ML18040A339

Forwards EPIPs & Rev 36 to Site Emergency Plan.Procedures Submitted as Required by Section V to App E of 10CFR50

ML18040A339
Person / Time
Site:	Nine Mile Point
Issue date:	04/24/1998
From:	Terry C NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18040A340	List: ML18040A339
References
98-EP-020, 98-EP-20, NUDOCS 9805060102
Download: ML18040A339 (166)

Text

CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9805060102 DOC.DATE-',98/04/24 NOTARIZED: NO FACIL:50-220 Nine Mile Point Nuclear Station, Unit 1, Niagara Powe

,50-410 Nine Mile Point Nuclear Station, Unit 2, Niagara Moha AUTH.NAME AUTHOR AFFILIATION TERRY, C.D.

Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

DOCKET 05000220 05000410

SUBJECT:

Forwards EPIPs

&. Rev 36 to Site Emergency Plan. Procedures submitted as required by Section V to App E of 10CFR50.

DISTRIBUTION CODE: A045D COPIES RECEIVED: LTR 1

ENCL I

SIZE:

) +

TITLE: OR Submittal:

Emergency Preparedness

Plans, Implement'g Procedures, C p NOTES:

RECIPIENT ID CODE/NAME PD1-1 LA HOOD,D r~

INTERNAL: AEOD/HAGAN,D NRR/DRPM/PE RB EXTERNAL: NOAC COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 RECIPIENT ID CODE/NAME PD1-1 PD NUDOC~STRACT NRC PDR COPIES LTTR ENCL 1

1 2

2 1

1 1

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NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)

ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:

LTTR 10 ENCL 10

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NIAGARAMOHAWK C EN ERATION BUSINESS GROUP NINE MILEPOINT NUCLEARSTATION/LAKEROAD, P.O. BOX 63. LYCOMING,NEW YORK 13(83/TELEPMONE (315} 349.7263 FAX(315}34W753 CARL D. TERRY Yice President Nuclear Safety Assessment and Support April 24, 1998 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 file code:

98"EP 020 RE:

Nine MilePoint Unit 1 Docket No. 50-220 DPR-63 Nine MilePoint Unit 2 Docket No. 50-410 NPF-6 Gentlemen:

Enclosed please find copies of the followingEmergency Procedures for Niagara Mohawk Power Coiporation's Nine Mile.Point Nuclear Station:

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EPMP-EPP-02, Revision 14, "Emergency Equipment Inventories and Checklists"

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EPIP-EPP-13, Revision 08, "Emergency Response Facilities Activation and Operation".

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EPIP-EPP-11, Revision 03, "Hazardous Material Incident Response"

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EPIP-EPP-10, Revision 03, "Security Contingency'Event"

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EPIP-EPP-22, Revision 02, "Damage Control"

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EPIP-EPP-30, Revision 03, "Prompt Notification System Problem Response" EPIP-EPP-08, Revision 08, "Off-Site Dose Assessment and Protective Action Recommendation"

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Site Emergency Plan, Revision 36 These procedures are being submitted as required by Section V to Appendix E of 10 CFR Part 50. Should you have any questions, please feel free to contact Mr. James D. Jones, Director ofEmergency Preparedness at (315}

349~86.

Very trul

urs, Carl D. Teiry,'V'resident Nuclear Safety Assessment and Support lda Enclosure Mr. H.J. Miller,Regional Admini'strator, Region I (2 copies)

Mr. B.S. Norris, Senior Resident Inspector Mr. D.S. Hood, Senior Project Manager, NRR Records Management 9805060i02 980424 PDR ADOCK OSOO0220 F

PDR Qrr I,5

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NIAGARA MOHAWK, POWER CORPORATION NINE MILE POINT NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EPI-EP->>

~EY IE PROMPT NOTIFICATION SYSTEM PROBLEM R

SPONS TECHNICAL SPECIFICATION REqUI ED

/

Approved By:

'bow~'.

L. Rademacher Plant Manager -

Da Approved By:

J. T. Conway Pla Manag Unit~2 Da e s/)7 THIS IS A FULL REV SION Effective Date:

PERIODIC REVIEM DUE DATE

~RRCH 2998

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Page 3

EPIP-EPP-30 Rev 02

SECTION 1.0 PURPOSE 1AABO CIINT NTE.

PAGE

2. 0 PRIMARY RESPONSIBILITIES 3.0 4.0 PROCEDURE 3.1 Unit 1 Station Shift Supervisor 3.2 Central Region Operator 3.3 Station Haintenance Supervisor and Supervisor DEFINITIONS.

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Communications Group 1

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5.0 REFERENCES

AND COHHITHENTS 6.0 RECORD REVIEW AND DISPOSITION ATTACHHENT 1:

PNS PROBLEM NOTIFICATION/RETURN-TO-SERVICE CHECKLIST (UNIT 1 SSS)

ATTACHHENT 2:

CENTRAL REGIONAL OPERATORS CHECKLIST.

ATTACHMENT 3:

SIREN PROBLEM RESPONSE GROUP MATRIX AND CALL-OUT LIST ATTACHMENT 4:

DESCRIPTION OF SIREN LOCATIONS.

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8 Page ii EPIP-EPP-30 Rev 02

1.0

~PU POS To provide criteria for the evaluation, notification, and corrective actions required in response to problems associated with any component of the Oswego County Prompt Notification System (PNS).

2. 0 PRINAR SPO SIBILITIES 2.1 U t Stat o

Shift Su ervisor SSS

2. 1.1 Receives notification of Prompt Notification System (PNS) problems.

2. 1.2 Completes the PNS Problem Notification/Return-to-Service Checklist (Unit 1 SSS)

(Attachment 1).

2.2 Station Naintenance/Coaeunication Group On-Call Supervisor Directs appropriate personnel in correcting PNS problems.

2.3 Oswego County Fire Dispatcher - Provides response to siren alarms and takes appropriate action.

2.4 Central Regional Operators Receive reports of a PNS problem and complete Attachment 2.

I 3.0

~ROCEUUR

3. 1 Unit 1 Station Shift Su ervisor 3.1.1 Copy information on Prompt Notification System problem to Attachment 1, Section 1,

as received via REGS or telephone.

3. 1.2 Complete actions as appropriate in Attachment 1, Section 2

and 3, 3.2 Ce t al e

o 0 erator 3.2. 1 Copy information on Prompt Notification System problem to Attachment 2 as received via telephone.

3.2.2 Complete appropriate actions as indicated on Attachment 2.

3.2.3 Utilize call-out 'Iist (Attachment 3) to contact repair group supervisors, if needed.

3.3 Statio a ntenance Su ervisor and Communications Grou Su ervisor Dispatch repair crews as requested by the Central Region Operator.

Page 1

EP IP-EPP-30 Rev 02

4.D D~tl II 4.1 t't c tio S stem - A communications system used for notifying the public of an emergency at Nine Mile Point.

It consists of the outdoor sirens

system, the National Heather Service tone alert radio

system, and the Emergency Broadcast System/Emergency Alert System (EBS/EAS).

4.2 ~4-44 f ltt 4

t ftt 2

4 Notification System, this means that the component cannot perform its intended function.

5.0 R

E C S CO T

E S

5.1 ce see Documentatio SEP, Site Emergency Plan 4

5.2 Standa ds e u at o s and Codes 5.2.1 FEMA-REP-10, Guide for the Evaluation of Alert and Notification System for Nuclear Power Plants 5.2.2 NUREG-0654-FEMA-REP-I, Criteria for Preparation and Evaluation of Radiological Emergency

Response

Plans and Preparedness in Support of Nuclear Power Plants 5.2.3 NUREG-1022, Supplement 1, Licensee Event Reporting System Description of System and Guidelines for Reporting Events 5.3 Po cies o

s a

d rocedu es 5.3.1 NIP-ECA-01, Deviation/Event Report 5.3.2 EPMP-EPP-08, Maintenance Testing and Operation of the Oswego County Prompt Notification System

4. 4 ~it Sequence NCTS Number

~Nmbe None Descri tion Page 2

EP IP-EPP-30 Rev 02

SOS 0

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Attachment 1,

"PNS Problem Notification/Return-to-Service Checklist" 6.2 The following records generated by this procedure are not required for retention in the Permanent 'Plant File:

60 CO S

6. 1 The following records generated by this procedure shall be maintained by Records Management for the Permanent Plant File in accordance with NIP-RMG-01, Records Management:

~, "Central Regional Operation Checklist" Page 3

EPIP-EPP-30 Rev 02

TTACHH NT I Sheet I of 2 COMPLETED BY Print Name/initial Date SEGTloN 1.0 - lN)T)ALNDT)F)cATioN FROID CoUNTY The fo//owinp /nformetion willbe transmitted by Oswego County.

Complete the form es appropriate.

This is the Oswego Corer ty Weminp point.

This rinp /s for the Nine Mile Unit 1 end Un/t 2 Control Rooms, Rtzpetrick Contro/ Room and the Stets Weminp point. Th/sis to notify you ofe failure of the Oswego County prompt Notif/cation System.

Stand by forrollcell.

Stand by to Copy:

0 Unit 1 Control Room 0 Unit 2 Control Room 0 fitzpotrick Control Room 0 State Warning Point 1

Message transmitted et:

Date:

Time:

2 Reported by:

Name:

Locedon:

3 The following sirenis) have been out of service for more then one hour /C/rcle as eppropr/ete/:

1 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 '25 26 27 28 29 30 31 32 33 34 35 36 37 4

The following siren(s) ere beck in service (Circle as epproprieteJr 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 5

There hes been e false activation of the following siren(s) (Circ/e as appropriate/:

1 2

3 4

5 8

7 8

9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 6

The 0 Tone Alert 0 EBS/EAS /Mark as epproprieteJ System hes been out of service for one hour es of /Time/:

7 The 0 Tone Alert 0 EBS/EAS /Merk as approprieteJ System is beck in service es of /TimeJ:

8 Comments:

9 All stations stand by to acknowledge receipt of the message

/Repeat rollcelleboveJ.

0 Unit 1 Control Room 0 Unit 2 Control Room 0 Fitzpatrick Control Room 0 State Warning Point Page 4

EPIP-EPP-30 Rev 02

TTACM EN Sheet 2 of 2 SEenoN 2.0 - DETERMINATIDN OF AcnONS To BE TAKEN 2.1 IF Item 3 In Section 1.0 - Initial Notification from County" is applicable, THEN perform Steps 3.1 through 3.3 as applicable.

2.2 IF Item 4 in Section 1.0 - Initial Notification from County" is applicable, THEN perform Step 3.3.

2.3 IF Item 5 in Section 1.0- Initial Notification from County is applicable, THEN perform Step 3.2 then Step 3.4.

2.4 IF Item B In Sect)on 1.0- lnit)al Notification from County is applicable, THEN perform Steps 3.1 through 3.3, es applicable.

2.5 IF Item 7ln Section 1.O-initialNotificetionfromCounty is applicable, THENperform Step 3.3.

SEOTIDN 3.0 - NDTIFicaTIDN DETEmlNaTION 3.1 IF ANYof the criterie below are met, THEN notify the NRC of e major loss of notification capability, in accordance with 10CFR50.72.

Nineteen {19) or more sirens are out-of-service simultaneously for one (1) hour or greater Four {4) or more sirens ere out-of-service simultaneously for twelve (12) hours or greater The National Weather Service INWS) is unable, for a period of one (1) hour or greater to activate Tone-Alert Radios Activation of the Emergency Broadcast System IEBS/EAS) is ineffective for e period of one hour or greeter.

IF NRC notification ls required, THEN initiate a DER in accordance with NIP-EGA<1 after completion of this checklist.

Date Time Initials b.

Notifythe Unit 2 Station Shift Supervisor of intent to notify the NRC to report a PNS problem co Notifythe JAF Control Room, Station Shift Supervisor of intent to notify the NRC

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d.

Notifythe NRC vie the ENS (Rsd Rhons) of the PNS problem.

3.2 Notified the Director Emergency Preparedness of the PNS problem

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0 See EP Department On-cell Schedule 3.3 Copy of this completed checklist forwarded to:

Emergency Preparedness Department Nine Mile Point Nuclear Station.

3.4 If the PNS problems involved a siren false activation, notify the Nuclear Communications end Public Affairs On-call Supervisor Page 5

EP IP-EPP-30 Dav A7

TTACHHENT 2 omp et y

nr ate ACTIONS TAKSN IXITIAU)"

DATE 1

Notification of siren problem reoelved from:

0 Oswego County Warning Point 0 Other 2

Siren problem wos reported os (riel(cote belowJ:

0 Siren problem(a) involveis) power distribution outage ond no Apparatus Needing Attention fANA) is required.

When power is restored, go directly to Step B.

0 Sirenis) or Activation System Out of Service (Go to Stop 3J 0 Sirenis) False Activation (Go to Step 4J 3

Sirens Outwf&ervloe 3a The following sirens reported out of service (Circle os eppropnkrrelc 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 28 27 28 29 30

~ 31 32 33 34 35 36 37 3b Record specific lnforinotion provided on the siren problem; request that Fire Control provide the alarm or condition:

3c Go to Stop 5o or 5b 4

Slreni ~) False Activation, 4o A false activation was reported on (Circle os opprrppnkrfeJt 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 28 27 28 29 30 31 32 33,34 35 36 37 4b Record specifio information provided on the siren problem:

4o Go to Stop Sc or 5d 5

Slrenis) Repair Criteria (ind(cote be(owJ.(then fio to Step 7J Sae Attachment 3 for "Appropriate Department or Personnel" 5a One or two sirens out-of-service, complete ANAform ond forward to the appropriate deportment for repairs.

5b Three or more sirens out-of-service or activation system out-of-service, immediately contact and dispatch appropriate personnel to correct the siren problems, Consult appropriate on. call department schedules to determine on. cell individuals for each responsible deportment.

5c A false activation has been corrected {silenced), immediately dispatch appropriate personnel to investigate.

Sd A false activation hes not been corrected lsilenced), dispatch appropriate personnel immediately to silence the siren ond complete an ANAto investigate the cause.

5e Name of personis) contacted:

Time:

Notifications 6o When the power hos been restored, Inform the Oswego County Worning Point, 343-1313.

"Power hes bean restored to all sirens as of hours.

Bb If Oswego County Warning Point indicates that all sirens are back in service, go to Step 7.

6c If Oswego County Warning Point indicates that any slrenis) are still out-of-service, go to Step 7 and initiate o new Central Regional Operators Checklist, and subsequent ANA.

7 Copy of chio completed checkgst forwarded to:

Emergency Preparedness Deportment Nine Milo Point Nuclear Station Ifsteps orinstructions do not apply, enter N/A (Nor ApplicobleJ in the Iniriels Column.

Page 6

EPIP-EPP-30 Rev 02

ATTACHMENT 3 S

R P 0 LEM RESPONS GROUP MATRIX ND C LL-OUT LIST Alarm or Condltbn Responsible Groupie)

Intrac Ensbbd Siren Ann Qren Alert Qren Attack Qren Run Ok Sinn Run Intrsc Siren Run (sny condltbn)

CP3 AC Fall or AC Power FsN Battery Low Doors Open Com Fall Any Computer Mslfunctbn/FsNure Any Intrac Problem Reported False Actfvatbn {withor without SAMS Indbatbn)

Nuisance Alarm Ior sny conditbn that Fks Control feels ls worth Inves69sSna)

Stetbns or Rsdb Ststbns or Radb Ststbns or Radio Stations or Rsdb Radio Ststbns or Radio Rsdb or Stations Computer Statbns or Rsdb Suspected Physical Dsrns9a to Skan Iwlth or without SAMS alarm)

Stations Work Phone Payer J. Brftt B. ConnsNy S. Dombk F. Howley M. Lechut R. Menikhslm A. Rebeor 836.8829 662 648'I 387.8184 387-SS88 698.6998 836-9419 693.1930 460.2813 460 2390 480.2389 460-2387 692%142 692+1 24 692+1 68 3384 3437 3460 3448 3447 3388 3449 T. laden W. Dalfsraro J. WeN W. Edwards G. Smith R. Hudson 896-6822 487-7819 298 6818 89S-6713 652.6311 7374M07 460 2378 460-2379 460 2379 460.2379 480-2379 798.616'I 3378 3763 3612 6826 339S 6285 Co>IMI ar NOTE: Ifoff-hours, usa ONLYIf Fka Control SAMS ls inopersbla.

Unit 1-Control Room 349-2480'Request that the On.Call ISC Supervisor ba contacted.

Page 7

EPIP-EPP-3O Rrst/ 09

ATTACHMENT 4 SCR 0

0 S

0 ONS Sheet 1 of 2 2.

3.

4.

5.

6.

7.

8.

9.

Approximately 0.9 miles west of Energy Center driveway west of Nine Mile ¹1 on Lake Shore Road by Staging Area.

End of Lake Road East junction of Nine Mile Point Road.

Pleasant Pt.

Road off North Road (Co. Rt. ¹1) toward lake, access by wooden gate.

End of North St.

Road and, Dempster Beach Drive (Co. Rt. ¹1) past Hickory Grove Drive.

Butterfly Road - off North Road (Co. Rt. ¹1) where North Road and 104B meet.

Mexico Point Road off 104B by Adele's Bar.

Hager Road off Route ¹3 just before Len-Marr Golf Course.

Airport Road off Co. Rt. ¹29 by radio towers.

Corner of 104 West and Fred Haynes Boulevard (Rudy's entrance).

10.

Utica Street and Third Avenue - Oswego Gas Dist. Yard.

Behind Fort Ontario Skating Rink Off East 9th St.,

Oswego by east side pool behind City Garage.

12.

Burt Street, Paloma Sub.

13.

14.

Gardner Road - bottom of hill before Johnson Road from Oswego Center to South West Oswego Sub.

Galletta's Greenhouse on Maple Avenue (Co. Rt. ¹20) off W. 5th Street Road.

15.

One mile down west side of dirt road just East of Old Timer's Inn.

16.

17.

18.

3.0 miles west of site on Route lA, Lake Shore Road between Alcan and Nine Mile ¹1.

Co. Rt. ¹1, 1.5 miles East of Lakeview Rd.

Co. Rt. ¹27 - Lycoming Fire Barn (past Rhinehart's old house) can be used for fire signal.

19.

Off Kocher Road - East of Middle Road.

20.

Scriba Recreation Center (Corner Creamery Road and Route 104)

Page 8

EPIP-EPP-30 Rev 02

ATTACHMENT 4 SC ON OF S

OC IONS Sheet 2 of 2 21.

Duke Road 22.

City Line Road Oswego South of Speedway by Mine Creek Inn.

23.

Off Hall Road - Dutch Ridge Road (by Steve Baxter's house).

24.

Old Rt.

57 across from Riverside Cemetery.

25.

Benson Avenue (Co. Rt. 825 by Minetto Fire Barn).

26.

Old Rt.

57 between Fulton and Minetto North of Fairview Cemetery.

27.

Bundy Crossing on March Road between Kingdom Road and Route 481.

28.

Between Rt.

104 and Lake Shore Road on Middle Road off east of Co. Rt.

29.

29.

Co. Rt. fl North Road - east of Shore Oaks Road.

30.

Intersection of NY 104 and 104B.

31.

Sundown Road, Vermillion off Co. Rt. 35 (Road goes by church in Palermo).

32.

Co. Rt.

k'16 by Flat Rock Camp Site comes out at intersection Rt.

3 and 104 in Mexico at stop light.

33.

104 and Lincoln Avenue, Mexico (Mexico Sub).

34.

104 East - by Gun Club approximately I/2 mile east of Jerrett Road siren in field.

35.

O'onnor Road east off Co. Rt.

29 next to power lines Pilins home between Hall Road and 104.

36.

Corner of Mest Utica and 6th Street.

37.

Corner of Co. Rt.

88 and Doolittle Road.

Page 9

EPIP-EPP-30 Rev 02

0

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-EPP-22 REVISION 01 DAMAGE CONTROL TECHNICAL SPECIFICATION REQUIRED Approved by:

N. L. Rademacher Plant Manager - Unit I aifi.: )~

Date Approved by:

K. A. Dahlberg P

t Manager Unit vu Vs Date THIS IS A FULL REVISION PERIODIC REVIEW, 07/3.0/97, NO CHANGE PERIODIC REVIEW,07/22/96,NO CHANGE Effective Date:

9/22/95 NOT TO BE USED AFTER SUBJECT TO PERIODIC REVIEW

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~Ch Coversheet LIST OF EFFECTIVE PAGES Pacae No.

Chan e No.

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9 10 11 12 13 I

July 1992 Page i EPIP-EPP-22 Rev 00

TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE

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1

2.0 REFERENCES

AND COMMITMENTS 1

3.0 DEFINITIONS...........................

2 4.0 RESPONSIBILITIES........................

2 5.0 PRECAUT IONS

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4 6.0 LIMITATIONS AND ACTIONS.....................

5 7.0 PREREOUI SITES..........................

5 8.0 PROCEDURE 5

.1 Equipment 8.

8.2 Damage Control Team gualification/Composition

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6 8.4 Damage Control Team Coordinator and OSC Instrumentation and Control Coordinator 8

8.5 Maintenance Coordinator and Instrumentation and Control

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Coordinator 9.0 ACCEPTANCE CRITERIA.

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9 12 10.0 RECORD REVIEW AND DISPOSITION..................

12 ENCLOSURE 1:

EMERGENCY DAMAGE CONTROL

SUMMARY

FORM 13 July 1992 Page ii EP IP-EPP-22 Rev 00

.I

1.0 PURPOSE To define the actions which provide for the assessment,

repair, and maintenance of equipment/components during an emergency.

2.0 2.1

2.2 REFERENCES

AND COMMITMENTS Technical S ecifications None Policies Pro rams and Procedures 2.2. 1 EPIP-EPP-18, Activation and Direction of Emergency Plan 2.2.2 EPIP-EPP-23, Emergency Personnel Action Procedures 2.2.3 EPMP-EPP-02, Emergency Equipment Inventories and Checklists 2.2.4 EPMP-EPP-01, Maintenance of Emergency Preparedness 2.2.5 2.2.6 EPIP-EPP-02, Fire Fighting EPIP-EPP-06, Inplant Emergency Surveys 2.3 2.2.7 EPIP-EPP-15, Health Physics Procedure 2.2.8 Site Emergency Plan (SEP) Sections 5 and 7

2.2.9 AP-4.0, Administration of Operations Commitment Sequence Number NCTS Number 003238-22 003197-03, 003238-11 003238-11, 003197-03, 502722-00 003197-09 Descri tion Use the Work Control Center.

Allow for verbal authorizations from the TSC.

Streamline the dispatch process.

