ML18017A288
| ML18017A288 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/28/1996 |
| From: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18017A215 | List: |
| References | |
| PLA-4474, NUDOCS 9607050280 | |
| Download: ML18017A288 (191) | |
Text
CATEGORY' 1
e REGULATORY INFORMATION DZSTRlBUTION STEM (RIDE)
ACCESSION NBR:9607050280 DOC.DATE: 96/06/28 NOTARIZED: NO DOCKET I FACIL:50-387 Susquehanna Steam Electric Station, Unit 1, Pennsylva 05000387 50-388 Susquehanna Steam Electric Station, Unit 2, Pennsylva 05000388 AUTH. NAME AUTHOR AFFILIATION BYRAM,R.G. pennsylvania Power S Light Co. /7g"Q. 7g~g@
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards Rev 24 to "SSES Emergency Plan," incorporating changes associated w/EOF move (approved by NRC staff),
organizational a administrative changes. A DISTRIBUTION CODE: A045D COPIES RECEIVED:LTR f ENCL 2 TITLE: OR Submittal: Emergency Preparedness Plans, Implement'g Procedures, SIZE: AI(8 C T
E NOTES: 05000387 G
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-2 PD 1 1' POSLUSNY,C 1 1 INTERNAL~CFILE CE TER UE 2 NRR/DRPM/PERB 1 1 NUDOCS-ABSTRACT 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 NOTES: 1 1 D
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N NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5 (EXTi 415-2085) TO ELIMINATE YOUR NAME FROM DISTRIBUTION L1STS FOR DOCUMENTS YOU DON'T NEEDt TOTAL NUMBER OF COPIES REQUIRED: LTTR .9' ENCL 9
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Pennsylvania Power 8 Light Company Two North Ninth Street ~ Allentown, PA 18101-1179 ~ 610/774-5151 Robert G. Byram Sen/or Vlcc President-Nuclear 610/774-7502 Fax: 610/774-5019 JUN 20 1996 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION NOTIFICATIONOF TRANSFER OF EMERGENCY FUNCTIONS TO THE NEW EMERGENCY OP~TIONS FACILITYIN WILKES-BARRE Docket Nos. 50-387 and 50-388 Pennsylvania Power 2, Light Company will be implementing the move of its Emergency Operations Facility (EOF) from directly west of the plant on Confers Lane to the East Mountain Business, Center off Exit 47A of Interstate 81 near Wilkes-Barre. The implementation will take place on July 1, 1996. Attached is Revision No. 24 to the Emergency Plan for Susquehanna SES Units 1 and 2 which incorporates the changes associated with the EOF move (approved by the NRC staff) and other organizational and administrative changes that do not decrease the effectiveness of the Emergency Plan.
The only noticeable effect will be to those offsite agencies who would report to the new EOF location during an emergency. For all others the change will be unnoticeable. Phone numbers will be transferred and remain the same.
Ifyou have any comments or questions, please contact Ms. Cynthia A. Smith at (717) 542-3233.
Very truly yours, R. G yr Attachment g0 9607050280 960628 PDR ADOCK 05000387 F PDR
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FILE R41-2 PLA-4474 Document Control Desk copy:NRC Region I Ms. M. Banerjee NRC Sr. Resident Inspector-SSES Mr. R. Keimig Section Chief-Region I Mr. C. Poslusny, Jr. NRC Sr. Project Manager-OWFN Mr. J. Syracuse Luzerne County Emergency Management Ms. I. Miller Columbia County Department of Emergency Services Mr. C. Wynne PEMA
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'* P '.c'A * ~ C THIS DOCUMENT HAS BEEN UPDATED TO INCLUDE REVISIONS THROUGH 22 DATED 04/95 .
I SUSQUEHANNA STEAM ELECTRIC STATION
'"- EMERGENCY PLAN'.
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"..";,;:," 'LlST. OF 'EFFECTIVE"PA'GES:;-:: ' ,--- .'
This': list';of 'effective::pa'ges:,'is':: provided for'he convenien'ce.'f rthe'-'end users'f..'th' Susqueharina: SES Emergency Plan';-'" It'is'eprinted: in'.Its:entirety';and', distiibuted"with each',revision;-.:.,';.....,-'.: ..:.,
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-; ',:,;;~7::-i'::i'. ".'."':."-',:<.':..:',;..'; ",: . i::,'.' REVISION Title 22 04/95 Table of Contents i 22 04/95 22 04/95 22 04/95 SECTION 1.0 - DEFINITIONS 22 04/95 1-2 22 04/95 1-3 22 04/95 22 04/95 1-5 22 04/95 SECTION 2.0 - ACRONYMS 2-1 22 04/95 2-2 22 04/95 SECTION 3.0- REFERENCES 22 04/95 SECTION 4.0 - SCOPE AND CONTENTS 4-1 22 04/95 4-2 22 04/95 Fi ure4.1 10/88 Fi ure4.2 10/88 SECTION 5.0 - EMERGENCY CONDITIONS 21 04/94 21 04/94 21 04/94 21 04/94 21 04/94 21 04/94 Table5.1 a e1 22 04/95 Table5.1 a e2 22 04/95 Table5.1 a e3 22 04/95 Table5.1 a e4 22 04/95 Table 5.1, a e5 22 04/95 Table5.1 a e6 22 04/95 Table 5.1 a e7 22 04/95 Table 5.1 a e 8 22 04/95 Table 5.1 a e 9 22 04/95 Rev. 22, 04/95 LEP-1
PAGE REVISION DATED Table 5.1, a e10 22 04/95 Table 5.1, a e11 22 04/95 Table 5.1, a e12 22 04/95 Table 5.1 8 B13 22 04/95 Table 5.1 a e14 22 04/95 Table 5.1, a e15 22 04/95 Table 5.1 e16 22 04/95 Table 5.1 a e17 22 04/95 Table 5.1 a e18 22 04/95 Table 5.1, a e19 22 04/95 Table 5.1 e20 22 04/95 Table 5.1, a e21 22 04/95 Table 5.1 8 B22 22 04/95 Table 5.1 B 23 22 04/95 Table 5.1 a e24 22 04/95 Table 5.1 a e25 22 04/95 Table 5.1, e26 22 04/95 Table 5.1 8 B27 22 04/95 Table 5.1 a e28 22 04/95 Table 5.1 a e29 22 04/95 Table 5.1, a e30 22 04/95 Table 5.1 8 B31 22 04/95 Table 5.1 8 B32 22 04/95 Table 5.1, 8 B33 22 04/95 Table 5.2, B1 22 04/95 Table 5.2, ae2 22 04/95 Table 5.2, B3 22 04/95 Table 5.2 e4 22 04/95 Table 5.2 e5 22 04/95 Table 5.2 e6 22 04/95 Table 5.2 a e7 22 04/95 SECTION 6.0 - ORGANIZATIONALCONTROL OF EME RGEN CIES 22 04/95 22 04/95 22 04/95 22 04/95 22 04/95 22 04/95 22 04/95 22 04/95 22 04/95 6-10 22 04/95 6-11 22 04/95 6-12 22 04/95 Rev. 22, 04/95 LEP-2 l
PAGE'-., , . REVISION DATED 6-13 22 04/95 6-14 22 04/95 6-15 22 04/95 6-16 22 04/95 6-17 22 04/95 6-18 22 04/95 6-19 22 04/95 Table 6.1 a e 1 22 04/95 Table6.1, a e2 22 04/95 Table6.2, a e1 22 04/95 Table6.2, a e2 22 04/95 Table6.2, a e3 22 04/95 Table6.2 a e4 22 04/95 Table B.3, a e 1 15 01/92 Fi ure 6.1 22 04/95 Fi ure 6.2a 18 05/93 Fi ure 6.2b 1B 01/93 Fi ure 6.3 22 04/95 Fi ure6.4 19 11/93 Fi ure 6.5 21 04/94 Fi ure 6.6 10/88 Fi ure 6.7 15 01/92 SECTION 7.0 - EMERGENCY MEASURES 7-1 22 04/95 7-2 22 04/95 7-3 22 04/95 7-4 22 04/95 7-5 22 04/95 22 04/95 7-7 22 04/95 Table 7.1 a e1 18 05/93 Table7.1 a e2 18 05/93 Table7.2 a e1 22 04/95 Table 7.2 a e2 22 04/95 Table 7.2 a e3 22 04/95 Table 7.3 a e1 20 12/93 Table7.3 a e2 20 12/93 Table 7.3, a e3 20 12/93 Table 7.3, a e4 20 12/93 SECTION 8.0- EMERGENCY FACILITIES AND EQUIPMENT 22 04/95 22 04/95 22 04/95 22 04/95 22 04/95 22 04/95 Rev. 22, 04/95 LEP-3
PAGE 'REVISION DATED 8-7 22 04/95 8-8 22 04/95 8-9 22 04/95 8-10 22 04/95 8-11 22 04/95 8-12 22 04/95 8-13 22 04/95 8-14 22 04/95 8-15 22 04/95 8-16 22 04/95 8-17 22 04/95 8-18 22 04/95 8-19 -22 04/95 Table 8.1, a e1 17 03/93 Fi ure 8.1 10/88 Fi ure 8.2 10/88 Fi ure 8.3 10/88 Fi ure 8.4 10/88 Fi ure 8.5 10/88 Fi ure 8.6 10/88 SECTION 9.0 - MAINTENANCEEMERGENCY PREPAREDNE SS 22 04/95 22 04/95 22 04/95 22 04/95 22 04/95 Table9.1, a e1 22 04/95 Table9.1 a e2 22 04/95 APPENDIX A - LETTERS OF AGREEMENT A-1 22 04/95 A-2 22 04/95 A-3 22 04/95 APPENDIX B - WIND ROSES AND DOSE/DISTANCE PLOTS 15 01/92 B-2 15 01/92 15 01/92 Fi ure B.1 10/88 Fi ure B.2 10/88 Fi ure B.3 10/88 Fi ure B.4 10/88 Fi ure B.5 10/88 Fi ure B.6 10/88 Fi ure B.7 10/88 APPENDIX C - SSES EMERGENCY PLAN POSITION SPECIFIC PROCEDURES TYPICAL 22 04/95 Rev. 22, 04/95 LEP-4
PAGE.'- -. REVISION-. DATED C-2 22 04/95 C-3 22 04/95 APPENDIX D - EQUIPMENT INFORMATION LISTINGS D-1 21 04/94 21 04/94 21 04/94 21 04/94 21 04/94 21 04/94 21 04/94 21 04/94 21 04/94 D-10 21 04/94 D-11 21 04/94 D-12 21 04/94 D-13 21 04/94 D-14 21 04/94 D-15 21 04/94 D-1B 21 04/94 D-17 21 04/94 APPENDIX E - CORPORATE POLICY STATEMENT E-1 21 04/94 Corporate Policy Statement, 21 04/94 letter dated 04/01/94 APPENDIX F - NUREG 0654 INITIATINGCONDITIONS NOT INCLUDED ON TABLE 5.1 F-1 18 05/93 F-2 18 05/93 F-3 18 05/93 APPENDIX G - SSES EVACUATIONTIME ESTIMATES G-1 15 01/92 Evacuation Time Estimates, cover page 10/88 Re ort Dated 08/81 Evacuation Time Estimates, title page 10/88 Re ort Dated 08/81 TOC 10/88 10/88 1-2 10/88 1-3 10/88 10/88 1-5 10/88 10/88 2-1 10/88 2-2 10/88 2-3 10/88 10/88 Rev. 22, 04/95 LEP-5
PAGE:,. REVtSION DATED 10/88
'-5 10/88 2-7 10/88 2-8 10/88 2-9 10/88 2-10 10/88 2-11 10/88 2-12 10/88 2-13 10/88 2-14 10/88 2-15 10/88 2-16 10/88 10/88 10/88 10/88 10/88 10/88 10/88 10/88 10/88 3-9 10/88 3-10 10/88 3-11 10/88 3-12 10/88 3-13 10/88 10/88 3-15 10/88 4-1 10/88 4-2 10/88 10/88 10/88 10/88 10/88 10/88 10/88 10/88 10/88 10/88 10/88 10/88 10/88 10/88 10/88 5-10 10/88 5-11 10/88 Rev. 22, 04/95 LEP-6
PAGE'."'::. ::. REVISION =
DATED
'-12 10/88 5-13 10/88 5-14 10/88 5-15 10/88 5-16 10/88 10/88 6-2 10/88 6-3 10/88 10/88 10/88 10/88 10/88 10/88 10/88 6-10 10/88 A endixA Descri tion of Netvac title a e 10/88 Re ort a es:
10/88 A-2 10/88 A-3 10/88 10/88 A-5 10/88 Appendix B, Roadway'Network and Capacities 10/88 title a e Re ort a es:
10/88 10/88 10/88 APPENDIX H - DOWNSTREAM SUSQUEHANNA RIVER WATER USAGE H-1 15 01/92 H-2 15 01/92 H-3 15 01/92 H-4 15 01/92 APPENDIX I - POPULATION UPDATE FOR SSES EMERGE NCY PLANNING ZONE 15 01/92 Population Update for SSES EPZ, cover page 10/88 Re ort Dated 07/82 Population Update for SSES EPZ, title page 10/88 Re ort Dated 07/82 Re ort a es Re ort Dated 07/82:
TOC 10/88 10/88 1-2 10/88 1-3 10/88 10/88 Rev. 22, 04/95 LEP-7
PAGE::- ,:, REVISION DATED 2-1 10/88 2-2 10/88 2-3 10/88 10/88 2-5 10/88 10/88 2-7 10/88 2-8 10/88 2-9 10/88 2-10 10/88 10/88 22 04/95 22 04/95 10/88 10/88 APPENDIX J - NUREG-0654 PLANNING STANDARD AND EVALUATIONCRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN 15 01/92 J-2 15 01/92 J-3 15 01/92 15 01/92 J-5 15 01/92 15 01/92 J-7 15 01/92 J-8 15 01/92 J-9 15 01/92 J-10 15 01/92 15 01/92 J-12 15 01/92 J-13 15 01/92 Rev. 22, 04/95 LEP-8
, .;.'. -.,""..;:.,',TA'BLE'OF'CONTENTS,".:.,:::.,-'::;=:-.'.'~'.::,...;...,
SECTION TITLE PAGE 1.0 DEFINITIONS 2.0 ACRONYMS 2-1
3.0 REFERENCES
4.0 SCOPE AND CONTENTS 4.1 SCOPE 4-1 4.2 CONTENTS 4-1 5.0 EMERGENCY CONDITIONS 5.1 CLASSIFICATION SYSTEM 5-1 5.2 SPECTRUM OF POSTULATED ACCIDENTS 5-3 6.0 ORGANIZATIONALCONTROL OF EMERGENCIES 6.1 NORMALOPERATING ORGANIZATION 6-3 6.2 ON-SITE EMERGENCY ORGANIZATION- HASE I 6-3 6.3 OFF-SITE RESOURCES AND ACTIVITIES- HASE II 6-9 6.4 COORDINATION WITH PARTICIPATING GOVERNMENT AGENCIES 6-14 6.5 RESTORATION 6-18 7.0 EMERGENCY MEASURES 7-1 7.1 ASSESSMENT ACTIONS FOR ALLEMERGENCY CLASSIFICATIONS 7-1 7.2 CORRECTIVE ACTIONS 7.3 PROTECTIVE ACTIONS 7.4 AID TO AFFECTED PERSONNEL 7-7 8.0 EMERGENCY FACILITIES AND E UIPMENT 8.1 ON-SITE EMERGENCY CENTERS 8-1 8.2 PP8tL OFF-SITE EMERGENCY CENTERS 8.3 COUNTY AND STATE EMERGENCY CENTERS 8-12 8.4 ASSESSMENT FACILITIES 8-13 8.5 PROTECTIVE FACILITIES 8-13 8.6 ADDITIONALCOMMUNICATIONSSYSTEMS 8-15 8.7 ON-SITE FIRST AID AND MEDICALFACILITIES 8-15 8.8 DAMAGE CONTROL E UIPMENT 8-15 8.9 INFORMATIONSYSTEMS 8-15 9.0 MAINTAININGEMERGENCY PREPAREDNESS 9-1 9.1 ORGANIZATIONALPREPAREDNESS 9-1 9.2 REVIEW AND UPDATING 9-3 9.3 MAINTENANCEAND INVENTORYOF EMERGENCY EQUIPMENT/
SUPPLIES 9.4 PUBLIC EDUCATION AND INFORMATION 10.0 APPENDICES A LETTERS OF AGREEMENT B WIND ROSES AND DOSE/DISTANCE PLOTS SSES EMERGENCY PLAN POSITION SPECIFIC PROCEDURES ICAL D E UIPMENT INFORMATIONLISTINGS E CORPORATE POLICY STATEMENT F NUREG 0654 INITIATINGCONDITIONS NOT INCLUDED ON TABLE 5.1 G SSES EVACUATIONTIME ESTIMATES H DOWNSTREAM SUS UEHANNARIVER WATER USAGE I POPULATION UPDATE FOR SSES EMERGENCY PLANNINGZONE J NUREG4654 PLANNING STANDARD AND EVALUATIONCRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN Rev. 22, 04/95
".'."'::i.'LISTING'OF'TA'BLES'.'.1 TABLE TITLE CLASSIFICATIONOF EMERGENCY CONDITIONS 5.2 EMERGENCY ACTIONS BASED ON CLASSIFICATION 6.1 TYPICAL STATION PERSONNEL EMERGENCY ACTIVITYASSIGNMENTS 6.2 MINIMUMON-SITE AND OFF-SITE EMERGENCY ORGANIZATIONCAPABILITIES 6.3 ADDITIONALASSISTANCE FROM OUTSIDE PP8Q 7.1
SUMMARY
OF IMMEDIATENOTIFICATIONAND RESPONSE FOR ALL CLASSIFICATIONS 7.2 EMERGENCY EXPOSURE CRITERIA 7.3 PROTECTIVE ACTION RECOMMENDATIONS 8.1 RELATIONSHIP OF THE PRIMARY PARAMETER, SECONDARY DISPLAY, AND ALGORITHMS ON SPDS 9.1 TRAININGOF SUS UEHANNASES EMERGENCY RESPONSE PERSONNEL Rev. 22, 04/95
- ,;,LISTING OF FIGURES
- .'.1 FIGURE TITLE MAP OF THE SSES VICINITY 4.2 MAP OF SSES 50 MLE INGESTION EXPOSURE ZONE 6.1 SUS UEHANNA SES ORGANIZATION 6.2a EOF ORGANIZATION One Hour Activation 6.2b EOF ORGANIZATION ull Staffed 6.3 TSC ORGANIZATION 6.4 MOC ORGANIZATION 6.5 GENERAL OFFICE EMERGENCY ORGANIZATION 6.6 LONG TERM RESTORATION ORGANIZATION 6.7 COMMUNICATIONSINTERFACE WITH OFF-SITE AGENCIES 8.1 MAP OF THE SUS UEHANNASES EMERGENCY FACILITIES 8.2 TECHNICALSUPPORT CENTER FLOOR PLAN 8.3 EMERGENCY OPERATIONS FACILITYFLOOR PLAN 8.4 LOCATIONOF BACKUP EMERGENCY OPERATIONS FACILITY 8.5 SPDS/PCS DATASYSTEMS 8.6 SIREN LOCATION Rev. 22, 04/95
SUSQUEHANNA STEAM ELECTRlC STATlON EMERGENCY PLAN LlS T OF EFFECTlVE PAGES This list of effective pages is provided for the convenience of the end users of the Susquehanna SES Emergency Plan. It is reprinted in.its entirety and distributed with each revision.
