Revision as of 19:48, 10 November 2019

Text

Emergency Plan Implementing Procedures, Including Revision 035 to RP/0/A/5000/001 and Revision 036 to RP/0/A/5000/001
	ML16070A245
Person / Time
Site:	Catawba
Issue date:	03/08/2016
From:	Henderson K; Duke Energy Carolinas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	CNS-16-016 RP/0/A/5000/001, Rev. 035, RP/0/A/5000/001, Rev. 036
	Download: ML16070A245 (97)
	v • d • e

Kelvin Henderson DUKE Vice President ENERGY°Catawba Nuclear Station Duke Energy CNS-1 6-016 CNO1VP 14800 Concord Road York, SC 29745 o: 803.701.4251 March 8, 2016 f-803.701.3221 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

Subject:

Duke Energy Carolinas, LLC Catawba Nuclear Station Units 1 and 2 Docket Nos. 50-413 and 50-414 Emergency Plan Implementing Procedures Please find enclosed for NRC Staff use the following Emergency Plan Implementing Procedures:

RP/O/A/5000/001 Classification of Emergency Revision 035 RP/0/A/5000/001I Classification of Emergency Revision 036 Due to a printing error in Revision 035 on page 1 of 5, Enclosure 4.1, Revision 036 has also been included. These revisions are being submitted in accordance with 10OCFR 50.54(q) and do not cause a reduction in the effectiveness of the Emergency Plan Implementing Procedures or the Emergency Plan.

There are no new regulatory commitments in these documents. By copy of this letter, two copies of these documents are being provided to the NRC, Region II.

If there are any questions, please call Tom Arlow at 803-701-4027.

Kelvin Henderson Vice President, Catawba Nuclear Station Attachments

U.S. Nuclear Regulatory Commission March 8, 2016 Page 2 xc (w/attachments):

Catherine Haney, Regional Administrator U. S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1 257 (w/o attachments):

Jeffrey Whited NRC Project Manager (CNS)

U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8-B1A 11555 Rockville Pike Rockville, MD 20852-2738

Page 1 of S DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME I PROCEDURE TITLE SRP/0/A/5000/001 Classification of Emergency (Rev. 035)

RP/0/A/5000/002 Notification of Unusual Event (Rev. 045)

RP/0/A/5000/003 Alert (Rev. 050)

RP/0/A/5 000/004 Site Area Emergency (Rev. 053)

RP/0/A!5000/005 General Emergency (Rev. 054)

RP/0/A/5000/06 Deleted RP/0/A/5000/006 A Notifications to States and Counties from the Control Room (Rev. 033)

RP/0/A/5000/006 B Notifications to States and Counties from the Technical Support Center (Rev. 0/37)

. RP/0/A/5000/006 C Deleted RP/0/A/5 00 0/0 07 Natural Disaster and Earthquake (Rev. 043)

RP/0/A/5000/08 Deleted RP/0/B/5000/008 Hazardous Materials Spill Response (Rev. 043)

RP/0/A/5000/009 Collision/Explosion (Rev. 012)

RP/0/A/5000/0 10 Conducting a Site Assembly or Preparing the Site for an Evacuation (Rev. 027)

RP/0/A/5000/1l1 Deleted RP/0/B/5000/12 Deleted RP/0/B/5000/0 13 NRC Notification Requirements (Rev. 038)

RP/0/B/5000/14 Deleted RP/0/A!5000/0 15 Core Damage Assessment (Rev. 007)

. RP/0/B/5000/016 Deleted RP/0/B/5000/17 Deleted February 17, 2016

Page 2 of 5 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME I PROCEDURE TITLE RP/0/A/5000/01 8 Emergency Worker Dose Extension (Rev. 002)

RP/0/B/5000/019 Deleted RP/O/A/5000/020 Technical Support Center (TSC) Activation Procedure (Rev. 038)

RP/0/A/5000/021 Deleted RP/0/B/5000/022 Deleted RP/0/B/5000/023 Deleted RP/0/A/5000/024 OSC Activation Procedure (Rev. 034)

RP/0/B/5000/025 Recovery and Reentry Procedure (Rev. 003)

RP/0/A/5000/026 Site Response to Security Events (Rev. 017)

RP/0/B/5 000/028 Nuclear Communications Emergency Response Plan (Rev. 006)

February 17, 2016

Page 3 of 5 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II PROCEDURE TITLE HP/O/B/1000/006 Emergency Equipment Functional Check and Inventory (Rev. 060)

HP/0/B/1009/001 Deleted HP/0/B/1009/003 Radiation Protection Primary to Secondary Leakage Program (Rev. 012)

HP/0/B/1009/004 Environmental Monitoring for Emergency Conditions Within the Ten-Mile Radius of CNS (Rev. 031)

HP/0/B/1009/005 Personnel/Vehicle Monitoring for Emergency Conditions (Rev. 018)

HP/0/B/1009/006 Alternative Method for Determining Dose Rate Within the Reactor Building (Rev. 009)

HP/0/B/1 009/007 In-Plant Particulate and Iodine Monitoring Under Accident Conditions (Rev. 020)

HP/0/B/1009/008 Contamination Control of Injured Individuals (Rev. 016)

HP/0/B/1009/009 Deleted HP/0/B/1009/014 Radiation Protection Actions Following an Uncontrolled Release of Liquid Radioactive Material (Rev. 009)

HP/0/B/1009/016 Deleted HP/0/B/1009/017 Deleted HP/1/B/1009/017 Deleted HP/2/B/1009/017 Deleted HP/0/B/1009/0 18 Deleted HIP/0/B/1009/019 Emergency Radio System Operation, Maintenance and Communication (Rev. 010)

HP/0/B/1009/024 Implementing Procedure for Estimating Food Chain Doses Under Post-Accident Conditions (Rev. 002)

February 17, 2016

Page 4 of 5 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II PROCEDURE TITLE HP/0/B/1009/025 Deleted HP/0/B/1 009/026 Superseded SH/0/B/2005/00 1 Superseded SH/0/B/2005/002 Deleted SH/0/B/2005/003 Deleted OP/0/A!6200/02 1 Deleted SR/0/B/2000/001I Deleted SR/0/A/2000/001 Standard Procedure for Corporate Communications Response to the Emergency Operations Facility (Applies to Catawba/McGuire/Oconee) (Rev. 002)

SR/0/B/2000/002 Deleted SR/0/A!2000/003 Activation of the Emergency Operations Facility (Rev. 008)

SR/0/B/2000/003 Deleted SR/0/A!2000/004 Notifications to States and Counties from the Emergency Operations Facility for Catawba, McGuire and Oconee (Rev. 006)

SR/0/B/2000/004 Deleted AP/0/A/5500/046 Hostile Aircraft Activity (Rev. 008)

AD-EP-ALL-0202 Emergency Response Offsite Dose Assessment (Rev. 001)

AD-EP-ALL-0203 Protocol for the Field Monitoring Coordinator During Emergency Conditions (Rev 000 AD-EP-ALL-0204 Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release (Rev 000)

AD-EP-ALL-0301 Activation of the Emergency Response Organization Notification System (ERONS) (Rev. 000)

February 17, 2016

Page 5 of 5 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II PROCEDURE TITLE AD-EP-ALL-0406 Duke Energy Management Network (DEMNET) (Rev 001)

February 17, 2016

Form 703-1. Procedure Process Record (PPR)

SIII- 41 Duke Energy (I) ID No. RP/0/A/5000/001 PROCEDURE PROCESS RECORD RC 0 o. 035 PREPARATION (2) Strat ion _____

Ca.awa.Nucear.Satio (3) Procedure Title Date ~ VI (5) Requires NSD 22, Applicability Determination?

[] Yes (New procedure or revision with major chang'es) - Attach NSD 228 documentation E] No (Revision with minor changes)

(6) Reviewed By* ________________________________(OR) (KI) D)ate _______

Cross-D~isciplinary Review By*'________________________(OR) (KI) NA ______ ate_______

Reactivity Mgmt. Review By*~ ((OR) NA_______Date_______

Mgmt. Involvement Review By* (Ops. Mgr.) NA_______ ate ______

(7) Additional Reviews *___

(8) Approved By* L*.,*, ,t * -*,*. Date .-7-./ O///

PERFORMANCE (Compare witih control copy every 14 calendar days while work is being performed.)

(9) Compared with Control Copy* Date_________

Cornpared with Control Copy* l)are_________

Compared with Control Copy* ____________________________________D[)te _____

(1I0) Date(s) Performed Work Order Number (WO#)

COMPLETION (I I) lProcedure Completion Verification:

E] Yes [] NA Checklists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?

E] Yes E] NA\ Required enclosures attached'?

E] Yes [] NA Charts, graphs, data sheets, etc. attached, dated, identified, and marked'?

E] Yes E] NA Calibrated Test Equipment, if used, checked out/in antd referenced to this procedure?

E] Yes E] NA Procedure requirements met?

Verified By*

(12) Procedure Completion Approved* ______ l)ate ________

(13) Remarks 'Attachr additionalpoges, if necessary)

P tinted Nooe and Simnatoore

Form 703-1. Procedure Process Record (PPR) 511.14)

Duke Energy (I) ID,'o. RP/0/A15000/00I PROCEDURE PROCESS RECORD Re ~oiNo. 035 PREPARATION (2) Station ___ Catawba Nuclear Station (3) Procedure Title Classification of Emergency (4) Prepared By* C~\c~r . Date -~ Y' (

1' (5) Requires NSD 228 Applicability Determination?

[] Yes (New procedure or revision with niajor changes) - Attach NSD 22S documentation E] No (Revision wVith minor changes)

(6) Reviewed By* (OR) (KIb l)ute_______

Cross-Disciplinary Review By" ________________________(Q R)(K[) NA ______ ate_______

Reactivity Mgmt. R~eviewv By* (OR) NA____ D__late_____

Mgmt. Involvement Review By* (Ops. Mgr.) NA________Date_______

(7) A\dditional Reviewvs ,1 . (

(8) Approved B3y *_.(,t,, Date **, ,*,_,',

PERFORMANCE (Compare wiith control copy every 14 calendardlays while work is being per~hrmed.)

(9) Compared with Control Copy* _______________________________________________ )ate________

Compared with Control Copy* ___________________________________________ Date _______

Compared with Control Copy* _______________________________________ ate_______

(1U) Date(s) Performed Work Order Number (WO#) ________________________________________________

COMPLETION (11) P'rocedure Completion Verification:

E] Yes [] NA Checklists and/or blanks initialed, signed, dated, or filled in NA. as appropriate!

E] Yes E] Ni\ Required enclosures attached?

E] Yes E] NA C*harts, graphs, data sheets, etc. attached, dated, identified, anid marked?

[] Yes [] NA Calibrated Test Equipment, if used, checked out/in and referenced to this procedure'?

E] Yes [] NA Procedure requirements met?

Verified By* ______________ IDate_______

(12) Procedure Completion A~pproved* [)ate _______

(13) Remarks (Attach Ltdd~iioal poges, if necessaor)

I*'rinted Naome and Signaottre

ENEGY.

Facility Code : CN Applicable Facilities:

Document Number: RP/0/A/5000/001 Document Revision Number : 035 Document EC Number :

Change Reason :

Document Title : Classification of Emergency Arlow, Tom A EP Manager review 2/16/2 016 Notes :

10 CFR 50.54(q) Screening Evaluation Form Screening and Evaiuation Number Applicable Sites BNP []

EREG #:01 997084 CNS l[]

PPR AR# 01935311 CR3 []

HNP []

MNS []

5AD #:01995501 ONS []

RNP C]

GO C]

Document and Revision Classification of Emergency RP/0/A./5000/001 Revision 035 Part 1. Description of Activity Being Reviewed (event or action, or series of actions that may result in a change to the emergency pian or affect the implementation of the emergency plan):

Activity description RP/0/A/5000IO01 (Classification of Emergency ) Rev.035

1) Procedure Body Section 2 Immediate Actions- Step 2.4 - Changed to read "I' the plant was in Mode 1-4 and a valid condition affects fission product barriers, proceed to Enclosure 4.1 (Fission Product Barrier Matrix)

O__R refer to EAL wallboards".

2) Procedure Body Section 2 Immediate Actions- Step 2.5 - IF'a General Emergency is NOT declared in Step 2.40..OR the condition does NOT affect fission product barriers, review the listing of enclosures ORR refer to EAL wallboards to determine if the event is applicable to one the categories shown.

3) Procedure Body Section 3 Subsequent Actions- Step 3.1 - Changed to read "To escalate, dc-escalate, or terminate the Emergency, compare plant conditions to the Initiating Conditions of Enclosures 4. 1 through 4.7 OR EAL wallboards".

4) Procedure Body Section 3 Subsequent Actions- Step 3,2 - Changed to read - 'Refer to Enclosure 4.8 (Definitions/Acronyms) O__R 4.9 (Emergency Declaration Guidelines), as needed.'

Re ferences:

PRR0193531 1

Part I1.Activity Previously Reviewed?E Is this activity Fully bounded by an NR,C approved 10 CFR 50.90 submittal or Yes El[ No IX 10 CFR 50.54(q) Continue to Alert and Notification System Design lBeport? Effectiveness Attachment 4 Evaluation is not ,10CFR If yes, identify bounding source document number or approval reference and required. Enter 50.54(q) ensure the basis for concluding the source document fully bounds the proposed justification Screening change is documented below: below and Evaluation complete Form, Part Ill Justification: Attachment 4, Part V.

Bounding document attached (optionall)

Part Ill. Editorial Change ',Yes El[ No X Is this activity an editorial or typographical change only, such as formatting, 10 CFR 50.54(q) Continue to paragraph numbering, spelling, or punctuation that does not change intent? Effectiveness Attachment 4, Evaluation is not Part IV and Justification: required. Enter address non

,,justification and editorial complete changes Attachment 4,

___________________________________________Part V & VI.

Part IV. Emergency Planning Element and Function Screen (Reference Attachment 1, Considerations for Addressing Screening Criteria) '

Does this activity involve any of the following, including program elements from NUREG-0654/FEMA REP-i Section I17 If answer is yes, then check box.

1 10 CFR 50.47(b)(1) Assignment of Responsibility (Organization Control)___

1la Responsibility for emergency response is assigned. El 1lb The response organization has the staff to respond and to augment staff on a continuing basis El (24-7 staffing) in accordance with ithe emergency plan.___

2 10 CFR 50.47(b)(2) Onsite Emergency Organization __

2a Process ensures that on-shift emergency response responsibilities are staffed and assigned [

2b The process for timely augmentation of on-shift staff is established and maintained. [

3 10 CFR 50.47(b)(3) Emergency Riesponse Support and Resources __

3a Arrangements for requesting and using off site assistance have been made. El 3b State and local staff can be accommodated at the EOF in accordance with the emergency plan. El (NA for CR3) __

4 10 CFR 50.47(b) (4) Emergency Classification System 4a A standard scheme of emergency classification and action levels is in use. El

__(Requires final approval of Screen[ and Evaluation by EP CFAM.)

5 10 CFR 50.47(b) (5) Notification Methods and Procedures

5a Procedures for notification of State and local governmental agencies are capable of initiating notification C]

of the declared emergency within 15 minutes (30 minutes for CR3) after declaration of an emergency and providing follow-up notificati~on.

5b Administrative and physical means have been established for alerting and providing prompt instructions []

to the public within the plume exposure pathway. (NA for CR3)

Sc The public ANS meets the design requirements of FEMA-REP-1 0, Guide for Evaluation of Alert and C]

Notification Systems for Nuclear'Power Plants, or complies with the licensee's FEMA-approved ANS design report and supporting FEMA approval letter. (NA for CR3)___

Part IV. Emergency Planning Element and Function Screen (cont.)

6 10 CFR 50.47(b)(6) Emergency) Communications __

6a Systems are established for prompt communication among principal emergency response C]

organizations.

6b Systems are established for prompt communication to emergency response personnel. []

7 10 CFR 50.47(b)(7) Public Education and Information 7a Emergency preparedness informnation is made available to the public on a periodic basis within the []

plume exposure pathway emergency planning zone (EPZ). (NA for CR3)___

7b Coordinated dissemination of p~ublic information during emergencies is established. [

8a Ad Cqu Ft acilities8 a mr gemant ya cined to esuppor ency r s onet e q imer 8a 10qut CfR 04)8 mrecacilities andmitiedt upr eqimerentyrsos.[

8b Adequate equipment is maintained to support emergency response. ___

9 10 CFR 50.47(b)(9) Accident A~ssessment 9a Methods, systems, and equipm'ent for assessment of radioactive releases are in use. JC 10 10 CFR 50.47(b)(10) Protective Response 10Oa A range of public PARs is available for implementation during emergencies. (NA for CR3) C]

10Ob Evacuation time estimates for the population located in the plume exposure pathway EPZ are available C]

to support the formulation of PARs and have been provided to State and local governmental authorities. (NA for CR3) 10Oc A range of protective actions is available for plant emergency workers during emergencies, including C]

those for hostile action events.

10Od KI is available for implementation as a protective action recommendation in those jurisdictions that []

chose to provide KI to th~e public.

11 10 CFR 50.47(b)(1 1) Radiologic.al Exposure Control 11a The resources for controlling radiological exposures for emergency workers are established. C

[

12 10 CFR 50.47(b)(12) Medical and Public Health Support 12a Arrangements are made for medi~ical services for contaminated, injured individuals. C[

13 10 CFR 50.47(b)(13) Recovery 'Planning and Post-accident Operations 13a Plans for recovery and reentry are developed. C

[

14 10 CFR 50.47(b)(14) Drills and Exercises 14a A drill and exercise program (including radiological, medical, health physics and other program areas) C]

is established.

14b Drills, exercises, and training ev.olutions that provide performance opportunities to develop, maintain, C]

and demonstrate key skills are assessed via a formal critique process in order to identify weaknesses.

14c Identified weaknesses are corrected. C]

15 [10 CFR 50.47(b)(1 5) Emergency Response Training 15a ~Training is provided to emergency responders.

Part IV. Emergency Planning Element and Function Screen (cont.)

16 [10 CFR 50.47(b)(16) Emergency Plan Maintenance___

16a Responsibility for emergency plan development and review is established. jC 16b Planners responsible for emergency plan development and maintenance are properly trained. JC PART IV. Conclusion If no Part IV criteria are checked, a 10 CFR 50.54(q) Effectiveness Evaluation is not required, then complete X , 10 CFR 50.54(q) Screening Evaluation Form, Part V. Go to Attachment 4, 10 CFR 50.54(q)

Screening Evaluation Form, Part VI for instructions describing the NRC required 30 day submittal.