High Intensity Lights are available if required for both Units 1

and 2.

July 1992 Page I

EPIP-EPP-22 Rev 00

3.0 DEFINITIONS None 4.0 RESPONSIBILITIES 4.1 Station Shift Su ervisor SSS of the Affected Unit 4.1.1 4.1.2 4.1.3 Assumes the role of Site Emergency Director (SED) until properly relieved by a ranking site supervisor.

Evaluates the consequences of a radiological emergency as the emergency pertains to nuclear safety and the overall operation of the plant.

Evaluates the use of Damage Control Teams to minimize, control, or terminate the emergency condition.

4.2 TSC Maintenance Coordinator 4.2.1 4.2.2 Reports to the Site Emergency Director (SED} or SSS.

Manages:

a.

c ~

Equipment repair Equipment maintenance Installment of emergency

systems, structures, and components 4.2.3 d.

Mitigation and cleanup activities Provides technical and administrative direction to the Damage Control Teams per EPIP-EPP-23, Emergency Personnel Action Procedures, 4.3 TSC Instrumentation and Control Coordinator 4.3.1 4.3.2 Reports to the Maintenance Coordinator.

Manages:

a ~

18C equipment repair during an emergency b.

ILC equipment maintenance during an emergency c ~

d.

Emergency IKC component installation H

Mitigation and clean-up activities during an emergency July 1992 Page 2

EPIP-EPP-22 Rev 00

4.3.3 Provides technical and administrative direction to the Damage Control Teams per EPIP-EPP-23, Emergency Personnel Action Procedures.

0 erations Su ort Center OSC Coordinator 4.4.1 Reports to the Site Emergency Director {SEO).

4.4.2 Coordinates OSC activities:

a.

Maintains communications with Technical Support Center

{TSC) Coordinators and the SED.

b.

Maintains direct communications with the Damage Control

Teams, through the OSC communicator.

c.

Directs the Damage Control Team Coordinator.

{NCTS 1) d.

Determines when to relocate coordination of damage repair/corrective action to the Work 'Control Center for the affected unit.

4.5 EOF Administrative Lo istics Mana er The Administrative/Logistics Manager is responsible for administrative and logistic functions required to support the off-site and on-site emergency organizations.

TSC The Radiolo ical Assessment Mana er 4.6.1 4.6.2 Manages activities to control radiation exposure.

Manages the on-site dose assessment aspects of an emergency to determine radiological consequences and hazards to station personnel.

4.7 TSC The Station Surve Sam le Team Coordinator 4.7.1 4.7.2 Assists in the evaluation of in-plant dose assessment aspects of an emergency to determine potential or actual radiological hazards to site personnel.

Interfaces with the Maintenance Coordinator, Fire Department Coordinator, and any other coordinators dispatching emergency teams to ensure appropriate radiation protection precautions and exposure control methods are provided.

4.8 OSC Dama e Control Team Coordinator 4.8.1 Reports to the OSC Coordinator.

July 1992 Page 3

EPIP-EPP-22 Rev 00

4.8.2 Provides technical and administrative direction to Damage Control Teams as directed by the OSC Coordinator and/or the Haintenance Coordinator.

4.8.3 4.8.4 Assesses damaged equipment, necessary personnel, or equipment needs to effect emergency repairs.

Keeps OSC personnel informed of Damage Control and Repair activities.

4.8,5 Ensures the 'emergency team leaders maintain accountability for respective team members.

4.9 OSC Instrumentation and Control Coordinator 4.9. 1 Reports to the OSC Coordinator.

4.9.2 Provides technical and administrative direction to the I&C members of Damage Control Teams.

4.9.3 Coordinates with the Damage Control Team Coordinator assessment of any damaged I&C related equipment and necessary repairs.

4.9.4 Keeps OSC personnel informed of I&C Damage Control and Repair activities.

4. 10 OSC Radiation Protection Team Coordinator N

Provide briefings as the radiological conditions associated with the Damage Control change.

4. 11 Dama e Control Team Leader Haintain accountability of respective team members.

4.12 Dama e Control Team 4.12.1 Reports to the Haintenance Coordinator and/or I&C Coordinator.

4.12.2 Conducts assessment,

repair, and maintenance operations.

5.0 5.1 5.2

~CANCIC N N Teams may be dispatched before or during the accountability process.

Depending upon the urgency of the situation and the radiological conditions, the Damage Control Team may be dispatched by the TSC without an RWP with a Radiation Protection Technician providing continuous radiological job coverage.

July 1992 Page 4

EPIP-EPP-22 Rev 00

6.0 LIMITATIONS AND ACTIONS None I.

~EE III ITE None 8.0 8.1 PROCEDURE

~fni ment 8.1.1 The equipment which may be used to perform damage control actions can be found in the following kits/locations:

a.

Communications Equipment -

OSC Emergency Equipment Cabinet b.

Unit 1 Fire Kits Turbine Bldg.

El 261',

1st and Bridge Screenhouse El 261',

SW Corner Admin. Bldg.

El 261', Vestibule c.

Unit 2 Fire Kits-Access Passageway Screenwell Bldg.,

Reactor Bldg.,

El Reactor Bldg.,

El Reactor Bldg'

El Reactor Bldg.,

El Control Bldg.,

El Turbine Bldg.,

El Turbine Bldg.,

El Service Bldg.,

El Turbine Bldg.,

El (AP)

El 261'SW)

El 261',

Southwest 328',

Northwest 306',

Southeast 261',

Southeast 261',

Northwest 261',

Southeast 306',

Southeast 277', Northeast 261',

Foam Room 306',

Northwest d.

Inplant Survey Kits -

OSC Emergency Equipment Cabinet e.

Protection Gear -

OSC Emergency Equipment Cabinet f.

Rescue Cabinet -

OSC g.

Tools Haintenance Shop h.

Damage Repair Supply Kit Storeroom (Unit 1) i.

Damage Control Tool Box - Screen House (Unit 1)

July 1992 Page 5

EP IP-EPP-22 Rev 00

8.1.1 (Cont)

(NCTS 4) j.

High Intensity Lights - Electrical "Dirty Shop" T.B.

261'l (Unit 1) 8.1.2 EPHP-EPP-02, Emergency Equipment Inventories and Checklists provides a complete description of the equipment contained within the Damage Repair Supply Kit and Damage Control Tool Box.

8.2 8.1.3 8.1.4 Damage 8.2.1 Obtain additional equipment from the Haintenance

Shop, storeroom, or other station equipment storage areas.

Request equipment from other resources, such as rental equipment companies, through the Administrative/Logistics Nanager located in the Emergency Operations Facility (EOF).

Control Team uglification Com osition A qualified Damage Control Team member is:

a.

Listed in the List of gualified Personnel for Staffing Emergency Positions; AND b.

Self Contained Breathing Apparatus (SCBA) trained and verified using the most current Respiratory Status Report; AND 8.2.2 c.

Damage Control trained.

Typical Compositioz a.

Normal Working Hours 1.

Haintenance Supervisor or Chief Nechanic/Electrician 2.

Radiation Protection Technician 3.

Maintenance or ISC personnel, as required b.

Off Hours l.

Operator 2.

Radiation Protection Technician 3.

Haintenance or IIEC personnel, as available July 1992 Page 6

EP IP-EPP-22 Rev 00

8.3 Dama e Control Teams Damage Control Teams should:

8.3.1 Obtain a briefing from one or more of the following:

a.

Site Emergency Director (SED) b.

Haintenance Coordinator c.

IKC Coordinator d.

Damage Control Team Coordinator e.

OSC I&C Coordinator f.

Radiation Protection Team Coordinator 8.3.2 8.3.3 Repeat key briefing points to ensure a clear understanding of the briefing.

Briefing topics should include:

a.

Radio check before entering plant; contact OSC and TSC communicators b.

Required damage assessment and repair activities c.

Anticipated levels of radiation and contamination d.

Suggested routes e.

Required protective gear f.

Respiratory requirements and qualification g.

Exposure limits allowed for work h.

Tools and equipment required i.

Procedure adherence 8.3.4 Obtain needed emergency equipment from the OSC emergency

cabinets, Naintenance

Shop, storeroom, or from normal station supplies.

This equipment should include:

a.

Tools b.

Respiratory Protection Equipment c.

Protective Clothing July 1992 u y Page 7

EPIP-EPP-22 Rev 00

8.3.4 8.3.5 8.3.6 8.3.7 (Cont) d.

Communications Equipment, when using radios for Damage Control Activities at Unit 1 use Channel t3, (Rad Teams/Maint./IKC),

Damage Control Activities at Unit 2 use Channel 4

(Rad Teams) and Channel 6 (Maint/IKC).

e.

Damage Repair Equipment 8efore leaving equipment storage location, perform a check on equipment to ensure operability.

Review the Radiation Work Permit (RWP) and procedures that have been written for the tasks, if applicable.

(See Section 5.2)

Obtain a debriefing upon completion of mission, as appropriate.

8.4 Oama e Control Team Coordinator and OSC Instrumentation and Control Coordinator Damage Control Team Coordinator and OSC Instrumentation and Control Coordinator should:

8.4.1 8.4.2 Assess damaged equipment for personnel and equipment needs to effect emergency repairs; Select personnel needed to complete identified tasks by:.

a.

Ensure properly trained, qualifications, number needed, remaining authorized

exposure, and respiratory qualification (based on Respiratory Status Report) are addressed and in accordance with Section 8.2.

8.4.3 8.4.4 b.

Document the Damage Control Team members on the Emergency Damage Control Summary Form (Enclosure 1).

Provide technical and administrative direction to Damage Control

Teams, as required.

Ensure Damage Control Teams are briefed on the mission and document the briefing on Emergency Damage Control Summary Form (Enclosure 1).

a.

Document the Damage Control Team members on Emergency Damage Control Summary Form (Enclosure 1).

b.

Ensure training, qualifications, number needed, remaining authorized

exposure, and respiratory qualification (based on Respiratory Status Report) are addressed when selecting personnel.

July 1992 Page 8

EPIP-EPP-22 Rev 00

8.4.5 Dispatch Damage Control Teams when briefing is completed and approvals are obtained.

Record on Emergency Damage Control Summary Form (Enclosure 1).

NOTE:

IF directed by Maintenance Coordinator, Damage (NCTS 2)

Control Teams may be dispatched with verbal authorization from the TSC rather than waiting For the signed Emergency Damage Control Summary Sheet.

8.4.6 Identify and document the tools, equipment, and supplies required to complete the tasks on Emergency Damage Control Summary Form (Enclosure 1).

a.

Include special items/materials that may be of assistance in timely completion of the tasks.

b.

If the mission requires entry into or through a

radiologically.hazardous

area, ensure coordination with the RAM or the SSSTC.

8.5 8.4.7 Inform OSC personnel and the Maintenance Coordinator of Damage Control activities.

8.4.8 Debrief the Damage Control Teams as appropriate.

Maintenance Coordinator and Instrumentation and Control Coordinator Maintenance Coordinator and Instrumentation and Control Coordinator should:

8.5.1 8.5.2 8.5.3 8.5.4 Confer with the SED and other TSC staff to determine damage repair and inspection needs.

Define tasks to be completed and record on Emergency Damage Control Summary Form (Enclosure 1).

Establish communications with the OSC Coordinator and/or appropriate OSC staff.

Assess the avail ability of personnel for staffing Damage Control Teams.

8.5.5 8.5.6 Coordinate with other TSC and OSC Coordinators (e.g.,

Radiation Protection, Security) for access of Damage Control Teams into vital area(s).

Have the Damage Control Team Coordinator select personnel needed to complete the tasks identified.

July 1992 Page 9

EPIP-EPP-22 Rev 00

8.5.7 When applicable, initiate an RWP to cover the tasks.

a.

Consult with the RAN and/or SSSTC.

b.

When the TSC and the OSC facilities have been staffed and activated by the SED, the normal RWP process may be modified as follows:

1.

Approval by the SED on the Emergency Damage Control Summary Form (Enclosure 1), with an RWP number entered in Section IV.

8.5.8 8.5.9 (NCTS 2,3) 8.5.10 8.5.11 8.5.12 8.5.13 2.

The Naintenance Coordinator should promptly brief the appropriate SSS on the specifics of the approved tasks.

3.

The Emergency Damage Control Summary Form (Enclosure

1) shall define the preferred and alternate ingress/egress routes where available.

4.

Use remote readout instrumentation to determine ingress/egress routes where available.

5.

If available, provide maps and/or plant maps and/or plant drawings showing such routes.

Obtain approvals indicated on the Emergency Damage Control Summary Form (Enclosure 1).

Document verbal approvals as indicated on the Emergency Damage Control Summary Form (Enclosure 1).

When necessary, review, modify, write and/or implement any procedure(s) to be used.

Ensure the tasks and special or modified procedures are

approved, reviewed, and appropriate personnel notified as indicated on the Emergency Damage Control Summary Form (Enclosur e 1).

Q0OT',:

Distribute the Emergency Damage Control Summary Form (Enclosure 1) as follows:

a.

Retain third copy of triplicate form.

Nuclear Regulatory Commission (NRC) and guality Assurance (gA) review may be deferred until after the mission.

Ensure Damage Control Team is briefed on the mission and document 'the briefing on the Emergency Damage Control Summary Form (Enclosure 1).

July 1992 Page 10 EPIP-EPP-22 Rev 00

8.5.13 8.5.14 (Cont) b.

Forward first and second copy to OSC Coordinator.

c.

Ensure the first (original) copy is returned to TSC after form is completed.

t If determined necessary through the review and approval

process, direct the Damage Control Team to carry out a dry run of the tasks.

8.5.15 8.5.16 Direct the Damage Control Team via the OSC Coordinator or Damage Control Team Coordinator.

NOTE:

Communicate with the Damage Control Teams through the OSC Damage Control Team Coordinator or OSC Coordinator (via telephone or TSC-OSC dedicated line).

Contamination Control Activities a.

When repair of damaged equipment is NOT practical or feasible during the course of the emergency or following severe plant contamination:

l.

Develop a "Contamination Control Mission" 2.

Reassess the situation using the guidance provided in Steps 8.5. 1 through 8.5. 16.

b.

Examples of such a mission are:

1.

Isolation of the offending system, subsystem, or component 2.

Manually ensuring containment isolation 3.

Isolation of a severely contaminated room 4.

Performance of radiological clean-up operations 5.

Pumping of spills to radwaste system 6.

Contingency for dealing with exceeding the capacity of the radwaste system c ~

Ensure contamination control activities are coordinated with and documented in the RANs or SSSTCs Log.

July 1992 Page 11 EP IP-EPP-22 Rev 00

8.5. 17 Installation of Special

Systems, Structures, and Components a.

b.

C.

When installation of special

systems, structures, and components is required during the course of the emergency:

1.

Develop an "Installation Mission" 2.

Follow Steps 8.5. 1 through 8.5. 16 Examples of such a mission are:

A l.

Installation of additional Radwaste Oemineralizers and Filters 2.

Construction of temporary shield walls Ensure -installation activities are documented in the Maintenance Coordinator's Log.

9.0 ACCEPTANCE CRITERIA None 10.0 R CORD REVIEW AND DISPOSITION Documentation generated through the implementation of this procedure should be forwarded:

Manager Emergency Preparedness Emergency Preparedness Department Nine Mile Point Nuclear Station July 1992 Page 12 EP IP-EPP-22 Rev 00

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NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE

~E REVISION 07 MERGENCY RESPONSE FACILITIES ACTIVATION AND OPERATION TECHNICAL SPECIFICATION REQUIRED

(

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Approved by:

N. L. Rademacher Plant Manager - Unit I Dat Approved by:

J. T.

Conway Pl t Manager - Uni Da e

THIS IS A FULL REVISION Effective Date:

03/21/97 PERIODIC REVIEW DUE DATE

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. ~IN Coversheet IST OF EFFECTIVE PAGES

~Pa e No.

'Chanche No.

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N 2

3 5

6 7

8 12 13 15 16

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17 March 1997 Page i EP IP-EPP-.13 Rev 07

I 4

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V

SECTION 1.0 2.0 PURPOSE RESPONSIBILITIES TABLE OF CONTENTS PAGE 3.0 4.0 PROCEDURE e

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3. 1 Declaring a Facility Operational 3.2 Activating the Technical Support Center (TSC) 3.3 Activating the Operations Support Center (OSC) 3.4 Activating the Emergency Operations Facility (EOF)

DEFINITIONS.

5.0 REfERENCES AND COMMITMENTS 6.0 RECORD REVIEW AND DISPOSITION

,-ATTACHMENT 1:;,'AGER EMERGENCY MESSAGE FORMAT.

ATTACHMENT 2:

ERF HABITABILITYCRITERIA AND SURVEY GUIDELINES ATTACHMENT ATTACHMENT ATTACHMENT 3:

DETERMINATION OF TSC HABITABILITYFOLLOWING A DBA 4:

TSC ACTIVATION CHECKLIST.

5:

TSC EMERGENCY VENTILATION SYSTEM ACTIVATION/DEACTIVATION.

10 ATTACHMENT 6:

OSC ACTIVATION.

ATTACHMENT 7:

EOF ACTIVATION CHECKLIST.

ATTACHMENT 8:

ACCOUNTABILITY LOG ATTACHMENT 9:

EMERGENCY VENTILATION SYSTEM OPERATION LOG ATTACHMENT 10:

NUCLEAR LEARNING CENTER EMERGENCY CHECKLIST 12 13 14 15 March 1997

'age ii EP IP-EPP-13 Rev 07

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1.0 PURPOSE

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To describe the activation and operation of the Emergency

Response

Facilities (ERFs).

NOTE:

This procedure does not address the Joint News Center (JNC).

The JNC is discussed in other procedures.

Specific responsibilities of ERO members are provided in EPIP-EPP-23, Emergency Personnel Action Procedure.

2.0 RESPONSIBILITIES

2. 1 Director Emergency Preparedness is responsible for maintaining the ERF's in a state of readiness to become operational if the need arises.

2.2 Corporate Emergency Director/Recovery Manager determines whether the EOF is operational.

2.3 EOF Administrator. is primarily responsible for the activation of the EOF.

2.4 Site Security Supervisor is responsible for allowing access to the Nuclear Learning Center during off-normal hours.

The Technical. Data Coordinator is primarily responsible for activation of the TSC.

The Operations Support Center Coordinator is primarily responsible for the activation of the OSC.

2.7 The Site Emergency Director determines whether the TSC is operational.

3.0 PROCEDURE

3. 1 Declarin a Facilit 0 erational a.

Facilities should be declared operational within 60 minutes from the time the facility activation was requested.

NOTES:

1.

The time of the latest notification method is used for Step 3. l.a.

This is normally the pager or telephone notification time.

2.

It is NOT necessary for the facility to "assume control" to declare the facility operational.

b.

The facility should be declared operational when:

1.

Sufficient personnel are available to perform necessary functions as appropriate'or the situation.

This 'should include the staffing includedvin'*each"'facilities activation checklist.

"March 1997 "Page.

1

".EP IP-;EPP-13 Rev.07

3.l.b (Cont) 2.

Equipmeht necessary to perform functions as appropriate for the situation is available.

3.

The facility has been initially determined to be habitable.

(OSC and TSC only) 3.2 3.3 ctivatin the Technical Su ort Center TSC NOTE:

The TSC is activated during an Alert, Site Area Emergency or General Emergency, or when directed by the Site Emergency Director.

3.2. 1 The Technical'ata Coordinator or designee shall activate the TSC in accordance with Attachment 4 and inform the SED when the checklist is complete.

3.2.2 The Radiological Assessment Manager shall ensure TSC habitability surveys are completed using Attachment 2 as a-,

guide.

ctiv tin the 0 erations Su ort Center OSC EMOTE:

The OSC is activated during an Alert, Site Area Emergency "or General Emergency, or when directed by the Site Emergency Director.

3.4 3.3. 1 The OSC Coordinator ot designee shall activate the OSC in accordance with Attachment 6 and inform the SED when the checklist is complete.

3.3.2 The OSC Rp Team Coordinator shall ensure OSC habitability surveys are completed using Attachment 2 as a guide.

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ctivatin the Emer enc 0 erations Facilit EOF NOTE:

The EOF is activated during an Alert, Site Area Emergency, General Emergency, or when directed by the Site Emergency Director.

The EOF Administrator or designee shall activate the EOF in accordance with Attachment 7 and inform the CED when the checklist is complete.

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Harch 3997"'age '2'P.I P.-.EPP-13 Rev 07

4. 0 DEFINITIONS

4. 1 Emergency

Response

Facility (ERF) - Include all facilities designated for activation during a declared emergency and includes:

~

Technical Support Center (TSC)

~

Operations Support Center (OSC)

~

Emergency Operations Facility (EOF) 4.2 Operational - Indicates the ERF is capable of performing its intended function.

t

5.0 REFERENCES

AND COMMITMENTS

5. 1 Licensee Documentation None 5.2 Standards Re ulations and Codes 5.2. 1

10CFR50, Appendix E,

Emergency. Planning and Preparedness for Production and Utilization Facilities (Section IV.E.9) 5.2.2 5.2.3 NUREG-0654, Rev 1, Criteria for Preparation and Evaluation of Radiological Emergency

Response

Plans and Preparedness in Support of Nuclear Power Plants NUREG-0737, Suppl.

1, Requirements for Emergency

Response

Capability (Generic Letter No. 82-33),

December 17, 1982 5.2.4 NUREG-0696,.Functional Criteria for Emergency

Response

'acilities, February 1981 5.3 Policies Pro rams and Procedures 5.3. 1 EPIP-EPP-20, Emergency Notifications 5.3.2 EPIP-EPP-14, Emergency Access Control 5.3.3 EPIP-EPP-23, Emergency Personnel Action Procedure 5.3.4 SEP, Site Emergency Plan 5.3.5 NDD-EPP, Emergency Preparedness 5.3.6, EPIP-EPP-19, Site Evacuation Procedure 5.4 "Commitments None March 1997

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Page.3 EP IP-EPP..13 Rev 07

6.0 RECORDS REVIEW AND DISPOSITION 6.1 The following records generated by this procedure shall be maintained by Records Hanagement for the Permanent Plant File in accordance with NIP-RHG-01, Records Hanagement:

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None 6.2 The following records generated by this procedure are not required for retention in the Permanent Plant File:

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None C

Harch 1997 ';

Page '4~

EP IP;EPP,,13.,

Rev 07

ATTACHMENT 1 PAGER EMERGENCY MESSAGE FORMAT The pagers are a digital type pager and do not transmit a verbal message.