PAGE -
REVISION DATED Title 24 06/96 Table of Contents i 24 06/96 24 06/96 24 06/96 SECTION 1.0 - DEFINITIONS 24 06/96 1-2 24 06/96 1-3 24 06I96 24 06/96 1-5 24 06/96 SECTION 2.0 - ACRONYIIS 2-1 06/96 2-2 24 06/96 SECTION
3.0 REFERENCES
3-1 24 06/96 SECTION 4.0 SCOPE AND CONTENTS 4-1 24 06/96 4-2 24 06/96 Figure 4.1 10/88 Figure 4.2 10/88 SECTION 5,0 EIIERGENCY CONDITIONS 5-1 21 04/94 5-2 21 04/94 5-3 21 04/94 21 04/94 5-5 21 04/94 5-6 21 04/94 Table 5.1, page 1 22 04/95 Table 5.1, page 2 22 04/95 Table 5.1, page 3 22 04/95 Table 5.1, page 4 22 04/95 Table 5.1, page 5 22 04/95 Table 5.1, page 6 22 04/95 Table 5.1, page 7 22 04/95 Table 5.1, page 8 22 04/95 Table 5.1, page 9 22 04/95 Rev. 24, 06/96 'EP-1
PAGE REVISION 'ATED 5.1,
'able page 10 22 04/95 Table 5.1, page 11 22 04/95 Table 5.1; page 12 22 04/95 Table 5.1, page 13 22 04/95 Table 5.1, page 14 22 04/95 Table 5.1, page 15 22 04/95 Table 5.1, page 16 22 04/95 Table 5.1, page 17 04/95 Table 5.1, page 18 22 04/95 Table 5.1, page 19 '22 04/95 Table 5.1, page 20 22 04/95 Table 5.1, page 21 22 04/95 Table 5.1, page 22 22 04/95 Table 5.1, page 23 22 04/95 Table 5.1, page 24 22 04/95 Table 5.1, page 25 04/95 Table 5.1, page 26 22 04/95 Table 5.1, page 2? 22 04/95 Table 5.1, page 28 22 04/95 Table 5.1, page 29 22 04/95 Table 5.1, page 30 22 04/95 Table 5.1, page 31 22 04/95 Table 5.1, page 32 22 04/95 Table 5.1, page 33 22 04/95 Table 5.2, page 1 22 04/95 Table 5.2, page 2 22 04/95 Table 5.2, page 3 22 04/95 Table 5.2, page 4 04/95 Table 5.2, page 5 22 04/95 Table 5.2, page 6 22 04/95 Table'5.2, page 7 22 04/95 SECTION -
6.0 ORGANIZATIONALCONTROL OF ENIERGENCIES 6-1 24 06/96 6-2 24 06/96 6-3 06/96 24 06/96 6-5 24 06/96 6-6 24 06/96 6-7 06/96 6-8 24 06/96 6-9 24 06/96 6-10 24 06/96 6-11 24 06/96 6-12 24 06/96 Rev. 24, 06/96 LEP-2
I PAGE REVISION DATED 6-13 24 06/96 6-14 24 06/96 6-15 06/96 6-16 24 06/96 6-17 24 06/96 Table 6.1, page 1 04/95 Table 6.1, page 2 22 04/95 Table 6.2, page 1 24 06/96 Table 6.2, page 2 24 06/96 Table 6.2, page 3 24 06/96 Table 6.2, page 4 24 06/96 Table 6.3, page 1 24 06/96 Figure 6.1 24 06/96 Figure 6.2 24 06/96 Figure 6.3 22 04/95 Figure 6.6 06/96 Figure 6.7 06/96 SECTION 7.0 - EMERGENCY MEASURES 7-1 24 06/96 7-2 24 06/96 7-3 24 06/96 24 06/96 7-5 24 06/96 7-6 24 06/96 7-7 24 06/96 7-8 24 06/96 Table 7.1, page 1 24 06/96 Table 7.1, page 2 24 06/96 Table 7.2, page 1 22 04/95 Table 7.2, page 2 22 04/95 Table?.2, page 3 22 04/95 Table 7.3, page 1 20 12/93 Table 7.3, page 2 12/93 Table 7.3, page 3 20 12/93 Table 7.3, page 4 20 12/93 SECTION 8.0 - EMERGENCY FACILITIES AND EQUIPMENT 8-1 24 06/96 8-2 24 06/96 8-3 24 06/96 24 06/96 8-5 24 06/96 8-6 06/96 Rev. 24, 06/96 LEP-3
PAGE-'EVISION 8-7 24 DATED 06/96 8-8 24 06I96 8-9 06/96 8-10 24 06/96 8-11 24 '06/96 8-12 24 06/96 8-13 24 06/96 8-14 24 06/96 8-15 24 06/96 8-16 24 06/96 8-17 24 06/96 8-18 06/96 8-19 24 06/96 8-20 24 06/96 Table 8.1, page 1 17 03/93 Figure 8.1 24 06/96 Figure 8.2 12 10/95 Figure 8.3 24 06/96 Figure 8.4 10/88 Figure 8.5 10/88 Figure 8.6 10/88 SECTION 9.0 - MAINTENANCEEMERGENCY PREPAREDNESS 9-1 06/96 9-2 24 06/96 9-3 24 06I96 24 06/96 9-5 24 06/96 Table 9.1, page 1 22 04/95 Table 9.1, page 2 22 04/95 APPENDIX A - LETTERS OF AGREEMENT 24 06/96 A-2 24 06/96 A-3 24 06/96 APPENDIX 8 - WIND ROSES AND DOSE/DISTANCE PLOTS 8-1 15 01I92 8-2 15 01/92 8-3 15 01/92 Figure 8.1 10/88 Figure 8.2 10/88 Figure 8.3 10/88 Figure 8.4 10/88 Figure 8.5 10/88 Figure 8.6 10/88 Figure 8.7 10/88 Rev. 24, 06/96 LEP-4
PAGE REVISION DATED APPENDIX C - SSES EMERGENCY PLAN POSITION SPECIFIC PROCEDURES (TYPICAL)
C-1 24 06/96 C-2 24 06/96 APPENDIX D EQUIPMENT INFORMATION LISTINGS D-1 24 06/96 D-2 24 06/96 D-3 24 06I96 DA 06/96 D-5 24 06I96 D-6 24 06/96 D-7 24 06/96 D-8 24 06/96 D-9 24 06/96 D-10 24 06/96 D-11 24 06/96 D-12 24 06/96 D-13 24 06/96 D-14 24 06/96 D-15 24 06/96 D-16 24 06/96 APPENDIX E - CORPORATE POLICY STATEMENT E-1 21 04/94 Corporate Policy Statement, 21 04/94 (letter dated 04/01/94)
APPENDIX F - NUREG 0654 INITIATINGCONDITIONS NOT INCLUDED ON TABLE 5.1 F-1 18 05/93 F-2 18 05/93 F-3 18 05/93 APPENDIX G - SSES EVACUATIONTIME ESTIMATES G-1 15 01/92 Evacuation Time Estimates, cover page 10/88 (Report Dated 08/81)
Evacuation Time Estimates, title page 10/88 (Report Dated 08/81)
TOC 10/88 10I88 1-2 10/88 1-3 10/88 10/88 1-5 10/88 1-6 10/88 2-1 10/88 2-2 10/88 Rev. 24, 06/96 LEP-5
PAGE REVlSlON DATED 2-3 10188 10/88 2-5 10/88 2-6 10/88 2-7 10/88 2-8 10/88 2-9 10/88 2-10 10/88 2-11 10/88 2-12 10/88 2-13 10/88 2-14 10/88 2-15 10/88 2-16 10188 3-1 10/88 3-2 10/88 3-3 10/88 3-4 10/88 3-5 10/88 3-6 10/88 3-7 10/88 3-8 10/88 3-9 10/88 3-10 10/88 3-11 10188 3-12 10/88 3-13 10/88 3-14 10/88 3-15 10/88 4-1 10/88 4-2 10/88 4-3 10/88 10/88 4-5 10/88 4-6 10188 4-7 10/88 5-1 10/88 5-2 10/88 5-3 10/88 10/88 5-5 10/88 5-6 10/88 5-7 10/88 5-8 10/88 5-9 10/88 Reu. 24, 06/96 LEP-6
PAGE, REVISION DATED 5-10 10I88 5-11 10/88 5-12 10/88 5-13 10/88 5-14 10/88 5-15 10/88 5-16 10/88 6-1 10/88 6-2 10/88 6-3 10/88 10/88 6-5 10/88 6-6 10/88 6-7 10/88 6-8 10/88 6-9 10/88 6-10 10/88 Appendix A Description of Netvac title page 10/88 Report pages:
A-1 10/88 A-2 10/88 A-3 10/88 10/88 A-5 10/88 Appendix B, Roadway Network and Capacities 10/88 title page Report pages:
10/88 10/88 10/88 APPENDIX H - DOWNSTREAM SUSQUEHANNA RIVER WATER USAGE H-1 15 01/92 H-2 15 01I92 H-3 15 01/92 HQ 15 01/92 APPENDIX I - POPULATION UPDATE FOR SSES EMERGENCY PLANNING 2ONE 01/92 Population Update for SSES EPZ, cover page 10/88 (Report Dated 07/82)
Population Update for SSES EPZ, title page 10I88 (Report Dated 07/82)
Report pages (Report Dated 07/82):
TOC 10/88 10/88 1-2 10/88 1-3 10/88 Rev. 24, 06/96 LEP-7
PAGE 'EVISION DATED 10/88 2-1 10/88 2-2 10/88 2-3 10/88 2-4 10/88 2-5 10/88 2-6 10/88 2-7 10I88 2-8 10/88 2-9 10/88 2-10 10/88 3-1 10/88 3-2 22 04/95 3-3 22 04/95 10/88 3-5 10/88 APPENDIX J - NUREG-0654 PLANNING STANDARD AND EVALUATION CRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN 24 06/96 J-2 24 06/96 J-3 24 06/96 J-4 24 06/96 J-5 24 06I96 J-6 24 06/96 J-7 24 06/96 J-8 24 06/96 J-9 24 06/96 J-10 24 06/96 24 . 06/96 J-12 24 06/96 J-13 24 06/96 Rev. 24, 06/96 'EP-8
-, TABLE OF CONTENTS SECTION TITLE PAGE "1.0 DEFINITIONS 2.0 ACRONYMS 2-1
3.0 REFERENCES
3-1 4.0 SCOPE AND CONTENTS 4-1 4.1 SCOPE 4-1 4.2 CONTENTS 4-1 5.0 EMERGENCY CONDITIONS 5-1 5.1 CLASSIFICATION SYSTEM 5-1 5.2 SPECTRUM OF POSTULATED ACCIDENTS 5-3 6.0 ORGANIZATIONALCONTROL OF EMERGENCIES 6-1 6.1 NORMAL OPERATING ORGANIZATION 6-3 6.2 ON-SITE EMERGENCY ORGAN IZATION- (PHASE II) 6-3 OFF-SITE RESOURCES AND ACTIVITIES- (PHASE III) 6-9 6.4 COORDINATION WITH PARTICIPATING GOVERNMENT AGENCIES 6-13 6.5 RESTORATION 6-16 7.0 EMERGENCY MEASURES 7-1 7.1 ASSESSMENT ACTIONS FOR ALLEMERGENCY CLASSIFICATIONS 7-1 CORRECTIVE ACTIONS 7-4 7.3 PROTECTIVE ACTIONS 7-4 7.4 AID TO AFFECTED PERSONNEL 8.0 EMERGENCY FACILITIES AND EQUIPMENT 8-1 8.1 ON-SITE EMERGENCY CENTERS 8-1 8.2 PP&L OFF-SITE EMERGENCY CENTERS 8-6 8.3 COUNTY AND STATE EMERGENCY CENTERS 8-12 ASSESSMENT FACILITIES 8-13 8.5 PROTECTIVE FACILITIES 8-13 8.6 ADDITIONALCOMMUNICATIONSSYSTEMS 8-15 ON-SITE FIRST AID AND MEDICALFACILITIES 8-15 8.8 DAMAGECONTROL EQUIPMENT 8-15 8.9 INFORMATIONSYSTEMS 8-15 9.0 MAINTAININGEMERGENCY PREPAREDNESS 9-1 9.1 ORGANIZATIONALPREPAREDNESS 9-1 REVIEW AND UPDATING 9-3 9.3 MAINTENANCEAND INVENTORY OF EMERGENCY EQUIPMENT/ 9-4 SUPPLIES 9.4 PUBLIC EDUCATION AND INFORMATION 9-4 10.0 APPENDICES A LETTERS OF AGREEMENT B WIND ROSES AND DOSE/DISTANCE PLOTS SSES EMERGENCY PLAN POSITION SPECIFIC PROCEDURES (TYPICAL)
D EQUIPMENT INFORMATIONLISTINGS CORPORATE POLICY STATEMENT NUREG 0654 INITIATINGCONDITIONS NOT INCLUDED ON TABLE 5.1 SSES EVACUATIONTIME ESTIMATES DOWNSTREAM SUSQUEHANNA RIVER WATER USAGE I POPULATION UPDATE FOR SSES EMERGENCY PLANNING ZONE NUREG-0654 PLANNING STANDARD AND EVALUATIONCRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN Rev. 24, 06/96
LISTING OF TABLES ..
TABLE TITLE 5.1 CLASSIFICATIONOFEMERGENCY CONDITIONS 5.2 EMERGENCY ACTIONS BASED ON CLASSIFICATION TYPICAL STATION PERSONNEL EMERGENCY ACTIVITYASSIGNMENTS 6.2 MINIMUMON-SITE AND OFF-SITE EMERGENCY ORGANIZATIONCAPABILITIES 6.3 ADDITIONALASSISTANCE FROM OUTSIDE PP&L 7.1
SUMMARY
OF IMMEDIATENOTIFICATIONAND RESPONSE FOR ALL CLASSIFICATIONS 7.2 EMERGENCY EXPOSURE CRITERIA PROTECTIVE ACTION RECOMMENDATIONS 8.1 RELATIONSHIP OF THE PRIMARY PARAMETER, SECONDARY DISPLAY, AND ALGORITHMS ON SPDS 9.1 TRAINING OF SUSQUEHANNA SES EMERGENCY RESPONSE PERSONNEL Rev. 24, 06/96
LISTING OF FIGURES FIGURE TITLE 4.1 MAP OF THE SSES VICINITY 4.2 MAP OF SSES 50 MILE INGESTION EXPOSURE ZONE 6.1 SUSQUEHANNA SES ORGANIZATION 6.2 EOF ORGANIZATION TSC ORGANIZATION 6.6 LONG TERM RESTORATION ORGANIZATION COMMUNICATIONSINTERFACE WITH OFF-SITE AGENCIES 8.1 MAP OF THE SUSQUEHANNA SES EMERGENCY FACILITIES 8.2 TECHNICAL SUPPORT CENTER FLOOR PLAN 8.3 EMERGENCY OPERATIONS FACILITYFLOOR PLAN 8.4 LOCATION OF BACKUP EMERGENCY OPERATIONS FACILITY 8.5 SPDS/PCS DATA SYSTEMS 8.6 SIREN LOCATION Rev. 24, 06/96
1:.'0: DEFINITIONS!'.".,:,' ' =
1.1 ACCIDENT - An unforeseen and unintentional event which may result in an emergency.
1.2 ALERT - An Emergency Condition, see definition 1.14.
1.3 ASSE SMENT ACTIONS - Those actions taken during or after an incident to obtain and process information that is necessary to make decisions to implement specific emergency measures.
1.4 /DE - The Committed Dose Equivalent; dose to an organ due to an intake of radioactive material during the 50 year period following the intake.
1.5 COLUMBIA C Y EMER EN Y MANA EMENT A EN Y EMA-Emergency response coordinating agency for Columbia County, responsible for implementing ofF-site action upon direct notification from Susquehanna SES or PEMA.
1.6 Myh I I fh C IP I II I'hl dl auxiliary systems are controlled.
1.7 RPORATE MANAGEMENT OMMITTEE CM - The PP&L Management group which determines major policy commitments for the company. The CMC membership includes the President of the company, and the other top executives.
1.8 RRE TIVE A TI NS - Those emergency measures taken to ameliorate or terminate an emergency situation.
1.9 DEPARTMENT F ENVIRONMENTAL RE UR ES/8 A F RADIATION PROTE TION ER/BRP The State-level agency responsible to provide guidance and recommendations for specific o6-'site protective measures.
I.I~ D~SEPROIH ION.A d I d I fh p <<Id dl I d I dl 'd d at a given location, normally offsite, (determined from the quantity of radioactive material released and the appropriate meteorological transport and dispersion parameters).
P yll.yh I dl I Idl'dd p<<MIP I p I f time.
'1.12 EMER EN Y A TI N LEVELS AL - Operational or radiological parameters which, when exceeded, require the implementation of portions of this plan. EALs for various emergency conditions are specified in Table 5.1.
1.13 EMERGEN Y ACTI N - Those steps taken, as a result of exceeding an Emergency Action Level in the Emergency Plan, to ensure that the situation is assessed and that the proper corrective and/or protective actions are taken.
Rev. 22, 04/95
1.14 EMER EN Y ONDITION - The characterization of several classes of emergency situations consisting of exclusive groupings including the entire spectrum of possible radiological emergency situations. The four classes of emergencies, listed in increasing severity, which PP&L has incorporated into this Emergency Plan are outlined in Section 5.0 of this plan.
1.15 EMER EN Y RDINAT R - Designated Susquehanna SES staff members responsible for coordinating specific emergency organization functions.
1.16 EMER EN Y DIRE T R - The PP&L individual responsible for direction of onsite activities during an emergency at the Susquehanna SES.
1.17 EMER EN Y MANAGER - Designated Susquehanna SES and General Office Personnel who are responsible for managing specific emergency organization functions.
1.18 EMER EN Y OPERATI NS ENTERS - Designated State and county emergency management agency headquarters facilities, designed and equipped for the purpose of exercising effective coordination and control over disaster operations carried out within their jurisdiction.
1.19 =
EMER EN Y OPERATIONS FACILITY- PP&L Emergency Response Facility located near the reactor site to provide continuous coordination and evaluation of PP&L activities during an emergency having or potentially having environmental consequences.
1.20 EMER EN Y PLAN B ARY - Same as the legal site boundary with the exception of those sectors which border on U.S. Route 11, where Route 11 forms the boundary; used to calculate offsite dose rates, project dose to the public and to determine necessary protective actions.
1.21 EMER EN Y PLAN IMPLEMENTINGPROCEDURES - Specific procedures defining in detail the action to be taken in the event of an emergency condition. The Emergency Plan Implementing Procedures will be separate from, but may incorporate and refer to, normal plant operating procedures and instructions and Emergency Plan Position Specific Procedures.
1.22 EMER EN Y PLAIN Z NE - There are two Emergency Planning Zones. The first is an area, approximately ten (10) miles in radius around the Susquehanna SES, for which emergency planning consideration of the plume exposure pathway has been given in order to ensure that prompt and effective actions can be taken to protect the public in the event of an accident. The second is an area approximately 50 miles in radius around the Susquehanna SES, for which emergency planning consideration of the ingestion exposure pathway has been given.
Rev. 22, 04/95 1-2
1.23 EMERGENCY PLAN POSITION SPECIFIC PROCEDURES - Procedures describing how to perform tasks assigned to emergency positions. Each procedure includes an overview of the position's tasks, detailed instructions, and relevant material. Used together, these procedures are designed to implement the Emergency Plan during a 1.24 declared emergency.
~EXCL I NANNA- Th (see Figure 8.1) determined in accordance SS N h with SES 10CFR100.11.
'I'I ffhdd'f 1.25 FEDERAL EMER ENCY MANA EMENT AGEN Y MA - Within the context of this plan, serves as the primary contact for, requests for Federal assistance; lead coordinator all non-technical federal response.
1.26 ENERALEMER EN Y-AnEmergencyClassification. Seedefinition1.14.
1.27 ENERAL OFFI E ENGINEERlN SUPPORT CENTER - The general office area activated for Nuclear Plant Engineering resources in support of technical problem resolution.
1.28 LDE - Lens Dose Equivalent; the external exposure to the lens of the eye.
1.29 L ZERNEC YEMER EN YMANA EMEN'I'A EN Y EMA - The host county emergency response coordinating agency, responsible for implementing off-site action upon either direct notification from the Susquehanna SES or from PEMA.
1.30 MEDIA PERATI N ENTER - The designated location &om which news releases, press conferences and other media interfacing can be provided.
1.31 NUCLEAR REG ATORY OMMISSION C - Within the context of this plan, the Federal agency responsible for verifying that appropriate emergency plans have been implemented and for conducting investigative activities associated with a radiological emergency.
1.32 QFFSITE - Any area outside the PP&L site boundary surrounding the Susquehanna SES.
1.33 FFSITE RADI L I AL IN IDENT - Any radiation incident affecting areas beyond the site boundary and posing a significant threat to public health and safety.
1.34 QNSITE - The area viithin the PP&L site boundary surrounding Susquehanna SES.
1.35 PERATI NAL PORT ENTER OS - The primary on-site assembly area for operations support team personnel during the initial phase of an emergency.
1.36 PENN YLVANIAEMER EN YMANAGEMENTA EN Y EMA - Within the context of this plan, the lead state-agency for radiological emergency planning, response and recovery and for providing guidance to local government for development of radiological emergency plans and programs.
Rev. 22, 04/95 1-3
1.37 PLANT PROCED S - Those procedures utilized by the plant operations staff to control and manipulate the plant under both normal and abnormal circumstances.
1.38 POWER DISPAT HER - Individual manning the PPkL Power Control Center in the corporate headquarters in Allentown.
1.39 ~0TH ~ AIIHA-Th 'I' <<I I 'b'f ty <<dA*
Barrier) designated to implement the requirements of 10CFR73.
1.40 PROTE TIVE ACTION GUIDE A - The projected dose to reference personnel, or other defined individual, from an unplanned release of radioactive material at which a specific protective action to reduce or avoid that dose is recommended.
1.41 PR TE TIVE A TION - Those emergency measures taken for the purpose of preventing or minimizing radiological exposures.