If any Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV criteria are checked, then complete , 10 CFR 50.54(q) Screening Evaluation Form, Part V and perform a 10 CFR 50.54(q)

Effectiveness Evaluation. Shaded block requires final approval of Screen and Evaluation by EP CFAM.

[]

The changes included in this revision include enhancements for allowing the use of wallboards.

These changes do not impact any planning standard functions, and therefore do not require 50.54Q; evaluation.

Preparer Name (Print): Mandy B. Hare Part V. Signatures:r Preparer Sign tue / / ., Date:2/4/16 S('o-ReiwrNm Pit:TmAlwReviewer Signature:cd Date:

Approver (EP Manager Name (Print): Cecil Fletcher Apr SintDate: ,

Approver (CFAM, as required) Name (Print) " Approver Signature: Dat:

Part VI. NRC Emergency Plan and Implementing Procedure Submittal Actions Create two EREG General Assignments.

One for EP to provide the 10 CFR 50.54(q) summary of the analysis, or the completed 10 CFR 50.54(q).

to Licensing.

One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect.___

QA RECORD

Duke Energy Company Procedure No.

CATAWBA NUCLEAR STATION RPIOIA/5O001001 Classification of Emergency Revisioli No.

035 Reference Use PERFORMANCE I This Procedure was printed on 2/16/20 16 10:54 AM from the electronic library as:

(ISSUED) - PDF Format Compare with Control Copy every 14 calendar days while work is being performed.

Compared with Control Copy

Date _______

Compared with Control Copy

Date _______

Compared with Control Copy

Dt El Yes El NA Required attachments included?

El Yes El NA Charts, graphs, data sheets, etc. attached, dated, identified, and marked?

El Yes El NA Calibrated Test Equipment, ifused, checked out/in and referenced to this procedure?

El Yes El NA Procedure requirements met?

Verified By Date

Printed ANcme anzd Si~gnature Procedure Completion Approved Date

PrintedNa/oe and Signature Remarks (attach addfitional pages, ifnecessa~y)

IMPORTANT: Do NOT mark on barcodes. lPrinted Date: '2/16/16*

t ,acmetNumb*er: "T2D l l11 IIiII ~IlIIIIII IIl IIll I IIllIl Procedure No.: *RP/tO/A/5OO)O/O01*

RP/OIAI5000100 i Page 2 of 4 Classification of Emergency

1. Symptoms 1.1. Notification of Unusual Event

1. 1.1I Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated.

1.1.2 No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety occurs 1.2 Alert 1.2.1 Events are in process or have occurred which involve an actual or potential substantial degradation of the level of'saf'ety of the plant or a security event that involves probable life threatening risk to site personnel or dlamagze to site equipment because of HOSTILE ACTION.

1.2.2 Any releases are expected to be limited to small fractions of"the EPA Protective Action Guideline exposure levels.

1.3 Site Area Emergency 1.3.1 Events are in process or have occurred which involve actual or likely major failures of"plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (I1)toward site personnel or equipment that could lead to the likely failure of"or: (2) that prevent effective access to equipment needed for protection of the public.

1.3.2 Any releases are not expected to result in exposure levels which exceed [PA Protective Action Guideline exposure levels beyond the site boundary.

1.4 General Enmergency 1.4. 1 Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of"physical control of the facility.

1.4.2 Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site ajrea

2. Immediate Actions

2. 1 IF performing this procedure due to security-related event(s) considered to be a CREDIBLE THREAT or HOSTILE ACTION, perform the following.

RP/O/AI5000/00 Page 3 of 4 I..F Security reports that a SECURITY CONDITION or HOSTILE ACTION is imminent (15 minutes) or in-progress, notify station personnel via the plant page to take the appropriate protective actions. Refer to RP/0/B/5000/026, Site Response to Security Events, as soon as possible for scripted message.

Perform accelerated notification to the NRC within 15 minutes of the occurrence of" the event.

2.2 Assessment, classification and declaration of any applicable emergency condition should be completed within 15 minutes after the availability of indications or information to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded. (Refer to Enclosure 4.9, Emergency Declaration Guidelines, as needed) 2.3 Determine operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response of the event.

2.4 [F' the plant was in Mode 1-4 and a valid condition affects fission product barriers, proceed to Enclosure 4.1l (Fission Product Barrier M'atrix) OR. refer to [AL wvallboards.

2.5 IF a General Emergency is NOT declared in Ste p 2.4 OR. the condition does NOT affect fission product barriers, review the listing of enclosures OR refer to [AL wallboards to determine if the event is applicable to one the categories shown.

2.6 Compare actual plant conditions to the Emergency Action Levels evaluated in step 2.4 and/or 2.5 and declare the appropriate Emergency Class as indicated.

2.7 Document the declaration time.___________

2.8 Activate the ERO per the appropriate Response Procedure (RP) utilizing the Control Room ERG Notification Job Aid.

2.9 IF the declaration is made in the Control Room, announce the classification and declaration time to the Control Room Crew at the first opportunity that will not interf'ere with the performance of the crew or the fhow of the Emergency Procedure.

2. 10 IF the declaration is made in the TSC or EOF, announce the classification and declaration time to the applicable facility personnel.

RPIOIAI/001001 Page 4 o f 4 2.11 Implemnent the applicable Emergency Response Procedure (RP) for that classification and continue with subsequent steps of this procedure.

Notification of Unusual Event RP/O/A/5000/O02 Alert RP/0/A/5000/003 Site Area Emergency RP/O/A/5000/004 General Emergency RP/0/A/5000/005

3. Subsequent Actions 3.1 To escalate, de-escalate, or terminate the Emergency, compare plant conditions to the Initiating Conditions of Enclosures 4.1 through 4.7 OR. EAL wallboards.

3.2 Refer to Enclosure 4.8 (Definitions/Acronyms) OR 4.9 (Emergency Declaration Guidelines), as needed.

3.3 Refer to Section D of the Catawba Emergency Plan for basis information about thle Emergency Classification System as needed.

3.4 Refer to RP/0/A/5000/020, "TSC Activation Procedure' concerning the use of 10CFR50.54(x). If the TSC is activated, contact the TSC Emergency Coordinator ([C) for concurrence when using I10CFR50.54(x).

4. Enclosures

4. 1 Fission Product Barrier M'atrix 4.2 System Malfunctions 4.3 Abnormal Rad Levels/Radiological Effluent 4.4l Loss of Shutdown Functions 4.5 Loss of Power 4.6 Fires/Explosions and Security Events 4.7 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety 4.8 Definitions/Acronyms 4.9 Emergency Declaration Guidelines 4.1I0 Radiation Monitor Reading for Enclosure 4.3 EALs

S Enclosure 4.1 RPIOIAI500010011 Fission Product Barrier Matrix Page 1 of 5 ission Product Barrier status (,Intact, Potential Loss, or Loss). Add points for all barriers. Classify J)W.

Ie events) could occur which results in the conclusion that exceeding the Loss or Potential Loss thresholds is hours). In this IMMINENT LOSS situation, use judgment and classify as if the thresholds are exceeded.

ission Product Barrier status, the Fuel Clad Barrier should be considered to be lost or potentially lost if the conditions

or potential loss EALs were met previously validated and sustained, even if the conditions do not currently exist.

ion (C SF) indications are not meant to include transient alarm conditions which may appear during the start-up of ment. A CSF condition is satisfied when the alarmed state is valid and sustained. The STA should be consulted to alidated prior to the CSF being used as a basis to classify an emergency.

of All AC Power Procedure, is implemented with an appropriate CSF alarm condition valid and sustained, the CSF classify an emergency prior to any function restoration procedure being implemented within the confines of ECA-

___{ IC jAlert IC f Site Area Emergency { IC General Emergency

4. l.A.l Loss OR Potential Loss 4.1.S.1 Loss OR Potential Loss 4. I.G.I Loss of All Three Barriers of of Both Nuclear Coolant System Nuclear Coolant System AN I Fuel Clad 4.l.A.2 Loss OR_Potential Loss Loss 4.l.G.2 Loss of Any Two B~arriers of Fuel Clad AND AN I l'otential Loss Potential Loss of the Third Combinations of B~oth Nuclear Coolant System ANt)

Fuel Clad 4.L.A.3 l~oss of Containmnent Cot llt a' mlncolt A N)

AN ) ILoss OR Potenthil Loss

0 Enclosure 4.1 RP/O/A/5000/001I Fission Product Barrier Matrix Page 2 of 5 NOTE: lf a barrier is affected, it has a single point value based on a "potential loss" or" a "loss." "Not Applicable" is inclu~ded in the table as a place holder only, and has no point v'alue assigned.

Barrier IPoints (1-5) Potential Loss (X) Loss (X) Total IPoints Classification Containment 1 3 1- 3 Unusual Event

-NCS 4 5 4 -6 Alert Fuel Clad 4 5 7 -10 Site Area Elmergency Total Points *,*+*:;i}.i**.ii:.i* 1*.;:*

1 - 13 General Emergency

1. Compare plant conditions against the Fission Barrier Matrix on pages 3 through 5 of 5.

2. Determine the "'potential loss" or "loss" status for each barrier (Containment, NCS and Fuel Clad) based on the EAL symptom description.

3. For each barrier, write the highest single point value applicable for the barrier in the "'Points" column and mark the appropriate "'loss"~

COltllnnl.

4. Add the points in the lPoints'" column and record the sum as "'Total Points".

5. Determine the classilqcation level based on the number of "Total Points".

6. In the table on" page 1 of 5, under one of the four "'classification" columns, select the event number (e.g. 4.1I.A. 1 for Loss of Nuclear Coolant System) that best fits the loss of harrier descriptions.

7. Usingt the number (e.g. 4.1 .A. I). select the preprinted notification form OR a blank notification form and complete the required nflornmt ion Ibr Emergency Coordinator approval and transmittal.

0 Enclosure 4.1 RPIOIA15000100 1 Fission Product Barrier Matrix Page 3 of 5 4.1.C CONTAINMIENT BARRI,1ER 4.1.N NCS BARRIER 4.I.F FUEL CLAD BARRIER POTENTIAL LOSS -/ LOSS - POTENTIAL LOSS - LOSS - POTENTIAL LOSS - LOSS -

(I Point) (3 Points) (4 Points) (5 Points) (4 Points)

(5 Points)

. . . . . h .. .. . .. .. . .I - I -* I

1. Critical Safety Function Status i. Critical Safety Funlctiun Status 1. Critical Safety Function Status

Containment-RED

Not applicable

NCS Integrity-Red . N

,lot applicable

Core Cooling-

Core Cooling-Red Orange

Core cooling-RED

Heat Sink-Red Path is indicated

Heat Sink-Red for > 15 minutes

2. Containnment Conditions 2. NCS Leak Rate 2. Primary Coolant Activity Level

Containment

Rapid unexplained

Unisolable leak

GREATER TIHAN Pressure > 15 PSIG decre~ase in

Not applicable

Coolant Activity exceeding the available makeup GREATER THAN containment capacity of one capacity as 300 ltCi/cc Dose

H2 concentration > pressure following charging pump in indicated by a loss Equivalent Iodine 9% initial increase thle normal of NCS subcooling. (DEl) 1-131 charging mode

Containmcni Containment with letdown pressu~re greater than pressure or sump isolated.

3 psig with less than level response not oree full train of NS consistent with and a VX-CARF LOCA conditions, operating after actuation.

NOTE: Refer to Emergency Plan, Sect. D, 4.1 .C.2, last paragraph for inability to maintalin normaal tannuluis pressure.

(-'ON'I'INIIEI) CONTINIIFI)

CONT'INUIED NTNJ)

CONTINIJEI)

Enclosure 4.1 RIp/O/A/5000/001 Fission Product Barrier Matrix Page 4 of 5 4.1.C CONTAINMENTI BARRIER 4. I.N NCS BARRIER 4.1I.F FUEL CLAD BARRIER POTENTIAL LOSS - LOSS - POTENTIAL LOSS - LOSS - POTENTIAL LOSS - LOSS -

(I Point) (3 Points) (4 Points) (5 Points) (4 Points) (5 Points)

. ... . . . .. . . . ."

T- ..

F -1.. . .. . . . . ... . . . . . .m- "II.. . . . . . . . .

3. ContainmentIsolation Valves Status After 3. SC. Tube Rupture 3. C~ontaiunment Radiation M'onitoring Con~tainnment Isolation Actuation Not applicable Containment Primary-to-

Indication that a Not applicable

Containment isolation is Secondary leak SG is Ruptured and radiation monitor incomplete and a rate exceeds the has a Non-lsolable 53 A or 53 B direct release path capacity of one secondary line fault Reading at time from containment charging pump in since Shutdown.

exists to the the normal

Indication that a environment charging mode SG is ruptured and 0-0.5 hrs > 99 R/hr

with letdown a prolonged release 0.5-2 hrs > 43 R/hr isolated. of contaminated 2-4 hrs > 31 R/hr secondary coolant 4-8 hrs > 22 R/hr is occurring from >8 hrs > 13 R/hr the affected SC to the environment

4. SC Secondary Side Release WNithi Primary-to- 4. Cointainiaent Radiaition NMoiitoringf 4. Emnergenmcy Coordiinator/EOF IDirector Secondary Leakagze Jiudgenment

Not applicable

Release of

Any condition, including inability to monitor

Not applicable

Not applicable secondary side to the barrier that in the opinion of the the environment Emergency Coordinator/EOF Director w~ith primary to indicates LOSS or POTENTIAL LOSS of the sccondatr, leakage fuel clad barrier.

GREATER THAN Tech Spec allowvable END (N)O N'I N 1!* I) OlNLiD UI-D CONTIN

Enclosure 4.1 RP/O/A/5000/O01I Fission P~roduct Barrier Matrix Page 5 of 5 4.1.C CONTAINMENT BARRIER 4.I.N NCS BARRIER 4.1I.F FUEL CLAD BARRIER POTENTIAL LOSS - LOSS - POTENTIAL LOSS - LOSS - LOSS -

(I Point) (3 Points) (4 Points) (5 Points) POTENTIAL LOSS (4 Points) - (5 Points)

. . . . .. . . . . . . . .. . . .. . . . . . . . . . . . .. . .I I II ... . l F .. . .

5. Significant Radioactive Invenutory In 5. Emiergenc*' Coordiiuator/EOF Director Conitainmnezut .Judgenement

Containment Rad. Any condition, including inability to monitor

Not applicable Monitor EMF53A or the barrier that in the opinion of the 53B Emergency Coordinator/IEOF Director Reading at time since indicates LOSS or POTENTIAL LOSS of

°shutdown: the NCS barrier.

U - 0.5 hr > 390 R/lhr

(.5 - 2 hr >170 RIhr 2-4 hr > 125 R/hr 4-8 hr > 90R/hr

>8 hr > 531Uhr EN...pD

6. Emieri, ency Coordinator /EOF Director J udgmnent Any condition, including inability to monitor the barrier that in the opinion of the Emergency Coord inator/EOF Director indicates LOSS or PO1'ENTIAL LOSS of the containmeni batTier.

EN I

Enclosure 4.2 RP/O/A/5000/001I System Malfunctions Page 1 of 2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.2.U1.1 Inability to Reach Required 4.2.A.1 Unplanned Loss of Most or All 4.2.S.1 Inability to Monitor a END Shutdown Within Technical Safety System Annunciation or Significant Transient in Specilication Limits. Indication in Conitrol Room Progress.

With Either (I) a Significant OP~ERATING MODE: 1, 2, 3, 4 Transient in Progress, or (2)

Compensatory Non-Alarming OPER ATING MODE: 1,2,3,4 4.2.U.1-1 Plant is not brought to required Indicators Unavailable.

operating mode within Technical 4.2.S. 1-1 The following conditions Specifications LCO Action Statement OPERATING MODE: 1, 2, 3, 4 exist:

Time.

4.2.A.1I-I The following conditions exist: Loss of most (>50%)

4.2.U.2 Unplanned Loss of M'ost or All Safety Annunciators associated with System Annunciation or Indication in Unplanned loss of most (>50%) safety systems.

the Control Room for Greater Than annunciators associated with safety 15 Minutes. systems for greater than 15 minutes. AND OPERATING MODE: 1 ,2, 3, 4 AND A SIGNIFICANT PLANT TRANSIENT is in 4.2.U.2-1 The following conditions exist: In thle opinion of the Operations progress.

Shift Manager/Emergency Unplanned loss of most (>50%) Coordinator/EOF Director, the AND annunciators associated with safety loss of the annunciators or systems for greater than 15 minutes. indicators requires additional Loss of the OAC.

personnel (beyond normal shift AND compliment) to safely operate thle AND unit.

AND1 Inability to provide manual Inathe opinion of the Operation~s Shift monitoring of any of the Manager/Emergency CoordinatoriEOF EITIIER of the following: following Critical Safety Director, the loss of the annunciators

A SIGNIFICANT PLANT Functions:

or indicators requires additionafl TRANSIENT is in progress personnel (beyond normal shift

suberiticality compliment) to saflyv operate thle unit.

Loss of the OAC.

core cooling

heat sink ENI)

eontaln~ntelt.

('ONTINIIEI) ENDI

Enclosure 4.2 RP/O/A/5000/O01I System Malfunctions Page 2 of 2 UNUSUJAL EVENT ALERT SITE AREA EMERGENCY GENER,*AL EMERGENCY 4.2.U..3 Fuel Clad Degradation.

OPERATING MODE: I, 2, 3, 4I, 5 4.2.U.3-1 Dose Equivalent 1-131 greater than thle Technical Specifications allowable limit.

4.2.U.4 Reactor Coolant System (NCS)

Leakage.

OPERATING MODE: 1,2,3,4 4.2.U.4-l Unidentified leakage > 10 gpm.

4.2.UJ.4-2 Pressure boundary leakage > 10 gprn.

4.2.U.4-3 Identified leakage > 25 gpm 4.2.U.5 Unplannied Loss of All Onisite or Offsite Coinnunicationls.

OIPERATING MODE: ALL 4.2.11.5-1 Loss of all onsite communications capability (internal phone system, PA system, onsite radio system) affecting the ability to perfonn routine operations.