The message received over a digital pager will be in the format of:

000¹¹¹ 1st ¹:

T e of Notification 1

Drill 2 Not a Drill 9 Test of Pager System 2nd ¹:

Affected Unit 1

Unit 1

2 Unit 2 3 - Both Units 4 JAF 9 - Test of pager System 3rd ¹:'e ortin Location 1 -

No Response Required 2 - Normal Emergency Duty Location 3 - Alternate Emergency Duty Location 9 Test of Pager System March;1997 Page 5.

EP IP.-EPP-13; Rev'7 ""'*

ATTACHMENT 2

'RF HABITABILITYCRITERIA AND SURVEY GUIDELINES A

~NOT :

Eating, drinking, chewing (and where allowed) smoking are permissible in the

TSC, OSC and EOF unless otherwise posted or announced.

Initial Habitabilit Determination NOTE:

The purpose of performing initial habitability is to provide a

. rapid determination of habitability to support making the facility operational within the required time.

a.

qualified and available personnel should perform an initial check of radiol'ogical conditions.

Utilize readily available instrumentation such as count rate meters, VAHPs and hand/foot monitors.

b. If facility habitability is suspect as indicated by any elevated radiation, contamination or airborne levels above expected background levels, consult.with the.-facility lead regarding actions, post "no eating, drinking; chewing"; sign. as appropriate, and ensure announcement is made.

c.

Implement habitability surveys in accordance with Step 2.

2.

Habitabilit Surve s

a ~

b.

C.

d.

Verify proper operation of the following (as applicable)

Hand and Foot monitors Friskers/GM meters P INGs Portal monitors Establish radiological control of the facility.

l.

Establish any needed

signs, ropes or step-off pads.

2.

Post "No eating, drinking, chewing" sign as needed.

Survey the facility as follows:

1.

Count rate survey for general area radiation levels and/or contamination Utilize dose rate meter as necessary Smears for contamination Air sample to check for airborne concentrations 2.

3.

If any of the following criteria are met, then continued facility habitability should be evaluated:

I.

VAMP in alarm OR general area dose rates

>7 mRem/hr (Exceeding these conditions for >30 days could cause an individual to exceed the emergency dose limit of 5 rem.)

2.

PING in alarm.

-3:

Any elevated radiation, contamination or airborne levels.

I 0 I Harch=,)997=.

Page '6 EP.I.P.;.EPP-1.3, Rev 07

'Cont)

ATTACHMENT 2 (Cont) e.

Survey adjacent areas for indications of changes in radiation or contamination levels.

f.

Perform follow-up surveys for changes in radiation and contamination levels on an on-going'asis.I,

g. If facility habitability is suspect, then consult with the facility lead regarding actions.

h.

Request facility lead, announce habitability status and any subsequent changes.

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March 1997 Page.

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EPIP-EPP-13 Rev 07

ATTACHMENT 3 DETERMINATION OF TSC HABITABILITYFOLLOWING A DBA 10 te

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ETEHMINATION OF TSC HABITABILITY FOLLOWING A DBA-LOCA

.:=:-.:

Requlremenc5 Recircularxon Filcer nnan be in operation prior oo oakingj sample.

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NOT ACCEPTABLE (NOT HABITABLE)

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March 1997age 8

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EPI P-EPP-13 Rev 07

-ATTACHMENT '4 TSC ACTIVATION CHECKLIST NOTE:

The first staff member to arrive at the TSC should initiate actions required by this checklist

'g'i>'N

't 1.

Perform the following:

NOTE:

WHEN Step l.a through 1.c are complete THEN the facility may be considered operational.

a.

Verify that the following staff (as a minimum) are available and have signed in on the ERF staffing board:

0

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Site Emergency Director

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Reactor Analyst Coordinator

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Radiological Assessment Hanager

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Maintenance Coordinator

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Technical Data Coordinator

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TSC/EOF/CR Liaison

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Security Liaison '

b.

Conduct Initial Habitability Determination in accordance with Attachment 2.

c.

Direct personnel listed in l.a (above) verify the operability of required equipment.

This may include:

~

telephones (direct dial, dedicated lines)

~

process/SPDS computer 2.

Perform the following:

NOTE:

The following need NOT be,.completed to consider. the TSC operational:

a.

Verify the EROS computer is activated in accordance with EPIP-EPP-20 within one hour of an alert or higher (Unit 2 only).

b.

Activate the TSC Emergency Ventilation in accordance with Attachment 5.

0 c.

Turn the hand/foot monitor on.

0 d.

Activate Control Room camera and verify operability.

Harch 1997 Page 9-.

~

EP IP-EPP-13 Rev 07

Activation ATTACHMENT 5 "

TSC EHERGENC VENTILATION.SYSTEH ACTIVATION DEACTIVATION 1.

Turn key operated mode select switch (KS-2) from "Normal to Accident".

2.

Verify Damper MD-1 is OPEN

[Red Light];

3.

Verify Damper MD-2 is OPEN

[Red Light].

4.

Verify Damper MOD-1 is CLOSED [Green Light].

~

Verify Fan Red Light is ON [Fan is Operational].

t%

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6.

Emergency Ventilation System is now activated.

7a.

Note that Power Source is:

0 Normal (green) 0 Emergency.(red)'.,

7b.

If Power Source is in Emergency mode:.immediately Notify Tech Data Coordinator, or S.E.D.

8.

9.

VAMP turned on and checked.

PING turned on (by a qualified individual only) and checked.

NOTE:

l. If radiological conditions in the TSC exceed 7 mR/hr (as

" measured by VAMPs or habitability surveys), notify the RAM.

I y

p 2.

Should PINGs or habitability surveys indicate that radioiodine may be a concern to facility occupants, then

. consult.EPIP-EPP-15 regarding the.need for thyroid

'roph'ylaxis.

Deactivation 1.

Turn key operated mode select switch (KS-2) from "Accident to Normal".

2.

Depress green start button.

3.

Verify Damper MD-1 is CLOSED [Green Light].

4.

Verify Damper MD-2 is CLOSED [Green Light].

5.

Verify Damper MOD-1 is OPEN

[Red Light].

6.

Verify Fan Red Light is OFF [Fan is now off].

.7.

Emergency Venti"lation System is now off.

Mar'ch':1997'age 10'."".

EPIP.'-EP,P-,'1'3'~

""'ev 07

ATTACHMENT 6 OSC ACTIVATION NOTE:

The first staff member to arrive at the OSC should initiate actions required by this checklist.

1.

Perform the following:

NOTE:

MHEN steps l.a through 1.c are complete, THEN the facility may be considered operational:

0 a.

Verify that the following staff (as a minimum) are available and have signed in on the ERF staffing board:

~

OSC Coordinator

~

Rad Protection Team Coordinator

~

Damage Control Team Coordinator 0

b.

Conduct Initial Habitability Determination in accordance with Attachment 2.

0 c.

Direct:pe'rsonnel'--listed~.in'l.a (above) verify the operability of required equipment.

This may include:

~

Telephone (direct dial, dedicated lines)

~

Personnel Accountability Computer 0

d.

Inform the OSC Coordinator of status.

2.

Perform the following:

NOTE:

The following need NOT be completed to consider the OSC operational.

I a.

Place sign on main door to Unit 1 Admin (G) building indicating that all individuals must use the employee entrance.

0 b.

Inform the TSC when survey teams are assembled and ready to be dispatched.

0 c.

Notify SED when operational.

Ha'rch 1997 Page 11 EP IP-.EPP-'13 Rev 07

ATTACHMENT 7 EOF ACTIVATION CHECKLIST NOTE: The first staff member to arrive at the EOF should initiate actions required by this checklist.

Perform the following:

NOTE:

WHEN steps l.a through 1.b are complete, THEN the facility may be considered operational:

a.

Verify that the following staff (as a minimum) are available and have signed in on the ERF staffing board:

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Corporate Emergency Director

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Offsite Dose Assessment Manager

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EOF Administrator

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Communications Coordinator

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Technical Assistant

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%l b.

Direct personnel listed. in l.a (above) verify the operability of required equipment.

This may include:

telephones (direct dial, dedicated lines) dose assessment computer process/SPDS computer radio c.

Inform the CED of status.

2.

Perform the following:

NOTE:

The following need NOT be completed to consider the EOF operational:

a.

Set up stanchions and barrier to ensure personnel enter through the radiological monitoring room.

b.

Verify the portal monitor is on.

c.

Notify the Nuclear Learning Center that an emergency has been declared and to execute the NLC Checklist in accordance with Attachment 10.

d.

Ensure a Security Force Member and a clerk staff the EOF registration desk.

e.

Instruct all non-emergency personnel to leave the EOF.

March" 1997

'='.

Page '1'2'PIP-'EPP-'13>>

Rev 07

ATTACHNENT 8 ACCOUNTABILITY LOG Page of Facil ty Locat on ate (NN/DD/YY)

Name Dept/Company Time In 'ime Out Emergency Role/

Position Destination 4'arch 1997

'" Page 13="

EPIP-EPP-13.,

Rev 07

ATTACHMENT 9' ENERGENCY VENTILATION SYSTEN OPERATION LOG INSTRUCTIONS:

1. Record date and time system started and stopped.

2. Record duration of run in units of hours.

3. Notify Respiratory Protection (Ext. 2657) when last line completed.

Date Start Time Date Stop Time Run Time (Hours

• Total Run Time from Previous Log New Total Run {Hours) =

Reviewed by Date (MM/D /YY)

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Harch=19971 tr Page 14,:

EP I'P-;EPP..13:..'ev 07

Initials Date ATTACHMENT 10 NUCLEAR LEARNING CENTER ENERGENCY CHECKLIST Date:

Sheet 1 of 3 1.

Notification of an emergency received from:

(EOF Administrator).

Message received should state the following information:

This (is/is not) a drill.'he Nine Mile Point Nuclear Station Unit (1/2) has declared a(n)

(emergency classification)

(Unusual.Event)

(Alert Situation)

(Site Area Emergency)

(General Emergency)

All emergency personnel are to report to their emergency posts.

All other personnel are to continue with normal duties and await further instructions.

Repeat information back to caller as.you hear'it.

(3-way conversation to confirm message is understood) 2.

Ensure the PA System is in operating mode:

a)

DEACTIVATE the "ALL CALL" button by pressing the button (color of button turns from green to black) b)

ACTIVATE all areas except:

-The Simulator being used for the Drill (Unit 1 - Zone 3)

(Unit 2 - Zone 4)

(Note:

Green light turns on when activated.)

c)

DEACTIVATE the "Alarm Silence Alarm" by pressing the button.

3.

Depress red button on microphone and ANNOUNCE THE FOLLOWING MESSAGE TWO TINES:

"ATTENTION ATTENTION This This (is/is not) a drill.

(is/is not) a drill.

The Nine Mile Point Nuclear Station Unit (1/2) has declared a(n)

(emergency classification)

All emergency personnel are to report to their emergency posts.

All other personnel are to continue with normal duties and await further instructions.

This This (is/is not) a drill.

(is/is not) a drill."

March 1997 Page

.1'5,

.: EP IP.-EPP-.13,.

Rev 07

Initials Date ATTACHMENT 10 (Cont)

.- Sheet 2 of 3 4.

ACTIVATE the "Alarm Silence Alarm" by pressing the button.

5.

Notification of a reclassification recei ved from:

(EOF Administrator).

Message received should state the following information:

. This

"'(is/is not) a drill.

The Nine Mile Point Nuclear Station Unit (1/2) has upgraded the emergency to a

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(Site Area Emergency or General Emergency).

All personnel are to continue with normal duties and await further instructions.

- 6.

Hake a reclassification,,announcement:-

a)

DEACTIVATE'he-'."Alarm'Silence 'Alarm".-. by pressing the button; b)

Depress red button'n microphone and ANNOUNCE THE FOLLOMING MESSAGE TWO TINES:

ATTENTION ATTENTION Thi s (is/i s not) a dri 1 1.

This (is/is not) a drill.

I The Nine Nile Point Nuclear Station Unit (1/2) has upgraded the emergency to a

(Site Area Emergency or General Emergency).

All.personnel are to continue with normal duties and await further instructions.

0 This This (is/is not) a drill.

(is/is not) a drill.

c)

ACTIVATE the "Alarm Silence Alarm" by pressing the button.

7.

Notification of Emergency Event terminated received from (EOF Administrator).

Message received should state the following information:

This'is/is not) a drill.

This (is/is not) a drill.

The Nine Mile Point Nuclear Station Unit (1/2) emergency has been terminated.

'arch'~'1997-'-'-'age J6,.

'P IP..ZPP.-..13;" ".

Rev 07

ATTACHMENT 10 (Cont)

Sheet 3 of 3 8.

Hake a termination announcement:

a)

DEACTIVATE the "Alarm Silence Alarm" by pressing the button.

b)

Oepress red button on microphone ANNOUNCE THE FOLLOWING MESSAGE TWO TIMES:

ATTENTION - ATTENTION This This (is/is not) a drill.

(is/is not) a drill.

The Nine Nile.Point Nuclear Station Unit (1/2)

'drill has.been terminated.

c)

ACTIVATE the "Alarm Silence Alarm" by pressing the button.

9.

Return PA system to normal operation.

a)

ACTIVATE the ALL CALL button, the EOF button, and the ZONE button by pressing each button.

(color of button turns from black to green)

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'Harch'997;.

Page 17.;

-'"-'PIP-EPP,-.13...

Rev 07

40 4

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NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-EPP-11 REVISION 02 HAZARDOUS MATERIAL INCIDENT RESPONSE TECHNICAL SPECIFICATION RE(UIRED

(

Approved By:

N. L. Rademacher Approved By:

J.

T. Conway Pl nt Manager - Unit 1

Pl t Manager Uni Da Da e PERIODIC REVIEW, 07/02/97, NO CHANGES PERIODIC REVIEW,07/22/96,NO CHANGE Effective Date:

PERIODIC REVIEW DUE DATE

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April 1996 Page i EPI P-EPP-11 Rev 02

SECTION 1.0 PURPOSE TABLE OF CONTENTS PAGE

2. 0 PRIMARY RESPONSIBILITIES 3.0 PROCEDURE 3.1 Chief Shift Operator 3.2 Station Shift Supervisor 3.3 Fire Chief 3.4 Cleanup Supervisor 3.5 Security 3.6 Environmental Protection 3.7 Radiation Protection 2

2 2

2 3

3 3

4 4.0 DEFINITIONS

5.0 REFERENCES

AND COMMITMENTS 6.0 RECORD REVIEW AND DISPOSITION ATTACHMENT 1:

CSO CHECKLIST HAZARDOUS MATERIAL EMERGENCY ATTACHMENT 2:

SSS CHECKLIST HAZARDOUS MATERIAL EMERGENCY 4

5 6

7 April 1996 Page ii E PIP-EPP-11 Rev 02

1.0 PURPOSE To provide direction for the notification and coordination of personnel to respond to a hazardous material (HAZHAT) incident at the Nine Nile Point Nuclear Site.

2.0 PRIMARY RESPONSIBILITIES 2.1 2.2 2.3 The Fire Chief at the affected unit is in charge of the initial response and setting up the incident command post.

Fire Brigade Personnel perform initial incident assessment and mitigate the consequences of the HAZHAT incident in accordance with established procedures.

Environmental Protection Personnel 2.4 2.3. 1 Assess the situation for reportability, making notifications to offsite regulatory agencies in accordance with the Chemical Spill Contingency Plan and Procedure.

2.3.2 Assist in obtaining outside assistance if needed.

2.3.3 Provide direction to ensure that wastes generated are in a form that is acceptable for offsite disposal, as applicable, and appropriate shipping containers are used.

Station Shift Supervisor is responsible for:

2.4. 1 Providing overall direction and control of any HAZHAT incident as it relates to the safe operation of the affected unit.

2.5 2.6 2.7 2.4.2 Determining if the Emergency Plan should be entered based on Emergency Action Levels listed in EPIP-EPP-Ol/02 (Classification of Emergency Conditions Unit 1/Unit 2)

Chief Shift Operator is responsible for making announcements to onsite personnel in accordance with Attachment 1 of this procedure.

NNPNS Occupational Safety and Health Personnel are responsible for providing assistance as requested.'upervisor In Charge of Cleanup is responsible for reviewing the HSDS information with Incident Response Personnel and supervision of the cleanup.

April 1996 Page 1

EPIP-EPP-11 Rev 02

3.0 PROCEDURE NOTE:

Entry into this procedure is expected for any hazmat incidents that may

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Pose a threat to personnel, safe plant operation or the environment.

3.1 Chief Shift 0 erator 3.2 Upon notification of a HAZMAT incident, the CSO shall complete the CSO checklist "Hazardous Material Emergency" (Attachment 1).

Station Shift Su ervisor 3.2.1 Upon notification of a HAZMAT incident by the CSO, the SSS shall:

3.3 a.

Advise the CSO of the need to elevate the level of personnel response based on the circumstances of the incident.

b.

Complete the SSS checklist "Hazardous Material Emergency" (Attachment 2).

c.

Determine the applicability of 10CFR50.72 notification

criteria, and if appropriate, notify the NRC.

Fire Chief 3.3.1 Upon hearing the announcement for a HAZMAT incident the Fire Chief shall:

3.3.2 a.

Acknowledge receipt of the announcement to the CSO.

b.

Report to the scene of the HAZMAT incident and set up a

command post.

Upon arrival at the scene the Fire Chief shall:

a.

Assess the situation for the mitigation of the HAZMAT incident.

3.3.3 b.

Direct Fire Protection personnel to obtain the necessary equipment and respond to the scene to mitigate the HAZMAT incident.

c.

Request the necessary assistance through the CSO for additional help.

The Fire Chief should turn over all cleanup responsibilities including termination assessment to the supervisor of the department which owns the process from which the spill occurred.

April 1996 Page 2

EP IP-EPP-11 Rev 02

3.4 3.3.4 Assess the HAZMAT incident as appropriate for termination and recommend the SSS terminate the incident -as appropriate.

Cleanu Su ervisor 3.5 3.4.1 3.4.2 3.4.3

~Securit The supervis'or of the department which was operating the system at the time of the spill shall:

a.

Assume cleanup responsibilities from the fire chief.

b.

Assign personnel as necessary to cleanup the spill, as directed by trained personnel (typically NMPC Fire Staff).

c.

Obtain direction on specific details from:

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Chemistry (sampling analysis and MSDS information)

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Environmental Protection (packaging and outside assistance)

The Cleanup Supervisor shall inform the SSS and the Environmental Protection Department when the spill is cleaned up.

Assess the HAZMAT incident as appropriate for termination and recommend the SSS terminate the incident as appropriate.

3.6 Provide security as needed to keep unauthorized personnel away from the spill.

Environmental Protection 3.6.1 Upon arrival at the scene or notification of a HAZMAT incident the Environmental Protection Personnel shall:

3.6.2 a.

Assess the situation for reportability and make the notifications per the appropriate environmental procedure.

b.

Provide direction to ensure that response actions minimize potential environmental impacts.

c.

Provide direction to ensure any wastes generated are in a form acceptable for offsite disposal, as applicable, and appropriate shipping containers are used.

Assist the Cleanup Supervisor by obtaining outside assistance from a qualified vendor, if needed.

April 1996 Page 3

EPIP-EPP-11 Rev 02

3.7 Radiation Protection 3.7.1 3.7.2 Upon arrival at the scene the RP Technician shall perform the necessary surveys.

Ensure compliance with the appropriate Radiation Protection Procedures.

4.0 DEFINITIONS Hazardous Materials Any element, compound or combination thereof, which is detonable, flammable, corrosive, toxic, an oxidizer, an etiologic agent, of highly reactive and which because of handling, storage processing, or packaging may have detrimental effects upon plant personnel, the public, equipment, and/or the environment.

5.0 REFERENCES

AND CONMITMENTS 5.1 References 5.1.1 6NYCRR 372 Hazardous Waste Manifest System and Related Standards for Generators, Transporters, and Facilities

5. 1.2 6NYCRR 595 Release of Hazardous Substances

5. 1.3 40 CFR 112.7 Guidelines for Preparation and Implementation of a Spill Prevention Control and Countermeasure Plan

5. 1.4 U.S.

EPA Regulations:

40 CFR302 - Designation, Reportable guantities, and Notification

5. 1.5 US EPA REG 40 CFR355 Emergency Planning and Notification

5. 1.6 29CFR1910-120 Hazardous Waste Operations and Emergency

Response

5. 1.7 NMPNS Chemical Contingency Spill Plan and Procedure

5. 1.8 NMPNS Unit 1 Oil Spill Prevention Control and Countermeasure Plan

5. 1.9 NMPNS Unit 2 Oil Spill Prevention Control and Countermeasure Plan 5.2 Commitments None April 1996 Page 4

EP IP-EPP-11 Rev 02

6.0 RECORD REVIEW AND DISPOSITION The following records generated by this procedure as the result of an actual declared emergency shall be maintained by Records Management in accordance with NIP-RMG-Ol:

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Attachment 1,

CSO Checklist Hazardous Material Emergency

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Attachment 2,

SSS Checklist Hazardous Material Emergency The following records generated by this procedure that are not the result of an actual declared emergency are not required for retention in the Permanent Plant File:

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Attachment 1,

CSO Checklist Hazardous Material Emergency

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SSS Checklist Hazardous Material Emergency April 1996 Page 5

EP IP-EPP-11 Rev 02

ATTACHMENT 1 CSO CHECKLIST HAZARDOUS MATERIAL EMERGENCY 1.0 Notified of potential HAZMATincident:

By Location(s)

Unit 1

0 Unit 2 0 Site 0

Material(s)(if Known)

Cause(s) 2.0 Notify the SSS 3.0 Make announcement as follows:

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a. Place the GAItronics in the merge mode.......................

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b. Sound the Station Alarm for 10 seconds and make the following announcement:

"ATTENTION,ATTENTION, THIS (IS/IS NOT) A DRILL. A HAZARDOUS MATERIALINCIDENTHAS BEEN REPORTED AT UNIT (1/2).

FIRE PROTECTION SHALLRESPOND TO: AREA OF INCIDE

. ALL OTHER PERSONNEL SHOULD REMAINCLEAR OF THE AREA."

Repeat the alarm and the announcement,,.......................

0 4.0 Provide the incident details to the Fire Brigade Leader................

0 5.0 Check plant parameters, initiate any required Special Operating Procedure(s) or Emergency Operating Procedure(s)..........................

CI 6.0 Obtain the location of the HAZMATincident command post from the Fire Brigade ~der........................................

0 7.0 At the direction of the SSS that the incident is terminated, make the following announcement:

a.

Place the GAItronics in merge mode.........................

0 b.

Sound the Station Alarm for 10 seconds and make the following announcement:

AITENTION, ATTENTION, THIS (IS/IS NOT) A DRILL. THE HAZARDOUS MATERIALINCIDENTAT UNIT (1/2) LOCATED AT HAS BEEN TERMINATED.