1.42 I~IDA I ND H-Th h IH f df I b bNby h bdy yh the body. A rem is a unit of dose measurement.
1.43 RADI A TIVE MATERIAL - Any solid, liquid, or gas which emits radiation spontaneously.
1.44 RADI L I AL EMERGEN Y RESP N E TEAM RT - The response team from the Division of Radiological Health, State Board of Health, Pennsylvania Emergency Management Agency, and other State agencies, which will be dispatched to the scene of radiological emergencies. The team provides technical guidance and other services to local governments or an affected nuclear facility.
1.45 RADIOLOGICALLYC NTROLLED AREA CA - The area enclosed by the outer perimeter of the Turbine, Reactor, Radwaste Buildings for the operating Units, portions of the Low'Level Rad Waste Handling Facility and other areas designated by Health Physics.
1.46 RADIOL I ALLY NTR LLED'REA EVA ATI N - Evacuation of nonessential individuals &om some or all of the Radiologically Controlled Area.
1.47 RE VERY A TI N - Those actions taken after the emergency to restore the plant as nearly as possible to its pre-emergency condition.
1.48 RE VERY MANAGER -'he PP&L individual responsible for the management of emergency response activities during an emergency at Susquehanna SES.
1.49 R~E (Acronym for roentgen equivalent man) - A unit of measure of radiation dose in biological tissue.
1.50 REM TE ASSEMBLY AREA - A designated area, outside the exclusion area, for the assembly of evacuated plant personnel, ifnecessary, during a Site Evacuation.
Rev. 22, 04/95 1-4
1.51 SDE - Shallow Dose Equivalent; external exposure of the skin or extremity which is measured at 0.007 cm in tissue.
1.52 SITE AREA EMER ENCY - An Emergency Condition. See definition 1.14.
1.55 ~SITE EVACUA I N-E I IEI Idp I I I' 81 (the fenced in area of Susquehanna SES).
'.54 /TATE - The Commonwealth of Pennsylvania.
1.55 STATI N ASSEMBLY AREA - An area designated for the assembly of specific groups of individuals for the purpose of personnel accountability.
1.56 TE HNICAL PORT CENTER - A designated on-site location where the conditions during and after an accident can be analyzed to provide technical and radiological assessments of the accident to the Emergency Director.
1.57 TEDE - Total Effective Dose Equivalent; integrated doses consisting of the sum of external doses from plume shine, 50 year committed effective dose equivalent from inhalation (CEDE), and 4 day ground shine doses.
1.58 T~RYlt IO OUSE-R 41 I 8 <<h hy Id I gbiOE I I g radioactive materials.
1.59 !ESUEUAC NT-A E g yC 411 . 5* d II 114 1.60 WHOLE BODY EXPO - Direct radiation exposure to the body from external sources.
Rev. 22, 04/95 1-5
1.0 DEFIMTIONS' An unforeseen and unintentional event which may result in an emergency.
1.2 ~~ - An Emergency Condition, see definition 1.14.
1.3 - Those actions taken during or aAer an incident to obtain.and process information that is necessary to make decisions to implement specific emergency measures.
1.4 QQQ - The Committed Dose Equivalent; dose to an organ due to an intake of radioactive material during the 50 year period following the intake.
1.5 Emergency response coordinating agency for Columbia County, responsible for 1.6 ~.TI implementing off-site action upon direct notification from Susquehanna SES or PEMA.
i auxiliary systems are controlled.
i fhC IP If hilUd'i 1.7 - The PP&L Management group which determines major policy commitments for the company. The CLC membership includes the President of the company, and-the other top executives.
1.8 - Those emergency measures taken to ameliorate or terminate an emergency situation.
1.9
- The State-level agency responsible to provide guidance and recommendations for specific off-site protective measures.
1 ~ 10 - A calculated estimate of the potential radiation dose to individuals at a given location, normally off-site, (determined from the quantity of radioactive material released and the appropriate meteorological transport and dispersion parameters).
- The amount of radiation an individual can potentially receive per unit of time.
1.12 - Operational or radiological parameters which, when exceeded, require the implementation of portions of this plan. EALs for various emergency conditions are specified in Table 5.1.
1.13 - Those steps taken, as a result of exceeding an Emergency Action Level in the Emergency Plan, to ensure that the situation is assessed and that the proper corrective and/or protective actions are taken.
Rev. 24, 06/96
1.14 - The characterization of several classes of emergency-situations consisting of exclusive groupings including the entire spectrum of possible radiological emergency situations. The four classes of emergencies, listed in increasing severity, which PPEcL has incorporated into this Emergency Plan are outlined in Section 5.0 of this plan.
1.15 - Designated Susquehanna SES staff members responsible for coordinating specific emergency organization functions.
1.16 - The PPckL individual responsible for direction of on-site activities during an emergency at the Susquehanna SES.
1.17 - Designated Susquehanna SES and General OKce Personnel who are responsible for managing specific emergency organization functions.
1.18 - Designated State and county emergency management agency headquarters facilities, designed and equipped for the purpose of exercising effective coordination and control over disaster operations carried out within their jurisdiction.
1.19 - PPAL Emergency Response Facility co-located with the Media Operation Center in Plains Township, Pennsylvania, to provide continuous coordination and evaluation of PPkL activities during an emergency having or potentially having environmental consequences (Reference REFERENCES, Section 3.19).
1.20 - Same as the legal site boundary with the exception of those sectors which border on U.S. Route 11, where Route 11 forms the boundary; used to calculate off-site dose rates, project dose to the public, and to determine necessary protective actions.
1.21 - Specific procedures defining in detail the action to be taken in the event of an emergency condition. The Emergency Plan Implementing Procedures will be separate from, but may incorporate and refer to, normal plant operating procedures and instructions and Emergency Plan Position Specific Procedures.
1.22 - There are two Emergency Planning Zones. The first is an area, approximately ten (10) miles in radius around the Susquehanna SES, for which emergency planning consideration of the plume exposure pathway has been given in order to ensure that prompt and effective actions can be taken to protect the public in the event of an accident. The second is an area approximately 50 miles in radius around the Susquehanna SES, for which emergency planning consideration of the ingestion exposure pathway has been given.
Rev. 24, 06/96 1-2
1.23 - Instructions describing
~-
how to perform tasks assigned to emergency positions. Each instruction includes an overview of the position's tasks, detailed instructions, and relevant material. Used together, these instructions are designed to implement the Emergency Plan during a declared emergency.
1.24 Th
- dd q h SES lhl~ dl flddtlf (see Figure 8.1) determined in accordance with 10CFR100.11.
1.25 - Within the context of this plan, serves as the primary contact for requests for Federal assistance; lead coordinator all non-technical federal response.
1.26 - An Emergency Classification. See definition 1.14.
1.27 LQE.- Lens Dose Equivalent; the external exposure to the lens of the eye.
-1.28 The host county emergency response coordinating agency, responsible for implementing off-site action upon either direct notification from the Susquehanna SES or from PEMA.
1.29 - The designated location from which news releases, press conferences and other media interfacing can be provided.
1.30 - Within the context of this plan, the Federal agency responsible for verifying that appropriate emergency plans have been implemented and for conducting investigative activities associated with a radiological emergency.
1.31 Q+5I1E - Any area outside the PP8eL site boundary surrounding the Susquehanna SES.
1.32 - Any radiation incident affecting areas beyond the site boundary and posing a significant threat to public health and safety.
1.33 Q~Q - The area within the PPkL site boundary surrounding Susquehanna SES.
1.34 - The primary on-site assembly area for operations support team personnel during the initial phase of an emergency.
1.35 - Within the context of'this plan, the lead state-agency for radiological emergency planning, response and recovery and for providing guidance to local government for development of radiological emergency plans and programs.
1.36 - Those procedures utilized by the plant operations staff to control and manipulate the plant under both normal and abnormal circumstances.
Rev. 24, 06/96 1-3
- Individual manning the PPkL Power Control Center in the
~-Th'll 1.37 corporate headquarters in Allentown.
1.38 h i i lyl* (P <<dA Barrier) designated to implement the requirements of 10CFR73.
1.39 V - The projected dose to reference personnel, or other defined individual, from an unplanned release of radioactive material at which a specific protective action to reduce or avoid that dose is recommended.
1.40 - Those emergency measures taken for the purpose of preventing or minimizing radiological exposures.
L41~-Thq the body. A rem lyf dpi is a unit of dose measurement.
t bdbU*tdyyp i f 1.42 - Any solid, liquid, or gas which emits radiation spontaneously.
1.43 - The response team from the Division of Radiological Health, State Board of Health, Pennsylvania Emergency Management Agency, and other State agencies, which will be dispatched to the scene of radiological emergencies. The team provides technical guidance and other services to local governments or an affected nuclear facility.
1.44 - The area enclosed by the outer perimeter of the TurbineReactor,'Radwaste Buildings for the operating Units, portions of the Low Level Rad Waste Handling Facility and other areas designated by Health Physics.
1.45 Evacuation of nonessential individuals from some or all of the Radiologically Controlled Area.
1.46 - Those actions taken after the emergency to restore the plant as nearly as possible to its pre-emergency condition.
1.47 - The PP&L individual responsible for the management of emergency response activities during an emergency at Susquehanna SES.
1.48 RQh[ (Acronym for roentgen equivalent man) - A unit of measure of radiation dose in biological tissue.
1.49 - A designated area, outside the exclusion area, for the assembly of evacuated plant personnel, ifnecessary, during a Site Evacuation.
Rev. 24, 06/96 1-4
1.50 QQP - Shallow Dose Equivalent; external exposure of the skin or extremity which is measured at 0.007 cm in tissue.
1.51 - An Emergency Condition. See definition 1.14.
1.52 - Evacuation of all nonessential personnel within the plant site area (the fenced in area of Susquehanna SES).
1.53 51~ - The Commonwealth of Pennsylvania.
1.54 - An area designated for the assembly of specific groups of individuals for the purpose of personnel accountability:
1.55 - A designated on-site location where the co'nditions during and after an accident can be analyzed to provide technical and radiological assessments of the accident to the Emergency Director.
1.56 II I~ - Total Effective Dose Equivalent; integrated doses consisting of the sum of external doses from plume shine, 50 year committed effective dose equivalent from
~-Rdi inhalation (CEDE), and 4 day ground shine doses.
1.57 i p <<h*hy idl Ihdl i kg*i 8 radioactive materials.
1.58 - An Emergency Condition. See definition 1.14.
1.59 - Direct radiation exposure to'the body from external sources.
Rev. 24, 06/96 1-5
2.0'ACRONVMS 2.1- ANS- Alert Notification System 2.2 ARI- Alternate Rod Insertion 2.3 ARM- Area Radiation Monitors 2.4 BEOF- Backup Emergency Operations Facility 2.5 CAM -. Continuous Air Monitors 2.6 CEMA- Columbia County Emergency Management Agency 2.7 CR- Control Room 2.8 CREOASS- Control Room Emergency Outside Air Supply System 2.9 CTN- Centrex Telephone Network 2.10 DAC Derived Air Concentration 2.11 DCC- Document Control Center 2.12 DER/BRP- Department of Environmental Resources/Bureau of Radiological Protection 2.13 DOE- U.S. Department of Energy 2.14 EAL- Emergency Action Levels 2.15 ECCS- Emergency Core Cooling Systems 2.16 ED- Susquehanna Emergency Director 2.17 EMA- Emergency Management Agency 2.18 EMC- Emergency Management Coordinator (Municipality) 2.19 EOC- Emergency Operations Center 2.20 EOF- Emergency Operations Facility 2.21 EP- Susquehanna SES Emergency Plan 2.22 EPA Environmental Protection Agency 2.23 EP-PS- Emergency Plan Position Specific Procedures, 2.24 EPZ- Emergency Planning Zone 2.25 ERDS- Emergency Response Data System 2.26 ERF- Emergency Response Facility 227 ETN- Electronic Tandem Network 2.28 FEMA- Federal Emergency Management Agency 2.29 FPC- Fuel Pool Cooling 2.30 FSAR- Susquehanna SES Final Safety Analysis Report, Units 1 and 2 2.31 FTS- Federal Telecommunications System 2.32 GOESC- General Of6ce Engineering Support Center 2.33 HHS Health and Human Services 2.34 HPCI- High Pressure Coolant Injection System 2.35 LCEMA- Luzerne County Emergency Management Agency 2.36 LCO- Limiting Condition for Operation 2.37 LER- License Event Report 2.38 LOCA- Loss of Coolant Accident 2.39 MIDAS Meteorological Information and Dose Assessment System 2.40 MOC- Media Operations Center 2.41 MSIV- Main Steam Isolation Valve 2.42 MSL- Main Steam Line II Rev. 21, 04/94, 2-1
2.43 NEP Nuclear Emergency Planning 2.44 NERO- PP&L Nuclear Emergency Response Organization 2.45 NRC- U.S. Nuclear Regulatory Commission 2.46 NSSS Nuclear Steam Supply System 2.47 ODCM- Quite Dose Calculation Manual 2.48 OSC- Operations Support Center 2.49 PAGs- EPA Protective Action Guides 2.50 PASS- Post Accident Sampling System 2.51 PCS- Plant Computer System 2.52 PEMA- Pennsylvania Emergency Management Agency 2.53 PNS- Public Notification System 2.54 PORC- Plant Operations Review Committee 2.55 PP&L- Pennsylvania Power & Light Company 2.56 PSP- Pennsylvania State Police 2.57 RCIC- Reactor Core Isolation Cooling 2.58 RDAS- Remote Data Analysis System 2.59 RHR- Residual Heat Removal 2.60 RPS- Reactor Protection System -
2.61 Rx- Reactor 2.62 SCC Security Control Center 2.63 SGTS- Standby Gas Treatment System 2.64 SLC- Standby Liquid Control 2.65 SOP- Special OfBce of the President 2.66 SPDS>> Safety Parameter Display System 2.67 SPINGs - .
System Particulate, Iodine, and Noble Gas Monitor (Vent Monitoring System) 2.68 SRC- Susquehanna Review Committee 2.69 SSE- Safe Shutdown Earthquake 2.70 SSES- Susquehanna Steam Electric Station 2.71 TR- Temperature Recorder 2.72 TSC- Technical Support Center 2.73 UMC- Unit Monitoring Console (PCS) 2.74 UPS- Uninterruptable Power Supply 2.75 USDA- United States Department of Agriculture Rev. 21, 04/94 2-2
3;0 REFERENCES;'.1 CEMA Emergency Plan - Radiological Emergency Response Plan for incidents at the Susquehanna Steam Electric Station 3.2 DER/BRP Emergency Plan - Bureau of Radiation Protection "Plan for Nuclear Power Generating Station Incidents" 3.3 NRC Generic Letter 91-14, "Emergency Telecommunications" 3.4 LCEMA Emergency Plan - Radiological Emergency Response Plan for Incidents at the Susquehanna Steam Electric Station.
3.5 NUTMEG 0654/FEMA-REP Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness In Support of Nuclear Power Plants.
3.6 NUREG 0696 - Final Report - Functional Criteria for Emergency Response Facilities.
3.7 NUIKG0737 - Clarification of TMI Action Plan Requirements.
t 3.8 3.9 3 10
~
NUREG 1392 - Emergency Response Data System Implementation PEMA Emergency Plan - Annex E to Commonwealth of Pennsylvania Operations Plan", Nuclear Incidents (Fixed Facility).
Susquehanna SES Emergency Plan Position Specific Procedures.
"Disaster 3.11 Susquehanna SES Letters of Agreement with oF-site emergency organizations.
3.12 Susquehanna SES Physical Security Plan and Security Training and Qualifications Plan.
3.13 Susquehanna SES Plant Procedures.
3.14 10CFR Part 50 - Domestic Licensing of Production and Utilization Facilities 3.15 Susquehanna SES Alert and Notification Design Report 3.16 SSES Preparedness, Prevention and Contingency Plan 3.17 SSES Hazardous Material Emergency OfF-Site Emergency Response Plan 3.18 EPA 400-R-91-001 - Manual of Protective Action Guides and Protective Actions for Nuclear Incidents Rev. 22, 04/95 3-1
4.0: SCOPE"AND CONTENTS";.
SSES includes two boiling water reactor electrical generating units. The station is located in Salem Township, Luzerne County, in east central Pennsylvania, about five miles northeast of Berwick, Pennsylvania (See Figure 4.1), This Emergency Plan applies to the operation of Unit 1 and Unit 2.
4,1 COPE This Plan provides guidance for both on-site and oft'-site emergency situations. It ranges in scope from relatively minor events and occurrences involving small releases of radioactive material, up to and including a major nuclear emergency having significant off site radiological consequences.
This Plan, together with the state, county, and municipal radiological emergency response plans, provides detailed guidance and direction for taking emergency measures by the NERO to ensure the health and safety of the public living within the 10-mile EPZ of SSES. Additional guidance is provided in state and county plans for ingestion pathway preventive measures out to 50 miles (See Figure 4.2).
Additional guidance on specific emergency actions for non-radiological releases of hazardous materials can be found in two other emergency plans: the SSES Preparedness, Prevention, and Contingency Plan and the SSES Hazardous Material Emergency OF-Site Response Plan.
4~CONTENT 4 2.1 l ificati n This Plan provides for a graded response for distinct classifications of emergency conditions, action within those classifications, and criteria for escalation to another classification. This classification system is also used by PEMA, DER/BRP, LCEMA AND CEMA. This system is covered in Section 5.0.
4.2.2 r anization Control The PP&L organization for control of emergencies begins with the on-shift station personnel and contains provisions for augmentation and extension to include other station personnel, PP&L corporate personnel, and outside emergency response organizations.
The total emergency program includes the support of state, federal and local emergency organizations. Detailed provisions are made for implementing protective measures against direct radiation exposure for the public within a radius of at least ten miles aom the SSES. Additional preventive measures may be taken beyond that distance to preclude ingestion pathway exposures.
Specific agreements are also made with local ofF-site support organizations to provide fire fighting, medical, law enforcement, and trafBc control services.
Rev. 22, 04/95 4-1
State, County and Federal agencies have lead responsibilities specifically related to this Plan.
Organizational control is covered in Section 6.0.
4.2.3 Emer enc Measures The mechanisms through which this Plan provides for the proper response to emergency conditions at SSES include identification of the event, initial and ongoing assessment, and initial and ongoing emergency actions. Emergency actions include classification of event, completion of notifications, activation of onsite and offsite NERO, requests for offsite assistance, implementing onsite protective actions, recommending offsite protective actions, and activation of the restoration organization. These mechanisms are discussed in Section 7.0.
4 2 4 Emer en Facilities Emergency facilities and equipment are provided to ensure the capabilities for prompt, efficient assessment and control of situations over the entire spectrum of probable and postulated emergency conditions. The facilities and associated equipment and their emergency functions are described in Section 8.0.
425Em r en Trainin A concept of in-depth preparedness is employed regarding the SSES emergency program. This concept is emphasized in the training program and in preparedness drills and exercises. Personnel are trained to provide an in-depth response capability for required actions in an emergency situation. Section 9.0 includes the means to achieve and maintain preparedness and to ensure maintenance of an effective emergency program.
Rev. 22, 04/95 4-2
'.- ..6.0'RGANIZATIONALCONTROL-'OF EMERGENCIES PP&L's Emergency Plan is based upon a four phase approach to accident response and mitigation.
Phase I- Immediate Res on (Reference Figure 6.3 and Table 6.1). Phase I consists of identification of the emergency condition, initiation of prompt corrective action and initiation of prompt notification to local, state and federal agencies as well as appropriate members of PP&L's NERO. This initial phase is implemented by the on-shift organization. The on-shift organization has been staffed and trained to be capable of both safely operating the unit and quickly and effectively responding to an emergency condition. Initially, the Shift Supervisor, the highest ranking management individual on-shift, will assume the role of ED.
The Shift Supervisor, as ED:
a) Classifies the condition.
b) Initiates corrective actions and coordinates emergency management activities.
c) Designates a communications coordinator to notify off-site agencies and initiate call-in of selected personnel.
d) Notifies plant personnel over the PA system for accountability and/or evacuation.
e) Designates an OSC Coordinator who organizes and directs in-plant emergency team functions.
off f) Notifies the Vice President-Nuclear Operations or his designated alternate, informs him of the situation, and requests relief if appropriate. For conditions under an Unusual Event the Shift Supervisor is likely to remain as ED through termination of the condition, due to probable short duration or low severity of the event:
g) Ensures that on-site emergency response individuals and groups are notified, using the PA system or direct communications. Depending on the nature and severity of the condition, TSC staf6ng may be called out.
h) Ensures that initial dose projections are done and makes resulting recommendations regarding oF-site protective actions.
i) Ensures that off-duty station personnel are notified to assist as necessary with emergency activities. These notifications are made, via the radio paging system or by telephone backup, to individuals designated for dut availability status to fill key emergency response positions. Those key positions are identified in Sections 6.2 and 6.3. Other off-duty personnel are called in as required.
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Upon activation of Phase II, additional personnel are available, and control and dissemination of in-plant teams shifts from the OSC to the TSC.