4.2.UJ.5-2 Loss of all offsite communications capability (Duke Emergenacy M-anagemtent Network [DE MN El].

NR(" ETIS linies, ol'lhite radio system, commcreial phonec system) allicting the abilitly to commun~icate wvith of'tsite antltori ties.

END)

Enclosure 4.3 RP/0/A/5000/001I Page 1 of"5 Abnormal Rad Levels/Radiological Effluent

[;NUSI!AI, I-\.'ENT ALERT SITE AiREA E:M ERG EN(CV G;ENERAl. EMERG ENC\Y 4.3.L .1 Any Unplanned Release (ofGaseous or 4.3.A.1 Any I nlplaunnd Release of 4.3.S.1 Boundary Dose Resulting 4.3.G.1 Boundary l)ose Resultitng Liquid Radioactivity to the Gaseous or Liquid fronm an Actual or f'rom an Actual or Environment thtat Exceeds Two Tiumes Radioactivity to the Imminent Release of hmnmitent Release of the SL(: Limits for 60 Minutes or Eiuvironmcnt thatt Exceeds Radioactivity Exceeds 100 Radioactivity that Exceeds Longer. 200 Times the SLC limits mrem TED)E or 500 mrem 1000 mrenm TEDE or 5000) for 15 Minutes or Longer. CDE Adult TIhyroid for onrei CDE Adult Thyroid OPERV [TINC MODE: AII the Actual or Projected for the Atuald or OPElRATING MODE: ALL Duration of the Release. Projected Duration of the 4.3.Ui.1-1 A valid Tlrip 2 alarm on radiation monitor Release.

E~vlF-49L or ENvlF'-57 or > 60 minuteS or 4..3.A.1-1 A\ valid indication on radiation OIPERATING NIOIOE: ALiL will likely continue for >_60 minultes monitor EMF- 49L or EMvF-57 of OPER*ATIING MODE: ALL which indicates that the release may have > 1.2E+05 cpm lbr> 15 minutes 4.3.S.1-1 A valid indication on exceeded the initiating condition and or will likely continue for Ž--15 radiation monitor EMF- 4.3.G.1-1 A valid indication on indicates the need to assess the release minutes, which indicates that the 36L of> 2.7E+06 cpm radiation monitor EMF-36t-with procedure [-IP/0/B/1009/0 14. release may have exceeded the sustained for> IS1 of>_8.3E+03 cpm initiating condition and indicates minmutes. sustained lbr > 15 minutes.

4I.3.tJ..i-2 A valid indication on radiation monitor the need to assess the release with EMF- 36L of>_ 3.(0E+t04 cpm for->_ 60) procedure H-P/0/B3/1009/014. 4.3.S.1-2 Dose assessment teamn 4.3.G.1-2 Dose assessment team minutes or will likely continue for >-60 calculations in~dicate dose calculations indicate dose minutes. which indicates that the release consequences greater than conseqtuences greater than may have exceeded the initiating 100 mrem "IEDE or 500 1000 ,mrem TEDE or 5000 condition and indicates the need to assess (Continued) mrem CDE Adult Thlyroid mrcm CDL Adtmh Thyroid the release with procedure AID-HP-ALIL- at the site houndary. at the site boundary.

0202.

lConmtin ned)

(( "ontini,ed)

0 Enclosure 4.3 R.P/O/A/5000/OO01 Abnormal Rad Levels/Radiological Effluent Page 2 of 5 UNU.SUAL, EVENT ALERT SITE AREA EM1ERGENCY GENERA I EM'ERGENCY 4.3.12...-3 Gaseous effluent being released 4.3.A.1-2 A valid indication on radiation 4.3.S.1-3 Analysis of field survey 4.3.G.1-3 Analysis of field survey exceeds two times SLC 16.1 1-6 for > nmonitor EMF- 36L of_> results or theld survey results or field survey 60 minutes as determined by RP~ 5.4E+05 cpm for> 15 minutes samples indicates dose samples indicates dose procedure. or will likely continue for >-15 consequences greater consequences greater minutes. which indicates that than 100 mrem TEDE or than 1000 ,mrem TEDE 4,3.U.1-4 Liquid effluent being released the release may have exceeded 500 mrem CDE Adult or 5000 mrem CDE exceeds two times SLC 16.11 I- for> the initiating condition and Thyroid at the site Adult Thyroid at the site 60 minutes as determined by RP indicates the need to assess the bounmdary. ho unda ry.

procedure. release with procedure AD-EP-ALL-0202. Note 1I: These EMF readings are Note I: These EMF readings are Note: If the monitor reading is sustained calculated based on average calculated based on average for the time period indicated in the 4.3.A.1-3 Gaseous effluent being annual meteorology, site anntual meteorology, site EAL AND the required assessments released exceeds 200 times the boundary dose rate, and boundary dose rate, and (procedure calculations) cannot be level of SLC 16.11-6 for> 15 design unit vent flow rate. design unit vent flow rate.

completed within this time period, minutes as determined by RP Calculations by the dose Calculations by the dose declaration must be made based on procedure. assessment team use actual assessment team use actual the valid radiation monitor reading. meteorology, release meteorology, release 4.3.A.1-4 Liquid efiluent being released duration, and unit vent flow duration, and unit vent flow (Continued) exceeds 200 times the level of rate. Therefore, these EM~F rate. Therefore, these EMF SLC 16.11-1 for> 15 minutes readings should not be used if iread ings should not be uised as determined by RP dose assessment team if dose assessment team procedure. calculations are available. calculations are available.

Note: If the monitor reading is Note 2: If dose assessment team Note 2: If dose assessment team sustained lbr the time period calculations cannot be calculations cannot be indicated in the EAL AND the completed in 15 minutes, completed in I 5 minutes.

required assessments then valid mtonitor reading then valid monitor (procedure calcula.tions) should be used for emergency reading should be used for cannot be completed within class iIi cation. emergency classification.

this time period, declaration mast be made baise on the ENDI END) valid rad iat ion monitor reading.

(ConltinuLed)

Enclosure 4.3 RP/O/A/5000/001I Abnormal Rad Levels/Radiological Effluent Page 3 of"5 UNLUSI.1AL EVENT ALERT SITE AREA EMERGENCY GENERAL EM'ERGENCY 41.3. I.2 Uneixpected Increase in Plant 4.3.A.2 Miajor Damage to Irradiated Radiation or Airborne Fuel or Loss of Water Level Concentration. that Has or Will Result in the Uncovering of Irradiated OPERATING MODE: ALL Fuel Outside the Reactor Vessel.

4.3.U.2-1 Indication of uncontrolled water Does not apply to spent fuel in diy cask level decrease of greater than _6 storage. Refer to EPLAN Section D inches inl the reactor refueling cavity basis document with all irradiated fuel assemblies remaining covered by water. OPERATING MODE: ALL 4.3.A.2-1 An unplanned valid trip I1 4.3.U.2-2 Uncontrolled water level decrease of alarm on any of the greater than 6 inches in the spent fuel following radiation pool and fuel transfer canal with all monitors:

irradiated fuel assemblies remaining covered by water. Spent Fuel Building Refueling Bridge 4.3.U.2-3 Unplanned valid area EM~F reading IEMF-15 increases by a factorof 1,000 over 2EMF-4 normal levels as shown in Enclosure 4.10. Spent Fuel Pool Ventilation I EMIF-42 END 2EMF-42 Reactor Building Refueling Bridge (applies to Mode 6 and No Nlode Only)

IEMF-17 2EMlF-2 Containment Noble Gas Monitor (Applies to Mode 6 and No Mode (Jnly) 1 EMF-39 2EiNlF-3')

l( " liii ijed I

0 VP Enclosure 4.3 RP/0/A/5000/001 Abnormal Rad Levels/Radiological Effluent Page 4 of"5 UiNtSUAkL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.2-2 Plant personnel report that water level drop in reactor refueling cavity. spent fuel pool, or fuel transfer canal has or will exceed makeup capacity such that any iIradiated fuel will become uncovered.

4.3.A.2-3 NC system wide range level <95% after initiation of NC system make-up.

AND Any irradiated fuel assembly not capable of being lowered into spent fuel pool or reactor vessel.

4.3,A.2-4 Spent Fuel Pool or Fuel Transfer Canal level decrease of>2 feet after initiation of makeup.

AN___D_

Any irradiated fuel assembly not capable of being fully lowered into the spent fuel pool racks or transfer canal fuel transfer system basket.

(C'ontinued)

0 0 Enclosure 4. RP/0/A/5000/001 Abnormal Rad Levels/Radiological Effluent Page 5 of 5 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.3 Release of Radioactive M~aterial or Increases in Radiation Levels WVithin the Facility That Impedes Operation of Systems Required to Mlainitaini Safe Operations or to Establish or Maintain Cold Shutdown.

OPERATING MODE: ALL 4.3.A.3-1 Valid reading on IEMF-12 greater than 15 mremlhr in the Control Room.

4.3.A.3-2 Valid indication of radiation levels greater than 15 mrem/hr in the Central Alarm Station (CAS) or Secondary Alarm Station (SAS).

4.3.A.3-3 Valid radiation monitor reading exceeds the levels shown in Enclosure 4.10.

ENI)

0 Enclosure 4.4 RP/0/A/5000/001I Loss of Shutdown Functions Page 1 of 3 UJNU~SUAL EVENT' ALERT SITE AREA EMERGENCY GENERAL EMIERGENCY END 4.4.A. I Failure of Reactor 4.4.S.1 Failure of Reactor 4.4.G.1 Failure of the Reactor Protection System Protection System Protection System to Instrumentation to iostrnmnentation to Coniplcte an Automatic Trip Complete or initiate an Complete or Initiate an and Mianual Trip Was NOT Automatic Reactor Trip Automatic Reactor Trip Successful and There is Once a Reactor Protection Once a Reactor Protection Indication of an Extreme System Setpoint Has Been System Setpoint Has Beeni Challenge to the Ability to Exceeded and Manual Trip Exceeded and Manual Trip Cool the Core.

Was Successful. Was NOT Successful.

OPERATING MODE: 1 OPERATING MODE: 1, 2, 3 OPERATING MODE: I 4.4.G.1-1 The following conditions exist:

4.4.A.1-1 The following conditions exist: 4.4.S.1-1 The following conditions exist:

Valid reactor trip signal Valid reactor trip signal Valid reactor trip signal received or required and received or required and received or required and automatic reactor trip automatic reactor trip automatic reactor trip was not successful.

was not successful. was not successful.

AND AND AND M~anual reactor trip from the Manual reactor trip from the M'anual reactor trip from the control rooml was uot control room is successful and control room was not successfufl in reducing reactor reactor power is less than 5% successful in reducing reactor power to less than 5% and and decreasing. power to less than 5% and decreasing.

decreasing.

(Cnntinuedl) ANDI

((omntiniuedl) ErIT'HER of' the following conditions exist:

Core ('ooling (SF-RED

1-eat Sink (SF-RED.

EN I

Enclosure 4.4 RP/0/A/5000/001I Loss of Shutdown Functions Page 2 I'3 UNUSUAL EVENT A LERT SITE AREA EMERGENCY GENERAL EM~ERG ENCY 4.4.S.2 Complete Loss of Functioni 4.4.A.2, Inability to M~aintain Plant Needed to Achieve or in Cold Shutdown.-

Maintain ltot Shutdown.

OPERATING MODE: 5, 6 OPERATING MODE: 1, 2,3, 4 4.4.A.2-1 Total loss of ND and/or RN 4.4.S.2-1 Suberiticality CSF-RED.

and/or KC.

4.4.S.2-2 1-eat Sink CSF-RED.

AND 4.4.S.3 Loss of Water Level in the One of the following: Reactor Vessel That Has or Will._[ Uncover Fuel in the

Inability to maintain Reactor Vessel.

reactor coolant temperature OPERATING MODE: 5,6 below 2000 F 4.4.S.3-1 Failure of heat sink causes loss

Uncontrolled reactor of cold shutdown conditions.

coolant temperature rise to

>180 0 F. AND Lower range Reactor Vessel Level Indication System END (RVLIS) decreasing after initiation of NC system makeup.

4.4.S.3-2 Failure of heat sink causes loss o f cold shutdown conditions.

A~NI Reactor Coolant (NC) system mid or wide range level less than 11% and decreasing after initiation ot NC system makeup.

(C(iollltin lied)

Enclosure 4.4 RPIOIAI5S 001001 Loss of Shutdown Functions Page 3 of 3 IUNIUSIAL EVENT' ALERT SITE AREA E M ERGENCY GENERAL EMERGENCY 4.4.S.3-3 Failure of heat sink causes loss of cold shutdown conditions.

AND Either train ultrasonic level indication less than 7.25% and decreasing afier initiation of NC system makeup.

END

0 Enclosure 4.5 RP/O/A/5000/OO01 Loss of Power Page 1 o f2

[UNUSUAIL EVENT ALERT' SITE AREA EMERGENCY GENERAL EMERGENCY 4.5.U.1 Loss of All Offsite 4.5.A.1 Loss of All Offsite 4.5.S.1! Loss of All Of1site 4.5.G.1 Prolonged Loss of All Power to Essential Power and Loss of All Power and Loss of All (Offsite and Onsite) AC Busses for Greater Than Onsite AC Power to Onsite AC P~ower to Power.

15 Minutes. Essential Busses During Essential Busses.

Cold Shutdown Or OPERATING MODE: 1, 2, 3, 4 OPERATING MODE: 1,2, 3, 4I Refueling Mode. OPERATING MIODE: 1, 2,3, 4 4.5.G.1-1 Prolonged loss of all 4.5.U.I-1 The tbllowing conditions OPERATING MIODE: 5, 6, No 4.5.S.1-1 Loss of all oti~ite and offsite and onsite AC exist: Mode onsite AC power as power as indicated by:

indicated by:

Loss of offsite power to 4.5.A.i-I Loss of all offsite and Loss of power on essential buises ETA and onsite AC power as Loss of power on essential buses ETA and ETB for" greater than 15 indicated by: essential buses ETA and ETB for greater than 15 minutes. ETB. minutes.

Loss of power on AN_.D_ essential buses ETA and AND AN....D ETB.

Both emergency diesel Failure to restore power to Standby Shutdown generators are supplying AND at least one essential bus Facility (SSF) fails to power to their respective within 15 minutes. supply NC pump seal essential busses. Failure to restore power to injection OR CA supply at least one essential bus (Continiuedj to Steam Generators.

within 15 minutes.

(Continued) AND (Continued)

(Conitinued)

0 0 Enclosure 4.5 RPIO/AtS001001 Loss of Power Page>2 or)2 1JNIJSI.JAIL EVENT" ALERTI SITE AREA EMERGENCY GENERAL. EMERGENCY OPERATING MODE: 5, 6, No 4.5.A.2 AC power to essential 4.5.S.2 Loss of All Vital DC At least one of the Mode busses ireduced to a Power. Iollowing conditions single power source for exist:

4.5.LL.I-2 The following conditions greater than 15 minutes OPERATING MODE: 1, 2,3, 4 exist: such that an additional

Restoration of at least Loss of offsite power to single failure could 4.5.S.2-1 The following conditions one essential bus essential buses ETA and result in station exist: within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is ETB for greater than] 15 blackout. NOT likely minutes. Unplanned loss ot both AND OPERATING MODE: 1, 2, 3, 4 unit related busses: EBA

Indication of One emergency diesel and EBD both <112 continuing generator is suipplying 4.5.A.2-1 The following condition VDC, and EBB and EBC degradation of core power to its respective exists: both <109 VDC. cooling based on essential bus. Fzission Prodtuct AC power capability has AN__.DD Barrier monitoring.

4.5.U.2 Unplaiiued Loss of been degraded to one Required DC Power essential bus powered Failure to restore power to ENI)

During Cold Shutdown or from a single power at least one required DC Refueling Miode for source for > 15 riin. due bus within 15 minutes Greater thani 15 Minutes. to the loss of all but one from the time of loss.

of:

OPERATING MODE: 5, 6 END SATA SATB 4.5.11.2-1 The following conditions ATC ATD exist: DiG A DIG B I ilplaliied loss of1 both unit [NI) irelated busses: EBA and 1.BD1 both <112 \'DC. and EBB and EBC both <109 V DC.

ANID Fa i ure_ to restore po~~'er Ito alleast one treulireul D(" bus wvithiin 15 Ininntes fromn lhe lime ofl loss.

I.N I)

Enclosure 4.6 IP/O/A/5000/O01I Fire/Explosion and Security Events Page 1 of 3 UNUISUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.6.U.1 Fire Within Protected Area 4.6.A.1 fire or Explosion Affecting 4.6.S.1 HOSTILE ACTION within 4.6.G.1 HOSTILE ACTION Boundary NOT the Operability of Plant the PROTECTED AREA Resulting in Loss of Physical Extinguished Within 15 Safety Systems Required to Control of the Facility.

Min utes o f Detection OR._ Establish or Manintain Safe OPERATING MODE: ALL Explosion Within the Sbhutdown. OPERATIN(G M~ODE: ALL Protected Area Boundary. 4.6.S.1-I A HOSTILE ACTION is OPERATING MIODE: 1, 2, 3, 4, 5, 6 occurring or has occurred 4.6.G.l-1 A H-OSTILE ACTION has OPERATING MODE: ALL within the PROTECTED occurred such that plant 4.6.A. 1-1 The following conditions AREA as reported by the CNS personnel are unable to operate 4.6.U.I-1 Fire inl any of the following exist: Security Shift Supervision equipment required to areas NOT extinguished (Non-security events) maintain safety functions.

within 15 minutes of control Fire or explosion in any of the EN.._D room notification or following areas: 4.6.G.I-2 A IHOSTILE ACTION has verification of a control room

Reactor Building caused failure of Spent Fuel fire alarm.

Auxiliary Building Cooling Systems and

Diesel Generator Rooms IMMINENT fuel damage is

Reactor Building

Control Room likely Ibr a FRESHLY OFF-

Auxiliary Building

RN Pumphouse LOADED REACTOR

Diesel Generator Rooms

SSF CORE in pool.

Control Room

CAS

RN Pumphouse

SAS

SSF

FWST ENI)

CAS

Doghou~ses (Applies in

SAS Mode 1, 2, 3, 4 only).