April 1996 Page 6

EP IP-EPP-11 Rev 02

ATTACHMENT 2 SSS CHECKLIST HAZARDOUS MATERIAL BlERGENCY Unit 1 o Unit 2 a Site a

1.0 Obtain relevant information concerning the Hazardous Material incident from the CSO 2.0 Determine the applicability of 10CFR50.72 notification criteria and if appropriate notify the NRC

. 0 3.0 Activate the Emergency Plan as required in accordance with EP IP-EPP-18 4.0 Initiate any required Special Operating Procedure(s) or Emergency Operating Procedure(s) 5.0 Evaluate the necessity of a Station Evacuation in accordance w]th EPIP-EPP-05 6.0 Notify the following of the HAZMAT incident and request assistance if needed:

, Normal Hours Occupational Safety and Health Radiation Protection (if inside the area)

Environmental Department Affected Unit Plant Manager Security Supervisor

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radiologically controlled 0000 Off Normal Hours Contact the groups listed under normal hours using the departmental on call list as appropriate 7.0 Upon notification that the HAZMAT incident is under control AND has been turned over for clean-up OR the incident was not considered a

HAZMAT incident, terminate the event 0

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8.0 Instruct the CSO to make the termination announcement

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April 1996 Page 7

EP IP-EPP-11 Rev 02

f 1

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP IP-EPP-10 REVISION 02 SECURITY CONTINGENCY EVENT TECHNICAL SPECIFICATION RE(UIRED Approved By:

N. L. Rademacher Plant Manager - Unit 1

ate Approved By:

J. T. Conway P

a t Manager Unit 2 Date PERIODIC REVIEW, 07/02/97, NO CHANGES Effective Date:

PERIODIC REVIEW DUE DATE

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~SC ~0 1.0 PURPOSE B

E OF CON N

S PAGE

2.0 REFERENCES

AND COHHITHENTS 3.0 DEFINITIONS

4. 0 RESPONSIBILITIES 2

3 5.0 PRECAUTIONS

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6 6.0 LIHITATIONS AND ACTIONS.

7.0 PREREQUISITES 6

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8. 1 Personnel in Affected Area(s) 8.2 Station Shift Supervisor (SSS) 8.3 Chief Shift Operator (CSO) 8.4 Security Coordinator 8.5 Security

Response

Force Leader

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9.0 ACCEPTANCE CRITERIA 10.0 RECORD REVIEW AND DISPOSITION ATTACHMENTS.

FIGURE 1:

UNIT 1 SECURITY RELATED EQUIPHENT LISTING FIGURE 2:

UNIT 2 DIVISION I TAMPERING Table A Locations FIGURE 2:

UNIT 2 DIVISION TAMPERING Table B Actions FIGURE 2:

UNIT 2 DIVISION II TAMPERING Table C Locations FIGURE 2:

UNIT 2 DIVISION I TAMPERING Table D Actions SECURITY RELATED EHERGENCY EVENT SITE SECURITY SUPERV FLOWCHART FIGURE 3:

FIGURE 4:

SECURITY CONTINGENCY EVENT (CSO CHECKLIST)

FIGURE 5:

SECURITY RELATED EMERGENCY EVENT SSS/SED FLOWCHART.

ISOR 9

9 10 11 18 26 32 37 41 42 43 February 1997 Page ii EPIP-EPP-10 Rev 02

~'i 1

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1.0 PURPOSE 1.2 1.3 This procedure describes:

Operations and Security response to Security Contingency Events (SCEs).

The methods establishing and maintaining an effective interface when SCEs are initiated or occur during a safety related emergency.

Guidance on coordination of efforts in response to SCEs.

2.0 EFERENCES AND COMMITMENTS 2.1 echnical S ecificatio s

2.2 None Standards Re ulations and Codes 2.2.1

'10CFR73.55, Requirements For Physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage 2.3 2.2.2 NUREG/CR - 4093, Safety/Safeguards Interactions During Safety-Related Emergencies At Nuclear Power Reactor Facilities Policie's Pro rams and Procedures 2.3.1 2.3.2 2.3.3 2.3.4 2.3.5'.3.6 237.

2.3.8

'i'ne Mile Point Nuclear Station Security and Safeguards Contingency Plan EPIP-EPP-13, Emergency

Response

Facilities Activation and Operation EPIP-EPP-01, Classification of Emergency Conditions, Unit 1

EPIP-EPP-02, Classification of Emergency Conditions, Unit 2 EPIP-EPP-23, Emergency Personnel Action Procedure EPIP-EPP-21, Radiation Emergencies EPIP-EPP-20, Emergency Notifications EPIP-EPP-25, Emergency Reclassification and Recovery 2.3.9 '-SAP-11.0, Basic Emergency Plan Duties 2.3. 10 S-SEC-8. 1, Security Alert and Heightened Awareness February 1997 Page 1

EPIP-EPP-10 Rev 02

2.4 Commitments-Sequence Number Commitment Number Descri tion None 3.0 DEFINITIONS 3.1 3.2 Securit Co tin enc Event A deliberate.act or perceived threat of an act which could imperil the station and endanger the public health and safety by exposure to radiation.

Securit Com romise 3.3 Security related event which has.been determined to be a Security Alert in accordance with Nuclear Security Department procedures.

Hei htened Aware ess A state of increased security based on receipt of reliable information which indicates that events occur ring on a worldwide, national, or regional scale could possibly impact the security of Nine Mile Point Nuclear Station.

3.4 Securit A ert Level I 3.5 A state of preparedness and initial response in reaction to receipt of information that is believed to indicate existence of a credible security-related threat.

The major activities on-going at this level include notification of'appropriate site personnel and off-site

agencies, information gathering, briefing of Response Force personnel, preparation of response strategies and perhaps, deployment of response personnel to functions which support security readiness to meet the potential realization of the threat.

Securit Alert evel The declaration of a Level II Alert is based upon observation of physical evidence or activity which substantiates the existence of a credible security-related threat.

The determination may be arrived at gradually through activities on-going during Level I, or may be made immediately upon recognition of activities or evidence which are overtly security-related (ie., discovery of a suspicious

device,

'observation of sabotage in progress, etc.).

In either case, activities on-going at this level involve activation of the Response Force and implementation of response procedures and strategies in order to mitigate potential consequences of the threat.

February 1997 Page 2

EP IP-EPP-10 Rev 02

3.6 rotectin E ui ment This may'nclude stationing of security or other personnel to ensure the'continued operability of equipment.

4.0 RESPONSIBIL TIES 4.1 Cor or te mer e c 0'rector ecover Hang er CED RH On arrival at the station:

4.1.1 4.1.2 Assumes overall authority for direction and control of emergency.

response and recovery.

Primarily directs:

a.,

Public and press relations b.

Interaction with federal, state, and local

~ organizations c.

Logistics d.

Off-site emergency measures

• e.

Outside assistance, 4.2 Site Emer enc Director SED 4.2.1 Evaluates plant conditions and declares emergency conditions.

4.2.2 4.2.3 4.2.4.

4.2.5 4'.2;6 Implements the Nine Mile Point Nuclear Station (NHPNS) Site Emergency Plan.

Ensures appropriate personnel are dispatched into affected area(s) to:

a.

Evaluate/investigate plant conditions b.

Hake observations and verify the necessary equipment/system(s) are available c.

Ensure power supplies are available and properly configured Directs emergency response organization.

Assumes overall authority for control of the emergency situation until relieved by.the Corporate Emergency Director/Recovery Manager.

Directs suspension of safeguard measures such as vehicle/personnel searches, if warranted by response to the Security Contingency Event (SCE).

February 1997.

Page 3

EP IP-EPP-10 Rev 02

4.3 4.3.1 Station Shift Su ervisor SSS Assumes the role of Site Emergency Director (SED) until properly relieved.in accordance with EPIP-EPP-18, Activation and Direction of the Emergency Plan.

4.3.2 4.3.3 4.3.4 4.3.5 4.3.6 4,3.7 Initiates the classification of emergency conditions based on available information and in accordance with EPIP-EPP-01 and EPIP-EPP-02.

r Provides direction to Chief Shift Operator (CSO) for emergency announcements.'ssigns Operations personnel to Security

Response

Forces as necessary.

Initiates any.Operating, Special Operating or Emergency Operating Procedures required.

Authorizes suspension of Security Safeguards when appr'opriate in accordance with 10CFR50.54x.

Ensures the.NRC is notified when Security Safeguards are suspended in accordance with 10CFR50.54y.

4.4 C

Shift 0 erator CSO 4.4.1 Ident'ifies alarms and annunciators

received, broadcasts appropr'iate emergency announcements, and when directed, initiates a station evacuation.

4.4.2 Notifies Nuclear Security of suspicious or observed events which could be security related.

4.5 Securit Site Su ervisor General Su ervisor-Securit 0 erations or Nuclear Securit Chief 4.5. 1 Assumes the role of Security Coordinator, providing command and direction to the Nuclear Security Department response organization.

4.5.2 4.5.3 4.5.4 4.5.5 Hay select and declare the appropriate Security Alert Level, and notifies the. SSS and Nuclear Security Department management personnel.

Ensures appropriate security contingency procedures are implemented.

Coordinates continued response efforts with the SSS or the SED during an SCE.

Contacts off-site law enforcement agencies for assistance and coordinates on-site activities.

February 1997 Page 4

EPIP-EPP-10 Rev 02

4.5.6 4.5.7 Increases or reduces the access controls provided by the security system, and takes necessary compensatory actions.

Ensures a Security Force Hember is sent to the affected Control Room to provide communications between the Control Room staff and Nuclear Security.

4.6 Securit U it S ervisor or CAS 0 e ator 4.6.1 Assumes the role of Response Force Leader, controlling and coordinating the response activities of Security Response Forces at one or both units.

4.6.2 4.6.3 4.6.4 Hay select and declare the appropriate Security Alert Level if first authority informed of a Security Contingency Event requiring immediate response.

Activates Security Response Force.

Ensures Security personnel respond to the affected plant areas.

4.6.5 4.6.6 4.6.7 4.6.8 Continually updates Security Coordinator of actions taken in response to the emergency and of information gathered during the response.

Implements further contingency response measures directed by the Security Coordinator.

As applicable, ensures non-security personnel attached to Security

Response

Forces are briefed on safety concerns.

If applicable notifies the Security Coordinator of the need for additional personnel to respond to the emergency including the need for off-site law enforcement assistance.

4.7 4.8 Licensed Operators shall. participate as members of the Security

Response

Forces as requested.

Securit Force Hember 4.8.1 4.8.2 4.8.3 F

t 4.8.4 As members of the Security

Response

Force, respond to SCEs in accordance with direction'rom the Response Force Leader.

Take appropriate safety and. radiological precautions in response to equipment threats/sabotage.

In consultation with the Licensed Operator, identify abnormal equipment/system configurations and/or suspicious materials, personnel, etc.

Provide security for non-Security personnel, and secure areas as directed.

February 1997 Page 5

EPIP-EPP-10 Rev 02

4.9 0 erations Su ort Center OSC Coordinator 4.10 4.9.1 On activation of the Operations Support Center (OSC),

reports to the OSC and contacts the SED.

4.9.2 Assembles required personnel, equipment, and supplies to effec'tively respond to the SCE.

4.9.3 Implements this procedure.

4.9.4 Performs actions required by appropriate procedures including EPIP-EPP-23, Emergency Personnel Action Procedure.

4.9.5 Upon request, provides specialized personnel to respond to plant damage or other situations, as necessary.

Station Personnel';10.)

Upon notification of an

SCE, obey directions given by emergency announcements.

4.10.2 4.10.3 Evacuate local areas as requested.

Maintaih vigilance and report to the Control Room suspicious personnel, activities, or materials.

5.0

~PR AU lONB None 6.0 LIMITATIONS AND ACT'IONS 6.1 6.2 6.3 6.4 Security Contingency Events (SCEs) include, but are not limited to acts of sabotage, equipment tampering',

or threats.

To ensure appropriate response to an SCE:

6.2. 1 A'oncerted effort is required to coordinate actions among all station departments.

6.2.2 Iri particular, the Nuclear.Security and Operations Departments coordinate SCE response.

This procedure does not alter or otherwise change personnel actions dictated in station departmental procedures.

The SSS or SED directs and controls emergency activities at the management level between the Operations and Nuclear Security Departments.

'Normal chain of command within each department is maintained during the response.

February 1997 Page 6

EPIP-EPP-10 Rev 02

I.U

~PRERE UIRIIRE None 8.0 PROCEDURE

8. 1 Personnel

'n Affected rea s

8.1.1 Evacuate as indicated by emergency announcements or as directed by Nuclear Security personnel.

Warn others to exit the area and report as stated in the announcement.

8.1.2 Note any abnormal conditions upon leaving the area.

8.1.3 Do not enter or re-enter an area where a Security Contingency Event (SCE) is in progress unless it is approved by the Station Shift Supervisor (SSS), Site Emergency Director (SED), or Nuclear Security.

NOTE:

When local evacuation is not urgent, radiation protection personnel will instruct personnel working in protective clothing to change into personal clothing in the normal manner when leaving the work area.

8.2

8. 1.4 When wearing protective clothing in an area where a local evacuation is taking place:

a.

Remove the outer set of protective clothing at the job location when wearing a double set.

b.

Remove rubber shoe covering and rubber gloves at the

.job location when wearing one set.

c.

Proceed directly to the nearest step off pad/access control station wearing one set of protective clothing.

d.

Monitor for contamination.

. e.

Change into clean clothing.

Station Shift Su ervisor SSS 8.2.1

=

- Upon notifi'cation of an

SCE, implement appropriate actions in accordance with the Security Related Emergency Event SSS/SED Flowchart (Figure 5).

8.2.2 When Operations personnel are first to discover sabotage, contact Security Supervision to discuss the details of the SCE.

February 1997 Page 7

EPIP-EPP-10 Rev 02

8.2.3 In conjunction with the Security Coordinator, identify station equipment and systems affected by the security threat.

'a ~

If equipment or systems are listed on the Unit 1

Security Related Equipment Listing (Figure 1) or the Division Tampering (Figure 2) determine priority of security response (for example, equipment necessary for plant shutdown should be searched and secured before equipment or systems not required for plant shutdown).

b.

.Use Figure I for Unit 1 and Figure 2 for Unit 2 as noted below:

I.

~fi ure I: If the SCE involves one or more of the components under the Affected Systems/Equipment column; consider investigating the components listed under the Unaffected Systems/Equipment column; 2.

~F're If,the SCE involves a component listed on Table A, consider investigating the components enlisted on Table B.

3.

Ficiure 2: If the SCE involves a component listed on Table C, consider investigating the components listed on Table D.

8.3 Chief Shift 0 erator CSO 8.3.1 Complete the Security Contingency Event (CSO Checklist)

(Figure 4);

8.3.2 Notify SSS of details of SCE,or of any suspicious plant alarms.

8.3.3 8.3.4 8.3. 5 8.3s6 8.3.7 8.3.8 Ensure plant operating parameters are normal.

Ensure the reactor is in safe operating condition.

Identify possible SCEs {for example, telephoned threats, possible

sabotage, etc.).

P Notify Nuclear Security of security related emergency conditions and request appropriate response.

Implement required Operating, Special Operating or Emergency Operating Procedures.

Mhen local evacuation is required and direction received from the

SSS, make the appropriate emergency announcement in accordance with Secur'ity Contingency Event (CSO Checklist)

(Figure 4).

February 1997 Page 8

EPI P-EPP-10 Rev 02

8.4 8.3.9 Repeat emergency alarm and announcement.

Site Securit S

erviso 8.4.1 8.4.2 Upon notification of an

SCE, implement actions in accordance with Nuclear Security Contingency procedures and Figure 3 Security Related Event Site Security Supervisor Flowchart.

Contact the affected unit SSS to discuss the details of the SCE.

8.4.3 When appropriate, declare a Security Alert Level 1 or Security Alert Level 2.

Notify the SSS or SED immediately upon declaration.

8.5 ecurit Res onse Force eader 8.5.1 8.5.2 Upon notification of an

SCE, implement appropriate actions in accordance with Security Contingency Procedures and this procedure.

Coordinate with and integrate non-Security personnel into

Response

Force as directed by the Security Coordinator.

9.0 ACCEPTANCE CRITERIA None 10.0 CORD REVIEW AND DI POSITIO The following records generated by this procedure as the result of an actual declared emergency shall be maintained by Records management for the Permanent Plant File in accordance with NIP-RHG-Ol:

~

Figure 4, Securing Contingency Event (CSO Checklist)

The following records generated by this procedure that are not the result of an actual declared emergency are not required for retention in the Permanent Plant File:

~

Figure 4, Security Contingency Event (CSO Checklist)

February 1997 Page 9

EPIP-EPP-10 Rev 02

C H NTS Figure 1:

Figure 2:

Figure 3:

Figure 4:

Figure 5:

Unit 1 Security Related Equipment Listing Unit 2 Division Tampering Security Related Emergency Event, Site Security Supervisor Flowchart Security Contingency Event (CSO Checklist)

Security Related

Event, SSS/SED Flowchart February 1997 Page 10 EP IP-EPP-10 Rev 02

FIGURE 1:

UNIT S CURI Y

AT D E

U PHENT LISTING Sheet 1 of 7 If a Security Event or suspected Security Event occurs which involves one or more of the fo11owing:

Affected Area Affected Systems/Equipment Then:

You shou1d investigate and consider protecting one or more of the fo11owing:

Unaffected Systems/

Equipment, 1.

Reactivity Control A. Control Rod Drive System Pump 11 Pump 12 B. Liquid Poison System-Pump ll

- Pump 12 A. Liquid Poison System Pump 11 Pump 12 B. Control Rod Drive System

- Pump ll Pump 12 2.

Decay Heat A. Condenser-Condensate-Feedwater Remova1 to Hot Shutdown B. Emergency Condensers - Loop 11 Loop 12 C. Auto Depressurization A. Emergency Condensers

- Loop ll Loop 12 Auto Depressurization B. Condenser/Condensate and Feedwater/Auto Depressurization C. Condenser/Condensate and Feedwater Emergency Condensers Loop ll Loop 12 February 1997 Page 11 EP IP-EPP-10 Rev 02

FIGURE 1:

UNIT 1

S CUR V R TED UIPHENT LISTING Sheet 2 of~

If a Security Event or suspected Security Event occurs which invo1ves one or more of the following:

Affected Area Affected Systems/Equipment Then:

You should investigate and consider protecting one or more of the following:

Unaffected Systems/

Equipment 3.

Main Coolant A. Condensate/Feedwater Inventory Control A. Core Spray Control Rod System Containment Water Loop ll Loop 12 Drive Pump 11 Pump 12 Spray Raw Pump ill Pump 122 B. Contro1 Rod Drive System Pump ll

- Pump 12 B. Condensate/Feedwater Core Spray Loop ll Loop 12 Containment Spray Raw Water Pump 'ill Pump 122 C. Core Spray Loop II Loop 12 C. Condensate/Feedwater Control Rod Drive System Pump ll Pump 12 Containment Spray Raw Mater Pump ill Pump 122 D. Containment Spray Raw Mater Pump 111

- Pump 122 D. Condensate/Feedwater Contro1 Rod Drive System Pump ll Pump 12 Core Spray

- Loop ll

- Loop 12 February 1997 Page 12 EPIP-EPP-10 Rev 02

FIGURE 1:

UNIT 1 SECURITY RELAT D E UIPMENT LIS ING Sheet 3 of 7 Affected Area If a Security Event or suspected Security Event occurs which involves one or more of the following:

Affected Systems/Equipment Then:

You may wish to investigate and consider protecting one or more of the following:

Unaffected Systems/

Equipment 4.

Decay Heat A.

. Emergency Condensers Loop ll Removal To Loop 12 Cold Shutdown A.

Auto Oepressurization System Core Spray

- Loop ll

- Loop 12 Containment Spray-Loop ll

- Loop 12

-or-B.

Shutdown Cooling

- Loop ll Loop 12 Loop 13 Auto Depressurization System Core Spray

- Loop ll

- Loop 12 Containment Spray Loop ll Loop 12 Containment Spray Raw Water

- Loop ll

- Loop 12 Containment Spray Raw Water

- Loop 11 Loop 12

-or-B.

Emergency Condenser Loop ll Loop 12 February 1997 Page 13 EP IP-EPP-IO.

Rev 02

FIGURE 1:

UNIT S CURIT UIP NT L ST G

Sheet 4 of Affected Area If a Security Event or suspected Security Event occurs which involves one or more of the following:

Affected Systems/Equipment Then:

You may wish to investigate and consider protecting one or more of the following:

Unaffected Systems/

Equipment

-or-C.

Reactor Building Closed Loop Cooling

- Pump ll Pump 12

- Pump 13

-or-D.

Emergency Service Water Pump ll Pump 12

-or-C.

Auto Depressurization System Containment Spray Raw Water to Core Spray Loop 12 Containment Spray Loop ll Loop 12 Containment Spray Raw Mater Loop ll Loop 12

-or-D.

Emergency Condenser Loop Il Loop 12

+

Auto Depressurization System Fire Water Via Feedwater Tie-In Containment Spray Loop ll Loop 12

+

Containment Spray Raw Water Loop ll Loop 12 February 1997 Page 14 EPIP-EPP-10 Rev 02

~

~

FIGURE 1:

UNIT 1

S CUR TY R LATED UIPMENT LISTING Sheet 5 of 7 Affected Area If a Security Event or suspected Security Event occurs which involves one or more of the fo11owing:

Affected Systems/Equipment Then:

You may wish to investigate.and consider protecting one or more of the following:

Unaffected Systems/

Equipment

-or-E.

Core Spray Loop ll Loop 12

-or-E.

Emergency Condenser

- Loop II

- Loop 12 Shutdown Cooling System

- Loop ll

- Loop 12 Loop 13 Reactor Building Closed Loop Cooling Pump ll

- Pump 12

- Pump 13 Emergency Service Water Pump ll Pump 12

-or-F.

Containment Spray

- Loop ll

- Loop 12 F.

Cont.

Spray RW - Pump ill Pump 112

-or-Containment Spray Raw Mater Pump 112 Pump 121

-or-G.

Containment Spray Raw Water

- Loop ill Loop 122

-or-G.

None February 1997 Page 15 EP IP-EPP-10 Rev 02

FIGURE 1:

U S

CUR TY S

NG Sheet 6 of Affected Area If a Security Event or suspected Security Event occurs which involves one or more of the following:

Affected Systems/Equipment Then:

You may wish to investigate and consider protecting one or more of the following:

Unaffected Systems/

Equipment B.