Phase II - Activation of On-Site NERO - (Reference Figure 6.3 and Table 6.2) Upon notification by the on-shift organization, the VP-Nuclear Operations or his designated alternate, reports to the site to assume the role of ED. Support coordinators and staffs in areas of technical assessment, radiological assessment and operational coordination also report to the site. These individuals form the nucleus of the ED's Team and activate the TSC. The TSC is fully functional within 30 to 60 minutes of initial notification. As the Vice President-Nuclear Operations and his support coordinators arrive, they are briefed by the Shift Supervisor and then, in turn, assume responsibility from the Shift Supervisor for their particular areas of expertise. Emergency management activities, including communications, are under the control of the Plant Superintendent or his designated alternate; dose projection and assessment activities are directed by the Radiation Protection Coordinator; technical expertise is directed by the Tech Support Coordinator, the Operations Coordinator oversees Operations activities and the Damage Control
. Team Coordinator oversees in-plant damage control actions. The TSC takes over all emergency management and support activities from the on-shift organization, freeing them to devote their efforts towards establishing and maintaining the plant in a safe, stable condition.
Pha III-A iv i n of ff-sit NER - (Reference Figures 6.2a, 6.2b, 6.4, 6.5 and Table 6.2).
This organization staffs the Emergency Operations Facility, General Office Engineering Support Center, and Media Operations Facility to provide in-depth technical and off-site radiological assessment.
The Emergency Operations Facility is activated automatically at a Site Area Emergency, but can be activated earlier at the discretion of the Emergency Director or Recovery Manager. Upon activation of the Emergency Operations Facility, personnel shall report to the EOF and be prepared for full functional operation within one hour.
Functional operation will include:
~ Management of overall emergency response
~ Coordination of radiological and environmental assessment
~ Determination of recommended protective actions
~ Coordination of emergency response activities with Federal, State, local county and municipal agencies Site based EOF personnel will be notified and report to the EOF at an ALERT classification to prepare the facility should activation become necessary. The EOF is initially staffed by Site personnel at an Alert classification. Upon activation, General Of5ce personnel will be notified and report to the EOF as soon as reasonably possible.
NOTE: Site based personnel are capable of fully activating the Emergency Operations Facility.
Rev. 22, 04/95 6-2
The General Office Engineering Support Center is also staffed by personnel from the General OfBce. It is activated within one hour of notification, directed by the Engineering Support Manager, interfacing with the TSC and EOF. The EOF and GOESC, upon activation, will relieve the Emergency Director and the on-site organization of external responsibilities, allowing them to
,<<devote their entire efforts to in-plant activities.
Pha e IV - Restoration - This phase leads ultimately to the return to service of the unit. The organizational and philosophical concepts that are utilized during this phase are highly dependent upon the nature of the emergency. The restoration phase does not begin until there is complete assurance that the plant is in a stable shutdown condition and that there are no inadvertent or unplanned significant release of radioactivity to the environment.
6.1 N RMAL OPERATIN R ANIZATION
, The normal Operating Organization during working hours is illustrated in Figure 6.1. Minimum
. shift response during oF-hours is as follows:
1 Shift Supervisor (SRO) 1 Unit Supervisor (SRO) 1 Unit Supervisor (RO)
'ssistant 2>> Licensed Operators (RO) 1 Shift Technical Advisor 3>> Non-Licensed Operators I>> Health Physics Technician 1 Chemistry Technician 1 Security Shift Supervisor 1 Assistant Security Shift Supervisor 10 Security Officers per unit 62 ON- ITEEMER EN Y R ANIZATI N- HA EI 621 Emer en Dir r The Shift Supervisor assumes the role of ED until he is relieved by the VP-Nuclear Operations, or his designated alternate. Typical alternates are the Manager - Nuclear Maintenance and the Manager - Nuclear Plant Services. When the TSC is activated, and the Shift Supervisor is relieved, the Shift Supervisor reassumes responsibility for plant operating functions in the control room.-
The Shift Supervisor ensures that the VP-Nuclear Operations, or designated alternate, is promptly notified of an emergency condition.
The ED assumes full responsibility for the implementation and administration of the Emergency Plan and is responsible for assuring continuity of resources until he relinquishes those C
Rev. 22, 04/95 6-3
responsibilities to the Recovery Manager. The responsibility and authority of the ED are set forth in Appendix E.
The ED cannot relinquish any of the above responsibilities until the anival of and assumption of responsibilities by the Recovery Manager at the EOF. At that time, he may relinquish any of the above responsibilities ~exce those related to maintaining the Unit in a safe shutdown condition with adequate core cooling and no uncontrolled radioactive material releases.
If the ED cannot perform this function during the emergency, he will be succeeded by the Operations Coordinator until another qualified Emergency Director arrives to assume this responsibility.
Functional responsibilities of the ED include:
a) Immediately upon notification of an existing or potential emergency, report to the Control Room and initiate assessment activities, including classification of the emergency and dose projections ifappropriate.
b) Unilaterally implement the immediate on-site corrective and protective actions to bring the incident under control and mitigate its effects.
c) Assure that appropriate notifications and recommendations to off-site organizations are made within 15 minutes.
d) Appoint Emergency Coordinators for assistance with current and continuing emergency control, but assume those responsibilities until the positions are filled.
e) Augment the on-site NERO with duty roster personnel and other available station staff members as dictated by the emergency condition.
x f) Continue reassessment of emergency status and make appropriate recommendations including protective actions to off-site organizations.
g) Ensure that information released is accurate and released through the proper channels.
h) Activate Emergency Facilities described in Section 8.0.
i) Assign technical liaison to EOCs ifrequested.
j) Communicate with and provide information to the Recovery Manager, EOF Support Manager, Public Information Manager, and Engineering Support Manager.
k) Issuance of Radioprotective Drugs in accordance with prescribed procedures and should include consultation with the Radiation Protection Coordinator and medical consultants.
t) Taking essential corrective action which may involve the risk of emergency radiation exposure to NERO personnel. Table 7.2 provides the basic criteria for this decision.
O Rev. 22, 04/95 6-4
m) Request Federal assistance to augment NERO capabilities as necessary. Such requests should be coordinated with PEMA and/or DER/BRP.
6.2.2 0 erati n oordinaor-,,
This position is filled by the Manager of Nuclear Operations or a designated alternate. Typical alternates are the Shift Supervisor or the Plant Scheduling Supervisor.
Responsibilities:
a) Direct Control Room and in-plant operational activities through the Shift Supervisor.
b) Advise the ED on plant operations.
62.3 TSCC mm nicator This position is initially filled by a Plant Control Operator. When the TSC is activated this position is typically filled by simulator instructors from the Susquehanna Training Center.
Responsibilities:
a) Make proper notification to oF-site organizations.
b) Initiate call-in procedures as requested by the ED.
c) Function as liaison for emergency-related communications between the ED and on-site and off-site emergency groups.
d) Maintain communications with the NRC.
e) Maintain records concerning the emergency.
6.2.4 Health Ph sics Netw rk ommunicator This position is filled by qualified Health Physics personnel when the TSC is activated.
Responsibilities:
~
a) Communicate radiological data to the NRC via the Health Physics Network.
625 Radiation Pr tecti n ordin t r This position is filled by the Health Physics Supervisor. Typical alternates for this position are the qualified Health Physics personnel.
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Responsibilities a) Perform initial dose projection and off-site environmental assessment until relieved by the Interim Radiation Support Manager or Radiation Support Manager.
b) Provide radiological advice to the ED concerning on-site emergency activities.
c) Provide protective action recommendations to the ED.
d) Maintain communication with and provide information to the Interim Radiation Support" Manager and the Radiation Support Manager.
e) Maintain communication with and provide radiological information to DEWBRP until relieved by the Interim Radiation Support Manager or Radiation Support Manager.
f) Provide on-site radiation monitoring personnel for efHuent release assessment.
g) Provide radiation monitoring personnel for emergency team efForts.
h) Direct personnel and area contamination control and decontamination activities.
6.26 T hni u rt o rdinat r This position is filled by the Engineering and Installation Planning Supervisor. Typical alternates for this position are System Engineering management personnel.
Responsibilities:
a) Analyze mechanical, electrical, and instrument and control problems; determine alternate solutions, design and coordinate the installation of short-term modifications.
b) Analyze thermohydraulic and thermodynamic problems and develop solutions.
c) Assist in the development 'of procedures necessary for conducting emergency operations.
d) Analyze conditions and develop guidance for the ED and operations personnel.
e) Resolve questions concerning Operating License requirements with NRC representatives.
f) Maintain lead technical responsibility, coordinating dissemination of technical work assignments to EOF and GOESC.
g) Maintain communication with and provide technical information to DER/BRP until relieved by the Lead Technical Support Stair or Site Support Manager. O Rev. 22, 04/95 6-6
6.2.7 Administrative Coordinator This position is filled by the Supervisor - Site Support. Typical alternates are Site Support management personnel.
Responsibilities:
a) Coordinate provisions for transportation, food and other logistical support for emergency personnel.
b) Provide personnel and work schedules for relieving emergency personnel.
c) Act as liaison with outside groups in providing additional resources such as manpower, equipment, supplies and transportation.
6.2.8 Securi Co rdinator This position is filled by the Manager - Nuclear Security. The typical alternate for this position is a Security Supervisor.
Responsibilities:
a) Maintain plant security and institute appropriate contingency measures.
b) Account for personnel in accordance with EP-PS's.
c) Provide access and trafBc control for off-site PP&L locations such as the EOF.
6.2.9 OSC Coordinator This position is filled by the Assistant Unit Supervisor. If the AUS is unavailable the Shift Supervisor will designate a replacement.
Responsibilities:
a) Direct the activities of the in-plant Emergency Teams such as damage control, fire brigade and first aid and rescue until relieved by the TSC.
NOTE The fire brigade leader is the Assistant Unit Supervisor. However, the coordination of various team activities is the responsibility of the OSC Coordinator.,
b) Coordinating the availability and assignment of personnel supporting activities for the ED and other NERO managers until relieved by the TSC.
Rev. 22, 04/95 6-7
6.2.10 Dama e Control Team Coordinator The Damage Control Team Coordinator position is filled by Maintenance Functional Team Managers.
Responsibilities:
a) Ensure damage control resources are allocated on the right priorities by assigning tasks to available resources.
b) Dispatch in-plant teams.
c) Communicate with Operations and the Technical Support Coordinator.
6.2 11 T Radio Communicator This position is filled by a Maintenance or I&C Engineer.
Responsibilities:
a) Maintain radio communications with all in-plant teams.
b) Maintain an up-to-date status of in-plant radiological conditions.
c) Track dose levels of in-plant team members.
6.212 Maintenan & or in t r The Maintenance Coordinator position is filled by Maintenance Management personnel. The I&C Coordinator position is filled by I&C Management personnel.
Responsibilities:
a) Organizing, briefing, dispatching, and directing, as necessary, the on-site damage control teams.
b) Providing personnel assistance and support to in-plant teams as necessary.
c) Supporting technical group activities and operations as necessary.
6.2 13 Chemist rdinator The Chemistry Coordinator position is filled by an ANSI qualified chemist. A typical alternate for this position would be a Senior Chemist.
Rev. 22, 04/95 6-8
Responsibilities:
a) Assemble and direct the activities of chemistry personnel to assure information on plant status is accurate and available.
6.3 OFF-SITE RE OUR ES AND ACTIVITIES HA E III Notification of the Recovery Manager is made for all levels of emergencies by the Communications Coordinator in the Control Room or TSC. An on-call duty roster is kept in the CR and TSC.
For an Unusual Event or Alert, ifthe Recovery Manager decides to activate the off-'site NERO, the Communications Coordinator directs the Security Controller to notify all required personnel by contacting Security to activate the paging system or by direct telephone contact from the SCC Controller.
For a Site Area or General Emergency, EOF activation is automatic. EOF staff is notified via a paging signal generated by SSES Security or direct telephone from the SCC Controller. Field team call-in is initiated by the NEP Duty Planner.
631 E F r anizati n 6.3.1.1 Interim Radiation Su ort Mana er This position is filled by management personnel from the site having a health physics background.
Typical alternates would be the Supervisor-Modification Installation or the Supervisor-Nuclear General Training.
Responsibilities a) Until arrival of the Radiation Support Manager, m'anage interim radiological functions in the EOF.
~ Offsite dose calculations, projections, and assessment.
~ Make protective'action recommendations to the Recovery Manager.
~ Communicate with DER/BRP Radiological.
~ Control field monitoring teams.
6.3.1.2 Interim Recove Mana r This position is filled by site supervision having a technical background. Typical alternates would be the Supervisor-Chemistry or the Manager-Nuclear Information Services.
Rev. 22, 04/95 6-9
Responsibilities a) Until arrival of the Recovery Manager, act as the company representative, contributing a prognosis, knowledge, and data to federal and state agencies, and assume responsibility for:
~ PP&L's emergency response effort to assure priority issues are being addressed and a common understanding of the situation exists.
~ Represent the company in discussions with state and federal agencies.
~ Reclassify the emergency based on continuing assessment of the situation.
~ Make protective action recommendations.
6.3.1.3 Recove Mana er This position is filled by the Vice President-Nuclear Engineering. The typical alternate is the Manager-Independent Evaluation Services.
Ifthe Recovery Manager cannot perform this function during the emergency, he will be succeeded by the Interim Recovery Manager or the Assistant Recovery Manager.
Responsibilities:
a) Providing continuous coordination and evaluation of PP&L activities during an emergency having or potentially having environmental consequences.
b) .Managing overall PP&L emergency response and as'suring continuity of resources.
c) Acting as lead interface with off-'site government agency officials.
d) Assure appropriate notifications and recommendations to offsite organizations are timely.
e) Continue reassessment of emergency status and make appropriate recommendations including protective actions to oF-site organizations.
f) Ensure that information released is accurate and made through proper channels.
g) Directing the activities of all other EOF managers'.
h) Request Federal assistance to augment NERO capabilities as necessary. Such requests should be coordinated with PEMA and/or DER/BRP.
i) Notify PEMA Emergency Operations Center of Protective Action Recommendations.
Rev. 22, 04/95 6-10
j) Send a representative to the State and risk counties. If conditions result in implementation of the Federal Radiological Emergency Response Plan, assign a representative to the Federal Response Center, to the Federal Radiological Monitoring and Assessment Center, and to the Joint Information Center (most likely the PIM).
6.3.1.4 Lead Technical u taffer This position is typically filled by qualified engineers.
Responsibilities:
a) Analyze technical and radiological data, identifying inconsistencies.
b) Further the response organization's understanding of the accident.
c) Provide technical information to the Recovery Manager and offsite agencies.
6315 i u ortMana er This position is filled by the Manager-Nuclear Training. A typical alternate for this position is the Senior Project Engineer-Nuclear Training.
Responsibilities:
a) Access in-plant technical and radiological information.
b) Provide analysis of in-plant data to the Recovery Manager.
c) Provide analysis of in-plant data and support the needs of Federal and State Agency personnel located in the EOF.
d) Oversee formal communications leaving the EOF.
6.3.1.6 Admini ra ive u ort Mana er This position is filled by the Safety and Health Consultant-Nuclear. A typical alternate is the Planning and Scheduling Foreman.
Responsibilities:
a) Providing personnel and work schedules for relieving emergency personnel.
b) Providing housing, food, office equipment, etc., for off-site support personnel.
c) Making necessary contractual arrangements for the emergency response efforts.
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d) Procuring equipment, supplies, and additional personnel needed to support the emergency response eForts.
e) Providing additional manpower for scheduling activities deemed appropriate by the Recovery Manager.
6.3 1.7 Radia i n Su ort Mana er This position is filled by the Supervisor-Operations Technology. A typical alternate is the Supervisor - Environmental Services-Nuclear.
Responsibilities:
a) Evaluating the magnitude'and eFects of actual or potential radioactive releases from the plant.
b) Recommending appropriate o6site protective measures to the Recovery Manager.
c) Recommending appropriate emergency classifications to the Recovery Manager.
d) Communicating with the Radiation Protection Coordinator in the TSC and with DER/BRP radiological personnel.
e) Controlling field monitoring teams.
6.3.1 8 EOF C mmunicator This position is typically filled by personnel assigned to the Nuclear Training Center.
Responsibilities:
a) Assume responsibility fiom the TSC for offsite notifications.
b) Transmit information about the emergency to oFsite organizations.
c) Function as liaison for questions received from other organizations.
d) Maintain a record of emergency notifications.
~
6.3 2 Media erations Center The ED ensures that the MOC (Figure 6.4) is promptly notified and provided with available details of the emergency. The MOC stafF transmits information regarding the emergency and items of potential interest to municipal groups, initiates appropriate news-releases and responds to questions from public information representative. After the Recovery Manager assumes control of the EOF, he updates the Public Information Manager.
Rev. 22, 04/95 6-12
6.3.2.1 Public Information Mana er This position is filled by the Special Assistant to the President - Susquehanna. Typical alternate is the Senior Public Information Specialist.
Responsibilities:
a) Serving as official company spokesman.
b) Preparing and disseminating SSES information to the public via the news media.
c) Interpreting plant status information for the news media and other agencies.
d) Arranging for news media conferences.
e) Rumor control.
f) Establishes interfaces and coordinates news. releases with the federal and state agencies in the MOC.
6.3.3 General ffice Su o Facilities Emergency Support from the General Office is provided from the General Office Engineering Support Center (GOESC).
The GOESC is located in the Corporate Offices in Allentown. Activation of the GOESC is automatic during a SITE AREA or GENERAL EMERGENCY, and may also occur in. an UNUSUALEVENT or ALERT ifthe Recovery Manager deems such action appropriate.
6.3.3 1 En 'neerin u rt Mana er This position is filled by the Manager-Nuclear Technology. A typical alternate is the Supervisor-Nuclear Fuels Engineering.
Responsibilities:
a) Provide technical information and management support to the Emergency Director and Recovery Manager.
b) Provide priority guidance to the Engineering Support Leader and staff c) Support technical needs of the Site Support Manager.
634 L c ff- iteSu ervice The ED ensures that appropriate ofF-site emergency support groups are contacted to provide the type and level of assistance which may be necessary to deal with the existing emergency Rev. 22, 04/95 6-13
condition. The organizations listed below may be contacted for assistance. Methods available for contacting these support groups include direct telephone communications with individual organizations, use of the 911 telephone system for emergency services, and message relay through LCEMAor CEMA.
~ Salem Township Fire Company No. 1 (fire and rescue)
~ East Berwick Hose Company No. 2 (fire and rescue)
~ Shickshinny Area Volunteer Ambulance Association (ambulance service)
~ Shickshinny Fire Department (fire)
~ Nescopeck Ambulance Association (ambulance service)
~ Hobbie Volunteer Fire Company (ambulance service)
~ Pond Hill-LillyLake Fire Company (ambulance service)
~ Hunlock Creek Ambulance Association (ambulance service)
~ Berwick Ambulance Association (ambulance service)
~ Berwick Hospital Paramedic Unit (ambulance service)
~ Berwick Hospital (medical treatment)
~ Geisinger Medical Center (backup medical treatment and Life Flight helicopter service)
~ Pennsylvania State Police (traffic control and other assistance)
~ Reliance Fire Co. (fire) 6.35 Off- it Su ortServi s An emergency at SSES may require additional technical services and equipment. This type of assistance may be obtained from the organizations listed in Table 6.3. /
64 OORDINATI NWITHPARTI IPATING VERNMENTA ENCIE The ED, and upon EOF activation, the RM, ensures that off-site authorities are notified and apprised of emergency events at SSES.
Notification of an Unusual Event is primarily to ensure that the authorities are cognizant of the details of events which may arouse public concern and initiate inquiries by news media or members of the public.
Rev. 22, 04/95 6-14
6.4,1 Count A encies LCEMA and CEMA provide for:
~ Planning and coordination with municipal, State and Federal authorities.
~ Initial response to noti6cation by SSES.
~ Alert and warning of local populations within the 10 mile EPZ.
~ Evacuation and other protective measures for local populations within the 10 mile EPZ.
~ Emergency services.
~ Situation analysis.
~ Operation of county EOC.
LCEMA and CEMA also provide direction for the local organizations which are assigned action or support responsibilities under their plans.
The primary method of notification to LCEMA and CEMA is via the Centrex Telephone Network (CTN). Secondary methods are radio and regular telephone.
6.4.2 State A encies PEMA provides for:
~ Issuance of planning guidance.
~ Coordination of State response to nuclear incidents.
~ Coordination of multi-county Emergency Response Planning.
~ Provision for emergency public information.
~ Coordination of State agencies and departments.
DER/BRP provides for:
~ Technical consultation on Radiological and Plant conditions.
~ Accident assessment.
~ Recommendations for protective actions.
Rev. 22, 04/95 6-15
~ Recommendations for protection of potable water and food.
~ Recommendations for recovery and re-entry (off-site).
~ Operation of DER/BRP EOC.