Doghouses

FWST AND

Turbine Building

Service Building One of the following:

Monitor'Tank Building

ISFSI

Aff~ected safety system

[.Jit I.;1 -Iranslbrnmer Yard parameter indications show Areas -degraded performance (Contiinued) ttConlinued)

Enclosure 4.6 RP/0/A/5000/00 I Fire/Explosion and Security' Events Page 2 of 3 UNUSUAL EVENT ALERT SIT'E AREA EMERGENCY GENERAL EMERGENCY 4.6.U.1-2 Report by plant personnel of *Plant personnel report an unanticipated explosion visible damtage to within protected area permanent structures or boundary resulting in visible equipment within the damage to permanent specified area required to structure or equipment or a establish or maintain safe loaded cask in the ISFSI. shutdown within the specifications.

4.6.U_.2 Confirnmed SECUJRITY CONDITION or T'hreat Note: Only one train of a system Which Inidicates a Potential neceds to be affected or Degradation in the Level of damaged in order to satisfy Safety of the Plant.

this condition.

OPERATING MODE: All 4.6.A.2 Fire or Explosion Affecting the Operability of Plant 4.6.U..2-1 A SECURITY CONDITION Sa.fety Systems Required to that does NOT involve a Establish or Maintain Safe HOSTILE ACTION as reported by the CNS Security Shutdown.

Shift Supervision.

OPERATING MODE: No M~ode 4.6.LJ.2-2 A credible site-specilie security threat notiflication. 4.6.A.2-I The following conditions exist:

4.6.11.2-3 A validated notilication from (Non-security events)

NRC providing ijiformatioji ol' Fire or exp~losion in any of the an airerati threat. following areas:

Spent Fuel Pool ENI)

Auxiliary Buildingz.

RN Pump house AND One of the following:

Spent Fuel Pool level alnd/or" temlperalture showv degraded performlance t(-'ontinulicd)

Enclosure 4.6 RP/0/A/5 000/001 Fire/Explosion andi Security Events Page 3 of' 3 I)NLISLAL EVENT AILERT SITE AREA EMERGENC'Y GENERAL ENIER(GENCY' Plant personnel report visible damage to permanent structures or equipment supporting spent fuel pool cooling.

4.6.A.3 HOSTILE ACTION Within tihe OWNER CONTROLLED AREA or Airborne Attack Threat.

OPERATING MODE: ALL 4.6.A.3-1 A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the CNS Security Shift Supervision 4.6.A.3-2 A validated notification from NRC of airliner attack threat within 30 minutes of the site.

ENI)

Enclosure 4.7 RP/O/A/5 000/001 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety Page 1 of 4 UNUSuA*L EVENT' ALERT SITE AREA EMERGENCY GENERAL EM'ERGENCY 4.7.1U.1 Natural and Destructive 4.7.A.!I Natural and Destructive 4.7.S.1 Control Room Evacuation 4.7.G.1 Other Conditions Existing Phenomena Affecting tihe Phenomena Affecting the Ha4s Been Initiated and Plant Which in the Judgement of Protected Area. Plant Vital Area. Conitrol Cannot Be the Emergency Established. Coordinator/EOF Director OPERATING MODE: ALL OPERATING MODE: ALL Warrant Declaration of OPERATING MODE: ALL General Emergency.

4.7.U1.1-1 Tremor felt and valid alarm on 4.7.A.1-1 Valid "OBE Exceeded" Alarm tihe Syscom Seismic on IAD-4.B/8 4.7.S.1-1 The following conditions OPERATING MODE: ALL Monitoring Systemn (OAC C 1D22 52). exist:

4.7.AAl-2 'Tornado or high winds: Control Room evacuation has been 4.7.G.1-I Other conditions exist which 4.7.U1.1-2 Report by plant personnel of initiated per in the Judgement of the toi-nado striking within Tornado striking plant AP/II(2)/A15500/017 Emergency Coordinator/EOF protected area structures within the vital AN.__D Director indicate:

botmdary/ISFSI. a rea: Control of the plant cannot be established fi'om the ASP or (1) actual or imminent 4.7.U1.1-3 Vehicle crash into plant the SSF within 15 minutes. substantial core degradation e Reactor Building structures or systems within Auxiliary Building with potential for loss of protected area FWST 4.7.S.2 Other Conditions Existing containmaent 0i boundary!/ISFSlI. Diesel Generator Rooms Which in the Judgement of 0

Control Room the Emergency OR 4.7.U1.1-4 Report of turbine Fa~ilure a RN Pumphouse Coordinator/EOF Director resulting in casing penetration 0 SSF Warrant Declaration of Site (2) potential for uncontrolled or damage to turbine or Doghouses Area Emergency. radionuclide releases. These generator seals. CAS releases can reasonably be a

SAS OPERATING MIODE: ALL expected to exceed 4.7.1_1.1-5 Independent Spent Fuel Cask Environmental Protection tipped over or dr'opped greater 4.7.S.2-l Other conditions exist which Agency Protective Action than 24 inches. OR Guideline levels outside the in the Judgement of the sustained winds >_74 mph for Emergency Coordinator!EGF site boundary.

4.7.11..1-6 Uncontrolled Ilooding in the

> 15 minutes. Director indicate actual or ISFSI area.

likely major f~itilures ol plant En

__)

4.7.11..1-7 Tornado generatecd missiles(s) (Continued) functions needed lor impacting the ISFSi. protection of the~ public.

{(C oiitn liicud)

END

0 Enclosure 4.7 RPIO/AI/500I/O01 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety Page 2 o1"4 IJNUSUJAL EVENT ALERT SITE AREA EMER*GENCY' GFNERAL EMERGENCY 4.7.1_1.2 Release of Toxic or 4.7.A. 1-3 Visible structural damage Flanmnable Gases D~eemed caused by either:

Detrimental to Safe

Vehicle crashes Operation or the Plant. OR

Turbine failure generated OPERALTING MODE: ALL missiles, OR 4.7.U.2-l Report or detection of'toxic or

Other catastrophic events flammable gases that could enter within the site boundary on any of the following plant in amounts that can aff'ect safe structures:

operation of the plant.

Reactor Building

Auxiliary Building 4.7.U.2-2 Report by Local. County or

FWST State Officials for potential

Diesel Generator Rooms evacuation of site personnel SControl Room based on offsite event.

RN Pump 1-ouse

SSF 4.7.U.3 Other Conditions Existing

Doghouses Which in the Judgeinent of

CAS the Emergency

SAS Coordiziator/EOF Director Warrant Declaration of an Unusual Event.

(Continued)

OPERATING MODE: AILL 4.7. U.3-1I Other conditions exist which in the j udgcmlcnt o f thte Emcrgency Coordinazor/ELOF D)irector indic'ate a potential degradatlion ofth ltevel of Siitct\' of'thlw plaint.

[NI)

Enclosure 4.7 RI?/01A/5000/00 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety Page 3 of"4 UNUSUIAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.7.A.2 Release of Toxic or Flammable Gases Within a Facility Structure Which Jeopardizes Operation of Systems Required to Maintain Safe Operationis or to Establish or Majatain Cold Shutdown.

OPERATING MODE: ALL 4.7.A.2-1 Report or detection of toxic gases within a Facility Structure in concentrations that will be life threatening to plant personnel.

4.7.A.2-2 Report or detection of flammable gases within a Facility Structure in concentrations that will affect the safe operation of the plant.

Structures lor the above EALs:

Reactor Building

Auxiliary Building

Diesel Generator Ro~oms

Control IRtooi

RN Ptinmphouse

SSF

CAS

S:\S (C~oniniiiid)

Enclosure 4.7 IP/0/A/5 000/001 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety Page 4 of 4 UINUISUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.7.A.3 Control Room Evacuation llas Beeni Initiated.

OPERATING MODE: ALL 4.7.A.3-I Control Room evacuation has been initiated per AP/1 (2)/A/5500/0 17.

4.7.A.4 Other Conditions Existing Which ini the Judgemnent of the Emergency Coordinator/EOF Director Warrantr Declaration of an Alert.

OPERATING MODE: ALL 4.7.A.4-10dtler conditions exist which in the Judgement of the Emergency Coordinator/EOF Director indicate that plant safety systems may be degraded and that increased monitoring of plant functions is warranted.

END

Enclosure 4.8 RP/O/A/5000/O00 Definitions/Acronyms Pagze I of 4 ALERT- Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of hostile action. Any releases are expected to be limited to small fractions of the EPA protective action guideline exposure levels.

ALL (As relates to Operating Mode Applicability) - Mlodes 1, 2, 3,4,5,6 and No M~ode (Defueled)

BOMB - Refers to an explosive device suspected of having sufficient force to damage plant systems or" struictuires.

CARF - Containment Air Return Fan.

CIVIL DISTURBANCE - A group often (10) or more people violently protesting station operations or activities at the site. A civil disturbance is considered to be violent wvhen force has been used in an attempt to injure site p~ersonnel or damage plant property.

COGNIZANT FACILITY STAFF - Any member of facility staff, who by virtue of training and experience.

is qualified to assess the indications or reports for validity and to compare the same to the EALs in the licensee's emergency classification scheme (Does not include staff"whose positions require they rcport, rather than assess, abnormal conditions to the facility.).

CREDIBLE THREAT - A threat should be considered credible when:

Physical evidence supporting the threat exists.

Information independent (law enforcement) from the actual threat message exists that supports the threat.

A specific group or organization claims responsibility for the threat.

EPA PAG - Environmental Protection Agency Protective Action Guidelines for exposure to a release of radioactive material.

EMERGENCY RELEASE - Any unplanned, quantifiable radiological release to the environment during~ an emergency event. The release does not have to be related to a declared emergency.

EXPLOSION - A rapid. violent unconfined combustion, or a catastrophic failure of pressurized equ~ipment (e.g., a steam line or f'eedwater line break) that imparts energy sufficient to potentially damage or creates shrapnel to actually damage permanent structures, systems or components. An electrical breaker flash that creates shrapnel and results in damage to other components beyond scorching should also be considered.

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

FIRE - Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute fires. Observation of flames is preferred but is NOT required if"large quantities of smoke and heat are observed. An electrical breaker f'lash that creates high temperatures for a short duration and merely localized scorching to that breaker and its coinpartinent shouild not be considered a fire.

FRESHLY OFF-LOADED REACTOR CORE - The complete removal and relocation of all fuel assemblies from the reactor core and placed in the spent fuel pool. (Typical of a 'No Mode' operation during a refuel outage that allows safety system maintenance to occur and results in maximum decay heat load in the spent fuel pool system.)

Enclosure 4.8 RPIOIA/5000/O()I Definitions/Acronyms Page 2 o f 4 FUNCTIONAL - A component is fully capable of meeting its design function. It would be declared INOPERABLE if unable to meet Technical Specifications.

GENERAL EM'ERGENCY- Events are in process or have occurred which involve actual or imminent substantial core degradation or melting wvith potential for loss of containment integrity or hostile action that results in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA protective action guideline exposure levels offsite for more than the immediate site area.

HOSTAGE - A person(s) held as leverage against the station to ensure demands will he met by the station.

HOSTILE ACTION - An act toward an NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidates the licensee to achieve an end. This includes attack by air.

land, or water using guns, explosives, PROJECTILES, vehicles or other devices used to deliver destructive force. Other acts that satisfy, the overall intent may be inacluded. HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concer'ted attack on the NPP. Non-terrorism-based EALs should be used to address such activities (e.g.. violent acts between individuals in the OWNER CONTROLLED AREA).

HOSTILE FORCE - One or more individuals who are engaged in a determined assault, overtly or by' stealth and deception. equipped with suitable weapons capable of killing, maiming or causing destruction.

IMMINENT - Mitigation actions have been ineffective, additional actions are not expected to be successful.

and trended information indicates that the event or condition will occur. Where IMMINENT time fr'ames are specified, they shall apply.

INOPERABLE - A component does not meet Technical Specifications. The component may be f'unctional, capable of meeting its design.

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

INTRUSION - A person(s) present in a specified area without authorization. Discovery of a BOMB in a specified area is indication of INTRUSION into that area by a HOSTILE FORCE.

ISFSI - Independent Spent Fuel Storage Installation - Includes the components approved for loading anod storage of spent fuel assemblies.

LOSS - A component is INOPERABLE and not FUNCTIONAL.

NO MODE - Defueled.

OWNER CONTROLLED AREA - Area outside the protected area fence that immiiediatelv surrounds the plant. Access to this area is generally restricted to those entering on official business.

PROJECTILE - An object directed toward a NPP that could cause concern for its continued operability.

reliability or personnel saf-ety.

PROLONGED - A duration beyond normal limits, defined as 'greater than 15 minutes" or as determined b'c the judgment of the Emergency Coordinator.

Enclosure 4.8 RP/O/A/5000O/O0 I Definitions/Acronyms Page 3 o f4 PROTECTED AREA - Typically, the site specific area which normally encompasses all control led areas within the security PROTECTED AREA fence.

REACTOR COOLANT SYSTEM (RCS/NCS) LEAKAGE - RCS Operational Leakage as defined in the Technical Specification Basis B 3.4.13.

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

SABOTAGE - Deliberate damage, misalignment, or misoperation of plant equipment with the intent to render the equipment unavailable. Equipment found tampered with or damaged due to malicious m ischie f nay not meet the definition of SABOTAGE until this determination is made by security superv ision.

SECURITY CONDITION - Any Security Event as listed in the approved security contingency plan that constitutes a threat/compromise to site security, threat/risk to site personnel or a potential degradation to the level of safety of the plant. A SECURITY CONDITION does not involve a HOSTILE ACTION.

SIGNIFICANT PLANT TRANSIENT- An unplanned event involving one or more of the f'ollowing: J)

Automatic turbine runback >25% thermal reactor power, (2) Electrical load rejection >25% full electrical load; (3) Reactor Trip, (4) Safety Injection, (5) Thermal power oscillations > 10%.

SITE AREA EMERGENCY - Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (I) toward site personnel or equipment that couild lead to the likely failure of or; (2) that prevent effective access to equipment needed for the protection of the public.

Any releases are not expected tO exceed EPA Protective Action Guidelines to exposure levels beyond the site boundary.

SITE BOUNDARY - That area, including the protected area, in which Duke Energy has the authority to control all activities, including exclusion or removal of personnel and property.

SLC - Selected Licensee Commitments.

SUSTAINED - A duration of time long enough to confirm that the CSF is valid (not momentary,).

TERMINATION - Exiting the emergency condition.

TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) - The sum of external dose exposure to radioactive plume, to radionuclides deposited on the ground by the plume, and the internal exposure inhaled radionuclides deposited in the body.

TOXIC GAS - A gas that is dangerous to life or health by reason of inhalation or skin contact (e.g. chlorine l.

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

UNPLANNED - An event or action is UNPLANNED if it is not the expected result of normal operations.

testing, or maintenance. Events that result in corrective or mitigative actions being taken in accordance with abnormal or emergency procedures are UNPLANNED.

Enclosure 4.8 RPi0/Ai5000i00O( 1 Definitions/Acronyms Page 4 oft 4 UNUSUAL EVENT- Events are in process or have occurred which indicate a potential degradation1 ofthe level of safety of the plant or indicate a security threat to facility protection has been initiated. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.

VALID - An indication or report or condition is considered to be VALID when it is conclusively verified by:

(1 ) an instrument channel check, or (2) indications on related or redundant instrumentation, or (3) by direct observation by plant personnel such that doubt related to the instrument's operability, the condition's existence or the report's accuracy is removed. Implicit in this definition is the need for timely assessment.

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

VISIBLE DAMAGE - Damage to equipment or structure that is readily observable without measurements.

testing, or analyses. Damage is sufficient to cause concern regarding the continued operability or reliability of aff'ected structure, system, or component. Example damage: deformation due to heat or impact, denting.

penetration, rupture, cracking, paint blistering.

VITAL AREA - Areas within the PROTECTED AREA that house equipment important for nuclear safety.

Access to a VITAL AREA is allowed only if an individual has been authorized to he in that area pe:r the security plan. Therefore, VITAL AREA is a security term.

Enclosure 4.9 RPlOli/150001001 Emergency Declaration Guidelines Page 1 of 2 THE FOLLOWING GUIDANCE IS TO BE USED BY THE EMERGENCY COORDINATOR IN ASSESS ING EMERGENCY CONDITIONS.

Assessment, classification and declaration of any applicable emergency condition shouild be completed with 15 minutes after indication or information is available to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded.

The Emergency Coordinator shall review all applicable initiating events to ensure proper classification.

The BASIS Document (located in Section D of the Catawba Nuclear Site Emergency Plan) is available for review if any questions arise over proper c lassification.

Emergencies are declared for the site. If an event results in multiple emergency action levels onl a unit or different emergency action levels on each unit, then the emergency' declaration shall be based on the higher classification. Information relating to the unit with the lesser classification wvill be noted as additional information on the Emergency Notification Form (EN F).

If an event occurs, and a lower or higher plant operating mode is reached before the classification can be made, the classification shall be based on the mode that existed ait thle time the event occurred.

The fission product barrier matrix is applicable only to those events that occur at (Mode 1-4) hot shutdown or higher. An event that is recognized at cold shutdown or lower (Mode 5 or 6) shall not be classified using the fission product barrier matrix. Reference would be made to the other enclosures that provide emergency action levels for specific events (e.g. severe weather, fire.

security).

If a transient event should occur, the following guidance is provided.

I. Some emergency action levels specify that a condition exist for a specific duration prior to declaration.

a. For these EALs, the classification is made when the Emergency Coordinator assessment concludes that the specified duration is exceeded or will be exceeded (i.e. condition cannot be reasonably corrected before the duration elapses)..

whichever is sooner.

b. If a plant condition exceeding EAL criteria is corrected before thle specified duration time is exceeded, the event is NOT classified by that EAL. Lower Severity EALs, if any, shall be reviewed for possible applicability' in these cases.

Enclosure 4.9 RP!O/A/5000/O0 I Emergency Declaration Guidelines Page 2 of 2

2. If"a plant condition exceeding EAL criteria is not recognized at the time of"occurrence.

but is identified well after the condition has occurred (e.g. as a result of routine log or record review) and the condition no longer exists, an emergency shall NOT be declared.

Reporting under IOCFR5O.72 may be required. Such a condition could occur, f'or example, ifra f'ollow-up evaluation of an abnormal condition uncovers evidence that the condition was more severe than earlier believed.

