I of 14 Notification Reference Effective Date: 02,'28/03 B. K. Molloy S. M. Partin Site Protective Services Writer Owner Cognizant Organization TABLE OF CONTENTS 1 PIURPOSE AND SCOPE......................... ................................................................................ 2 2 DEFINITIONS AN-D ABBREVIATION~1 17 ........................................................................... 2 3 DETAILS.................................................. ,.............................................................................. 3 4 FINAL CONDITIONS............................ ,.............................................................................. 7 5 REFERENCES ........................................ ............................................................... ..... a........o : Drills and Exercises ............................. 9 : Communication System Tests ............................. 10 Data Sheet : Shift Manager Initial Notification List ............................. 12 Data Sheet 2: Plant Status .......... ; 13
Reference I PNIP-2080-EPP-107 I Rev. 17 I Pagc 2 of 14 Notification I 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 differcnt sequence.
2 DEFINITIONS AND ABBREVIATIONS Term Ieaning DrilllExercise 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 MISP 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 Turnover ADialogic Emergency Response Organization pager
Reference l P.P-2080-EPP-107 l Rev. 17 Page 3 of 14 Notification activation that signals a change in the on-duty team.
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-perfonn 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 b recognized. J 3.2 Actions CALTION: Do not use the 91 1 or 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, THIEN determine where the ERO should respond.
- Code 91 I' 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-10_ Rev. 17 Pag 4 f i4 Notification 3.2.2 IF a pager code was identified in step 3.2.1, THEN call the SAS at extension 1118 or II 19 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.
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 an Unusual Event exists, THEN perform step 3.2.3.a.
- IF an Alert exists, TIJEN perforn step 3.2.3.b.
- IF a Site Area Emergency or General Emergency exists, THEN perform step 3.2.3.c.
Modify the announcements in steps 3.2.3.a, 3.2.3.b, and 3..3.c as necessary to ensure that:
Directions to activate the ERO facilities are only given ONE time for the event in progress.
- Accountability is performed only ONE time for the event in progress.
- Other contingencies are addressed as determined by the SEC (e.g.,
security concems, radiation release, etc.).
- a. FOR .AN UNUSUAL EVENT:
"Attention all personnel. An Unusual Event has been declared due to (brief descriptioq_ Continue with your work and be prepared for future announcements."
Reference PM[P-2080-EPP-107 J -Rv 7Page 5 of 14 Notification
- b. FOR AN ALERT:
"Attention all personnel. An Alert has been declared due to (brief description) . Activate the Operations Support Center, Technical Support Center, Emergency Operations Facility and the Emergency Nevs Center. All other personnel stand by for further announcements."
- c. FOR A SITE AREA EMERGENCY OR GENERAL EMERGENCY:
I. Sound the Nuclear Emergency Alarm from the Control Room and broadcast the following:
"Attention all personnel. A (Sjite Area Emerg4ency or General Emergency z has been declared due to (brief descnption) . 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 I and Unit 2 Containment Evacuation Alarrn.
3.2.4 On any touch-tone telephone, dial 646 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 Accidcnt Notification form, EMID-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 517-336-6250 using the [SP bridge phone (extension l 088) in the back of the Control Room.
- Berrien County Sheriff's Department at 8-1-269-983-391 1. IF the automated system answers, THEN dial 7200.
Reference l PrvP-2080-EPP-107 -Rev. 17 Page 6 of 14 Notification
- c. Document phone calls on Data Sheet 1, Shifl Manager Initial Notification List.
- d. Provide the inforrnation from the Nuclear Plant Accident Notification forrn, verbally to the MSP and the Berrien County Sheriffs Department.
- e. Request a call back from the MSP and Berrien County Sheriffs Department.
- f. Inform the MSP that the Nuclear Plant Accident Notification form will be faxed.
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:
a 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 rclieved 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 Emergcncy News CenterfJPIC 8-284-5892 Visitors' Center 2906 or 2907
Reference 'MP-2080-EPP-107 ev. 17 Page 7 of 14 I ~~~~~~~~~Notiication 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 EhID-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.
