Text

Independent Spent Fuel Storage Installation, Submittal of Changes to the Emergency Response Plan and Implementing Procedures
	ML100550711
Person / Time
Site:	Calvert Cliffs
Issue date:	02/12/2010
From:	Fick M; Constellation Energy Group
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
	ERPIP-109, Rev 00800
	Download: ML100550711 (197)
	v • d • e

Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 CENG a joint venture of A Constellation 6'7.eDF Energy- ,,D CALVERT CLIFFS NUCLEAR POWER PLANT February 12, 2010 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit Nos. I & 2; Docket Nos. 50-317 & 50-318 Independent Spent Fuel Storage Installation Docket No. 72-8 Changes to the Emergency Response Plan and Implementing Procedures As required by 10 CFR 50.54(q), 10 CFR Part 50 Appendix E.V, and 10 CFR 72.44(0, changes to the Emergency Response Plan Implementing Procedures are enclosed. These changes do not decrease the effectiveness of the Emergency Response Plan.

Should you have questions regarding this matter, please contact Mr. Douglas E. Lauver at (410) 495-5219 or Mr. Michael J. Fick at (410) 495-5216.

Very truly yours, Michael J. Fick Director - Emergency Preparedness MJF/CAN/bjd

Enclosures:

ERPIP-109, Revision 00800 ERP, Revision 04100 cc: S. J. Collins, NRC Resident Inspector, NRC E. W. Brach, NRC (Without Enclosures)

D. V. Pickett, NRC S. Gray, DNR f\hl-

Constellation Energy Calvert Cliffs Nuclear Power Plant TECHNICAL PROCEDURE ERPIP-1 09 RADIATION MONITORING SYSTEM COMMUNICATOR (CR)

Revision 00800 Safety Related REFERENCE USE Applicable To:

Calvert Cliffs Nuclear Power Plant Approval Authority:

Plant General Manager

RADIATION MONITORING SYSTEM COMMUNICATOR (CR) ERPIP-109 Revision 00800 Page 2 of 10

SUMMARY

OF ALTERATIONS Revision Change Summary of Revision or Change 008 00 Updated Section 2.0. Removed the Scope of the procedure. The Scope indicated that steps in section 6.2, Operations, could be performed in any order, however, the steps must to be performed in the order they are presented.

Updated Section 3.1, Developmental References. Changed 3.1.6 from PR-1-1i01, Preparation and Control of Calvert Cliffs Technical Procedures to CNG-PR-1.01-1005, Control of Constellation Nuclear Generation Technical Procedure Format and Content.

(RPA-2007-1499). PR-1-101 is no longer used.

CNG-PR-1.01-1005 is the new fleet procedure.

Updated Section 3.1, Developmental References. Changed 3.1.7 from PR-1-103, Use of Procedures, to CNG-PR-1.01-1009, Procedure Use and Adherence Requirements. (RPA-2007-1499).

PR-1-103 is no longer used. CNG-PR-1.01-1009 is the new fleet procedure.

Updated Section 3.2, Performance References. Added CNG-PR-3.01-1000, Records Management. This reference, formally, PR 100 was referred to in Section 9.0, Records and was never referenced in the performance section.

6.2 Note Deleted "The steps in Subsection 6.2 may be performed in any order." This does not apply to section 6.2.

6.2.1 Added "Refer to Attachment 2, RMS Setpoint to obtain additional information as needed" 6.2.2.1, 6.2.2.2, and 6.2.2.3 Updated Steps to correct the out of date instructions for transmitting data for the Radiation Monitoring System Communicator. (PCR-09-01984) (PCR-09-05884) 6.2.4.1 Added Note to correct the out of date instructions for transmitting data for the Radiation Monitoring System Communicator. (PCR-09-01984) (PCR-09-05884) 6.2.4.1 Deleted Emergency Operations Facility, Environmental Assessment Office because it no longer exists. The position is located in the DAO. (PCR-09-01984) 8.1.2 Added "according to CNG-PR-3.01-1000, Records Management" Added Attachment 2, RMS Setpoints, to Table of Contents. This is not currently in Revision 00703. The Attachment is in Revision 00703 but not stated in the Table of Contents.

Changed all references from "web page" to SharePoint to comply with current usage.

Converted the procedure into the CEG template.

RADIATION MONITORING SYSTEM COMMUNICATOR (CR) ERPIP-109 Revision 00800 Page 3 of 10 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPO SE .................................................................................................................................. 4 2.0 APPLICABILITY/SCO PE ....................................................................................................... 4 2.1. Applicability ........................................................................................................... .. 4 2.2. Responsibilities .......................................................................................................... 4

3.0 REFERENCES

AND DEFINITIO NS ...................................................................................... 4 3.1. Developm ental References ......................................................................................... 4 3.2. Perform ance References .......................................................................................... 5 3.3. Definitions ....................................................................................................................... 5 4.0 PREREQ UISITES ........................................................................ ....................................... 5 4.1. Training and Qualification ......................................... 5 4.2. Initial Conditions ........................................................................................ I............. 5 5.0 PRECAUTIO NS ......................................................................................................................... 5 6.0 PERFO RMANCE .............................................................................................................. 5 6.1. Activation ........................................................................................................................ 5 6.2. Operation .................................................... 6 6.3. Deactivation ........................................................................................... .................... 7 7.0 BASES .......................................................................................... ............................................ 7 8.0 RECO RDS ................................................................................................................................. 7 ATTACHM ENT 1, RM S STATUS ....................................................................................................... 8 ATTACHMENT 2, RMS SETPOINTS ..................................................................... 9

RADIATION MONITORING SYSTEM COMMUNICATOR (CR) ERPIP-109 Revision 00800 Page 4 of 10 1.0 PURPOSE This procedure provides emergency response instructions to the Radiation Monitoring System (RMS) Communicator (CR) at the Control Room when responding to an emergency action' level called at Calvert Cliffs Nuclear Power Plant.

2.0 APPLICABILITY/SCOPE 2.1. Applicability 2.1.1. This procedure applies to the RMS Communicator (CR).

2.1.2. Performance of this procedure is in the order of Activation (Subsection 6.1), Operation (Subsection 6.2) and Deactivation (Subsection 6.3).

2.2. Responsibilities 2.2.1. The RMS Communicator (CR) shall:

1. Report directly to the Shift Manager (CR).

2. Record RMS data.

3. Transmit RMS data for other Emergency Response Centers.

4. Update RMS data for other Emergency Response Centers.

3.0 REFERENCES

AND DEFINITIONS 3.1. Developmental References 3.1.1. NUREG 0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 3.1.2. 10 CFR 20, Standard for Protection Against Radiation 3.1.3. 10 CFR 50.47, Emergency Plans 3.1.4. 10 CFR 50 Appendix E to Part 50, Emergency Planning and Preparedness for Production and Utilization Facilities 3.1.5. Calvert Cliffs Nuclear Power Plant Emergency Response Plan 3.1.6. CNG-PR-t .01-1005, Control of Constellation Nuclear Generation Technical Procedure Format and Content 3.1.7. CNG-PR-1.01-1009, Procedure Uses and Adherence Requirements 3.1.8. CNG-PR-3.01-1000, Records Management

RADIATION MONITORING SYSTEM COMMUNICATOR (CR) ERPIP-109 Revision 00800 Page 5 of 10 3.2. Performance References 3.2.1. Calvert Cliffs Nuclear Power Plant Emergency Response Plan 3.3. Definitions 3.3.1. None 4.0 PREREQUISITES 4.1. Training and Qualification 4.1.1. Personnel performing this procedure shall be qualified on the tasks or activities contained in this procedure.

4.2. Initial Conditions 4.2.1. One of the following emergency action levels is called at Calvert Cliffs Nuclear Power Plant:

Alert 0 Site Area Emergency.

General Emergency 4.3. Documentation and Support 4.3.1. Forms needed to implement this pr'ocedure are contained as attachments to this procedure.

Forms may be computer generated or revised without requiring a change or revision to this procedure, providing the intent is not changed, and the required information is not deleted from the existing forms.

5.0 PRECAUTIONS 5.1. Declared pregnant women and minors are not authorized to perform emergency functions.

6.0 PERFORMANCE 6.1. Activation 6.1.1. REPORT to Control Room on notification of an Alert, Site Area Emergency, OR General Emergency.

6.1.2. NOTIFY GS - Nuclear Plant Operations (GS-NPO) (CR) OR Shift Manager (CR) of your presence for accountability.

RADIATION MONITORING SYSTEM COMMUNICATOR (CR) ERPIP-109 Revision 00800 Page 6 of 10 6.2. Operation NOTE Additional Attachment 1, RMS Status forms are stored in the "Emergency Forms" file cabinet located in Unit-1 DAS.

6.2.1. RECORD information specified on Attachment 1, RMS Status, from the control panels. Refer to Attachment 2, RMS Setpoints to obtain additional information as needed.

6.2.2. UPDATE the Emergency Response SharePoint RMS Status information (this may be delegated) at approximately 15 minute intervals by performing the following steps:

1. Using Copier, E-MAIL RMS Status form to your email address.

2. OPEN file and SAVE RMS data file to your desktop as "rmsOl" "rms02", "rms03", and so forth.

3. UPLOAD the RMS data file to the ERO SharePoint at:

http://moss.constellation.com/cgg/home/ero/ccnpp/default.aspx 6.2.3. SUBMIT updates to the Emergency Response SharePoint at approximately 15 minute intervals.

6.2.4. IF the Emergency Response SharePoint is not operable, THEN TRANSMIT RMS Status to the centers listed below by any means possible (for example, telephone; facsimile machine; runner).

NOTE Phone and Fax Numbers are available in the Emergency Response Facility Phone Book located on the ERO SharePoint under CCNPP Drill/Event Data tab titled ERF Contact Information.

1. NOTIFY the following respective centers of the data transmission method being used:

Operational Support Center

Emergency Operations Facility, Dose Assessment Office I

RADIATION MONITORING SYSTEM COMMUNICATOR (CR) ERPIP-109 Revision 00800 Page 7 of 10 6.3. Deactivation 6.3.1. WHEN notified of event termination, THEN

1. COLLECT records generated during the event.

2. RETURN equipment AND unused material to the designated storage locations AND DISPOSE of trash in the appropriate locations.

.3. FORWARD records to Shift Manager (CR) for turnover to the Director - Emergency Preparedness.

7.0 BASES None 8.0 RECORDS I -

8.1. Records generated by this procedure may be permanent, non-permanent, or lifetime radiological records depending on the circumstances under which they are generated.

Records shall be captured and controlled as follows:

8.1.1. During an actual event as described in the purpose statement of this procedure, records shall be considered permanent records and submitted to the Emergency Preparedness Unit for V final disposition according to CNG-PR-3.01-1000, Records Management.

Attachment 1, RMS Status 8.1.2. During an actual event as described in the purpose statement of this procedure, dosimetry records, that is, any dose-related record including access history records, are considered radiological lifetime records and are to be handled and maintained according to CNG-PR-3.01-1000, Records Management.

8.1.3. During a drill or exercise, records generated shall be considered non-permanent records and submitted to the Emergency Preparedness Unit for evaluation and retention according to CNG-PR-3.01-1000, Records Management.

Attachment 1, RMS Status

RADIATION MONITORING SYSTEM COMMUNICATOR (CR) 0 ERPIP-1 09 Revision 00800 Page 8 of 10 Page 1 of 1 ATTACHMENT 1, RMS STATUS Date:

Time 1-RR-11 0-RR-11 2-RR-21 1-RI-7004 (51) R/HR 1-RI-5316A (61) RJHR 0-RI-7017 (51) RJHR 0-RI-7020 (56) R/HR 2-RI-7004 (51) RIHR 2-RI-5316A (61) RIHR U-1 East ECCS PpRm U-1 Cntmt RC Waste PP RM SFP HX Rm U-2 East ECCS PpRm U-2 Cntmt 1-RI-7005 (52) RIHR 1-RI-5415 (66) CPM 0-RI-7016 (52) R/HR 0-RI-7023 (57) RJHR 0-RI-7027 (62) R/HR 2-RI-7005 (52) R/HR 2-RI-5415 (66) CPM U-1 West ECCS PpRm Main Vent Gaseous Misc Waste PP RM Chem Lab Gas Anal Equip RM U-2 West ECCS PpRm Main Vent Gaseous 7-V 1-RI-7006 (53) R/HR 1-RI-5410 (70) CPM - ' 0-RI-5420

- (65) CPM 2-RI-7006 (53) R/HR 2-RI-5410 (70) CPM Sample RM WP Vent - Fuel Hand Area Vent Sample RM WP Vent -

S-RI-5406 (71) CPM 0-RI-7018(54) RIHR 0-RI-7025 (59) R/HR 0-RI-5425 (66) CPM 2-RI-5406 (71) CPM

" 'RM " U-1 ECCS PP Vent Waste Gas Equip Spent Mach Fuel Handling Access Cont Area Vent U2 ECCS PP Vent 1-RI-7011 (60) R/HR .0RI-7024 (60) R/HR 0-RI-5350 (67) CPM 2-RI-7011 (60) RJHR -j,*

U-1 West .e SFP Area RM Cont Rm Vent U-2 West Pen Rm

0 RADIATION MONITORING SYSTEM COMMUNICATOR (CR) ERPIP-109 Revision 00800 Page 9 of 10_

Page 1 of 2 ATTACHMENT 2, RMS SETPOINTS Time 1-RR-11 O-RR-11 2-RR-21 Device 1-RI-7004 1-RI-5316A O-RI-7017 0-RI-7020 0-RI-7026 2-RI-7004 2-RI-5316A Location U-I Cntmt Scale U-i East ECCS R/HR RC Waste PP RM SFP HX Rm New Fuel Storage U-2 East ECCS Pp U-2 Cntmt Range PpRm R/HR E.-4/E 1 R/HR RJHR Area JRPJR Rm R/HR High Alarm E-4/E1 150 mr/hr E-4/E1 E-4/E1 R/HR RIHR E-4/E1 5 mr/hr 6 mr/hr E-4/E1 E-4/E1 150 mr/hr 100 mr/hr 5 mr/hr 100 mr/hr Device 1-RI-7005 1-RI-5415 0-RI-7016 0-RI-7023 0-RI-7027 2-RI-7005 2-RI-5415 Location Scale U-1 Westt ECCS Main Vent Gaseous Misc Waste PP RM Chem Lab Gas Anal Equip RM U-2 West ECCS Pp Main Vent Gaseous PpRm R/HR R/HR Rm Range R/HR CPM R/HR E-4/El E-4/E1 R/HR CPM High Alarm E-4/E1 El/E6 E-4/E1 1 mr/hr 2 mr/hr E-4/E1 El/E6 100 mr/hr 30,000 cpm 25 mr/hr 100 mr/hr 30,000 cpm Device 1-RI-7006 1-RI-5410 0-RI-7019 0-RI-7022 0-RI-5420 2-RI-7006 2-RI-5410 Location WP Vent Scale Sample RM CPM Decon RM Liquid Waste Evap Fuel Hand Area Vent Sample RM WP Vent Range RJHR ElE6 R/HR Rm CPM R/HR CPM iger E-4/E1 E60 E-4/E1 R/HR El/E6 E-4/E1 El/E6 High60 mr/hr 5 mr/hr 600 cpm 60 mr/hr 600 cpm 20 mr/hr

RADIATION MONITORING SYSTEM COMMUNICATOR (CR) ERPIP-1 09 Revision 00800 Page 10 of 10 Page 2 of 2 Attachment 2, RMS SETPOINTS (Continued)

Time 1-RR-11 0-RR-11 2-RR-21 Device 1-RI-7010 1-RI-5406 0-RI-7018 0-RI-7025 0-RI-5425 2-RI-7010 2-RI-5406 Location U-1 ECCS PP Vent U2 ECCS PP Vent Scale U-1 BAST RM Waste Gas Equip Spent Fuel Handling Access Cont Area U-2 BAST RM Range RIHR E-4/E1 CPM E1/E6 RM R/HR Mach Vent R/HR CPM R/HR CPM EV1E6 High Alarm 20 mr/hr E-4/E1 E4/E1 El/E6 E-4/E1 1,000 cpm 2000 cpm E-4/E1 10 mr/hr 100 cpm 20 mr/hr 10 mr/hr Device 1-RI-7011 0-RI-7021 0-RI-7024 0-RI-5350 2-RI-701 1 Location Cant Rm Vent U-2 West Pen Rm Scale U-1 West Pen Rm Drum Storage RM SFP Area RM CPM R/HR Range - " R/HR R/HR R/HR E1/E6 E-4/El High Alarm E-4/E1 E-4/El E-4/El 120 cpm 50 mr/hr 75 mr/hr 10 mr/hr 5 mr/hr Device 1-RI-5317A 1-RIC-5421 2-RI-5317A 2-RIC-5421 Location Scale U-1 Cntmt Hi Range 11 Main Stm Eff RJH U-2 Cntmt Hi Range 21 Main Stm Eff Range R/H E/E4 R/H R/H High Alarm EO/E8 10 mr/hr EO/E8 E-4/E4 6 r/hr 6 r/hr 10 mr/hr Device 1-RIC-5415 RIC-5422 R/H 2-RIC-5415 2-RIC-5422 Location U-1 PLT Vent U-2 PLT Vent Scale Eff Noble Gas 12 Main Stm Eff Eff Noble Gas 22 Main Stm Eff Range High Alarm UCi/Sec UCi/Sec R/H EI/E8 R/H El/E8 E-4/E4 137,000 uci/sec E-4/E4 137,000 uci/sec 10 mr/hr 10 mr/hr

~ 4 CALVERT CLIFFS NUCLEAR POWER PLANT Emergency Response Plan REVISION 41 Effective Date: 1/21/2010 Writer Janna jacksoti.')CV~~

anbd Signae Date Reviewer: Joyce T~uret -

tDate.

Director .-EP:: Mike Fick PrintcdN ndemidSgnature Date PORC Mtg. #:

(Signature indicate pwdor:,tetWas. ~ in to NS.2-IO I) Date Approved:

Plant (~eneraI Manager'.) Date

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CALVERT CLIFFS NUCLEAR POWERTPLANT EMERGENCY RESPONSE PLAN TABLE OF CONTENTS SECTION PAGE INTRODUCTION I. SITE DESCRIPTION..'.................... ......................... I II.. PURPOSE...................... .................. I I1H. CONCEPT ............................................... 2 IV. EMERGENCY RESPONSE DOCUMENTS ............ I.............................. 3 A. .

Emergency Response Plan ........................... 3 B. EmergencyaResponse Pln Implementation Procedures ............ 4 V. DEFINITIONS .... .............. .......... ...............

VI. ABBREVIATIONSANDACRONYM .L..............

Attachment I21, Emergency: paingZnes ............... 10.................

Attachment 1-2, 10-Mile Ergefcy Planning Zone Bundary.,.,..... i.i

2. EMIRGENCY CONDITIONS:

1. 'CLASSIFICATION SYSTEM fl. UNUSUAL-EVENT .................. ....... 22......................................................

A. Description ....................... 2..........................................

B. Emergency Action Levels .............. 2 2...........................................

III. ALERT .... 2

.AAlL ER T ........ ...... .. . ,.............

.............. * ... ..... ........ ..*..; ....:._...*.... i......

,. , ... 2

'A. Dergen De sci......2 .....

B. Description ActiontL

....Emergency vls.........

.L ...: ............ . ..,...... ..... ..........................

.. . ......... ............. 2 3:

IV. SERAREA EMERGEN.C .

...... .. ...... 3 A. Description. ...

1.~ ~ ~ v ActiOn" 'Levels.

Emergency : " .. -"""

...........* i '........

3...

V GE. nE L EMe ...........

VLSECTRUM A. OFOkDGC ti.............

Description ...~

..... ::.. ... .:,....i.;.................

..... .:i..,. 44 B. Emergency. Ac inivls ... ............ ..... ... 4...

5 VI. SPECTRUM OF POSTULATE ACCIDENTS ....... ...... 4 A. Consequences, o'f Posttlaed Accidnts o5.....I....... ...

I. Radioactive Contamination .............. 5.....

2. Airborne Ra.iactvit ........

3. Radiatio.Mo A g (Extemýrl Radiadtn) .. ...... 6

4. Rtadioaitve W is t inment or Transprtation

, 7

b. LqudRdotieWse.

C. Gae6 Radiibctive W-aste."a...... .... ..

.. 9 Revision41l

TARLE OF CONTENTS .(Cooainued SECTION PAGE

.2. EMERGENCY CONDITIONS (Continued) 5 Fuel Handling incidents ............................................. .0

a. Inside Containment Building ............ ....... ,10

b. Outside Containment Building..,. ......... 11

6. Waterbome Radioactive Release Incidents ............... 13

7. Fires ....................... .......... 14

8. Explosions ............. .......... ... ............... 15

a. Outside Radiologically Controlled.Areas. ........ 15

b. Inside Riol0gically ControlledAreas.... .... %f5

9. Toxic-AtmoshereReease Incidenti...-.... ...,.o.. 15

10. Major esne*i. Ucnrle njuty ta ees ~,1 . ~ 16"

12. Disastex ,.....................

bNatr .... ...... 7 B. Hypothetical Accident Conditions ....... ............. 17 Attachment 2-1, Updated Final Safety Analysis Report (UFSAR)

Chapter 14 SafetyAnalysis: Accident/IncidentClassi1fica8o........18 3., ORGANIZATION.

. OPERATING ORGzANIZATION.................... .............. i I" STANDING REVIEW COMM"ITEES...........

1l1. EMERGENCYORGANIZATI ON ......... ..... .

A. Eme~rgeny DiretoorlRcoveiy Maae . ~ ;3

13. 'iTechnioialSupport Center Manager.....W...A 3 C. General SUPOMIisor-;Nula Plant.Operations . , . .

D. S a nagerti i ....... . ......................

.E Emnergen qyOperatioqs Facility Director, ... ............... A.4 F. operational Support CenterDeco. .. 4 G. Radiation Protecti Director . ...... ... *...."... .... . .4 H. Maintenant Team Leaders and Maintenance Teams ..............

I. Opera"i-.Team Lex'a-"r-and Operatio Teaa . 5-J. 1.nginering iret. ............... ......- ...... 5 K. SafetS:ervices....... .. ...,..

..... O. .1 " . ..... T~oml*.

emo ... ........, brn Rovlion0 41

TABLE OF CONTENTS (Continued)

SECTION PAGE

3. ORGANIZATION (Continued)

Q. Security Coordinator .... ......... v........................ 7 R, Radiologioal Assessment Director ................. ..... .... 7 S. Communicators.......,.................... ........... 8 T. Fitness-For-Duty Tester .............. ........ . ...... .9 U. Telecominunications/Information Technology ............... o... 9 IV. RECOVERY ORGANIZATION,.......... ............................. 9 A. Emergency Director/Recovery Manager (Recovery Phase)..... 9 B. Support Managers and Directors,................. I.............. 10 I. Public Information ........................ 10

2. Admfinistrative. ....................... ..........

3. Telecommunications/Informi ation'Technology.......... 11 C. Emeirgecy *Operaions Faciliy Director (Re y)....... .11 D. Technical.Representatives. .. ...... 1........2........

V.- C.ONTRACTED SERVICES-.......ý.. ...... .... ~

A. contractors... . ... .............

2 B3. Other ............................ ... ..... ............

VI. LOCAL SERVICES .................................... ................ 12 VII. PARTICIPATING GOVERNMENTAL AGENCIES ..... ..... i3 A. State.ofMaryland ........... ............... , -.. , 13 B. Functions and Responsibilities-of Key Ag eies: andOffici~als. .14 C. Planning Zone Support........................................ . 17 D. Support from Federal Agencies......................... . 19 AttacIment 3-1, Management Organization.................. 20 Attachment 3-2, Minimum On-Site Staffnmg:Requiremenýs*.,, ........ 22 Attachmnt: 3-3 Emergeney Organiti on...................:24 Attah.meit 3-5, Center Interfaces- Unusual E ent.and At.......26 iAttachment 3-6, Center Interfaces: Site Area andGeneraldEmgeny.. 27 4, :EMERGENCY MASURE I. RECOGNITION AND CLASSIFI ION. ...... 1 H. NOTIFICATION ....................... . ...............

A. On.;SiWePersonnel ....... ......

B. Of-Sie' Agencies ..........

C . Mess ages ............ . .... . ;.. ...... ......... ...... 2.i...

D. Prompt Public Notification.... ......... 3 3............

II4 AUG TATION. .......................... ............... ...... 4 RevieIln 411

TABLE OFCONTENTS (Continued)

SECTION PAGE

4. EMERGENCY MEASURES (Continued)

IV. ACCIDENT ASSESSMENT"....... ............. . .......................... 4 V. REPAIR AND CORRECTIVE ACTION..........., ........................ 5 VI. PROTECTIVE ACTIONS.- .......... ......... .............. 5 A. Accountability ........... ........................... . .. .......... 5 B. Evacuation ... ý.. ... .a................................................. .. .6 C. Off-Site Recommendations ................. ................. ................ 6 VII. EXPOSURE CONTROL.... ........... ..... .......... 7 VIII. CONTAMINATION CONTROL .. .. .......................... 8 IX. PERSONNEL EMERGENCIES... ...... 8 Attachment 44, Off-Nornal-Condition R!esonse Sequence ............ 9:

Attcmn 4-2, Of-ieAec oiiin1:0 S. ACILIIESAND OIPMQ I AC1JTE~... .C. ... ....

a. EmC rgol R OaF.il. . ,. ,,*................................. 1 C. Tecthical Suppo.enter.... ........ 2

D. Operational Support:C nter . .......... . ........ ;...... ...... 4 E. Joint Information Center ............ ............ ........ 44....

F. Laboratories ,. ........ .. .................. . ........ ..... 6 G.beco nination. 6 H. Mei l....... . .... .........

COMMUNICATIOca ............. ... ......... . .

B. Meteorolog el ............... ...

C.. RaiCologca Montr II F. Field Monitoring ......................... .............. 12 1......

G. Environmental Monitoring . ..... , . .12........

H. Post Am a a g...... *. ...... .......... .12 J t l W 1;.. .tGtCYnI.*,..,, ... ...... 13 V"PRO¶CTWE-CO O,.~. ................... 13 VI. RDOR*CIBRG.... . 13 Reviin4

TABLE OF CONTENTS(Continued)

SECTION PAGE

5. FACILITIES AND EQUIPMENT (Continued)-,

Attachment 5-1, Facility Functional Objectives,......................... 14 Attachment 5-2, Emergency Operations Facility............... w............. 15 Attachment 5-3, Emergency Operations Facilityrand'Joint :

Information Center Location ............................ . 16 Attachment-5-4,:TSC Location Relative to Control Room ....... 4... 17 Attachment5-5,5Characteristics of Technical Support Center vs.

Emergency Faciity...... ....................... I ............ .1.8.. ....

Attachent ::5-6,Public lInformtion Flow,.,.*:....*v;..::i..*::*,*; 19 6,. MAINTAINNG PREPAREDNESS.

T . ......... ................. ..... .............. .........

A. General Orientation . ................................... 2.......................

1 B. Emergency Personnel .................................... ................ !

C. Public ..... ................... ................... 2 D. Emergency. Preparedness Unit ............ .... ........... . 3

11. EXERCISES AND DRILLS .......................... ......... .... ... 3:

WIl. PROGRAM. ESPONSIBILITY .......... ......... 3 Iv. EQUIPMENT INVENTORY AND MAINTENANCE..1..,,...2... 3 V. PROG AMEVIEW AN;DUPDATE..... ..... ...... ......... 4 Vt. REOD...... . . . . . ..... 5

'7. REFERENCES APPENDIX A - LIOUEFIED NATURAL GAS CONTINGENCY

1. DEFINITIONS ....................................

A. Liquefied:Natural Gas .................... .. ........ I.........

B. Mhane............ ...... ............................ ..........

11. POTENTIAL. THREAT..--"............. .......... *.

I11. CONCERNS AND ACTIONS INAN NATURAL GAS M ERGENCY ............. ..... .......

.... . ..... ........ 4 WV. COMMUNICATIONS11 _.

V. NA!TUR-A-LGASR-EFERENCQES.... . . .,~. 5 APPNDI B EMRGNCV RESPQNSE PL.AN Ij! I1fll Revisim'.41

TABLE OF CONTENTS (Continued)

SECTION PAGE APPENDIX C - EVACUATION TIME ESTIMATES .. 1 APPENDIX D -LETTES OFAGREEMmN AttachmeinitD-!, Calvert Volunteer Fire & Rescue Association ........... 2 Attachment-D-2; Memon fromn Site Vice:Presidentassigning. corporate.

authorityto Emergency Diretors ....................................................... 3 Attachment D-3 ,Cal.v6etMemomialHospital Emergency Department Staff Letter of Support.... ........ ............................................................. 4 Attachment D-4, Radiation Emergency Assistance Center/Training Site (REAC/TS) ........................... . 5 Attachment D-5, Department of Energy Brookhaven Area Office dated 2002 - update not required per letter 7 Attahment ,D-6Institutc of Nuclear Power Operations (INPO) dated 208- upda torequired er l.eter ........................ 8 A.tacphaw 7 Delawa!$ ogiec SurVey1 .University of Commuic-Ati- '3' Between Coe C0-4 Poitnt LNGPlant ,ons: ,and CCNPP 10 Attaoc nt D-90, CCPP :Halth.Physics (Radiation Safety)

Guidance and;Assistance for Calvert Metobrial Hospital,....*.............. 13 Attachment.D-10, St. Leonard iFire and kescue (Alternate ERO Assembly) ......... ,. ...... ...... ......................... 14 Attachment D. 11, Solomons Volunteer Rescue and Department (Alternkae ERO assembly loai ion) .................. 15

.APPENDIX E -WM NRCA64 ,CROS,9IIEEC

.eviion .41

CALVERT CLIFFS NUCLEAR POWER PLANT EMERGENCY RESPONSE PLAN INTRODUCTION SITE DESCRIPTION Calvert Cliffs Nuclear Power Plant is a fixed nuclear facility located in Lusby, Maryland. It is owned and operated by Constellation Energy Nuclear Group, LLCý(CENG). The site consists of two units. Each unit includes a.two loop pressurized water reactor. The reactors are designed for a gross electrical output of approximately 910 MWE. Cooling water is supplied by the, Chesapeake Bay. The site contains an Independent Spent Fuel Storage Installation (ISFSI)., The ISFSI is a life-of-plant storage facility for spent nuclear fuel assemblies discharged from Calvert Cliffs Units tand 2.