C.

Emergency Condenser Loop 11

- Loop 12 Auto Depressurization System 5.

Depressuri-A.

Hain Condenser zation A.

B.

C.

Emergency Condenser Loop 11 Loop 12 Auto Depressurization System Hain Condenser Auto Depressurization System Hain Condenser Emergency Condenser Loop ll Loop 12 6.

Emergency Diesel Generators and/or Power Boards 102 A,

Emergency Diesel Generator 102 and/or Power Board 102.

A.

Emergency Diesel Generator

103, Power Board 103 and associated loads; alternate feeder breaker R.

B.

Emergency Diesel Generator 103 and/

or Power Board 103.

B.

Emergency Diesel Generator 102; Power Board 102 and associated loads; alternate feeder breaker R-1012 and

))5KV switchyard.

7.

Fire Detection Power Board 178 Loss Zone T28 and/or of Normal Supply.

T2D; D4166; Breakers R-1031 or R-)053.

Power Board 168; Breakers R-)021, R-)043, R-1042, R-1041; Fire Zones T2B and T2D Diesel'enerator 102

'nd Power Board 102.

February 1997 Page 16 EPIP-EPP-10 Rev 02

FIGURE 1:

UNIT 1 SECURITY RELATED E UIPHENT LISTING Sheet 7 of 7 Affected Area If a Security Event or suspected Security Event occurs which involves one or more of the following:

Affected Systems/Equipment Then:

You may wish to investigate and consider protecting one or more of the following:

Unaffected Systems/

Equipment

8. Fire Detection Power Board 16B Loss of Zone T2A and/or Normal Supply.

T2D; D4156; Breakers R-1021 or R-1043.

Power Board 178; Breakers R-1031, R-1053, R-1052, R-1051; Fire Zones T2B and T2D; Diesel Generator 103 and Power Board 103.

9. Hain Control Room

-or-Aux. Control Room

-or-Cable Spreading Room Fire, Explosion, or other forms of damage may cause loss of major plant equipment,

systems, and/or indications.

Remote Shutdown Panels ll and 12; Emergency Diesel Generators 102 103 10.

D.

C. Control A. Battery 11 and/or Battery Board and Instru-ll ment Power.

B. Battery 12 and/or Battery Board 12.

A. Battery 12 and Battery Board 12, and Battery Charger 12.

B. Battery ll and Battery Board 11, and Battery Charger 11.

February 1997 Page 17 EPIP-EPP-10 Rev 02

FIGURE 2:

UN T S 0 Table A Locations P

NG Sheet 1 of 8 The following is an alphabetized list of components and areas of concern.

The response is indicated in a specific footnote and/or Table B.

DS T

OG Two Nitrogen tanks (2IAS*TK4, TK5) and the associated instruments, pipes and valves on the Fl El 289'f the Reactor Building AUX IAR AY 0

l. @001 a.

Div I Motor Control Center (2NHS*MCC102) b.

Div I DC Switch gear (2DMS*MCCAl) c.

Div I (Green) conduit in this area d.

RCIC Suction Valve from the CST (2ICS*MOV129)~

~

2. ~Fi a.

Service Mater Valves (2SMP*MOV19A, 19B) b.

Div I (Green)

Cable Trays

3. ~F1 a.

RHR A Heat Exchanger Room b.

Div I (Green)

Cable Trays

4. 175'l El a.

RHR A Pump Room 8

RHR A Heat Exchanger Room BATTERY 1.

Div I Battery (2BYS*BAT2A), in Div I SWGR RM Fl El 261'ontrol Building February 1997 Page 18 EPI P-EPP-10 Rev 02

FIGURE 2'NIT 2 D VIS 0 I

AHPERING Table A Locations Sheet 2 of 8 CAB CHASES TRAYS Div I (Green)

Cable

Chases, West Side of Control Building at Elevations:

214', 237', 261', 289',

306'.

Div I (Green)

Cable tray's from Div I Diesel, Control Building Fl El 244'.

Div I (Green)

Cable trays, Center West of Control Building Fl El 237',

5.

6.

Div I (Green)

Cable trays Reactor Building North side at Elevations:

289 261

~ 240

~

215

~

196 Div I (Green)

Cable trays

& Conduit Reactor Building North at Elevations:

289', 261', 240', 215',

196'iv (Green)

Cable trays

& Conduit North Aux Bays at Elevations:

240',

215',

196'HARGER (Battery Chargers) l.

-2BYS*CHGR2A2 or 2BYS*CHGR2Al, Div I SWGR Room CONTROL BUILDING Div I 289',

2.

Div I (Green)

Cable chases West side Elevations:

214', 237', 261',

306'Green), Cables from Div I Diesel, Fl El 244'.

Div I (Green)

Cable

Room, West Center Fl El 237'.

Div I Switch Gear Room Fl El 261'.

Div I Battery Room Fl El 261'Inside Div I SWGR Room) 6.

Div I Remote Shutdown System

Room, Fl El 261'.

Any Div I Panel or termination Cabinet on the West Side in the Relay

Room, Fl El 289'ebruary 1997 Page 19 EPIP-EPP-10 Rev 02

CON 0

0 FIGURE 2:

UN T S 0 TAMP RING Table A Locations E

Sheet 3 of 8 2.

North or South banks of CRD Hydraulic Control Units Manual Control Station, Reactor Building Fl El 261'orth Side 3.

Instrument racks:

2CES*RAK101 or RAK102, Reactor Building Fl El 261'orth 4.

Pumps:.

2RDS-P1A or PlB, Reactor Building Fl El 215', North 5.

Piping or Instr.

Rack (2CES-RAK103) Reactor Building Fl El 215', North

~EIE I

IIEEAT Div I Diesel Room to include:

diesel, fuel supply, air compressor, air tanks, fuel transfer, day tank, control panels ECTRIC TUNNE S I.

Div I (Green),

140 Electrical Tunnel or Trays, Fl El 215'.

Div I (Green),

35 Electrical Tunnel or Trays, Fl El 215'.

Div I (Green),

315 Electrical Tunnel or Trays, Fl El 215'STRUMENT R

CKS 1.

Div I (RHS A) Instruments on Instrument Rack 2CES"RAK018 (2H22*P018)

Fl El 175'f Reactor Building 2.

RCIC Instrument Racks:

H22eP0177 (RCIC Sect A) or H22*P029 (2CES*RAK029) Fl El 175'f Reactor Building '

3.

Div I Reactor Pressure and Level Instrument Racks (H22*P004) on Fl El 261'f Reactor Building (Near the North bank of Hydraulic Control Units) 4.

ADS Instrument Rack on Fl El 289'f the Reactor Building, near the two Nitrogen Tanks, on the North Side February 1997 Page 20 EP IP-EPP-10 Rev 02

FIGURE 2:

UNIT 2 D

IS 0 TAMP RING Table A Locations TO CO 0

C T RS Sheet 4 of 8 1.

Fl El 261'f the Reactor Building, North Side, 2NHS-MCC011 2.

Fl El 240'f the North Auxiliary Bay, 2EHS*MCC102 3.

Fl El 261'f the Control Building (Div I SWGR Room),

2EHS*MCC103 I

4.

Fl El 261'f the Div I Service Water Pump Bay Room, 2EHS*MCC101

~ITROGEN 1.

2GSN-TK2, Fl El.261'f the Reactor Building Track Bay 2.

Two ADS Tanks (2IAS*TK4, or TK5), valve, piping, instruments on Fl El 239'f the Reactor Building 3.

Safety Relief Valves or piping on Fl El 289'f the Reactor Building PIPE CHASES l.

Reactor Building exposed Pipe Chase on the North Side, Outside Wall, Fl El 289'nd below 2.

Reactor Building enclosed vertical pipe chase with RCIC/RHS Steam Piping RCIC

(

RCIC Room, Fl El 175'f the Reactor Building 2.

RCIC Valve Rooms, Fl El 196'f the Reactor Building 3.

RCIC Steam Line Outboard Isolation Valve (2ICS*MOV121), Fl El 261'f the Reactor Building (in enclosed Pipe Chase) 4.

RCIC Injection Valves (2ICS*MOV126 5 AOV156), Fl El 289'f the Reactor Building 5.

RCIC Control Boxes, Fl El 240'f the South Aux Bay February 1997 Page 21 E PIP-EPP-10 Rev 02

CTOR U

D G

1.

~15'IGURE 2:

U Table A Locations P

G Sheet 5 of 8 a.

Div I Instrument Rack (H22-POIS) b.

RCIC Instrument Racks H22-P017, RCIC Sect A, or H22-P029, RCIC Pnl B'

c.

RCIC Equipment, Room' d.

Service Water and Residual Heat Removal Horizontal Piping Runs on the North Side 2.

Fl El 196'.

Div I Valve Pits

{above and below grade) b.

Both RCIC Valve Rooms' c.

Vertical Pipe Chase, North Side - Outside Wall d.

Service Water Pipes and Valves e.

Horizontal and Vertical Green Cable Trays and Conduit f.

Horizontal Piping Runs on the North Side (include 2RHS*NOV3A and piping) g.

Green Vertical Cable Chase on the North Outside Wall 3.

Fl El 215'.

Green Horizontal 8 Vertical Electrical Cable Trays b.

Control Rod Drive Pumps or Instrument Racks (2CES*RAK103)'

c.

Vertical Pipe Chase North Side Outside Wall d.

Green Vertical Cable Chase on the North Outside Wall 4.

~Fi 11 a.

Vertical Pipe Chase, North Side, Outside Wall b.

Vertical Green Cable Chase, North Side, Outside Wall c.

Horizontal and Vertical Green Cable Trays February 1997 Page 22 EPIP-EPP-I 0 Rev 02

4.

ELELEE

'IGURE 2:

UN T D V SION TAMPERING Table A Locations Sheet 6 of 8 d.

RHR Shutdown Cooling from Recirc Loop A, Outboard Isolation Valve 2RHS*MOV113

~ 'in a Locked Room) e.

RHR Shutdown Cooling return to Recirculation Loop A, 2RHS*MOV40A 6.

~F1 1

6 a.

Div I Vessel Level and Press Instrument Racks (H22-P004) b.

Nitrogen tank 2GSN-TK2, South Side Track Bay c.

RCIC/RHR Steam Line Outboard Isolation Valve (2ICS*MOV121) enclosed Pipe Chase, East Side '

d.

2NHS-MCC011, North Side e.

CRD Hydraulic Units, Both Banks (North and South Sides) f.

CRD Hydraulic Manual Control Station, North Side g.

CRD Instrument

Racks, 2CES*RAK102, 2CES*RAK101, North Side h.

Div I (green)

Cable Chase i.

Div I (green) Horizontal Cable Trays j.

Vertical pipe chase 'on the North Side 6.

Fl El 289'.

Two ADS Nz Tanks (2IAS*TK4, 2IAS*TK5), pipes, valves '

b.

RCIC Injection Valves '

(2ICS*MOV126 and AOV156) c.

RHS A Injection Valve (2RHS*MOV24A) or piping d.

Stand by Liquid A Pump, tanks or valves, Squib valves, piping, containment penetration RELAY ROOM (Fl El 289'f Control Building) 1.

Any Div I Panel 2.

Div I Cable Chase (West Side) 3.

Div I Termination Cabinets (West Side)

February 1997 Page 23 EP IP-EPP-10 Rev 02

FIGURE 2:

UNIT 2 D VIS ON I TAMPERING Table A Locations

~ll NNT NIINTE IIN

( f1 El Ntl' t

1 I

N till Nt 1.

Div I Remote Shutdown Panel Sheet 7 of 8 RESIDUA HEAT R MOVA 1.

Heat Exchanger A Room (Fl El 175'nd Fl El 196'f North Aux Bay)

Pump A Room (Fl El 175'f Aux Bay North) 3.

RHR A Instrument

Rack, 2CES*RAK018 (2H22*P018)

(Fl El 175'f Reactor Building, North) 4.

Shutdown Cooling from Reactor Outboard Isolation Valve Reactor Building Fl El 240'ast in an enclosed room (2RHS*MOV113) '

5.

Shutdown Cooling Return to Recirculation Loop A (2RHS*MOV40A), Reactor Building Fl El 240'orth in enclosed room 6.

RHS 'A. Injection Valve general

area, Fl El 289'f the Reactor Building, Northeast Side SERVICE WATER 1.

Service Water Pumps:

A, C, E and piping or valves in SWP Pump Room 2.

Any Div I Service Water Pipe or Valve: located in the Reactor Building STANDBY LI UID SYSTEM 1.

Fl El 289'eactor Building (Storage Tank, valves, Pump A or piping)

SWITCH GEAR N

~

Div I AC Switch Gear (2ENS*SWG103)

Fl El 261'ontrol Building 2.

Div I DC Switch Gear (2BYS*SWG002A) Fl El 261'ontrol Building 3.

2NHS-MCC011, Fl El 261'f Reactor Building (North Side) 5.

2EHS*MCC101, Div I Service Water Pump Room approximately Fl El 260'EHS*MCC102, Aux Bay North, Fl El 240'.

2EHS*MCC103, Div I Switch Gear Room, Control Building F1 El 261'ebruary 1997 Page 24 EP IP-EPP-10 Rev 02

TANKS FIGURE 2:

U 0

Table A Locations P

G Sheet 8 of 8 1.

ADS Nitrogen Tanks (2IAS*TK4 or 2IAS*TK5), Fl El 289'eactor Building'.

Nitrogen Tanks (2GSN-TK2) in Reactor Building Track Bay, Fl El 261'~

Standby Liquid Control Tank on Fl El 289'f Reactor Building TUNNELS ELECTRICAL l.

140'lectrical Tunnel (Div I, green),

Fl El 215'.

35 Electrical Tunnel (Div I, green),

Fl El 215'.

315 Electrical Tunnel (Div I, green),

Fl El 215'OTES:

1.

2.

3.

4.

5.

6.

.Consideration should be given to first searching and

.securing the NMP2 Switchyard, the Scriba Switchyard, the Div I, II, SWGR and Battery Rooms, and the Normal Switchgear Rooms after any Tampering with the Divisional Diesel Generators or Service Water Supply to these diesels.

Consideration should be given to first searching and securing the Main Steam Line Tunnels, the Turbine Bypass Valves, the Main Condenser, the Off-Gas System, UPS3A and 3B, Nz Tank 2, 2IAS-TK3 (261'eactor Building North) after any tampering with the Nitrogen System which results in complete loss of Normal and ADS Nitrogen.

Consideration should be given to first searching and securing the Standby Liquid Control:

tanks, pumps and valves on the Fl El 289'f the Reactor Building for any tampering with the CRD Hydraulic Control Units (Reactor Building Fl El 261'), the CRD pumps (Reactor Building Fl El 240') or the CRD Manual Control Station (RB Fl El 261').

Consideration should be given to first searching and securing the Nitrogen tank (2GSN-TK2) in the Reactor Building Track Bay (Fl El 261'),

ADS Supply Tanks (2IAS*TK4, 2IAS*TK5), piping and valves on Reactor Building Fl El 289'or any tampering with the shutdown cooling outboard isolation valve from the reactor (2RHS*MOV113).

This list only addresses components required.for safe shutdown.

Other damaged or tampered components might not require as in depth a response.

HPCS (Div III Diesel, Switch Gear, Cable Trays, Pump

Room, Instrumentation) only needs to be protected in the event that RCIC is compromised.

February 1997 Page 25 EPIP-EPP-10 Rev 02

FIGURE 2:

UNI DIV S ON AHPERING Table B Actions Sheet 1 of 6 This Table B is a listing of Division II equipment and is used in response to Division I Tampering.

Consider searching and securing all components and areas in this list.

This table is an adjunct to Table. A.

a So th 175'.

RHR B Heat Exchanger Room 2.

RHR B Pump Room Reactor Buildin South 180' 360'l El 175'.

General area to include:

a.

Instrument plates with Service Mater

{SWP) discharge header flow and RHR PIB Suet.

Press 2RHS*PT3B.

b.

RHR B Instrument Rack 2CES*RAK021 (2H22*P021) 2.

Div II (Yellow) Conduit 3.

RHR 5 SWP piping runs on the south and east side 4.

5.

6.

7.

Aux Ba HPCS pump room' HPCS Instrument

Rack, 2CES*RAK024 (2H22*P024)'

HPCS Suet.

Valve from CST, 2CSH*MOV101' Div III (purple) conduit '

South Fl l

96'.

RHR B Heat Exchanger Room

. 2.

Div II {Yellow) vertical cable trays Reactor Buildin South 180'-360'l El 196'.

General Area South a.

RHR piping to include 2RHS*HOV30B b.

CSH piping '"

February 1997 Page 26 EPIP-EPP-10 Rev 02

FIGURE 2'N DIVIS ON TAMPER NG Table B Actions Sheet 2 of 6 Reactor B ildin So th 180 -360' 96'Cont) 2.

Valve Pit on 196'L for RHR B Valves 3.

Div II.(Yellow) vertical cable chase (southeast side) 4.

Div II (Yellow) horizontal cable trays 5.

RHR C,

CCP, SWP pi.pe chase on southwest side 6.

RHR B, HPCS, vertical pipe chase southeast side 7.

8.

9.

10.

Ax. Ba Valve Pit on 196'l El for CSH sup.

pool Suet.

valves (2CSH*MOV118)

CSH test return valves (2CSH*MOV110, "MOV112) and piping '

DIV III (Purple) and non-divisional vertical cable chase (northwest ssde) '.

Div III (Purple) horizontal cable trays '

South Fl El 215'.

Div II (Yellow) Vertical 8 Horizontal Cable Trays Reactor Buildin'outh 180'- 360'l El 215'.

CRD pumps (2RDS PlA, -PlB) 2.

CRD Instrument Rack (2CES RAK103) 3.

Div II (Yellow) horizontal cable trays 4.

Div II (Yellow) vertical cable chase (southeast side) 5.

RHR C,

CCP, SWP pipe chase on southwest side 6.

RHR B, HPCS vertical pipe chase (southeast side) 7.

8.

Div III (Purple) horizontal cable tray' Non-divisional 5 Div III vertical cable chase (northeast side)'

9.

HPCS full flow test to the sup pool (2CSH*MOVlll) 8 Min flow (2CSH*MOV105)

February 1997 Page 27 EP IP-EPP-10 Rev 02

ux.

FIGURE 2:

So t 1

0'able B Actions Sheet 3 of 6 1.

Div II (Yellow) Motor Control Center, 2EHS*MCC302 2.

.3.

Div II (Yellow) Conduit Div II (Yellow) DC Motor Control Center, 2DMS*MCCB1 4.

General Area eactor d

So t 180'- 360' l

40'.

Gen. Area 180' 360', Div II (Yellow) horizontal cable trays 2.

RHR B shutdown cooling return to recirc Loop B, outboard isolation valve (2RHS*MOV40B in a locked room) 3.

RHR B shutdown cooling supply from the reactor outboard isolation valve (2RHSMOV113), locked room 4.

Vertical.cable chase Div II (Yellow) southeast side 5.

RHS B, HPCS pipe chase southeast side 6.

7'.

RHS C,

CCP, SWP pipe chase - southwest'ide Div III (Purple)

& non-divisional cable chase northwest side~

'acto d

. Fl 6

Div II (Yellow) horizontal cable trays 2.

Div II (Yellow) vertical cable chase 3.

Div II Vessel Level

& Pressure Instrument Rack (H22P027) 4.

Motor Control Center 2NHS-MCC011 5.

N2 tank in track bay (2GSN-TK2) 6.

HCU Banks on the north

& south side 7.

CRD Manual Control Station 8.

B RHS

& HPCS vertical pipe chase February 1997 Page 28 EPIP-EPP-10 Rev 02

FIGURE 2:

U V

0 Table B Actions Reactor ld

. Fl l

261'.

SWP, RHR C, CCP vertical pipe chase R

NG Sheet 4 of 6 10.

12.

Div III Instrument Racks

H22P026, H22P005' Div III (Purple) horizontal cable trays '

Div III (Purple) and non-divisional vertical cable chase '

eacto Bld Fl El 89'.

General Area 2.

RHR B piping 3.

RHR B, HPCS pipe chase 4.

5.

SLS pumps

& tanks ADS Nz tanks

& Nz distribution piping 6.

Yellow vertical cable chase 7.

Yellow horizontal cable trays 8.

9.

Control HPCS piping HPCS (purple) cable trays '

Buildin Fl El 214'.

Div II (Yellow) 230 cable tunnel (east,

south, east) 2.

Div II (Yellow) cable area Control Buildin Fl l

1.

Div II (Yellow) 37'orizontal cable trays center room east side 2.

Div II (Yellow) horizontal

& vertical cable trays east side February 1997 Page 29 EP IP-EPP-10 Rev 02

,FIGURE 2:

UN S 0 Table B Actions Co t o ildi l

44' NG Sheet 5 of 6 2.

Div II (Yellow) cable trays Div III (Purple) cable trays '

Control Buildin Fl El 261'.

Div II SWGR Room Div II (Yellow) cable chase (east side) 3.

Remote Shutdown Room B (Div II) 4.

Div II Bat Room (in Div II SWGR room) 5.

6.

Div III (HPCS)

BAT Rm' Div III (HPCS)

SWGR Rm' Cont o

uildin F

l 289'.

3.

Div II (Yellow) cable chases

& cabinets (east side)

Dlv III (Purple) cable trays

& cabinet's

'elay Room (check: the general

area,

'inside all termination cabinets and panels) 4.

Computer Room 5.

Control HVAC rooms containing the Control Building Special Filter Trains Buildin Fl El 306' 1.

Div II (Yellow) cable chase (east side) 2.

Div III (Purple) cable trays

& cabinets 3.

Control Room: Termination cabinets

& inside panels 4.

HVAC rooms containing the Control Building Special filter Trains, February 1997 Page 30 EPI P-EPP-10 Rev 02

FIGURE 2:

UNIT 2 D VISION TAMPERING Table B Actions iesel Gener tor Buildin l

261'.

Div II Diesel Generator Room

& Control Room 2.

Div III (HPCS) Diesel Generator Room 8 Control Room '

Normal Switch Gear Bld

. Fl El 261'.

2NNS-SWG015 (Stub bus) 2.

2EHS-US5 (Stub bus) 3.

US4 Other Areas Sheet 6 of 6 1.

Div II Service Water (SWP)

Pump Room Bay (all elevations) a.

Include SWP pumps B,, D, F including all piping 8 valves b.

Include Motor Control Center 2EHS*MCC301 2.

Div II (Yellow) 230'lectrical

Tunnel, Fl El 215'south 5 east side) 3.