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 Berien County Sheriffs Department, on Data Sheet I, Shift Manager Initial Offsite Notification List.
3.2.11 Tnforrn the Security Shift Supervisor of the time of the Emergency Classification.
- a. Direct the Security Shift Supernisor 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 Exercisc is being conducted, THEN perform the applicable portions of Attachment 1.
3.3.2 IF a Communication System Ttest is being conducted, THEN perform the applicable portions of Attachment 2.
4 FINAL CONDITIONS 4.1 Emergency. is closed-out.
Reference I PP-2080-EPP-107 Rev. 17 Page 8 of 14 Notification 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 PNIP-7030-001-001, Prompt NRC Notification 5.2 Writing Refercnces:
5.2.1 Source
References:
- a. NUREG 0654 FEMA REP-I, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants (Rev. ).
- b. Cook Nuclear Plant Emergency Plan.
5.2.2 Gencral Refercnces
- a. None.
Reference I PNIP-2080-EPP-107 l Rev. 17 Page 9 of 14 Notification Attachment I Drills and Exercises Page:
___ ~~~~~~~~~~~~~~9 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 41-1 I 18 and directs Security to implement the Dialogic Emergency Response Organization pager system for an announced or unannounced drill as dirccted 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 MIanager directs the Simulator control room staff to sound the Nuclear Emergency Alarn 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 l PNIP-2080-EPP-107 Rev. 17 j Page 10 of 14 Notification Attachment 2 Communication System Tests Pages:
- - 11 COMIVIUNICATION SYSTEM TESTS 1.1I Nuclear Emergency Alarm Test and ERO Tumover'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 11 8 to direct Security to activate the Dialogic Emergency Response Organization pagers for a Turnover.
1.1.2 Test Nuclear Emergency Alarm Annoiunce:
"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 5 to 10 seconds and then rcset by pushing "OVERIDE" button.
Announce:
"The test of the Nuclear Emergency Alarm is complete. Oncoming duty ERO personnel should call Dialogic wvhen the ERO pager activates."
Acceptance Criteria:
NEA alarm is heard in the Control Room.
Print Name/Signature Date
Reference I PrIP-2080-EPP-107 Re.17 l PaIge 11 of 14 Notification Communication System Tests Pages:
1 to ~~~~~~~~1-11 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. Testis complete."
Acceptance Critcria: (only required to be verified during normal work days).
Emergency Planning personnel report that PA systcm 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 and October 3 ".
- Station an AEO within range of the Beach PA system speakers.
- Make the following announcement using the Beach PA system microphone.
- "This is a test of the Beach Public Address System. Test complete."
- Acccptance Criteria:
Announcement is hcard by the AEO stationed for the test.
Date Pr-int Name/Signature Print NarnelSignature Datc
Referenc` T PMP-2080-EPP-107 cRev. Pae 12 of 14 Notification Data Sheet Shift Manager Initial Notification ListPae 1~2 ON-SITE PHONE NUNIBER CONTACT ESTABLISHED INITIALS /
NOTIFICATION TIE Security (SAS) for I I 18 or 119 /
Dialogic Activation Training and 1646 /
Buchanan Office PA Announcement OFF-SITE PHONE NUNIBER CONTACT EVENT NOTIFICATION ESTABLISHED CLOSEOUT INITIALS / TIME INITIALS / DATE Berrien County Sheriff's 8-1-269-983-3911 / /
Department . _
REQUEST CALL BCSD Person Contacted:_ _
BACK VERIFICATION Time Call Back Received:_
Nlichigan State 8-1-517-336-6250 1 /
Police REQUEST CALL MvISP 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
/ I 8-1-301-415-0553 NRC Person Contacted:_
Continuous contact will be required for an Alert, Site Area Emergency, or General Emergency