II. PURPOSE, The Emergency Prepairedne*ss program for the Calvert Cliffs Nuclear Power Plant consists of the Emergency Response Plan, off-siteradiological emergency plans, and procedures for protection of plant personnel and the general public. This program helps 'providedose savings for a spectrum of accidents. Some of these accidents could produce offsite dose in excess of the Environmental Protection Agency's Protective Action Guides. The Calvert Cliffs Emergency Response Plan and Maryland State Radiological Emergency Plan ensure the following are achieved:

A. Effective coordination of activities among response organizations.

B. Early warning and instructions for the population-at-risk.

C. Continuous assessment of on-site and off-site actual or potential consequences.

D. Effective emergency measures implementation.

E. Cun Revision 41

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I1. CONCEPT A. Calvert Cliffs Nuclear Power Plant Emergency Response Plan has been developed to' protect the general public and site personnel from possible consequences of emergency conditions. Combined 'with its implementation procedures and radiological emergency plans of the State and local agencies, the Emergency Response Plan allows for:

1. 'Early emergency condition recognition and classification.

2., Prompt notification of agencies via reliable communication channels and personnel to augment the normal operating personnel.

3. Prompt pre-planned protective actions for protecting the population-at-risk; B. Calvert Cliffs Nuclear Power Plant is staffed with personnel trained to respond to-emergencies. Additionally, written agreements are maintained with federal agencies, private contractors, and State and local agencies that are required by law to provide" assistance to ensure resources can be readily available in as short a time as possible to cope with emergencies and to protect the population-at-risk. The agencies and resources provided are described in:

1. Calvert Cliffs'Nuclear Power Plant Emergency Response Plan

2. Maryland Radiological Emergency Plan, Annex Q.

3. Calvert County, Dorchester County, and St. Mary's County Radiological Emergency Plans and Standard Operating Procedures

4. Virginia, Radiological Emergency Response Plan

5. Delaware, Radiological Emergency Plan

6. District of Columbia, District Response Plan.

Maryland Radiological Emergency Plan, Annex Q, describes State and local agency roles and interfaces for carrying out protective and parallel actions in a 10-mile-radius plume zone and 50-mile-radius ingestion zone from Calvert Cliffs Nuclear Power Plant.

Attachment 1-1, Emergency Planning Zone, and Attachment 1-2, 10-Mile Emergency Revision 41

III. CONCEPT (Continued)

Planning Zone Boundary, shows the geographical area within the plume and ingestion zones.

C. Documents used in developing the Emergency Response Plan and-implementation procedures are listed in Section 7, Calvert Cliffs Nuclear Power Plant Emergency Response Plan References; SIV. EMERGENCY RESPONSE DOCUMENTS A. Emergency Response Plan The Emergency Response Plan ensures that emergency situations, including those involving radiation or radioaivemaeral, handled properly and efficiently. The Emergency Response Plan covers a spectrum of emergencies from minor localized emergencies to majoremergencies involving off-site emergency response. The Emergency Response Plan provides for advance planning required to, develop implementation. methods..The Emergency Response Plan describes:

1. An emergency classification'system used at the-plant and emergency measures to be taken-that are.compatible with those used by Federal, State and county emergency response agenciesand organizations. ,

2. Organizational controdof emergencies by onsite, offsite, and augmentation organizatiois, including identification of normal and emergency operating organizations.

3. Identification of Federal,.State. and county authorities and agencies and other outside organizations that are available for assistance,.including plans and agreements pertaining to participating offsite organizations and agencies.

4. Requirements for ensuring a high degree of emergency preparedness and operational readiness such as through training, drills, reviews, and audits.

Revision 41 C.

[V. EMERGENCY RESPONSE DOCUMENTS (Continued)

5. Information pertaining to onsite and offsite emergency facilities and equipment such as the Emergency Operations Facility, Technical Support Center, Operational Support Center, and Joint Information Center.

6. Figures and tables that display information and data such as organizations, maps, and population distributions.

B. Emergency Response Plan Implementation Procedures Emergency Response Plan Implementation Procedures are used in conjunction with plant operating, chemistry, radiological control, security, and other technicail procedures, as appropriate, to respond to emergency conditions and mitigate accident consequences. These documents are made available to those individuals, facilities, and organizations where immediate use of such instructions would be required during an emergency. These documents provide:

1. Specific criteria called Emergency Action Levelsto assessý classify, upgrade and downgrade emergency situations should the severity increaseor decrease.

2. Specific instructions for emergency organizations including respoisibilities, facilities, equipment, emergency classification, and seeking emergency. assistance used to implement the Emergency Response Plan and support implementation of the State radiological Emergency Response Plan..

3. Specific authorities and responsibilities for emergency response personnel, responsible for assessing emergency, conditions and providing steps to be taken to mitigate the consequences of an accident. .

.4. Specific instructions, to ensure prompt actions, notifications, and communications.

5. A record ofconpleted actions.

6. A mechanism for maintaining emergency preparedness.

ý;ý'. , 1:* Revision 41

IV EMERGENCY RESPONSE DOCUMENTS (Continued)

Emergency Response Plan Implementation Procedures are developed to respond to a variety of accident scenarios. These include minor events up to core melt situations with unplanned radioactive material release to the environment. While the emergency level(s) listed in the procedures is sufficient to cause their implementation, it is not necessary to implement all Emergency Response Plan Implementation Procedures under these conditions. Specific procedures may not be used if the actual emergency does not call for their use. For example: a security threat may not result in plant damage and an unplanned release; therefore, radiological '

monitoring procedures may not be used.

V. DEFINITIONS A. Radiologically Controlled Area (RCA) [Restricted Areal - Any plant area(s) where radiation levels are equal to or greater than 2.0 mrem in. one hour,. OR where a person could receive a Total Effecting Dose Equivalent(TEDE);of 100 mrem in a year, OR removable radioactive contamination exists at levels detectable above background, OR any room which contains radioactive materials inexcess of 10-timesthe quantity of material specified in 10 CFR 20, Appendix C.

B. Emergencv - situation that may result in undue risk to public/site personnel health and safety, or significant damage to plant equipment. Emergency phases::

1. Occurrence - actual physical event with associated alarms,% warning signals, and immediate protective actions provided within the facility.

2. Emergency - actions taken to protect lives and property. These actions are taken by on-site personnel at the time of event. Only equipment and resources immediately available are of value in this phase.

3. Recovery/Restoration - actions are planned, organized, and directed towards recovery from the results of the event. Actions include restoring equipment and condition to original,: oracceptable intermediate state. Offisite equipment and personnel may be used.. -When situation control is established, restoration efforts are abandoned.

Revision 41

V. DEFINITIONS (Continued)

C. Emergency Operations Center (EOC) - designated Stateand local facilities designed and equipped for agency emergency operations coordination and control.

D. Emergency Planning Zones (EPZs)

.' Plume EPZ area, about 10 miles in radius from Calvert Cliffs Nuclear Power Plant centerpoint, for which plume exposure emergency planning considerations have been given to protect people and property.

2. Ingestion EPZ area, about 50 miles in radius from Calvert Cliffs Nuclear Power Plant centerpoint, for which ingestion exposure emergency planning consideration has been given to protect people and property.

E.- Exclusion Boundary - That area of CCNPP site within 1H150:meter radius of either containment as defined in Section 100.3(a) of 10 CFR 100..

F. Ingestion Exposure Pathway - Pathway where principal exposure would be from 9 ingestion of contaminated water or food (e.g,, milk, fresh-vegetables). Potential exposure time could range from hours to months.

G. Off-site - area outside Calvert Cliffs property boundary.

H. On-site - area within Calvert Cliffs property boundary.

I. Plume Exposure Pathway - Pathway where principal exposure source is from:

1. Plume and deposited materials for whole body external gamma radiation exposure.

2. Passing radioactive plume for inhalation exposure. Exposure time could range from hours to days.

J.: Projected Dose.- calculated:or estimated radiological dose thatthe affected population could receive if no protective actions are taken.

7 .:.- ... -9i Revision 41

V. DEFINITIONS (Continued)

K. Projected Dose Commitment - calculated or estimated future dose commitment which could be received by population-at-risk individual(s) from inhalation or ingestion of radioactive material if no protective actions are taken.

L. Property Boundary - outer limits Calvert Cliffs Nuclear Power Plant property.

M. Protective Actions - measures taken to prevent orjminimize a projected dose.

N. Protective Action Guides - projected total effective dose equivalent to individuals in the general population that warrants protective action as described in the Environmental Protection Agency's Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, October 1991 (EPA-400-R-92-00 1).

0. Protective Action Recommendations (PAR) protective actions recommended by Calvert Cliffs Nuclear Power Plant to State and Coufity decision makers to prevent or minimize a projected total effective dose equivalent to individuals in the general.

population. .

P. Radiation Incident - unexpected event, occurrence, or circumstance involving radiation exposure or radioactive contamination requiring a report pursuant to 10CFR20.2203.

Q. Recovery Actions - actions taken after an emergency to restore the plant as nearly as possible to pre-emergency condition.

Revision 41

pW VI. ABBREVIATIONS & ACRONYMS ALARA As Low As Reasonably Achievable ANSI American National Standards Institute AOP Abnormal Operating Procedures.

CCNPP Calvert Cliffs Nuclear Power Plant CENG Constellation Energy Nuclear Group CFR Code of Federal Regulations-DHS Department of Homeland Security DOE Department of Energy DOT Department of Transportation EAL Emergency Action Level EDRM Emergency Director/Recovery Manager EOC Emergency Operations Center EOF Emergency Operations Facility EOP Emergency Operating.Procedures EPA Environmental Protection Agency EPU Emergency Preparedness Unit EPZ Emergency Planning Zone ERP Emergency Response Plan ERPIP Emergency Response Plan Implementation Procedure EWP Emergency Work Permit FEMA Federal Emergency Management Agency FRMAP Federal Radiological Monitoring and Assessment Program HEW Health Education and Welfare HP Health Physics HSM Horizontal Storage Module I& E Inspection & Enforcement (Branch of NRC)

INPO Institute of Nuclear Power Operations Revision 41

VI. ABBREVIATIONS & ACRONYMS (Continued)

ISFSI Independent Spent Fuel Storage Installation JIC Joint Information Center LNG Liquefied Natural Gas LOCA Loss of Coolant Accident MDE Maryland Departmentof the Environment MEMA Maryland Emergency Management Agency NFPA National Fire Prevention Association.

NRC Nuclear Regulatory Commission" NRR Nuclear Reactor Regulation (Branch of NRC)

NSRB Nuclear Safety ReviewBoard..

01 Operating Instructions OP Operating Procedures.

OSC. Operational Support Center.

PAG Protective Action Guidelines PAR Protective Action Recommendation "

PAXNAS Patuxent River Naval Air'Station:

PORC Plant Operation'Review Commiitee

PPRP Power*Plant Research Program

'RAD Radiological Assessment Director REAC/TS Radiation Emergency Assistance Center/Training site.*

RMS Radiation Monitoring System RPD Radiation Protection Director SCBA Self-Contained Breathing Apparatus TSC Technical:Support Center U-I Unit I U-2 Unit 2 USCG United States Coast Guard.,

UFSAR Updated Final Safety Analysis Report Revision 41

ATTACHMENT 1-,l EMERGENCY PLANNING ZONE MMA TL AND 7,HARFORDO N" FREDERICK CECI CASTL ICICARROLLI BALTIMOREE S .,OWARO(

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PlumeZo-L 0 Miles H IgsinZone ;.50 Mrles .9.

Revision 41

ATTACHMENT 1-2 10-MILE EMERGENCY PLANNING ZONE BOUNDARY and'

.2 r

SCALVERT CLIFFS III LE PLAINT mum

.Revision 41

CALVERT CLIFFS NUCLEAR POWER PLANT EMERGENCY RESPONSE PLAN EMERGENCY CONDITIONS CLASSIFICATION SYSTEM Emergency classifications are:"

I. Unusual Event

2. Alert

3. . Site Area Emergency.

4. General Emergency Each, classification requires immediate action to classify the accident, notify off-site agencies and support groups, and mobilize emergency organizations as required to cope with the emergency.

Accidents are classified and reclassified (more and less severe) as situations warrant.

Unusual Event and Alert-classifications provide early notification of minor events and ensure timely response for more severe emergencies. Assembly of Calvert Cliffs Emergency Response Organization is initiated for an Alert classification. Full mobilization of emergency personnel and organizations is initiated for Site Area and General Emergency.

Each emergency classification is characterized by Emergency Action Levels consisting of specific plant parameters or conditions.T The Emergency Action Level scheme is consistent with R.G. 1.101, Emergency Planning and Preparedness for Nuclear Power Reactors, Revision 4, July, 2003, as modified by CCNPP, Inc.,,submittals to the NRC. Satisyinmg Emergency Action Level criteria other than a General Emergency does not necessitate immediate protective action implementation; it ensures time is available to confirm in-plant readings by implementing assessment measures on-site and off-site.:-

Classification philosophy is to declare the highest class emergency for Emergency Action Levels met or exceeded. For example, a Site Area Emergency would be declared immediately, if the Emergency Action Level is met or exceeded,. lower classes Will not be declared first.

Revision'41

II. UNUSUAL EVENT A. Description 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. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.

B. Emergency Action Levels Initiating conditions establishedas Emergency Action Levels for determining an Unusual Event classification are listed in the Emergency Response Plan Implementation Procedures. An Unusual Event is declared any time that respective Emergency Action Levels are-metor exceeded...Aii min revents areanalyzed in light of their potential for' degrading the level'of plant safety.-

III ALERT A. Description Events are in process or have occurred which involve an actual or potential substantial degradation of the. eveI of safety of the plant or a security event ihat involves probable life threatening risk to site personnel or damage to site eequipment because of hostile action. Any releases are expected to be limited to, small fractions.of the EPA Protective Guideline exposurelevels.

.. .,Action.

Alert classiicaition ensures personniel are available to: '

1. Respond to worsening situations. .

2. Perform confirmatory radiation monitoring.

3. Provide off-site authorities with information.

B. Emergency Action Levels Initiating conditions established as Emergency-Action Levels:for. determining an Alert emergency classification are listed in the Emergency Response Plan Implementation Procedures.

Revision 41

I.

III. ALERT (Continued)

B. Emergency Action Levels (Continued)

An Alert is declared any time that respective Emergency Action Levels are met or exceeded..,

IV. SITE AREA EMERGENCY A. Description Events are in process or have occurred which involve an, actual or likely major failures of plant functions needed for protection of the publicor hostile action that'result in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) prevents effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure~levels beyond the site boundary.

Site Area Emergency classificationensures:

1. Response centers are manned.

2. Survey teams are dispatched.

3. Personnel required for near site evacuation ae, at their duty stations.

4. The public is-updated through off-site~authorities. -

B. Emergency Action Levels Initiating conditions established as Emergency Action Levels for determining Site Area EnEmergency classification, are listed in the Emergency Response Plan Implementation Procedures.,

A Site Area Emergency is declared any time that respective Emergency Action Levels are met or exceeded.

Revision 41

V. GENERAL EMERGENCY A. 'Description 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.

General Emergency classification ensures:

1. Initiation of predetermined warning and protective actions for ithe 'public.

2. Continuous plant information and off-site measurement assessment.

3. Initiation of additional measures as indicated by actual orpotential releases.

4. Consultation with off-site authorities.

5. Public updates through.off-site authorities..,,

B. Emergency Action Levels Initiating conditions established as Emergency Action Levels for determining General Emergency are listed inEmergency Response Plan Implementation Procedures. A General Emergency is declared-,any time that a respective Emergency Action Level is met or exceeded.

VI. SPECTRUM OF POSTULATED ACCIDENTS The Emergency ResponsePlan considerS emergency consequences ranging from minor.

emergencies involving small portions of the plant to extremely unlikely events haying potential for radioactivity release affecting the general public. Emergencies not unique to.nuclear power piýnts are consided. Provisions'must be made for dealing witihthese emergencies as they could become complicated by radiological considerations.

Revision 41

Vt. SPECTRUM OF POSTULATED ACCIDENTS (Continued)

Accidents hypothesized for Calvert Cliffs Nuclear Power Plant are encompassed by the emergency classifications.

"On-site," for this section only, is that area of Calvert Cliffs Nuclear Power-Plant site within an 1150 meter radiuscif either Containment; defined in Section 1003(a) of I0CFRI00 as the exclusion area.

A. Consequences of Postulated Accidents

1. Radioactive Contamination (Reference 55, UFSAR, Section 11.3, Rev. 38)

Personnel Radiation safety procedures and controls are.established to ensure radioactive contamination-levels within plant radiologically controlled areas are maintained as low as practical and contamination is notspread beyond radiologically controlled area boundaries..

To preclude contamination spread, personnel. leaving radiologically controlled areas must remove anti-contamination clothing and be monitored for radioactive contamination. Radiological control and monitoring.systems are designed to prevent people from leaving siteý with detectable radioactive contamination.

During emergencies personnel monitoring takes place.at controlled area exits.

Back-up monitoring may be performed at points such as the Nuclear Security Facility and/or perimeter control points.' *.

2. Airborne Radioactivity (Reference 55, UFSAR, Section. 11.1.2.2.3, Rev. 34)

Incidents involving potential airborne radioactivity range from small incidents affecting localized in-plant areas (such as a laboratory sample spill of gaseous or.

volatile radioactivity), to major radiological incidents resulting in airborne radioactive material releases greater than Technical Specification limits. The latter may affect the general public.

Revision 41

VI. SPECTRUM OF POSTULATED ACCIDENTS (Continued)

2. Airborne Radioactivity (Continued)

Off-site consequence expected from a small release outside Containment (laboratory spills; continuous uncontrolled leakage from pump seals or valve stems; releases due to credible size piping failures) is within the Offsite Dose.

Calculation Manual limits. In-plant consequences of such incidents may involve implementation of radiological controls to protect personnel from airborne and surface radioactive contamination. Radiation safety procedures are followed to ensure contamination does not spread to other plant areas. When warranted, contamination control measures are implemented for drinking water and food.

The Radiation Monitoring System, a comprehensive process and area radiation monitoring system, detects Containment structure and Auxiliary Building high airborne'activity releases and alarms in the Control Room. Shift personnel investigate high radiation alarms and .take-actiori to control the radioactivity source and its environmental release pathway.

-3. Radiation Monitoring (External Radiation) (Reference 55, UFSAR, section 11 -.2.3, Rev. 36)

Areas where.external radiation hazards can adversely affect on-site or off-site individuals are monitored by Radiation Monitoring System area monitors or by portable detection equipment through routine plant surveillance.

Unexplained radiation level indications initiate investigations to determine the radiation source. Established radiation safety practices protect in-plant personnel from high radiation fields.,

.':':"*:":i"' / 'i:".*...;;- z*.:.* **...**!9: .

Revision 41

VI. SPECTRUM OF POSTULATED ACCIDENTS (Continued)

4. Radioactive Waste Containment or Transportation Disposal Incidents

a. Solid Radioactive Wastes and Materials (Reference 55, UFSAR, Section

11. 1.2.3 through 11.1.2.7, Rev. 34)

Solid radioactive wastes and materials are-packaged and shipped according to Department of Transportation regulations. Shipments are classified:

I) Low specific activity (LSA)/surface contaminated objects (SCO) material.

2) Type A quantities (e.g-, typical dry active waste (DAW), resins).

3) Type B items such as higher radioactivityconcentrations on filters and higher activity dewatered ion exchange resins.

4) Highway Route Controlled (e.g., in-core instrumentation detectors).

Solid waste is, packaged and stored inside controlled areas which are designed to handle radioactive material.

The most serious solid radioactive waste handling incident on-site is a Spent Resin Metering Tank rupture. This tank is located in a shielded room in the solid waste handling area. Resin released from a tank rupture will not affect on-site personnel except during clean-up operations. Radiation safety procedures would be used to control radiation exposures during clean-up phases.

No off-site consequenceswillresult from this or other in-plant solid radioactive waste inciddnts.

Revision 41

VI. SPECTRUM OF POSTULATED ACCIDENTS (Continued)

a. Solid Radioactive Wastes and Materials (Continued)

Radioactive waste and material is packaged in containers that meet Department of Transportation Requirements (49 CFR), and if required, the packages are approved by the NRC (IOCFR 71). The containers minimize consequences of off-site vehicle accidents involving solid radioactive waste.

b. Liquid Radioactive Wastes (Reference 55, UFSAR, Section 11.1.2.1, Rev. 34)

Liquid radioactive waste handling, processing, and storage components are located within the Auxiliary Building. Liquids spilled from leaks in Waste Processing System components are collected in Auxiliary Building drains and are routed to the Miscellaneous Waste Processing System receiver tank. I The most serious liquid waste incident having environmental consequences is inadvertent Reactor Coolant Liquid Waste Receiver Tank discharge. Waste Processing System design prevents this by automatic closure of redundant isolationvalves. Radiation monitors upstream of the'discharge valvesmonitor for radioactivity in excess of allowable limits. Monitor alarms actuate isolation valves closure to stop waste discharge to the environment.

The liquid waste discharge radiaiion motiitor setpoint is established so that the concentration of radioactive material release to unrestricted areas in liquid effluents does not exceed the limits of the Offsite Dose Calculation Manual. The setpointis established as described in the Offsite Dose Calculation Manual. Radioactivity released from this incident before isolation valves closure or from releases just below the monitor setpoint will not result in significant environmental consequences. .

Revision 41

VI. SPECTRUM OF POSTULATED ACCIDENTS (Continued) -

b.. Liquid Radioactive Wastes (Continued)

No radiological consequences affecting on-site personnel from inadvertent liquid waste tank discharge are expected. Other in-plant liquid radioactive waste incidents (pipe leaks, spills) are detected by the Radiation Monitoring System or by routine plant surveillance. These incidents would create local contamination problems. Radiation Safety Procedures would control radiation exposures during clean-up and repair.

c. Gaseous Radioactive Waste (Reference 55, UFSAR, Section 11.1.2.2, Rev. 34)

Gaseous-radioactive, waste collection, handling, and storage components are located within the Auxiliary Building. Waste Gas System leakage enters the Auxiliary Building ventilation. system past a gaseous radiation monitor and is discharged to the plant vent. This plant vent also has a radiation monitor. Any significant Waste Gas System leakage is detectable by the Radiation Monitoring System.

The most serious gaseous waste incident affecting the offsite environment is: unexpected, uncontrolled, release of radioactive xenon and krypton, fission gases release from a Waste Gas decay tank rupture.

Reference 55, UFSAR Section 11.1.2.2.3, specifies that using conservative assumptions (quantity of gas and meteorology) whole body immersion dose at the nearest exclusion zone boundary is 0.182 rem.

This incident does not represent a severe public health and safety hazard.

SOn-site persoinnel aire protected from radiological consequences of Waste Gas decay tank rupture or sall Waste Gas system leaks by the Auxiliary Building design(ineluding ventilation system) and by plant radiation safety practices and proicdures.

Revision441

Vt. SPECTRUM OF POSTULATED ACCIDENTS (Continued)

5. Fuel HandlingIncidents (Reference 55, UFSAR, Section 14.18.3.1, Rev. 41 and Reference 50, ISFSI USAR, Section 8.2.8, Rev. 18)

a. Inside Containment Building Fuel Assembly damage from mishandling is minimized by equipment design, detailed operating procedures, and operator training. Should a fuel assembly be dropped or otherwise damaged during handling, a Containment radioactive release could occur. "Containment ventilation exhaustfair is monitored before release to atmosphere. Monitor indication and alarms for increased activity level cause the affected area to be evacuated.

Activity release through the Containment Purge System is prevented by automatic Containment supply and exhaust fans damper closure.

Equipment hatch is closed and personnel hatches continuously manned during: fuel handling operations.

Spent fuel handling is done under water. A significant portion of radioactivity released from ruptured fuel rods would be retained in the refueling water rather than being released as airborne radioactivity.

Refueling machine safety features and off-site consequences of a postulated incident involving rupture of 176 fuel rods in one fuel '

assembly (contained within Containment structures) due to dropping are presented in Reference 55, Section 14.18.3.1. Analysis indicates that because both doors of the containment personnel air lock may be open, all activity released is assumed to be unfiltered. The containment air voiume is assumed to be released over a two hour time period. The 0-2 hour dose at the exclusion boundary will not exceed 0.457 rem whole bodyand 14.06 rem thyroid is presented. in Reference 55, Table 14.18-2.

Although the failure of 176 fuel rods upon dropping a fuel assembly has been assumed, it is expected that no fuel rods would fail.

Revision 41

VI. SPECTRUM OF POSTULATED ACCIDENTS (Continued)

5. Fuel Handling Incidents (Continued)

b. Outside Containment Building

1) AUXILIARY BUILDING - Equipment provided in the Spent Fuel Pool area is not identical to equipment in the Containment refueling pool area, however, similar safety related design criteria are applied. The Spent Fuel Pool area ventilation system is equipped with charcoal filter units assumed to be 90 percent efficient for inorganic iodine. A release from the Auxiliary

" Building does notconstitute a significant off-site hazard.

Radioactivity released from the rupture of 176 fuel rods of a dropped fuel assembly outside Containment is calculated to give 0-2hour doses to individuals located at the exclusion boundary of 0.157 rem whole body dose and 3.71 rem thyroid dose as presented in Reference 55, Table 14.18-2.

Reference 55, Section 14.18, discusses fuel handling incidents Within the AuxiliaryBuilding. Plant safety analysis uses

.conservative assumptions for activity released from damaged fuel rods, the decontamination achieved by spent fuel water, the charcoal filter absorption efficiency for iodine, and the atmospheric dispersion factor. The most severe incident analyzed is therelease of activity from a complete fuel assembly (176 damaged fuelrods). This conservative approach results in a calculated 0-2 hour d6se at the exclusion boundary of 0.157 rem Whole bodý and 3.71'rem:thyroid. It is concluded that this incident does not have significant off-site consequences.

Revision 41

VI. SPECTRUM OF POSTULATED ACCIDENTS (Continued)

I) AUXILIARY BUILDING (Continued)

On-site consequences of postulated fuel handling incidents inside or outside Containment require immediate evacuation of affected plant areas. The incident clean-up phase requires decontamination of surfaces and fuel pool water. This is accomplished according to established plant radiation safety practices.

2) DRY FUEL STORAGE - Radioactivity release from~fuel assembly damage associated with the Independent Spent Fuel StorageInstallation is minimized by design factors described in Ref. 50, Updated Safety Analysis Report for.the Independent Spent. Fuel Storage. Installation.

The Independent Spent Fuel Storage Installation system consists of a Dry Shielded Cariister, containing up to 32 fuel assemblies.

The Dry Shielded Canister is transported inside a special shielded.Transfer Cask to a concrete Horizontal Storage Module.

The Horizontal Storage Module is located at the Independent Spent Fuel Storage Installation protected area. During fuel loading the Transfer Cask and Dry Shielded Canister are placed into the Stent Fuel Pool., Fuel damage during loading would be consistent with Section VI.A.5.b. 1. of the Emergency Response Plan. After the, fuel isloaded a shield plug is installed and the TransfCask assembl is moved to the Cask Washdown Pit.

There it is dewatered, backfilled with helium and double seal welded... Once seal welded, there are no credible accidents which will breach a Dry Shielded Canister to allow a possible leakage path. The Transfer Cask is placed on a trailer or on the self-propelled horizontal cask transporter and transported to the Independent Spent Fuel Storage Installation to be positioned in a Horizontal Storage Module.

Revision 41

VI. SPECTRUM OF POSTULATED ACCIDENTS (Continued)

2) DRY FUEL STORAGE (Continued)

The Horizontal Storage Module has all passive cooling components and is surrounded by a protected area. The Independent Spent Fuel Storage Installation protected area is monitored by dosimetry around the fence. During fuel transfer operations from the Spent Fuel Pool to the Horizontal Storage Module, the maximum expected fuel assembly temperature will be 732"F. Maximum allowable is 1,058°F. During storage in the Horizontal Storage Module, maximum fuel temperature will be 618 0F or less. These temperature maximums ensure no fuel cladding damage. Reference 50,; SAR for ISFSI, Section 8, describes the accident analysis for all conditions. No offsite doses will occur, under any credible accident with the exception of Dry Shielded Canister leakage. Reference 50, SAR for ISFSI, Section 8.2.8, assumes thatfor this accident that all fuel rods are ruptured in all 32, fuel assemblies, with concurrent Dry Shielded Canister leakage. This accident results in 30% of all fission gases being instantaneously released to the atmosphere and a maximum controlled area boundary whole body dose of 0.0001 rem and a skin dose of .0178 rem.

6. Waterborne. Radioactive Release Incidents

'In-plat incidents other than liquid iadioactive waste.could result in radioactive material release to the Chesapeake Bay. The most serious incident of this type is*an uncontrolled water loss from a 420,000 gallon RefuelingWaiter Tanlk Unit 2 Refueling Water Tank leakage drains directly to the shore through storm drains. Undiluted leakage could douse an individual standing in the outfall.

Revision 4 1

0-VI. SPECTRUM OF POSTULATED ACCIDENTS (Continued)

6. Waterborne Radioactive Release Incidents (Continued)

Assuming a maximum 0.1 uCi/cm 3 activity in the Refueling Water Tank and a 1,000 gal/min., leak rate, radioactive concentration in the water discharge would be 0.1 uCi/cm 3 . An individual deluged directly in this concentration for one hour will receive a skin dose,of <130 mrem. It is concluded this release incident would require exclusion of swimmers and boat operators from the area of the discharge. Operators are alerted to Refueling Water Tank leakage by level alarms on the tank.

7. Fires Fireresistant'materials are used in plant design and construction to the "fullest extent practicable. An extensive fire detection and protection system is provided (described in Reference 55, Section 9.9) to minimize the extent of in-plant fires.

In-plant fires are combated by Operations personnel with assistance as necessary. from others. Fires occurring within radiologically controlled areas involve immediate efforts to prevent airborne contamination spread. Other than the potential for radiation contamination or exposure, fire consequences at Calvet Cliffs Nuclear Power Plant are the same as any power plant (e.g., smoke, heat, equipment damage). Immediate and follow-up measures are taken to protect firefighting personnel according to Refe&ence 37. These measures incud euse of protective clothing, respiratory protective devices, land engineering controls (e.g., ventilation control).