Initially, SSES notifies PEMA, who, in turn, notifies DER/BRP. DER/BRP calls back to SSES to obtain radiological and plant condition information and establishes a communication link with SSES via CTN. Ifthe emergency warrants, DER/BRP responds to the EOF.
The primary method of notification to PEMA is via the Centrex Telephone Network (CTN).
CTN communications between SSES and DER/BRP are used for transmitting radiological and technical information/recommendations.
643 Federal A encies As detailed in the Federal Radiological Emergency, Response Plan (FRERP), the Federal government maintains extensive capabilities to assist states and licensees in responding to radiological emergencies. The ED, and upon EOF activation, the RM are authorized to request Federal assistance. Such requests should be coordinated with PEMA and/or DER/BRP.
N~R - designated Lead Federal Agency (LFA) under the FRERP.
The primary method of notification to the NRC is via the Emergency Notification System (ENS).
Upon notification of an emergency classification, the NRC will enter one of several response modes based on the severity of the event. Response modes include:
Normal (Increased Regional Monitoring)
Standby Initial Activation Expanded Activation In the Normal and Standby modes, NRC site presence is provided by the Resident Inspectors who typically observe activity in the Control Room and TSC. On Initial Activation, a site team will be dispatched with 15-25 individuals that can arrive at the site within several hours. Response assignments are primarily at the EOF, with a few individuals located at the MOC, TSC, Control Room and OSC. Ifconditions warrant, the NRC can go to Expanded Activation, where the NRC Lead for the response is shHted from NRC Headquarters Operations Center to the NRC Leader of the Site Response Team. Assigned locations are similar to the initial site team.
~DE - provides radiological monitoring and assessment assistance.'he primary method of notification to DOE is by telephone, although assistance is typically requested through the Lead Federal Agency (NRC) or through the State (DER/BRP). Initial DOE response is by a Radiological Assistance Program (RAP) team dispatched from the DOE Rev. 22, 04/95 6-16
Brookhaven Area OKce. This team of 4-6 people can arrive within eight hours and would operate primarily out of the EOF.
Ifthe situation necessitates additional technical assistance, DOE can set up and staff a Federal Radiological Monitoring and Assessment Center (FIMAC) in the vicinity of SSES. A FRMAC, which draws DOE resources and personnel from its Nevada Operations OfBce, can be operational within about 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The location of such a center would be selected based on actual radiological deposition patterns. The Federal FRMAC team is initially managed by DOE, with personnel also provided by NRC, EPA, USDA, HHS, and other agencies. The State and PP&L would assign personnel to the FRMAC to coordinate monitoring activity. As many as 200 people could be assigned to a fully functioning FRMAC.
FEMA - responsible for coordinating all Non-technical Federal response.
Ifthe emergency situation has warranted implementation of the Federal Plan (FRERP), FEMA will set up and staff a Federal Response Center (FRC) in the vicinity of SSES. The location of such a center. would be selected based on current needs and conditions. Access to all Federal non-technical assistance is through the FRC where representatives of participating agencies are based. As many as 100 people could be assigned to a fully functioning FRC.
her Federal A ncie In addition to NRC, DOE and FEMA, 14 other Federal agencies are available to provide assistance under the Federal Plan (FRERP). The extent of participation depends on the nature and magnitude of the event. A full listing of these agencies and description of their missions is found in the Federal Plan (FRERP).
Additional information on available resources can be found in NUREG-1442/ FEMA-REP-17, "Post-Emergency Response Resources Guide."
in Inf rma i n enter The Federal Plan (FRERP) provides for each participating agency to be represented at a Joint Information Center, along with the State and the facility licensee. For Susquehanna, it is expected that these parties will agree to utilize PP&L's MOC to fulfill this on-scene Joint Information Center role.
R ore Av' F dr Re one A. Lodging and Food Service - Lodging and food service for personnel operating from the FRlVfAC, FRC and JIC are available from local commercial resources in the Wilkes-Barre, Hazleton, and Bloomsburg areas.
B. Communications - Capability provided by DOE and FEMA, supplemented by standard telephone service to be established when facilities are selected, are adequate for the FRMAC and FRC.
Rev. 22, 04/95 6-17
C. Security - Security arrangements for the FRMAC and FRC can be made by the DOE and FEMA, respectively, with local resources.
D. Transportation - Federal response personnel will provide their own transportation by renting commercially available vehicles.
E. Airport - Wilkes-Barre/Scranton International Airport, Avoca, Pennsylvania.
6~6T QN The PP&L NERO continues to provide appropriate emergency response functions until such time as the emergency has been terminated or the PP&L Corporate Management Committee (CMC) has approved the implementation of a long-range restoration organization. Termination from an emergency condition is through joint evaluation by the organizations involved. In the case of a severe emergency involving o6-'site consequences, this would include the Recovery Manager,
. DER/BRP, and NRC. The Sr. Vice President-Nuclear requests that the CMC establish a restoration organization when the following guidelines have been met:
~ In-plant systems are stable, adequate core cooling established and contingency systems and plans available.
~ In-plant radiation levels are stable or are decreasing with time.
~ Releases of radioactive material to the environment are under control or have ceased.
~ Any fire, flooding or similar emergency conditions are under control or have ceased.
Although planning for restoration varies according to the emergency, a long-term restoration organization that is general in nature has been defined. The restoration organization is a project-type organization with their major activities conducted from the EOF. This organization is
'depicted in Figure 6.6 and major responsibilities are defined below.
~ Rest ra ion Mana r - A designated officer or senior manager from PP&L qualified to manage SSES restoration operations.
~ Plant rati ns M a er - A designated manager from PP&L qualified to control plant operations including security.
~ Technical Su ort Mana er - A designated manager from PP&L qualified to manage a technical group.
~ f Mana er Radiolo 'cal ontrol and Waste Mana ement - A designated manager qualified to manage the radioactive waste and radiological control aspects.
~ n ructi n Mana r - A designated manager qualified to coordinate the activities of PP&L, NSSS supplier and construction forces on proposed plant modifications or other construction support.
Rev. 22, 04/95 6-18
~ Adviso u ort Function - Advisory support consists of senior representatives of the NSSS supplier, the NRC, and special consultants.
~ Schedulin lannin Mana er - A designated manager to coordinate plans and schedules for the Restoration Manager.
~ Administration and Lo istics Mana er - A designated manager who is responsible for providing administrative, logistic, communications and personnel support.
~ Pu lic Information Mana er - A designated manager qualified to manage public relations activities.
During restoration operations, the radiation exposure limits of 10CFR20 apply. Compliance with those limits are the responsibility of the Restoration Manager via the applicable Health Physics organization.
At the time of declaring that an emergency has entered the restoration phase, the Restoration Manager is responsible for providing notification to all applicable agencies.
Restoration actions that plan for, or may result in, radioactive release are evaluated by the Restoration Manager as far in advance of the event as is possible. Such events and data are reported to the appropriate off-site emergency response organizations and agencies prior to initiating release.
.Rev. 22, 04/95 6-19
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AS SOON AS 'AJOR FUNCTIONAL POSITION TITLE AVAILABILITY REASONABLY AREA LOCATION MAJOR TASKS OR EXPERTISE ON SHIFT 3040 MIN. POSSIBLE Damage Control OSCnSC Overall Coordination OSC Coord.
Radio Comm.
Mgmt. of Damage Damage Control Control Teams Team Cooid.
TSC Radio Comm.
Chemistry Sampling Chemistry Tech Mechanical Repair Mech. Maintenance 1 Electrical Repair Elec. Maintenance 1 l&C Repair l&C Tech. 1 Radwaste 0 s. Radwaste 0 rator 1 Fire Fi htin Local Su rt Rescue/First Aid Local Su rt Site Access Control On Station Security, Comm., Security SS 1
& Personnel Personnel Accountability Security Ass't SS 1 Accountability Secunty Controlr 2 Emerg. Sec. Mgmt. Security Officers 10 TSC Securit Coord.
Technical Control Room Engig. & Eval. Shift Tech. Adv.
Assessment and TSC Mgmt. of Support Tech. Support Operations Support Resources Coordinator Operations Coord.
EOF Mgmt. of Support Site Support Mgr.
Resources Rev. 22, 04/95 Page 1
.'! i.'-;:;":ll:i':-.".-."..=.".!: '-':.':.';:",';"';:-".;MINIMVNl.':ONITE "AND.:.OFF,-',SITE:EINERGENCY:-'ORGANIZATION::.C MAJOR AS SOON AS FUNCTIONAL POSITION TITLE AVAILABILITY REASONABLY AREA LOCATION MAJOR'ASKS OR EXPERTISE ON SHIFT 3040 MIN. POSSIBLE Technical TSC Engineering Eval. & Reactor Assessment 8 Operations Support Engr. /Thermal 1 Operations Support Hydraulics 1 (Cont'd.) l&C Engr. 1 Chemistryl 1 Radiochemistry Mechanical Engr.
Overall Plant Design Mechanical Systems GOESC Engineering Eval. & Plant/Refueling Operations Support Operations Fire Protection Chemical Engr.l Radiochemistry Radwaste Mgmtl Decontamination Plant Maintenance Vendor/AE Support Engr. Support Mgr.
EOF Engineering Eval. 8 Overall Plant Design 0 rations Su rt Plant Operations Control Room Establish and maintain Shift Supv.(SRO) 1 and Assessment of and/or Plant safe shutdown condition Unit Supv.(SRO) 1 Operational Aspects Proper Control Room Operator 2 (RO)
Non-Licensed 0 rators Rev. 22, 04/95 Page 2
MAJOR AS SOON AS FUNCTIONAL POSITION TITLE AVAILABILITY REASONABLY AREA LOCATION MAJOR TASKS OR EXPERTISE ON SHIFT 3040 MIN. POSSIBLE Emergency Direction Control Room Overall Emergency Shift Supv.
and Control TSC Management 8 Emergency Dir.
EOF Cootdination Recove M r.
Notification/ Control Room Notify PP&L, State, Local Comm. Coord.
Communication TSC 8 Federal personnel & Comm. Coord. 2 EOF maintain communication Comm. Coord. 2 SCC Securit Controller Radiological TSC Overall Mgmt. & Rad. Protection Accident Coordination Coordinator Assessment & EOF Overall Mgmt. & Rad. Support Mgr.
Support of Coordination Operational Accident Survey Team Pers. 2 2 Assessment TSC On-Site Surveys Survey Team Pers. 2 4 EOF Off-Site Surveys Health Physics 2 2 OSC Radiation Protection Trained Personnel o Access Control o HP Coverage o Personnel Monitoring o Dosimetry OSC Radiochemistryl Chemistry Tech.
Chemistry Analysis Rev. 22, 04/95 Page 3
MAJOR AS SOON AS FUNCTIONAL POSITION TITLE AVAILABILITY REASONABLY AREA LOCATION MAJOR TASKS OR EXPERTISE ON SHIFT 3040 MIN. POSSIBLE Radiological EOF Accident Assessment 8 Plant Operationsl Accident Characteristics Refueling Ops.
Assessment 8 Fire Protection Support of Chemical Operational Accident Engr'adiochemistry Assessment (cont'd) Radwaste MgmtJ Deconta min ationl Rad Control/HP Plant Maintenance 1 EOF Offite Dose Gale. and Rad Assessment Team 2 Assessment Rev. 22, 04/95 Page 4
SUSQUEHANNA SES ORGANIZATION Senior Vice President Nudear Vice President Nudear Operations Manager Nudear Phnt Manager Nudear Manager Nudear Training Operations UfncU Ulll Supenrisor Plant SupeNhor Maintenance Supenrisor Malnt. Supervisor ENuents Shift Supervhor Development Scheduhng Production/Outage Producthn Senrices Management Susquehanna S
Production Su NSS F nctional Team Supervisor Site Supenrisor Nudear Supenrisor Reactor Maint. Senrices Supervhor Support Services Instruction Engineering r in Production Su Funcional Team Maint. Phnning Supervisor Health Supevisor Operations Su Information Phys@a Engineering S
Production Su Hect'unctional Malnt. Electrical Team Supenrisor Upeivisor Supenrisor Ghemhtry Operators Instruction Production S l&G Fncttcnaal Team MainL l&G Supervhor Manager Nudear Bahnce of Phnt Procurement Suiienrisor Susquehanna Steam Ehctric Station Units 1 and 2
'mergency Phn SUSQUEHANNA SES ORGANIZATION
SUSQUEHANNA SES ORGANIZATION Senior Vice President Comptroller Nuclear Advocate Superintendent of Plant SSES Manager Hanager Hanager Manager Nuclear Haintenance Nuclear Plant Services Nuclear Security Nuclear Operations Supervisor Supervisor Supervisor Supervisor Oay Shift Supervisor Maintenance Outage/ Maint. Production Plant Scheduling Security Operations Operations Production Services Supervisor Supervisor 6 Individuals Effluents Management Security Training Shift Supervisors Supervisor Shifts A-F Supervisor IKC Production Supervisor Testing Team Haintenance Supervisor Supervisor Planning Site Services Security Support Supervisor Supervisor Reactor Engineering Supervisor Valve Team NSSS Team Supervisor Supervisor Supervisor Prod. Services Health Physics Site Access Services Supervisor Operations Supervisor S Contractors Engineering Supervisor Predictive Balance of Haintenance Supervisor Plant Team Radiological Operation Supervisor Operations Technical Support Supervisor Supervisor Electrical Chemistry Lead Engineer Shift Team Technica'I Advisors Rev. 18 05I93 Susquehanna Steam Electric Station Units 1 end 2 Emergency Plan SUSQUEHANNA SES ORGANI ZAT ION FIGURE 6.1
2;O'CRONVMS 2.1 ANS-'RI-Alert Notification System 2.2 Alternate Rod Insertion 2.3 ARM- Area Radiation Monitors 2.4 CAM- Continuous Air Monitors 2.5 CCDES- Columbia County Department of Emergency Services 2.6 CR- Control Room 2.7 CREOASS- Control Room Emergency Outside Air Supply System 2.8 CTN- Centrex Telephone Network 2.9 DAC Derived Air Concentration 2.10 DCC- Document Control Center 2.11 DEP/BRP- Department of Environmental Protection/Bureau of Radiological Protection 2.12 DOE- U.S. Department of Energy 2.13 EAL- Emergency Action Levels 2.14 ECCS- Emergency Core Cooling Systems 2.15 'D- Director at Susquehanna SES
'mergency 2.16 EMA- Emergency Management Agency, 2.17 EMC- Emergency Management Coordinator (Municipality) 2.18 EOC- Emergency Operations Center 2.19 EOF- Emergency Operations Facility 2.20 EP- Emergency Plan of Susquehanna SES 2.21 EPA Environmental Protection Agency 2.22 EP-PS- Emergency Plan Position Specific Instructions 2.23 EPZ- Emergency Planning Zone 2.24 ERDS- Emergency Response Data System 2.25 ERF- Emergency Response Facility 2.26 ETN- Electronic Tandem Network 2.27 FEMA- Federal Emergency Management Agency 2.28 FPC- Fuel Pool Cooling 2.29 FSAR- Susquehanna SES Final Safety Analysis Report, Units 1 and 2 2.30 FTS- Federal Telecommunications System 2.31 HHS Health and Human Services 2.32 HPCI- High Pressure Coolant Injection System 2.33 LCEMA- Luzerne County Emergency Management Agency 2.34 LCO- Limiting Condition for Operation 2.35 LER- License Event Report 2.36 LOCA- Loss of Coolant Accident 2.37 MIDAS Meteorological Information and Dose Assessment System 2.38 MOC- Media Operations Center 2.39 MSIV- Main Steam Isolation Valve, 2.40 MSL- Main Steam Line 2.41 NEP Nuclear Emergency Planning 2.42 NERO- Nuclear Emergency Response Organization at PP&L Rev. 24, 06/96 2-1
2.43 NRC -, Nuclear Regulatory Commission 2.44 NSSS Nuclear Steam Supply System 2.45 ODCM- Offsite Dose Calculation Manual 2.46 OSC- Operations Support Center 2.47 PAGs- Protective Action Guides from EPA 2.48 PASS- Post Accident Sampling System 2.49 PCS- Plant Computer System 2.50 PEMA- Pennsylvania Emergency Management Agency 2.51 PICSY- Plant Integrated Computer System 2.52 PNS- Public Notification System 2.53 PORC- Plant Operations Review Committee 2.54 PP8cL- Pennsylvania Power k, Light Company 2.55 PSP- Pennsylvania State Police 2.56 RCIC- Reactor Core Isolation Cooling 2.57 RDAS- Remote Data Analysis System 2.58 RHR- Residual Heat Removal 2.59 RPS- Reactor Protection System 2.60 Rx- Reactor 2.61 SCC- Security Control Center 2.62 SDS- Satellite Display System 2.63 SGTS- Standby'as Treatment System 2.64 SLC- Standby Liquid Control 2.65 SOP- Special Office of the President 2.66 SPDS- Safety Parameter Display System 2.67 SPINGs- System Particulate, Iodine, and Noble Gas Monitor (Vent Monitoring System) 2.68 SRC- Susquehanna Review Committee 2.69 SSE- Safe Shutdown Earthquake 2.70 SSES- Susquehanna Steam Electric Station 2.71 TR- Temperature Recorder 2.72 TSC- Technical Support Center 2.73 UMC- Unit Monitoring Console (PCS) 2.74 UPS- Uninterruptable Power Supply 2.75 USDA- United States Department of Agriculture Rev. 24, 06/96 2-2
3'O'EFERENCES 3.1 CCDES Emergency Plan - Radiological Emergency Response Plan for incidents at the Susquehanna Steam Electric Station 3.2 DEP/BRP Emergency Plan - Bureau of Radiation Protection "Plan for Nuclear Power Generating Station Incidents" 3.3 NRC Generic Letter 91-14, "Emergency Telecommunications" 3.4 LCEMA Emergency Plan - Radiological Emergency Response Plan for Incidents at the Susquehanna Steam Electric Station.
3.5 NUREG 0654/FEMA-REP Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness In Support of Nuclear Power Plants.
3.6 NUREG 0696 - Final Report - Functional Criteria for Emergency Response Facilities.
1 3.7 NUREG 0737 - Clarification of TMI Action Plan Requirements.
3.8 NUREG 1392 - Emergency Response Data System Implementation 3.9 PEMA Emergency Plan - Annex E to Commonwealth of Pennsylvania "Disaster Operations Plan", Nuclear Incidents (Fixed Facility).
3.10 . Susquehanna SES Emergency Plan Position Specific Procedures.
3.11 Susquehanna SES Letters of Agreement with off-site emergency organizations.
3.12 Susquehanna SES Physical Security Plan and Security Training and Qualifications Plan.
3.13 Susquehanna SES Plant Procedures.
3.14 10CFR Part 50 - Domestic Licensing of Production and Utilization Facilities 3.15 Susquehanna SES Alert and Notification Design Report 3.16 SSES Preparedness, Prevention and Contingency Plan 3.17 SSES Hazardous Material Emergency Off-Site Emergency Response Plan 3.18 EPA 400-R-91-001 - Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 3.19 NRC Letter dated April 17, 1996, MOVING THE EOF TO THE NORTHEAST DIVISION HEADQUARTERS (TAC NOS. M91377 AND M91378), Docket Nos. 50-387/50-412 Rev. 24, 06/96 3-1
4.0 SCOPE AND-CONTENTS SSES includes two boiling water reactor electrical generating units. The station is located in Salem Township, Luzerne County, in east central Pennsylvania, about five miles northeast of Berwick, Pennsylvania (See Figure 4.1). This Emergency Plan applies to the operation of Unit 1 and Unit 2.
This Plan provides guidance for both on-site and off-site emergency situations. It ranges in scope from relatively minor events and occurrences involving small releases of radioactive material, up to and including a major. nuclear emergency having significant off-site radiological consequences. This Plan, together with the state, county, and municipal radiological emergency response plans, provides detailed guidance and direction for taking emergency measures by the NERO to ensure the health and safety of the public living within the 10-mile EPZ of SSES.
Additional guidance is provided in state and county plans for ingestion pathway preventive measures out to 50 miles (See Figure 4.2).
Additional guidance on specific emergency actions for non-radiological releases of hazardous materials can be found in two other emergency plans: the SSES Preparedness, Prevention, and Contingency Plan and the SSES Hazardous Material Emergency Off-Site Response Plan.
This Plan provides for a graded response for distinct classifications of emergency conditions, action within those classifications, and criteria for escalation to another classification. This classification system is also used by PEMA, DEP/BRP, LCEMA AND CCDES. This system is covered in Section 5.0.
The PP&L organization for control of emergencies begins with the on-shift station personnel and contains provisions for augmentation and extension to include other station personnel, PP&L corporate personnel, and outside emergency response organizations.
The total emergency program includes the support of state, federal and local emergency organizations. Detailed provisions are made for implementing protective measures against direct radiation exposure for the public within a radius of at least ten miles from the SSES. Additiorial preventive measures may be taken beyond that distance to preclude ingestion pathway exposures.
Specific agreements are also made with local off-site support organizations to provide fire fighting, medical, law enforcement, and traffic control services.