Non-divisional power and HPCS electrical tunnels (Blue cable trays Fl El 210'hich parallel Div I on West) '

NOTE:

HPCS requires protection only when the RCIC is compromised.

February 1997 Page 31 EPIP-EPP-10 Rev 02

FIGURE 2:

U T2 S0 Table C Locations A PERING Sheet I of 5 The following is an'lphabetized list of components and areas of concern.

The response is indicated in a specific footnote and/or Table D.

U I IARY'BA SOUTH l.

~F1 2

22 a.

Div II Motor Control Center (2NHS*HCC302) b.

Div II DC Switch gear (2DHS*MCCBl) c.

Div II (Yellow) conduit in this area 2.

1 5'.

Div II (Yellow) Vertical and Horizontal Cable Trays 3.

Fl El 196'.

RHR B Heat Exchanger Room b.

Div II (Yellow) Cable Trays 4.

Fl El 175'.

RHR B Pump Room L RHR B Heat Exchanger Room

~ATTER I.

Div II Battery (2BYS*BAT28), in Oiv II SMGR RH Fl El 261'ontrol Building CABLE CHASES TRAYS 1.

Div II (Yellow) Cable Chases, East Side of Control Building at elevations:

214', 237', 261', 289',

306'.

Oiv II (Yellow) Cable Trays from Div II Diesel, Control Building Fl El 244'.

Oiv II (Yellow) Cable Trays from Center East of Control Building Fl El 237'.

Div II (Yellow) Cable Trays Reactor Building South Side at elevations:

289', 261', 240', 215',

196'ebruary 1997 Page 32 EPIP-EPP-10 Rev 02

FIGURE 2:

U T

S 0 Table C Locations

~AB E

HA ES TINY (C

t)

AMP R

NG Sheet 2 of 5 5.

Div II (Yellow) Cable Trays and Conduit Reactor Building South elevations:

289', 261', 240', 215',

196'.

Div II (Yellow) Cable Trays and Conduit in South Aux Bays at elevations:

240',.215',

196'HARGER (Battery Chargers) 1.

2BYS*CHGR2B2 or 2BYS*CHGR2Bl, Div II SWGR Room (261'ontrol Building)

CONTROL 'BUILDING 1.

Div II (Yellow) Cable chases East side elevations:

214', 237', 261',

289',

306'.

Div II (Yellow) Cables from Div II Diesel, Fl El 244'.

Div II (Yellow) Cable

Room, East Center Fl El 237'.

Div II Switch Gear Room Fl El 261'.

Div II Battery Room Fl El 261'Inside Div II SWGR Room) 6.

Div II Remote Shutdown System Room; Fl El 261'.

Any Div II Panel or Termination Cabinet in the Relay

Room, Fl El 289'IESEL GENERATOR 1.

Div II Diesel Room to include:

diesel, fuel supply, air compressor, air tanks, fuel transfer, day tank, control panels ELECTRICAL TUNNELS 1.

Div II (Yellow), 230'lectrical. Tunnel or Trays, Fl El 215'NSTRUMENT RACKS 1.

Div II (RHS B) Instruments on 2CES*RAK021, Fl El 175'f Reactor Building 2.

Div II Reactor Pressure and Level Instrument Rack (H22*P027) on Fl El 261'f Reactor Building (Near the South bank of Hydraulic Control Units)

February 1997 Page 33 EP IP-EPP-10 Rev 02

FIGURE 2:

UN T D

S 0 TAMP RING Table C Locations OR CO RO C

NT RS Sheet 3 of 5 1.

Fl El 261'f the Reactor Building, South Side, 2NHS-MCC012 2.

Fl El 240'f the South Auxiliary Bay, 2EHS*HCC302 3.

Fl El 261'f the Control Building (Div II SMGR Room),

2EHS*HCC103 4.

Fl El 261'f the Div II Service Mater Pump Bay Room, 2EHS*MCC101 PIPE CHASES 1.

Reactor Building exposed Pipe Chase on the South Side, Outside Wall, Fl El 289'nd below CTOR BUIL ING 1.

l1 E1 17 a.

Div II (RHR B) Instrument Racks'(2CES*RAK021) b.

Service Water and Residual Heat Removal Horizontal Piping Runs on the South Side 2.

Fl El 196'.

Div II (RHR B) Valve Pits b.

Vertical Pipe Chase (HPCS*RHSB), South Side -'Outside Wall c.

Horizontal Piping Runs on the South Side to include 2RHS*HOV3B and Piping d.

Vertical (Div II) (Yellow) Cable Chase on the South Side e.

Horizontal and Vertical Div II (Yellow) Cable Trays and Conduit 3.

Fl El 215'.

Yellow Horizontal 5, Vertical Electrical Cable Trays b.

HPCS. and RHS B Vertical Pipe Chase on the South Side Outside Mall c;

Yellow Vertical Cable Chase on the South Outside Wall February 1997 Page 34 EP IP-EPP-10 Rev 02

FIGURE 2:

UNIT 2 DIVIS ON I TAMPERING Table C Locations

((EAATOR RC C(AR

. (C 4.

Fl El240'heet 4 of 5 a.

HPCS 5

RHS B Vertical Pipe Chase, South Side, Outside Wall b.

Vertical Yellow Cable

Chase, South Outside Wall c.

Horizontal and Vertical Yellow Cable Trays d.

RHR Shutdown Cooling return to Recirculation Loop B, 2RHS*MOV40B 5.

Fl El 261' a.

Div II Vessel Level and Press Instrument Racks (H22-P027) b.

2NHS-MCC012, South Side c.

Div II (Yellow) Vertical Cable Chase South Side d.

Div II (Yellow) Horizontal Cable Trays e.

RHR B, HPCS Pipe Chase on the South Side 6.

Fl El 289'.

RHS B Injection Valve (2RHS*MOV24B) or piping b.

Standby Liquid B Pump, valves, Squib valves, piping, containment penetrations

~RELAY RC (11 E(

ERR' C

1 1

R i(Ei R(

1.

Any Div II Panel 2.

Div II Cable Chase (East.Side) 3.

Div II Termination Cabinets (East Side)'EMOTE SHUTDOWN (Fl El 261'f Control Building) 1.

Div II Remote Shutdown Panel February 1997 Page 35 EP IP-EPP-10 Rev 02

FIGURE 2:

U T 2 0

Table C Locations R SI UA H AT R MOVA P

R G

Sheet 5 of 5 1.

Heat Exchanger B Room (Fl El 175'nd Fl El 196'f, South Aux Bay) 2.

Pump B Room (Fl El 175'f South Aux Bay) 3.

RHR B. Instrument

Rack, 2CES*RAK021 (Fl El 175'f Reactor Building, South) 4.'hutdown Cooling Return to Recirculation Loop B (2RHS*MOV40B), Reactor Building Fl El 240'outh 6.

RHS B Injection Valve area, Fl El 289'f the Reactor Building, South Side SERVICE WATER 1.

Service Water Pumps:

B, D,

F piping or valves in SWP Pump Room 2.

Any Div II Service Water Pipe or Valve located in the Reactor Building STAND Y LI UID SYSTEM 1.

Fl El 289'eactor Building (valves, Pump B or piping)

~NIT H G

4R

\\

l.

Div II Switch Gear (2ENS*SWG303)

Fl El 261'ontrol Building 2.

Div II DC Switch Gear (2BYS*SWG002A) Fl El 261'ontrol Building 3.

2NHS-MCC012, Fl El 261'f Reactor Building (South Side) 4.

2EHS*MCC301

, Div II Service Water Pump Room Fl El 261'.

2EHS*MCC302, Aux Bay South, Fl El 240'UNNELS LECTRICAL 1.

Div II (Yellow) 230'lectrical Tunnel (East, South East), Fl'l 215'OTES:

l.

Consideration should be given to first searching and securing the NMP2 Switchyard, the Scriba Switchyard, the Div I and Div II SWGR and Battery Rooms, and the 'Normal Switchgear Rooms after any tampering with the Divisional Diesel Generators or Service Water Supply to these diesels.

2.

This list only addresses components required for safe shutdown.

Other damaged or tampered components might not require as in depth a response.

February 1997 Page 36 EP IP-EPP-10 Rev 02

FIGURE2:

U DVSO Table D Actions RING Sheet 1 of 4 This Table D is a listing of Division I equipment and is used in response to Division II tampering.

Consider searching and securing all components and areas in this list.

This Table is an adjunct to Table C.

U AY 0 TH F

175'.

RHR A Heat Exchanger Room RHR A Pump Room REACTOR BUILDING'L EL 175'.

General area North to include:

a.

RHR R Instrument Rack H22-P018 b.

RCIC Sect A Instrument Rack H22-P017 c.

RCIC Pump Room and Pipe Tunnels

- d.

RCIC Pl Oil Clr Cntr Valve 2ICS*PT115 e.

RHR.and SWP Piping Runs on the North Side f.

DIV I (Green)

Conduit 2.

RCIC Panel B Div 2 Instrument Rack H22-P029 AUX BAY NORTH FL EL 196'.

RHR B Heat Exchanger Room 2.

Div I (Green) Vertical Cable Trays REACTO U

DING NORTH 0-180' 1.

General Area North 96'.

RHR Piping to include 2RHS*HOV30A 2.

Valve Pit (above and below grade) for all RHR A Pipes and Valves 3.

Div I (Green) Vertical Cable Chase (Northwest Outside Wall) 4.

Div I (Green) Horizontal Cable Trays February 1997

..,Page 37 EP IP-EPP-10 Rev 02

FIGURE 2:

UN T 2 SIO TAMPERING Table D Actions ACTOR U

D G NORT 0-O' 96'.

Pipe Chase on the North Side Sheet 2 of 4 6.

U AY RCIC Pipe and Valve Rooms (two rooms)

ORTH 15'.

Div I (Green) Vertical and Horizontal Cable Trays REACTOR BU NG ORTH 0- 80' 5'.

Div I (Green) Horizontal Cable Trays 2.

Div I (Green) Vertical Cable Chase 3.

Vertical Pipe Chase on the Outside Wall (Northwest)

AU BAY NORTH 40'.

Div I (Green)

Motor Control Center 2EHS*MCC102 2.

Div I (Green)

Conduit 3.

Div I (Green)

DC Motor Control Center, 2DMS*MCCA1 4.

General Area 5.

RCIC Suction Valve from CST REACTOR BUILDING NORTH 0-180 F

EL 240'.

General Area 2.

Div I (Green) Horizontal Cable Trays 3.

RHR A Shutdown Cooling Return to Recirculation Loop A Outboard Isolation Valve 2RHS*MOV40A (Locked Room) 4.

Vertical Cable Chase Div I (Green)

Northeast (Outside Wall) 5.

Vertical Pipe Chase on Northwest Outside Wall February 1997 Page 38 EPI P-EPP-10 Rev 02

FIGURE 2:

UNIT 0

TNPERING Table D Actions C

OR U

D G

F L 26 Diy I (Green) Horizontal Cable Trays Sheet 3 of 4 2.

Div I (Green) Vertical Cable Chase (Northeast Outside Mall) 3.

Div I Vessel Level k Pressure Instrument Rack (H22 P004) 4.

Motor Control Center 2NHS-HCC012 5.

Vertical Pipe Chase (Northwest Outside Wall) 6.

Nitrogen Tank (2GSN-TK2) in the Track Bay R ACTOR BUI D L

289'.

General Area North and East a.

RHR A Piping and Injection Valves r

b.

Green, Vertical Cable Chase c.

Green Horizontal Cable Trays or Conduit 2.

Standby Liquid Pump A, Piping, Tank and Valves to the Containment 3.

ADS Nz Tanks and Nz Distribution Piping 4.

RCIC Injection Valve CONTROL BUI D NG F

4'.

Div I (Green) 140, 35',

315 Electrical Tunnel 2.

Div I (Green)

Cable Area CONTROL BUILDING FL L

237'.

Div I (Green) Horizontal Cable Trays Center Room West Side 2.

Div I (Green) Horizontal and Vertical Cable Trays West Side CO RO BUILDING F L

244'.

Div I (Green)

Cable Tray February 1997 Page 39 EP IP-EPP-10 Rev 02

CO RO U

NG FIGURE 2:

U 2

S Table D Actions 6'heet 4 of 4 1.

Div I SWGR Room 2.

Div I (Green)

Cable Chase (West Side) 3.

Remote Shutdown Room A (Div I) 4.

Div I Battery Room (in Div I SWGR Room)

CONTROL BU ING 89'.

Div I (Green)

Cable Chases and Cabinets (West Side) 2.

Relay

Room, Check Inside all Div I Cabinets and Termination Cabinets (West Side) 3.

Computer Room 4.

HVAC Rooms Containing the Control Building Special Filter Train CONTROL BUILDING FL EL 306'.

Div I (Green)

Cable Chase (West Side) 2.

Control Room:

Termination Cabinets (West Side) and inside all panels 3.

HVAC Rooms Containing the Control Building Special Filter Train DIESEL GENERATOR BUILDING FL EL 261'.

Div I Diesel Generator Room and Control Room OTHER AREAS 1.

Div a ~

I Service Water (SWP)

Pump Room Bay (all elevations)

SWP Pumps A, C, E including all pipes and valves b.

Motor Control Center 2EHS*MCC101 2.

Div I (Green) 140

, 35

, 315'lectrical Tunnels February 1997 Page 40 EPIP-EPP-10 Rev 02

FIGURE 3:

S CURITY RELATED EMERGENCY T SIT S CURITY SUP RVISOR FLOMCHAR

~

rt Security Contingency Event Implement Contingency Procedures Assignl Assume

Response

Force Leader Activate the STOC Assign/Assume Accountability Coordinator Notifythe SSS Activafe

Response

Team as necessaIy

Response

Force Leader Activafe

Response

Force Security Coordinator (STOC Send SFM to Confrol Room Verify Accountability Re ort completed Suspension of Safeguards Required?

Obtain SSS.

"authorization to suspend safeguatds in accordance with 10CFR60.54x/y Coordinate 8 integrate

Response

Force personnel Perform security call-out SFM fo ERFs as necessary Assist Accountability Coordinator Respond as directed by SSS/SED Assist DCT Coordinator Send Oscars to OSC for DCTs implement EPIP-EPP-10 Ensure Access Authorfzation Establish Roadblocks February 1997 Page 41 EP IP-EPP-10 Rev 02

'FIGURE 4:

SECURITY'ONTINGENCY EVENT CSO CHECKLIST arne ate nit D1D2 Initial/Time 1.0 Notified of Security Related Emergency Event 2.0 Notify SSS

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3.0 Check plant parameters 4.0 Notify Nuclear Security Supervisor,

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5.0 Initiate any Operating, Special Operating or Emergency Operating Procedures required 6.0 lfdirected by the SSS, announce the following:............................

~N:

For emergency announcements, make the Gaitronics announcement at your unit using the Merge Mode.

Station Alarm "Attention. Attention, this fisfis not a drill. An emergency exists at Unit (1/2J Personnel shall evacuate the (locationJ immediately and stay out until further notice. "

If not urgent:

"Ifin protective clothing,. change in the normal manner and leave area.

Repeat alarm and announcement.

~NT:

For emergency announcements, make the Gaitronics announcement at your unit using the Merge Mode.

Station Alarm Attention Attention, thi.s iislisnot a drill. The emergency event at Unit ttygt is terminated Allpersonn.el may return to their normei work locations Repeat alarm and 'announcement.

8.0 Emergency Event terminated...........',......

February 1997 Page 42 EP IP-EPP-10 Rev 02

FIGURE 5:

SECURITY RE ATED E

V NT SSS S

F OWCHART Notwed of Security Contingency Event Activate Emergency Plan (EPIP-EPP-18)

Ifrequired Activate Emergency Facilities as required Assist Security in assessing threat Dispatch Operators to assist in search effort Prioritize Security Response as required:

This may include directing Security to ensure safety of operators performing plant assessment Has Plant Damage occurred?

.Evaluate damage, implement appropriate OPs, SOPs and or EOPs as required Security Safeguards Suspended'?

Continuously

monitor, reclassify as required Shutdown the Plant?

Verifyfinspect systems required for shutdown are operable

.Direct Security to control inspected systemslareas Shutdown the plant using appropriate station procedures Determine whether to shutdown or continue plant operations. Consider the following:

~ Ifshutdown or continued plant operation willjeopardize public health and safety.

~ Ifequipment necessary for shutdown or continued operation is in jeopardy or can be maintained operable.

~ Ifoperators can continuously maintain safe access to equipment required forshutdown or continued operation.

~ Ifthe security related event has already affected plant equipment required for shutdown or continued operation

~ Ifother conditions exist that would prohibit shutdown or co ti uedo e

ion Advise Security Coordinator.

~Use of photo/ID badges Search vehicles Search hand carried package's

~Search and ID personnel

~Registration of personnel

~Access control of VitalAniae

~NotifyNRC IAW10CFR 50.54x &y

.Perform appropriate OP tests, valve lineups to verify required system operability

.Direct Security to control access to verified systemslareas

~Continually evaluate prudency of continued ant o ration February 1997 Page 43 EP IP-EPP-10 Rev 02

').

J i

0

l 1

+ ~

i ~

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE PIP-EPP-08 REVISION 0 OFF-SITE DOSE ASSESSMENT AND P OTECTIVE ACTION RECOMMENDATION TECHNICAL SPECIFICATION RE(UIRED Approved By:

N. L. Rademacher Plant Manager - Unit I Da Approved By:

J. T. Conway P

t Manager Unit Da e THIS IS A FULL REVISION I

PERIODIC REVIEW, 02/23/98, NO CHANGE Effective Date:

PERIODIC REVIEW DUE DATE:

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SECTION 1.0 2.0 3.0 TABLE OF CONTENTS PURPOSE

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PRIHARY RESPONSIBILITIES PROCEDURE

3. 1 Dose Assessment and Protecti.ve Action'from the Control Room e

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3.2 Dose Assessment and Protective Actions from the EOF PAGE 1

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3 4.0 DEFINITIONS.

5.0 REFERENCES

/COMMITMENTS ATTACHMENT 1:

INITIAL DOSE ASSESSHENT AND PROTECTIVE ACTIONS ATTACHMENT 2:

USE OF THE EDAMS.COMPUTER.

ATTACHMENT 3:

- METEOROLOGICAL DATA ACQUISITION ATTACHMENT 4:

RELEASE RATE DETERMINATION.

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6 10 12 20 ATTACHMENT 5:

REFINED DOSE ASSESSMENT AND PROTECTIVE

(

FIGURE 5.1:

CHRONOLOGICAL RELEASE RATE LOG.

FIGURE 5.2:

EDAMS DATA ENTRY FORM ACTIONS......

26 31 32 February'-'1997 Page ii

..-" EP IP--EPP-08 Rev 07

f 1

5 44 k

0

= j 0

1.0 PURPOSE To provide the methods for determining meteorology data, release

rates, dose assessment and protective actions during accident conditions at Nine Nile Point.

2.0 PRINRY RESPONSIBILITIES 2.1 The Station Shift Supervisor/Site Emergency Director (SSS/SED):

2.1.1 Ensures meteorological data acquisition, release rate determination, and dose assessment are performed during the initial stages of an emergency to support development of Protective Action Recommendations (PARs)

Approves PARs and ensures their timely issue to the State and County 2.2 The Corporate Emergency Director (CED) approves PARs prior to their transmittal to the State and County, following EOF activation.

2.3 The Radiation Assessment Nanager (RN) is responsible to the SED for,,;

managing the onsite radiological monitoring and assessment aspects of the station during an emergency, following TSC activation.

2.4 2.6 Chemistry Technicians perform release rate assessments, obtain meteorological

data, and develop PARs, prior to EOF activation.

The Offsite Dose Assessment Nanager (ODN) manages the offsite dose aspects of an emergency in order to assess the radiological consequences to the public, following EOF activation.

The Radiological Assessment Staff is responsible to the ODAH for obtaining meteorological

data, determining source term, performing dose assessment, and developing PARs, following EOF activation.

3.0 PROCEDURE 3.1 Dose Assessment and Protective Action from the Control Roo CAUTION Calculation involving the determination of release rates and/or protection action shall be self-checked for accuracy.

3.1.1 Chemistr Technician Actions a ~

Consult the SSS/SED on plant conditions and possible release patlis. If a General Emergency has been declared",

assist SSS/SED in making Protective Action Recommendations based on"plant."conditions using Attachment 1.

February 1997 Page 1

EPIP-EPP-08'ev 07

3.1.1 (Cont) b.

Access EDAHS computer using Attachment 2

Co Obtain meteorological data using Attachment 3.

d.

Assess effluent monitor readings and conditions.

e.

Determine release rate using Attachment 4.

Combine multiple release points as follows:

1.

Sum all release points from the same elevation (ground or elevated).

2.

Calculate the total release rate from combined ground and elevated sources using the workspace on Attachment l.

g, Use Attachment 1 flowchart and advise SSS/SED of any

,PARs'recommended by the flowchart.

If an unmonitored'tmospheric release is suspected or known to be in progress, assist the SSS/SED in the following actions:

1.

Advise the SSS/SED to expedite the dispatch of Radiation Protection (RP) Technician.

Request assistance of the unaffected Unit or J.A.

Fitzpatrick if needed.

2.

The RP Technician should be dispatched to potential plume centerline (wind direction (degrees) 2 180 plume centerline),

as close to the "site boundary, as practicable.

.See Attachment 1, Figure 1.4 for Site boundary location.

3.

Perform the actions indicated in Attachment 1

should readings indicate 1 rem/hr based on field survey.

h.

Assist Communications Aide in completing the meteorological data and release rate sections of the Part 1 Notification Fact Sheet.

Continue to monitor meteorological

data, changes in effluent conditions or conditions that might lead to abnormal radiological effluents.

Turn over al:1 duties to the

EOF, when requested to do so.

IP II o

February.1997,

~ v Page 2'P IP-EPP-"08 Rev 07

3.1.2 SSS Actions a.

Verify that the Chemistry Technician is performing dose assessment and protective action development in a timely fashion and in accordance with Attachment l.

b.

Assess any release rates provided by the Chemistry Technician against the Emergency Action Levels (EAL).

c..

Review and approve PARs recorded on the Notification

. Fact Sheet Part 1,

as required.

Use ERPA map in Attachment 1 if desired.

3.2 Dose Assessment and Protective Actions from the EOF 3.2.1 Offsite ose Assessment N

er 0

AM Actions NOTE:

IF at any time the initiating conditions listed in Attachment 1 are met, THEN perform the actions

..l.isted in that attachment.

" -'" :a.*,-Perform,:actions as indicated in EPIP-EPP-23.

b.

Verify Environmental Survey Sample Team Coordinator has been assigned and is:

1.