.Radiation Moitor~in System andin-plant portable radiation monitors alert plant staff to. the presence of airborne radioactivity that could present a hazard to firefighting personnel or personnel outside the site boundary. Indication of high activity causes dispatch of survey teams in areas do'nind of the fire. Prtectivei measures are implemented based on monitoring results.

Revision 41

VI. SPECTRUM OF POSTULATED ACCIDENTS (Continued) 8'. Explosions

a. Outside Radiologically Controlled Areas Explosion potential outside radiologically controlled areas is associated with equipment containing volatile liquids or gases.

In-plant consequences of explosions outside radiologically controlled areas could be severe regarding equipment damage and personnel injury. It is unlikely there would be off-site consequences for such incidents because explosions are generally localized. Seismic and missile protection design criteria used for controlled areas minimizes the risk to systems capable of producing radioactive releases.

b. Inside Radiologically Controlled Areas Explosion potential. inside radiologically controlled areas is primarily associated with hydrogen gas for Reactor Coolant System chemistry control. Hydrogen gas is present in chemical and volume control equipment vapor spaces and in liquid and gaseous Radioactive Waste Processing systems.

Explosion possibility is minimized by design by preventing accumulation of explosive a'ir-hydrogen mixtures and by continuous monitoring of vessel gas composition. The most severe off-site consequences are those associated with waste gas dec tank rupture.

9. Toxic'Atmosphere Release Incident No toxic gases (i.e., chlorine gas) are stored or used at CCNPP.

Revision 41

VI. SPECTRUM OF POSTULATED ACCIDENTS (Continued),

10. Major Uncontrolled Steam Release (Reference 55, UFSAR, Section 14.14, Rev. 37)

Uncontrolled steam release incidents are analyzed for core safety analysis in Reference 55, Section 14.14. The analysis concludes that little or no coreldamage will occur (conservative assumptions used). A major steam line rupture with no previous primary to secondary leakage

will not have on-site or off-site radiological consequences. The most severe incident "nalyzed is a 1.0 square foot steam line break between Containment and the main steam isolation valve with a loss of AC power. Parametric studies in break size demonstrate that 0.75 square feet breaks rut in a maximum number of fuel failures. The resultant iadi6activity release to atmosphere is calculated to produce exposures to individuals at the site boundary of< 0.2 rem whole body dose and < 5 rem thyroid dose (Reference 55, Section 14.14.4.3.b.). Major steam line breaks inside Containment'will produce essentially no off-site consequences., Steam and associated radioactivity will be retained within the structure, On-site personnel are protected from radiological consequences by following plant radiation safety procedures; i . Personnel Injury.

Personnel injury involving radioactive contamination is initially treated in the controlled area First Aid Room located in the Auxiliary Building.

Prompt attention is given to life endangering injuries in preference to decontamination.. All reasonable efforts are made to decontaminate injuries to no detectable activity above background. If decontamination is.impossible the pat4ient is cove*ed (unless contraindicated, i.e., causing injury insult), to avoid contamination spread until medical aid is obtained or the patient is hospitalized. Auk Revision 41

VI. SPECTRUM OF POSTULATED ACCIDENTS (Continued)

II. Personnel Injury (Continued)

Medical treatment beyond first aid, (physician services or hospitalization) are determined by the extent and nature of injuries in consultation with practicing physicians.

12. Natural Disasters Natural phenomena are discussed in detail in Reference 55, Section 2.3 and 2.6.

B. Hypothetical Accident Classification Events hypothesized in Calvert Cliffs Nuclear Power Plant Updated Final Safety Analysis Report, Reference 55, Chapter 14, fall into one of the four emergency classifications. Attachment 2-1, UFSAR Chapter 14 Safety Analysis: Accident/Incident Classification, lists these and other events and their likely emergency classification.

Some accidents may not result in as high a class as noted in Attachment 2-1. Equipment assumed to be operable in the Chapter 14 analysis are assumed to operate for this evaluation.

The Updated Safety Analysis Report for the Independent Spent Fuel Storage Installation (Reference 50) lists hypothesized events associated with ISFSI fuel handling events. No non-security related event will result in an emergency classification higher than Unusual Event.

Revision 41

P,' ge*.' 1',4.:df 22.'.

C ATTACHMENT 2-1 UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR) CHAPTER 14 SAFETY ANALYSIS: ACCIDENT/INCIDENT CLASSIFICATION Page 1 of 5 UFSAR CHAPTER 14 OFF-SITE DOSE PROBABLE'EAL BASED ACCIDENT CONSEQUENCES ADDRESSED BY INITIATINGCONDITION COMMENT(S)

(0-2 Hours) REACHED 14,2 CONTROL ELEMENT None Shown 10 CFR 50,72 N/A Unplanned reactor trip WITHDRAWAL EVENT 14.3 BORON DILUTION None Shown Equipment Failure A.U.1.1.1. Inadvertent Criticality The operator has sufficient time EVENT to mitigate the incident prior to

"__going critical.

14.4 EXCESS LOAD EVENT None Shown Fission Barrier H.A.5.1.2 Any loss or potential Declaration is based on loss of fuel cladding or RCS uncontrolled RCS cooldown and

.... _ exceeding P-T limit.

14.5 LOSS OF LOAD EVENT None Shown Equipment Failure H.A. 1.1.1 Failure of reactor At worst case, failure of protection system instrumentation automatic trip requires manual

. "to complete or initiate an trip based on EOP-0.

-*automatic reactor scram once a Reactor Protection System setpoint has been exceeded and manual scram was successful 14.6 LOSS OF FEEDWATER None Shown 10 CFR 50.72 N/A Unplanned reactor trip.

EVENT __....__

14.7 EXCESS FEEDWATER None Shown 10 CFR 50.72 N/A Unplanned reactor trip.

HEAT REMOVAL EVENT 14.8 RCS None Shown Fission Barrier H.A.5.1.2 Any loss or potential Small break LOCA which is "DEPRESSURIZATION *"loss of fuel cladding or RCS addressed byCoolant Leakage EALs for loss or potential loss of RCS barrier.

14.9 LOSS OF COOLANT None Shown. Electrical H.U.2. 1.1 Loss of all offsite This incident stems from loss of FLOW EVENT power to vital buses for greater off-site power.

__ _...._ _than

_-__ _ __ _....__ _ __"_....._ 15 minutes- _ _ _ _

14.10 LOSS OF 0.04 rem thyroid Electrical H.U.2.1.1 Loss of all offsite I NONEMERGENCY AC 0.0006 rem whole body Radioactivity Release power to vital buses for greater 44 POWER -than 15 minutes Revision 41

ATTACHMENT 2-1 UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR) CHAPTER 14 SAFETY ANALYSIS: ACCIDENT/INCIDENT CLASSIFICATION.

Page 2 of 5 UFSAR CHAPTER 14 OFF-SITE DOSE PROBABLE EAL BASED ACCIDENT CONSEQUENCES ADDRESSED BY INITIATING CONDITION COMMENT(S)

'_ __ _ __ _(0-2 Hours) REACHED 14.11 CONTROL ELEMENT None Shown 10 CFR 50.72 N/A Unplanned reactor trip.

ASSMEBLY DROP EVENT _ _."__ __-

14.12 ASYMMvETRIC STEAM None Shown 10 CFR 50.72 N/A Unplanned reactor trip.

-GENERATOR EVENT .... __

14.25 EXCESSIVE None Shown N/A N/A This can be mitigated by CHARGING EVENT operator, There is no effect on power level.

14.13 CONTROL ELEMENT < 50.0 rem thyroid Fission Barrier A.G.3.2.5 Offsite dose resulting Declaration is based on the

.ASSEMBLYEJECTION < 1.5 rem whole body Radioactivity Release from an actual or imminent breaching of the RCS pressure

'EVNT release of gaseous radioactivity boundary and escalation to exceeds. 1000mR TEDE or General Emergency based on 5000mR thyroid CDE for the prolonged release.

actual projection duration of the release using actual meteorology H.S.5.1.3 Loss or potential loss of any two barriers 14.14 'STEAM LINE BREAK < 5 rem thyroid Radioactivity Release H.A.5.1.2 Any loss or potential Declaration is, based on E.. <u.2 rem whole body

_VN,_-hl o iso nBarrier Fission are loss offel cladding or RCS ntrle RCS exuncoed S cooldown and limit.

.EquipmentFailure"" . A.G.312.5 Offsite dose resulting exceeding P-T from an actual or imminent release of gaseous radioactivity Electrical*exceeds.1000m.LR TEDE or 50OOmR thyroid CDE for. the actual projection duration of the

_.. _ _ __-__ _.__._..._,__........ ___.__ , release using actual meteorology 44 Revision 41

ATTACHMENT 2-1 UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR) CHAPTER 14 SAFETY ANALYSIS: ACCIDENT/INCIDENT CLASSIFICATION Page 3 of 5 UFSAR CHAPTER 14 OFF-SITE DOSE PROBABLE EAL BASED ACCIDENT CONSEQUENCES ADDRESSED BY INITIATING CONDITION COMMENT(S)

(0-2 Hours) REACHED H.A,5.1.2 Any loss or potential loss of EALs address key concerns of SG 14.15 STEAM GENERATOR 22 rem thyroid Radioactivity Release fuel cladding or RCS Tube Rupture and its results. From TUBE RUPTURE 0.66 rem whole body Fission Barrier H.S.5.1.3 Loss or potential loss of any EOP-6 and EAL basis, the most EVENT two barriers likely declaration is Alert based on A.G.3.2.5 Offsite dose resulting from potential loss of RCS barrier.

an actual or imminent release of Escalation to General Emergency is gaseous radioactivity exceeds 1000mR based on prdlonged release.

TEDE or 5000mR thyroid CDE for the actual projection duration of the release using actual meteorology 14.16 SEIZED ROTOR EVENT. < 12.0 rem thyroid Radioactivity Release A.U.1.2.1 Fuel Cladding Degradation Effect of seized rotor is damage to

< 0.2 rem whole body Fission Barrier A.G.3.2.5 Offsite dose resulting from 5% fuel pins.

an actual or imminent release of gaseous radioactivity exceeds 1000mR TEDE or 5000mR thyroid CDE for the actual projection duration of the release using actual meteorology 14.17 LOSS OF COOLANT Expected fuel clad rupture Radioactivity Release H.S.5.1.3 Loss or potential loss of any Loss/Potential Loss of Fuel Clad ACCIDENT Fission Barrier two barriers Barrier and RCS Barrier (Temperature) 14.18 FUEL HANDLING 14.06 rem thyroid Radioactivity Release A.U.3.3.1 Unexpected rise in plant INCIDENT 0.457 rem Whole body Equipment Failure radiation A.S.3.2.4 Offsite dose resulting from an actual or imminent release of gaseous radioactivity exceeds 100mR TEDE or 500 mR thyroid CDE for the actual or projected duration of the release 14.19 TURBINE GENERATOR None Shown Other Hazards'.. ' H.U.4.2.1 Natural and destructive H.U.4.2.1 addresses turbine failure OVERSPEED INCIDENT . . . phenomena affecting the Protected with observable casing dama&#. If

'Area (turbine) missiles generated affect safe H.A.4.2.2 Natural and destructive shutdown, escalation to AleJs via phenomena affecting the Vital Area H.A.4.2.2, Destructive Phencoena

__.. _ ___, ___ ___.... ........._ _: .(turbine) - .Affecting Safe Shutdown.

Revision 41

21 1of:22 ATTACHMENT 2-1 UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR) CHAPTER 14 SAFETY ANALYSIS: ACCIDENT/INCIDENT CLASSIFICATION,"

Page 4 of 5 USFAR CHAPTER 14 OFF-SITE DOSE PROBABLE EAL BASED ACCIDENT CONSEQUENCES ADDRESSED BY INITIATING CONDITION COMMENT(S)

(0-2 Hours) REACHED 14.20 CONTAINMENT None Shown Fission Barrier H.S.5.1.3 Loss or potential loss Based UFSAR Analysis of RESPONSE of any two barriers containment response to DBA, containment operating within design limits results in a Site Area Emergency as highest

.__emergency class.

14.21 HYDROGEN This postulate accident was ACCUMULATION IN removed from the FSAR by CONTAINMENT -- license amendment 262/239 14.22 WASTE GAS INCIDENT 0.464 rem whole body Radioactivity Release A.S.3.2.4 Offsite dose resulting from an actual or imminent release of gaseous radioactivity exceeds 100mR TEDE or 500 nmR thyroid CDE for the actual or projected duration of the release 14.23 WASTE PROCESSING 0.430 rem thyroid Radioactivity Release A.U.3.1.*1 Any unplanned release If a sustained dose does not SYSTEM INCIDENT 0.0016 rem whole body of gaseous or liquid radioactivity occur, this incident is reportable to the environment that exceeds under'10 CFR 50.72. Emergency two timesthe radiological declaration is based on predicted effluent technical specifications maximum dose due to this for 60 minutes longer incident exceeding the threshold of 0.1 mrem whole body in one hour.

14,24 MAXIMUM 118 rem thyroid Fission Barrier H.G.5.1.4 Loss of any two Escalation to General Emergency HYPOTHETICAL 10.6 rem whole body Radioactivity Release barriers with a loss or potential is based on exceeding 20% clad ACCIDENT ....... _ __...._ _ _ __"_ loss of a~third damage.

44 Revision 41 A

S ATTACHMENT 2-1

'of 22!!

UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR) CHAPTER 14 SAFETY ANALYSIS: ACCIDENT/INCIDENT CLASSIFICATION Page 5 of 5 USFAR CHAPTER 14 OFF-SITE DOSE PROBABLE EAL BASED ACCIDENT CONSEQUENCES ADDRESSED BY INITIATING CONDITION COMMENT(S)

(0-2 Hours) REACHED 14.26 FEEDLINE BREAK 2.2 rem thyroid Fission Barrier A.A.7.1.2 Emergency Director EVENT < 0.1 rem whole body Equipment Failure judgment Other Hazards H.S.S.1.3 Loss or potential loss of any two barriers A.S.3.2.4 Offsite dose resulting from an actual or imminent release of gaseous radioactivity exceeds 100mR TEDE or 500 mR thyroid CDE for the actual or projected duration of the release 44 1' p Revision 41

RGNCY ESf0_9 ~2~& -

CALVERT CLIFFS NUCLEAR POWER PLANT EMERGENCY RESPONSE PLAN:

ORGANIZATION' I. OPERATING ORGANIZATION The first line of control of any emergency at Calvert Cliffs Nuclear Power Plant lies with the normal shift personnel on duty at such time as an remergency situation:Ishould occur. Assistance is available within one hour from other plant staff and operating personnel. Additional assistance is available from Constellation Energy, Federal, and State agencies and contractor personinel.

Corporate Headquarters supports the ERO in the following functional'area: BGE Customer Care.

Customer Care provides a fully staffed call in center 24/7. and is able to field rumor control issues while providing feedback to the Joint Information Center representatives. Additionally, Headquarters aligned personnel assigned to CCNPP are considered available for assignment to the ERO if their duties do not include extended travel and they have the approval of their corporate sponsor. Attachment 3-1, Management Organization, provides an organizational chart of supporting organizations. Emergency positions are staffed so relations to responsibilities and duties of the normal staff complement are essentially unchanged. Operating Organization personnel resources provide the means for continuous (24-hour) plant operations, including manning of communications links.,

IL STANDING REVIEW COMMITTEES Two committees are established in the Updated Final, Safety Analysis Report, Section 12.5, Review and Audit of Operations,: to ensure .adequate~review of matters pertaining to nuclear plant safety

..and integrity. The Plant Operations Review Committee functions in an advisory capacity to the

..Plant General Manager-Calvert Cliffs Nuclear Power Plant. The Nuclear Safety, Review Board is an independent review organization functioning in an advisory capacity to the Chief Nuclear Officer. Membership and specific responsibilities of the Plant Operations and Safety Review Committee and Nuclear Safety Review Board are detailed in CEG Fleet procedures.

Revision 41

fIt. EMERGENCY ORGANIZATION Emergency Preparedness Unit maintains a list of personnel assigned as primary and alternates to emergency positions. Emergency titles apply to interim, alternate, and primary candidates alike.

The first person assuming an emergency' position retains title, authority, and responsibilities until relieved. Attachment 3-2, Minimum On-Site Staffing Requirements, lists the minimumronsite staffing. The following attachments show Emergency Organization relationships:

- Attachment 3-3, Emergency Organizations

Attachment 3-4, Recovery Organizations

Attachment 3-5, Center Interface: Unusual Event and Alert

Attachment 3-6, Center Interface: ýSite Area and General Emergency A. Emergency Director/Recovery Manager Thie Emergency Director/Recovery Manager has the authority and responsibility to manage and direct the emergency response and serves as the main contact at&tli site. n6 Addition to directing staff and operations personnel, he or she can call on additional Comiipany and outside agencies assistance as needed.:Additional staff will be called'upon to support overall operations of ihe-Emergency Operations Facility and may include Additional personnel to supportadministratiVe, accountability, media control, etc. Emergency Director/Recovery Manager responsibilities, include but are not limited to, emergency classification; immediate and unilateral initiation'of emergency actions, includiing making notifications and providing protective action recommendations to authorities responsible for implementing off-site emergency measures; and requesting Federal assistlance. The Emergency[Director/Recovery Managerhas primary responsibility for interface with governmental agencies-having action responsibilitieslto ensure the protection of the population-at-risk within the Calvert Cliffs-Nuclear Power Plant emergency planning

.zones.

it a The decision'io notify and make offsite protective action recommendations to off-aygatedL authorities SSit may not be deled.

The Emergency Director/Recovery Manager is also responsible for onsite protective actions and reentry operations. The Shift Manager (staffed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) assumes the Interim-Emergency Director/Recovery Manager position ,at the onset of an emergency and retains it until relieved by augmenting'personnel. When physically present and updated on plant 9

conditions, the General Supervisor-Nuclear Plant Operations may succeed the Shift Manager until they in turni are relieved. by people assigned to the Emergency Revision 41

IIl. EMERGENCY ORGANIZATION (Continued)

A. Emergency Director/Recovery Manager (Continued)

Director/Recovery Manager position as their primary responsibility. Transfer of authority and responsibility is by voice acknowledgment of relieving party.

B. Technical Support Center Manager The Technical Support Center Manager reports to the Emergency Director/Recovery Manager as senior licensee official on-site. This person provides guidance and technical assistance to the operating supervisor in the Control Room with the objective of taking the plant to a safe condition with minimal effect on the health and safety of plant personnel and the public.

C. General Supervisor-Nuclear. Plant Operations The General Supervisor =-.Nuclear Plant Operations is the operating supervisor in the Control Room. This person-provides general supervision to the Shift Manager; overall coordination of maintenance and related activities necessary to supportControl Room needs; and liaison with the Technical Support Center Manager. The, General Supervisor -

Nuclear Plant Operations reports to the Technical Support Center Manager.

D. Shift Manager The Shift- Manager has auhioritiy and responsibility'for ieactofrplant manipulations including implementation of normal, abnormal, and emergency procedures. The Shift Manager reports to the General Supervisor-Nuclear Plant Operations.

Shift Technical Advisor:

The Shift Technical Advisor assists the Shift Manager by making recommendations pertaining to plant safety, operations, accident assessment, and procedures.

First Aid Responders:

Nuclear Plant Operations, under the supervision of the Shift Manager, provides first a aid medical services to injured persons.

Revision 41

II[. EMERGENCY ORGANIZATION (Continued)

D. Shift Manager (Continued)

Fire Brigade Responders:

Nuclear Plant Operations, under the. supervision of the Shift Manager, provides fire fighting services to the site.,

E. Emergency Operations Facility Director The Emergency Operations Facility Director has the authority and responsibility for managing Emergency Operations Facility operations. This responsibility includes.

information flow, interfacing with Technical Representatives'and assisting Emergency Director/Recovery Manager as directed.

F. Operational Support Center Director The Operational Support Center Director has authority and responsibility for mechanical, electrical and instrument correctivie actions and for providing s upport for onsite protective actions, plant operations, and reentry and recovery. TheiOperational Support Center Director also coordinates logistic support for the Control Room so accessto it is restricted to personnel specifically requested. The, Operational Support Center Director reports to the Techniciail Support CenterManager, or in this person's absence, the General Supervisor Nuclear Plant Operations. ,

G. Radiation Protection Director The Radiation Protection Director has authority and responsibilityI for onsite radiation protection and personnel radiation exposure control. TheRadiation Protection Director also coordinates with the Radiological Assessment Director for support. The Radiation Protection Director reports to the Operational Support Center.Director.

The Shift Radiation Safety Technician (staffed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) assumes this position at emergency onset and retains it until relieved by augmenting personnel.

Revision 41

.LIl EMERGENCY ORGANIZATION (Continued)

G. Radiation Protection Director (Continued)

Functions reporting to and coordinated by the Radiation Protection Director include:

I. Survey Team Responsible for Iodine Sampling, Radiological Job Coverage, Radiological Access Control and Emergency.Response Facility monitoring (Control Room/Technical Support Center, Operational Support Center/Nuclear Security Facility,.and the South Service Building Cafeteria). "

H. Maintenance Team Leaders and Maintenance Teams The Maintenance Team Leaders coordinate their teams' activities for Irepair and damage control (mechanical, electrical, instrument). The teams are responsible for. assessing equipment damage and affecting repairs. Maintenance Team Leaders report to the Operational Support Center Director. Technicians reporting to and coordinated by the O *Maintenance Team Leaders include:

' Mechanical Maintenance Technicians

Electrical Maintenance Technicians

Instrument Maintenance Technicians

1. Operations Team Leader and Operations Team The Operations Team Leader directs extra operators who comprise the Operations Team for support as requested byithe Control Room.. The Operations Team supplements on shift operators for operations tasks. TheOperations Team Leader reports to the Operational Support.Center Director.

J. Engineering Director The Engineering Director has authorty anddresponsibility f6r providing direct mechanical, and electriital engineering oversight to Operational Support Center Engineering personnel.

The Engineeining Director has authority and responsibility for providing engineering support in connection with the UFSAR, ISFSI, USAR, the license, and modifications, and Revision 41

Ill. EMERGENCY ORGANIZATION (Continued)

J. Engineering Director (Continued) for overseeing Activities ofenginieers and technicians in response to requests from the Operational Support Center Director, Technical Support Center Manager, and Emergency Operations Facility personnel.. This support includes core protection and analysis. This function is supported in:the OperationalSupport Center by a mechanical engineer, and an electrical engineer,7and in the Technical Support Center by a:technical advisor. If necessary, contractor services may be brought to bear by the EngineeringAdvisor. This action does not preclude the Technical Support Center Manager from soliciting contractor engineering support. The Engineering Director reports to the Operational Support Center Director.,

K. safety Servces, A Safety Services representative serves as an advisoi to Nuclear Plant Operations during a fire and first aid response. Safety Services reports jo the OSC-Dilrector.

L. Security Liaison 9 The Security Liaison is a Nuclear Security Officer responsible for maintaining an interface between the Operational Support Center and the Security Shift Supervisor. The Security Liaison reports to the Security Shift Supervisor.

M. Security'Shift Supervisor The Security Shift Supervisor has the authority to and is responsible for implementing the Nuclear Security Plan. The Secu*rity'Shift Supervisbr repot to..thedNuclear Security Coordinator. The Security Shift Supervisor positionalso'supports personnel accountability activities.

N.. :,Chemistry Team Leader and Chemistry Team

,The Chemistry Team Leader directs the Chemistry Team in drawig and analyzing liquid samples. The Chemistry TeamLeader reports to the Chemistry Director.

Revision 41

0. Technical Support Center Director The Technical Support Center Director has authority and responsibility for core'protection and analysis, for pursuing analysis of potential problems or phenomenon and for assessing strategies derived from likely paths to core melt and containment failure. The Technical Support Center Director reports to the Technical Support Center Manager.

Functions reporting to and coordinated by the Technical Support Center Manager include:

1. Reactor Engineering: Responsible, fo core damage assessment and severe accident management assessment performed by Reactor Engineers and Reactor Engineers -

Thermal Hydraulics.

2. Technical Analysis: Responsible for plant' damage assessment concentrating on systems analysis and containment integrity performed by the Technical Analyst.

3. Operational Analysis: Responsible for plant damage assessment concentrating on operational insights and reactor coolant system integrity performed by the Operational Analyst.

4. Technical Support Center Computer Maintenance:. Responsible for activating the Emergency Response Data System.

P. Chemistry Director The Chemistry Director has authority and responsibility for coordinating sampling and sample analysis, and evaluation of plant fluid systems. The Chemistry Team under the supervision of a Chemistry,Team. Leader supports the Chemistry Director. The Chemistry Director reports to the Technical Support Center Manager.

Q. Security Coordinator .

The Security Coordinator supervises andcoordinates all security related activities onsite including those of the Security Shift Supervisor (the Security Shift Supervisor supervises Nuclear Security Officers and Security System Operato'rs)and'fitness-for-duty testing activities. The Security Coordinator reports to the Technical Support Center Manager.

R. Radiological Assessment Director The Radiological Assessment Director reports to the Emergency Director/Recovery

_Manager. This position has authority and responsibility to assess, map, and coordinate Revision 41

[It. EMERGENCY ORGANIZATION (Continued)

R. Radiological Assessijent'Director (Continued) calculations of radiological data required to depict onsite and offsite radiation dose and/or exposure rates.

This position evaluates radiological conditions and makes recommendations to the Emergency Director/Recove6y Manager. The OffSite Survey Team reports to and is directed by the Radiological Assessment Director. Dose assessment tasks may be divided between the Radiological Assessment Director and an alternate, if an alternate Radiological Assessment Director is available. The principal responsibility of the Radiological Assessment Director is to provide protective action recommendations and radiological evaluations to the Emergency Director/Recovery Manager. Performance of

-'radiological evaluations may beis'signed to the alternate Radiological Assessment Director. At emergency onset, the Shift Cheinistry Technician (staffed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) performs interim dose assessment until relieved by the Radiological Assessment Director.

Radiological Assessment Director support is provided by the following:

1. Environmental Assessment:.:

This person acts in an advisory capacity to the Radiological Assessment Director regarding environmental sampling and analysis.

2. Offsite Monitoring:

The Offsite Survey Team monitors radiation dose rates and radioactivity concentrations at assigned, locations offsite for use in offsite radiological assessment.

3. Radiological Assessment Specialists:

These personnel Perform radiological calculations and assessments required to depict offsite radiationdose and/or exposure rates.,

S. Communicators

'Communicators report tothe director of their respective emergency center.

Communicators have authority and responsibility for communications according to Emergency Response Plan Implementation Procedures. Communication responsibilities include initial and f16w-up communications with Calvert CliffsNuclear Power Plant, State, local and Federal W 4I)*i Revision 41

IlI. EMERGENCY ORGANIZATION (Continued)

S. Communicators (continued) personnel; communications with regulatory agencies through the Emergency Notifications System; and communication of plant parameter status data, environmental status data, Radiological Monitoring System status data; and communications between emergency response facilities.

T. Fitness-For-Duty Tester Personnel provided at onsite or offsite emergency response facilities thatare specially trained to conduct fitness-for-duty testing for emergency responders, as needed. Fitness-for-duty activities are coordinated and supervised, by the Security Coordinator.

U. Telecommunuications/Information Technology The Telecommunications Support Manager provides computer support at the EOF and JIC.

The Telecommunications Support Manager. has authority and responsibility for coordination of all communications and informationtechnology, activities.

IV. RECOVERY ORGANIZATION The offsite emergency organization (Recovery Organization) is normally directed from the Emergency Operations Facility. Constellation Energy provides corporate support and additional resources to the Recovery Organization as needed. The RecoveryOrganization is activated at the direction of the Emergency Director/Recovery Manager. The Recovery Organization is responsible for providing additional personnel and technical assistance from offsite sources.

. *A. Emergency Director/Recovery Manager (Recovery Phase)

The Emergency Director/Recovery Manager transitions to a different role when the determination has been made to enter the recovery phase of the event.

The Emergency Directoi/Recovery Manager ensures'auigmentation and support of Calvert Cliffs Nuclear Power Plant's response efforts (including assuring continuity of technical, i.inistirative and materialres6urc6s) and may interface with Federal, State, and local adum Sagency representatives.'This positio hhas the authority to request Federal assistance if a situation wanrants. Attachments 3-4 and 3- show the Recovery Organization interrelationships; Revision 41

IV. RECOVERY ORGANIZATION (Continued)

A. Emergency Director/Recovery Manager (Recovery Phase) (continued)

The Emergency Director/Recovery Manager may choose to speak for the Company. This representation may occur during major press conferences (e.g., with the Governor or the Maryland Secretary of the Environment) or at intervals commensurate with the need. The decision to act as spokesperson will be based on recommendations from the Joint Information Center Director. The Emergency Director/Recovery Manager retains responsibility. for Calvert Cliffs Nuclear Power Plant's activities throughout an emergency (on a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months basis). If not physically in the Emergency Operations Facility or Joint Information Center, the Emergency Director/Recovery Manager will be in close proximity to one or the other and will be on call for status changes or deviations from standing orders.

B. SupportManagers and Directors

1. Public.Information The Joint Information Center Director maintains overall command andcontrol of the Joint Information Center operations, including coordination with government authorities, liaison between Emergency Director/Recovery Manager, and media response and rumor control. This position reports to the Emergency Director/Recovery Manager.

Positions reporting to and coordinated by the Joint Information Center Director include:

a. Corporate Spokesperson: Supports the JIC:Director by providing timely,

- technically accurate and complete briefings to the media when required or

directed.

Ab. Joint Information Center Administrative Manager: Coordinates

. activation/deactivation of the JIC and assigns responsibilities to the

,,;Administrative Support personnel at the JIC. Coordinates Emergency

. Director/Recovery Managers review/appro~val of press releases and information flow. between the EOF and JIC.

c. Customer Relations Representative: Provides:interface between the Calvert Cliffs Nuclear Power Plant Joint Public Information organizations and the BGE Customer Service, Customer Care Center.

Revision 41

~~ EN,'

IV. RECOVERY ORGANIZATION (Continued)

B. Support Managers and Directors (continued)

d. Administrative Support Pool provides general support to the JIC staff.

e. Technical Advisor: Obtains plant technical information (e.g., plant parameters data, radiological monitoring~data, and environment monitoring data) and ensures it is understood by the Calvert Cliffs JIC staff.

f, Technical Writer: is responsible for preparing written material including news releases, briefing summaries and'other materials as.directed by the Corporate Spokesperson pertaining to the event at CCNPP.

g. Rumor Control Coordinator: Liaison between the Customer Relations Representative, -BGE Customer Service Customer Care Center, and the

, Joint Information Center; ensuring BGE Customer Care has up to date information and rumors are communicated to the JIC corporate spokesperson.