Reference PMIP-200-P17 _ . Rev. 17 j Pagc 13 of 11 Notification 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 Mivargin? 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)
Other:
RCS Pressure Control
- Pressurizer PORVs Closed? Yes No
- Pressurizer Safeties Closed? Yes No
Reference PIP-2080-EPP-107 RPae 14 of 14 Notification Data Sheet 2 Plant Status Pages:
13 - 14 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 S 'G - Condenser Dump Valves S/G -- Atmospherie Dump Valves S/G - Safety Valves RCS -- FeedlBleed Decay Heat Removal System (RHR)
S/G Inventory Control - Check all that apply for the current plant conditions lain Fcedwater Aux. Feedwater Other:
Containment Control
- Ice Condenser Doors OPEN? Yes No
- Containment Sprays ON? Yes No
- Hydrogen Recombiners/lgniters ON? Yes No
- Containment Isolation Valves fail to CLOSE? Yes No
- Plase A Actuation? Yes No
A EVIEW AND APPROVAL TRACKING FORM F%;..E£aS SPBsU'i7tJ% 0 Number: PMP-2080-EPP-108 Rev. 4 Change: 0
Title:
Initial Dose Assessment IajA/fr- :-
l Correction (Full Procedure) 0 Change (Full Procedure) with Review of Change Only l Correction (Page Substitution) E Change (Page Substitution) with Review of Change Only ED Cancellation El New Procedure or Change with Full Review El Superseded (list superseding procedures):
Change Driver/CDI Tracking No(s).:_____ N/A Cross-Discipline Reviews: Programmatic Reviews:
El Chemistry E Training Ol ALARA El Performance Assurance l Maintenance O Work Control 0 Bus. Services Proc Grp a Reactivity Mgmt Team l[ NDM [:aComponent Engineering EO SPS (Safety & Health) 3 Operations O. E Design Engineering El Surveillance Section
_PA/PV
_ O Emerg Oper Proc Grp El System Engineering D Reg Affairs O O Environmental . ._a RP El None Required El ISIIST Coordinator E None Required Cognizant Org Review: Q jDate: qt lJ b\la 2Technical Review: ( t 1 ( Date: K 1 >
El Ops Mgr Concurrence: N/A Date: /
0D Owner Concurrence ( .A- .L 's 9AQ41WwAe Date: L/la_/Ot Updated Revision Summary attached? 0 Yes 10 CFR 50.59 Requirements complete? Tracking No.a .- 0 (3 t¶-0 0 Yes E N/A Implementation Plan developed? (Ref. Step 3.4.18) 0 Yes El N/A Package Complete: - 9 1 Date: I.JjjL PORC Review Required: 3 Yes E No Mtg. No.: 393B Administrative Hold Status: El Released El R issued 3 N/A CR No.:
Approval Authority Review/Approval: . Cl Date: I IO Expiration Date/Ending Activity Effective Date:5J/3 lL
_NO W ,
Periodic Review conducted? (Data Sheet S Complete) El Yes 0 No Commitment Database Updated? Y Yes ON/A NDM notified of new records or changes to records that could affect record retention? El Yes 0 N/A This form is derived from the information in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. 9a, Data Sheet 1, Review and Approval Tracking Form. Page I of L
- REVISION SUMA%RY Number: PMP-2080-EPP.108 Revision: 04 Change: 00
Title:
Initial Dose Assessment Revision 4 incorporates the new State of Michigan EMD-32 notification forms and revision 7 to the Dose Assessment (DAP) computer program. Because revision 7 of DAP contains on line help, the amount of procedure detail relative to operation has been reduced.
Revision 4 also puts this procedure into the new format.
Section or Step Change/Reason For Change
1.0 Change
Objective Deleted Reason: New procedure format does not require an Objective section.
This information was included in the Purpose and Scope section of Revision 4.
2.0 Change
References section moved Reason: References have been moved to step 5. The reference were also updated to reference the requirements of the Emergency Plan and EPA400-R-92-001 Manual of Protective Action Guides and Protective Actions for Nuclear Incidents.
3.0 Change
Responsibilities Reason: Added clarification of responsibilities. The SEC maintains responsibility for the implementation of this procedure and imust approve all EMD-32 forms.
4.0 Change
Limitations and Precautions section deleted.