Rev. 24, 06/96 4-1
State, County and Federal agencies have lead responsibilities specifically related to this Plan.
Organizational control is covered in Section 6.0.
The mechanisms through which this Plan provides for the proper response to emergency conditions at SSES include identification of the event, initial and ongoing assessment, and initial and ongoing emergency actions. Emergency actions include classification of event, completion of notifications, activation of onsite and offsite NERO, requests for offsite assistance, implementing onsite protective actions, recommending offsite protective actions, and activation of the restoration organization. These mechanisms are discussed in Section 7.0.
Emergency facilities and equipment are provided to ensure the capabilities for prompt, efficient assessment and control of situations over the entire spectrum of probable and postulated emergency conditions. The facilities and associated equipment and their emergency functions are described in Section 8.0.
A concept of in-depth preparedness is employed regarding the SSES emergency program. This concept is emphasized in the training program and in preparedness drills and exercises.
Personnel are trained to provide an in-depth response capability for required actions in an emergency situation. Section 9.0 includes the means to achieve and maintain preparedness and to ensure maintenance of an effective emergency program.
Rev. 24, 06/96 4-2
6.0 ORGANIZATIONALCONTROI OF EMERGENCIES PP&L's Emergency Plan is based upon a four phase approach to accident response and mitigation.
(Reference Figure 6.3 and Table 6.1).,: Phase I consists of identification of. the emergency condition, initiation of prompt corrective action and initiation of prompt notification to local, state and federal agencies as well as appropriate members of PP&L's NERO. This initial phase is implemented by the on-shift organization. The on-shift organization has been staffed and trained to be capable of both safely operating the unit and quickly and effectively responding to an emergency condition. Initially, the Shift Supervisor, the highest ranking management individual on-shift, will assume the role of ED.
The Shift Supervisor, as ED:
a) Classifies the condition.
b) Initiates corrective'actions and coordinates emergency management activities.
c) Designates a communications coordinator to notify off-site agencies and initiate call-in of selected personnel.
d) Notifies plant personnel over the PA system for accountability and/or evacuation.
e) Designates an OSC Coordinator who organizes and directs in-plant emergency team functions.
Notifies the Plant Manager-Susquehanna SES or his designated alternate, informs him of if the situation, and requests relief appropriate. For conditions under an Unusual Event the Shift Supervisor is likely to remain as ED through termination of the condition, due to P robable short duration or low severit y of the event.
g) Ensures that on-site emergency response individuals and groups are notified, using the PA system or direct communications. Depending on the nature and severity of the condition, TSC staffing may be called out.
h) Ensures that initial dose projections are done and makes resulting recommendations regarding off-site protective actions.
(
i) Ensures that off-duty station personnel are notified to assist as necessary with emergency activities. These notifications are made, via the radio paging system or by telephone backup, to individuals designated for off-duty availability status to fill key emergency response positions. Those key positions are identified in Sections 6.2 and 6.3. Other off-duty personnel are called in as required.
Rev. 24, 06/96 6-1
Upon activation of Phase II, additional personnel are available, and control and dissemination of in-plant teams shifts from the OSC to the TSC.
- (Reference Figure 6.3 and Table 6.2) Upon notification by the on-shift organization, the Plant Manager-Susquehanna SES or his designated alternate, reports to the site to assume the role of ED. Support coordinators and staffs in areas of technical assessment, radiological assessment and operational coordination also report to the site. These individuals form the nucleus of the ED's Team and activate the TSC. The TSC is fully functional within 30 to 60 minutes of initial notification. As the Plant Manager-Susquehanna SES and his support coordinators arrive, they are briefed by the Shift Supervisor and then, in turn, assume responsibility from the, Shift Supervisor for their particular areas of expertise. Emergency management activities, including communications, are under the control of the Emergency Director or his designated alternate; dose projection and assessment activities are directed by the Radiation Protection Coordinator; technical expertise is directed by the Tech Support Coordinator, the Operations Coordinator oversees Operations activities and the Damage Control Team Coordinator oversees in-plant damage control actions. The TSC takes over all emergency management and support activities from the on-shift organization, freeing tom to devote their efforts towards establishing and maintaining the plant in a safe, stable condition.
V - (Reference Figures 6.2, 6.4, and Table 6.2). This organization staffs the Emergency Operations Facility to provide in-depth technical and off-site radiological assessment.
The Emergency Operations Facility is" activated automatically at an Alert or higher emergency classification., Upon activation of the Emergency Operations Facility, personnel shall report to the EOF and be prepared to take over management of the emergency from the TSC at a Site Area Emergency or higher classification. When the initial emergency classification is a Site Area Emergency or higher, the EOF will take over the management of the emergency within 90 minutes of the declaration of a Site Area Emergency. At the discr'etion of the Emergency Director or Recovery Manager, the EOF can be activated and take over management of the emergency earlier.
Functional operation will include:
~ Management of overall emergency response
~ Coordination of radiological and environmental assessment
~ Determination of recommended protective actions
~ Coordination of emergency response activities with Federal, State, local county and municipal agencies
- This phase leads ultimately to the return to service of the unit. The organizational and philosophical concepts that are utilized during this phase are highly dependent upon the nature of the emergency. The restoration phase does not begin until there is complete t
Rev. 24, 06/96 6-2
assurance that the plant is in a stable shutdown condition and that there are no inadvertent or unplanned significant release of radioactivity to the environment.
... The normal Operating Organization during working hours is illustrated in Figure 6.1. Minimum shift response during off-hours is as follows:
1 Shift Supervisor (SRO) 1 Unit Supervisor (SRO) 1 Assistant Unit Supervisor (RO)
. 2* Licensed Operators (RO)
I Shift Technical Advisor 3* Non-Licensed Ope'rators 1* Health Physics Technician 1 Chemistry Technician 1 Security Shift Supervisor 1 Assistant Security Shift Supervisor 10 Security Officers per unit The Shift Supervisor assumes the role of ED until he is relieved by the Plant Manager-Susquehanna SES, or his designated alternate. Typical alternate is the Manager - Nuclear Maintenance. When the TSC is activated, and the Shift Supervisor is relieved, the Shift Supervisor reassumes responsibility for plant operating functions in the control room.
The Shift Supervisor ensures that the Plant Manager-Susquehanna SES, or designated alternate, is promptly notified of an emergency condition.
The ED assumes full responsibility for the implementation and administration of the Emergency Plan and is responsible for assuring continuity of resources until he relinquishes those responsibilities to the Recovery Manager. The responsibility and authority of the ED are set forth in Appendix E.
The ED cannot relinquish any of the above responsibilities until the arrival of and assumption of responsibilities by the Recovery Manager at the EOF. At that time, he may relinquish any of the above responsibilities gzggg those related to maintaining the Unit in a safe shutdown condition with adequate core cooling and no uncontrolled radioactive material releases.
Rev. 24, 06/96 6-3
If the ED cannot perform this function during the emergency, he will be succeeded by the Operations Coordinator until another qualified Emergency Director arrives to assume this responsibility.
Functional responsibilities of the ED include:
a) Immediately upon notification of an existing or potential emergency, report to the Control Room and initiate assessment activities, including classification of the if emergency and dose projections appropriate.
b) Unilaterally implement the immediate on-site corrective and protective actions to bring the incident under control and mitigate its effects.
c) Assure that appropriate notifications and recommendations to off-site organizations are made within 15, minutes.
d) Appoint Emergency Coordinators for assistance with current and continuing emergency control, but assume those responsibilities until the positions are filled.
e) Augment the on-site NERO with duty roster personnel and other available station staff members as dictated by the emergency condition.
')
Continue reassessment of emergency status and make appropriate recommendations including protective actions to off-site organizations.
g) Ensure that information released is accurate and released through the proper channels.
h) Activate Emergency Facilities described in Section 8.0.
i) Assign technical liaison to EOCs ifrequested.
j) Communicate with and provide information to the Recovery Manager and the Public Information Manager.
k) Issuance of Radioprotective Drugs in accordance with prescribed procedures and should include consultation with the Radiation Protection Coordinator and medical consultants.
l) Taking essential corrective action which may involve the risk of emergency radiation exposure to NERO personnel. Table 7.2 provides the basic criteria for this decision.
m) Request Federal assistance to augment NERO capabilities as necessary. Such requests
[
should be coordinated with PEMA and/or DEP/BRP.
Rev. 24, 06/96 6-4
This position is filled by the Day Shift Supervisor or a designated alternate. Typical alternates are SRO qualified personnel.
Responsibilities:
a) Direct Control Room and in-plant operational activities through the Shift Supervisor.
b) Advise the ED on plant operations.
This position is initially filled by a Plant Control Operator. When the TSC is activated this position is typically filled by simulator instructors from the Susquehanna Training Center.
Responsibilities:
a) Make proper notification to off-site organizations.
b) Initiate call-in procedures as requested by the ED.
c) Function as liaison for emergency-related communications between the ED and on-site and off-site emergency groups.
d) Maintain communications with the NRC.
e) Maintain records concerning the emergency.
This position is filled by qualified Health Physics personnel when the TSC is activated.
Responsibilities:
a) Communicate radiological data to the NRC via the Health Physics Network.
This position is filled by the Health Physics Supervisor. Typical alternates for this position are the qualified Health Physics personnel.
Responsibilities:
a) Perform dose projections.
Rev. 24, 06/96 6-5
b) Provide radiological advice to the ED concerning on-site emergency activities.
c) Provide protective action recommendations to the ED.
d) Maintain communication with and provide information to the Dose Assessment [
Supervisor.
e). Maintain communication with and provide radiological information to DEP/BRP until relieved by the Dose Assessment Supervisor.
f) Provide on-site radiation monitoring personnel for eAluent release assessment.
g) Provide radiation monitoring personnel for emergency team efforts.
h) Direct personnel and area contamination control and decontamination activities.
i) Provide dose projections to the Dose Assessment Supervisor.
j) Perform initial off-site environmental assessment until relieved by the Dose Assessment Supervisor.
This position is filled by System Engineering supervisory personnel.
Responsibilities:
a) Analyze mechanical, electrical, and instrument and control problems; determine alternate solutions, design and coordinate the installation of short-term modifications.
b) Analyze thermohydraulic and thermodynamic problems and develop solutions.
c) Assist in the development of procedures necessary for conducting emergency operations.
d) Analyze conditions and'develop guidance for the ED and operations personnel.
e) Resolve questions concerning Operating License requirements with NRC representatives.
f) Maintain lead technical responsibility, coordinating dissemination of technical work assignments to EOF.
g) Maintain communication with and provide technical information to DEP/BRP l Technical.
Rev. 24, 06/96 6-6
This position is filled by the Supervisor - Site Support. Typical alternates are Site Support management personnel.
Responsibilities:
a) Coordinate provisions for transportation, food, and other logistical support for emergency personnel.
b) Provide personnel and work schedules for relieving emergency personnel.
c) Act as liaison with outside groups in providing additional resources such as manpower, equipment, supplies, and transportation.
This position is filled by the Manager - Nuclear Security. The typical alternate for this position is a Security Supervisor.
Responsibilities:
a) Maintain plant security 'and institute appropriate contingency measures.
b) Account for personnel in accordance with EP-PS's.
This position is filled by the Assistant Unit Supervisor. If the AUS is unavailable the Shift Supervisor will designate a replacement.
Responsibilities:
a) Direct the activities of the in-plant Emergency Teams such as damage control, fire brigade and first aid and rescue until relieved by the TSC.
The fire brigade leader is the Assistant Unit Supervisor. However, the coordination of various team activities is the responsibility of the OSC Coordinator.
b) Coordinating the availability and assignment of personnel supporting activities for the ED and other NERO managers until relieved by the TSC.
Rev. 24, 06/96 6-7
The Damage Control Team Coordinator position is filled by Maintenance supervisory personnel.
A typical alternate would be the Maintenance Production Services Supervisor.
Responsibilities:
a) Ensure damage control resources are allocated on the right priorities by assigning tasks
~ to available resources.
b) Dispatch in-plant teams.
c) Communicate with Operations and the Technical Support Coordinator.
This position is filled by a Maintenance Engineer.
Responsibilities:
a) Maintain radio communications with all in-plant teams.
b) Maintain an up-to-date status of in-plant radiological conditions.
c) Track dose levels of in-plant team members.
The Maintenance Coordinator position is filled by Maintenance Management personnel. The I&C Coordinator position is filled by I&C Management personnel.
Responsibilities:
a) Organizing, briefing, dispatching, and directing, as necessary, the on-site damage control teams.
b) Providing personnel assistance and support to in-plant teams as necessary.
c) Supporting technical group activities'and operations as necessary.
The Chemistry Coordinator position is filled by an ANSI qualified chemist. A typical alternate for. this position would be a'Senior Chemist.
Rev. 24, 06/96 6-8
Responsibilities:
a) Assemble and direct the activities of chemistry personnel to assure information on plant status is accurate and available.
F Notification of the Recovery Manager is made for all levels of e'mergencies by the Communicators in the Control Room or TSC. An on-call duty roster is kept in the CR and TSC.
At the discretion of the Recovery Manager, the EOF can be activated at an Unusual Event.
Activation of the .EOF is automatic at an Alert, Site Area Emergency, or:.General Emergency classification. NERO is notified of the facility activation by the Alternate Security 'Control Center using the Telenotification System.
This position is filled by the Vice President-Nuclear Operations. The typical alternate is the Manager-Independent Evaluation Services.
If the Recovery Manager cannot perform this function during the emergency, he will be succeeded by the Assistant Recovery Manager.
Responsibilities:
a) Providing continuous coordination and evaluation of PP&L activities during an emergency having or potentially having environmental consequences.
b) Managing overall PP&L emergency response and assuring continuity of resources.
c) Acting as lead interface with off-site government agency officials.,'.
d) Assure appropriate notifications and recommendations to offsite organizations are timely.
e) Continue reassessment of emergency status and make appropriate recommendations including protective actions to off-site organizations.
f) Ensure that information released is accurate and made through proper channels.
g) Directing the activities of all other EOF managers.
Rev. 24, 06/96 6-9
h) Request Federal assistance to augment NERO capabilities as necessary. Such requests should be coordinated with PEMA and/or DEP/BRP.
r i) Notify PEMA Emergency Operations Center of Protective Action Recommendations.
j) Send a representative to the State and risk counties. If conditions result in implementation of the Federal Radiological Emergency Response Plan, assign a representative to the Federal Response Center, to the Federal Radiological Monitoring and Assessment Center, and to the Joint Information Center (most likely the PIM).
This position is filled by personnel qualified for the position of Recovery Manager.
'I Responsibilities:
a) Provide assistance as requested by the Recovery Manager.
b) Take over the position of Recovery Manager should the Recovery Manager be unable to perform his duties during an emergency.
This position is typically filled by Nuclear Engineering supervisory personnel.
Responsibilities:
a) Manage engineering support resources in the EOF.
b) Provide technical support to aid in decision making process.
This position is filled by the Manager-Nuclear Training. A typical alternate for this position is the Senior Project Engineer-Nuclear Training.
Responsibilities:
a) Provide analysis of in-plant data to the Recovery Manager.
b) Oversee formal communications leaving the EOF.
c) Oversee proper facility set up.
d) Provide administrative support.
Rev. 24, 06/96 6-10
e) Oversee security.
This position is filled by the Supervisor-Operations Technology. A typical alternate is the Supervisor - Environmental Services-Nuclear.
Responsibilities:
a) Evaluating the magnitude and effects of actual or potential radioactive releases from the plant.
b) Recommending appropriate off-site protective measures to the Recovery Manager.
c) Recommending appropriate emergency classifications to the Recovery Manager.
d) Communicating with the Radiation Protection Coordinator in the TSC and with DEP/BRP radiological personnel.
e) Controlling field monitoring teams.
This position is typically filled by engineering disciplines.
Responsibilities:
a) Assume responsibility from the TSC for off-site notifications.
b) Transmit information about the emergency to off-site organizations.
c) Function as liaison for questions received from other organizations.
d) Maintain a record of emergency notifications.
This position is filled by personnel from the Nuclear Licensing Group.
r a) Support the Recovery Manager with the off-site agency interface.
b) Provide technical assistance to the off-site agencies.
Rev. 24, 06/96 6-11
The ED ensures that the MOC (Figure 6.2) is promptly notified and provided with available details of the emergency. The MOC staff transmits information regarding the emergency and items of potential interest to municipal groups, initiates appropriate news releases and responds to questions 'from public information representative. AAer the Recovery Manager assumes control of the EOF, the Public Information Manager reports to the Recovery Manager.
This position is filled by the Special Assistant to the President - Susquehanna. Typical alternate is the Senior Public Information Specialist.
Responsibilities:
a) Serving as official company spokesperson.
')
Preparing and disseminating SSES information to the public via the news media.
c) Interpreting plant status information for the news media and other agencies.
d) Arranging for news media conferences.
e) Rumor control.
f) Establishes interfaces and coordinates news releases with the federal and state agencies in the MOC.
The ED ensures that appropriate off-site emergency support groups are contacted to provide the type and level of assistance which may be necessary to deal with the existing emergency condition. Organizations that may be contacted for assistance during an emergency condition at SSES are listed in Attachment A, Letters of Agreement. Methods available for contacting these
, support groups include direct telephone communications with individual organizations, use of the 911 telephone system for emergency services, and message relay through LCEMA or CCDES.
t An emergency at SSES may require additional technical services and equipment. This type of assistance may be obtained from the organizations listed in Table 6.3.
Rev. 24, 06/96 6-12
The ED, and upon EOF activation, the RM, ensures that off-site authorities are notified and apprised of emergency events at SSES.
Notification of an Unusual Ev'en/ is primarily to ensure that the authorities are cognizant of the details of events which may arouse public concern and initiate inquiries by news media or members of the public.
LCEMA and CCDES provide for:
~ Planning and coordination with municipal, State, and Federal authorities.
~ Initial response to notification by SSES.
~ Alert and warning of local populations within the 10 mile EPZ.
~ Evacuation and other protective measures for local populations within the 10 mile EPZ.
~ Emergency services.
~ Situation analysis.
~ Operation of county EOC.
LCEMA and CCDES also provide direction for the local organizations which are assigned action or support responsibilities under their plans.
The primary method of notification to LCEMA and CCDES is via the Centrex Telephone Network (CTN). Secondary methods are radio and regular telephone.
PEMA provides for:
Issuance of planning guidance.
~ Coordination of State response to nuclear incidents.
~ Coordination of multi-county Emergency Response Planning.
~ Provision for emergency public information.
Rev. 24, 06/96 6-13
~ Coordination of State agencies and departments.
DEP/BRP provides for:
~ Technical consultation on Radiological and Plant conditions.
~ . Accident assessment.
~ Recommendations for protective actions.
~ Recommendations for protection of potable water and food.
~ Recommendations for recovery and re-entry (off-site).
~ Operation of DEP/BRP EOC.
Initially, SSES notifies PEMA, who, in turn, notifies DEP/BRP. DEP/BRP calls back to SSES to obtain radiological and plant condition information and establishes a communication link with SSES via CTN. Ifthe emergency warrants, DEP/BRP responds to the EOF.
The primary method of notification to PEMA is via the Centrex Telephone Network (CTN).
CTN communications between SSES and DEP/BRP are used for transmitting radiological and technical information/recommendations.
As detailed in the Federal Radiological Emergency Response Plan (FRERP), the Federal government maintains extensive capabilities to assist states and licensees in responding to radiological emergencies. The ED, and upon EOF activation, the RM are authorized to request Federal assistance. Such requests should be coordinated with PEMA and/or DEP/BRP.
5EQ - designated Lead Federal Agency (LFA) under the FRERP.
The primary method of notification to the NRC is via the Emergency Notification System (ENS).
Upon notification of an emergency classification, the NRC will enter one of several response modes based on the severity of the event. Response modes include:
Normal (Increased Regional Monitoring)
Standby Initial Activation Expanded Activation In the Normal and Standby modes, NRC site presence is provided by the Resident Inspectors who typically observe activity in the Control Room and TSC. On Initial Activation, a site team will be dispatched with 15-25 individuals that can arrive at the site within several hours.
Rev. 24, 06/96 6-14
Response assignments are primarily at the EOF, with a few individuals located at the MOC, TSC,'Control Room and OSC. Ifconditions warrant, the NRC can go to Expanded Activation, where the NRC Lead for the response is shifted from NRC Headquarters Operations Center to the NRC Leader of the Site Response Team. Assigned locations are similar to the initial site team.
DQE - provides radiological monitoring and assessment assistance.
,~
The primary method of notification to DOE is by telephone, although assistance is typically requested through the Lead Federal Agency (NRC) or through the State (DEP/BRP). Initial DOE response is by a Radiological Assistance Program (RAP) team dispatched from the DOE Brookhaven Area Office. This team of 4-6 people can arrive within eight hours and would operate primarily out of the EOF.