2. Administrative The Administrative Support Manager has authority and responsibility for administrative, logistical, procurement, and, offsite security support activities.

3. Telecommunications/Information Technology The Telecommunications, Support Manager provides computer support at the EOF and JIC. The Telecommunications Support Manager has authority and responsibility for coordination of all communications and information technology activities.,

C:..' EmergencyvOperations Facility Director (Recovery Phase),

The Emergency Operations Facility Dire'tor has the'authority and responsibility for managing Emergency Operations Facility operations. This responsibility, includes, information flow, interfacing with Technical Representatives and assisting Emergency Director/Recovery Manager as directed.

Revision 41

IV. RECOVERY ORGANIZATION (Continued)"

D. Technical Representatives Emergency Response Plan Implementation Procedures provide for dispatching representatives to principal off-sitegovernmental emergency operations centers. Personnel assigned and, specific responsibilities are addressed in Emergency Response Plan Implementation Procedures. Technical Representatives do not have decision and/or recommendation-making authority.

V. CONTRACTED SERVICES A. Contractors Contractors and private organizations may be requested to provide assistance to and augmentation of the emergency organization. Assisting groups may include the NSSS V.

supplier,'plant Architect-Engineer or any industry support company. These support services are outlined in memorandums of agreement in Appendix D and include support for Fire and Rescue, Ambulance Services, Medical Services to include Physicians, Nuclear Incident Training, Nuclear Emergency Consulting and Techinical Assistance, Earthquake cconfirmation, Disastir planiniiig memorandums between local utilities. Specific contractors are dependent on emergency situation needs and are described-in* associated Emergency Response Implementing Procedures.

B. Other The Institute for Nuclear PowerOperations publication "Emergency Resources Manual" (Ref. 39) lists points of contact, location, and.support available from nuclear facilities.

. Resources wouldbe requested based on emergency situation needs through INPO.

VI. LOCAL SERVICES '

Appendix D, Letters of Agreement, contains written agreements identifying services provided by local agencies for handling emergencies, (e.g., medical, hospital and fire fighting organizations).

Provisions are made for transportation and treatment of injured personnel who may also be contaminated. Agreement letters identify authorities, responsibilities, and limits on the actions of the respective agency.

Revision 41

VII. PARTICIPATING GOVERNMENTAL AGENCIES Functions performed by Federal, State, and county agencies are summarized in the following subsections. Appendix D, Letters of Agreement, contains written agreements identifying services provided by Federal, State, and county agencies.

Detailed information is contained in:

1. Maryland Emergency Operations'Plan, Annex Q, Radiological Emergency Plan

2. Calvert County, Dorchester County, and St. Mary's County Radiological Emergency Plans and Standard Operating Procedures.

3. Virginia Radiological Emergency Response Plan

4. Delaware Radiological Emergency Plan

5. District of Columbia, District Response Plan A. State of Maryland The Maryland Emergency Operations Plan, AnnexQi Radiological Emergency Plan is the official State plan for responding to radiological emergencies. State officials and agencies identified inthe Plan having overall command, coordination, key, and support responsibilities include:

1. The Governor

2. Maryland Emergency Management Agency (MEMA)

3. Department of Health and Mental Hygiene,

4. Maryland Department of Agriculture,

5. Mary!and Department of Environment

6. Department of Natural Resources,

7. ..Maryland State Police

8. Department of Human Resources Revision 41

VII. PARTICIPATING GOVERNMENTAL AGENCIES (continued)

A. State of Maryland (continued)

9. Department of Transportation

10. Maryland State Department of Education'

11. Department of Housing and Community Development

12. Maryland Military Department/Nlational Guard,

13. Maryland Institute for Emergency Medical Services System

14. Office of the Comptroller of the Treasury

15. Office of the State Fire Marshal B. Functions and ResPonsibilities of Key Agencies and Officials

1. The Secretary - Maryland Department of the Environment has the authority of the Governor and maintains responsibility for overall command of an emergency response. Major areas ofaction under his/her commandinclude:

a. Accident assessment .

b. Notification and communication

c. Command and coordination

d. Protective actions

1) Evacuation

2) Ingesiion o'f Potassium Iodide or thyroid protection

3) Take shelter

4) Access control

5) Food, water, and milk control

e. Parallel actions.,

1) Emergency medical services

2) Radiation exposure control

3) Law en'forcement and crime prevention

4) Mass Care :

5) Re-entry

6) Return

7) Relocation AM_

Revision 41

VI. PARTICIPATING GOVERNMENTAL AGENCIES (continued)

B. Functions and Responsibilities of Key Agencies and Officials (continued)

f. Public Information

2. The MEMA coordinates State, private, and Federal agency response to and from CCNPP to aid County emergency operations. The MEMA directs County requests for assistance: to appropriate State. and Federal agencies.

3. The State Department of Environment makes available resources and personnel to perform the following:

a. Provide technical information to the Secretary-Department of the Environment.

b. Dispatch field monitoring teams toemergency area(s).

c. Set -upheadquarters for direction of activities by the State Radiological Health Administrator at the Accident Assessment Center in the near site Emergency Operations Facility.

d. Determine when assistance is required from the Federal Department of Energy and request such assistance.

e. Determine when protective actions for the public are required and inform State and local authorities. /-

f. Provide guidance 'in establishing public restricted areas.

g. Provide containihation-control action'guides.

h..* Request outside radiological monitoring assistance when needed.

i. Provide-guidance'for externa human and animal decontamination.

j. Provide guidance for facilities, equipment, and area decontamination.

k. Provide guidance to the State Departments of Agriculture and Health and Mental Hygiene for controlling the use of milk and agricultural products.

-. 1 Determine and notify appropriate authorities when people may return to evacuated areas.

m. Provide direction of Ingestion Pathway Coordinating Committee activities.

Revision 41

VII. PARTICIPATING GOVERNMENTAL AGENCIES (continued)

B. Functions and Responsibilities of Key Agencies and Officials (Continued)

4. The State Department of Health and Mental Hygiene makes available resources and personnel to perform the following:

a. Dispatch agricultural sampling teams to effected areas.

b. Provide guidance to the State Department of Agriculture for controlling the use of milk and agricultural products.

c. Provide laboratory analysis of field samples.

d. Support Ingestion Pathway Coordination Committee activities.

5. The Maryland State Police render assistance as follows:

a. Establish off-site command post in vicinity of the plant site.

'b. Evacuate and exclude individuals from designated public and private areas.

c. . Control traffic into and out of designated areas.

d. Transport Maryland Department of Environment Monitoring Teams on request. 9

e. Assist in medical evacuation via helicopter.

f. Aid in emergency communications.

g'.. Coordinate with County Sheriffs to assist in communications, evacuations, and traffic control.

6. ,.The Maryland Department of Natural Resources ,Police Force and the Fisheries Service render assistance as follows:

a. Evacuate and prevent entry .to:designated water areas.

b., ..- Aid inemergency.communication s.l.

c. Assist in radiological monitoring.

d. Assist in waterborne population evacuation as required.

7. The Maryland'Emergency management Agency Public Information Officer is r.e.s responsible for coordination of State and locainformation releases. The Public Information Officer coordinates with Calvert Cliffs Nuclear Power Plant's Joint Revision 41

VII. PARTICIPATING GOVERNMENTAL AGENCIES (Continued)

Information Center Director to prevent conflicting statements between State/local and Calvert Cliffs Nuclear Power Plant's spokespersons.

C. Planning Zone Support

1. Plume Exposure Emergency Planning Zone Calvert County, Dorchester County, ahd St. Mary's County Radiological Emergency Plans and Standard Operating Procedures summarize the plan used by county agencies within the Plume Exposure Emergency. Planning Zone. Command of county agencies is under the direction of the Board of County Commissioners, or County Council for each county. Coordination and responsibility for implementing protective actions is the responsibilit~y of the Director of each county's Emergency Management Agency.

2. Ingestion Emergency Planning Zone,

a. Maryland The ingestion EPZ for CCNPP includes all or portions of thirteen Maryland counties.

Anne Arundel County

Queen Anne's County

Calvert County. Somerset County

Caroline County . St. Mary's County

Charles County

Talbot County

Dorchester County

Wicomico County

Kent County . Worcester County

. Prince George's.County ..

Functions and responsibilities of agencies responsible for emergency response are described in the Maryland Emergency Operations Plan, Annex Q, and Radiological Emergency Plan.

Revision 41

VII, PARTICIPATING GOVERNMENTAL AGENCIES (Continued)

C. Planning Zone Support (Continued)

b. Commonwealth of Virginia The ingestion EPZ for CCNPP includes all or portions of the following Virginiapolitical subdivisions:

Counties Cities

-1. Accomack (Tangier Isla'nd) Alexandria

2. Arlington 2. Falls Church

3. Caroline

4". Essex

5. Fairfax

6. King George

7. King and Queen

8. Lancaster

9. Middlesex

10. Northumberland

11. Prince William. ...

12. Richmond

13. Stafford

14. Westmoreland Functions and activities of these agencies are described in the Virginia Radiological Emergency Response Plan.

9 Revision 41

VII. PARTICIPATING GOVERNMENTAL AGENCIES (Continued)

C. Planning Zone Support (Continued)

c. State of Delaware Functions and activities of agencies responsible for emergency response in the Delaware portion of the ingestion EPZ are described in the Delaware Radiological Emergency Plan and Implementing Procedures.

d. District of Columbia Functions and activities of agencies responsible for emergency response in the Washington, D.C., portion of the ingestion EPZ are described in the District of Columbia, District Response Plan.

D. Support From Federal Agencies Calvert Cliffs Nuclear Power Plant is located about 70 miles south of Baltimore and 50 miles southeast of Washington, D.C. The site is less than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months driving time from either city or their respective airports (Baltimore-Washington International; Ronald Reagan National). A helicopter landing can be accommodated at Calvert Cliffs Nuclear Power Plant and the Emergency Operations Facility. Emergency facilities have been designed to meet the space and communications needs of a small scale Federal response. Federal Radiological Emergency Response Plan implementation may require the use of Andrews Air Force Base and/or Federal, State or local facilities to accommodate the large volume of associated personnel.

The following subsections identify Federal agencies that could be individually called on for support during an emergency at CCNPP.

1. U.S. Nuclear Regulatory Commission - Region I, Office of Inspection &

Enforcement, King of Prussia, Pennsylvania. The Directorate of Regulatory Operations will be notified of radiological incidents in accordance with 10CFR20.403, and will conduct appropriate investigative activities.

2. U.S. Department of Energy, Brookhaven Area Office, Upton, New York. The Brookhaven Area Office of the U.S. Department of Energy will provide assistance, consultation, and services in accordance with Appendix D, agreement letter.

I Revision 41

ATTACHMENT 3-1 MANAGEMENT ORGANIZATION (Page 1 of 2)

Constellation Energy Group Revision 41

ATTACHMENT 3-1 MANAGEMENT ORGANIZATION (Page 2 of 2)

Calvert Cliffs Nuclear Power Plant Eninern

" \ýceraetY Plant General . Traing ieri gSecity manageraanager a Refiabty Ptepwe~lss . . .SA**l& Heam I-I Engk-Meenni syst- Eno,.

.. ma'h .9 b i.d a

: *.[

Revision 41

S ATTACHMENT 3-2 MINIMUM ON-SITE STAFFING REQUIREMENTS Page I of 2 MAJOR POSITION, TITLE, WITHIN FUNCTIONAL MAJOR TASKS OR EXPERTISE ON SHIFT AREA APPROX.

60 MINUTES Plant operations and Shift crew personnel per Technical --

assessment of operational Specifications aspects Emergency direction and Shift Manager or 1(b) --

control (c) . Shift Technical Advisor Notification/ Notify licensee, Federal, 1(b) 3 communication State, and local personnel and maintain communications Support of operational Site emergency Manager accident assessment coordination V. - VI.

Senior Health Physics Rla. Off-site dose (HP) expertise Radiological accident assessment I assessment b. Off-site surveys Survey Team - 4

c. On-site surveys Survey Team 2

d. In-plant surveys Survey Team 1 2

e. Chemistry/radio- Chemistry Technicians 1 1 chemistry Plant System Technical support Rx Core Engineer - 2 Engineering, repair and Electrical Engineer - 1 corrective actions Mechanical Engineer - I Repair and corrective Mechanical maintenance - 3 actions Rad Waste Operator 1(b) --

Electrical maintenance - 2 Instrument and Control --

(I&C) Technician 2 Protective actions Radiation protection:

(in/plant) operational a. Access control Survey Team l(b) 6 aspects b. HP coverage for repair, corrective actions, search and rescue first-aid and firefighting

c. Personnel monitoring

d. Dosimetry Firefighting Fire Brigade personnel per Technical Local Specifications Support.(d)

Rescue operations and First Aid Team personnel 2(b) Local first aid Support (d)

Site access control and Security, communications, Security personnel per Security Plan --

personnel accountability personnel accountability I Revision 41

ATTACHMENT 3-2 MINIMUM ON-SITE STAFF[NG REQUIREMENTS Page 2-of 2 (a) Additions required for Alert, Site Area Emergency and General Emergency.

(b) Provided by shift personnel assigned other functions.

(c) Overall direction of facility response to be assumed by person(s) assigned Emergency Director/Recovery Manager position as primary responsibility when all centers are fully manned. Direction of minute--to-minute facility operations remainswith the. Technical Support Center Manager in the Technical Support Center.

(d) Additions within approximately 30 minutes.

Revision 41

Key- Iposoitio TitT, ATIACHLMNI 3-3 Locatbon EMERGENCY ORGAMIZATION authority/ntefface r - -----------I EmergencyDirectorl I rergentesponweI Recovery Manager c--e-d--er-acedud,nan I I umEvei orAie-, See ErngeWn Operafhfo Facty I AbdaxWer3-5 I Technical Support Center Manager Tedfc~at upr Center Technicl Support Cedter fDrecto Emeren Opetions Facifty Diedor Reactor Core Engineer Operational SW*or Centiel Technical Analyst SafetY Services opw new Analyst Caawuucalims Communkiuars ConPr&e Main~tenance FFD-Tester LF Telem~mmuicaim Sopim t WMaW a Commrmicaw tViw Rroftogcl Assessrnet Dirctor Ofiil Survey Teams Raft&A* Afssessmert Specialist I Emrwimenta Aessemel Direckor OoseAsssir Office-BEamq ~cOperattos Facity Revision 41

Key:

ATTACHMENT 3-4

___.RECOVERY ORGANIZATION Position Title Location Authority Interface

-- Interface Only Technical Representative .

Emergency Operations Center Revision 41

NOUN'*-~- A.d.. ~.u$ma*%tt;*

2 Key-.

ATTACHMENT 3-5 CENTER INTERFACES:

UNUSULAL EVENT Sof con mnicalaxis li -

May access ditectht or Auftho Interface buieiface vft EDreclacRecovery Manager moves to fts center Caket co unty Inedface with Iocal agencies (e-g. poce, ifre.

Technical Support Center Emergency Operations Center ves-i, hospital) is ftiough Teduwicl Siippat Center EmergencManagemenil Caled County Eme[gency Uanaer/Wieif ED Operations Center, st,Uaiys County EmegeneecOperations Center E-mergecy M-anageen IDkdw Mayaad Emergency Managvent Agency IMEMRA EmeigencManagerneat Revision 41

(** *.,*,*.: E N;*,:.,., .. E 1ý ý7,,'.** :im". :.,: .**;: **.*****'*:* * :. ! '"*,:**:*** :,: .::-.::*,*._-* = ,* .

Key: ATTACIIMENT 3-6 CenterlFacility CENTER INTERFACES:

Organiz3aicna ti&e at end ALERT, SITE AREA AND GENERAL of co0mmuiatis fink.

May access dir-ecdy or EMERGENCY through iommunicator HNormal Wiedace

-teace avadab Joint Information Center Emergency Operations Facility Joim bIcmatmon Cente Director corp- Spokesperson Emeirency Dectoarecoveq Manager

- q ORmon Fa Dketior Contro-lRoom Revision 41

CALVERT CLIFFS NUCLEAR POWER PLANT EMERGENCY RESPONSE PLAN EMERGENCY MEASURES RECOGNITION AND CLASSIFICATION Calvert Cliffs Nuclear Power Plant staff recognizes and responds to off-normal plant conditions.

Abnormal and Emergency Operating Procedures allow personnel to mitigate emergency consequences and correct off-normal conditions quickly. These procedures reference the Emergency Response Plan Implementation Procedures. Emergency Response Plan Implementation Procedures contain procedures and guidance for accident assessment and emergency classification. These procedures implement the Emergency Response Plan.

Attachment 4-1, Off-Normal Condition Response: Sequence, shows the basic response sequence followed during off-normal conditions.

II. NOTIFICATION A. On-Site Personnel Emergency Response Plan Implementation Procedures provide for 24-hour on-site personnel warning, alerting, activating, and'advising for emergency situations. This includes:

I. Employees without emergency assignments.

2. Visitors and persons in on-site public access areas.

3. Contract and construction personnel.

B. Off-Site Agencies Emergency Response Plan Implementation Procedures 'provide for 24-hour alerting,

'notifying, and mobilizing CEG off-site response organizations and for 24-hour alerting

..and notifying non-CEG off-site response organizations as provided in Attachment 4-2, Off-site Agency Notification. These procedures include means for message verification.

Revision 41

II. NOTIFICATION (Continued)

C. Messages

1. Initial emergency messages sent from the plant are detailed in the Emergency Response Plan Implementation Procedures. Messages contain:

a) Emergency class and nature of incident.

b) Whether a release is taking place.

c) Potentially affected population and areas.

d). Whether protective measures are necessary.

2. Emergency .Response Plan Implementation Procedures provide for, facility follow-up messages to off-site authorities. These procedures contain:

a) Incident location, caller name, and communications identification.

b) Nature of incident, date/time, and classification. -

c) Actual or projected release type (airborne, waterborne, surface spill) and estimated duration/impact times.

d) Radioactive material release quantity estimate andrelease points/heights.

e) Released material chemical and physical form including relative quantities and concentrations of noble gases, iodines, and particulates.

f) Meteorological conditions (wind speed, direction-to and from), stability indicator, precipitation.

g) Actual or projected site boundary dose rate; site boundary projected integrated dose. .

h) _Projected dose rates and integrated dose at projected peak and at 2, 5, and 10 miles including sector(s) affected.

i): -Inplant, on-site, off-site surface radioactive contamination estimate.

j) Facility response actions in progress.

Revision 41

II. NOTIFICATION (Continued)

C. Messages (Continued) k) Recommended emergency actions, protective measures, and recommendations set forth in Enviromnental 'Protection Agency's Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA-400-R-92-00 1), Tables 2-1 and 2-2.

1) Support requests.

m) Incident prognosis (worsening/terminating)-. ..

3. Initial and follow-up messages provide supporting information for messages developed by State and local agenciesý for the public. Initial and fo1!wi'-up' messages are consistent with the classification scheme addressed in the Emergency Response Plan Implementation Procedures.

4. Off-site authorities responsible for implementing protective measures within the plume exposure pathway Emergency Planning Zone receive initial (prompt

-notification) and follow-up messages directly, Provisionexists to make Initial Notifications within- 15 minutes of emergency declaration.

D. Prompt Public Notification Prompt public notification using sirens or backup methods such as route alerting that facilitates public awareness to turn on their televisions or radios and listen for information or instructions broadcast by state or local goyernment authorities on the Emergency Alert System.

A physical means has been established-and.demonstrated to exist, forproyiding prompt public notification withintheplumeexposure pathway Emergency Planning Zone. The Public Alert and Notification System is described in detail in Calvert Cliffs Nuclear Power Plant's response to FEMA-43, Standard Guide for the Evaluation of Alert and Notification Systems for Nuclear Power Plants (Reference 49), and subsequent correspondence with the Federal Emergency Management Agency.

Revision 41

III. AUGMENTATION Emergency Response Plan Implementation Procedures provide means to augment on-shift personnel within a short period after emergency declaration.

IV. ACCIDENT ASSESSMENT Accident assessment consists of a variety of actions taken to determine the nature, effects, and severity of an accident and includes evaluation of reactor operator status reports, damage assessment reports, meteorological observations, seismic observations, fire reports, radiological dose projections, in-plant radiological monitoring, offsite (environmental) radiological monitoring, etc.

Emergency Response Plan Implementation Procedures provide methods and techniques for:

A. Determining radioactive material release source term.

Example: Relationship between Containment radiation monitor reading and radioactive material available for release from Containment.

B. Determining radioactive material release based on plant: system parameters and effluent monitors (graphic recorders and the plant computer provide records to back calculate total amounts of plant released radioactivity).

C. Establishing the relationship between effluent monitor readings and on-site/off-site exposure and contamination for various meteorological conditions.

D.r Determiningrelease rate/projected dose if assessment instrumentation isoff-scale or inoperable.

E'. Rapid assessment and chemical sampling and. analySisof magnitude and location of radiological hazards (actual or potential) through liquidoit gaseous release pathways.

Revision 41

MV. ACCIDENT ASSESSMENT (Continued)

F. Relating measured parameters (e.g., Containment levels, water and air activity levels) to dose rates for key isotopes (i.e., NUREG-0654, Table 3, Page 18) and gross radioactivity measurements. Provisions are made for estimating integrated dose from projected and actual dose rates and for comparing these estimates with protective action guides.

G. Periodically estimating total population exposure.

H. Relaxing protective measures to allow reentry-into an evacuated area and for return of areas to normal use. This condition includes provision for informing the response organizations that a recovery operation is being initiated and of any changes in the organization structure that may occur.

V. REPAIR AND CORRECTIVE ACTION Those emergency measures taken to lessen or terminate an emergency situation at or near the source of the problem includes measures taken to prevent an uncontroIled release of radioactive materiaI 'or to reduce the magnitude of a release. Corrective action includes equipment repair or shutdown, installation of emergency structures, fire fighting, and damage control.

VI. PROTECTIVE ACTIONS A. Accountability Emergency Response Plan Implementation Procedures provide the capability to account for all individuals on-site during a Site-Area.Emergency or General Emergency, to ascertain the names of missing individuals within 30 minutes of a Site Area Emergency or General Emergency declaration, and to account for all on-site individuals continuously thereafter. To accomplish accountability, site assembly is executed at Alert level emergency in anticipation of emergency escalation. The accountability process begins when assembly is complete.

Revision 41

VI. PROTECTIVE ACTIONS (Continued)

B. Evacuation

!. Evacuation routes for on-site individuals allow access to Maryland Route 2/4 via the plant access road and Camp Canoy Road (through Camp Canoy facility)..

Transportation is by personal vehicle.

Two roads allow alternative evacuation routes for inclement weather, high traffic density, and specific radiological conditions.

2. Emergency Response Plan Implementation Procedures provide for on-site, non-essential personnel evacuation during a Site Area or General Emergency.

C. Off-Site Recommendations

1. Guidelines for the choice of protective actions during an emergency, consistent with Federal Guidance, are provided in the Emergency Response Plan Implementation Procedures. The effectiveness of evacuation and protection afforded in residential units and other shelters is assumed to be that which is described in Federal Guidance.

2. Reports considered in determining evacuation effectiveness and local protection afforded include:

a) "Public Protection Strategies for Potential Nuclear Accidents,"

."Sheltering Concepts with Existing Public and Private Structures" (SAND. 77-1725), Sandia Laboratory.

"Examination of Off-Site Radiological Emergency Measures for Nuclear Reactor Accidents involving Core melt". (SAND 78-0454), Sandia Laboratory.

c) "Protective Action Evaluation, Part H, Evacuation and Sheltering as Protective Actions Against Nuclear Accidents Involving Gaseous Releases" (EPA 520/1-78-001B).

Revision 41

WýýZ m

VI. PROTECTIVE ACTIONS (Continued)

C. Off-Site Recommendations (Continued) d) "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents" (EPA 400-R-92-00 1).

e) "Criteria for Protective Action Recommendations for Severe Accidents" (NUREG-0654/FEMA-REP-1, Rev. 1, Supp. 3).

f) "RTM-96, Response Technical Manual" (NUREGIBR-0150, Vol. 1, Rev. 4.).

g) "Accidental Radioactive Contamination of Human Food and Animal Feeds: Recommendations for State and Local Agencies" (Center for Devices and Radiological Health, FDA, August 13, 1998).

VII. EXPOSURE CONTROL A. Emergency Response Plan Implementation Procedures and Radiation Safety Procedures provide an on-site radiation protection program including exposure guidelines implementation methods for use during emergencies. Provisions are made for distribution of dosimeters (both direct reading and permanent record devices); ensuring dosirneters'are read'at appropriate frequencies; maintaining dose records for emergency workers.

B. TheEnmergency Response Plan Implementation Proicedures' permit on-site Workers to receive radiation exposures while carrying out lifesaving or other emergency activities.

They facilitate expeditious decision making and a reasonable consideration of relative risks.

1. Exposure guidelines are consistent with Environmental Protection Agency's Guidance on Dose Limits for Workers Perforini-g Emergeiicy Services (EPA-400-R-92-001)

Revision 41

VII. EXPOSURE CONTROL (Continued)

2. Guidelines are established for:

a) Providing first aid and medical treatment service.

b) Undertaking corrective actions.

c) Performing assessment actions.

d) Performing personnel decontamination.

e) Injured person removal and ambulance service.

VIII. CONTAMINATION CONTROL A. Radiation Safety Procedures provide on-site contamination/decontamination control measures for:-?

1. Area access control.

2. Equipment, supplies, and instruments. ..

3 Persofnel (including wounds).

These procedures specify levels at which decontamination needs to be performed and provides, for decontaminants suitable for expected contamination types including radio/iodine skin contamination.

Emergency food and water supplies will, be brought to the site as needed. Food and water brought to the site will be protected~against contamination.,

B. Radiation Safety Procedures provide for radiological monitoring of people evacuated from the site.

IX. PERSONNEL EMERGENCIES Emergency Response Plan Implementation Procedures describe:actions taken in response to personnel emergencies (with and without contamination considerations).

Revision 41

S ATTACHMENT 4-1 OFF-NORMAL CONDITION RESPONSE SEQUENCE EVENT OCCURS Plant parameters out of normal range or a potentially damaging event is recognized Plant Ope"Won-41elated fiaAns Protection Evaluate event In-irnediale Actions 1) Determine radioactivity release potential.

initated according to 2) Declare radiological event iwarranted.

AOPs*IEOPs** 3) Calculate projected doses.

4) Compare conditions to Technical Speciications

5) Compare conditions to EALs*

tm ClassiTfy Event Acc-o"rdg to EALs FoflGW-up actions taken according to AOPsIEOPs Unusual AW Site Area . General Event Ermergency Emergency

- Initiate Emergency Response Ptan Implementing Procedures.

- Reclass as warranted-

- Compare conditions to Protective Action Guides.

-A0P 4biwni OpeuaqProeon~

~EOP -Emu~ecyOpAing Prownuse M -ErnenyAdia Leve Revision 41

ATTACHMENT 4-2 OFF-SITE AGENCY NOTIFICATION Facilities Maintenance &

Ops Emergency Director/

BGE Customer Care Recovery Manager Nuclear Secuity 24 HmwQpealim CnVrMn*2ffi Lime

...NommWai*MAHois Revision 41

CALVERT CLIFFS NUCLEAR POWER PLANT EMERGENCY RESPONSE PLAN FACILITIES AND EQUIPMENT FACILITIES Specific locations on-site and off-site have been designated as emergency control and support centers. These centers are equipped to control, assess, and correct emergency conditions and allow timely communication between centers. The centers' functional objectives are presented in -1, Facilities Functional Objectives.

A. Control Room Plant operations are directed from the Control Room. Nuclear plant instrumentation, Area and Process Radiation Monitoring System instrumentation, controls and instrumentation for reactor and turbine generator operation are provided here. A description of the Control Room is contained in the Updated Final Safety Analysis Report (Ref. 55) Section 7.6.2. Emergency equipment available to .the Control Room is listed in Emergency Response Plan Implementation Procedures.

B. Emergency Operations Facility

1. The EmergencyOperations Facility floor plan is shown in Attachment 5-2, Emergency Operations Facility,1 and its location in Calvert County is shown in Attachment 5-3, Emergency Operations Facility and Joint Information Center Location.

2. The Emergency Operations Facility is equipped for manIaging overall emergency response; coordinating'radiological and environmental assessment (including receipt'and analysis of field monitoring data and sample media coordination);

determining recommended public protective actions; and coordinating emergency response activities With Federal, State and local agencies. When activa it is staffed by Calvert Cliffs Nuclear Power Plant, Federal, State and local personnel designatedto perform these fuinctions. It is the location from which Calvert Cliffs Nuclear Power Plant provides overall resource management in response to emergencies having actual or potential environmental consequences.

Revision 41

I. FACILITIES (Continued)

B. Emergency Operations Facility (Continued)

3. Provision is made for acquisition, display, and evaluation of radiological, meteorological, and plant system data pertinent to determine off-site protective measures. For an emergency or exercise, access is restricted to only personnel assigned to the facility.

4.- The Emergency Operations Facility is located about twelve miles from the site, in Calvert Industrial Park, Skipjack Road at Hallowing.Point Road. It is a well engineered structure for design life of Calvert Cliffs Nuclear Power Plant.

Detailed emergency equipment listing for the Emergency Operations Facility is contained in Emergency. Response Plan Implementation Procedures..

C. Technical Support Center

1. The location of the Technical Support Center at Calvert Cliffs Nuclear Power Plant is shown in Attachment 5-4, TSC Location Relative to Control Room.

2. The Technical Support Center is a work area fordesignated technical, engineering, and management personnel who provide technical support to plant operations personnel during emergency conditions. Technical Support Center resources are used to provide guidance and technical assistance to the Control Room. It, has facilities for and functions as the Emergency Operation Facility during an Alert level emergency and for a Site AreaEmergency and General Emergency until the Emergency Operation Facility is activated. Technical Support Center facilitates reactor operator relief from peripheral duties and communications not directly related to reactor systemoperations. Attachment 5-5, Characteristics of Technical Support Center vs. Emergency Operations Facility, shows characteristics of Technical Support Center relative to plant operations. The Technical Support Center will be fully operational within approximately one hour after activation.