3. If an emergency classification is warranted, but the plant condition is corrected prior to declaration and notification, the Emergency Coordinator must consider thle potential that the initiating condition (e.g. Failure of Reactor Protection System or earthquake) may have caused plant damage that warrants augmenting the on-shif't personnel via activation of the Emergency Response Organization. The following action shall be taken:

a. For UNUSUAL EVENTS, the condition shall be declared and notifications made. The event may be terminated in the same notification or in a follow-up notificati on.

b. For ALERT, SITE AREA EMERGENCY, and GENERAL EMERGENCY. the event shall be declared and the emergency response organization activated.

DETERMINATION OF "EVENT TIME" (TIME THE 15 MINUTE CLOCK STARTS)

I.Event time is the time at which indications become available that an EAL has been exceeded.

2. Event time is the time the 15 minutes clock starts for classification.

3. The event classification time shall be entered on the emergency notification form.

MOMVENTARY ENTRY INTO A HIGHER CLASSIFICATION If', while in an emergency classification, the specified EALs of a higher classification are met momentarily, and in the judgment of the Emergency Coordinator are not likely to recur, the entry into the higher classification must be acknowledged. Acknowledgment is perf'ormled as follows:

If"this condition occurs prior to the initial notification to the emergency response organization and off site agencies, the initial message should note that the site is currently in the lower classification, but had momentarily met the criteria f'or thne higher classification. It should also be noted that plant conditions have improved and stabilized to the point that the criteria f-or the higher classification are not expected to be repeated.

0 Enclosure 4.10 RPIOIAiSO001001I Radiation M'onitor Readings fo~r Enclosure 4.3 Page 1 of Note: These values are not inatended to apply to anticipated temporary increases due to planned events (e.g. incore detector movement, radwaste container movemenat, depleted resin transfers, etc.).

Detector Elevation Column Identifier Unusual Event Alert SnR/hr mR/hr 1EMF-lI 522' FF, 57 Auxiliary Building Corridor 500 5000 I1ENMF-3 543' GG, 55 Unit I Charging Pump Area 100 5000 IEMF-4 543' GG. 59 Unit 2 Charging Pump Area 100 5000 I ENIF-7 560' NN, 55 Unit I Auxiliary Building Corridor 1500 5000 1EMF-8 560' >NN, 59 Unit 2 Auxiliary Building Corridor 500 5000 I EMF-9 577' LL. 55 Unit 1 Aux. Building Filter Hatch 100 5000 I EME- 10 577' LL. 58 Unit 2 Aux. Building Filter H~atch 100 5000 I EMvF-22 594' KK, 53 Containment Purge Filter Area 100 5000 2EMF-9 594' KK, 61 Containment Purge Filter Area 100 5000

Page I of 5 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME I PROCEDURE TITLE SRP/0/A/5000/001 Classification of Emergency (Rev. 036)

RP/0/A/5000/002 Notification of Unusual Event (Rev. 045)

RP/0/A/5000/003 Alert (Rev. 050)

RP/0/A/5000/004 Site Area Emergency (Rev. 053)

RP/0/A/5 000/005 General Emergency (Rev. 054)

RP/0/A/5000/06 Deleted RP/O/A!5000/006 A Notifications to States and Counties from the Control Room (Rev. 033)

RP/0/A!5000/006 B Notifications to States and Counties from the Technical Support Center (Rev. 037)

. RP/0/A/5000/006 C Deleted RP/0/A/5 000/007 Natural Disaster and Earthquake (Rev. 043)

RP/0/A!5000/08 Deleted RP/0/B/5000/008 Hazardous Materials Spill Response (Rev. 043)

RP/0/A/5000/009 Collision/Explosion (Rev. 012) ,

RP/0/A15000/010 Conducting a Site Assembly or Preparing the Site for an Evacuation (Rev. 027)

RP/0/A/5000/1 1 Deleted RP/0/B/5000/12 Deleted RP/0/B/5000/0 13 NRC Notification Requirements (Rev. 038)

RP/0/B/5000/14 Deleted RP/0/A/5000/015 Core Damage Assessment (Rev. 007)

. RP/0/B/5000i016 RP/0/B/5000/17 Deleted Deleted February 18, 2016

Page 2 of 5 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME I PROCEDURE TITLE RP/0/A/5000/01 8 Emergency Worker Dose Extension (Rev. 002)

RP/0/B/5000/019 Deleted RP/0/A/5000/020 Technical Support Center (TSC) Activation Procedure (Rev. 038)

RP/0/A/5000/021 Deleted RP/0/B/5000/022 Deleted RP/0/B/5000/023 Deleted RP/0/A/5000/024 OSC Activation Procedure (Rev. 034)

RP/O/B/5000/025 Recovery and Reentry Procedure (Rev. 003)

RP/0/A/5000/026 Site Response to Security Events (Rev. 017)

RP/0/B/5000/028 Nuclear Communications Emergency Response Plan (Rev. 006)

February 18, 2016

Page 3 of 5 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II PROCEDURE TITLE HP/0/B/1 000/006 Emergency Equipment Functional Check and Inventory (Rev. 060)

HP/0/B/1009/001 Deleted HP/0/B/1009/003 Radiation Protection Primary to Secondary Leakage Program (Rev. 012)

HP/0/B/1009/004 Environmental Monitoring for Emergency Conditions Within the Ten-Mile Radius of CNS (Rev. 031)

HP/0/B/1 009/005 Personnel/Vehicle Monitoring for Emergency Conditions (Rev. 01 8)

HP/0/B/1009/006 Alternative Method for Determining Dose Rate Within the Reactor Building (Rev. 009)

HP/0/B/1009/007 In-Plant Particulate and Iodine Monitoring Under Accident Conditions (Rev. 020)

HP/0/B/1009/008 Contamination Control of Injured Individuals (Rev. 016)

HP/0/B/1 009/009 Deleted HP/0/B/1009/014 Radiation Protection Actions Following an Uncontrolled Release of Liquid Radioactive Material (Rev. 009)

H-P/0/B/1009/016 Deleted HP/0/B/1009/017 Deleted FIP/1/B/1009/017 Deleted FIP/2/B/1009/017 Deleted l-P/0/B/1009/018 Deleted JHP/0/B/1009/019 Emergency Radio System Operation, Maintenance and Communication (Rev. 010)

IIP/0/B/1 009/024 Implementing Procedure for Estimating Food Chain Doses Under Post-Accident Conditions (Rev. 002)

February 18, 2016

Page 4 of5 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II PROCEDURE TITLE HP/0/B/1009/025 Deleted HP/0/B/1009/026 Superseded SH/0/B/2005/00 1 Superseded SI-/0/B/2005/002 Deleted SH/0/B/2005/003 Deleted OP/0/A/6200/021 Deleted SR/0/B/2000/001 Deleted S R/0/A/2000/00 1 Standard Procedure for Corporate Communications Response to the Emergency Operations Facility (Applies to Catawba/McGuire/Oconee) (Rev. 002)

SR/0/B/2000/002 Deleted SR/0/A/2000/003 Activation of the Emergency Operations Facility (Rev. 008)

SR/0/B/2000/003 Deleted SR/0/A/2000/004 Notifications to States and Counties from the Emergency Operations Facility for Catawba, McGuire and Oconee (Rev. 006)

SR/0/B/2000/004 Deleted AP/O/A/5500/046 Hostile Aircraft Activity (Rev. 008)

AD-EP-ALL-0202 Emergency Response Offsite Dose Assessment (Rev. 001)

AD-EP-ALL-0203 Protocol for the Field Monitoring Coordinator During Emergency Conditions (Rev 000 AD-EP-ALL-0204 Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release (Rev 000)

AD-EP-ALL-03 01 Activation of the Emergency Response Organization Notification System (ERONS) (Rev. 000)

February 18, 2016

Page 5 or"5 DUKE ENERGY COMPANY CATAWBA NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX VOLUME II PROCEDURE TITLE AD-EP-ALL-0406 Duke Energy Management Network (DEMNET) (Rev 001)

February 18, 2016

Form 703-1. Procedure Process Record (PPR)

(RIO0-14)

Duke Energy (I) ID No. RPI0/AI5000I001 PROCEDURE PROCESS RECORD Revision No. 036 PREPARATION (2) Station Catawba Nuclear Station (3) Procedure Title Classification of Emergency Classiicatio ofEerec (4) Prepared By* *;. /*tf!,i.-f:*. (j.

4,/i4/la, Date (5) Requires NSD 228 Applicability Determination?

[] Yes (New procedure or revision with major changes) - Attach NSD 228 documentation E] No (Revision with minor changes)

(6) Reviewed By*

ICU*0- -* *"* *.- ( (Kl)

Date*

Cross-Disciplinary Review *y* (QR) (KI) NA

Reactivity Mgmt. Review By* .(QR) NA .1I* Ii Mgmt. Involvement Review By* .fOps. Mgr.) NA * . I (7) Additional Reviews Reviewed By*g )ate Reviewed By* 11kate PERFORMANCE (Compare with control copy every 14 calendar days while work is being performed.)

(9) Compared wVith Control Copy* _______________________________________late_______

Compared with Control Copy* lDate______

Compared with Control Copy* ___________________________a__________DIte______

(10) Date(s) Performed Work Order Number (WO#) _____________________________________________

COMPLETION (It ) Procedure Completion Verification:

0] Yes [] NA Checklists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?

0] Yes 0] NA Required enclosures attached?

[] Yes 0] NA Charts, graphs, data sheets, etc. attached, dated, identified, and marked?

0] Yes 0] NA Calibrated Test Equipment, if used, checked out/in and referenced to this procedure?

0] Yes 0] NA Procedure requirements met?

Verified By* _____________ l)ate _______

(12) Procedure Completion Approved'* lDate (13) Remarks (Attach additionalpages, if necessary,)

PrintedNamte aitd Signature I

~ENERGY!,

Facility Code : CN Applicable Facilities :

Document Number: RP/0/A/5000/001 Document Revision Number : 036 Document EC Number :

Change Reason :

Document Title : Classification of Emergency Hare, Mandy B. EP manager designee review 2/1 7/20 16 Notes :

10 CFR 50.54(q) Screening Evaluation Form Screening and Evaluation Number* Applicable Sites BNP El EREG #:2001696 CNS [

PPR AR# 2001696 CR3 El HNP El MNS El 5AD #:02001728 ONS El RNP El GO El Document and Revision RP/0/A/5000/001 Revision 036 [ Classification of Emergency Part I. Description of Activity Being Reviewed (event or action, or series of actions that may restult in a change to the emergency plan or affect the imnplementation of the emergency plan):

Activity

Description:

RP/O/A15000/O F(Classification of Emergency) Rev.036

1) Enclosure 4.1 - page 1 of 5 - Corrected Fusion PDF error during rendition. No content wats chatnged.

There was an error during the rendition to a PDF that caused a portion of the page to be cut off.

References:

PRR02001.696 Part II. Activity Previously Reviewed? Yes El No El]

Is this activity Fully bounded by an NRC approved 10 CFR 50.90 submittal or 10 CFR 50.54(q) Continue to Alert and Notification System Design Report? Effectiveness Attachment 4 Evaluation is not ,10 CFR If yes, identify bounding source document number or approval reference and required. Enter 50.54(q) ensure the basis for concluding the source document fully bounds the proposed justification Screening change is documented below: below and Evaluation complete Form, Part Ill Justification: Attachment 4, Part V.

Bounding document attached (optional)

Part Ill. Editorial Change Yes IIX No El Is this activity an editorial or typographical change only, such as formatting, 10 CFR 50.54(q) Continue to paragraph numbering, spelling, or punctuation that does not change intent? Effectiveness Attachment 4, Evaluation is not Part IV and Justification: required. Enter address non justification and editorial Corrected Fusion PDF error during rendition. No content was changed. There was an complete changes error during the rendition to a PDF that caused a portion of the page to be cut off. The Attachment 4, procedure is required to be revised to correct these issues. Part V & VI.

Part IV. Emergency Planning Element and Function Screen (Reference Attachment 1, Considerations for Addressing Screening Criteria)

Does this activity involve any of the following, including program elements from NUREG-0654/FEMA REP-i Section I1? If answer is yes, then check box.

1 10 CFR 50.47(b)(1) Assignment of Responsibility (Organization Control) la Responsibility for emergency response is assigned. El 1b The response organization has the staff to respond and to augment staff on a continuing basis [

(24-7 staffing) in accordance with the emergency plan.V 2 10 CFR 50.47(b) (2) Onsite Emergency Organization___

2a Process ensures that on-shift emergency response responsibilities are staffed and assigned El 2b The process for timely augmentation of on-shift staff is established and maintained. J[]

3 10 CFR 50.47(b) (3) Emergency Response Support and Resources __

3a Arrangements for requesting and using off site assistance have been made. El 3b State and local staff can be accommodated at the EOF in accordance with the emergency plan. El

__(NA for CR3) 4 10 CFR 50.47(b) (4) Emergency Classification System 4a A standard scheme of emergency classification and action levels is in use. El (Requires final approval of Screen and Evaluation by EP CFAM.)

5 10 CFR 50.47(b) (5) Notification Methods and Procedures 5a Procedures for notification of State and local governmental agencies are capable of initiating notification El of the declared emergency within 15 minutes (30 minutes for CR3) after declaration of an emergency and providing follow-up notification.

Sb Administrative and physical means have been established for alerting and providing prompt instructions El to the public within the plume exposure pathway. (NA for CR3)___

Sc The public ANS meets the design requirements of FEMA-REP-1 0, Guide for Evaluation of Alert and El Notification Systems for Nuclear Power Plants, or complies with the licensee's FEMA-approved ANS design report and supporting FEMA approval letter. (NA for CR3)___

Part IV. Emergency Planning Element and Function Screen (cont.)

6 10 CFR 50.47(b)(6) Emergency Communications 6a Systems are established for prompt communication among principal emergency response El organizations.

6b Systems are established for prompt communication to emergency response personnel. El 7 10 CFR 50.47(b)(7) Public Education and Information

7a Emergency preparedness information is made available to the public on a periodic basis within the []

plume exposure pathway emergency planning zone (EPZ). (NA for CR3) 7b Coordinated dissemination of public information during emergencies is established. [

8 10 CFR 50.47(b)(8) Emergency Facilities and Equipment___

8a Adequate facilities are maintained to support emergency response. [

8b Adequate equipment is maintained to support emergency response. ____

9 10 CFR 50.47(b)(9) Accident Assessment 9a Methods, systems, and equipment for assessment of radioactive releases are in use. J]

10 10 CFR 50.47(b)(10) Protective Response 10a A range of public PARs is available for implementation during emergencies. (NA for CR3) []

10Ob Evacuation time estimates for the population located in the plume exposure pathway EPZ are available EJ to support the formulation of PARs and have been provided to State and local governmental authorities. (NA for CR3) 10Oc A range of protective actions is available for plant emergency workers during emergencies, including EJ those for hostile action events.

10Od KI is available for implementation as a protective action recommendation in those jurisdictions that 0]

chose to provide KI to the public.

11 10 CFR 50.47(b)(1 1) Radiological Exposure Control 11la The resources for controlling radiological exposures for emergency workers are established. 0

[

12 10 CFR 50.47(b)(12) Medical and Public Health Support 12a Arrangements are made for medical services for contaminated, injured individuals. []

13 10 CFR 50.47(b)(13) Recovery Planning and Post-accident Operations 13a Plans for recovery and reentry are developed: []

14 10 CFR 50.47(b)(14) Drills and Exercises 14a A drill and exercise program (including radiological, medical, health physics and other program areas) 0]

is established.

14b Drills, exercises, and training evolutions that provide performance opportunities to develop, maintain, []

and demonstrate key skills are assessed via a formal critique process in order to identify weaknesses.

14c Identified weaknesses are corrected. []

15 10 CFR 50.47(b)(15) Emergency Response Training iaTraining is provided to emergency responders. 0 Part IV. Emergency Planning Element and Function Screen (cont.)

16 10 CFR 50.47(b)(16) Emergency Plan Maintenance 16a Responsibility for emergency plan development and review is established. 0]

16b Planners responsible for emergency plan development and maintenance are properly trained. 0]

PART IV. Conclusion If no Part IV criteria are checked, a 10 CFR 50.54(q) Effectiveness Evaluation is not required, then complete , 10 CFR 50.54(q) Screening Evaluation Form, Part V. Go to Attachment 4, 10 CFR 50.54(q)

Screening Evaluation Form, Part VI for instructions describing the NRC required 30 day submittal.

The changes included in this revision include editorial changes only. This revision corrected Fusion PDF error during rendition. No content was changed. There was an error during the rendition to a PDF that caused a portion of the page to*

be cut off. No planning standards were impacted because there were no content changes to the procedure.

If any Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV criteria are checked, then complete , 10 CFR 50.54(q) Screening Evaluation Form, Part V and perform a 10 CFR 50.54(q)

Effectiveness Evaluation. Shaded block requires final approval of Screen and Evaluation by EP OFAM.

Part V. Signatures;

Preparer Name (Print): Tina Kuhr Preparer Signature: Date:2/1 6/16 Reviewer Name (Print): Mandy Hare Re jwer Signatur Date:2/17/16 Approver (EP Manager Name (Print): Tom Ariow App.prove&., nat1_*

,):/,* *'*7ze/,*tat:/7 Approver (CFAuM, as required) Name (Print) Approver Signature: z -7.) ae Part VI. NRC Emergency Plan and Implementing Procedure Submittal Actions Create two EREG General Assignments.

One for EP to provide the 10 CFR 50.54(q) summary of the analysis, or the completed 10 CFR 50.54(q),

to Licensing.

One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect.___

QA RECORD

UF Duke Energy Company Procedure No.

CATAWBA NUCLEAR STATION RP/O/.-1sooo/oo1 Classification of Emergency Revision No.

036 Rcference Use PERFORaMANCE This Procedure was printed on 2/17/2016 3:25 PM from the electronic library as:

(ISSUED) - PDF Format Compare with Control Copy every 14 calendar days while work is being performed.

Compared with Control Copy

_________________________Date _______

Compared with Control Copy *__________________________Date _______

Compared with Control Copy

Date________

Irinted NVane and Signature Date(s) Pertbrmed Work Order/Task Number (WOn)

COMPLETION O [ Yes [] NA Checklists and/or blanks initialed, signed, dated, or filled in NA-. as approprkite'?

E] Yes [] NA Required attachments included?

[] Yes 0] NA Charts, graphs, data sheets. etc. attached, dated, identified, and marked?