Reason: Section is no longer required for PMP. The applicable limitations and precautions were moved to purpose and scope and are inbedded within the Details section of the procedure.
5.0 Change
Initial Conditions section deleted.
Reason: Section is no longer required for PMP.
6.0 Change
Supplementals section deleted.
Reason: The listing of supplemental attachments are now included in the Table of Contents of the procedure as Attachments.
Attachment 1 was deleted.
7.0 Change
Instructions was renamed to Details Reason: Name changed to comply with PRC.002 fornat 0 .
This is a free-form as called out in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. 9. Page r of L
REVISION
SUMMARY
Number: PMP-2080EPP.108 Revision: 04 Change: 00
Title:
Initial Dose Assessment.
Section or Step Change/Reason For Change
7.0 Change
Section completely re-written Reason: Revision 7 to the Dose Assessment Program provides on-line help and additional help for each object on the input and results screens. Therefore detail about the actual operation of the program was eliminated from the procedure. The Details section of the procedure now provides the user instructions on:
- Which EMD-32 forms are required and at what frequency
- Where to obtain meteorological data
- Where to obtain radiological release data
- Shut down status and times
- Determining coolant types
- Determining if a release is occurring
- Projected release duration
- Classification levels and initiating conditions These are all items that must be obtained that are external to the dose assessment program, but are required for its operation.
The procedure also provides instruction for the disposition of the information to the state and county after the SEC approves the form(s). Change: The attachment was deleted Reason: An Icon will be placed on thecomputers when the program is loaded on each computer. DAP provides on-line help to assist the user with its operation.
This is a free-form as called out in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. 9. Page 3of d
REVISION
SUMMARY
Number: PMP-2080-EPP.i08. Revision: 04 Change: 00
Title:
Initial Dose Assessment Section or Step Change/Reason For Change Change: Attachment 2 was split into attachment 1 and 2 of revision 4.
Reason: Attachment 1 of Rev 4 provides instructions for additional methods of obtaining meteorological data should the primary methods be unavailable. Attachment 2 of Rev 4 contains additional methods for determining Pasquill Category should the primary method on the PPC/RDR be unavailable.
~~*~Qffic tQ'W,~o ra~n '~f F ~ ?%
This is a free-form as called out in PMP-2010-PRC-002, Procedure Correction, Change, and Review, Rev. 9. Page q of 9
fLicni l PMP-2080-EPP-108 Rev. 4 Page 1 of 9 Initial Dose Assessment Information Effective Date: 73 lot P. E. Holland P. E. Holland Emergency Planning Writer Owner Cognizant Organization TABLE OF CONTENTS 1 PIPOSE AND SCOP13 ......................................... 2 2 DEFINITIONS AND ABBR1IEVIATIONS . . . 2 3 RE.SPONSIBLITES .. 2 4 DETAILS ... 3 5 REFERENCES ......................................... . .. 5 : Meteorological Data. 7 : Pasquill Category. 9
1 PURPOSE AND SCOPE 1.1 This procedure provides instructions for performing initial dose assessment for releases of radioactive material from the plant.
1.2 Use of this procedure should be limited to actual emergencies and emergency drills.
2 DEFINITIONS AND ABBREVIATIONS Term Meaning DAP Dose Assessment Computer Program EMD-32a State of Michigan Emergency Notification form (Nuclear Plant Event Notification)
EMD-32b State of Michigan Technical Notification form (Nuclear Plant Event Technical Data)
PAR Protective Action Recommendation PPC Plant Process Computer RMS Radiation Monitoring System SEC Site Emergency Coordinator 3 RESPONSIBILITIES 3.1 The SEC is responsible for the implementation of this procedure.
3.2 The SEC must review and approve all EMD-32a and EMD-32b forms prior to transmission to Berrien County or the State of Michigan. This is a non-delegable responsibility.
Information PMP-2080-EPP-108 Rev. 4 F- Page 3 of 9 Initial Dose Assessment 4 DETAILS NOTE: DAP contains extensive on line help. Help for any particular subject may be obtained by placing the mouse over the object in question. If help is available it will appear at the bottom of the screen.