Revision 41

FACILITIES (Continued)

C. Technical Support Center (Continued)

3. The Technical Support Center is located on the 55 foot elevation with an Annex on the 58 foot elevation. It is contiguous with and has direct (door) access from the Control Room (can also be accessed from the Turbine Hall). Habitability duplicates Control Room for postulated accident conditions. Space available is considered adequate for personnel and equipment assigned. Radiological protection of personnel is. afforded by radiation nmonitoring personnel.

4. Two computer systems provide data gathering, trending, storage, and display to permit accurate accident assessment with minimum interference of Control Room operation:

' Safety Parameter Display System computer provides continuous indication'of plant parametersfrom'which quick assessments of plant safety status can: be made.

" Technical Support Center computer provides real time and historical displays and reports to assist' in analysis of unit shutdown.

These systems have backup battery power supply to maintain continuity of Technical Support Center functions and immediately resume data acquisition, storage, and display if primary source loss occurs.,

Parameters monitored in the Technical Support Center include NUREG 0737 Supplement I variables asmodified by Calvert Cliffs Nuclear Power Plant's submittals to NRC.

5. The Technical Support Center contains or has access to'complete and up-to-date plant.records and procedures including:

a., *,Drawings/Schematics

b. Technical Specifications

c. Operating Instruction/Abnormal Operating Procedures/Emergency Operating Procedures

d. Final Safety Analysis Report

e. Emergency Response. Plan Implementation Procedures Revision 41

17__ g-~ - -f!~~;~

FACILITIES (Continued)

C. Technical Support Center (Continued)

6. Detailed emergency equipment listing is contained in Emergency Response Plan Implementation Procedures.

D. Operational Support Center The Operational Support Center is located within the protected area (co-located with the Outage Control Center (OCC)) separate from Control Room-and Technical Support Center. It provides space for the assembly of support personnel during an emergency.

From this location plant logistic support (e.g., maintenance and engineering), required to bring the plant to a safe, stable condition is coordinated. In this way, access to the Control Room is restricted to personnel specifically requested by the Control Room. In addition,- from thisjlocation plant, systems and engineering is coordinated to respond to Stheneeds of the Technical Support Center and the Emergency Operations Facility. No specific habitability criteria are established. Detailed Operational Support Center emergency equipment listing is contained in Emergency Response Plan Implementation Procedures. Implementation Procedures include provisions for performing Operational Support Center functions by essential support people from a second (alternate) location.

E. Joint Information Center

1. The Joint Information Center location is shown in Attachment 5'-3, Emergency Operations Facility and Joint Information Center Location.

. .. " The Joint Information Center is a central location foriCalvert Cliffs Nuclear Power Plant personnel to meet with NRC, State and County representatives for releasing emergency announcements to news media.

3. The Joint Information Center is located about twelve miles*from the site, in Calvert Industrial Park, Skipjack Road at Hallowing PointRoad. It is a well engineered structure for design life of Calvert Cliffs Nuclear Power Plant.

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FACILITIES (Continued)

E. Joint Public Information Center (Continued)

4. The Joint Information Center will be activated for a Site Area Emergency and General Emergency. In the first few hours of an emergency (while the Joint Information Center is being activated) Corporate Communications will provide an information clearing house from their current location. Should a crisis assume prolonged proportions after the center has been activated, Corporate Communications can provide additional personnel. The Joint Information Center, once activated, provides media representatives and public information officers immediate access to accurate emergency related information. The Joint Information Center contains equipment for document reproduction, telecopying, web access, communications, and televisionelectrical connections. The Joint Information Center is acentral clearing house forregular information exchange such that all parties have the most current and accurate information to communicate to the public. Attachment 5-6, Public information Flow identifies the flow of public information after Joint Information Center activation.

Revision 41

I. FACILITIES (Continued)

F. Laboratories

1. On-site The Chemistry Laboratory (Auxiliary Building) is available for emergency response during a design basis accident.. This availability includes design basis accidents that are coincident with a loss of off-site power. The laboratory can receive power from the plant's emergency diesel generators. General capabilities include:

Radionuclide identification in various sample media.

" - Analysis and~measurement of radionuclides in samples taken within the plant and sampls taken in the plant site and.offsite environment,

2. Off-site The General Services Division, Constellation Generation Group maintains a fixed counting laboratory in the Fort Smallwood Road Shops Complex. It is available in about two hours. General capabilities include:

Dosimetry of Legal Record processing.

Radiological Environmental monitoring equipment and sample media.

Radiological Environmental sampling, and analysis of soil, water, air, vegetation, etc.

Radiological Environmental Consulting.

G. Decontamination Facilities:

69 foot Auxiliary Building, Rad-Con area.

" Farm Demonstration Building (on-site). Serves relocated on-site personnel.

Calvert Memorial Hospital, Prince Frederick Revision 41

I. FACILITIES (Continued)

G. Decontamination (Continued)

These facilities contain provisions for radiological decontamination of personnel, their wounds, supplies, instruments and equipment. These facilities have extra clothing and decontaminants suitable for the type of contamination expected; including radioiodine skin contamination. Detailed inventory lists and instructions for these facilities are part of Emergency Response Plan Implementation Procedures. Waste disposal, subsequent to decontamination activities, is according to Radiation Safety procedures.

H. Medical

1. On-Site A first aid room located in the Auxiliary Building (69 foot level) facilitates medical treatment and initial assessment of radiation exposure and uptake.

Emergency Response Plan Implementation.Procedures provide detailed listing of emergency equipment kept there.

2. Off-Site Arrangements have been made for local and back-up hospitals and medical services having the capability for evaluation of radiation exposure and-uptake.

This arrangement includes assurance that persons providing these services are adequately prepared to handle contaminated individuals.; Arrangements with other hospitals having similar capabilities are contained in the Maryland.

Emergency Operations Plan, Annex Q, Radiological Emergency Plan.

Equipment kept at the local off-site facility is listed in the Emergency Response Plan.Implementation Procedures.-:

31. ..Transport Agreements are maintained for transporting victims of radiological accidents to dmedical support facilities.

Revision 41

lI. COMMUNICATIONS Emergency Response Plan Implementation Procedures describe the primary and backup means of communications between Calvert Cliffs Nuclear Power Plant, local, State and Federal response organizations. Systems are compatible with one another and include:

A. A minimum of a telephone link and alternate (State/local).

B. Provision for communications with contiguous State/local governments within the Emergency Planning. Zones.

C. Provision for communications as needed with Federal emergency response organizations.

D. Provision for communications between Plant, Emergency Operati6ns Facility, State and local emergency operations centers and radiological monitoring teams.

E. Provision for alerting or activating emergency personnel in each response organization.

F. Provision for Calvert Cliffs, Nuclear Power Plant communication with NRC headquarters and NRC. Regional Office Emergency Operations Center and the Emergency Operations Facility and radiological monitoring team assembly area.

G. Coordinated communication link for fixed and mobile medical support facilities.

lII MONITORING INSTRUMENTATION A. Geophysical Phenomena Monitors

1. On-site

a. Meteorological/Hydrologic

1) Primary Systems: Meteorological tower is equipped with:.

1O1m & 60m - wind speed/direction'sensors.

Revision 41

IIl. MONITORING INSTRUMENTATION (Continued)

A. Geophysical Phenomena Monitors (Continued) 1Om to 60m - Temperature Gradient System with Aspirated Radiation Shields and Rosemount Bulb sensors (10m & 60m ambient temperature).

" Ground level Precipitation Gauge.

2) Backup System: The Emergency Response'Plan Implementation Procedures provide instructions for accessing back-up meteorological data in the event the primary meteorological data becomes unavailable.

This equipment is used to initiate emergency measures according to Emergency Response Plan Implementation Procedures, Emergency Action Levels. Primary systems produce current local meteorological data that provides the means to estimate radioactive material dispersion due to accidental, atmospheric releases by the plant and is consistent with recommendations addressed in Safety Guide 23, as supplemented by Supplement 1 to NUREG-0737. The backup system utilizes near site meteorological data that provides

. .information when the primary, system is out of service.

b. Seismic

The updatedFinal Safety Analysis Report (Reference 55): Section 7.5.7 identifies seismic monitoring systems -ised to initiatenemergency classification according to Emergency Response Plan Implementation Procedures.

Revision 41

((II MONITORING INSTRUMENTATION (Continued)

A. Geophysical Phenomena Monitors (Continued)

2. Off-Site

a. Agreements are maintained with off-site agencies to acquire geophysical phenomena monitor data for emergency access when necessary. These agencies are identified in the Emergency Response Plan Support Services listing.

b. Regional meteorological information is available via communication with the National Weather Service. At CEG's Electric Systems Operations Building, Rutherford Business Center capabilities include weather radar monitor and National Weather Service information via the satellite based data system, (National Weather Wire System) from the

'Washington WeatheraForecast'Office in Sterling, Virginia.

B. Meteorological Model, A Class A, atmospheric transport and diffusion assessment model (Ref. 21, App. 2) is maintained on independent, redundant, computers in the Control Room, Technical Support Center, and Emergency Operations Facility (includes a separate computer for state use).

Provisions exist-for NRC modem access to meteorological parameters. The variable trajectory, puff advection, atmospheric dispersion model is used to determine the magnitude of the impact of an accidental release of rdioactivity and provides continuous real time (s the release is occurring) assessment of predicted effluent transport and diffusion. The modeluses input from meteorological data systems and source term

-estima~tes~to provide estimates of dose rates, and dose to 10 miles, and deposition rates, total deposition and subsequent gamma exposure:from contaminated ground to 50 miles.

The model accounts for source decay, plume depletion mechanisms, building wake, plume rise and mixing height. For the 10-mile EPZ, the model uses finite cloud techniques to estimate plume exposure dose irates, four-day external dose rates from deposition, thyroid dose rates and dose rates due to inhalation.

Revision 41

III. MONITORING INSTRUMENTATION (Continued)

B. Meteorological Model (Continued)

Accumulated dose is calculated as the sum of external exposure to the plume, internal exposure due to inhalation in the plume and external exposure to ground deposition according to EPA-400: guidance. A complete description is referenced in the Emergency Response Plan. Implementation Procedures and in the RADDOSESystem documentation.

C. Radiological Monitors The Updated Final Safety Analysis Report (Reference 55) Chapter 11lidentifies radiological monitors (e.g., process, area, effluent, wound and portable monitors and sampling equipment) available for initiating emergency measures according to Section 2, Emergency Conditions. Specific instruments are incorporated in Emergency Response Plan Implementation Procedures..

D. Process Monitors The Updated Final Safety Analysis Report (Reference 55) Chapter 7, identifies process monitors (e.g., reactor coolant system pressure and temperature,6coitainmrent pressure and temperature, liquid levels, flow rates, status or line-up of equipment components) available for initiating emergency measures according to Section 2, Emergency Conditions. Specificinstruments are incorporated in Emergency Response Plan Implementation Procedures.

E. Fire/Combustion Monitors The Updated Final Safety Analysis Report (Reference 55) Section' 9.9, identifies fire and combustion products detectors available for initiating emergencyý, measures according to Section 2, EmergencyCo':nditions.

Revision 41

IIt[. MONITORING INSTRUMENTATION (Continued) -

F.. Field Monitoring Emergency Response Plan, Implementation Procedures describe field monitoring capabilities and resources within plume exposure Emergency Planning Zone which are intrinsic to Calvert Cliffs Nuclear Power Plant's conceptof operation. These capabilities include transportation and monitoring equipment (dose ratemeters and sampling devices). Sampling devices are capable of detecting and measuring radioiodine concentrations in air as low as I E-7 uCi/cc under field conditions. Interference from noble gas presence and'background radiation do not decrease the stated minimum detectable-activity.: Maps identify: preselected sampling and monitoring points using sector and zone designators such as those in Reference 2 1, Table J- 1.

G. Environmental Monitoring The Updated Final Safety Analysis Report (Reference.55), Section 11.2.3.4 and Offsite Dose Calculation Manual, describe the off-site radiological monitoring program for the area surrounding Calvert Cliffs Nuclear Power Plant. Appropriate equipment is provided to facilitate this program. The monitoring equipment meets, as a minimum, the NRC Radiological Assessment Branch Technical Position for the Environmental Radiological Monitoring Program...

H. Post Accident Sampling The Updated Final Safety Analysis Report (Reference 55),Section*9.6.2.2 describes capabilities and resources available to provide initial values and continuing assessment through the course of an accident for post accident samplinhg. 'Capability to sample and

'analyze the containment atmosphere and Reactor Coolant.System meets or exceeds NUREG 0737, Item 1l.B.3requirements as modified by Calvert Cliffs Nuclear Power Plant's submittals to NRC. Calvert Cliffs Nuclear Power Plant procedures detail system operations .

Revision 41

I!1. MONITORING INSTRUMENTATION (Continued)

I. In-plant Iodine Instrumentation Radiation Safety Procedures and Emergency Response Plan Implementation Procedures describe in-plant iodine instrumentation which provides on-site capabilities for determining initial iodine values and continuing assessment through the course of an accident.

IV. EMERGENCY KITS Emergency Response Plan Implementation Procedures identify emergency kits/lockers and their contents (protective equipment, communications equipment, radiological monitoring equipment and emergency supplies).

V. RESPIRATORY PROTECTION Radiation Safety Procedures provide for individual respiratory protection for individuals remaining or arriving on-site during emergencies.

VI. PROTECTIVE CLOTHING Supplies of apparel include coveralls, rubber gloves, shoe covers and boots, and hoods.

Inventories are maintained for normal plant use by Radiation Safety personnel. Emergency clothing supplies are kept at specific areas and emergency centers. This clothing is issued to personnel required to enter areas of known or suspected radioactive contamination. For emergency conditions, normal street clothing is considered as protective apparel. It can be supplemented, as necessary, to protect skin surfaces.

VII. RADIOPROTECTIVE DRUGS Emergency Response Plan Implementation Procedures provide for use of radioprotective drugs (e.g., individual thyroid protection) for individuals remainingor arriving on-site during emergencies.

Revision 41

AT1'ACHMENT 5-1 FACILITY FUNCTIONAL OBJECTIVES Emergency Operations Facility (EOF) 1) Managing overall CCNPP response.

2) Coordinate response activities with Federal, State and County agencies'.

3) Coordinate radiological and environmental assessment.

4) Determine recommended protective actions.

5) Receive and analyze of field monitoring data and coordination of sample media.

4 Technical Support Center (TSC) 1) Provide plant management and analytical support to Operations personnel during emergency conditions.

2) Relieve reactor operators of peripheral duties and communications not directly related to reactor system manipulations.

3) Prevent congestion in the Control Room.

4) Perform EOF functions in Alert, Site and General Emergency, until the EOF is functional Operational Support Center (OSC) 1) Provide and coordinate logistic support (i.e.,

maintenance, etc. to bring the plant to a safe, stable condition).

2) Restrict Control Room access to personnel specifically requested by Shift Manager or General Supervisor-Nuclear Operations.

3) Provide and coordinate engineering support for TSC and EOF.

Joint Information Center (JIC) 1) Provide media representatives with immediate access to accurate emergency related information, generated by all involved agencies.

2). Provide equipment for document reproduction, telecopying, communications, and television electrical connections.

Revision 41

UPPER STATUS PLENUM ROOM U,

STATE.' NRC /

LOCAL FEMA

-- MECHANICAL MICROWAVE TELEPHONE/ MENS WOMENS SECURITY ROOM ELECTRICAL EXTRA ROOM ROOM ROOM ENTRY yWL Storage MOE NRC CONFERENCE ROOM ROOM ROOM AUDIO/E VIDEO

" f I ROOM LUNCH ROOM DOSE STATUS ASSESSMENT ROOM SUPPLY ROOM STAIRS 0 0

ATTACHMENT 5-3 EMERGENCY OPERATIONS FACILITY AND JOINT INFORMATION CENTER LOCATION Revision 41

S ATTACHMENT 5-4 TSC LOCATION RELATIVE TO CONROL ROOM TtLRBlfra u4LL XAccess to TSC fromt EL. -i5' Revision 41

ATTACHMENT 5-5 CHARACTERISTICS OF TECHNICAL SUPPORT CENTER VS. EMERGENCY OPERATION FACILITY

.e;.Control Room and Operational Support Center)

CONTROL ROOM & TECHNICAL SUPPORT CENTER OPERATIONAL SUPPORT CENTER Activities performed by trained, licensed Activities performed by high level engineering operators in the Control Room supported by OSC and management personnel. Supported by the maintenance engineering staff. OSC engineering staff.

0 Actions based on: 0 Actions based on:

Specific procedures to assure success of

Accident management strategies derived safety functions (criticality control, core from likely paths to core melt and coverage, heat removal, containment) containment failure.

Reaction to plant symptoms (flux, flows,' Anti cipation of potential problems or pressures, temperatures) phenomenon Success-oriented (goal is to bring plant to a safe " Defensive strategy (do what is necessary to save stable condition) the core and containment)

Limited number of options prescribed

Broad range of options in response to unfolding events

" Requires authority to overrule established Strong incentives for adherence to procedures procedures 4 Actions should be unambiguously beneficial

Actions may have negative side effects

Time for decision making on order of minutes

Time for decision making on order of hours to days. .

Revision 41

Nitc ATTACHMENT 5-6 PUBLIC INFORMATION FLOW

- Normal Information-Flow

.......... Back-up Information Flow Revision 41

CALVERT CLIFFS NUCLEAR POWER PLANT EMERGENCY RESPONSE PLAN MAINTAINING PREPAREDNESS TRAINING An integrated training program provides for andensures initial, annual, and continuing training of appropriate individuals and groups involved in emergencies.

A. General Orientation General Employee Training describes the program that provides training to all persons having access to Calvert Cliffs Nuclear Power Plant and includes Emergency Response Plan indoctrination.

B. Emergency Personnel Plant procedures establish a training program for instructing personnel who implement radiological emergency response plans. Specialiied initial training, annual, and continuing training programs (including scope, nature and frequency) is provided for:

1. Directors or coordinators of response. organizations.

2: Personnel responsible for accident assessment.

3. Radiological monitoring teams and radiological analysis personnel.

4. Security and fire fighting personnel...

5. Onsite repair and damage cohtrol/correctional action teams.

6. First aid and rescue personnel. This training includes courses equivalent to or exceeding Red Cross Multi-Media..

7. Local support services personnel including Emergency Management/Emergency Services personnel. :Site specific training is provided to ihose off-site oiganizations'who may ie called upon to provide assistance.

Revision 41

TRAINING (Continued)

B. Emergency Personnel (Continued)

8. Medical support personnel.

9. Recovery Organization personnel.

10. Personnel responsible for transmission of emergency information instructions.

The training program for members of the emergency organizations includes practical drills in which individuals demonstrate ability to perform assigned emergency functions.

C. Public

1. Calvert Cliffs Nuclear Power Plant coordinates annual updating and dissemination of information to the public regarding how they will be notified and what their actions should be. in an emergency. The information includes but is not necessarily limited to:

a. Educational information on radiation.

b. Contact for additional*information;

c. Protective. measures, e.g., evacuation routes and relocation centers, sheltering, respiratory protection, radioprotective drugs.

d. Special needs of the handicapped.

Means for accomplishing this dissemination include publication distribution, information in telephone books, and signs or notices to refer the transient population to the phone directory or other source of local emergency information.

This program provides thiepermanent and transient adulit*opulation within the plume exposure Emergency Planning Zone an adequate opportunity to become aware of the information annually., P.ublications and information provide written material that is likely to be available in a residence during an emergency.

Revision 41

I. TRAINING (Continued)

C. Public (Continued)

2. Calvert Cliffs Nuclear Power Plant disseminates information annually to acquaint news media with emergency plans, information concerning radiation, and points of contact for release of public information in an emergency.

D. Emergency Preparedness Unit Emergency Preparedness Unit maintains a training program for Emergency Preparedness Unit members responsible for the planning effort. Training includes attendance at emergency planning seminars, information workshops and training classes, and literary reviews..

II. EXERCISES AND DRILLS Plant procedures provide for periodic exercises to evaluate major portions of emergency response capabilities; drills to develop and maintain skills; tests to verify communications operability; and correction of deficiencies identified as a result of any of the preceding. During drills, on-the-spot correction of performance errors is made with a demonstration of proper performance offered by the controller. Correction of errors made in exercises is through Self-Assessment and Corrective Actions programs described in plant procedures.

III. PROGRAM RESPONSIBILITY The Director-Emergency Preparedness has Corporate authority and responsibility for Calvert Cliffs Nuclear Power Plant radiological emergency response planning. This responsibility includes emergency plan development and updating and coordination of plans with other response organizations.

IV. EQOUIPMENT INVENTORY AND MAINTENANCE Emergency equipment and instrumentation ae inspected, inventorieddand/or operationally checked once each calendar quarter, after each use and/or whenever tampering is suspected.

Revision 41

IV. EQUIPMENT INVENTORY AND MAINTENANCE (Continued)

Equipment calibration is according to plant procedures that endorse manufacturers' calibration recommendations. Sufficient reserves are available to replace items removed from emergency kits for calibration and repair.

V. PROGRAM REVIEW AND UPDATE A. Calvert Cliffs Emergency Response Plan and plant procedures and agreements contained there-in are updated as needed. Updates include changes identified by drills and exercises.

B. Calvert Cliffs Emergency Response Plan and Emergency Response Plan Implementation Procedure changes and revisions shall be reviewed by the Plant Operations and Review Committee. The Plant Operations and ReviewCommittee shall submit recommended changes to the Nuclear Safety Review Board according to plant procedures.

C. Calvert Cliffs Emergency Response Plan and Emergency Response Plan Implementation Procedures and approved changes are forwarded to appropriate organizations and individuals having responsibility for their implementation. Revised pages are marked to show changes, except where changes are extensive.

D. The Calvert Cliffs Emergency Response Plan is certified by the Director-Emergency Preparedness to be current on an annual basis. Emergency Response Plan Implementation Procedures are certified by the Directoi-Emergency Preparedness to be current on a biennial basis.,

E. Documents that are associated with the Calvert Cliffs Emergency Response Plan that.

contain telephone numbers are updated quarterly.

F. Emergency Preparedness will ensure that all emergency preparedness program elements are reviewed by persons who have tio dired res9pnsibility for the implementation 'ofthe emergency preparedness program either.:.....,

1. At intervals not to exceed 12 months or, Revision 41

V. PROGRAM REVIEW AND UPDATE (Continued)

2. As necessary, based on an assessment against performance indicators, and as soon as reasonably practicable after a change occurs in personnel, procedures, equipment, or facilities that potentially could adversely affect emergency preparedness, but notilonger than 12 months after the change. In any case, all elements of the emergency preparedness program are to be reviewed at least once every 24 months.

This review includes an evaluation for adequacy of interfaces with the State and local governments and of drills, exercises, capabilities, and procedures. The Director - Emergency Preparedness will evaluate and correct review findings.

The results of the review, along with the recommendations for improvement, must be documented and reported to corporate and plant management., Parts of the review involving the adequacy evaluation of the interface with the State and local governments are made available to them. Review results are retained for five years.

G. Annually, emergency action levels are reviewed with State and local government authorities.

VI. RECORDS A. Plant procedures describe retention requirements for records generated as a result of the implementation of the Emergency Response Plan.

B. Records pertaining to the independent review of the emergency preparedness program will be collected, stored, maintained and retrieved according to plant procedures.

Independent review records include:

1. Review report (includes findings and recommendations).

2. Review findings and recommendations resolution.

3. Reports pertaining to interface with offsite agencies shall be made available to the appropriate state or local government.

Revision 41

CALVERT CLIFFS NUCLEAR POWER PLANT EMERGENCY RESPONSE PLAN REFERENCES

1. ANSI/ANS-3.7. 1.- 1979, American National Standard. for Facilities and MedicalCare in Onsite Nuclear Power Plant Radiological Emergencies.

2. ANSI/ANS-3.7.2.- 1979, American National Standard for Emergency Control Centers for Nuclear Power Plants.

3. ANSIIN320-1979, American National Standard Performance Specifications for Reactor Emergency Radiological Monitoring Instrumentation.

4. ANS-3.2/ANSI NI 8.7-976, Administrative Controls and Quality Assurance for the operations Phase of Nuclear Power Plants.

5. "Decontamination and Treatment of the Radioactively Contaminated Patient," Calvert Memorial Hospital and Calvert Cliffs Nuclear Power Plant..

6. Calvert Cliffs Nuclear Power Plant Operating License Unit 1,NO. DPR-53 and Unit 2 NO. DPR-69, including:

a. Appendix A, Technical Specifications (Safety)

b. Appendix B, Technical.Specifications (Enviromental)

7. Calvert Cliffs Nuclear Power Plant Procedures:

a. Nuclear Program administrative interdepartmental, departmental and section/unit Procedures

b. Radiation Safety Procedures, c.'. Nuclear Engineering Operating Instructions

d. Operating Procedures (Emergency Operating Procedures, Abnormal Operating Procedures, Operating Instructions)

e. Security Plan Implementation Procedures

f. Security Plan

g. Calvert Cliffs Safety Parameters Display.System Alarm Manual

h. Fleet Industrial Safety Manual L. Offsite Dose Calculation Manual Revision 41

8. Department of Health, Education, andWelfare, Food and Drug Administration, 21 CFR Part 1090, "Accidental Radioactive Contamination of Human Food and Animal Feeds" Proposed Rules, Federal Register, Vol. 43, No. 242, December 15, 1978.

9. Department of Health, Education, and Welfare, Food and Drug Administration Notice on "Potassium Iodide as a Thyroid-Blocking Agent in a Radiation Emergency," Federal Register, Vol. 43, No. 242, December 15, 1978.

10. Federal Radiation Council Report NO. 7, May. 1965, Background'Material for the Development of Radiation Protection Standards.

11. Final Safety Analysis Report (FSAR), Calvert Cliffs Nuclear Power Plant, Inc., Calvert Cliffs Nuclear Power Plant.

12. Markee,/E. H., "On the Relationships:of:Range to StandardDeviation~of the Wind Fluctuations, "Monthly Weather Review, Vol.91, No: 2 (February 1963).

13. National Councilon Radiation Protection Report NO. 39, January 15, 1971,w"Basic Radiation Protection Criteria."

14. National Council on Radiation Protection Report 53 March I',1977i "Review of NCRP Radiation Dose Limits for Embryo and Fetus in Occupationally-Exposed Women."

15. National Council on Radiation Protection, Report NO. 55, August l, 1977, "Protection of the Thyroid Gland in the Event of Releases of Radioiodine."

16. NUREG-75/087, Revision I. USNRC Standard Review Plan Section 9.5.1, Fire Protection Program, and Section 13.3, Emergency Planning.

17. NUREG-0396, EPA 520/1-78-016, November 1978, Planning Basis for thebDevelopment of Site and Local Government Radiological EmergencyResponse.Plans in Support of Light Water Nuclear Power Plants.:'

18. NUREG-0578 (extracts), July 1979, TMI-2 Lessons LelarnedTask Force Status Report and Short-Term Recommendations.

Revision 41

19. NUREG-'0600 (extracts), Investigation into the March 28, 1979 Three Mile Island Accident by Office of Inspection and Enforcement, dated August 1979.

20. NUREG-0610, USNRC Draft Emergency Action Level Guidelines for Nuclear Power Plants, dated September 1979.

21. NUREG-0654/FEMA-REP-1, Revision 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans for Preparedness in *Support of Nuclear Power Plants, November, 1980.

22. NUREG-0696, Functional Criteria for Emergency. Response Facilities, February, 1981.

23. D. Ramsden, F.H. Passant, C.O. Peabody, and R.G. Speight "Radioiodine Uptake in the Thyroid Studies of the Blocking and Subsequent Recovery~of the Gland Following and Administration of Stable Iodine, "Health Physics 13,633, Pergamon Press, 1967 (RA67).

24. Slade, D.H., "Dispersion Estimates from Pollutant Releases of a Few Seconds to 8-hours in Duration," Technical Note 2-ARL-I,ESSA, Washington, DC, (August, 1965).

25. State of Maryland Radiological Emergency Plan, (July, 2007 Revision:l0), Annex'Q.

26. Title 10, Code of Federal Regulations.

a. Part 20, Standards for Protection Against Radiation.

b. Part 50, Licensing of Production and Utilization Facilities.

c. Part 50, Appendix E, Emergency Plans for Production and Utilization Facilities.

d. Part 50, Appendix E, Emergency Planning and Preparedness for Production and

- Utilization Facilities, Proposed Rule, Published in the Federal Register on August 29, 1979

e. Part 1i00, Rkeator Site Criteria

27. U.S. NRC, Emergency Planning Review Guideline Number One-Revision One-Emergency Planning Acceptance Criteria For Licensed Nuclear Power Plants, dated September 7, 1979.

28. U.S. NRC, SECY-79-450, dated July 23, 1979, Action Plan for Promptly, Improving Emergency Preparedness.

Revision 41

29. U.S. NRC Regulatory Guide 1.16, Revision 4, dated August 1975, Reporting of Operating Information - Appendix A, TechnicaliSpecifications.

30. U.S. NRC Regulatory Guide 1.21, Revision 1, Dated June 1974, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants.

31. U.S. NRC Regulatory Guide 1.23, proposed Revision 1, September 1981, Meteorological Programs in Support of Nuclear Power Plants.

32. U.S. NRC Regulatory Guide 1.97, Revision 2, December 1980, Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident.

33. U.S. NRC Regulatory Guide 1.70, Revision 3,:Standard Format and Content'of Safety Analysis Reports for Nuclear Power Plants, Section 13.3, "Emergency Planning."

34. U.S. NRC Regulatory Guide 1.120 (for comment), Revision I dated November 1977, Fire Protection Guidelines for Nuclear Power Plants.

35. U.S. NRC Regulatory Guide 1.109, Revision 1, Dated October, 1977, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1.

36. Report to NRC prepared by Combustion Engineering, Inc., and submitted by Baltimore Gas and Electric as 'Environmental Impact of Extended Fuel Cycles in Calvert Cliffs Units I and 2."

November, 1979..

37. Calvert Cliffs Fire Fighting Strategies Maual.

38. Emergency Response Plan Implementation Procedures, Calvert Cliffs Nuclear Power Plant.

39. "Emergency Resources Manual (RP/EP-I)," Institute of Nuclear Power Operations.

40. NUREG/CR-13 11, October, 1979 "Examination of Offsite Radiological Emergency Protective Measures for Nuclear Power Accid6nts Involving: Core Melt.'