Preparing for the dispatch of -downwind survey teams.

2.

Is aware of meteorological advisor status.

c.

Perform or have performed the following:

l.

Obtain meteorology, data using Attachment 3 of this procedure.

2.

Obtain effluent monitor readings and calculate release rate using Attachment 4 of this procedure.

3.

Perform dose assessment calculation using Attachment 5 of this procedure.

d.

Determine PARs using Attachment 5 of this procedure.

e.

Interface with State and County representatives in the EOF.

1.

Keep State/County representatives informed of confirmed data and results.

2.

-Complete Part 2 Notification 'Fact 'Sheet with each significant change..in meteorological, actual

.release'ate,.and.

dose assessment data.

February'997

"';: P.'age 3

'""='-"EPIP-EPP-08

~.-.

Rev 07

3.2.1 (Cont) h.

Constantly reassess effluent monitors {release rate) and meteorological data for changes.

Perform new dose assessment as needed.

Develop new PARs and/or verify the adequacy of PARs already made.

As Downwind Survey Team (DST) becomes available, utilize it to verify release rates.

If these refined release rates differ significantly from those calculated from effluent monitor readings, reperform dose assessment using refined release rates.

Provide data for the Part 1 Notification Fact Sheet as requested.

4 Provide CED with pertinent information as needed.

1 1:

'-" Changing radiological conditions that may lead to PARs.'.

Protective 'actions for site staff.

3.2.2 Maintain Chronological Release Rate Log {see Figure 5.1).

Rad Assessment Staff NOTE:

IF at any time the initiating conditions listed in Attachment 1 are met, THEN perform the actions listed in that attachment.

0 a ~

b.

Perform actions as indicated in EPIP-EPP-23, if

'ppl icabl e.

Perform any actions as requested by the

ODAM, including:

Obtaining meteorological data (Attachment 3)

Obtaining release rate data (Attachment 4)

Performing dose assessment and protective action recommendations (Attachment 5)

4. 0 DEFINITIONS Page 4

~ "I

~

4.1 CDE~.

Committed dose. equivalent to the.,thyroid for the child.

4.2 EDAMS.

Emergency Dose Assessment Modeling System.

A PC-based

.computer. program that calculates release

rates, doses,-;and protective

-.-';actions, and obtains meteorological data,,for-emergencies.

V 4

~

'February.1997 EPIP-EPP-08

..Rev 07

4.3 4.4 4.5 4.6 NNS.

Meteorological Honitoring System.

Consists of the dedicated

computer, main, backup and inland towers and software.

Stores and edits site meteorological data.

RADDOSE.

A subprogram of EDAHS, it performs the dose assessment functions during emergencies.

RAS.

Radiological Asses'sment Staff.

Consists of those trained individuals who would report to the ODAM or RAH, and perform various assessment and data-gathering functions outlined in this procedure.

TEDE.

Total Effective Dose Equivalent.

5.0 REFERENCES

COMMITMENTS 5.1 censee Documentation 5.2 5.1. 1 NHP Unit 1

FSAR,Section XV 5.1.2 NHP Unit 2 USAR, Section 15 5.1.3

SEP, NHPC Nine Mile Point Nuclear Station Site Emergency Plan Standards Re ulations and Codes None 5.4 Policies Pro rams and Procedures 5.3.1 EPIP-EPP-07, Downwind Radiological Monitoring 5.3.2

'PIP-EPP-15, Health Physics Procedure 5.3.3 EPIP-EPP-20, Emergency Notifications 5.3.4 EPIP-EPP-23,.

Emergency Personnel Action Procedures Commitments None 6.0 RECORD REVIEM AND DISPOSITION The following records generated by this procedure due to an actual declared emergency shall be maintained by Records Management for the Permanent Plant File in accordance with NIP-RHG-Ol:

~

Attachment 1, Initial Dose Assessment and Protective Actions

~

Attachment 4, Release Rate Determination

~

Figure 5.1,~Chronological Release Rate Log

~

Figure'.2,'DAHS Data Entry Form

~

~

-;Any records generated, by this. procedure that are not due to an actual declared emergency-are; not required.for retention in the Permanent

~

Plant File.

February 1997 Page 5

EPIP-EPP-08 Rev 07

ATTACHNENT I ITIAL DOS ASSESSMENT AND PROTECTIVE ACTIONS Page I of 4 START 0

Hase Gene/n/E/hwpehcy bean doctored?

. Obtain Motaa1oghd Oats

. De>>lrrele Release Ra>>

is Taaf Ra>>ase Ra>>'reater tharl rates Ih Tab(e 1.1~ ear>>1 mstoocskogy?

Is there evtdence ol an I/n/nfrn/fr/redrelease?

YES YES YES EKIICUhIR

.ERPAs tg.326M ERPAs Ffrerrrfes dolrrfnd I~Table 1.2 or EDAMS~W SBELIEL ARema'eked ERPAs IF take breeze h plesenL THEM EVACUATE

'Lake Breeze Adjutted'RPAs tuse Table 1.2 or EDAMS Computer)

Advfse SSS/SEO that onhcWions for a GENERAL EMERGENCy have been met Verifythat Release Rates are suppotad by Rsdrptaic cohd5onL Cchsdec

. Care dah>>ge Eff4ent rholltollearghgs

. OryvnN High anne monaorleadhgs SSS trrspatch RP Tech to pftshe aenterlne Iwlnd direction/a ISgoi as cfose to sre boundary as practicaL RP Teoh to take does rats /earrings YES Is measured Dose rate s 1 Rem/hl?

NO Haa whd plectron Changed bye ao ance PARs were fast made?

NO YES RE~ALlIATEPARs Use this formula it release has a ground AND elevated source:

Ground Rolosse Rate (Ci/s)

Table 1.1 Ground Reloese Rate (Ci/s)

Hovstod Release Rote (Ci/s)

Table 1.1 Hovstod release rate (Ci/s)

IF > 1, A,General

,Emergency Exists February 1997 Page 6

EP IP.-EPP-08 Rev 07

ATTACHMENT I INITIALDOSE ASSESSMENT AND PROTECTIVE ACTIONS Page 2 of 4 TABLE 1.1 - GENERAL EMERGENCY RELEASE RATES

~'~-',<<'i;'-- ':--;.:<< '3-.;i,q.;. Ground Release (C(/s) ',.;r<<,"j,,<<~;."...,";,- r

, '; -':;. >, Elevated Release (Cf/s)

Wind Speed (ml/h)

A Stability Class B/C E/F/G Wind Speed (mi/h)

Stability Class D

B/C E/F/G 0-3 1333 213 119 38 0-3 2041 1124 3030 769 4-6 7-9 10-13 14-17 3226 286 143 5556 526 250 7692 769 357 10753 1075 500 48 83 117 164 4-6 7-9 10-13 14-17 3703 '09 769 769 5882 1515 1075 1250 7692 2083 1388 1724 11494 2857 1818 2273 18-21

)21 13514 1389 667 213 16393 1667 833 256 18-21

>21 14286 3704 2273 2778 17241 4348 2632 3226 TABLE 1.2 - AFFECTED ERPAs

~j~Wind Direction'Fi'omQ-"

to to

"> sr ~"'4><4:~~"

234 to 240 41'o 254'-';;;<, ~,";.'.~:;,>.-

255 to 62 79 to 29 to

'~ o >p<p.~i, c,jglr to 1

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4, 5,

, 9 4

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',:~'4, 4,

14, 15, 29 14;;,15,,29.i::-"'r:~ ",:;, '.<<!...;-~

14, 15, 16, 17, 29

'l4, 1,,1,~1 8, 14, 15, 16, 17, 18, 29

~ 'l4i'.1 i '1 i~1 7il<<l 4e s

s

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s

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, Lake Breeze Adjusted

,P'.;.'-'5'Mlle Radius),',

9 to

><>Sr')... '<y~ 'Pq 333 to 340 341.;to 349,

.;;-'<:;:~"-". e.';",::"-';

4,5,9,10,11 4,~5,",9,,;10;".1 l>;,'"",:.',. '~,: ~p ~:,.;

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r~

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8, 15, 16, 17, 18, 19, 20, 21, 25 8, 'l7..18;.19 20,21;24,"25:;<<':,

i 6,7, 12 6, 7;,.12 350 to 56 1

to 21 to 51 52to 5 5

to 6

to 70 5,, 9, 10, 11 s

~

s 5,6, 11

~

1.

~p C7

, 13, 1, 19, 20, 21, 22, 24, 25, 12

~

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4, 12 13,,19,,2021, 22, 23,,24, 25,;28, l2 13, 19, 20, 21, 22, 23, 24, 28, 12 1,1,, 1,,;., 4,,-1 13, 'l9, 1, 22, 23, 24, 28, 12 4,7 4

• ~s..~ '

4, 10 10 1;,to to to 115 to 146 147 to 2-13

.K 1

1, 1,

28 28,29

,2, 4,,-1

,l,l TABLE 1.3 - EPA 400 Protective Action Guidelines (EPA PAGs)

-; ', q,::,",",~SPAR,".;,, ;, ",,.;;,

";;.,;:, TEDE (rem),:.',.:.;.'." ',

" '~ -';

-... >':,,'CDEr (rem):,;;

Evacuate

>5 February 1997 Page 7

EPIP-EPP-08 Rev 07

ATTACHMENT I INITIAL DOSE ASSESSMENT AND PROTECTIVE ACTIONS FIGURE 1.4 - Site Boundary Map Page 3 of 4 g

I V

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~e Nine Mile Pornt Site Boundary The Site Boundary is indicated by the heavy black linc.

It 4'4 s,1 February 1997 Page 8'-

EP IP-EPP-08 Rev 07

ATTACHMENT 1 INITIALDOSE ASSESSMENT AND= P OTECTIVE ACTIONS page 4 of 4 FIGURE 1.5 - ERPA Map

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~eI~A Pipuiaaon Emergency Response Planning Areas (ERPA)

-.,with.1991 Population, Estimates February 1997 1

Page;-9 EPIP-FPP-O8 Rev 07

ATTACHMENT 2 USE OF THE'EOAMS COMPUTER Page 1 of 2 For the Control

Room, see Section 1.0 below.

For the

EOF, see Section 2.0 below.

1.0 CONTROL ROON EOANS Turn the system on:

Turn on the power to the EDAMS computer,

monitor, and printer.

After the computer boots, the EDAMS log-in menu will appear (Figure 2. 1),

and the default log-in selection will be highlighted.

1.2 Com uter roblems

'a ~

If at any time problems are experienced with the computer, depress the eject button on the front of the computer.

This will eject the laptop computer.

Continue this procedure with the laptop.

2.0 b.

If the laptop should fail, have Chemistry Tech from the unaffected Unit go to the unaffected Control Room and bring the EDAMS laptop back to the affected Control Room and continue with

. this procedure.

A

~NOT :

In this case, meteorological data will have to be obtained manually.

EO EDAMS 2.1 2.2 Turn the system on:

Turn on the power to the EDAMS computer,

monitor, and printer.

After the computer boots, the EDAMS log-in menu will appear (Figure 2. 1),

and the default log-in selection will be highlighted.

Com ute roblems.

~

If at any time problems are experienced with the computer, use

.the duplicate EDAMS'omputer in the EOF.

FIGURE 2.1 - EDAMS Main Menu

<';N>> '.;.~>er.,'~A

gd'EDAMS:lLQGIN;MENU~<<,.'.g;:.,~~

~j'~,".g':;:w'.j",';:.j.".;:;lL>>ogori

~t'Fi6Pa>>trick!Met >>data!,:.-'>:.":..--',j.'<-.j~-'

~~V~.";i':':::::'>>:'.:",'":i,"'i:Dial;upFit'zPa't'rick"'Met'.'data-,";!:,:::-'!.';"'."",::"."' '4-'

C~',"..':j,-'j!,'.j.-;iRun'n',Nlanva>>l:,Met,'Data! Input'Modejg;'.:~>~",';"'.-..",',.',:~

February'997 Page:10' IEP'I P-EPP-08.

Rev 07

ATTACHMENT,2 USE OF"THE EDAMS COMPUTER Page 2 of 2 3.0 SYSTEM USE

3. 1 A brief description of each EDAHS Hain selections is found below.

a ~

Release Rate Calculation.

Computerized worksheets for all methods of release rates.,

This option is plant specific.

b.

Emergency Meteorology Report.

A single screen that contains the latest fifteen minute meteorology data.

c.

Dose Assessment Model:

RADDOSE IV.

Emergency dose assessment model.

All plant specific release rate methods are available, and the latest fifteen minute meteorology data is automatically inputted to the model.

d.

Protective Action Recomnendations.

Determine PARs for each Emergency

Response

Planning Area (ERPA) e.

Other Selections:

~

Miscellaneous Meteorological Reports.'For Het Advisor use)

Contains the Emergency Heteorology Report and historical meteorological data for a'1l three towers.

~

RASCAL.

RASCAL is the NRCs dose assessment model; The most recent version is included in EDAHS for general use.

~

Field Team Calculations.

Provides a method for calculating results from downwind survey teams.

f.

Logoff 4.O DA S DOSE MODEL LIMI ATIONS 4.1 4.2 4.3 4.4 A calculational limitation of the dose assessment model occurs when an extreme wind (direction) shift takes place.

The model may not calculate doses in sectors that the plume skips over entirely within a single 15 minute calculation step.

EDAHS only allows the operation of one application at a time.

Dose rates and deposition rates reported by the model are the maximum for the sector, not necessarily the dose rate or. deposition rate at the center of the sector.

This avoids the situation of a narrow (stable) plume slipping between receptor points and being missed.

Deposition data reported is not intended for-an environmental evaluation; its intent is to indicate. areas of potentially high ground level concentrations.

February 1997 P.age ll EP IP-EPP-08 Rev 07*

~ ~

ATTACHMENT 3 ETEOROLOGICAL DATA AC UISITION Page I of 8 1.0 2.0 2.1 2.2 2.3 2.4-OBT I I G

ETEO 0 OG CAL DA A The methods of obtaining meteorological data are, listed below in the order that they should be used.

~

EDAHS (see Section 3.0 of this Attachment)

~

Strip Chart Recorder (see Section 4.0 of this Attachment)

~

- Manual input from alternate sources (see Section 5.0 of this Attachment)

USE OF METEOROLOGIC L DATA: GENERAL CONDITIONS EMOTE:

Wind Speeds measured at both the main and backup towers may at times be less than actual wind speeds.

When using the main tower winds and the wind direction.is between 0

and 100 or when using the backup tower and the wind direction is between 220 and 270

, caution should be exercised when estimating plume arrival time.

It is likely that the plume will arrive sooner than the measured wind speed would indicate and the, actual dose may be less than forecasted by E

( I DAHS.

f C

Hierarchy of NHP meteorological data sources is shown in Table 3. I below.

If substitute data is to be used, consult the Heteorological Advisor (if available).

If no release is in progress, or release path is unknown, use elevated data (200'ain tower), or substitute as outlined in Table 3. 1.

If using the 30'igma theta and the wind is blowing from 030 to 105 substitute to the next source per table 3. 1.

'The Heteorological"Advisor may use" any-source (Sodar,'ther

towers, characterization tables, etc.) or skills of the trade to satisfy the need for meteorological data.

TABLE 3.1 Hierarchy For Use of NHP Heteorological Data Sources 0

p>~~vgp~p: ppp ~ p g)t~~'~ yp '~~@pg

~~@~p+ppgo~ ppZ~>)c,.()i g~ gj<.~~vp

$':.:;::,::;MindSpeed',"5;.'.;~/'~(

Primar

~'-'ubstitutes 200'ain 100'ain 30'ain

.Primar Substitute's

- 200'T 30'i ma Theta.

30'i ma Theta 200'T

";. '." Primary equals::,Primary;Backup for Unit 2 February '1997 Pa'g e'.1-2:

- 'EPIP.;EPP-08.'c~

Rev 07

ATTACHNENT 3 N

EOROLOGICAL DATA AC UISITION.

Page 2 of 8 2.6

~7 Refer to Figure 3.2 to determine if lake breeze is a possibility (EOF only).

Refer to Figure 3.3 to determine if land breeze is a possibility (EOF only).

3.0 EOANS 3.1 To obtain meteorological data for the Notification Fact Sheet Part 1,

select Emergency Heteorological.Report from the EDAMS main menu.

Select the data as discussed in Table 3. 1.

3.2 Hit the F5 Key to print the data.

4.0 S RI C

AR ECORD R

CAUTION Do not use the'. L'ED re'adouts.associated with the strip chart recorders.

• * * * * * * '4<* *'"*i*'** *.** * * * * * * * * * * * * * * * *

• 50TE:

Use this data only if the method described in Section 3.0 of this Attachment is unavailable.

4.2 4.3 4 '

4.5 4.6 Strip chart meteorological data can be found in both of the Control

Rooms, and in the TSC.

Utilize Table 3.1 to determine source of data.

50TE:

, hT cannot be obtained in the TSC.

Utilize e8 in determining stability.

Figures 3.4 and 3.5 show sample strip chart traces showing ambient air temperature, BT, a8, wind speed and direction data.

Observe the values of the vertical temperature difference, hT, from the primary meteorological tower over the last 15 minute period.

The preferred reading is the 30'-200'elta temperature reading, for an elevated (stack) release.

Compare the values of bT to the Stability Classification Chart (Table 3.6) and select the appropriate stability class and record.

If values of bT are not available, then observe the values of a8, directly from the primary or backup meteorological tower recorders, over the last 15 minute period.

Compare these values of a8 to Table 3.6.

Using the chart, select the appropriate stability class and record.

If both data are available, use.the hT at 30'-200'levation for elevated releases:

use o8 at the. 30'levation, for ground (vent) releases.

February 1997

- Page 13 EP IP-EPP-08 Rev 07

ATTACHMENT 3'TEOROLOGICAL DATA AC UISIT'ION Page 3 of 8 4.8 If values for dT and cr8 are not available, then observe the wind direction trace over the last 15 minute period.

Determine o8 by dividing the horizontal deviation of the wind direction trace over the last )5 minutes by 6.

To make reading of the strip charts easier, you may want to advance the chart.

5.0 MANU INPUT FROM ALTERNATE SOURCES NOTE:

Use this data only if the methods described in Section 3 and 4 of Attachment 3 are unavailable.

• • • • • • • • • • • • • • • • • • • • • • +

4 *****

4 *****

CAUTION 5.1 Data obtained by the methods described below will not be site-specific and will likely introduce errors into dose assessments.

The Meteorological advisor shall be consulted regarding the use of all substitute data.

If the Meteorological advisor is not available, use the data as obtained.

• * * * * * * * *

• 4 * * * * * * * * * * * * * * * * * * * * * * *

• I Telephone the National Meather Service

{NWS) in Buffalo"at 800-462-7751 or 716-565-9001.

5.2 Request the current wind speed and direction, stability class and temperature.

5.3 Use this data as follows:

a.

Mind speed (NMS) elevated and ground wind speed b.

Mind Direction (NMS) elevated and ground wind direction c.

Stability Class (NWS) stability class d.

Temperature

{NWS) ambient temperature

.Febr'uary '1997 Page"1'4:

-.EP I'P-EPP-.08.

Rev 07

ATTACHMENT 3 METEOROLOGICAL DATA AC UISITION Page 4 of 8

~,

2.

3.

FIGURE 3.2 Lake Breeze/On-Shore Flow and Fumigation Flow Char t Obtain meteorological data per Section 1.0 of this Attachment.

Obtain lake intake water temperature from Unit 1 or 2 process computer or from Control Rooms.

Follow the flow chart answering, the appropriate questions.

Is a release possible between dawn and dusk?

NO YES Is the intake water temperature less than the air temperature?

YES Is Mind Speed less than 22 mph?

YES 1

Is Wind Direction out of the wind sector from 270 through 360 to 90?

YES Potential'='or-On-Shore, Flow or 'Fumigation ',:-":,;:

Exists:

OR Use "Lake Breeze Adjusted ERPAs" for PARs (Table 1.2 or EDANS)

NO NO Is Mind Speed less than 10 mph?

YES Potential "for. Lake Bre'eze'xi sts:*....,,

Use "Lake Breeze Adjusted ERPAs" for PARs (Table 1.2 or EDAHS)

NO Stop.'Analysis No modifications to PAR required

• Also note that there is a potential for a sudden shift in wind direction to 245'hrough to 65 if the lake breeze has not already formed.

February 1997 Page 15 EPIP-EPP-08 Rev 07

ATTACHMENT 3 0 0 OGICAL OAT C UISITION Page 5 of 8 FiGURE 3.3 LAND BREEZE FLOW CHART Is a release possible between dusk and 10 a.m.?

1.

2.

3.

NO Obtain Meteorological Data.

Obtain lake temperature.

Follow the flow chart answering the appropriate questions.

YES Are sky conditions nearfy clear (I.e., little or no clouds)?

NO YES Is the lake water temperature greater than the air temperature?

NO If h

h 1

YES Is 200 ft. Wind Speed less than 17 mph'?

YES NO

...,.. Is 200 ft. Wind Direction from 0904 through 180'o 270'?

The p'otential for Land Breeze still exists. Continue to monitor.

YES Is 200 ft delta T stability F or G?

YES Stop Analysis A Land Breeze is not expected.

Land Breeze may already exist and 200 ft. Wind Direction may not be representative of stack height winds.

'NOTE: There is a potential for a shift in Wind Direction to 090'hrough 180'o

',270 =.:at the weather tower.

February 1997 Page'6 EPI P-EPP-08" Rev 07

ATTACHNENT 3 OROLOGIC L DAT AC UISITION Page 6 of '8 F1GURE 3.4 SANtPLE AlR TEMPERATURE AND STABILITYCLASS TRACE - CONTROL ROOM

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0'60 ~ 1 Oi 60 ~ 0

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0 ~ l0 ~ l Asnhiont Ar Tomperaalro Scalo in Cvyee F4.

(Mont~ daal iaan1 ~

10 far valuos bolow 0'nd anavo 90'.

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February 1997 Page 17.

EpIP-EPP-08 Rev 07'

ATTACHMENT 3 METEOROLOGICAL DATA AC UISITION Page 6 of 8 SAMPLE WlND SPEED FIG AND WlND D URE 3.5 lRECTlON TRACE - CONTROL ROOM/TSC 540 Wind Diro ion Trooo

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1 Hour Trace 15 Minute Period

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20 MPH 5 MPH /Div.

20 MPH

'ppcax. 7 MPH

.0 February 1997 P

Page-18:

'EPIP-EPP-08 Rev 07

ATTACHMENT 3 ETEOROLOGICAL DATA AC UISITION Page 8 of 8 STABILITY CLASSIFICATION NMPC TURBULENCE PASQUILL CLASS

"'AT.