[] Yes [] NA Calibrated Test Equipment, if used, checked outhin and referenced to this procedure'?

[] Yes [] NA Procedure requirements met?

Verified Dy Date

Printed N~ame and SVignamtre Procedure Completion Approved Date

Printed Name and Signature Remarks (attach additionalpages, i/necessary)

IMPORTANT: Do NOT mark on barcodes. I'rmted Date. '2/"17.1o" Pirocedure No. 'RF'/OU./5i/S IIIO/l I'

RP/0/A/5000/00 I Page 2 o f 4 Classification of Emergency

1. Symptoms 1.1. Notification of Unusual Event I.1 .1 Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated.

1.1.2 No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety occurs 1.2 Alert 1.2.1I Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE ACTION.

1.2.2 Any releases are expected to be limited to small fractions of the EPA Protective Act ion Guideline exposure levels.

1.3 Site Area Emergency 1.3.1 Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (I) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevent effective access to equipment needed for protection of the public.

1.3.2 Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the site boundary.

1.4 General Emergency I1.4. 1 Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility.

1.4.2 Releases can be reasonably expectedto exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.

RP/0/A/5000/001 Page 3 of'4

2. Immediate Actions 2.1 IF performing this procedure due to security-related event(s) considered to be a CREDIBLE THREAT or HOSTILE ACTION, perform the Ibllowing.

F Security reports that a SECURITY CONDITION or HOSTILE ACTION is imminent (15 minutes) or in-progress, notify station personnel via the plant page to take the appropriate protective actions. Refer to RP/0/B/5000/t026. Site Response to Security Events, as soon as possible for scripted message.

Perform accelerated notification to the NRC within 15 minutes of the occurrence or" the event.

2.2 Assessment, classification and declaration of any applicable emergency condition shouild be completed within 15 minutes after the availability of indications or inf'ormation to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded. (Refer to Enclosure 4.9, Emergency Declaration Guidelines, as needed) 2.3 Determine operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response of the event.

2.4 IF the plant was in Mode 1-4 and a valid condition affects fission product barriers, proceed to Enclosure 4.1 (Fission Product Barrier Matrix) OR refer to EAL wvallboards.

__2.5 IF a General Emergency is NOT declared in Step 2.4 OR. the condition does NOT affect fission product barriers, review the listing of enclosures OR refer to EA\L wallboards to determine if the event is applicable to one the categories shown.

2.6 Compare actual plant conditions to the Emergency Action Levels evaluated in step 2.4 and/or 2.5 and declare the appropriate Emergency Class as indicated.

2.7 Document the declaration time. __________

2.8 Activate the ERO per the appropriate Response Procedure (RP) utilizing the Control Room ERO Notification Job Aid.

2.9 IF the declaration is made in the Control Room, announce the classification and declaration time to the Control Room Crew at the first opportuinity that will not intert'ere with the performance of the crew or the flow of the Emergency Procedure.

2. 10 IF the declaration is made in the TSC or EOF, announce the classification and declaration time to the applicable facility personnel.

RP/O/A/5000/00 I Page 4 o t"4 2.1!1 Implement the applicable Emergency Response Procedure (RP) f~or that classification and continue with subsequent steps of this procedure.

Notification of Unusual Event RP/0/A/5000/002 Alert RP/0/A/5000/003 Site Area Emergency RP/0/A/5000/004 General Emergency RP/0/A/5000/005

3. Subsequent Actions 3.1 To escalate, de-escalate, or terminate the Emergency, compare plant conditions to the initiating Conditions of Enclosures 4.1I through 4.7 OR EAL wallboards.

___3.2 Refer to Enclosure 4.8 (Definitions/Acronyms) OR 4.9 (Emergency Declaration Guidelines), as needed.

3.3 Ref'er to Section D of the Catawba Emergency Plan for basis inf'ormation about the Emergency Classification System as needed.

3.4 Ref'er to RP/0/A/5000/020, "TSC Activation Procedure"1 concern ingz the use of" 10CFR50.54(x). If the TSC is activated, contact the TSC Emergency Coordinator (EC) for concurrence when using IOCFR5O.54(x).

4. Enclosures

4. 1 Fission Product Barrier Matrix 4.2 System Malfunctions 4.3 Abnormal Rad Levels/Radio logical Effluent 4.4 Loss of Shutdown Functions 4.5 Loss of Power 4.6 Fires/Explosions and Security Events 4.7 Natural Disasters, Hazards and Other Conditions Affecting Plant Safety 4.8 Definitions/Acronyms 4.9 Emergency Declaration Guidelines 4.10 Radiation Monitor Reading for Enclosure 4.3 EALs

0 0 Enclosure 4.1 RPIOIA!5000/001I Fission lProduct Barrier Matrix Page 1 of'5 1.Use EALs to determine Fission Product Barrier status (Intact, Potential Loss, or Loss). Add points for all barriers. Classify according to the table below.

Note 1: An event (or multiple events) could occur which results in the conclusion that exceeding thle Loss or Potential Loss thresholds is IMMINENT (i.e., within 1-3 hours). In this IMMINENT LOSS situation, use judgment and classify' as if the thresholds are exceeded.

Note 2: When determining Fission Product Barrier status, the Fuel Clad Barrier should be considered to be lost or potentially lost if the conditions for the Fuel Clad Barrier loss or potential loss EALs were met previously validated and sustained, even if the conditions do not currently exist.

Note 3: Critical Safety Function (CSF) indications are not meant to include transient alarm conditions which may appear during the stait-up of engineered safeguards equipment. A CSF condition is satisfied when the alamred state is valid and sustained. The STA should be consulted to affirm that a CSF has been validated prior to the CSF being used as a basis to classify an emergency.

Example: If ECA-0.0, Loss of All AC Power Procedure, is implemented with an appropriate CSF alarm condition valid and sustained, the CSF should be used as the basis to classify an emergency prior to any function restoration procedure being implemented within the confines of ECA-O.O.

IC Unusual Event IC Alert IC Site Area Emergency IC General Emergency LossORossLoss Ptenial OR Potential Loss Potential Loss of of 41 1of Both Loss of 4.1nU.aI4.1ent.

otimn Nuclear Coolant System Nuclear Coolant System AND___All 4. G Three Barriers Fuel Clad Loss AND Loss OR P~otential Loss Potential Loss CombinationsLosf

4. U2 Loss ofl . A2o . S2o oh41.. Any Two Barriers AN D 4IU Containment 4... f4lS2o oh4102 Potential Loss of the Fuel Clad Nuclear Coolant System ANDThr Fuel CladThr Potentia Losssofof Containment ANI)

4. Conaimet.3t 4.1.S.3 Loss Ok Potential Loss of I .A.~ Loss OR Potential LossAnOtrBrie Aof OteyBare Any Other Barrier

0l Enclosure 4.1 RPlOI AI50 00/001 Fission Product Barrier Matrix Page 2 of 5 NOTE: lf a barrier is affected, it has a single point value based onl a "potential loss" or a "loss." "Not Applicable" is included in thle table as a place holder only, and has no point value assigned.

Barrier Points (1-5) Potential Loss (X) Loss (X) Total Points Classification Containmenat 1 3 1- 3 Unusual Event NCS 4 5 4 -6 Alert Fuel Clad 4 5 7 -10 Site Area Emergency Total Points <,>*,':,;:*::11 -13 General Emergency

1. Compare plant conditions against the Fission Barrier Matrix on pages 3 through 5 of"5.

2. Determine the "'potential loss" or "loss" status for each barrier (Containment, NCS and Fuel Clad) based on the EAL symptom description.

3. For each barrier, write the highest single point value applicable for the barrier in the "Points" column and mark the appropriate "loss" column.

4. Add the points in the "'Points" column and record the sum as "Total Points".

5. Determine the classification level based on thle number of "Total Points".

6. In thle table on page 1 of 5, under one of the four "'classification" columns, select the event number (e.g. 4.1I.A. I for Loss of Nuclear Coolant S,,ystem) that best fits thle loss of barrier descriptions.

7. Using the nillmlbcr (e.g. 4.1IA. I), select the prelprinted notification forml- O1_.R a blank notification forml and complete the required in formaat ion lfr Emer'gency Coordinator approval and transmittal.

Enclosure 4.1 RP/0/A/5000/001I Fission Product Barrier Matrix Page 3 of 5 4.1.C CONTAINMENTl BARRIER 4.I.N NCS BAR .RIER 4.I.1 FUEL CLA[ SBARRIER POTENTIAL LOSS - LOSS - POTENTIAL LOSS - LOSS - POTENTIAL LOSS - LOSS -

(I1 Point) (3 Points) (4 Points) (5 Points) (4 Points) (5 Points)

...... ...

Ill!ill ....

II1$ - M-Em im

1. Critical Safcty Function Status 1. Critical Safety Function Status 1. Critical Safety Function Status

Containment-RED

Not applicable

NCS Integrity-Red

Not applicable

Core Cooling-

Core Cooling-Red Orange

Core cooling-RED

Heat Sink-Red Path is indicated

Heat Sink-Red for > 15 minutes

2. Containment Conditions 2. NCS Leak Rate 2. Primary'Coolant Activity Level

[ I

Containment

Rapid unexplained

UnisoLable leak

GREATER THAN

Not applicable

Coolant Activity Pressure > 15 PSIG decrease in exceeding the available makeup

GREATER THAN containment capacity of one capacity as 300 p~i/cc Dose

H2 concentration > pressure following charging pump in indicated by a loss Equivalent Iodine 9% initial increase th*e normal of NCS subcooling. (DEl) 1-131 charging mode

Containment

Containment with letdown pressure greater than pressure or sump isolated.

3 psig with less than level response not trne full train of N S consistent with and a VX-CARF LOCA conditions.

operating atecr ac!uation.

NOT'E: Refer to Emergency Plan.

Sect. D. 4, .C1 last paragraph for inability to ma~intain nollnmal anUlulltS pfressture.

CONTINtJEI) ()TNJI I)ED

(-'ONTIN N NtEI

('ONTINIIED

Enclosure 4.1 RPIOIAIS001001 Fission Product Barrier Matrix Page 4 of 5 4.!.C CONTAINMENT BARRIER 4.I.N NCS BARRIER 4. I.F FUEL CLAI) BARRIER POTENTIAL LOSS - LOSS - POTENTIAL LOSS - LOSS -

POTENTIAL LOSS - LOSS -

(I Point) (3 Points) (4 Points) (5 Points) (4 Points) (5 Points) lil r.... .. .. . I I II

3. Containment lsolation Valves Status After 3. SC Tube Rupt ire ItI BIB tlhtl tIitiIUl J RTU lllfl B B*

lURB SC.fI*lflfl*

Containment Isolationi Actuation

.Not applicable . Containment Pri mary-to-

Indication that a Not applicable

Containment isolation is Secondary leak SG is Ruptured and radiation monitor incomplete and a rate exceeds the has a Non-Isolable 53 A or 53 B direct release path capacity of one secondary line fault Reading at time lioin containment charging pump in since Shutdown.

exists to the the normal

Indication that a environment charging mode SG is ruptured and 0-0.5 hrs > 99 R/hr with letdown a prolonged release 0.5-2 hrs > 43 R/hr isolated. of contaminated 2-4 hrs > 31 R/hr secondary coolant 4-8 hrs > 22 R/hr is occurring from >8 hrs > 13 R/hr the affected SG to the environmnent

4. Emereencv Coordinator/EOF Director

4. SC Secondary Side Release With Primary-to- 4. Containment Radiationi Nlonjiorinl!

Secondary Leakagle Judg~enent

Not applicable . Release of

Any condition, including inability to monitor

Not applicable Not applicable secondary side to the barrier that in the opinion of the thle environmlent Emergency Coord inator/EOF Director with primary to indicates LOSS or POTENTIAL LOSS of the secondary leakage fuel clad harrier.

GREATE-R TH-AN Tech Spec

illowabh" EN I

('()NTINI:EI) CONININU .D

Enclosure 4.1 RP/O/A/5000/001I Fission Product Barrier Matrix Page 5 of 5 4.1.C CONTAINMENT BARRIER 4.I.N NCS BARRIER 4.I.F FUEL CLA[ )BARRIER POTENTIAL LOSS - LOSS - POTENTIAL LOSS - LOSS - POTENTIAL LOSS -

LOSS -

(I Point) (3 Points) (4 Points) (5 Points) (4 Points) (5 Points)

. .... . ... . . . . .I ' - 'III I

5. Significant Radioactive Inventory, In 5. Emergency Coordinator/EOF Director Containment Judgement Containment Rad.

Not applicable

Any condition, including inability to monitor Monitor EMF53A or the batTier that in the opinion of the 53B Emergency Coordinator /EOF Director Reading at time since indicates LOSS or POTENTIAL LOSS of shutdown: the NCS barrier.

o - 0.5 hr > 390 R/hr 0.5 - 2 hr > 170 R/hr 2-4 hr > 125 k/hr 4 -8 hr > 90Rk/hr

>8 hr > 53kUhr END

6. Emergency Coordinator /EOF Director Judgment Any condition, including inability to monitor the barrier that in the opinion of the Emergency Coordinator/EDF Director indicates LOSS or POTENTIAL LOSS of the containment barrier.

END

Enclosure 4.2 RPIOIAI5000/001I System Malfunctions Page 1 of 2 UNU3SUAL EVENT ALERT SITE AREA EMERGENCY GENERAL. EMERGENCY 4.2.U.1 Inability to Reach Required 4.2.A.1 Unplanned Loss of Most or All 4.2.S.1 Inability to Monitor a END Shutdown Within Technical Safety System Annunciation or Significant Transient in Specification Limits. Indication in Control Room Progress.

With Either (1) a Significant OPERATING MODE: 1, 2,3, 4 Transient in Progress, or (2)

Compensatory Non-Alarming OPERATING MODE: 1, 2, 3, 4 4.2.U.!-l Plant is not brought to required Indicators Unavailable.

operating mode within Technical 4.2.S.1-I The following conditions Specifications LCO Action Statement OPERATING MODE: 1, 2, 3, 4 exist:

Time.

4.2.A. 1-1 The following conditions exist: Loss of most (>50%)

4.2.U.2 Unplanned Loss of Most or All Safety Annunciators associated with System Annunciation or Indication in. Unplanned loss of most (>50%) safety systems.

the Control Room for Greater Thain annunciators associated with safety 15 Minutes. systems for greater than 15 minutes. AND OPERATING MODE: 1, 2, 3, 4 AND A SIGNIFICANT PLANT TRANSIENT is in 4.2.Ui.2-I The following conditions exist: In the opinion of the Operations progress.

Shift Manager/Emergency Unplanned loss of most (>50%/) Coordinator/EOF Director, the AND annunciators associated with safety loss of the annunciators or systems for greater than 15 minutes. indicators requires additional Loss of the GAG.

personnel (beyond normal shift AND compliment) to safely operate the AND unit.

AN I Inability to provide manual In the opinion of the Operations Shif~t monitoring of any of' the Manager/Emergency Coordinator/EOF EITHiER of the following: following Critical Safety Director, the loss of the annunciators

A SIGNIFICANT PLANT or indicators requires additional TRANSIENT is in progress persoimcl (beyond normal shif~t

subcriticality COlnpl~iment) to sale~ly operate the unit,

Loss of the GAG.

core cooling

heat sink ENDI

containment.

('ON'IINI) ENEI)

I- N !)

Enclosure 4.2 RP/0/A/5000/001 System Malfunictions Page 2 of 2 U.NUSUAL EVENT ALERT SITE AREA EMERGENCY GENEiRAL EMERGENCY 4.2.11.3 Fuel Clad Degradatdion.

OPERATING MODE: 1, 2, 3, 4, 5 4.2.1_1.3-I Dose Equivalent 1-131 greater than the Technical Specifications allowable limit.

4.2.U1.4 Reactor C~oolant System (N CS)

Leakage.

OPERATING MODE: 1,2,3,4 4.2.U1.4-1 Unidentified leakage > 10 gpm.

4.2.U1.4-2 Pressure boundary leakage > 10 gpmn.

4.2.U.4-3 Identified leakage>Z 25 gpm 4.2.UJ.5 Unplannecd Loss of All Onsite or Offsite Commiuniicationts.

OPERATING MIODE: ALL 4.2.1_1.5-I Loss of all onsite communications capability (internal phone system. PA system. onsite radio system) affecting the ability to perlbrm routine operations.

4.2.1I.5-2 Loss of all offsite communications capabi Iity (Duke Emergency Mianagemenit Network {DI-rv.NI 'li.

NR(" ETS lines. of'fsite radio system, commercial phone system) affecting!

the ability to communicate wvith ol'lsite authl ori ties.

ENI)

0 Enclosure 4.3 RP/0/A/5000/001I Abnormal Rad Levels/Radiological Effluent Page 1 o1'5 IJNIJSI IAl, E:VENTI ALERT' SlITE AREA EM EIRGENC\: GENERtAI. EMER(GENCTY 4.3.ti.1 Any lUnplanned Release of(Gaseous or -t.3.A.1 Any Unplanned Release of 4.3.S.1 Boundary Dose Resulting 4.3.G.1 Boundary l)ose Resulting Liquid Radioactivity to the Gaseous or Liquid fronm an Actual or from an Actual or Environment that Exceeds Two Times Radioactivity to the Imminent Release of Inmminent Release of the SLC Limits fo~r 60 Minutes or Environnment that Exceeds Radioactivity Exceeds 100l Radioactivity that Exceeds Longer. 200 Times the SLC limits mirem TED)E or 500 anrem 1000 wrenm ITEDE or 5000 for 15 Mlinutes or Longer. CDE Adult Thyroid for mrema CDE Adult Thyroid OPERA ITIN(; MODE: ALL the Aetual or Projected fo~r the Actual or OPERATING MODE. ALL Duration of the Release. Projected Duration of the 4t.3.UAt-t A vatid '[rip 2 alarm on radiation monitor Release.

EMIF-49L or EMF-57 for > 60 minutes or OPERATING NMODE: ALL 4.3.A.l-1 A valid indication on radiation oil! likely continue obr> 601minutes monitor EMF- 49L or EMF-57 of OPERATING MIODE: ALL which indicates that the release may have _Ž1.2E+05 cpm lbr > 15 mfinutes 4.3.S.1-1 A valid indication on exceeded the initiating condition and or will likely continue for >Ž15 radiation monitor EMF- 4.3.G.t-1 A valid indication on indicates the need to assess the release mtnutes, which indicates that the 36L of">_ 2.7E+06 cpm radiation monitor EMF-36H]

with procedure H-P/0/B3/1009/0 14. releatse may have exceeded the sustained for > 15 of">_ 8.3 E+03 cpm initiating condition and indicates minutes. sustained tbr > I5 tminutes.