41. CCNPP Operating Procedures, OP-2 Rev. 5, April 1979, "Measurements of Radionuclides in Milk."

Revision41

42. CCNPP Operating Procedures, OP-4 Rev. 9, March 1980 "Procedures for Collection and Radioanalysis of Aquatic Samples."

43. CCNPP Operating Procedures, OP-5 Rev. 7, August 1979, "Collection and Radioanalysis of Terrestrial and Atmospheric Samples."

44. CCNPP Operating Procedures, OP-6 Rev. 3, June 1978, "External Radiation Dose Rate Measurements."

45. Commonwealth of Virginia, Radiological Emergency Response Plan (RERP).

46. State of Delaware, Radiological Emergency Plan (REP).

47. District of Columbia, District Response Plan.

48. NUREG-0818, October 1981, "Emergency Action Levels for Light Water Reactors" Draft Report for Comment.

49. "Upgraded Public Alert and Notification System for Calvert Cliffs Nuclear Power Plant,"

September 2002.

50. Updated Safety Analysis Report for Independent Spent Fuel Storage Installation.

51. Regulatory Guide, 1.101, U.S. NRC, Emergency Planning For Nuclear Power Plant.

52. USNRC Safety Guide 23, February 1972, "Onsite Meteorological Programs."

53. NUREG -0737, November 1980, "Clarification of TMI Action Plan Requirements."

54. NUREG-0737, Supplement 1, January 1983, "Clarification of TMI Action Plan Requirements:

Requirements for Emergency Response Capability."

55. Updated Final Safety Analysis Report (UFSAR), Calvert Cliffs Nuclear Power Plant, Units I and 2, Calvert Cliffs Nuclear Power Plant, Inc.

56. Nuclear Crisis Management Protocol, Business Continuity Program.

57. Calvert County REP and SOP.

58. St. Mary's County REP and SOP.

,' .*".*' . .. Revision 41 Revision 41

59. Dorchester County REP and SOP.

60. EPA manual of PAGs and Protective Actions for Nuclear Incidents, October 1991 (EPA-400-R-92-001).

Revisionf4l

APPENDIX A LIQUEFIED NATURAL GAS CONTINGENCY DEFINITIONS A. Liquefied Natural Gas Liquefied natural gas is mainly methane gas cooled to about -260'F so it changes from a gas to a liquid.

B. Methane

.Methane is a colorless, odorless gas that is flammable in concentrations of 5% and greater. It is positively buoyant with respect to iir above about 60'F.

II POTENTIAL THREAT The relative proximity of the Cove Point Liquefied Natural Gas Terminal to Calvert Cliffs Nuclear Power Plant creates the possibility that Aibnormal occurrences at the Liquefied Natural Gas Terminal, such as a spill of Liquefied Natural Gas, couldpose a potenfial thteat to the safety to equipment and/or personnel at Calvert Cliffs Nuclear Power Plant.

The worse case occurrence at Cove Point with respect to. Calvert Cliffs Nuclear Power Plant would bea large scale 25,000 m3 spill of Liquefied Natural Gas from an Liquefied Natural Gas tanker, directly onto the surface of the Chesapeake Bay in the vicinity of the unloading pier. Such a spill is postulated to occur if a Liquefied Natural Gas-laden tanker is involved in a collision with another vessel w4iereby one or more of the Liquefied Natural Gas tanks aboardthe tanker is ruptured. Releases of a smaller size or release from an onshore storage tank have bee- analyzed and shown to pose no significant thieat at Calvert Cliffs Nuclear Power Plant (Liquefied Natural

. A., B1,'and C).

Gas References Revision 41

I. POTENTIAL THREAT (Continued)

A significant Liquefied Natural Gas spill to the Chesapeake Bay from a ruptured tank of an Liquefied Natural Gas tanker in the vicinity of the Calvert Cliffs Nuclear Power Plant poses two potential hazards to the personnel and/or operations of the plant. With appropriate atmospheric and bay conditions, a methane vapor cloud emanating from a spill.could extend from the spill area to the plant vicinity, engulf portions of the plant, and then ignite.

The resultant heat energy released could be hazardous to personnel and could damage equipment.

Additionally, should a flammable concentration of methane vapor fill a confined space or room, an explosion could occur if it ignited. A specific hazard created by methane vapor is the possibility of asphyxiation if the concentration is great enough to reduce oxygen to below minimum life-support levels (approximately 17%).

The development and subsequent dispersion of a methane vapor cloud could occur as follows:

Liquefied Natural Gas (a very cold liquid) is lighter than water and insoluble in water and will form a pool on the surfacelof water if spilled. As it pools, it absorbs heat from the water.

Heating Liquefied Natural Gas causes it. to vaporize into methane gas. As the Liquefied Natural Gas pool spreads, the rate of vapor generation increases because there is more surface area for heat absorption: The diameter of the resulting vapor cloud normally will be much greater than its height, since vertical mixing will be inherent.-due'to local temperature inversion by the still cold methane gas cloud. :Although methane vapor is colorless, the cloud will appear-white dUe to condensation and/or freezing of water vaporucondensed from atmosphere onto the cloud surface.

The initial bulk temperature of newly vaporized methane is approximately -250'F. -At this temperature and at atmospheric pressure, methane vapor is approximately 50% more dense than ambient air. Consequently, there is no.tendency for the cloud to rise. Experimental data indicates that the vapor cloud continuesto spread radically, and there is very little vertical dispersion. Entrainment of air increases the cloud temperature, but generally, the density of the mixture remains above that of the diluting air. In instances where the heat input from the surface of the water, and/or heat input from the condensing and freezing of atmospheric water vapor is significant, the vapor cloud may become positively buoyant, thus terminating the threat to Calvert Cliffs Nuclear Power Plant since the methane will rapidly mix vertically and disperse. "

Revision 41

II. POTENTIAL THREAT (Continued)

Once a methane cloud begins to form, atmospheric and wind conditions may be such that the cloud could propagate toward Calvert Cliffs Nuclear Power Plant. Wind speeds of 5-15 mph with stable atmospheric conditions and wind direction from the spill to the plant are necessary to transport the cloud to Calvert Cliffs Nuclear Power Plant. As the cloud moves downwind, it is further diluted and dispersed by turbulent mixing withsurrounding air. In the absence of ignition, this process would continue until the concentration of methane in the cloud reduced to the Lower Flammability Limit, about 5%methane, and the methane is totally dispersed into the atmosphere (on the order of 20 minutes).

If at any point in tie vapor cloud the methane concentration is between, 5% and 15% (Lower Flammability Limit and Upper Flammability Limit, respectively) and an ignition source is present, the vapor cloud willignite. It will then slowly burn back to the source of the spill at a rate dependent upon the wind conditions. The cloud continues to bum until the concentration of methane is reduced below 5%.

A land-based spill at Cove Point will present no hazard to the plant or to plant personnel. This is principally due to the limited heat source provided by land versus water for Liquefied Natural Gas vaporization and intervening terrain between Cove Point and Calvert Cliffs Nuclear Power Plant.

An accidentt will threaten the safety of the plant and personnel 'only if it is a major-Liquefied Natural Gas spill from a tanker and the meteorological and bay.conditions are such that the resulting vapor cloud can travel the 3 to 4 miles to Calvert Cliffs Nuclear Power Plant. If there is no vapor ignition, the major concern is protection of the plant personnel in an oxygen deficient atmosphere.

If the plume ignites away from the plant structure additional concern is to heat flux generated by the burning cloud that could harm exposed personnel. By taking appropriate actions, hazards to plant personnel could be avoided, and threats to safety of the plant can be minimized.

Revision 41 -

III. CONCERNS AND ACTIONS IN A LIQUEFIED NATURAL GAS EMERGENCY The exclusion of methane from the Control Room is vital to plant safety and should be of utmost concern. Control Room ventilation system alignment must be considered as soon as a Liquefied Natural Gas threat is identified.

Plant operational needs will have to be considered and adjustments made if warranted.

Ventilation systems including the battery ventilation systems may have to be secured or isolated from outside intakes. Electrical lineups may have to be changed to preserve the ability of the plant to supply vital loads.

Doors and other outside openings to plant structures may. have to be secured.

Methane ignition could: result in a large scale fire in the vicinity of plant structures. Such a fire could place a significant heat load on equipment orcould result i serious personnel injury.

Methane incursion into confined spaces with subsequent ignition could result in an explosion.

Methane. concentrations may vary from area to area. Careful monitoring for methane*

concentrations in specific locations of interest, (i.e., insidea purmpmotor casing or inside of an electrical panel, etc.) should be performed prior togstarting up equipment.

Methane can asphyxiate and can result in dizziness, unconsciousness or even death if inhaled in sufficient concentrations. Personnel must take appropriate precautions.such as the .use of self-contained or airline respiratory devices.'

Access to the site could be affected by the presence of methane or a methane fire. Alternate means of routing assistance on-site and of removing personnel (e.g., for medical purposes) will be considered.

The free movement of personnel outside, of plant structures may be impossible, and thus early,,

prompt actions and decisions may be required.

Revision 41

IV. COMMUNICATIONS Emergency Response Plan Implementation Procedures describe communication networks between Calvert Cliffs Nuclear Power Plant and the Cove Point Liquefied Natural Gas Plant.

V. LIQUEFIED NATURAL GAS REFERENCES A. Liquefied Natural Gas (LNP) Hazards for Calvert Cliffs Nuclear Power Plant Final Report, May 28, 1993.

B. Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2, Liquefied Natural Gas Hazards Study, "Safety Evaluation by the Office of Nuclear Reactor Regulations (USNRC)

Regarding the Proximity of the Cove Point Facility," March 13, 1978.

C. Calvert Cliffs Nuclear Power Plant, Units I and 2, "Liquefied Natural Gas Hazards Update," March 9, 1978.

D. Risk Assessment Study for the Cove Point, Maryland Liquefied Natural Gas Facility, Science Applications, Inc. La Folla, CA, SIA-789-626-LJ, March 23, 1978.

E. Cove Point LNG Project Docket No. CPo 1-76-000. July 2001 F. NRC Letter to Calvert Cliffs Nuclear Power Plant, "Liquefied Natural Gas Hazard Analysis - Calvert Cliffs Nuclear Power Plant, Unit No. 1 (TAC No. M86704) and Unit No. 2 (TAC NO. M86705)." August 31, 1995.

G. Maryland Power Plant Research Program, "Cove Point LNG Terminal Expansion Project risk Study." June 28, 2006. DNR 12-7312006-147, PPRP-CPT-01.

H. Constellation Energy Nuclear Generation Group Letter to the U.S. Nuclear Regulatory Commission. "Calvert Cliffs Nuclear Power Plant; Unit Nos. 1&2; Docket Nos. 50-317

& 50-318, Independent Spent Fuel Storage Installation; Docket No. 72-8, revision to Hazards Analysis Related to Liquefied Natural Gas Plant operations at Cove Point."

February 20, 2008.

Revision 41

V. LIQUEF[ED NATURAL GAS REFERENCES (Continued)

I. NUREG-1407, "Protocol and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities." Final Report Published June 1991.

.. 9

-.. .9 Revision 41

APPENDIX B EMERGENCY RESPONSE PLAN DISTRIBUTION The Calvert Cliffs Emergency Response Plan and approved changes to the Emergency Response Plan are forwarded to all organizations and appropriate individuals with responsibility for implementation of the Emergency Response Plan. An Emergency Response Plan distribution list is maintained according to standard plant practices for document control.

The Calvert Cliffs Emergency Response Plan is submitted to the Nuclear Regulatory Commission (NRC)

Document Control Desk through standard plant practices for transmitting approved documentation to the NRC.

Revision 41

APPENDIX C EVACUATION TIME ESTIMATES" In April 2008 Constellation Energy instituted consultant KLD Associates, Inc. Revision I to the Evacuation Time Estimates (ETE). The ETE document is currently imaged in the Electronic Document Management System (EDMS). The document type is ETE.

Revision 41

APPENDIX D LETTERS OF AGREEMENT Letters of agreement between non-CCNPP and non-CEG agencies and individuals are maintained on file by the Director-Emergency Preparedness.

ATTACHMENTS

" Attachment D-1, Calvert County Volunteer Fire & Rescue Association.

Attachment D-2, Memo from Site Vice President assigning corporate authority to Emergency Directors

Attachment D-3, Calvert Memorial Hospital Emergency Department Staff Letter of Support

Attachment D-4, Radiation Emergency Assistance Center/Training Site (REAC/TS)

Attachment D-5, Department of Energy Brookhaven Area Office dated 2002 - update not required per letter.

Attachment D-6, Institute of Nuclear Power Operations dated 2008 - updates not required per letter

Attachment D-7, Delaware Geological Survey, University of Delaware.

" Attachment D-8, Memorandum of Understanding Regarding Communications Between Cove Point LNG Plant and the Calvert Cliffs Nuclear Power Plant

" Attachment D-9, CCNPP Health Physics (Radiation Safety) Guidance and Assistance for Calvert Memorial Hospital o Attachment D- 10, St. Leonard Volunteer Fire Department and Rescue Squad. (Alternate assembly location)

Attachment D- 11,Solomons Rescue Squad and VFD (Alternate assembly location)

Revision 41

ATTACHMENT D-I CALVERT COUNTY VOLUNTEER & RESCUE ASSOCIATION CALVERT COUNTY VOLUNTEER FIRE & RESCUE ASSOCIATION 175 Main Street Prince:Frederick,Maryland 2067-88 Calvert Cliffs Nuclear Power Plant 1650 C.so Clit Parkway Lub. ý .~ad2.0657 Thle Calv~er couinty Fire&Rm eAscain memb.er departmonts -iand pei ccpt~nia serics esombl~~ & t'oidngfire Afighugemergency mdki

-aervices kincuding transport ofihour.,d) and other emergency assistance. to tbe.- Calvert CUMff! Nuclear Power Plua in support of Calvert Cliffs Nudpau- Power Puant's This-as.c wi be implemened:at therequest of tho Calvert' Cli. Ntcxdi PoWer

,P]antomtixngAm upon euip t _a.ilabiity, with consid Wetifor ovcral ftire and*

Irili" itufrmatio. exchange AiHi be coodinated throughthe Caler Coumuy C- 9W*~mf"9LContrat canter.

Jr &o calvert Cont Fi*&

--- 9 eAmdI

'--1 tw Revision 41 -

ATTACHMENT D-2 MEMO FROM SITE VICE PRESIDENT ASSIGNING CORPORATE AUTHORITY TO EMERGENCY DIRECTORS CaIlvert Clif Nuclear Power Plant INTERNAL CORRESPONDENCE Septem:ber 5,20 TO, StoMner FRONK Jumes pina maen- xaCNPatonyResponse PLan amntd s t6e Ey.Dfr torRe y (PD/Mndtnii- tep MiaenwfIs~da nainiions aý ibs~rhid.~pbCs hat t4sftya nld pe~ctir si~y ier.1 margeny cnton.Ti clde qurn the ýsrvice of. banyopgny employees or grouip a.s noIcassary to.support tim I meiitaionoof rm~the togn~ RsouePAn. ntl ED/R-M positioni is Stgffod, Jte Shffl M~aager- act3smthe, Interim.6ED with the full autority of tha officei Yoiwap~ otbe P/Mahd thc Em ergmsoy 0epoa Wogniiw (1390) is ocecsaiy to Please ensureyourpeO* we atAWar of #mee condifions.

Stevn.M sPWe V~eo dent- ~1ver~ C Thcletir Po~r1~Int Revision 41

ATTACHMENT D-3 CALVERT MEMORIAL HOSPITAL EMERGENCY DEPARTMENT STAFF LETTER OF SUPPORT I"$O C&Ivt,.ay. tncuft.fl*wm Iu-ask zo5T Gavrt of fts Nuclear Power Plantt December 3, 200S Calvert Memnorial Tiospital 100 Hospital Road Prhice Frederik,, MID '20678

(CMXI woul prm ovitle 1 !+rpl n .i "~m tu o"*fm nj urics vosv hItm ad at on e po sur orc an minatiort. .

This eumer certifies MAs ag ceneaem betweenCAlvart ClifS Nuclear ftwer PlmAautAn the Calvert Memorial Hospital that in an emergency Lot situation a-.1-CNPP. all parties will.work tpgpther.: provie.*facilities =nd Fý: R .fS*p.ott-.*

hdSpftal care, as. uecessary dudtng-ridap~hgcal emelsency cven1s.

6 CCNPP sis0l) cotine i to .- . ,ansA to..

dies;* tt t dm! letters psM~ide, aecemsyý Mninlg %64CMJ Secefity and 13uOergny Rbamr staff associatcd with mudlaiodecouturfinaionu nd emecruency to" Of patiet1s.

o CCNPP shall provid P~~atd u Emergenc Aw stmoosr Centermi~aft.igSiw Z&rM ARAF)"tp triaini &ornihe OAk Vj'dV,.hntSutm to insgmenaey R6om Physiians ts s raaeaSSMy Imccp,

d WV*fthaml d lea!f health p&hysW:40 t sjsrit MH uigrdooial eontnzintitM tfont CCNP? P24rs#4a dbv a*,~a year.

-0 CalvertJmeutod4floOOOMM4 .... . "O SOOM A-e

()tnp il pnride novfcation three (3) mouths prior to costruct Mths lette rOfugrocumte sisal rmmnai ltzffbatuttil notified byeitbr to Iitt t=mna Q-4veru- l nt clvtMetrt osIa cwoý~tlIBziu Revision 41

ATTACHMENT D-4 RADIATION EMERGENCY ASSISTANCE CENTER/TRAINING SITE (REAC/TC)

Page I of2 Depart~ment of Energy Oak RidQGeO~ffi42*

PO. Box 2001 Oak Ridge. Tenressee 37631 October 27 2008 Mr..Steven C.Spex Diroctor Emrgetwcy Preparedness Calvertuliffs Nuclear Power Plant 1650 Calvert Cliffi Parkway Lusby, Maryland 20657

Dear Mr. Spect:

LETTER-OQ AGREEAM NT - RADIATION .EaERGECV:ASSISTANCE,

-CENTE-RfJhAMJNING:SMT (iUEACIS) SuppOIRT Pteae reference your letter of Oct*wbe 14, 2008 reqeting that the Department of Enerjgy (DOE) REACYAS facilities and team be availableito:provide back-up capability and assistance to thc.Calverit ClMNuclear Power Plant in the eventof a radiological emergecy. 'This response constitutes our agreement to provide this servitc upon your request.

We -wishto rcmind you that our-REACUS facilities in the Oak Ridge Institute for Sciec and Education (ORISE) ae governmem controlled and operated byt!e Oak Ridge Associated Universitics under contrat with DOE. Ttercefcir, RPACIT'S is

Pohibited from competing with commercial fimnn which can provide radiologitcg

ergency scrvices. Only if tie magnitude:or uniqueness.of a radiologica.:emergenCY

==eds your in4house and.con=m iaUy available capabilities would REAC/TS.be-authorized to provide back-up services.

Since these facilities ame goVCnirAWn controlindx 11 feeo*rlatain&ier srquirodin0 assure the aalabili asb .ack..i ~vcab REACflS. Kowe'iet if you u16tilzhe servicps of handlin1g such an WiicnitIncluding, all ch~rgcs bIlled tO DOE or ORISEti~ hoptl.n optian physicians.y Revision 41

ATTACHMENT D-4 RADIATION EMERGENCY ASSISTANCE CENTER/TRAINING SITE (REAC/TC)

Page 2 of 2 M~SC.pce 2October 27, 2008 lIdwuaton concerning- the R.BACISfc-iM taf ric viab~ n ieu Drector, Dr. Albart L. Wiley, OR;SE,M Oi'ffici Box 117, O6ki.Ri4g,Tezme*e 37831 or at telephone nunber (865) 576*3*.1.

6.n .

L. W * , MS-39, ORISE Revision 4.1

ATTACHMENT D-5 DEPARTMENTOF ENERGY BROOKHAVEN AREA OFFICE DATED 2002 - UPDATE NOT REOUIRED PER LETTER of 1 m* v, **m TIKI

S ,. .t - _ . . . -

4w Revision 41

S ATTACHMENT D-6 INSTITUTE OF NUCLEAR POWER OPERATIONS DATED 2008 - UPDATES NOT REQUIRED PER LETTER No" la~ tgeof AIOMi A4 &W39-77-44-8"C 543 tax ?-6E44-54i Soptember 30, 2008

Dear Ladies and Gentlemen:

ThiS' ettw celfifies that fte plant.emergen 'asiskt~anclle gremetbetwcen NPO and: its m uti~ities remains in effect. I te e ofan e=gn 6* .y at :your ilfty, 1NPO winl iasit i~acquiing t, c help of othe anztosi in eidity.a described It SectionlIofthe En Resources Argencmy Mnuaf,:INPO 3:001. If mquested, INPO will provide the following assistanee:.

Fatilitatetdrnkcal:infonmation flow. fromw teaffectedutilihy to the anclew, industry_

Locate replacmen equlpnmd ithdpesin with toahrdoa1 expctaum

Owtan toc *imialufonat andiw tyednerg~dn ln component and symmmIS.

Ptiklcu IN*P( ~IIi t*ent)hcItt iuteem ior Thi acman encntwil ttcf'ocuniltertietd i witr~Shou you have quetias.plaseval arkLeke t 77064-86'1 r e-mail kmkems@iapoAor9.

GF.k Revision 41

ATTACHMENT D-7 D)ELAWARE GEOLOGICAL SURVEY, UNIVERSITY OF DELAWARE-Delaware Geological Survey October 27.ý 2)MS Mr. Ste-en Speer, nfroewo Fxamermcy Prepaxdns 1650..Calvert QijM~pui Pzway Lusbyý.MWrytand.2063 Pcar~.ft erer Sui~t~ (IIS)wil be*bl W rov deismic, infoajxoton toYO yo mht itolanfri k esic iewdk.M It is aloademn4u'dilw nq~wol uzoslly benvassociated wihi 8A ca~hqzalo mte vditty f a fvt atiffStfraz w.AJsta cmhak&tcui fe h Ca~rUIb~wr lIn. ha data that we obtaairmbezlj a-ouseisntic stations ate avalslA: fiapon -46~

ThflScurnc pcra~tv a-fiesainnlui ewn nfllws yBO W) E) lNA t~d CM) BD~ WD NDatkloame 4t ikotwINe Coiny )li( NEDo i oat ne*~th brdetflewCatl ad er eumcs a&SCm i51oc*4nisj Co*uty M he 0~ucKeuw hocaxsn onttguKeom r faaei~k~ k~ ~tenriesan uiWs qtiat m azdSac~ a eluah a~ l& lo~~ k zalnC ne ~ aan yb U.15 aae uvyUG) ~aixsofteDSsain r tsando h ne -

S e dd lkw- ca 'h 3 Z 3-53~r3$

seomc4b n i lo~gcmasp t~~~~~Iceac~~~~~~~

hstt iozattifoladQ nyqeto Revision 41

ATTACHMENT D-8 MEMORANDUM OF UNDERSTANDING REGARDING COMMUNICATIONS BETWEEN COVE POINT LNG PLANT AND THE CALVERT CLIFFSNUCLEAR POWER PLANT Page I of 3 Memorandum of Understandi-g-

.g"arding commnicatliaus Between The flominjoat Cove int MLNG Plant and tke CaVert:CliffsNucear Power Plant nTHIS MoI*"*tMtM o.. UNDERSTANDING (MU) is :ma.e as..f t" 2A)C)I by and.. b et n Ce vck Cliff....dca C.,ii. t

.P.:- *a...as

.. t.e.

W .I 7S' C .. ei"eI*iý_

.Or<e" e -Oat'd:To FERC IZ 2"0"i, t*

establish un- n in $ C..tpesof#.Ojn.ida Io inci

.WhERPAýS,, C04, dcalsirsto 4egtabli acounMUniCstiou rtclbtweDh ate so tam airy~~1 type o:sfey ofkfý6tret o a;pm a scuit ýda Pointhe-.oxt ve Poone WIDREA, tre attsmi*pwIy desire that this MoIJ set.trbafan okfrsc commnicaionbut hat o. iabiity hal attch I th evet tht 'thi WaS, t6 Meet the aty comWunicaiCtons gxildeliues Set fodh herein.

A. Pa 112*~R(Tap& e reiteC-od aoer Covje Pitmýttbihadze~

linknd~ .$ov: Cam 094 cte ov o

~~ ~~een who Cockro ~ Point CW odo b V nW fX*1imanti wa..swnw Revision 41

ATTACHMENT D-8 MEMORANDUM OF UNDERSTANDING REGARDING COMMUNICATIONS BETWEEN COVE POINT LNG PLANT AND THE CALVERT CLIFFS NUCLEAR POWER PLANT Page 2 of 3 B- Nothiaziosl mnwal* owiiby o:Cowe Poin hll be .MWdeto CCNPP: using the meaiislisted below, ieofprozty:

I.fiec ie rdphone).

2. Radio. :

3. Commeicia phom to CCNPP Cetal

WM Station. (CAS) at 410-495-4692 r.. co. d r" " "Ala-Station at:410-495"4695-

4. commmewa pkorxe toý CCwfl'Opcrjt-wn'Shit Manaer a 410,49-501 5.omerclPhiOn Wo QCNPP W44~ Control Rom at41""94203 o C Notitcations by CCNshl be jade to Cow: Point. theons 0*in lUAWe below, 4m: the Follovaing ordi f rii

3. Cma*phmwto Cowi paiat.anage LNoipttip *12&-5 1.

(weekday - ddytme).

S. C. ,merci p. Coin POW .is ,.L**04 pe.o. a 4t... 6-

$10.

wekdy-daytime)

I. Co

"' imuf~inaci Pt, tcl4 oe o to COOP'*l

-Va~o~'otailds 1O h

2. ~ ~ ~ ~ ~ ~ wl tam--1spl~~rrabau a~eicm~w~oitma~ :r OtvpP.

Revision 41

MEMORANDUM OF UNDERSTANDING REGARDING COMMUNICATIONS BETWEEN COVE POINT LNG PLANT AND THE CALVERT CLIFFS NUCLEAR POWER PLANT Page 3 of 3 Ill. CnunicationsProtocol - CCN1PP to Cove Point A CCNP agrees to. notify Cove Point of the folbowing wmens related, to the CCNPP flicility.

I. Any situaion that the' aff of CCNPP control roomn or Security Directobelicves threatens the safe and/orsecmure operation of Cove Point and/or CCNPP.

IV. NoAbfi A.- NEITHER PARTY SH-ALL .m uERspoNSmiBL TO TM. OTNW FART ORANYTHID PARTY, ORcOTHERWI*SE A*0LE FOR.

IN1CBflI'IAL. INDIRE*CT, PUNATIE, XEMLARY, SPEaAJ. OW C EUMTI .A. OS IN CONNECTION W" INS MOYU (Wt~TU~ AIMN' INCONTRACTmp TORT STR ICT ABrI

~

OR ~ ICUIGWTHOUT

~ ~OhWIRf LtDMITATh)N. ANY L*oS$S OR .AIKA"O * *F OBY EASON OF UNAV*"A.,ABIlITYOF

.O..Sm..._. . ApLA.NT IL..T SUT ThT1RI~fO~I.LOSOF- USE. ?RET O VNE INVETORYOR- US9, CHARGES COS OF UHE)R REPACMNT OWE, ITERSTCHAP.E, COST OF CAMtTAt, ORcý CLN PCU-STO"MERS.

AGM"E ANI) ACCEPTED:-

OsA

~A2 DA i ....

Revision 41

ATTACHMENT D-9 CCNPP HEALTH PHYSICS (RADAITION SAFETY) GUIDANCE AND ASSISTANCE FOR CALVERT MEMORIAL HOSPITAL

. Costellation Energy Calvert Cliffs Nuclear Power Plant INTERNAL CORRESPONDENCE Letter of Agreement September 5, 2008 The ptutpose of this letter is to confirm an-agreement beWeff Calvert Memorial Hospital (CMID) and Constellation Energy. Calveitt Ctiffi Nuclear Power'Planit (CCNPP) to provide Health, Phy'sics.(Radiation Safety) guidanoc and assis*t e during an incident involving a radioactively contaminated injured patienrt Comnmwate with plant opering conditionsý Radiatikn Safety Techniciansnalth Physicatnds will be-available on a 24/7 basisto provide asistance. This includes, but is not limitedto. Radiologicl monitoringand exposure: ootrol, for anytypeof" idc (inctdng transpraion) tWnt.may invho radioactive mateilals. The approprinte contacts can be made by using the curren Rda ioa Emergrncy Telephonw Directory provida.in the Calvert Memorial Hospital Plan for Treatment and Decontamination of the Radioactive Contaminatcd Patient.

Steven C SPeer Director - Emergency Preparedness General Supervisor, Radiation Pitectim*--GNPP Revision 41

ATTACHMENT D-10 ST. LEONARD VOLUNTEER FIRE DEPARTMENT AND RESCUE SQUAD (ALTERNATE ASSEMBLY LOCATION)

Comtel-1Mo EnerW Calvert Cliffs Nuclear Power Plant To. Buddy Byer, Pesdent, StL L;6ozaid Volunteer Fi Department and Rescne Squad 200 Calvert BeDch Rcad P.O. Box 101o St. Lomud MD- 206s*S4101 Mr. Beyer.

o... .. te~ ...

TheClvevlfsEtrgnyRso D.ir ar.

.... n Team zequest-that Sqa .ecu etsdaftheporking

. tes4 "zgtgaeho t scearis tat ay resnt hissitatin is ifthere is an-ongoing security situab-On at the kit. In thi-S cnaiowe wouddQ* megnyprsie 10.~ orespu oa ~kwt' duty location ThW locatoe would beeither the Stonons Fire Dcpartsuent or the St.

Leonard Fim.Department.