1 Ifthe situation necessitates additional technical assistance, DOE can set up and staff a Federal Radiological Monitoring and Assessment Center (FRMAC) in the vicinity of SSES. A FRMAC, which draws DOE resources and personnel from its Nevada Operations Office, can be operational within about 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The location of such a center would be selected based on actual radiological deposition patterns. The Federal FRMAC team is initially managed by DOE, with personnel also provided by NRC, EPA, USDA, HHS, and other agencies. The State and PP8cL would assign personnel to the FRMAC to coordinate monitoring activity. As many as 200 people could be assigned to a fully functiorripg FRMAC.
EEhf5 - responsible for coordinating all Non-technical Federal response, If the emergency situation has warranted implementation of the Federal Plan (FRERP), FEMA will set up and staff a Federal Response Center (FRC) in the vicinity of SSES. The location of such a center would be selected based on current needs and conditions. Access to all Federal
~
non-technical assistance is through the FRC where representatives of participating agencies are based. As many as 100 people could be assigned to a fully functioning FRC.
yP "pg In addition to NRC, DOE, and FEMA, l4 other Federal agencies are available to provide assistance under the Federal Plan (FRERP). The extent of participation depends on the nature and magnitude of the event. A full listing of these agencies and description of their missions is found in the Federal Plan (FRERP).
Additional information on available resources can be found in NUREG-1442/ FEMA-REP-17, "Post-Emergency Response Resources Guide."
The Federal Plan (FRERP) provides for each participating agency to be represented at a Joint Information Center, along with the State and the facility licensee. For Susquehanna, it is Rev. 24, 06/96 6-15
expected that these parties will agree to utilize PP&L's MOC to fulfill this on-scene Joint Information Center role.
A. Lodging and Food Service - Lodging and food service for personnel operating from the FRMAC, FRC, and JIC are available from local commercial resources in the Wilkes-Barre, Hazleton, and Bloomsburg areas.
B. Communications - Capability provided by. DOE and FEMA, supplemented by standard telephone service to be established when facilities are selected, are adequate for the FRMAC and FRC.
C. Security - Security arrangements for the FRMAC and FRC can be made by the DOE and
~
FEMA, respectively, with local resources.
D. Transportation - Federal response personnel will provide their own transportation by renting commercially available vehicles.
E. Airport - Wilkes-Barre/Scranton International Airport, Avoca, Pennsylvania.
The PP&L NERO continues to provide appropriate emergency response functions until such time as the emergency has been terminated or the PP&L Corporate Leadership Council (CLC) has approved the implementation of a long-range restoration organization. Termination from an emergency condition is through joint evaluation by the organizations involved. In the case of a severe emergency involving off-site consequences, this would include the Recovery Manager, DEP/BRP, and NRC. The Sr. Vice President-Nuclear requests that the PP&L Corporate Leadership Council establish a restoration organization when the following guidelines have been met:
~ In-plant systems are stable, adequate core cooling established and contingency systems and plans available.
~ In-plant radiation levels are stable or are decreasing with time.
~ Releases of radioactive material to the environment are under control or have ceased.
~ Any fire, flooding or similar emergency conditions are under control or have ceased.
Although planning for restoration varies according to the emergency, a long-term restoration organization that is general in nature has been defined. The restoration organization is a project-type organization with their major activities conducted from the EOF. This organization is depicted in Figure 6.6 and major responsibilities are defined below.
Rev. 24, 06/96 6-16
d I manage SSES restoration operations.
d ff >> I g f PPALq IIII d
- A designated manager from PP&L qualified to control plant operations including security.
- A designated manager from PP&L qualified to manage a technical group.
-Ad*lg d g* q llf d g* d dl waste and radiological control aspects.
-Ad lg *d g* I llfld dl <<d III f PP&L, NSSS supplier, and construction forces on proposed plant modifications or other construction support.
- Advisory support consists of senior representatives of the NSSS supplier, the NRC, and special consultants.
- A designated, manager to coordinate plans and schedules for the Restoration Manager.
- A designated manager who is responsible for providing administrative, logistic, communications and personnel support.
- A designated manager qualified to manage public relations activities.
During restoration operations, the radiation exposure limits of 10CFR20 apply. Compliance with those limits are the responsibility of the Restoration Manager via the applicable Health Physics organization.
At the time of declaring that an emergency has entered the restoration phase, the Restoration Manager is responsible for providing notification to all applicable agencies.
Restoration actions that plan for, or may result in, radioactive release are evaluated by the Restoration Manager as far in advance of the event as is possible. Such events and data are reported to the appropriate off-site emergency response organizations and agencies prior to initiating release.
Rev. 24, 06/96 6-17
I TABLE 6.2 I
MINIMUMON-SITE AND OFF-SITE EMERGENCY ORGANIZATION CAPABILITIES MAJOR AS SOON AS FUNCTIONAL POSITION TITLE AVAILABILITY REASONABLY AREA LOCATION MAJOR TASKS OR EXPERTISE ON SHIFT 3040 MIN. POSSIBLE Damage Control OSCITSC Overall Coordination OSC Coord.
Radio Comm.
Mgmt. of Damage Control Damage Control .
Teams Team Coord.
TSC Radio Comm.
Chemistry Sampling Chemistry Tech.
Mechanical Repair Mech. Maintenance Electrical Repair Elec. Maintenance l8C Repair I&C Tech.
Radwaste Ops. Radwaste Operator Fire Fighting Local Support Rescue/First Aid Local Support Site Access Control On Station Security, Comm., Security SS 1
& Personnel Personnel Accountability Security Ass't SS 1 Accountability Security Controlr 2 Emerg. Sec. Mgmt. Security Officers 10 TSC Security Coord.
Technical Control Room Engrg. & Eval. Shift Tech. Adv.
Assessment and TSC Mgmt. of Support Tech. Support Operations Support Resources Coordinator Operations Coord.
EOF Mgmt. of Support EOF Support Supv.
Resources
- Available from Nuctear Engineering in Allentown Rev. 24, 06/96 Page 1
TABLE 6.2 (Continued )
NIINIMUMON-SITE AND OFFNITE E!NERGENCY ORGANIZATIONCAPABILITIES MAJOR AS SOON AS FUNCTIONAL POSITION TITLE AVAILABILITY REASONABLY AREA LOCATION MAJOR TASKS OR EXPERTISE ON SHIFT 3040 MIN. POSSIBLE Technical TSC Engineering Eval. 8 Reactor Assessment 8 Operations Support Engr. /Thermal Operations Support Hydraulics (Cont'd.) MC Engr.
Chemistry/
Radiochemistry Mechanical Engr.
Overall Plant Design Mechanical Systems EOF Engineering Eval. 8 Overall Plant Design Operations Support Fire Protection Chemical Engr./
Radiochemistry*
Radwaste Mgmt./
Decontamination Plant Maintenance" Vendor/AE Support'hift Plant Operations and Control Room Establish and maintain Supv. (SRO)
Assessment of and/or Plant safe shutdown condition Unit Supv. (SRO)
Operational Aspects Proper Control Room Operator (RO)
Non-Licensed Operators Emergency Direction Control Room Overall Emergency Shift Supv.
and Control TSC Management 8 Emergency Director EOF Coordination Recovery Manager
- Available from Nuclear Engineering in Allentown.
Rev. 24, 06/96 Page 2
TABLE 6.2 (Continued)
MINIMUMON-SITE AND OFF-SITE EMERGENCY ORGANIZATIONCAPABILITIES MAJOR AS SOON AS FONCTIONAL POSITION TITLE AVAILABILITY REASONABLY AREA LOCATION MAJOR TASKS OR EXPERTISE ON SHIFT 30-60 MIN. POSSIBLE Notification/ Control Room Notil'y PP8L, State, Local Comm. Coordinator Communication TSC 8 Federal personnel 8 Comm. Coordinator EOF maintain communication Comm. Coordinator SCC Security Controller Radiological TSC Overall Mgmt. 8 Rad. Protection Accident Coordination Coordinator Assessment 8 EOF Overall Mgmt. 8 Dose Assess. Supv.
Support of Coordination Operational Accident Assessment TSC On-Site Surveys Survey Team Pers.
EOF Off-Site Surveys Survey Team Pers.
OSC Radiation Protection Health Physics Trained Personnel o Access Control o HP Coverage o Personnel Monitoring o Dosimetry OSC Radiochemistry/ ~
Chemistry Tech.
Chemistry Analysis
- Available from Nuclear Engineering in Allentown.
Rev. 24, 06196 Page 3
TABLE 6.2 (Continued)
MINIMUMQN-SITE ANO OFF-SITE EMERGENCY ORGANIZATIONCAPABILITIES MAJOR AS SOON AS FUNCTIONAL POSITION TITLE 'VAILABILITY REASONABLY AREA LOCATION MAJOR TASKS OR EXPERTISE ON SHIFT 30-60 MIN. POSSIBLE Radiological EOF Accident Assessment 8 Plant Operationsl Accident Characteristics Refueling Ops.
Assessment 8 Fire Protection Support of Chemical Engr.l Operational Accident Radiochemistry Assessment (cont'd} Radeaste Mgmt.l Decontaminationl Rad Control/HP Plant Maintenance 1 EOF Off-Site Dose Gale. and Rad Assessment Staff 3 Assessment
- Available from Nuclear Engineering in Allentown.
Rev. 24, 06/96 Page 4
v
- TABLE 6.3
-: ADDITIONALASSISTANCE PROM OUTSIDE PP8rL Name/Address Emergency Function Availability (Hours) Reporting Location
~ General Electric San Jose, Engineering advise 'and analysis N/A GE facilities in San Jose CA 95125 for NSSS equipment Operations and Maintenance EOF expertise on NSSS equipment
~ Bechtel Engineering &, Analysis N/A Bechtel Facilities in San Francisco San Francisco, CA 94119 Engineering expertise 48 EOF
~ INPO Operations and Maintenance On call 24 hrs a day EOF Atlanta, GA 30339 expertise Dissemination of information N/A INPO HQ in Atlanta
~ PJM Nuclear Utility Operations, Maintenance, EOF Support Group Radiological personnel for augmenting emergency staffing iVOTFt The Technicaf Section maintains the information necessary to contact appropriate vendorsin case ofan emergency.
Rev. 24, 06/96 Page 1
SUSQUEHANNA SES ORGANIZATJON Senior Vice President
~ Nudear Vice President Nuclear Operations Plant Manager-Susquehanna SES Manager Outages
'anager Nudear Maintenance Manager Nudear Plant Services Manager Nuclear Operations Supervisor Plant Supervisor Maintenance Supervisor Maint. Supervisor ENuents Shift Supervisor Scheduhng ProductionlOutage Production Services Management Susquehanna Supervisor Site Supenrisor Reactor r U ion NSS Functional Team Support Services Engineering Supervsr Maint.
Supervisor Services Upelvlsof Supervisor Health r u lon re i rve a>n . Operations Functional Team Physics Supervsr Maint. En ineerin Plannin Su ervisor Manager Nudear r u ion Supervisor Chemistry Electrical Functional Security Supervsr Maint.
earn Supervisor Electrical Manager Nudear r u ion Rev. 24 06/96 l&C Functional Team Procurement Supervsr Maint. Susquehanna Steam Electric Station Supervisor I&C Units 1 and 2 Emergency Plan Balance of Plant Supervisor SUSQUEHANNA SES ORGANIZATION
A EOF ORGANIZATION ASSISTANT RECOVERY RECOVERY MANAGER MANAGER ENGINEER. DOSE PUBLIC LIAISON SUPORT EOF SUPPORT SUPPORT ASSESSMENT INFORMATION SUPERVISOR SUPERVISOR SUPERVISOR SUPERVISOR MANAGER
- DOSE PUBLIC NUClEAR FUELS COUNTY EOF ASSESSMENT OFFICIALS ENGINEER LIAISONS COMMUNICATOR STAFFER(S) CONTACTS ELECTRICAL FIELD TEAM NEP DUTY MOC SUPPORT COMMUNICATOR DIRECTOR PLANNER ENGINEER MECHANICAL ADMIN. TECHNICAl SUPPORT ASSISTANTS BRIEFERS ENGINEER RAD MONITORING TEAM GOVERNMENT AGENCIES SYSTEMS LEAD SECURITY NEWS MANAGER ENGINEER ENVIRONMENTAl SAMPLING TEAM SUPPORT Rev. 24 06/96 EOF DATA LINK SERVICES Susquehanna Steam Electric Station SUPERVISOR Units 1 and 2 Emergency Plan RAD LIAISON EOF ORGANIZATION FIGURE 6.2
PP8(L CORPORATE HEADQUARTERS PUSLIC IHFORMATIOH RESTORATIOH ADMIN/LOGISTICS MANAGER MANAGER MANAGER ADVISORY SCHEDULING/
SUPPORT PLANNING MANAGER TEC H N ICAL PLANT MANAGER OF COHSTRUCT ION SUPPORT OPERATIONS RADCON/WASTE MAHAGER MANAGER MANAGER MANAGEMENT CO gHI CO qv 555 O
M
~9
COjMIEUNICATIONINTERFACES mTH OFFSITE AGENCIES Control Control Room Room Coaa. Coma.
TSC TSC HPH TSC CoaNI. Coae. Coats.
EOF EOF HPH EOF Coats. Cmta. Coats, State and HRC LCEHA CEHA Federal Agencies OER/BRP Emergency Tech Rad Prot. Site Oirector Support Coord. Support (PAR) Coord. Hanagere
- Responsible for Recovery Lead Rad Supp. Interface with Hanager Tech Hanager Agencies Located (PAR) Staffer in EOf P REV. IS OI-92 Susqueha~ Stean Electric Station Units 1 and 2 Emergency Plan COHNJNI CAT IONS INTERFACE WITH OFF-SITE AGENCIES FIGURE 6.7
I;.";::;.".;" ';.:, ', ."',, ':'. ',7,0.;:-:.'MERGENCY'MEA'SURES::;;:;;:,,':,"
-.1 ASSESSMENT ACTIONS FOR ALLEMERGENCY CLA IFICATIONS Provisions are made for assessment through the course of an emergency to ensure effective coordination, direction and upgrading of emergency activities in a timely manner. The assessment actions are described in detail in EP-PSs.
Continuous assessment of the status of plant systems and radiological conditions is provided by plant instrumentation and is supplemented by routine surveillance functions. The occurrence of an Unusual Event is recognized by instrument alarms or indications, surveillance results or other observation of an off-normal condition by an individual at the station.
Assessment actions are described below. For an Unusual Event, one or more of the actions listed below will be initiated; for higher emergency classifications, actions are continued, intensified, and increased in frequency.
~ Perform surveillance of in-plant instrumentation.
~ Initial and continued observation of off-normal conditions.
~ Obtain assistance from off-duty personnel and/or off-site support groups.
~ Perform dose calculation activities. Correlate with field team data.
~ Deploy field radiological monitoring teams to perform direct radiation measurements and air sampling.
~ Perform sampling and analysis of environmental media.
~ Deploy on-site damage control teams.
~ Perform reactor coolant sampling and analysis.
7.1.1 Off-Sit Dose alculati ns The ED is responsible for initiating off-site dose calculation and assessment activities. These activities are performed"by health physics technicians who report to the control room. Data from the vent effluent monitors and the meteorological towers serve as inputs for the off-site dose calculation methods.
The ED is responsible for calling in personnel to the TSC to perform off-site dose assessment activities, The Radiation Protection Coordinator reports to the TSC within 30-60 minutes of notification. Subsequently, the off-site dose assessment activities at the TSC are turned over to the Interim Radiation Support Manager at the EOF. The Interim Radiation Support Manager Rev. 22, 04/95 7-1
reports to the EOF within one hour of notification. Upon arrival at the EOF the Radiation Support Manager relieves the Interim Radiation, Support Manager of ofF-site radiological responsibilities.
Field monitoring teams are directed to selected monitoring location(s) by the Radiation Protection Coordinator, Interim Radiation Support Manager, or Radiation Support Manager via radio communication. The results of the teams'urveys are used to update projected doses and dose calculational assumptions. This process is reiterated through the duration of the release in order to maintain an updated status of dose rates and accumulated dose within the pathway of the plume.
The initial field monitoring team(s) are staFed as required within 30-60 minutes. Additional team(s) are dispatched within one to four hours.-
Each on-site and near site monitoring team is supplied with a survey meter and low volume air sampler. TLDs are located at 19 sites around the station to provide early information on accumulated ofF-site doses. Two sets of TLDs are provided at each of these sites; one set for very early collection/exchange and readout and one set for dose accumulation during the period of release.
The ED and Recovery Manager recommend appropriate protective actions to PEMA Operations Center, Harrisburg, base'd upon the results of the oF-site dose assessment activities.
7.1.1.1 Meteor lo The SSES on-site meteorological measurement system is based upon an on-site 300'rimary meteorological tower located to the southeast of the station. The primary tower provides measurements of wind speed, wind direction, and wind variability at its 10 and 60-meter levels, temperature di6erential between the 10 and 60-meter levels, and ambient temperature and dew point at the 10-meter level. Precipitation is measured at ground level. In case of primary tower failure, a 10-meter on-site backup meteorological tower will provide measurements of wind speed, wind direction, and wind variability.
The meteorological systems are instrumented to provide continuous data to the control room and to the PCS for utilization in the TSC and EOF. Data which enter the PCS are viewable through various display formats and are also transmitted to the NRC via ERDS. Digital dataloggers are present at each of the two SSES meteorological towers. All data are stored locally and are available for acquisition by interrogation across telephone lines. Primary and backup tower strip chart recorders are located in the control room.
Additional meteorological information for emergency dose assessment purposes is available as needed from the National Weather Service Station at the Wilkes-Barre Scranton Airport at Avoca, about 30 miles northeast of the Susquehanna site, and the Philadelphia Forecast office of the National Weather Service.
Rev. 22, 04/95 7-2
7.1.1.2 Health Ph sics Considerations In the event of an unplanned radioactive release from either the reactor building vents, the turbine building vents or the standby gas treatment vent; gross noble gas, I-131, and gross particulate readings are available from the System Particulate Iodine Noble Gas (SPING) vent monitors.
The following Health Physics considerations are taken into account: selection of the accident type to closely approximate the isotopic mix and average gamma energies of the release occurring, radioactive decay from time of reactor shutdown, plume decay-in-transit and iodine and particulate depletion due to precipitation.
7.1.13 D s Cal ulati nsF rAi rneRelease A dose calculation model is used to make current, site specific estimates and predictions of atmospheric e6luent transport "and diffusion during and immediately following an accidental airborne radioactivity release. The purpose of the prediction is to provide an input to the assessment of the consequences of accidental radioactive releases to the atmosphere and to aid in the implementation of emergency response decisions.
The dose calculation model used is a fast running, time-dependent, variable trajectory plume segment "B" model with the following capabilities:
~
NOTE: A class "B" model is a numerical model which represents the actual spatial and temporal variations of plume distribution.
~ Computes atmospheric dispersion at the site based on atmospheric stability as a function of site specific terrain conditions with 15-minute upgrades of source term and meteorological conditions.
~ Provides estimates of deposition and relative concentration of radioactivity within the plume exposure and ingestion EPZs for the duration of the release.
~ Incorporated in the calculations is wet and dry deposition which enables dose estimates from three pathways - plume, ground shine, and inhalation.
The dose program complies with the "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," (EPA-400), 'adopting the dose calculation methodology in ICRP 426/30.
The following calculational options are available:
~ TEDE (Total Effective Dose Equivalent) integrated doses consisting of the sum of external doses from plume shine, 50 year committed effective dose equivalent from inhalation (CEDE), and 4 day ground shine doses.
~ TEDE dose rates for field team management.
~ Fifty year thyroid committed dose (CDE), from inhalation of radioactive materials.
Rev. 22, 04/95 7-3
~ Population dose (person rem) out to 50 miles.
~ Summary print of projected doses for each of four projection times.
~ Integrated ground dose for projected times specified by the user.
The dose calculation program is a stand alone program running on PCs located in the TSC and EOF.
7114 I.i i R l ase al 1 ti n Estimates of downstream river water concentrations are made by employing efHuent sample analysis or discharge monitor data, discharge flow rates and river elevation readings. The river elevation is used to estimate the travel time to the point of interest. The calculated degree of
,. mixing, together with the discharge monitor data and the discharge flow rates are used to calculate downstream concentrations.
7.2 ORRE TIVEA TI N Detailed operating procedures and plant procedures are utilized by the plant operating personnel to assist them in recognizing emergency events and taking the corrective actions necessary to place the plant in a safe condition. Table 7.1 shows personnel available to respond to an emergency. Additionally, EP-PSs describe subsequent and supplemental corrective actions for the scope of potential situations within each of the emergency classifications. These procedures are designed to guide the actions of the personnel to correct or mitigate the condition as early and as near to the source of the problem as feasible.
Some essential corrective actions may involve the risk of emergency exposure to NERO personnel. Such actions could involve preventing the release of large quantities of radioactive material, reducing damage to major equipment or life saving actions. Table 7.2 specifies the limits for emergency exposure and other relevant criteria to be considered. The ED is responsible for all corrective actions taken to mitigate the consequences of the accident on-site.