4.3.1U.1-2 A valid indication on radiation monitor the need to assess the release with EMF- 36L of_> 3.00E+04 cpm lbr > 60 procedure ItP/0/B/ 1009/014. 4.3.S.1-2 Dose assessment temn~ 4.3.G.1-2 Dose assessment team minutes or will likely' continue tbr _>60 calculations indicate dose calculations indicate dose minutes. which indicates that the release consequences greater than consequences greater than may have exceeded the initiating 100 mrem T1EDE or 500 1000 mrem TEDE or 5000 condition and indicates the need to assess (Continued) turen CDE Adult Thyroid mrem CDE Adult Thyroid the release with procedure AD)-EI'-ALL- at the site boundary. at the site boundary.

0202.

{(Continued) I Continued) t( 'ontinued)

Enclosure 4.3 RP/O/A/5000/001 Abnormal Rad Levels/Radiologicai Effluent Page 2 ot'5 UNulSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.U.1-3 Gaseous effluent being released 4.3.A.i-2 A valid indication on radiation 4.3.S.1-3 Analysis of field survey 4.3.G.1-3 Analysis of field survey exceeds two times SLC 16.11-6 lbr > monitor EMF- 36L of>_ results or field survey results or field survey 60 minutes as determined by RP 5.4E+05 cpm for > 15 minutes samples indicates dose samples indicates dose procedure. or will likely continue for Ž>15 consequences greater consequences greater minutes, which indicates that than 100 mrem TEDE or than 1000 inrem TEDE 4.3.U.I-4 Liquid effluent being released the release may have exceeded 500 mrem CDE Adult or 5000 mrem CDE exceeds two times SLC 16.11-I for> the initiating condition and Thyroid at the site Adult Thyroid at the site 60 minutes as determined by RP indicates the need to assess the bounmdarmy. boundary.

procedure. release with procedure AD-EP-ALL-0202. Note 1: These EMAF readings are Note I: These EMF readings are Note: If the monitor reading is sustained calculated based on average calculated based on average for the time period indicated in the 4.3.A.1-3 Gaseous effluent being annual meteorology, site annual meteorology, site EAL AND the required assessments released exceeds 200 times the boundary dose rate, and boundary dose rate, and (procedure calculations) cannot be level of SLC 16.11-6 for> 15 design unit vent flow rate. design unit vent flow rate.

completed within this time period, minutes as detennined by RP Calculations by the dose Calculations by the dose declaration must be made based on procedure. assessment team use actual assessment team use actual the valid radiation monitor reading. meteorology, release meteorology, release 4.3.A.1-4 Liquid effluent being released duration, and unit vent flow duration, and unit vent flow (Continuemd) exceeds 200 times the level of rate. Therefore, these EMF rate. Therefore, these EMF SLC 16.11-1 for> I5 minutes readings should not be used if readings should not be used as determined by RP~ dose assessment team if dose assessment team procedure. calculations are available. calculations are available.

Note: If the monitor reading is Note 2: If dose assessment team Note 2: If dose assessment team sustained for the time period calculations cannot be calculations cannot be indicated in the EAL AND the completed in I5 minu~tes. completed in 15 minutes, required assessments then walid monitor reading~ then valid monitor (procedure calculations) should be used lbr emergency reading should be used for cannot be comnpleted within classification. emergency classification.

this time period, declaration mstls be made based on the ENDI E NI valid rad iat ion monitor reading.

("ontinued)

0 Enclosure 4.3 RP/0/A/5000/001I Page 3 of 5.

Abnormal Rad Levels/Radiological Effluent UNUSIJAL EVENT ALERT SITE AREA EM'ERGENCV: GENERAL EMERGENCY 4.3.U.2 Unexpected increase iin Plant 4.3.A.2 Miajor Damage to Irradiated Radiation or Airborne Fuel or Loss of Water Level Concentration. that tlas or Will Result in the Uncovering of Irradiated OPERATING MODE: ALL Fuel Outside the Reactor V'essel.

4.3.UJ.2-1I Indication of uncontrolled water SDoes not apply to spent fuel in dry cask level decrease of greater than 6_ storage. Refer to EPLAN Section D inches in the reactor refueling cavity basis document with all irradiated fuel assemblies remaining covered by water. OPERATING MIODE: ALL 4.3.A.2-1 An unplanned valid trip II 4.3.11.2-2 Uncontrolled water level decrease of alarm on any of the greater than 6 inches in the spent fuel following radiation pooi and fuel transfer canal with all monitors:

irradiated fuel assemblies remaining covered by water. Spent Fuel Building Refueling Bridge 4.3.11.2-3 Unplanned valid area EMF reading 1IEMF- 15 increases by a factor of 1,000 over 2EMF-4 normal levels as shown in Enclosure 4.10. Spent Fuel Pool Ventilation 1EM F-42 EN I) 2EMF-42 Reactor Building Refueling Bridge (applies to Mode 6 and No Mode Only) l EMF-17 2EMF-2 Containment Noble Gas Monitor (Applies to Mode 6 and No* Mode Only)

I EM F-39 21N'lF-39 C(oniliiniud)

Enclosure 4.3 RPIOIAI5 000/001 Abnormal Rad Levels/Radiological Eftluent Page 4 of 5 UNUSUAL EVENTI ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.2-2 Plant personnel report that water level drop in reactor refueling cavity, spent fuel pool, or fuel transfer canal has or will exceed makeup capacity such that any irradiated fiuel will become uncovered.

4.3.A.2-3 NC system wide range level <95% after initiation ofhNC system make-up.

AN.__D_

Anly irradiated fuel assembly not capable of being lowered into spent fuel pool or reactor vessel.

4.3.A.2-4 Spent Fuel Pool or Fuel Transfer Canal level decrease of>2 feet after initiation of makeup.

ANDI Any irradiated fuel assembly not capable of being fully lowered inb the spent fuel pool racks or transfer canal fuel transfer system basket.

(Colnlinlued)

Enclosure 4.3 RP/0/A/5000/00 Abnormial Rad Levels/Radiological Effluent Page 5 of 5 IUNtJSUAI EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.A.3 Release of Radioactive M~aterial or Increases inl Radiation Levels Within the Facility That Inmpedes Operation of Systems Required to Mlaintain Safe Operations or to Establish or Maintain Cold Shutdown.

OPERATING MODE: ALL 4.3.A.3-1 V'alid reading on IEMF-12 greater than 15 mremihr in the Control Room.

4.3.A.3-2 Valid indication of radiation levels greater than 15 nmremihr in the Central Alarm Station

(_CAS) or Secondary Alarm Station (SAS).

4.3.A.3-3 \"alid radiation monitor reading exceeds the levels shown in Enclosure 4.1l0.

ENDI

Enclosure 4.4 RP/0/A/5000/001I Loss of Shutdown Functions Page 1 of 3 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAl. EMERGENCY ENDp~ 4.4.A. 1 Failure of Reactor 4.4.S.1 Failure of Reactor 4.4.G.1 Failure of the Reactor Protection System P~rotection System Protection System to liastrunientation to Instrunientation to Complete an Autonmatic Trip Comiplete or Iuitiate anl Complete or Initiate an and Manual Trip Was NOT Automatic Reactor Trip Automatic Reactor Trip Successful and There is Once a Reactor Protection Once a Reactor Protection Indication of an Extreme System Setpoint ilas Been System Setpoiut 1-as Beeni Challenge to the Ability to Exceeded and Manual Trip Exceeded and Manual Trip Cool the Core.

Was Successful. Was NOT Successful.

OPERATING MODE: I OPERATING MODE: 1, 2,3 OPERATING MODE: I 4.4.G.l-l The following conditions exist:

4.4.A.1-1 The following conditions exist: 4.4.S.1-1 The following conditions exist:

Valid reactor trip signal received or required and Valid reactor trip signal Valid reactor trip signal received or required and received or required and automatic reactor trip automatic reactor trip automatic reactor trip was not successful.

wa~s not successful. was not successful.

AND AND AND Manual reactor trip from the Manual reactor trip from the Manual reactor trip from the control room was not control room is successful and control room was miot successful in reducing reactor reactor power is less than 5% successful in reducing reactor

power to less than 5% and and decreasing. power to less than 5% and decreasing.

decreasing.

(Continued) AND)

(Continued) E ITIEI lof the followingt conditions exist:

Core Cooling CSF-RED

Heat Sink CSF-RED.

ENDI

Enclosu re 4.4 RP/0/A/5000/001I Loss of Shutdown Functions P~age 2 of 3

[UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.4.S.2 Complete Loss of Function 4.4.A.2 Inability to Miaintain Plant Needed to Achieve or in Cold Shutdown.

Mlaintain Hot Shutdown.

OPERATING MODE: 5, 6 OPERATING MODE: 1,2, 3, 4 4.4.A.2-I Total loss of ND and/or RN 4.4.S.2-I Subcriticality CSF-RED.

and/or KC.

4.4.S.2-2 Heat Sink CSF-RED.

AND 4.4.S.3 Loss of Water Level inl the One of the following: Reactor Vessel That I-las or Will__Uncover Fuel inl the

Inability to maintain Reactor Vessel.

reactor coolant temnperature OPERATING MODE: 5, 6 below 200 0 F 4.4.S.3-I Failure of heat sink causes loss

Uncontrolled reactor of cold shutdown conditions.

coolant temperature rise to

> 1800 F. ANI)

Lower range Reactor Vessel Level Indication System END (RVLIS) decreasing after initiation of NC system mnakeup.

4.4.S.3-2 Failu~e of heat sink causes loss of cold shutdown conditions:

AND Reactor Coolant (NC) system mid or wide range level less than 11% and decr-easing after initiation of NC system makeup.

{Conitinued)

0 0 Enclosure 4.4 RP/0/A/5000/001I Loss of Shutdown Functions Page 3 of 3 IJNISIAIi. EVENT' ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.4.S,3-3 Failure of heat sink causes loss of cold shutdown conditions.

AND Either train ultrasonic level indication less than 7.25% and decreasing after initiation of NC system makeup.

END

0 Enclosure 4.5 RP/O/A/5000/001I Loss of Powver Page 1 of 2 JNI.JSUIAL EVENT ALERT SITE AREA EMIERGENCY GENERAL EMERGENCY 4.5.UL.1 Loss of All Offsite 4.5.A.1 Loss of All Offsite 4.5.S.1 Loss of All Offsite 4.5.G.1 Prolonged Loss of All Power to Essential Power and Loss of All Power and Loss of All (Offsite and Onsite) AC Busses for Greater Than Onsite AC Power to Onsite AC Power to P~ower.

15 Minutes. Essential Busses During Essential Busses.

Cold Shutdown Or OPERATING NMODE: 1,2,3,4 OP~ERATING MODE: I, 2, 3, 4 Refueling Mode. OPERATING MODE: 1, 2, 3, 4 4.5.G.1-1 Prolonged loss of all 4.5.U.1-1 The following conditions OPERATING MODE: 5, 6, No 4.5.S.1-1 Loss of all off'site and offsite and onsite AC exist: Mode onsite AC power as power as indicated by:

indicated by:

Loss of offsite power to 4.5.A.I-1 Loss of'all ot/hite and Loss of power on essential buses ETA and onsite AC power as Loss of power on essential buses ETA and ETB for greater than 15 indicated by: essential buses ETA and ETB for greater than 15 minutes. ETB. minutes.

Loss of power on ANDI essential buses ETA and AND AND ETB.

Both emergency diesel Failure to restore power to Standby Shutdown generators are supplying AND at least one essential bus Facility (SSF) fails to power to their respective within 15 minutes. supply NC pump seal essential busses. Failure to restore power to injection OR CA supply at least one essential bus (Continued) to Steam Generators.

within 15 minutes.

(Continued) AND (Continued)

(Continnued)

0 Enclosure 4.5 RP/0/A/5000/001I Loss of Power Page 2 o1"2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.5.S.2 Loss of'All Vital I)C At least one of the OPERATING MOI)E: 5, 6, No 4.5.A.2 AC power to essential Mode busses reduced to a Power. following conditions sinlgle power source for exist:

'4.5.U.I1-2 The 1Ibllowinlg conditions greater than 15 nuinutes OPERATING MODE: 1, 2, 3, 4 exist: such that an additional

Restoration of at least Loss of off'site power to single failure could 4.5.S.2-1 The following conditions one essential bus essential buses ETA and result in station exist: within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is ETB for greater than I5 blackout. NOT likely minutes. Uniplanned loss of both AN_._D_ OPERATING MODE: 1, 2,3, 4 unait related busses: EBA

Indication of' One emergency diesel and EBD both <112 continuing generator is supplying 4.5.A.2-I The following condition VDC, and EBB and EBC degradation of core power to its respective exists: both <109 VDC. cooling based on essential bus. Fission Product AC power capability has AND Barrier monitoring.

4.5.U.2 Unplanned Loss or been degraded to one Required DC Power essential bus powered Failure to restore power to END IDuring Cold Shutdown or from a single power at least one required DC Refueling Mode for source for > 15 maii. due bus within 15 minutes Greater than 15 Minutes. to the loss of all but one from the time of loss.

of:

OPERATING; MODE: 5, 6 END SATA SATB 4S.5.LJ.2-1I The following conditions ATC ATD exist: DiG A D/G B l nlflauned loss of bo0th unit END related busses: IBA and LBD both <112 \"L)C. and I'BB13ad F B&( both - 109 V DC'.

ANxi___

IF iue to testorie power to at Ileast one requi jred I)(' bus within 15 inivmutcs from ihc tinme of loss.

E NI)

0 0

Enclosure 4.6 RPIOIAI50001001I Fire/Explosion and Security Events Page 1 of 3 UNUSUAL* EVENT ALERT SITE AREA EMERGENCY G EN ERAL EM ERG ENCY 4.6.LJ.1 Fire Within Protected Area 4.6.A.1 Fire or Explosion Affecting 4.6.S.1 110OSTILE ACTION within 4.6.G.! ltOSTILE ACTION Boundai'y NOT thne Operability of Plant the PROTECTED AREA Resulting in Loss of Physical Extinguished Within 15 Safety Systems Required to Control of the Facility.

Minutes of Detection OR Establish or Maintain Safe OPERAUTING MODE: ALL Explosion Within the Shutdown. OPERATING MODE: ALL JProtected Area Boundary. 4.6.5.1-I A IIOSTILE ACTION is OiPERATING MODE: 1, 2, 3, 4, 5, 6 occu~rring or has occurred 4.6.G.I-1 A hlOSTILE ACTION has OPERATING MODE: ALL withfin the IPROTECTED occurred such that plant 4.6.A.1-1 The following conditions AREA as reported by thne CNS personnel arc unable to operate 4.6.UJ.l-1 Fire in any of the following exist: Security Shif't Supervision equipment required to areas NOT extinguishned (Non-security events) maintain safety functions.

within 15 minutes of control Fire or explosion in any of the END room notification or following areas: 4.6.G.1-2 A HOSTILE ACTION has verification of a control room

Reactor Building caused failure of Spent Fuel fire alarm.

Auxiliary Building Cooling Systems and

Diesel Generator Rooms IMMINENT fuel damage is

Reactor Building *Control Room likely for a FRESHtLY OFF-

Auxiliary Building

RN Pumphouse LOADED REACTOR

Diesel Generator Rooms

SSF CORE in pool.

Control Room

CAS

RN Pumphouse

SAS

SSF

FWST END)

CAS " Doghouses (Applies in

SAS Mode I, 2, 3, 4 only).

Doghouses

FW\ST ANDI

" Turbine Bu~ilding

Service lBuilding Onle of the liollow~ing:

Monitor Tank Buildine

ISI:SI

Affected safety system

tin it 1'2 ransfIbriner Yard Iparaumcter indications show Area*.ilS degraded perlirmnance

((01'olin ed l(-'oniiinucd)

0 Enclosure 4.6 RP!OIAI5 000/001I Fire/Explosion and Security Events Page 2 of 3 UINUISUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.6. U.i1-2 Report by plant personnel of *Plant personnel report an unanticipated explosion visible damage to within protected area permlanenlt structures or boundary resulting in visible equipment within the damage to permanent specified area required to structure or equipment or a establish or maintain safe loaded cask inl the ISFSI. shutdown within the specifications.

4.6.[I.2 Confirmed SECURITY CONDITION or Threat Note: Only one train of a system Which Indicates a Potential needs to be affected or Degradationi in the Level of damaged in order to satisfy Safety of the Plant.

this condition.

OIPERATING MODE: All 4.6.A.2 Fire or Explosion Affecting tihe Operability of P~lant 4.6.U1.2-I A SECURITY CONDITION Safety Systems Required to that does NOT involve a ItOSTILE ACTION as Establish or Maintain Safe reported by the CNS Security Shutdown.

Shift Supervision.

OPERATING MODE: No Mode 4.6.U.2-2 A credible site-specific security threat notification. 4.6.A.2-1I The following conditions exist:

4.6.U1.2-3 A validated notificaltion frol' (Non-security events)

NRC providing inlormation ol Fire or explosion in any of the an aircrafft threat. following areas:

Spent Fuel Pool ENDI

Auxiliary Building.

RN Pump houise AND One of the following:

Spent Fuel Pool level anld/or tempeC~llratr sho~v degraded pcrlbrmance

!('on tin ued)

Enclosure 4.6 RP/0/A/5000/001 Fire/Explosion and Security Events Page 3 of 3 UJNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Plant personnel report visible damage to permanent structures or equipment supporting spent fuel pool cooling~.

4.6.A.3 IIOSTILE ACTION Within the OWNER CONTROLLED AREA or Airborne Attack Threat.

OPERATING MODE: ALL 4.6.A.3-1 A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the CNS Security Shift. Supervision 4.6.A.3-2 A validated notification from

NRC of airliner attack threat wiihin 30 minutes of the site.