It i eeyc osufkl f ievet ViAR 00cuu bocver, it is; ineveryone~s can be raew4at4O),9526" s ty Steven SPMr Dkirectr C~deruhm MCCMYPr~odienUuk fec/Loovls1L/tZ4 Revision 41

ATTACHMENT D-I I SOLOMON'S RESCUE SQUAD AND FIRE DEPARTMENT (ALTERNATE ASSEMBLY LOCATION)

CaXert Clivf CO Nt !NucerPwr Plant To: William Jonos President.SolowoMgS VolunteerRescue Squjad and FIreDeparmen 13150 .Trcwqa P.O. BOX 189 mr. Jones:

Tmen d*CpCme y Respom Team rm tat th*e *inareas t the Solomom's Rescue Squad-a* F*eDeparbuebe as a an em-rncy re tomotatc to C(NPPUsq*sisable. r oaf the scnarios that'may pnttant if there !s a t a t!toantthesite. In toaiaThat loainwudt dhrh nosFr eateto hSt' Leonad Fire Deparment It is unlikely that.serpe**.e .will *oimwowevrý,itir inaveryaws best iuterst to be prepared -forany sinanoim if thi agreeinem'in, isDimpal~ le sign and return, this, documentat yi aletcnenec.W prw( thcut itrz"ta thi prtnrsipproids.Sheuld you have any questianons, ýas~d9 nt hedufta to call. I can be reached at (416G) 495452f&.

Steven Spr, Da c m astm.nE "OreoA Revision 41

0- W",~~*

APPENDIX E NUREG-0654 CROSS REFERENCE This appendix cross references the Emergency Response Plan with NUREG-0654, Revision 1, November 1980.

Numbered items in this appendix correspond to NUREG-0654. Missing items are items from NUREG-0654 that do not apply to the licensee.

I. INTRODUCTION J. FORM AND CONTENT OF PLANS Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS In addition to addressing the substance of all 1.1 criteria, the plans must, of course, define the facility or facilities and area to which the plans apply.

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II. Planning Standards and Evaluation Criteria A. Assignment of Responsibility (Organization Control) Planning Standard Primary responsibilities for emergency response.by the nuclear facility licensee, and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS L.a. Each plan shall identify the State, local, 1.II Federal and private sector organizations 1.111 (including utilities), that are intended to 3.VI be part of the overall response 3.VII organization for Emergency Planning 3.VIII Zones. (See Appendix 5).

b. Each organization and sub organization 1.111 having an operational role shall specify 3.1 its concept of operations, and its 3.III relationship to the total effort. 3.IV 3.V 3.VI 3.VII

c. Each plan shall illustrate these Att. 3-3 interrelationships in a block diagram. AUt. 3-4 Att. 3-5.

Att. 3-6

d. Each organization shall identify a 3.III.A' specific individual by title who shall be 3.[V.A in charge of the emergency response.

e. Each organization shall provide for 24- 3.1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per day emergency response, 4.11 including 24-hour per day manning of Aft. 4-2 communications links.

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A. Assignment of Responsibility (Organization Control) (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS 2.a. N/A

b. N/A

3. Each plan shall include written 3.V agreements referring to the concept of 3.VI operations developed between Federal, 3.VH State, and local agencies and other App. D support organizations having an emergency response role within the Emergency Planning Zones. The agreements shall identify the emergency measures to be provided and the mutually acceptable criteria for their implementation, and specify the arrangements for exchange.of information. These agreements may be provided in an appendix to the plan or the plan itself may contain descriptions of these matters and a signature page in the plan may serve to verify the agreements. The signature page format is appropriate for organizations where response functions are covered by laws, regulations or executive orders where separate written agreements are not necessary.

4. Each principal organization shall be capable of continuous (24-hour) operations for a protracted period. The individual in the principal organization who will be responsible for assuring.

continuity of resources (technical, administrative, and material) shall be specified by title I,

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SB. Onsite Emergency Organization Planning Standard On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of response capabilities is available, and the interfaces among various onsite response activities and offsite support and response activities are specified.

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

1. Each licensee shall specify the onsite 3.1 emergency organization of plant staff 3.111 personnel for all shifts and its relation Att. 3-1 to the responsibilities and duties of the Att. 3-2 normal staff.complement

2. Each licensee shall designate an 3.1I1.A ERPIP-3.0, Immediate Actions, individual as emergency coordinator ERPIP-102,-General Supervisor-Nuclear who shall .be on shift at all times and "Plant Operations (CR) .

who shall have the authority and ERPIP-20 1,Technical Support Center responsibility to immediately and Director (TSC) unilaterally initiate any emergency ERPIP-202, Technical Support Center actions, including providing protective Manager (TSC) action recommendations to authorities ERPIP-501, Emergency .

responsible~for implementing offsite Director/Recovery Manager (EOF) emergency measures.

3. Each licensee'shal.identify a lineof 3.I1I.A ERPIP-3.0;, Immediate Actions succession for the emergency ERIP-1102, General Supervisor.- Nuclear coordinatorposition'and identify the Plant Operations (CR).

specific conditions for higher level ERPIP-201, Technical Support Center utility officials.assuming this function.,. Director (TSC)

ERPIP-202, Technical Support Center Manager,(TSC)

ERPIP-50 1, Emergency Director/Rýcovery Manager (EOF)

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B. Onsite Emergency Organization (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

4. Each licensee shall establish the 3.III.A ERPIP-3.0, Immediate Actions functional responsibilities assigned to 3.IV.A ERPIP- 102, General Supervisor - Nuclear the emergency coordinator and shall Plant Operations (CR) clearly specify which responsibilities ERPIP-20 1,Technical Support Center may not be delegated to other elements Director (TSC) of the emergency organization. Among ERPIP-202, Technical Support Center the responsibilities which* may not be Manager (TSC) delegated shall- be the decision to notify ERPIP-50 !, Emergency and to recommend protective actions to Director/Recovery Manager (EOF) authorities responsible for offsite emergency measures.

5. Each licensee shall specify the positions Sect. 3 ERPIP-3.0; Immediate Actions or title and major tasks to be performed 4.11 ERPIP-105, Control Room.,

by the persons to be assigned to the, Communicator (CR) functional areas of emergency activity. ERPIP-l102, General Supervisor'- NUclear

- For emergency situations specific Plant Operations (CR) assignments shall be made for all~shifts ERPIP-201, Technical Support Center and for plantstaff members, both onsite Director (TSC) and away from the site. These ERPIP-202, Technical Support Center assignments shall cover the emergency Manager (TSC) functions in Table B3- entitled, "Minimum StaffingRequirements for Emergency Response Organization Nuclear Power Plant Emergencies." (NORMS, Document: ERO)

The minimum on-shift staffing levels' shall be as indicated in Table B-1. The ERP Section 7, Reference 6. Calvert licensee must be able tioaugment on- Cliffs Nuclear Power Plant License Unit shift capabilities within a short period 1, NO.DPR-53 (Docket No. 50-317) and of time after declaration of an Unit 2 NO.DRR-69 (Docket No. 50-318) emergency.

6. Each licensee shall specify the interface Sect. 3 between and among the onsitei functional areas of eniergeny activity, licensee headquarters support local, services support, and State and local government response organization.

This shall be illustrated in a block diagram and shall include the onsite technical support center and the operational support (assembly) center and the licensee's near-site Emergency Operations Facility (EOF).

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B. Onsite Emergency Organization (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

7. Each licensee shall specify the 3.111.

corporate management; administrative, AUt. 372 and technical support personnel who will augment the plant staff as specified in the table entitled "Minimum Staffing Requirements for Nuclear Power Plant Emergencies," (Table B-I) and in the following areas:

a. logistics support for emergency 3.IV.B.2 personnel, e.g., transportation, 3.IV.B.3 communications, temporary quarters, food and water, sanitary facilities in the field, and special equipment and supplies procurement;

b. technical support for planning and 3.111. ERPIP-20 1',Technical Support Center reentry/recovery operations; Director (TSC)

ERPIP-202, Technical Support Center Manager (TSC)

ERPIP-302, Engineering Director (OSC)

c. management level interface with 3.IV.A governmental authorities; and

d. release of information to news media 3.IV.B.I during emergency (coordinated with government authorities).

8. Each licensee shall specify the 3.V ERPIP-201, Technical Support Center contractors and private organizations 3.VI Director (TSC) who may be requested to provide App. D technical assistance to and augmentation of the emergency organization.

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B. Onsite Emergency Organization (continued)

Applicability and Cross Reference Evaluation Critera ERP IMPLEMENTING DOCUMENTS

9. Each licensee shall identify the services 3.V to be provided by local agencies for 3.VI handling emergencies, e.g., police, 3.VLI ambulance, medical, hospital, and fire- App. D fighting organizations shall be specified. The licensee shall provide for transportation and treatment of injured personnel who may also be contaminated. Copies of the arrangements and agreements reached with contractor, private, and local support agencies shall be appended to the plan. The agreements shall delineate the authorities, responsibilities, and limits on the.

actions of the contractor, private organization, and local services support groups.

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C. Emergency Response Support and Resources Planning Standard Arrangements for requesting and effectively using assistance resources have been made, arrangements to accommodate State and local staff at the licensee's,near-site Emergency Operations Facility have been made, and other organizations capable of augmenting the planned response have been identified.

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS The Federal government maintains in- 3.VII.D depth capability to assist licensees, State and local governments through the Federal Radiological Monitoring and Assessment Plan (formerly Radiological Assistance Plan (RAP) and Interagency Radiological Assistance Plan (IRAP). Each State and Licensee shall make provisions for incorporating the Federal response capability into its operation plan, including the following:

a. Specific persons by title authorized to 3.111.A request Federal assistance; see A.I.d., 3.IV.A A.2.a.

b. Specific Federal resources expected,' 3.VII.D including expected times of arrival at specific nuclear facility sites; and

c. specific licensee, State and local 3.VII.D resources available to support the Federal response, e.g., air fields, command posts, telephone lines, radio frequencies and telecommunications centers.

2.a. N/A Revision 41

S C. Emergency Response Support and Resources (continued) 41 Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

b. The licensee shall prepare for the 3.IV.D ERPIP-720, Technical Representatives dispatch of a representative to principal (Calvert, St. Mary's, Dorchester, and offsite governmental.emergency State - EOCs) operations centers.

3. Each organization shall identify 5.1.F radiological laboratories and their general capabilities and expected availability~to provide radiological monitoring and analysis services which can be used in an emergency.

4. Each organization shall identify nuclear 3.VI INPO Resources Manual and other facilities, organizations or 3.VII individuals which can be relied upon in App. D an emergency to provide assistance..

Such assistance shall be identified and supported by appropriate letters of agreement.

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D. Emergency Classification System Planninp_ Standard A standard eme~rgency classification and action level scheme, the basis of which include facility system and effluent parameters, is in use by the nuclear facility licensee, and State and local response plans call for reliance on information provided by facility licensees for determinations of minimum initial offsite response measures.

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

1. An emergency classification and 2.1 ERPIP-3.0, Immediate Actions emergency action .level scheme as set 2.11 forth in Appendix I must be established 2.111 EAL Technical Basis Document by the licensee. The specific 2.lV instruments, parameters or equipment 2.V status shall be shown for establishing each emergency class, in the in-plant emergency procedures. The plan shall identify the parameter values and equipment status for each emergency class.

2. The initiating conditions shall include 2.11 ERPIP-3.0, InunediateActions the example conditions found in 2.111 Appendix I and all postulated accidents 2.IV in the Final Safety Analysis Report. 2.V (FSAR) for the nuclear facility. 2.VI Att. 2-1

3. N/A

4. N/A Revision 41

E. Notification Methods and Procedures Planning Standard Procedures have been established for notification, by the licensee of State and local response organization and for notification of emergency personnel by all response organizations; the content of initial and follow-up messages to response organizations and the public has been established; and means to provide early notification and clear instruction to the populace within the plume exposure pathway Emergency Planning Zone have been established.

Applicability and&Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

1. Each organization shall establish 2.1 ERPIP-3.0, Immediate Actions procedures which describe mutually 4.II.A ERPIP-105, Control Room agreeable bases for notification of 4.1I.B Communicator (CR) response organizations consistent with Aft. 4-1 ERPIP-209, Technical Support Center the emergency classification and action Att. 4-2 Communicator (TSC) level scheme set forth in Appendix 1. ERPIP-509, Emergency Operationis These procedures shall include means Facility Communicator (EOF) for verification of messages. The specific details of verification need not be included in the plan.

2. Each organization shall establish; 4.I1.A ERPIP-105, Control Room procedures for alerting, notifying, and 4.II Communicator (CR) mobilizing emergency response ERPIP-201, Technical SupportCenter personnel. Director (TSC).

ERPIP-209, Technical Support Center Communicator (TSC)

ERPIP-3.0, Immediate Actions ERPIP-501, Emergency Director/Recovery Manager (EOF)

ERPIP-503, Emergency Response Facility Director (EOF)

ERPIP-509, Emergency Operations Facility Communicator (EOF)

ERPIP-750, Security .

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S E.

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Notification Methods and Procedures (continued)

Applicability and CrossrReference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

3. The licensee in conjunction with State 4.lI.C.l ERPIP-3.0, Immediate Actions and local organizations shall establish the contents of the initial emergency messages to be sent from the plant.

These messages shall contain information about the class of emergency, whether a release is taking place, potentially affected population and areas, and whether protective measures may be necessary.

4. Each licensee shall make provisions for 4.II.C.2 ERPIP-3.0, Immediate Actions follow-up messages from the facility to offsite authorities which shall contain the following information if it isknown and appropriate:

a. location of incident andname and 4.11.C.2 ERPIP-3.0, Immediate Actions telephone number (or communications channel identification) of caller;

b. date/time of incident; 4.II.C.2 ERPIP-3.0', Immediate Actions

c. class of emergency; 4.II.C.2 ERPIP-3.0, Immediate Actions

d. type of actual or projected release 4.II.C.2 ERPIP-3.0, Immediate Actions (airborne, waterborne, surfacespill),

and estimated duration/impact times;

e. estimate of quantity or radioactiv* 4.Il.C.2 ERPIP-3.0, Immediate Actions material released or being released and the points and height of releases;'

f. chemical and physical form of released 4.1I.C.2 ERPIP-3.0, ImmediateActions material, including estimates of the relative quantities and concentration of noble gases, iodines and particulates;

g. meteorological conditions at 4.11.C.2 ERPIP-3.0, Immediate Actions appropriate levels (wind speed, direction (to and from), indicator of stability, precipitation, if any);

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E. .Notification Methods and Procedures (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

h. actual or projected dose rates at site 4.[1.C.2 ERPIP-3.0, Immediate Actions-boundary; projected integrated dose at site boundary;

i. projected dose rates and integrated dose 4.1I.C.2 ERPIP-3.0, Immediate Actions at the projected peak and at 2, 5 and 10 miles, including sector(s) affected;

j. estimate of any surface radioactive 4.1I.C.2 ERPIP-3.0, Immediate Actions contamination in plant, onsite or offsite;

k. licensee emergency response actions 4.II.C.21 , ERPIP-3.0, Immediate Actions underway;

1. recommended emergency actions,. 4.1I.C.2, ERPIP-3.0, Immediate Actions including protective measures;

m. request for any needed onsite support 4.ll.C.2 ERPIP-3.0, Immediate Actions by offsite organizations; and

n. prognosis for worsening or termination 4.I1.C.2. ERPIP-3.0, Immediate Actions of even based on-plant information.

5. N/A

6. Each organization shallestablish 4.1I.B ERPIP-3.0, Immediate Actions administrative and physical means, and 4.L.D ERPIP-102, General Supervisor - Nuclear the time required for notifying and 5.11 a-Plant Operations (CR).

providing prompt instructions to the ERPIP-201, Technical Support Center public within the plum exposure...,:.. Director (TSC) -

pathway Emergency Planning Zone. ERPIP-202,.Technical Support Center (See Appendix 3.). It shall be the Manager (TSC),

licensee's responsibility to demonstrate ERPIP-50t,.Emergency that such.means exist, regardless of. Director/Recpyory Manager (EOF) whoimplements this requirement. It shall be the responsibility, of the State and local governments to activate such - .

..a system.

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E. Notification Methods and Procedures (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

7. Each organization shall provide written 3.IV.B.1 JIC-02 messages intended for the public, 5.1.E.

consistent with the licensee's classification scheme.. Inparticular; draft messages to the public giving instructions with regard to specific protective actions to be taken by occupants of affected areas. Messages shall be prepared and included as part of the State and local plans. Such messages should include the appropriate aspects of sheltering, ad hoc respiratory protection, e.g.,

handkerchief over mouth, thyroid blocking or evacuation. The role of the licensee is to pr6videthe supporting.

information forthe messages. For ad, hoc respiratory protection see "Respiratory Protective Devices ...

Manual" American Industrial Hygiene Association, 1963 pp. 123-126.

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F. Emergency Communications Planning Standard Provisions exist* for prompt communications among principal response organizations to emergency personnel and to the public.

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS The communication plans for emergencies 5.11 shall include organizational titles and alternates for both ends of the communication links. Each organization shall establish reliable primary and backup means of communication for licensees, local, and State response organizations.

Such systems should be selected to-be compatible with one another. Each plan shall include:

a. provision for 24-hour per day notification to 3.1II.A. ERPIP-3.0, lmmediate.Actions and activation of the State/local emergency 4.11.B ERPIP-901, Communications Equipment response network; and at a minimum, a 5.11 telephone link alternate, including 24-hour Att. 4-2 per day manning of communications links that initiate emergency response actions.

b. provision for communications with 5.11 ERPIP-102, General Supervisor-Nuclear contiguous State/local governments within Plant Operations (CR) the Emergency Planning Zones; ERPIP-105, Control Room Communicator (CR)

ERPIP-20 1, Technical Support Center Director (TSC)

ERPIP-202, Technical Support Center Manager (TSC)

ERPIP-209, Technical Support Center Communicator (TSC)

ERPIP-3.0, Immediate Actions ERPIP-501, Emergency Director/Recovery Manager (EOF)

ERPIP-509, Emergency Operations Facility Communicator (EOF)

ERPIP-901, Communications Equipment

c. provisions for communications as needed 5.11 ERPIP-901, Communications Equipment with Federal emergency response organizations; Revision 41

F. Emergency Communications (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

d. provision for communications between the 5.11 ERPIP-901, Communications Equipment nuclear facility and the licensee's-near-site Emergency Operations Facility, State and local emergency operations centers, and radiological monitoring teams;

e. provision for alerting or activating 4.11A ERPIP- 102, General Supervisor - Nuclear emergency personnel in each response 4.11.B1 Plant Operations (CR) organization; and .5.11 ERPIP-105, Control Room Communicator (CR)

ERPIP-201, Technical Support Center Director (TSC)

ERPIP-202, Technical Support Center Manager (TSC)

ERPIP-209, Technical Support.Center Communicator (TSC) ,

ERPPA-3.0, Immediate.Actions ERPIP-50 1, Emergency Director/Recov'ery Manager (EOF)

ERPIP-503, Emergency Operations Facility Director (EOF)

ERPIP-509, Emergency Operations Facility Communicator (EOF)

ERPIP-750, Security ERPIP-90 1, Communications Equipment

f. provision for communications by the 5.11 ERPIP-104, Emergency-Notification System licensee with NRC headquarters and NRC Communications.(CR)

Regional Office Emergency Operations ERPIP-90 1, Communications Equipment Centers and the licensee's near-site Emergency Operations Facility and radiological monitoring team assembly area.

2. Each organization shall ensure that a 5.11 ERPIP-901, Communications Equipment coordinated communication link for fixed and mobile medical support facilities exists.

3. Each organization shall conduct periodic. 6.11 ERPIP-905, Exercises, Tests and Drills testing of the entire emergency 6.IV EPA-4302, Emergency Preparedness'Repetitive communications system (see evaluation Task and Administrative Controls criteria H.10, N.2.a and Appendix 3).

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G. Public Education and Information Planning Standard Information is made available to the public on a periodic basis on how theywill be notified and what their initial actions should be in an emergency (e.g., listening to a local broadcast station and remaining indoors), the principal points of contact with the news media for dissemination of.

information during an emergency (including the physical location or locations)'are established in advance, and procedures for coordinated dissemination of information .to the public, are established.

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS Each organization shall provide a 6.1.C.1 coordinated periodic (at least annually) dissemination of information to the public regarding how they will be notified and what their actions should be inan emergency. This information shall include, but not necessarily be limited to:

a. educational information on radiation;

b. contact for additional information;

c. ::protective measure, e.g., evacuation routes and relocation. centers,.

sheltering, respiratory protection; radio protective drugs;

d. special needs of the handicapped.

Means for accomplishing this dissemination may include, but are not necessarily limited to.: information in the telephone book, periodic..

information in utility bills; posting in public areas; and publications distributed on an annual basis.

9:?

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S G. Public Education and Information (continued)

.Applicability and Cross Reference Evaluation Criteria ERP.. IMPLEMENTING DOCUMENTS

2. The public information program shall 6.l.C.1 provide the permanent and transient adult population within the plume exposure EPZ an adequate opportunity to become aware of the information annually. The programs should include provision for written material that is likely to be available in a residence during an emergency. Updated information shall be disseminated at least annually. Signs or other measures (e.g., decals, posted notices or other means, placed in hotels, motels, gasoline stations and phone booths)

shall also be used to disseminate to any transient population within the plume exposure pathways EPZ appropriate information that would be helpful if an emergency or accident occurs. Such notices should refer the transient to the telephone director or other source of local emergency information and guide the visitor to appropriate radio and television frequencies.

3.a. Each principal organization shall 3.IV.B.1 designate the points of contact and 5.1.E physical locations for use by news Att. 5-7 media during an emergency. Att. 5-8 Att. 5-9

b. Each licensee shall provide space which 5.I.E may be used for a limited number of the news media at the near site Emergency.

Operations Facility.

4.a.

Each principal organization shall 3.IV.B.1 designate a spokesperson who should 5.I.E have access to all necessary information.

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G. Public Education and Information (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

b. Each organization shall establish 3[V.B. 1 arrangements for timely exchange of 3.VII.A information among designed 5.1.E spokespersons.

c. Each organization shall establish. 4.lI.C JIC-02.

coordinated arrangements for dealing, 51E with rumors.

5. Each organization shall conduct 6.1.C.2 coordinated programs at least annually to acquaint news media with the emergency plans, information concerning radiation, and points'of contact for release of public information in an emergency.

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h MRGENYEPNE H. Emergency Facilities and Equipment Planning Standard Adequate emergency facilities and equipment to support the emergency response are provided and maintained.

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS I. Each licensee shall establish a 5.1.C ERP1P-20 1, Technical Support Center Technical Support Center and an onsite 5.1.D Director (TSC) operations support center (assembly ERPIP-301, Operational Support Center area) in accordance with NUREG-0696, Director (OSC)

Revision 1.

2. Each licensee shall establish an 5.1.B Emergency Operations Facility from which evaluation and coordination of all licensee activities related to an emergency is to be carried out and from which the licensee shall provide information to Federal, State and local authorities responding to radiological emergencies in accordance with NUREG-0696, Revision 1.

3. N/A

4. Each organization shall provide for 3.111 ERPIP-102, General Supervisor - Nuclear timely activation and staffing of the 3.IV Plant Operations (CR) facilities and centers described in the 4.I1.A ERPIP-I105, Control Room Communicator plan. 4.II.B (CR)

ERPIP-201, Technical Support Center Director (TSC)

ERPIP-209, Technical Support Center Communicator (TSC)

ERPIP-3.0, Immediate Actions ERPIP-503, Emergency Operations Facility Director (EOF)

ERPIP-750, Security 9

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S H. Emergency Facilities and Equipment (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

5. Each licensee shall identify and 5.[II.A ERPIP-3.0, Immediate Actions establish on-site monitoring systems 5.1I1.B ERPIP-318, Onsite Survey Team (OSC) that are to be used to initiate emergency 5.I((.C ERPIP-821, Accidental Radioactivity measure in accordance with Appendix 5.111.D Release Rate Estimate 1, as well as those to be used for ERP[P-823,ý Dose Assessment Computer conducting assessment. ERPIP-825, Meteorological Data Acquisition Methods The equipment shall include:

01-46, Seismic Measurement Equipment

a. geophysical phenomenamonitors, (e.g., 5.III.A meteorological, hydrologic, seismic);,

b. radiological monitors,.(e.g., process, 5.lI1.C ERPIP-903, Monitoring Equipment and area, emergency, effluent, wound and 5.III.D Instrumentation portable monitors and sampling 5.III.F ERPIP-B.I, Equipment Checklists equipment); 5.HII.G ERP[P-B.2, Offsite Survey Points 01-3.5, Radiation Monitoring System O-44, Process Radiation Monitor 01-48, Wide RangeNoble Gas Monitor RSP 1-107, Personnel Contamination Assessment/Decontamination by RadiationSafety Technicians'

c. process monitors, (e.g., reactor coolant 5.III.D1 system pressure and temperature, liquid levels, flow rates, status or lineup of equipment components); and

d. fire and combustion products detectors. 5.1II.E 01-20, Fire Protection System (Common)

6. Each licensee shall make provision to 5.111 ERPIP-504, Environmental Assessment acquire data from or for emergency Director (EOF) access to offsite monitoring and analysis equipment including:

a. geophysical phenomena monitors, (e.g., 5.1[I.A meteorological, hydrologic, seismic);

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SH. Emergency Facilities and Equipment (continued)

Applicability and Cross Reference EvaluationCriteria 'ERP IMPLEMENTING DOCUMENTS

b. radiological monitors including rate 5.11I.C ERPIP-318, Onsite Survey Team (OSC) meters and sampling devices. 5.111.F ERPIP-507, Offsite Survey Team (EOF)

Dosimetry shall be provided and shall 5.II.G ERPIP-903, Monitoring Equipment and meet, as a minimum, the NRC Instrumentation.

Radiological Assessment Branch ERPIP-B. 1, Equipment Checklists Technical Position for the Environmental Radiological Monitoring Program; and

c. laboratory facilities, fixed or mobile. 5.1.F

7. Each organization, where appropriate 5.1II.F ERPIP-504, Environmental Assessment shall provide for offsite radiological 5.I11.G Director (EOF) equipment in the vicinity of the nuclear 5.IV ERPIP-507,' Offsite Survey Team (EOF) facility. ERPIP-B. 1,Equipment Checklists-ERPIP-B.2, Offsite Survey Points

8. Each licensee shall provide - 5.111.A meteorological instrumentation and App. D procedures, which satisfy the criteria in Appendix 2, and provisions to obtainý representative current meteorological, information from othersources.

9. Each licenseeshall provide for an 5.I.D ERPIP-B. 1, Equipment Checklists onsite operations support center (assembly area) which shall have adequate capacity, and supplies, including, for example, respiratory protection, protective clothing, portable lighting, portable radiation monitoring

-equipment, cameras and communications equipment for personnel present in the assembly areas.

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H. Emergency Facilities and Equipment (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

10. Each organization shall make 6.IV ERPIP-903, Monitoring Equipment and provisions to inspect, inventory and Instrumentation operationally check emergency ERP1P-B. 1, Equipment Checklists equipment/instruments at least once each calendar quarter and after each use.. There shall be sufficient reserves of instruments/equipment to replace those which are removed from emergency kits for calibration or repair.

Calibration of equipment shall be at intervals recommended by the supplier of the equipment.

11. Each plan shall, in an appendix, include 5.1.V ERPIP-B. I, Equipment Checklists identification.of emergency kits by general category (protective equipment, communications equipment, radiological monitoring equipment and emergency supplies).

12. Each, organization shall, establish a 5.1.B ERPIP-511, Radiological Assessment Director central point (preferably associated Att. 5-1 (EOF) with the licensee's near-site Emergency Operations Facility), for the receipt and

.analysis of all field monitoring data'and coordination of sample media.

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Accident Assessment Planning Standard Adequate methodssystems and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use.

Applicability and Cross Reference.

Evaluation Criteria ERP IMPLEMENTING DOCUMENTS Each .licensee shall identify plant 2.1 ERPIP-3.0,, Immediate Actions system and effluent parameter values ERPIP-600, Severe Accident Management characteristic of a spectrum of off- ERPIP-601., Severe Accident Management Initial normal conditions and accidents, and Diagnosis shall identify the plant parameter values ERPIP-602, Severe Accident Management of other information, which correspond Verification of Diagnosis to the example initiating conditions of ERPIP-603, Candidate High Level Actions Appendix 1. Such parameter values BD/CC.

and the corresponding emergency class ERPIP-604, Candidate High.Level Actions shall be included in the appropriate BD/CH facility emergency procedures. Facility ERPIP-605, Candidate High Level Actions emergency procedures shall specify the BD/CC kinds of instruments being used and ERPIP-606, Candidate High Level Actions BD/B ;

their capabilities. ERPIP-607, Candidate High Level Actions EXICC ERPIP-608, Candidate High Level-Actions EX/CH ERPIP-609, Candidate HightLevelkActions EX/I ERPIP-610, Candidate High Level-Actions EX/B ERPIP-61 1, Severe Accident Management Restorative Actions ERPIP-612, Candidate High Level Actions SFP Fuel Uncovered ERPIP-800, Core Damage Assessment (CDA)

ERPIP-801, CDA Using Containment Radiation Dose Rates ERPIP-802, CDA Using Core exit Thermocouples ERPIP-803, CDA Using Hydrogen ERPIP-804, Using Radiological Analysis of Samples Revision 41

Accident Assessment (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

2. Onsite capability and resources to 5.11I.C ERPIP-3.0, Immediate Actions provide initial values and continuing 5.IILH ERPIP-318, Onsite Survey Team (OSC) assessment throughout the course of an 5.111.1 accident shall include post-accident 01-35, Radiation Monitoring System sampling capability, radiation and 01-44, Process Radiation Monitor effluent monitors, in-plant iodine 1Of-48, Wide Range Noble Gas Monitor instrumentation, and containment radiation monitoring in accordance with NUREG-0578, as elaborated in NRC letter to all power reactor licensees dated October 30, 1979.

3. Each licensee shall establish methods and techniques to be used for determining:

a. the source term of releases of radioactive material within plant systems. An example is the relationship between the containment radiation monitor(s) reading(s) and-radioactive material available for release from containment.

b. the magnitude of the release of 4.IV.B ERPIP-824, Dose Assessment Reference radioactive materials based on plant system parameters and effluent monitors.

4. Each licensee shall establish the 4.IV.C ERPIP-824, Dose Assessment Reference

relationship between effluent monitor readings and onsite and offsite exposures and contamination for various meteorological conditions.

Revision 41

I. Accident Assessment (continued) ex Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

5. Each licensee shall have the capability 4.11.C ERPIP-825, Meteorological Data of acquiring and evaluating 5.11 Acquisition Methods meteorological information sufficient to 5.lIl.A.

meet the criteria of Appendix 2. There 5.111.B1 shall be provisions for access to meteorological information by at least the near site Emergency Operations Facility, the Technical Support Center, the Control Room and an offsite NRC center. The licensee shall make available to the State suitable meteorological data processing interconnections which will permit independent analysis by the State, of facility generated data in those States with the resources to effectively use this information.