NOTE: Dose assessment projections may only be performed using the DAP. F projected doses are NOT available and a PAR is necessary, THEN use the default PAR in PMP-2080-EPP-100.
4.1 Determine which forms are required.
4.1.1 EMD-32a, Nuclear Plant Event Notification.
Is only transmitted to the State/County within 15 minutes of a change to the emergency classification or PAR.
Must include an EMD-32b, Nuclear Plant Event Technical Data Form if the emergency classification is General Emergency and the PAR is based on dose calculations.
4.1.2 EMD-32b, Nuclear Plant Event Technical Data Form.
Required o be transmitted to the State/County within 30-minute intervals of the last EMD-32b or EMD-32a form.
4.2 Obtain meteorological data from the PPC. If the PPC is not available, Attachment 1, Meteorological Data, contains additional sources of meteorological data and Attachment 2, Pasquill Category, provides for Pasquill Category (Stability Class) determinations.
NOTE: Sources are listed in order of preference.
- 10 Meter Main
- 10 Meter Backup 60 Meter Main
Information PMP-2080-EPP-108 I Rev. 4 Page 4 of 9 Initial Dose Assessment 4.3 Obtain RMS radiological data from one of the following sources:
NOTE: Sources are listed in order of preference.
- RMS Display Terminals
- Direct readings from the Local Area Data Acquisition Modules 4.4 Determine the Unit I and Unit 2 reactor shutdown status and the date and time of shutdown as applicable.
4.5 Determine the Coolant Type.
Coolant Type Containment High Radiation Monitoring Reading Normal Coolant < 10 R/hr Cladding Damage < 1000 R/hr Fuel Melt > = 1000 R/hr 4.6 Determine whether an actual or potential release is occurring.
4.6.1 An actual release is occurring when any of the following are true:
- Valid indication on release point radiation monitoring system channels are present that are associated with a classified event,
- OR-
- Measured off-site radiation readings indicate a release is in progress,
- OR-O Indications exist that an unmonitored release may be occurring.
4.6.2 A potential release exists if calculated data is postulated based on present plant conditions (i.e., Containrnent Loss of Coolant Accident (LOCA)).
Information PMP-2080-EPP-108 [ Rev. 4 l Page 5 of 9 Initial Dose Assessment 4.7 Determine the Projected Duration of the Release.
IF the projected duration of the release is unknown, THEN use 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
IF releases are occurring from multiple points, TIEN use the longest projected duration.
4.8 Enter the data into the Dose Assessment Program.
NOTE: The classifications may change based on the results of the assessment being run and must be updated accordingly prior to submitting the EMD-32a or EMD-32b forms for transmittal to the state or county.
4.9 IF necessary, THEN update the current classification and tiating Conditions on the EMD-32a and EMD-32b.
4.10 Submit the EMD-32a and/or EMD-32b to the SEC.
4.11 The SEC approves the EMD-32 form(s).
4.12 Transmit the EMD-32 form(s) to the Berrien County Sheriff's Department and the State of Michigan.
5 REFERENCES 5.1 Use
References:
5.1.1 Dose Assessment (DAP) Computer Program 5.1.2 EMD-32a, Nuclear Plant Event Notification 5.1.3 EMD-32b, Nuclear Plant Event Technical Data Form 5.2 Writing
References:
5.2.1 Source References
- a. Donald C. Cook Nuclear Plant Emergency Plan
- b. EPA 400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents
Information PMP-2080-EPP-108 l Rev. 4_ Page 6 of 9 Initial Dose Assessment
- c. Meteorology and Atomic Energy 1968, U. S. Atomic Energy Commission
- d. Evacuation Time Estimates for the D. C. Cook Nuclear Plant Plume Exposure Emergency Planning Zone HMM Associates July 1992 5.2.2 General References
- a. Michigan Emergency Preparedness Plan
- b. Berrien County Emergency Preparedness Plan
Information PMP-2080-EPP-108 I Rev. 4 Page 7 of 9 Initial Dose Assessment Attachment 1 Meteorological Data Pages:
NOTE: Wind speeds are expressed as Miles per Hour. To convert Knots to Miles per Hour multiply by 1.15.