END

Enclosure 4.7 RP/0/A/5000/001I P~age I of 4 Natural Disasters, Iltazards, And Other Conditions Affecting Piant Safety UNUSUAL EVENT ALERT SITE AREA EMIERGENCY GENERAL EMIERGENCY 4.7.U.1 Natural and Destructive 4.7.A. 1 Natural and Destructive 4.7.S.1 Conitrol Room Evacuatiou 4.7.G.1 Other Conditions Existing Phenomena Affectinig tihe Phenomena Affecting the Iltas Been hnitiated and Plant Which in the Judgement of Protected Area. Plant Vital Area. Control Cannot Be the Emergency Established. Coordinator/EOF Director OPERA*TING MIODE: ALL OPERATING MODE: ALL Warrant Declaration of OPERATING MODE: ALL General Emergency.

4.7.U.l-1 Tremor felt and valid alarm on 4.7.A.1-1 Valid "~OBE Exceeded" Alarm the Syscom Seismic on I AD-4.B/8 4.7.S.1-1 The followving conditions OPERATING MODE: ALL Monitoring System (OAC C 1D225 2 ). exist:

4.7.A.i-2 Tornado or high winds: Control Room evacuation has been 4.7.G.1-1 Other conditions exist which 4.7.U.I-2 Report by plant personnel of initiated per in the Judgement of the tor'nado striking within Tornado striking plant API/1 (2)/A/5500/0 17 Emergency Coordinator/EOF protected area structures within the vital AND Director indicate:

boundary/ISFSl. a rea: Control of the plant cannot be established from the ASP or (I) actual or imminent 4.7.U.I-3 Vehicle crash into phlan

Reactor Building the SSF within 15 minutes. substantial core degradation structures or systems within

Auxiliary Building with potential for loss of protected area

FWST 4.7.S.2 Other Conditions Existing containment boundary/ISFSI.

Diesel Generator Rooms Which in the Judgement of

Control Roorn the Emergency OR 4,7.U.1-4 Report of turbine failure

RN Pumphouse Coordinator/EOF Director resutlting inl casing penetration

SSF Warrant Declaration of Site (2) potential for uncontrolled or damage to turbine or

Doghouses Area Emergenicy. radionuclide releases. These generator seals. releases can reasonably be

CAS

SAS OPERATING MODE: ALL expected to exceed 4.7.1_1.1-:5 Independenlt Spent Fuel Cask Environmental Protection tipped over or dropp~ed greater 4.7.S.2-1 Other conditions exist which Agency Protective Action than 24 inches. OR in the J udgemient of the Guideline levels outside the sustained winds >_74 mph lbr Emergency Coordinator/EOF- site boundary.

4.7.11.I-6 LUncontrolled flooding in the

-" I5 minutes. Director indicate actual or ISFSI area.

likely ma~jor lhuilures ofplant L-NI) 4.7.1 .1-7 "l'rnado generated missiles(s) t(oinllliuiedl functions needed lbr impactin-~ the ISFS I. protection of the public.

S('ioninuitd) I"N I)

0 Enclosure 4.7 RP/0/A/5 000/001 Natural Disasters, Hazards, Andi Other Conditions Affe~cting Plant Safety Page 2 of 4 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.7.11.2 Release of toxic or 4.7.A.1-3 Visible structural damage Fininniable Gases Deemed caused by cither:

Detrimental to Safe

Vehicle crashes Operation of the FPlant. OR

Turbine failure generated O IPERATING MODE: ALL missiles, OR 4.7.U1.2-I Report or detection of toxic or

Other catastrophic events flammable gases that could enter within the site boundary on any of the following plant in amounts that can affect safe structures:

operation of the phlan.

Reactor Building

Auxiliary Building 4.7.U1.2-2 Report by Local, County or

FW'ST State Officials for potential

Diesel Generator Rooms evacuation of site personnel

Control Room based on offsite event.

RN Pump I-ouse

SSF 4.7.U.3 Other Conditions Existing

Doghouses Which in the Judgemtent of

CAS the Emergency

SAS Coordinator/EOF Dir-ector Warrant Declaraition of art Unusual Event.

(C*ontinued)

OIPERATING MODE: ALL 4.7.11.3-1 Other conditions exist which in thle juidg~eicnt of, the Emergency Coord ilnatoriLOF-lirector indicate a potei ti al dcegradation of the level of satet o~t'"theU p3tlant.

VNI

0 Enclosure 4.7 RP/0/A/5000/00 Natural Disasters, Hazards, And Other Conditions Affe~cting Plant Safety Page 3 o1"4 UNUSUAL EVENT ALERT SITE AREA EM1ERGENCY' GENERAL EMERGENCY 4.7.A.2 Release of Toxic or" Flanmnable Gases Within a Facility Structure Which Jeopardizes Operation of Systems Required to Maintain Safe Operations or to Establish or Maintain Cold Shutdown.

OPERATING MODE: ALL 4.7.A.2-1 Report or detection of toxic gases within a Facility Structure in concentrations that will be life threatenine to plant personnel.

4.7.A.2-2 Report or detection of flammable gases within a Facility Structure in concentrations that will affect the safe operation of the plant.

Structures lbr the above EALs:

, Reactor Building

Auxiliary Building

Diesel Generator R~oomas

Control Room

RN lPumphouse

SSF

CAS

SAS

0 Enclosure 4.7 RP/O/A/5000/O0 Natural Disasters, Hazards, And Other Conditions Affecting Plant Safety Page 4 of 4 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.7.A.3 Control Room Ev'acuatjion llas Beeni Initiated.

OPERATING MODE: ALL 4.7.A.3-1 Control Room evacuation has been initiated per API/1 (2)/A15500/0 17.

4.7.A.4 Other Conditions Existing Which in the Judgemnent of the Emnergency Coordinator/EOF Director Warrant Declaration of an Alert.

OPERATING MODE: ALL 4.7.A.4-1 Other conditions exist which in the Judgement of the Emergency Coordinabor/EOF Director indicate that plant safety systems may be degraded and that increased monitoring of plant functions is warranted.

ENDI

Enclosure 4.8 RP/O/A/5000iOO0I Definitions/Acronyms Page I of"4 ALERT- Events are in process or have occurred which involve an actual or potential substantial degradation of the level of saf'ety of the plant or a security event that involves probable life threatening risk to sire personnel or damage to site equipment because of hostile action. Any releases are expected to he limited to small fractions of the EPA protective action guideline exposure levels.

ALL (As relates to Operating Mode Applicability) - Modes 1, 2, 3,4,5,6 and No Mode (De fueled)

BOMB - Refers to an explosive device suspected of having sufficient force to damage plant systems or structures.

CARF - Conatainment Air Return Fan.

CIVIL DISTURBANCE - A group often (10) or more people violently protesting station operations or activities at the site. A civil disturbance is considered to be violent when force has been used in anl attempt to injure site personnel or damage plant property.

COGNIZANT FACILITY STAFF - Any member of facility staff, who by virtue of train inJg and experience.

is qualified to assess the indications or reports fobr validity and to compare the same to the EALs in the licensee's emergency classification scheme (Does not include staff whose positions r'equire they report, rather than assess, abnormal conditions to the facility.).

CREDIBLE THREAT - A threat should be considered credible when:

Physical evidence supporting the threat exists.

Information independent (law enforcement) from the actual threat message exists that supports the threat.

o A specific group or organization claims responsibility for the threat.

EPA PAG - Environmental Protection Agency Protective Action Guidelines for exposure to a release of radioactive material.

EMERGENCY RELEASE - Any unplanned, quantifiable radiological release to the environment during an emergency event. The release does not have to be related to a declared emergency.

EXPLOSION - A rapid, violent unconfined combustion, or a catastrophic failure of pressurized equipmenlt (e.g., a steamline or feedwater line break) that imparts energy sufficient to potentially damage or creates shrapnel to actually damage permanent structures, systems or components. An electrical breaker flash that creates shrapnel and results in damage to other components beyond scorching should also be considered.

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

FIRE - Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute fires. Observation of flames is preferred but is NOT required if large quantities of smoke and heat are observed. An electrical breaker flash that creates high temperatures for a short duration and merely localized scorching to that breaker and its compartment should not be considered a fire.

FRESHLY OFF-LOADED REACTOR CORE - The complete removal and relocation of"all fuel assemblies fr'om the reactor core and placed in the spent ftiel pool. (Typical of a "No Mode" operation during a refuel outage that allows safety system maintenance to occur and results in maximum decay heat load in the spent fuel pool system.)

Enclosure 4.8 RP/0/AIS000/001 Definitions/Acronyms Page 2 of"4 FUNCTIONAL - A component is fully capable of meeting its design function. It would be declared INOPERABLE if unable to meet Technical Specifications.

GENERAL EMERGENCY- Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or hostile action that results in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA protective action guideline exposure levels offsite for more than the immediate site area.

HOSTAGE - A person(s) held as leverage against the station to ensure demands will be met by the station.

HOSTILE ACTION - An act toward an NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidates the licensee to achieve an end. This includes attack by air.

land, or water using guns, explosives, PROJECTILES, vehicles or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included. HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on thle NPP. Non-terrorism-based EALs should be used to address such activities (e.g.. violent acts between individuals in the OWNER CONTROLLED AREA).

HOSTILE FORCE - One or more individuals who are engaged in a determined assault, overtly or by stealhh and deception, equipped with suitable weapons capable of killing, maiming or causing destruction.

IMMINENT - M itigation actions have been ineffective, additional actions are not expected to be sutccessfl, and trended information indicates that the event or condition will occur. Where IMMVINENT time frames are specified, they shall apply.

INOPERABLE - A component does not meet Technical Specifications. Thle component may be f'unctional.

capable of meeting its design.

INABILITY TO DIRECTLY MONITOR - Operational Aid Computer data points are unavailable or gnu ges/panel indications are not readily available to the operator.

INTRUSION - A person(s) present in a specified area without authorization. Discovery of a BOMB in a specified area is indication of INTRUSION into that area by a HOSTILE FORCE.

ISFSI - Independent Spent Fuel Storage Installation - Includes the components approved for loading and storage of spent fluelI assemblies.

LOSS - A component is INOPERABLE and not FUNCTIONAL.

NO MODE - Defue led.

OWNER CONTROLLED AREA - Area outside the protected area fence that immediately surrcounds the plant. Access to this area is generally restricted to those entering on official business.

PROJECTILE - An object directed toward a NPP that could cause concern for its continued operability.

reliability or personnel safety.

PROLONGED - A duration beyond normal limits, defined as "greater than 15 m~inutes' or as determine~d by the judgment of the Emergency Coordinator.

Enclosure 4.8 RPi0/A/5000i00 I Definitions/Acronyms Page 3 of 4 PROTECTED AREA - Typically, the site specific area which normally encompasses all controlled areas wvithin the security PROTECTED AREA fence.

REACTOR COOLANT SYSTEM (RCS/NCS) LEAKAGE - RCS Operational Leakage as defined in the Technical Specification Basis B 3.4.13.

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

SABOTAGE - Deliberate damage, misalignment, or misoperation of plant equipment wvith the intent to render the equipment unavailable. Equipment found tampered with or damaged due to malicious mischief may not meet the definition of SABOTAGE until this determination is made by security supervision.

SECURITY CONDITION - Any Security Event as listed in the approved security contingency plan that constitutes a threat/compromise to site security, threat/risk to site personnel or a potential degradation to the level of safety of the plant. A SECURITY CONDITION does not involve a HOSTILE ACTION.

SIGNIFICANT PLANT TRANSIENT- An unplanned event involving one or more of the following: (I)

Automatic turbine runback >25% thermal reactor power, (2) Electrical load rejection >25% full electrical load; (3) Reactor Trip, (4) Safety Injection. (5) Thermal power oscillations >1 0%.

SITE AREA EMERGENCY - Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevent effective access to equipment needed for the protection of the public.

Any releases are not expected to exceed EPA Protective Action Guidelines to exposure levels beyond the site boundary.

SITE BOUNDARY - That area, including the protected area, in which Duke Energy has the autthority to control all activities, including exclusion or removal of personnel and property.

SLC - Selected Licensee Commitments.

SUSTAINED - A duration of time long enough to confirm that the CSF is valid (not nmomentary).

TERMINATION - Exiting the emergency condition.

TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) - The sum of external dose exposure to radioactive plume, to radionuclides deposited on the groutnd by the plume, and the internal exposure inhaled radionuclides deposited in the body.

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

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

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

Enclosure 4.8 RPIOIAI50001001 Definitions/Acronyms Page 4 of 4 UNUSUAL EVENT- Events are in process or have occurred which indicate a potential degradation of"the level of safety of the plant or indicate a security threat to facility protection has been initiated. No releases of radioactive material requiring offsite response or monitoring are expected unless fuirther degradation or" safety systems occurs.

VALID - An indication or report or condition is considered to be VALID when it is conclusively verified by:

(I) an instrument channel check, or (2) indications on related or redundant instrumentation, or (3) hy direct observation by plant personnel such that doubt related to the instrument's operability, the condition's existence or the report's accuracy is removed. Implicit in this definition is the need for timely assessment.

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

VISIBLE DAMAGE - Damage to equipment or structure that is readily observable without measurements, testing, or analyses. Damage is sutfficient to cause concern regarding the continued operability or reliability of affected strutcture, system, or component. Example damage: deformation due to heat or impact. denting, penetration, rupture, cracking, paint blistering.

VITAL AREA - Areas within the PROTECTED AREA that house equipment important for nuclear safety.

Access to a VITAL AREA is allowed only if an individual has been authorized to be in that area per the secuirity plan. Therefore, VITAL AREA is a security term.

Enclosure 4.9 RPiO/A/5000/OO01 Emergency Declaration Guidelines Page I ot'2 TI-E FOLLOWING GUIDANCE IS TO BE USED BY THE EMERGENCY COORDINATOR IN ASSESSING EMERGENCY CONDITIONS.

Assessment, classification and declaration of any applicable emergency condition should be completed with 15 minutes after indication or information is available to COGNIZANT FACILITY STAFF that an EAL threshold has been exceeded.

o The Emergency Coordinator shall review all applicable initiating events to ensure proper classification.

Thle BASIS Document (located in Section D of the Catawba Nuclear Site Emergency Plan) is available for review if any questions arise over proper classification.

Emergencies are declared for the site. If an event results in multiple emergency action levels on a unit or different emergency action levels on each unit, then the emergency declaration shall be based on the higher classification. Information relating to the unit with the lesser classifica'tion will be noted as additional information on the Emergency Notification Form (EN F).

If an event occurs, and a lower or higher plant operating mode is reached before the classification can be made, the classification shall be based on the mode that existed at the time the event occurred.

The fission product barrier matrix is applicable only to those events that occur at (Mode 1-4) hot shutdown or higher. An event that is recognized at cold shutdown or lower (Mode 5 or 6) shall not be classified using the fission product barrier matrix. Reference would he made to the other enclosures that provide emergency action levels for specific events (e.g. severe weather, fire.

security).

If a transient event should occur, the following guidance is provided.

1.Some emergency action levels specify that a condition exist for a specific dluration prior to declaration.

a. For these EALs, the classification is made when the Emergency Coordinator assessment concludes that the specified duration is exceeded or will be exceeded (i.e. condition cannot be reasonably corrected before the duration elapses),

whichever is sooner.

b. If a plant condition exceeding EAL criteria is corrected before the speci fied duration time is exceeded, the event is NOT classified by that EAL,. Lower Severity EALs, if any, shall be reviewed for possible applicability in these cases.

Enclosure 4.9 RR/O/A/5000/O01 Emergency Declaration Guidelines Pace 2 o f 2

2. If a plant condition exceeding EAL criteria is not recognized at the time of occurrence, but is identified well after the condition has occurred (e.g. as a result of routine log or record review) and the condition no longer exists, an emergency shall NOT be declared.

Reporting under 10OCFR50.72 may be required. Such a condition could occur, f'or example, ifra follow-up evaluation of an abnormal condition uncovers evidence that the condition was more severe than earlier believed.

3. If an emergency classit'ication is warranted, but the plant condition is corrected prior to declaration and notification, the Emergency Coordinator must consider the potential that the initiating condition (e.g. Failure of Reactor Protection System or earthquake) may have caused plant damage that warrants augmenting the on-shift personnel via activation of the Emergency Response Organization. Thle following action shall be taken:

a. For UNUSUAL EVENTS, the condition shall be declared and notifications made. The event may be terminated in the same notification or in a f'ollow-up notification.

b. For ALERT, SITE AREA EMERGENCY, and GENERAL EMERGENCY, rhe event shall be declared and the emergency response organization activated.

DETERMINATION OF 'EVENT TIME" (TIME THE I5 MINUTE CLOCK STARTS)

I. Event time is the time at which indications become available that an EAL has been exceeded.

2. Event time is the time the 15 minutes clock starts for classification.

3. The event classification time shall be entered on thle emergency notification fbrm.

MOMENTARY ENTRY INTO A HIGHER CLASSIFICATION If. while in an emergency classification, the specified EALs of a higher classification are met momentarily, and in the judgment of the Emergency Coordinator are not likely to recur, the entry into the higher classification must be acknowledged. Acknowledgment is performed as follows:

If this condition occurs prior to the initial notification to the emergen cy response organization and off site agencies, the initial message should note that the site is currently in the lower classification, but had momentarily met the criteria for the higher classification. It should also be noted that plant conditions have improved and stabilized to the point that the criteria for the higher classification are not expected to be repeated.

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Enclosure 4.10 RP/O/A/5000/001I Radiation Monitor Readings for Enclosure 4.3 Page 1IoflI Note: These values are not intended to apply to anticipated temporary increases due to planned events (e.g. incore detector movement, radwaste container movement, depleted resin transfers, etc.).

Detector Elevation Column Identifier Unusual Event Alert

____________mrRlhr mnR/hr IEMF-l 522' FF, 57 Auxiliary Building Corridor 500 5000 I EMF-3 543' GG, 55 Unit 1 Charging Pump Area 100 5000 1EMF-4 543' GG, 59 Unit 2 Charging Pump Area 100 5000 IEMF-7 560' NN, 55 Unit 1 Auxiliary Building Corridor 1500 5000 1EMF-8 560' NN, 59 Unit 2 Auxiliary' Building Corridor 500 5000 1EM~'F-9 577' LL. 55 Unit 1 Aux. Building Filter [latch 100 5000 I1EMF- 10 577' LL, 58 Unit 2 Aux. Building Filter Hatch 100 5000 1EMNF-22 594' KK, 53 Containment Purge Filter Area 100 5000 2EMF-9 594' KK, 61 Containment Purge Filter Area 100 5000