TEMP CHANGE WITH HEIGHT, oF/70(d" (rs DEGREES RANGE OF VALUES't'ABLE 3.6 - STABILITYCLASSIFlCATION CHART TEMP CHANGE WITH HEIGHT, oF/168ft'xtremely Unstabb hT/hZ < %.73 22.5 < otr <

hT/hZ <

'1.75 Moderately Unstatde 699htly Unstable Neutral 699htly Stable Moderately Stable Extremely Stab(e IV

-0.73 < hTIhZ < -0.65

-0.66 < hTlhZ < -0.68

&.68 < hT/hZ < %.19

%.19 < hTlhZ < 0.68 0.68 < hT/hZ <

1.63 1.63 < hTIhZ 2.1 < 09 < 3.8 1.38 < hT/hZ < 3.89

'off <

2.1 3.89 < hT/hZ 17.5 < od < 22.6

~1.76 < hTlhZ < -1.57 12.5 < od < 17,6

-1.67 < hT/hZ < -1.38 7.6 < oe < 12.6

~1.38 < hT/hZ < 4.48 3.8 < od < 7.6

%.48 <QT/hZ <

1.38 (21 (Sl Adjusted to correspond to the hT measured between the 30-foot and 100 foot levels.

Note on symbol convention 3.8 <oaf<7.6'eans that mt ls 9reatsr than or equal to 3.8 degrees but less than 7 6 degrees.

Adjusted to conespond to tha hT measured between the 30 foot and 200 foot;levels.

AT PH Rl TABILITY HARA TERIZATI N A. (I)

Mid-afternoon only, with clear skies or skies with very fevy thin clouds; late spring to early fall, winds usually are below 6 miles per hour, B. (II)

Late morning to mid-afternoon'only, with clear or partly cloudy skies; mid spring to mid-fall, winds are usually below 9 miles per hour.

C. (II)

D. (III)

Late morning to late afternoon only, with partly cloudy skies; spring through fall, winds are usually below 11 miles per hour.

All daytime, with overcast or partly cloudy skies or early morning and late afternoon with clear or partly cloudy skies, all night time with overcast skies or partly cloudy year around, winds are moderate to high (greater than 6 miles per hour).

E. (IV)

Typically night time only, with thin overcast or partly cloudy skies, all year around, winds less than 10 miles per hour.

F. (IV)

Typically night time only, with clear to partly cloudy skies, all year around, winds less than 7 miles per hour.

G. (IV)

Typically night time only, with clear skies or very few thin clouds all year around, winds less than 5 miles per hour.

.February 1997 Page 19 EPIP-EPP-08,

'Rev 07

ATTACHMENT 4 RELEASE RATE DETERMINATION Page 1 of 6 1.0 METHOD Access the EDAMS Computer using Attachment 2 of this procedure.

IF Unit 1 was selected, go to Section 2.0 of this Attachment.

IF Unit 2 was selected, go to Section 3.0 of this Attachment.

2.0 UNIT HODS 2.1 CL ~

b.

c d.

e.

~OG SMS Select monitor {7, 8, 10a or 10b)

~OTE:

Monitor 7 indicator 112-07A Monitor 8 indicator 112-08A Monitor 10a indicator RNlOA Monitor 10b indicator RNIOB Enter time that reading was obtained (using 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format)

Enter monitor reading (cpm for monitors 7 or 8, cps fot monitors 10a or 10b).

Use J. panel readings or the following computer points:

I

~

monitor 7,'use E334

~

monitor 8, use E335

~

monitor

10a, use E488

~

monitor 10b, use E489 Enter calibration factor. If unavailable, use default values below:

~

4.4E-8 for 7 or 8

~

4.4E-7 for 10a or 10b Enter Stack Flow (kcfm).

Use computer point C320 or calculate from Table 4.1.

g, Hit the "F9" key.

Print results.

r

~

r

~ r r

2.2 a ~

b.

c ~

'd.

RAGEMS Enter the time that the reading was obtained

{24 hour format).

Enter the monitor reading {cps).

Use J panel reading or computer point C321.

Enter calibration factor {use posted value).

Enter dilution factor as follows:

~

1 1E3 2E5 4E7 if 6 liter chamber is used if 30 cc chamber is used

. if 30 cc chamber plus first stage dilution is used.

Use Total Dilution Ratio (TDR) x1000 as the dilution factor, if.

TDR is known.

'f 30 cc chamber plus first'and -second stage dilution is used.

Use TDR x1000 as 'the dilution factor, if TDR is known.

r r

Pl February '1997-

- Page 20 EP IP-EPP-08 Rev 07

ATTACHMENT 4 ELEASE RATE OETERMINATION Page 2 of 6 e.

Enter Total Stack Flow (kcfm).

Use computer point C320 or calculate from Table 4.1.

g, 2.3 a ~

b.

c Hit the "F9" key.

Print results.

~k Enter the time that the reading was obtained (24-hour format).

Enter the monitor reading (mrem/hr).

Enter the calibration factor.

If unavailable, use default value of 0.5.

d.

e.

2.4 Enter Total Stack Flow (kcfm).

Use computer point C320 or. calculate from Table 4.1.

Hit the "F9" key.

Print the results.

'rab Sam le Noble Gas

• * * * * * * * * * * * * * * * * + * * * * * * * * *

• CAUTION In using grab samples to determine release

rate, the results may be invalid if significant changes in source terms have occurred since the sample was taken.

a ~

b.

Co Enter the time that the reading was obtained (24-hour format).

Enter total Noble Gas concentration (pCi/cc).

Enter Total Stack Flow (kcfm).

Use computer point C320 or calculate from Table 4.1.

1 d.

e.

2.5 Hit the "F9" Key.

Print the results.

Sack Calculation NOTE:

a ~

C.

Use back calculation of downwind survey team data to determine release rate when no other method is available, AND to verify calculated release rates.

Enter the 'time that the reading was'obtained (24-hour 'format).

Enter the wind sp'eed (mi/hr).

Use the method described in Attachment 3.

Enter

".E."" for elevated/s'ta'ck or "G" for ground/vent release.

February

)997

'Page'21

",EPIP-EPP-08 Rev 07

ATTACHMENT 4 RELEASE RATE'ETERNINATION'age 3 cf 6 d.

e.

h.

2.6 a ~

b.

2.7 NOTE:

'a ~

Enter the stability class (A-G).

Enter the three foot closed window reading from the ion chamber (mrem/hr).

If readings are in CPM, then convert using 3500 CPM 1

mrem/hr.

Enter the downwind distance that the above reading was obtained.

Hit the "F9" key.

Print the results.

~FSA Input from the Control Room or TSC staff is necessary to select the FSAR accident type that most closely describes the conditions 'being experienced.

Select the accident being experienced or projected (Use Attachment 5, Table 5.1).

~

~

~

Print results.

Co tainment Hi an e Nonitor This method is only valid if the monitor is able to "see" the release.

Therefore, consult Operations personnel on the validity of. monitor readings.

Enter the monitor ID or number.

b.

C.

d.

e.

g, h.

Enter the time that the reading was obtained (24-hour format).

4 Enter the date that the reading was obtained.

Enter the time of reactor shutdown (24-hour format).

Enter the date that the reactor was shutdown.

Enter the monitor reading (rem/hr).

Use computer point E467 or E468.

Enter the expected flow rate (kcfm) to the environment.

Consult with Operations personnel if needed.

Hit the "F9" key.

Print results.

2.8 or li uid.releases consult Nl-CSP-N204 February 1997 Page22'P IP-EP.P-OS:.

Rev 07

ATTACHMENT., 4 RELEASE RATE. DETERMINATION Page 4 of 6 3.0 UNIT METHODS GEMS a.

Enter the time that the reading was obtained (24-hour format).

b.

Enter "S" if this is a stack reading or "V" if it is a vent-reading.

c.

Enter monitor reading (pCi/s).

Use GEMS readings from SPDS display or the 882 panel.

.If offscale, use GEMS computer.

d.

Hit the "F9" key.

e.

Print results.

3.2 Grab Sam le Noble G'as CAUTION In using grab samples.to'et'ermine*.'elease'ate, the resul,ts may be invalid if significant changes~.-in'.source terms have occurred since sample was taken.

• * * * * * * * * * * * * *'* *.4' a.

Enter the time that the reading was obtained (24-hour format) b.

Enter total Noble Gas reading (pCi/cc).

c ~

Enter total stack or vent flow (kcfm).

Calculate from Figure 4.2 or 4.3.

d.

. Hit the "F9" Key.

e."

Print the results.

3.3 Back Calcu at o

3.4 Use Section 2.5 of this Attachment.

USAR Use Section 2.6 of this'ttachment.

3.5 3.6 Containment Hi h Ran e Monitor Use Section 2.7 of this Attachment.

Monitor readings are available on the DRHS system (RHSla,b,c or d), the SPDS display or the 880 panel.

For li uid releases consult N2-CSP-LWS-M203

,"'ebruary.

1997 Page,23".

EP IP-EPP-08

.Rev 07

ATTACHNENT 4 RE SE RATE DET NAT ON-Page 5 of 6 TABLE 4.1 FLOW RATES CORRESPONDING TO FAN CONFIGURATIONS FOR UNIT 'I

~ ~

~

~

J Orywall Vent, Purge, end Fdl Une (10.00 KCFM)

Turbine Building High Speed Fans (170.00 KCFM)

Turbine Building Low Speed Fane (120.00 KCFM)

Reactor Building Higb Speed Fans (70.00 KCFM)

Reactor Building Low Speed Fans (35.00 KCFM)

Waste Building (8.00 KCFM)

Waste Building Extension (5.30 KCFM)

Offgee'.Building (6.00 KCFM)-

Reactor Building Emergency Vent. (1.60 KCFM)

RSSB Extension (10.25 KCFM)

'@Pic+"~~+i?>: '<<t~~~'>> ~'~>P" '~<TOtBI ~S18Ck,'ROLV>t'~'+g>+P~'(f$ 'H4++'~$+p'$ s KCFM KCFM KCFM KCFM

'CFM KCFM KCFM KCFM KCFM KCFM KCFM

~

• '+ p

• a,,

mC:WAK,g't~."""' 'ABLE4.2 FLOW RATES CORRESPONDING TO FAN CONFIGURATIONS FOR UNIT 2 STACK CST Room 1

Fen (2200 SCFM)

Stack Substructure 1 Fen (1400 SCFM)

Turbine Building 1 Fen (40,000 SCFM) 444+pk8+r(@@PE" Turbine Building 2 Fans (80,000 SCFM)

Standby Ges Treatment (4,000 SCFM)

Nominal SCFM 4,000 40,000 44,035 Nominal cm /sac 1.89 E6 1.89 E7 2.08 E7 80,000 3.78 E7

'W~wd&4+ss@k 84,000 2200 3.96 E7 6.61 E5 1.04 E8 F'ebruary 1997 Page124 EP IP-EPP-.08 Rev 07

ATTACHNENT 4 S

ON, Page 6 of 6 TABLE 4.3 FLOW RATES CORRESPONDING TO FAN CONFIGURATIONS FOR UNIT 2 VENT TB 250',306'econ Rm 1 Fen (3300 SCFM)

Red waste L(ner 1 Fsn (800 SCFM)

Rsd waste Red waste Building Tanks 1 Fsn 1 Fen (47,800 (4910 SCFM)

SCFM) g~~>xg~~~X@+~<p4 Rsdwsete Building 2 Fane (95,600 SCFM) 4~j~.;,":j:xg<~~Ys's!

Aux Boiler (23,000 SCFM)

>gag(y>>+

Refueling Floor Refueling Floor Above (70,000 Below (70,000 SCFM)

SCFM)

Nominal SCFM 47,800 95,600 70,800 118,600 Nominal cm /sec 2.256 E7 4.512 E7 3.341 E7 5.597 E7

'>A~'sg~ "":WAR'4~a;

'I t+tggx+p(j%j+x'~

,pp~.@%kg,>i+i'Ay.O P,:,~yyr'~x/3>>l~

235 600 8.864 E7 1.112 E8 9.948 E7 1.22 E8 k@%$~~kk&i4Y' "4910

" 800 ""

3300 2.317 E6 3.775 E5 1.557 E6 February 1997

.'-- P.age, 25 EP IP-EPP-08 Rev 07

ATTACHMENT 5 REFINED DOSE ASSESSMENT AND PROTECTIVE ACTIONS Page l of' E.M

~MENMN l.l Genera Co siderations 1.1.1 The dose assessment program is called RAOOOSE.

1. 1.2 Meteorological data is automatically sent to RADOOSE by the Heteorological Monitoring System

{MHS).

The user can use this data or manually input data.

1.1.3 Source. term and release rate determination is identical to that described in Attachment 4.

1.2 Dose ssessment Procedure E

JODY:

The dose assessment model has many capabilities beyond those used in this procedure.

Use the "EDAMS Operators Manual"

{available in the EOF) for further reference.

1.2.1 1.2.2

, 1.2.3 1.2.4 1.2.5 1.2.6 Log on to EDAMS compute

.using Attachment 2.

Select "DoEse'*.A'ssessment.Model:

RADDOSE IV" from the EDAMS main menu.

Utilize "EOAMS Data Entry Form", Figure 5.2, or equivalent.

Select the affected unit.

Select "Begin New Incident" at the "Start-UP Menu" screen.

Hit the "delete" key if prompted.

Enter the following at the Accident Scenario Definition screen:

b.

C ~

d.

e.

g,

'rip Date.

This is the date that the reactor scrammed or was manually tripped.

IF the reactor is not shut down, enter tomorrows date.

Trip Time (24-hour format).

This is the time that the reactor scrammed or was manually tripped.

Release Date.

This is the date that the release to the atmosphere

began, or is projected to begin.

Release Time (24-hour format).

This is the time that release to atmosphere began or is projected to begin.

Enter the lake temperature (deg F). If unknown, hit "Enter" and historical data will be entered.

Enter the initials of the user (two or three initials).

Hit "F9" to accept 'all entries or "Esc" Nto back-up and cor rect.

0-NM' February 1'997 Page -26

EPIP-EPP-08 Rev 07

ATTACHMENT 5 REFINED DOSE" ASSESSMENT AND PROTECTIVE ACTIONS Page 2 of 5 1.2.7 Select "Enter Source Term Data" from the EDAHS main menu.

NOTES:

1.

Use Attachment 4 to obtain the information needed to complete this section.

2.4'The preferred source of release rate data is the actual isotopic distribution, if available.

1.2.8 e

a.

Select "Accident Type" by hitting the "F2" key, and choosing the accident that most suits the current conditions.

Use Table 5. 1 in making the choice.

b.

Select "Y" for elevated releases OR "N" for ground releases when asked, "Is this release Elevated?".

'0TE:

"Elevated" releases are releases from the stack.

"Ground" releases are from any other release point.

';"-"..Select the "Hethod" used to determine the release rate

'y hitting the "F2" key and selecting..

Enter the

'"Flowrate" and "Honitor Reading" if required.

d.

Select the Iodine release rate "Hethod" by hitting the "F2" key.

Enter the "Honitor Reading" and "Release Rate" if required.

e.

Up to three Accident'Types (and therefore three release paths) can be entered.

To enter additional release

paths, repeat Steps a

d above.

When all applicable accident types have been entered, proceed to the next step.

f:-

Upon completion-'of-'this screen, hit the "F9" key to accept or "Esc" to back-up.

The user will be queried only for the meteorological data required.

Enter meteorological data as required:

a.

When queried for "Enter/Edit Heteorological Data", hit "Enter".

b.

If the HHS is available, the data will be automatically displayed for the current time step.

Hit "F9" to

accept, or

~

Hit "F4" to update the screen

~

Hit "Ins" to insert data c.

If the HHS i,s unava'ilable, enter met data obtained from alternate'sources,,

as outlined in Attachment 3.of. this

. = "."...procedure.

February 1997 Page 27

. EPIP-EPP-08 Rev 07

ATTACHMENT 5 EF NED DOSE ASSESSMENT AND PROTECTIVE ACTIONS Page 3 of 5 Select "Perform Calculations" from-the EDAHS main menu.

1.2.9 CAUTION Any calculations performed on actual data shall be verified.

The ODAM may act as the checker for calculations performed by the Rad Assessment Staff.

a.

The map of the IO mile 'Emergency Planning Zone (EPZ) will appear with centerline dose rates when the

'" 'alculation is complete.

b.

Hit any key to go to the output menu.

c.

Select "Continue Calculations" from the output'menu.

d.

Select "Perform Forecast" from the RADDOSE main menu.

e.

Verify meteorology and source term data as required.

f. 'nter "Forecast Period" (i.e. - release duration).

Use 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> as a default value.

g.

Hit the "F9" key.

After the forecast map appears hit any key to go to the output menu.

1 ~

J

~

Select "Go to Report Menu".

Select "Print Complete 10-Hile ERPA Hap".

k.

Select."Print Complete Dose/Dose Rate Report".

e.

m.

Attach results of Step 1.2.9.j and k to EDAHS Data Entry Form, Attachment 5.2 or equivalent.

Verify that any results are supported by radiological and plant conditions.

Consider:

~

Core damage

~

Drywell high range monitor readings

~

Effluent monitor readings

~

Inplant radiological conditions lh

~

Containment hydrogen monitor readings Document the verification of the calculation using the signature lines on Figure 5.2 or equivalent.

February 1997 Page 28 EPIP-EPP-08 Rev 07

hTTACHNENT 5 F

ED DOS SS SS E

AND OT CTIVE ACTIONS'EFINED PROTECTIVE ACTIONS Page 4 of 5 2.1 2.2 These actions are initiated for the purpose of verifying the adequacy of PARs made using Attachment 1 of this procedure OR to develop PARs using projected doses obtained from Attachment 5, Step 1.2.9 of this procedure.

In determining PARs based on dose assessment, carefully consider factors such as release duration and Evacuation Travel Time Estimates (ETTE).

(For example, puff releases may yield doses in excess of Protective Action Guidelines for an evacuation, but the plume will pass before an evacuation could be completed).

ETTEs are available in the EOF.

NOTE:

County and State PARs take many factors into account that NMP procedures do not (i.e. - road conditions, special population needs, evacuation scenarios, and shelter vs evacuation doses).

Therefore;,diffe'rences

.in-PARs may occur.

The ODAM must'ccount for di'ffer'ences in PARs, when those differences exist.

This can be accomplished via consultation with County and State representatives in the EOF as to the assumptions used in their dose calculations and PAR development.

Obtain dose projection for each ERPA.

2.3.1 2.3.2 PARs are listed on the 10 mile ERPA map obtained per, Step 1.2.9. j.

The following criteria are used in determining the PAR for each ERPA.

PAR Evacuate TEDE rem CDE rem 2.3.3 2.3.4 Record the PAR for each ERPA on the Part 1 Notification Form and give to the CED for approval.

PARs that have been made previously must be accounted for when PARs're revised.

For example, if a PAR to evacuate an ERPA was previously made to the State/County and that PAR does not appear on a revised map from 1.2.9.j, that PAR must still be included on the revised recommendation to the State/County.

February 1997 Page 29 EP IP-EPP-08 Rev 07

ATTACHNENT 5 ED OOS ASS SSNENT. AND RO C IVE ACTIONS TABLE 5.1 - FSAR/USAR ACCIDENT TYPE Page 5 o+ 5

'Y::.".,".,.:!::i'.":;.': 'Ace)dent'Type

'".:.'..',,,'.".";. 'ReleaseRate"(Ci/s}

Unit 1:

lodine;,",,-...,

"ReIeas'e'Rate'(C(1s};,

.,

, Analyzed

',;'~,Re(ease'Point ';;

DBA Loss of Coolant Control Rod Drop Refueling Accident Steam Line Break Loss of Coolant (Realistic)

Unit 2:

1.84 E-1 1.17 E+1 3.79 E-2 1.1 E-1 1.53 E-3 2.08 E-6 5.12 E-5 3.78 E-5 5.38 E+1 8.31 E-7 Elevated Elevated Elevated Ground Elevated DBA Loss of Coolant Control Rod Drop Refueling Accident Steam Line Break Rad Gas Waste System Leak Instrument Line Failure Fuel Cask Drop Loss of Coolant (Realistic) 4.48 E-1 2.50 E-1 1.45 E 0 3.29 E 0 3.47 E 0 0.00 7.14 E-3 3.47 E 0 3.04 E-4 1.10 E-6 1A3 E-2 1.52 E+2 0.00 2.15 E-2 3,88 E-6 0.00 Elevated Ground Ground Ground Ground Ground Ground Elevated February 1997 Page'0 EP IP-EPP-08 Rev 07

FIGU'. 1 CHRONO 06 CAL ASE 06 ate:

I

(

+\\ '

ease orm; urvey ocauon:

omp et y:

Effluent Monitor Date Environmental Sampling Data Release Log Time of Monito Reedin Monitoi System Release Rate (Ci/sec)

Duration of Release N

ak tCC

+CC, y't:

Survey Time Location Gemma Dose Rate (mR/hr)

Ct Distance

", (Mi)

Wind Speed (mph) 0 ~ ~

Transit Time (min)

~ ~ ~ ~

Est. Time of Release from Site Release Rate (Ci/sec) I ig'>>

4

I C'

Assigned Release Rate (Ci/sec)

Assigned Time Interval 5

C>C CtC Notes:

Transit Time (min) ~ (Distance/Wind Speed) x 60 min/hr Est. Time of Release

~ Survey Time - Transit Time February 1997 Page 31 EP IP-EPP-08 Rev 07

FIGURE 5.2 EDANS DATA ENTR FORM D

"What lf" D

Actual Data (Checker Requiredl)

Rx Trip: Date:

D Unit 1 D

A Time:

Unit 2 I

P I

n Release:

Release Duration (Hr):

Containment DBA Control Rod Drop Refueling Accident Steam Line Break Loss of Coolant Rad Gas Waste System Inst. Line Failure, Fuel Cask Drop Severe Accident Elev/Grd Elev/Grd Elev/Grd Elev/Grd Elev/Grd Elev/Grd Elev/Grd Elev/Grd Elev/Grd.

Flow Rate Method Monitor Reading iodine Method

,.:. iodine Monitor....

Met Data:

D Automatic D Manual /Below)

Lake Temp F or Default Wind Speed (mi/hr)

Wind Direction (from - degrees)

Stability (A-G) emperature

( F)

Precipitation (in/15 min)

Elevated round Attach:

Misc:

~

Map from color printer "Complete Dose/Dose Rate" report Calculations Performed By:-

Calculations Verified By:

February 1997 Page 32 EP IP-EPP-08 Rev 07