IF all of the following are true:
The current date is between April 15 and October 31, The current time is between 1-hour after sunrise and 1-hour after sunset, Ambient temperature measured at the main tower is greater than the Lake Michigan temperature, Wind speed on the shoreline tower is 5 13.4 Miles per Hour, Pasquill category is A, B, C, or D, AND Shoreline tower wind direction is FROM 2050 to 230 (i.e., Wind is from the lake)
THEN consider lake breezes in the dose assessment process.
1.1 Obtain meteorological data from one of the following sources. Sources are listed in order of preference.
.1.1.1 Plant Process Computer 10 Meter Main 10 Meter Backup
- 60 Meter Main 1.1.2 Murray and Trettle
- a. Obtain the phone number from the Emergency Response Organization Phone Directory.
- b. Obtain:
Wind Speed in Miles per Hour Wind Direction from, in degrees Pasquill Category as a letter NOT a number Eight-hour and 24-hour meteorological forecast
Information PMP-2080-EPP-108 T Rev. 4 Page 8 of 9 Initial Dose Assessment Meteorological Data Pages:
1.1.3 Manual Acquisition of Meteorological Tower Data
- Contact the Technical Support Center and request a team be dispatched to collect this data.
1.1.4 National Oceanic and Atmospheric Administration (NOAA)
- Obtain the plant NOAA phone extension from the Emergency Response Organization Phone Directory.
- Use any NOAA weather radio.
Information PMP-2080-EPP-108 Rev. 4 T Page 9 of 9 Initial Dose Assessment Attachment 2 Pasquill Category Page:
1 Obtain Pasquill Category data from one of the following sources. Sources are listed in order of preference.
1.1 Plant Process Computer 1.2 Temperature Differential AT°F =T@60m-T@10m Pasquill Category aT OC = T a 60m - T @ lOm (Z 50 Meters) (Z = 50 Meters)
_____ _ _._-_:A_-.;._,- .', ., =,°C ,1;O.::,.
-1.8 < AT °F - 1.6 B -1.0 < AT OC s 0-.9
,:-li.6'! :AT0 F,: q .4 .. C', . -0.9< AThC O.8:.
-1.4 < AT OF S- 0.5 D -0.8 < AT QC - 0.3
,, ; ,+t'3' ::-
'-,$,'cE-[,oF E -.. :>,:-.:L . 403< A;T,C-S.+0.7-
+1.3 < AT°F s +3.6 F +0.7 < T 0C s +2.0
.'-,-' i .G. : : .. .0:<:T;0C 1.3 Standard Deviation of the Horizontal Wind Direction (STD)
STD Pasquill Category
- ,, STD 2 Z.25 ..,.",
22.5 STD > 17.5 B
' : .5.'.S "1 D > 12.5 C 12.5 > STD > 7.5 D
. i . 5~~ T D > 33f8 .8 .
3.8 2 STD > 2.1 F
. i:. ,'L2.1ST'-D G 1.4 Murray and Trettle
- See Attachment 1, Meteorological Data.
1.5 Observation Incoming Solar Radiation (Day Only)
(1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after sunrise to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> before sunset)
Sun Angle Cloud Cover Degrees from Horizon None 1/8 - S/8 518 - 7/8 8/8 Middle Clouds Low Clouds
..' 5°,!35o 7.;
- 9Slight Slight :'- - .
- ligIitj: . . : Sigbt , Slight 35o . 60. Moderate Slight Slight I Slight Slight
.. .6,,, , :$1ro
.. ngStrong
' - _ S ; Slight ..
Day Niht Wind Speed @10 meters Incoming Solar Radiation Thinly Overcast or < 318 Miles per Hour (Mph) Strong . Moderate Slight 2 4/8 Low Clouds Clouds Mph 5 . A A-B .B --
5 < Mph7 A-B B C E F 7 <MphSll ' B B-C C D E 11 < Mph< 13 C C -D D D D Mph > 13 C D D D D