.6. Each licensee shall establish the 4.IV.D ERPIP-82 I, Accidental Radioactivity methodology for determining the Release Monitoring and Sampling release rate/projected doses if the Methods, instrumentation used for assessment are off scale or inoperable.

7. Each organization shall describe the 5.III.F ERPIP-504, Environmental Assessment capability and resources for field Director (EOF) monitoring within the plume exposure. ERPIP-507; Offsite Survey Team (EOF)

Emergency Planning Zone which are an ERPIP-5 1, Radiological Assessment intrinsic part of the concept of . . Director (EOF)

. operations for the facility.

9 Revision 41

S Accident Assessment (continued)

Applicability and Cross Reference

Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

8. Each organization, where appropriate, 3.111 ERPIP-107, Chemistry Shift Technician provide methods, equipment and 3.IV ERPIP-3.0, Immediate Actions expertise to make rapid assessments of.. 4.II.A ERPIP-303, Radiation Protection Director the actual or potential magnitude and 4.1I.B (OSC) locations of any radiological hazards . 4.IV.E ERPIP-318, Onsite Surveys through liquid or gaseous release 5.II.F ERPIP-504, Environmental Assessment pathways. This shall include activation,, Director (EOF) notification means, field team ERPIP-507, Offsite Surveys composition, transportation, ERPIP-5 11, Radiological Assessment communication, monitoring equipment Director.

and estimated deployment times.

9. Each organization shall have a 5.III.F ERPIP-824, Dose Assessment Reference

.capability to detect and measureý ERPIP-318, Onsite Surveys radioiodine concentrations in air in-the ERPIP-507, Offsite Surveys plume exposure EPA As. low as 10- ERPIP-51 1, Radiological Assessment uCi/cc (microcuries percubic Director centimeter) under field conditions'. ERPIP-903, Monitoring Equipment and Interference from the presence of noble Instrumentation gas and background~radiation shall not ERPIP-B. 1, Equipment Checklists decrease the stated minimum detectable activity.

10. Each organization shall establish means 4.IV ERPIP-823, Dose Assessment Computer' for relating the various measured,, 5.lII.B.

parameters (e.g., contamination

levels, water and air activity levels) to dose rated for key isotopes (i.e., those given in Table 3, page 18) and gross radioactivity measurements. Provisions shall be made for estimating integrated dose from the projected and actual dose rates and for comparing these estimates with the protective action guides. The!

detailed provisions shall be described in.

separate procedures.

I I. N/A Revision 41

J. Protective Response Planning Standard A-range of protective actions have been developed for the plume exposure pathways EPZ for emnergency. workers and the public. Guidelines for the choice of protective actions during an emergency, consistent with Federal guidance, are developed and in place, and protective actions for the ingestion exposure pathway EPZ appropriate to the locale have been developed.,

Applicability apid Cross Reference Evaluation, Criteria ERP IMPLEMENTING DOCUMENTS 1 Each licensee shall establish themeans 4.I.A ERPIP- 102, General Supervisor- Nuclear and time required to warn or advise Plant Operations (CR) onsite individuals and individuals who ERPIP-105, Control Room Communicator may be in areas.controlled by the (CR) operator, including: - : ERPIP-201, Technical Support Center Director (TSC)

ERP[P-209, Technical Support Center Communicator ERPIP-3.0, Immediate Actions ERPIP-303, Radiation Protection Director ERPIP-318, Onsite Surveys; ERPIP-50F1, Emergency Director/Recovery Manager (EOF)

ERPIP-509, Emergency Operations Facilit Conmunicator ERPIP-750, Security

a. Employees not having emergency assignments;

b. Visitors;

c. Contractor and construction personnel; and

d. Other persons who may be in the public access areas on or passing through the.

S -site or within the owner controlled area.

9 Revision 41

~qi~cy ~*.

~AW)V I Protective Response (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

2. Each licensee shall make provisions for 4.VI.B. I ERPIP-201, Technical Support Center evacuation routes and transportation for Director (TSC) onsite individuals to some suitable ERPIP-501, Emergency Director/Recovery offsite location, including alternatives Manager (EOF) for inclement weather, high traffic density and specific radiological conditions.

3. Each licensee shall provide for 4.VII1.B ERPIP-318, Onsite Surveys

radiological monitoring of people evacuated from site.

4. Each licensee shall provide for the 4.VI.B.2 ERPIP-3.0, [tummediate Actions evacuation of onsite non-essential 51G ERPIP_50 1 Emergency Director/Recovery personnel in the event of a Site or Manager' General Emergency and shall provide.a, ERPIIP-710, Farm Demonstration Building decontamination capability at or near Decontamination Facility the monitoring point specified in J.3 ERPP-7s0, Security ERPIP-B.2 t rvey nts

5. Each licensee shall'provide for a 4.VI.A ERPIP-310,1Immediate Actions'!

capability to account for all individuals ERPiP' 02, General Supervisor -Nuclear onsite at the time of the'emergency and Plant Operations (CR) ascertain the names of missing ERPIP-20 I Technical Support Center individuals within 30 minutes of the Director (TSC) start of an emergency and account for ERPIP-30 I-,Operationa ISupport Center

all onsite individuals continuously Director (OSC)"

thereafter. ERPIP-50 I Emergency Director/Recovery Manager ERPIIP-50, Sec rty

6. Each licensee shall, for individuals remaining or arriving onsite during the emergency, make provisions for:

a. individual respirator protections; 5.V ERPIP-B.I, Equipment Checklist RSP 1-117, Issuance and Wearing of Respiratory. Protection Devices Used to Protect Against Airborne Radioactivity RP-1-100, Radiation Protection Manual Revision 41

J. Protective Response (continued)

Applicability and Cross Reference Evaluation Criteria ERP j IMPLEMENTING. DOCUMENTS

b. use of protective clothing; and 5.VI ERPIP-BA.1, Equipment Checklists RSP 1-200, ALARA Planning and SWP Preparation

c. use of radioprotectivedrugs, (e.g., 5.VII ERPIP-303, Radiation Protection Director individual thyroid protection). (OSC)

ERPIP-51 1, Radiological Assessment Director (EOF),.

7. Each licensee shall establish a 4.1l.C ERPIP-3.0, Immediate Actions mechanism for recommending Att. 4-2 ERPIP-102, General Supervisor - Nuclear protective actions to the appropriate Plant Operations (CR)

State and local authorities. These shall ERPIP-107, Chemistry Shift Technician include Emergency Action Levels. ERPIP-201, Technical Support.Center corresponding to projected dose to the, Director (TSC) population-at-risk, in accordance with ERPIPP-202, Technical Support Center, Appendix I and with the Manager (TSC).

recommendations set forth in Tables 2.1 ERPIP-501, Emergency Directoi/Recovery and 2.20of the Manual of Protective Manager (EOF)

Action Guides and Protective Actions, ERPIP-504, Environmental Assessment for Nuclear incidents (EPA-520/I .Director (EF) 001). As specified in Appendix 1, ERPIP-51 1, Radiological Assessment prompt notification shall be made, Director (EOF) directly to the offsite authorities.

responsible for implementing protective measures within the plume exposure pathway Emergency PlanningZone."

8. Each licensee's plan shall contain time App. C

,estimates for evacuation within the plume exposure EPZ. These shall be in accordance. with Appendix 4.

Revision 41

tMERGI-N~CY-R AMA tt J. Protective Response (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

9. N/A

10. The organization's plans to implement protective measures for the plume exposure pathway shall include:

a. Maps showing evacuation routes, 5.111.F ERPIP-504, Environmental Assessment evacuation areas, preselected Director (EOF) radiological sampling and monitoring, ERPIP-B.2, Offsite Survey Points points, relocation centers in host areas, and shelter areas; identifications of radiological sampling and monitoring points shall include the designators in Table J- I or an equivalent uniform system described in the plan);

b. Maps'showing population distribution App. C around the nuclear facility. This shall be by evacuation areas (licensees shall also present the information in a sector format);

c. Means for notifying all segments of the 4.11 transient and resident population; Att. 4-2 6.I.C

d. N/A

e. N/A

f. N/A

g. N/A

h. N/A

i. N/A

j. N/A Lc N/A Revision 41

S J. Protective Response (continued)

I Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS Time estimates for evacuation of: App. C

" various sectors and distances based on a dynamic analysis (time-motion study under various conditions) for the plume exposure pathway emergency planning zone (See Appendix 4); and

m. The basis for the choice of 4.VI.C ERPLP-504, Environmental Assessment recommended protective actions from Director (EOF) the plume exposure pathway during ERPIP-501, Emergency Director/Recovery emergency conditions. This.shall Manager include expected local protection afforded 2 in residential units or other shelter for direct and inhalation exposure, as well as evacuation time estimates.

11. N/A

'12. N/A`

The following reports may be considered in determining protection afforded:

(f) "Public Protection strategies for Potential Nuclear Reactor Accident" Sheltering Concepts with Existing Public and Private Structure" (SAND 77-1725), Sandia Laboratory.

(2) "Examination of Offsite Radiological Emergency Measures for Nuclear Reactor Accidents Involving Core Melt".(SAND 78-0454), Sandia Laboratory.

(3) "Protective Action Evaluation Part 11, Evacuation and Sheltering as Protective Actions Against Nuclear Accidents Involving Gaseous Releases" (EPA 520/1-78-0018).. U.S. Environmental Protection Agency.

Revision 41

K. Radioloeical Exposure Control Planning Standard Means for controlling radiological exposures, in an emergency, are established for emergency workers. The means for controlling radiological exposures shall include exposure guidelines consistent with EPA Emergency Worker and Lifesaving Activity Protective Action Guide.

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

1. Each licensee shall establish onsite exposure? 4.VII.B ERPIP-301, Operational Support Center guidelines consistent with EPA Emergency Director (OSC)

Worker and Lifesaving Activity Protective. ERPIP-303, Radiation Protection Director Actions Guide (EPA 520/1-75001) for: ERPIP-3 18, Onsite Surveys ERPIP-831, Radiation Exposure Guidance RSP-I 200, ALARAPlanning and RWP Preparation

a. removal of injured persons; 4.VII.B.2.e ERPIP-103, Nuclear Plant Operations ERPIP-312, Safety Services ERPIP-501, Emergency Director/Recovery Manager (EOF)

ERPIP-83 1, Radiation Exposure Guidance

b. undertaking corrective actions; 4.VII.B.2.b ERPIP-730, Radiation Protection Hospital Assistance RSP 1-117, Issuance and Wearing0of Respiratory Protection Devices Used to Protect Against Airborne Radioactivity

c. performing assessment actions; 4.VII.B.2.c- ERPIP-303, Radiation Protection Director ERPIP-83 1, Radiation Exposure Guidance RSP 1-107; Personnel Contamination Assessment/Decontamination by Radiation Safety Technicians

d. providing first aid, 4.VII.B.2.a ERPIP-103, Nuclear Plant Operations ERPIP-312, Safety Services, ERPIP-83 1, Radiation Exposure Guidance ERPIP 3.0, Immediate Actions Attachment 15 Personnel Emergency Revision 41

K. .Radiological Exposure Control (contifiued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMETING PROCEDURES

e. performing personnel decontamination; 4.VII.B.2.d ERPIP-103, Nuclear Plant Operations ERPIP-3 12, Safety Services ERPIP-7 10, Farm Demonstration Building Decontamination Facility RSP 1-107, Personnel Contamination Assessment/Decontamination by Radiation Safety Technicians

f. providing ambulance service; and 4.VII.B.2.e ERPIP-103, Nuclear Plant Operations ERPIP-312, Safety Services ERPIP 3.0, Immediate Actions'

g. providing medical treatment services. 4.VII.B.2.a ERPIP-501, Emergency Director/Recovery Manager (EOF)

ERPIP-730, Radiation Protection Hospital Assistance ERPIP-3.0, Immediate Actions

2. Each licensee shall provide an onsite 4.VII ERPIP-301, Operational Support Center radiation protection program to be Director (OSC)

I implemented during emergencies, ERPIP-303, Radiation Protection Director including methods to implement (OSC) exposure guidelines. The plan shall ERPIP-318, Onsite Surveys identify'individual(s), by position or ERPIP-83 1, Radiation Exposure title, who can autho0 eergency Guidance workers to receive doses in excess of 10 RSP-1-200, ALARA Planning and RWP .

CFR Part 20 limits. Procedures shall be, Preparation

worked out in advancefor permitting RSP 3-102, Personnel Radiation Dose onsite volunteers-to receive radiation Control exposures in the course of carrying out lifesaving and other emergency-.-

activities. These procedures shall

include consideration of relative risks.

Revision 41

K. Radiological Exposure Control (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS.

3.a. Each organization' shall make provisions 4.VII.A ERPIP-103, Nuclear Plant Operations for 24-hour-per-day capability to ERPIP-303, Radiation' Protection Director determine the doses received by (OSC) emergency personnel involved in any ERPIP-'312, Safety Services nuclear accident, including volunteers. ERPIP-318, Onsite Surveys Each organization shall make provisions RSP 1-116, Dosimetry Issue and Dose for distribution of dosimeters, both self- Calculations Performed by Radiation reading and permanent record devices. Safety Units RSP 3-102, Personnel Radiation Dose Control RSP 3-202, Special Dosimetry RSP 3-203, Direct Reading Dosimetry Use RSP 3-2 10, Panasonic Automatic TLD Reader System Operation

b. Each organization shall ensure that 3.IILH ERPIP-303, Radiation Protection Director dosimeters are read at appropriate 4.VII.A ERPIP-507, Offsite Surveys frequencies and provide for maintaining RSP 3-102, Personnel Radiation Dose dose records for emergency workers Control involved in any nuclear accident

4. N/A 5.a. Each organization, as appropriate, shall 4.VIII.A ERPIP-50 1, Emergency Director/Recovery specify action levels for determining the Manager need for decontamination. RSP 1-107, Personnel Contamination Assessment/Decontamination by Radiation Safety Technicians

-N Revision 41

S K.

)

Radiological Exposure Control (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

b. Each organization, as appropriate, shall 4.VII.B.2.d ERPIP-103, Nuclear Plant Operations establish the means for radiological 4.VIII ERPIP-312, Safety Services decontamination of emergency personnel 5.1.G ERPIP-50 1, Emergency Director/Recovery wounds, supplies, instruments and Manager equipment, and for waste disposal. ERPIP-710, FarmDemonstration Building Decontamination Facility.

RSP.I -107, Personnel Contamination Assessment/Decontamination by Radiation Safety Technicians Revision 41

Cross iereren . * ,. . . .

K. Radiological Exposure Control (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

6. Each licensee shall provide onsite 4.VIII ERPIP-303, Radiation Protection Director contamination control measures ERPIP-504, Environmental Assessment including: Director (EOF)

ERPIP-750, Security RSP 1-107, Personnel Contamination Assessment/Decontamination by Radiation Safety Technicians RP- I- 100, Radiation Protection Manual

a. area access control; 4.VIII.A ERPIP-303, Radiation Protection. Director

b. drinking water and food supplies; 4.VIII.A ERPIP-318, Onsite Surveys

c. criteria for permitting return of areas and 4.IV.H ERPIP-318, Onsite Survey Team (OSC) items to normal use, see Draft ANSI ERPIP-750, Security 13.12

7. Each licensee shall provide the 4.VflI.A ERPIP-103, Nuclear Plant Operations capability for decontaminating relocated 5.I.G ERPIP-312, Safety Services onsite personnel, including provisions ERPIP-7 10, Farm Demonstration for extra clothing and decontaminates Building Decontamination Facility suitable for the type of contamination ERPIP-B. 1, Equipment Checklist expected, with particular attention given RSP 1-107, Personnel Contamination to radioiodine contamination of the skin. Assessment/Decontamination by Radiation Safety Technicians Revision 41

S L. Medical and Public Health Support Planning Standard Arrangements are made for medical services for contaminated injured individuals. 1 Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS I. Each organization shall arrange for local 3.V ERPIP-730, Health Physicist Hospital and backup hospital and medical 3.VI Assistance services having the capability for 5.1.H.2 evaluation of radiation exposure and 6..13.8 uptake, including assurance that persons 6.11 providing these services are adequately App. D prepared to handle contaminated individuals.

2. Each licensee shall provide for onsite 4.IX ERPIP-3.0, Immediate Actions first aid capability. 5.1.H. I ERPIP-103, Nuclear Plant Operations 6.I.B.6 ERPIP-312, Safety Services

3. N/A

4. Each organization shall arrange for 3.V ERPIP-3.0, Immediate Actions transporting victims of radiological 3.VI ERPIP-103, Nuclear Plant Operations accidents to medical support facilities. 5.I.H.3 ERPIP-312, Safety Services-App. D ERPIP-730, Health Physicist Hospital Assistance I/ The availability of an integrated medical services system and a public health emergency plan serving the area in which the facility is located and, as a minimum, equivalent to the Public Health Service Guide for Developing Health Disaster Plan, 1974, and to the requirements of an emergency medical services system as outlined in the Emergency Medical Services System Act of 1973 (P. L.93-154 and amendments in 1979 P.L.96-142), should be part of and consistent with overall State and Local Disaster control plans and should be compatible with the specific overall emergency response plan for the facility.

Revision 41

M. Recovery and Reentry Planning and Postaccident Operations Planning Standard General plans for recovery and reentry are developed.

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

1. Each organization, as appropriate, shall 4.[V.H ERPIP-50 1, Emergency Director/Recovery develop general plans and procedures for Manager reentry and recovery and describe the means by which decisions to relax protective measures (e.g., reached). This process should consider both existing and potential conditions.

2. Each licensee plan shall contain the 3.[V position/title, authority and Att. 3-4 responsibilities of individuals who will fill key positions in the facility recovery organizations. This organization shall include technical personnel with responsibilities to develop, evaluate and direct recovery and reentry operations.

The recovery organization recommended by the Atomic Industrial Forum's "Nuclear Power Plant Emergency Response Plan" dated October 11, 1979, is an acceptable framework.

.3. Each licensee and State plan shall 4.IVl.H. ERPIP-501, Emergency Director/Recovery specify means for informing members of Manager the response organizations that a recovery operation is to be initiated, and of any changes in the organizational structure that may occur

4. Each plan shall establish a method for 4.1V.G ERPIP-51 1, Radiological Assessment periodically estimating total population Director exposure ERPIP-504, Environmental Assessment Director (EOF)

Revision 41

N. Exercises and Drills Planning Standard.

Periodic exercises are (will be) conducted to evaluate major portionsof emergency response capabilities, periodic drills are (will be) conducted to develop and maintain key skills, and deficiencies identified as a result of exercised or drills are (will be) corrected.

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS l.a. An exercise is an event that tests the 6.11 ERPIP-905, Exercises, Tests and Drills integrated capability and a major portion of the basic elements.existing within emergency preparedness plans and organizations. The emergency preparedness exercise shall simulate an emergency that results in offsite radiological releases which would require response by onsite authorities.

Exercises shall be conducted as set forth in NRC and FEMA rules.

b. An exercise shall include mobilization of 6.11 ERPIP-905,:Exercises, Tests and Drills State and local personnel and resources adequate to verify the capability to respond to an accident scenario requiring response. The organization shall provide for a critique of the annual exercise by Federal and State observers/evaluators.

The scenario should be varied from year to year such that all major elements of the plans and preparedness organizations are tested within a five-year period.'

Each organization should make provisions to start an exercise between 6:00 p.m. and midnight, and another between midnight and 6:00 a.m. once every six years. Exercises should be conducted under various weather conditions. Some exercises should be unannounced.

Revision 41

N. Exercises and Drills (continued) 1 Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

2. A drill is a supervised instruction period 6.11 ERPIP-905, Exercises, Tests and Drills aimed at testing, developing and maintaining skills in a particular operation. A drill is often a component of an exercise. A drill shall be supervised and evaluated by a qualified drill instructor. Each organization shall conduct drills, in additionto the annual exercise at the frequencies indicated below:

a. Communications Drills 6.11 ERPIP-905, Exercises, Tests and Drills Communications with State and local, governments within the plume exposure pathway Emergency Planning Zone shall be tested monthly. Communications with Federal emergency response organizations and States within the.

ingestion pathway shall be tested quarterly. Communications between the nuclear facility, State and local emergency operations centers, and field assessment teams shall be tested annually. Communication drills shall also include the aspect of understanding the content of messages.

b. Fire Drills 6.11 ERPIP-905, Exercises, Tests and Drills Fire drills shall be conducted in accordance with the plant (nuclear facility) technical specifications.

Revision 41

S N. Exercises and Drills (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

c. Medical Emergency Drills 6.11 ERPIP-905, Exercises, Tests and Drills A medical emergency drill involving a simulated contaminated individual which contains provisions for participation by the local support services agencies (i.e.,

ambulance and offsite medical treatment facility) shall be conducted annually.

The offsite portions of the medical drill may be performed as part of the required annual exercise

d. Radiological Monitoring Drills 6.11 ERPIP-905, Exercises, Tests and Drills Plant environs and radiological monitoring drills (onsite and offsite) shall be conducted annually. These drills shall include collection and analysis of all sample media (e.g., water, vegetation, soil and air), and provisions for communications and record keeping.

The State drills need not be at each site.

Where appropriate, local organizations shall participate.

e. Health Physics Drills 6.11; ERPIP-905, Exercises, Tests and Drills (1) Health Physics drills shall be conducted semi-annually which involve response to, and analysis of, simulated elevated airborne and liquid samples and direct radiation measurements in the environment. The State drills need not be at each site.

(2) Analysis of in-plant liquid 6.11 ERPIP-905, Exercises, Tests and Drills samples with actual elevated radiation levels including use of the post-accident sampling system shall be included in Health Physics drills by licensees annually.

Revision 41

N. Exercises and Drills (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

3. Each organization shall describe how 6.11 ERPIP-905, Exercises, Tests and Drills exercises and drills are to be carried out to allow free play for decision making and to meet the following objectives.

Pending the developments of exercise scenarios and exercise evaluation guidance by NRC and FEMA the scenarios for use in exercises and drills shall include but not be limited to, the following:

a. The basic objective(s) of each drill and exercise and appropriate evaluation criteria;

b. The date(s), time period, place(s) and participating organizations;

c. The simulated events

d. A time schedule of real and simulated initiating events;

e. A narrative summary describing the conduct of the exercises or drills to include such things as simulated casualties, o6ffsite fire department assistance, rescue of personnel, use of protective clothing, deployment of radiological monitoring teams, and public information activities; and

f. A description of the arrangements for and advance materials to be provided to official observers.

Revision 41

N. Exercises and Drills (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

4. Official observers from Federal, State or 6.11 ERPIP-905, Exercises, Tests and Drills local governments will observe, evaluate, and critique the required exercises. A critique shall be scheduled at the conclusion of the exercise to evaluate the ability of organizations to respond as called for in the plan. The critique shall be conducted as soon as practicable after the exercise, and a formal evaluation should result from the critique.

5. Each organization shall establish means 6.11 ERPIP-905, Exercises, Tests and Drills for evaluating observer and participant.

comments on areas needing improvement, including emergency plan procedural changes, and for assigning responsibility for implementing corrective actions. Each organization shall establish management control used to ensure that corrective actions are implemented.

Revision 41

0. Radioloeical Emereency Response Training Planning Standard Radiological Emergency Response training is provided to those who may be calledon to assist an emergency.

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

1. Each organization shall assure the 6.1 EP-1-306, Calvert Cliffs Emergency training of appropriate individuals. Response Organization Training EP-1-305, Calvert Cliffs Staff Augmentation

a. Each facility to which the plant applies 6.I.B.7 EP-l-306, Calvert Cliffs Emergency shall provide site specific emergency Response Organization Training

- response training for those offsite emergency organizations who may be called upon to provide assistance in the event of an emergency. I/

b. Each offsite response organization shall 6.I.B.7 EP-l-306, Calvert Cliffs Emergency participate in and receive training. Response Organization Training Where mutual aid agreements exist between local agencies such as fire, police and ambulance/rescue, the training shall also be offered to the other departments who are members of the mutual aid district.

1/ Training for hospital personnel, ambulance/rescue, police and fire departments shall include the procedures for notification, basic radiation protection, their expected roles. For-those local services support organizations who will enter the site, training shallalso include site access procedures and the identity (by position and title) of the individual in the onsite emergency organization who will control the organizations' support activities. Offsite emergency response support personnel should be provided with appropriate identification cards where required.

Revision 41

O. Radiological Emergency Response Training (continued)

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

2. The training program for members of the 6..13 ERPIP-905, Exercises, Tests and Drills onsite emergency organization shall, 6.11 EP-l-306, Calvert Cliffs' Emergency besides classrooms training, include Response Organization Training practical drills in which each individual demonstrates. ability to perfornm.his assigned emergency function. During, the practical drills, on-the-spot correction of erroneous performance shall be made and a demonstration of the proper performance offered by the instructor.

3. Training for individuals assigned to 6.1.B.6 EP- t-306, Calvert Cliffs Emergency licensee first aid teams shall include Response Organization Training courses equivalent to Red Cross Multi-Media.

4. Each organization shall establish a 6.1 EP-1-306, Calvert Cliffs Emergency training program for instructing and Response Organization Training qualifying.personnel who will implement radiological emergency response plans.

2/ The specialized initial training and periodic retraining programs and (including the scope, nature and frequency) shall be provided in the following categories: q 2/ If State and local governments lack the capability and resources to accomplish this training, they may look to the licensee and the:Federal government (FEMA) for assistance in this training.

NRC and FEMA encourage State and local governments which have these capabilities to continue to include them in their training programs.

9 Revision 41

0. Radiological Emergency Response Training (continued)

Applicability and Cross Reference :

Evaluation Criteria ERP IMPLEMENTING DOCUMENTS EP-l-306, Calvert Cliffs Emergency Response

a. Directors or coordinators of the response 6.1.B. 1 Organization Training organizations; EP-1-306, Calvert Cliffs Emergency Response

b. Personnel responsible for accident 6.I.B.2 Organization Training assessment; EP-1-306, Calvert Cliffs Emergency Response

c. Radiological monitoring teams and 6.I.B.3 Organization Training radiological analysis personnel; EP-1-306, Calvert Cliffs Emergency Response

d. Police, security andfire fighting 61B.4 Organizaiion Training personnel;

e. Repair Iand damage controlc orrectional 6.1.B.5 EP-l-306, Calvert Cliffs Emergency Response Organization Training action teams (onsite);

EP- 1-306, Calvert Cliffs Emergency Response

f. First aid rescue personnel; 6.1.B.6 Organization Training . . ,:

EP-l-306, Calvert Cliffs Emergency Response

g. Local support services personnel 6.LB.7 Organization Training including Civil Defense/Emergency.

Service personnel; EP-l-306, Calvert Cliffs Emergency Response

h. Medical support personnel; 6.[.B.8 Organization Training EP-1-306, Calvert Cliffs Emergency Response

i. Licensee's headquarters support 6.1.B.9 Organization Training.

personnel; EPO--306, Calvert.Cliffs Emergency Response

j. Personnel responsible for transmission 6.1.B.110 Organization Training.

of emergency' information and instructions.

5. Each organization shall provide for the 6.1 EP-1-306, Calvert Cliffs Emergency.

initial and annual retraining of personnel Response Organization Training with emergency response EP-l-305, Calvert Cliffs Staff "responsibilities. Augmentation Revision 41

All P. Responsibility for the Planning Effort: Development. Periodic Review and Distribution of Emergency Plans Planning Standards Responsibilities for plan development and review and for.distribution of emergency plans are established, and planners are properly trained.

Applicability and Cross Reference Evaluation Criteria ERP IMPLEMENTING DOCUMENTS

1. Each organization shall provide for 6.1D CNG-EP-!.01-1003, EPStaff Training training of individuals responsible for the planning effort

2. Each organization shall identify by title 6.111 the individual with the overall authority and responsibility for radiological.

emergency response planning.

3. Each organization shall designate an 6.111 Emergency Planning Coordinator with responsibility for the development and updating of emergency plans and, coordination of these plans with other response organizations.

4. Each organization shall update its plan 6.V.A. EP-!-100, Preparation and Control of the and agreements as needed, review and 6.V.C. Emergency Response Plan-certify it to be current on an annual

- basis. The update shall take into CNG-EP-1.01-1002, Control of Emergency

, account changes identified by drills and Preparedness Progr amActivities exercises.

5. The emergency response plans:and:. 6.V.B CNG-EP-1.01-1002, Control of Emergency approved changes to the plans shall be App. B Preparedness Program Activities forwarded to all organizations and appropriate individuals with 6.V.C.

responsibility for implementation of the plans. Revised pages shall be dated and marked to show where changes have been made.

Revision 41

i P. Responsibility. for the Planning Effort: Development, Periodic Review and Distribution of Emergency Plans (continued)

Applicability and Cross Reference Evaluation Criteria. ERP IMPL*EMENTING DOCUMENTS

6. Each plan shall contain a detailed Section 7 listing of supported plans and their source.

7. Each plan shall contain as an appendix Table of listing, by title, procedures required to Contents implement the plan. The listing shall.

include the section(s) of the plan to be App. E implemented by each procedure.

8. Each plan shall contain a specific table T of C of contents. Plans submitted for review App. E should be cross-referenced to these criteria.

9. Each licensee shall arrange for and 6.V.F conduct independent reviews of the - 6.VI emergency preparedness program at least every 12 months. (An independent review is one conducted by any competent organization either internal or external to the licensee's organization, but who are not immediately responsible for the emergency preparedness program). The review shall include the emergency plan. It implementing procedures and practices, training, readiness testing, equipment, and interfaces with State and local governments. Management controls shall be implemented for evaluation and correction of review findings. The result of the review, along with recommendations for improvements, shall be documented, reported to appropriate licensee corporate and plant management, and involved Federal, State and local organizations, and retained for a period of five year.

Revision 41

S P. Responsibility for the Planning Effort: Development, Periodic Review and Distribution of Emergency Plans (continued),

Applicability and Cross Reference Evaluation Criteria ERP [MPLEMENTING DOCUMENTS

10. Each organization shall provide for 6.V.E updating telephone numbers in emergency procedures at least quarterly..

. Revision 41

ML100550711

Text

SUBJECT:

Enclosures:

SUMMARY

3.0 REFERENCES

3.0 REFERENCES

Dear Mr. Spect:

Dear Ladies and Gentlemen:

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