73 PR TE TIVE A TI N Protective actions are implemented to prevent or mitigate consequences to individuals during or after a radiological incident. Protective actions within the SSES site boundary are the responsibility of the ED, but may include assistance by oF-site organizations. Protective actions outside the SSES site boundary are primarily the responsibility of State and local emergency organizations, but may include coordination of activities, dissemination of appropriate data, and recommendations by the ED or Recovery Manager. Protective action recommendations are outlined in Table 7.3.
Rev. 22, 04/95 7-4
7,3.1'n-Site Protective Actions Th'e primary protective measure for on-site personnel in an emergency is prompt evacuation from areas which may be affected by significant radiation, contamination or airborne radioactivity.
Respiratory protective equipment and clothing are provided at the plant and in the various emergency equipment kits for personnel who may be required to perform emergency activities.
Control of in-plant contamination is in accordance with SSES Health Physics procedures. In the event of radioactive contamination outside fenced security areas, but within the exclusion area, access to such areas is controlled by PPEcL with assistance from the PSP.
7.3,1.1 Local Ar Evacuati n This category refers to evacuation &om one area to another area within the same building. The initiation of a Local Area Evacuation results from ARM or CAM alarm(s) sounding in the same area within a building or &om observed conditions such as smoke or toxic gas, which may indicate a possible habitability problem. The initial response for individuals is to evacuate to area of the building, notify the plant Control Room of the conditions, and await further an'naffected instruction. The ED assesses the situation, activates appropriate procedures to rectify the condition and informs the personnel when to return to their respective work area via the PA system.
7.3.1.2 Radi lo 'call ntrolled Area Evacuation The initiation of a Radiologically Controlled Area Evacuation results from ARM, CAM, or other applicable monitor alarms, (i.e., fire alarms). Notification for personnel to proceed with a Radiologically Controlled Area Evacuation is announced over the plant PA system. The initial mandatory response by individuals is evacuation to an unaffected area. In this case, however, the nearest such area may not be in the same building, and multiple ARM, CAM, or fire alarms are probable.
The decision to implement a Radiologically Controlled Area Evacuation is the responsibility of the ED. Factors to be considered include the apparent levels of radiation and/or airborne radioactivity involved and the exposure to personnel that would result &om evacuating to Assembly Areas. In the event of multiple fire alarms within the Radiologically Controlled Area, with no potentiai hazard to personnel, such as workers in unaffected areas, the ED may deem it prudent not to evacuate such personnel and allow work to continue.
~ 7 3 1 3 Securi and Accountabili Accountability of on-site personnel during an emergency is accomplished through the use of the physical security system and procedures. The physical security system clearly establishes who is within the protected area. Personnel are summoned to accountability areas during an emergency via an alert signal transmitted over the PA system. The names of the personnel reporting in are compared to those logged through the security system in order to ensure total accountability.
Rev. 22, 04/95 7-5
7.3.1.4 Site Evacuation Site Evacuation requires that all individuals within the SSES site, except for Control Room, operations personnel and others with specific emergency assignments, leave the site. If off-site assembly is required by the ED, personnel will go to the Remote Assembly Area. The Primary Remote Assembly Area is the Susquehanna Energy Information Center (NE Sector), as shown in Figure 8.1. The alternate Remote Assembly Area is the EOF (WSW Sector). Security personnel and assembly area leaders will coordinate assembly and accountability at Remote Assembly Areas.
Implementation of a Site Evacuation is the responsibility of the ED. That decision is based on the severity of the incident, the likelihood of escalation, and the radiation and airborne radioactivity levels throughout the station. Notification is made via the PA system.
Accountability is accomplished in passage through the security gate and supervisory checks at the assembly area. Personnel and vehicle contamination surveys are performed at the Remote Assembly Area, using portable survey instruments.
732 ff i Pr iv A in The responsibility for actions to protect off-site individuals rests with the Commonwealth of Pennsylvania.
DER/BRP is responsible for evaluating information obtained from SSES and other sources and recommending appropriate off-site protective actions to PEMA. Such recommendations include:
~ Shelter for affected populations
~ Evacuation of affected populations
~ Administration of thyroid prophylaxis
~ Control of contaminated agricultural products T he principal off-site local coordinating agency is LCEMA. Since the area and population inside the ten-mile EPZ are partially within Columbia County, parallel emergency response functions are provided by CEMA. Upon notification by PEMA of a situation which may require protective actions for off-site populations, LCEMA and CEMA initiate appropriate actions. IfPEMA has lost communication or is otherwise unavailable, it is possible that the ED or Recovery Manager may contact LCEMA and CEMA directly with protective action recommendations, If time permits, LCEMA and CEMA obtain a review and verification by PEMA of recommendations made by the ED or Recovery Manager.
'LCEMAand CEMA protective actions include:
~ Prompt alerting of the population within ten miles of the SSES through the 'use of the Public Notification System described in Section 8.0.
~ Transmission of specific instructions to potentially affected populations via the Emergency Broadcast System.
~ Assistance for evacuation of the population within the ten-mile EPZ.
Rev. 22, 04/95 7-6
Reception and mass care centers for evacuated individuals.
Appendix G includes the estimated times to evacuate all or segments of the population from the 10-mile EPZ, identifies potential problem areas and provides contingencies for dealing with adverse conditions. It was utilized in the development of detailed evacuation plans by PEMA, LCEMA and CEMA.
7 4 AID TO AFFECTED PER ONNEL 7.4.1 Emer enc Ex osure All reasonable measures are taken to maintain the radiation exposure of emergency personnel who provide rescue, first aid, decontamination, ambulance, or medical treatment services within applicable limits specified in 10CFR20. Table 7.2 summarizes the emergency exposure criteria for entry or re-entry into areas for purposes of undertaking protective or corrective actions. Methods
. and conditions for permitting volunteers to receive emergency radiation exposures are described in EP-PSs, and provide for expeditious decisions with consideration to known and reasonable balance of associated risks.
7.4 2 Dec ntamina i n an First Aid Personnel contamination in emergency situations is controlled to the extent feasible by the normal methods of using protective clothing and surveying for contamination following the removal of such clothing. Personnel decontamination areas are available in-plant and at the EOF for emergency use. Decontamination efforts involving significant amounts of contamination are performed under the direction of Health Physics personnel.
In the'vent of Site Evacuation, Health Physics personnel conduct personnel surveys of individuals as they are evacuated. If personnel decontamination is required, EOF facilities are available to support the decontamination efforts of Health Physics personnel.
\
At least two persons who are qualified in first aid methods are on-site at all times. First aid to injured personnel can be performed in conjunction with any necessary decontamination methods.
However, if immediate treatment of the injury is vital, that treatment takes precedence over decontamination.'his philosophy also extends to oF-site emergency assistance involving radioactive contamination. For that purpose, measures are established to ensure timely off-site medical treatment.
7.4.3 Medical Trans ortati n and Treatment Arrangements and agreements have been made for the transportation and treatment of patients from SSES, who may have injuries complicated with radioactive contamination or who may have been involved in a radiation incident.
Rev. 22, 04/95 7-7
Cl Page 1 CODE: Unusual Event Alert Site Area Emergency General Emergency TABLE 7.1
SUMMARY
OF IMMEDIATENOTIFICATION AND RESPONSE FOR ALL CLASSIFICATIONS ONS I TE OFFS ITE IMMEDIATENOTIFICATIONS ACTIONS IMMEDIATENOTIFICATIONS ACTIONS Fire Bri ade 14 Fi htFire 1A Fire Units 1-4 Fi ht Fire 1-4 Dama e Control Team 1-4 Re airs 1-4 First Aid/Rescue Team (1-4) Rescue (1-4) Rescue Assistance (1-4) Rescue (1-4)
First Aid (1-4) Ambulance (1-4) Transport (1-4)
Hos ital 1-4 Treatment 1-4 Security Force (1-4) Security Measures (1A) PSP (1-4) Assist Security (1-4)
Personnel Evaluation 1-4 Dose Assessment Personnel (1-4) Dose Calculations (1-4 PP&L Headquarters (1-4) Confirmatory Calculations (2-4)
Dose Assessment 1-4 Maintain Communications 2-4 Field Monitoring Teams (1-4) Field Monitoring (1-4) Field Monitoring and Continuous Evaluation of Dose Projections 3,4 AII Other Station Personnel (1-4) Augment Shift PP &L Headquarters (1-4) Alert Key Personnel (2)
Resources/Activate (cont'd.) Activate and Staff Offsite NERO TSC (2) (3 4)
Augment Resources/Activate Recommend Offsite Action (3,4)
Offsite NERO (3,4)
Personnel Evacuation (as a ro riate 3,4 Rev. 18, 05/93
0 Page 2 TABLE 7.1
SUMMARY
OF IMMEDIATENOTIFICATION AND RESPONSE FOR ALL CLASSIFICATIONS ON8ITE ORR8 ITE IMMEDIATENOTIFICATIONS ACTIONS IMMEDIATENOTIFICATIONS ACTIONS Special Office of President/ Provide Info to Public via Media MOC 1-4 1-4 LCEMA, CEMA, PEMA, NRC Place PNS & Procedures on (1-4) Standby (2)
Activate and Staff Response Centers (2-4)
Activate the Emergency
Response
Data System (2-4)
Implement Near-Site Protective Measures (3)
Implement Off-site Protective Measures 4 NOTES: 1. Notification is required to LCEMA, CEMA, PEMA within 15 minutes of indication and verification of the event for Alert, Site, and General Emergency. Unusual event notifications are timely, but not necessarily immediate.
- 2. Initial notification for all levels of emergencies are to LCEMA, CEMA, PEMA, and NRC.
Rev. 18, 05/93
PP&L CORPORATE HEADQUARTERS PUBLIC RESTORATION DMIN/LOGISTICS INFORMATION MANAGER MANAGER MANAGER SCHEDULINGI TECHNICAL ADVISORY PLANT RADIOLOGICAL MAINTENANCE PLANNING SUPPORT SUPPORT MANAGER MANAGER MANAGER MANAGER MANAGER Rev. 24 Q6I96 Susquehanna Steam Electric Station Units 1 and 2 Emergency Plan LONG TERM RESTORATION ORGANIZATION
I COMMUNICATIONINTERFACES WlTH OFF-SITE AGENCIES Control Room Control Room Communicator Communicator TSC TSC Communicator Communicator TSC HPN Communicator EOF EOF Communicator Communicator z
xn.
State and Federal NRC PEMA LCEMA CCDES Agencies Liaison Support DEPlBRP Supervisor X
I O
'Responsible for Interface with Emergency Tech Support Rad Protection Agencies Located in EOF Director (PAR) Coordinator Coordinator Rev. 24 06I96 Susquehanna Steam Electric Station Units 1 and 2 Recovery Manager Engineering Radiological Emergency Plan (PAR) Support Supervisor Liaison COMMUNICATIONINTERFACES WITH OFF-SITE AGENCIES
7.0- EMERGENCY MEASURES Provisions are made for assessment through the course of an emergency to ensure effective coordination, direction and upgrading of emergency activities in a timely manner. 'The assessment actions are described in detail in EP-PSs.
Continuous assessment of the status of plant systems and radiological conditions is provided by plant instrumentation and is supplemented by routine surveillance functions. The occurrence of an Unusual Event is recognized by instrument alarms or indications, surveillance results, or other observation of an off-normal condition by an individual at the station.
Assessment actions are described below. For an Unusual Event, one or more of the actions listed below will be initiated; for higher emergency classifications, actions are continued, intensified, and increased in frequency.
~ Perform surveillance, of in-plant instrumentation.
~ Initial and continued observation of off-normal conditions.
~ Obtain assistance from off-duty personnel and/or off-site support groups.
~ Perform dose calculation activities. Correlate with field team data.
~ Deploy field radiological monitoring teams to perform direct radiation measurements and air sampling.
~ Perform sampling and analysis of environmental media.
~ Deploy on-site damage control teams.
~ .Perform reactor coolant sampling and analysis.
The ED is responsible for initiating off-site dose calculation and assessment activities. These activities are performed by health physics technicians who report to the control room. Data from the vent eQluent monitors and the meteorological towers serve as inputs for the off-site dose calculation methods.
The ED is responsible for calling in personnel to the TSC to perform off-site dose assessment activities. The Radiation Protection Coordinator reports to the TSC within 30-60 minutes of notification. t Rev. 24, 06/96 7-1
Field monitoring teams are directed to selected monitoring location(s) by the Radiation Protection Coordinator, Dose Assessment Supervisor, Dose Assessment Staffer, or Field Team Director via radio communication. The results of the teams'urveys are used to update projected doses and dose calculational assumptions. This process is reiterated through the duration of the release in order to maintain an updated status of dose rates and accumulated dose within the pathway of the plume.
The initial field monitoring team(s) are staffed as required within 30-60 minutes. Additional team(s) are dispatched within one to four hours.
Each radiological monitoring team is supplied with a survey meter and low volume air sampler.
TLDs are located at 19 sites around the station to provide early information on accumulated off-site doses. Two sets of TLDs are provided at each of these sites; one set for very early collection/exchange and readout and one set for dose accumulation during the period of release.
The ED and Recovery Manager recommend appropriate protective actions to PEMA Operations Center, Harrisburg, based upon the results of the off-site dose assessment activities.
The SSES on-site meteorological measurement system is based upon an 'on-site 300'rimary meteorological tower located to the east southeast of the station. The primary tower provides measurements of wind speed, wind direction, and wind variability at its 10 and 60-meter levels, temperature differential between the 10 and 60-meter levels, and ambient temperature and dew point at the 10-meter level. Precipitation is measured at ground level. In case of primary tower failure, a 10-meter on-site backup meteorological tower will provide measurements of wind speed, wind direction, and wind variability.
The meteorological systems are instrumented to provide continuous data to the control room and to the Unit One PCS and Unit Two PICSY for utilization in the TSC and EOF. Data which enter the Unit One PCS and Unit Two PICSY are viewable through various display formats and are also transmitted to the NRC via ERDS. Digital dataloggers are present at all of the SSES meteorological towers. All data is stored locally and is available for acquisition by interrogation across telephone lines. Primary and backup tower strip chart recorders are located in the control room.
Site specific, meteorological information for emergency dose assessment purposes can be obtained by contacting either the SSES Contract Meteorologist or the National Weather Service Station using the phone numbers provided in the SSES Emergency Telephone Directory.
In the event of'an unplanned radioactive release from either the reactor building vents, the turbine building vents or the standby gas treatment vent; gross noble gas, I-131, and gross Rev. 24, 06/96 7-2
particulate readings are available from the System Particulate Iodine Noble Gas (SPING) vent monitors.
The following Health Physics considerations are taken into account: selection of the accident type to closely approximate the isotopic mix and average gamma energies of the release occurring, radioactive decay from time of reactor shutdown, plume decay-in-transit and iodine and particulate depletion due to precipitation.
A dose calculation model is used to make current, site specific estimates and predictions of atmospheric effiuent transport and diffusion during and immediately following an accidental airborne radioactivity release. The purpose of the prediction is to provide an input to the assessment of the consequences of accidental radioactive releases to the atmosphere and to aid in the implementation of emergency response decisions.
The dose calculation model used is a fast running, time-dependent, variable trajectory plume segment "B" model with the following capabilities:
NOTE: A class "B" model is a numerical model which represents the actual spatial and temporal variations of plume distribution.
~ Computes atmospheric dispersion at the site based on atmospheric stability as a function of site specific terrain conditions with 15-minute upgrades of source term and meteorological conditions.
~ Provides estimates of deposition and relative concentration of radioactivity within the plume exposure and ingestion EPZs for the duration of the release.
~ Incorporated in the calculations is wet and dry deposition which enables dose estimates from three pathways - plume, ground shine, and'inhalation.
The dose program complies with the "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," (EPA-400), adopting the dose calculation methodology in ICRP 026/30. The following calculational options are available:
~ TEDE (Total Effective Dose Equivalent) integrated doses consisting of the sum of external doses from plume shine, 50 year committed effective dose equivalent from inhalation (CEDE), and 4 day ground shine doses.
~ TEDE dose rates for field team management.
~ Fifty year thyroid committed dose (CDE), from inhalation of radioactive materials.
I
~ Population dose (person rem) out to 50 miles.
Rev. 24, 06/96 7-3
~ Summary print of projected doses for each of four projection times.
~ Integrated ground dose for projected times specified by the user.
The dose calculation program is a stand alone program running on PCs located in the TSC and EOF.
Estimates of downstream river water concentrations are made by employing effluent sample analysis or discharge monitor data, discharge flow rates and river elevation readings. The river elevation is used to estimate the travel time to the point of interest. The calculated degree of mixing, together with the discharge monitor data and the discharge flow rates are used to calculate downstream concentrations.
Detailed operating procedures and plant procedures are utilized by the plant operating personnel to assist them in recognizing emergency events and taking the corrective actions necessary to place the plant'n a safe condition. Table 7.1 shows personnel available to respond to an emergency. Additionally, EP-PSs describe subsequent and supplemental corrective actions for the scope of potential situations within each of the emergency classifications. These procedures are designed to guide the actions of the personnel to correct or mitigate the condition as early and as near to the source of the problem as feasible.
Some essential corrective actions may involve the risk of emergency exposure to NERO personnel. Such actions could involve preventing the release of large quantities of radioactive material, reducing damage to major equipment or life saving actions. Table 7.2 specifies the limits for emergency exposure and other relevant criteria to be considered. The ED is responsible for all corrective actions taken to mitigate the consequences of the accident on-site.
Protective actions are implemented to prevent or mitigate consequences to individuals during or after a radiological incident. Protective actions within the SSES site boundary are the responsibility of the ED, but may include assistance by off-site organizations. Protective actions outside the SSES site boundary are primarily the responsibility of State and local, emergency organizations, but may include coordination of activities, dissemination of appropriate data, and recommendations by the ED or Recovery Manager. Protective action recommendations are outlined in Table 7.3.
Rev. 24, 06/96 7-4
The primary protective measure for on-site personnel in an emergency is prompt evacuation from areas which may be affected by significant radiation, contamination, or airborne radioactivity.
Respiratory protective equipment and clothing are provided at the-plant and in the various emergency equipment kits for peisonnel who may be required to perform emergency activities.
Control of in-plant contamination is in accordance with SSES Health Physics procedures. In the event of radioactive contamination outside fenced security areas, but within the exclusion area, access to such areas is controlled by PP &Lwith assistance from the PSP.
This category refers to evacuation from one area to another area within the same building. The initiation of a Local Area Evacuation results from ARM or CAM alarm(s) sounding in the same area within a building or from observed conditions such as smoke or toxic gas, which may indicate a possible habitability problem. The initial response for individuals is to evacuate to an unaffected area of the building, notify the plant Control Room of the conditions, and await further instruction. The ED assesses the situation, activates appropriate procedures to rectify the condition and informs the personnel when to return to their respective work area via the PA system.
The initiation of a Radiologically Controlled Area Evacuation results from ARM, CAM, or other applicable monitor alarms, (i.e., fire alarms). Notification for personnel to proceed with a Radiologically Controlled Area Evacuation is announced over the plant PA system. The initial mandatory response by individuals is evacuation to an unaffected area. In this case, however, the nearest such area may not be in the same building, and multiple ARM, CAM, or fire alarms are probable.
'he decision to implement a Radiologically Controlled Area Evacuation is the responsibility of the ED. Factors to be considered include the apparent levels of radiation and/or airborne radioactivity involved and the exposure to personnel that would result from evacuating to Assembly Areas. In the event of multiple fire alarms within the Radiologically Controlled Area, with no potential hazard to personnel, such as workers in unaffected areas, the ED may deem it prudent not to evacuate such personnel and allow work to continue.
Accountability of on-site personnel during an emergency is accomplished through the use of the physical security system and procedures. The physical security system clearly establishes who is within the protected area. Personnel are summoned to accountability areas during an emergency Rev. 24, 06/96 7-5
via an alert signal transmitted over the PA system. The names of the personnel reporting in are compared to those logged through the security system in order to ensure total accountability.
Site Evacuation requires that all individuals within the SSES site, except for Control Room operations personnel and others with specific emergency assignments, leave, the site. If off-site assembly is required by the ED, personnel will go to the Remote Assembly Area. The Primary Remote Assembly Area is the Susquehannaknergy Information Center (NE Sector), as shown in Figure 8.1. The alternate Remote Assembly Area is the old EOF (WSW Sector). Security personnel and assembly area leaders will coordinate assembly and, accountability at Remote Assembly Areas.
Implementation of a Site Evacuation is the responsibility of the ED. That decision is based on the severity of the incident, the likelihood of escalation, and the radiation and airborne radioactivity levels throughout the station. Notification is made via the PA system..
Accountability is accomplished in passage through the security gate and supervisory checks at the assembly area. Personnel and vehicle contamination surveys are performed at the Remote Assembly Area, using portable survey instruments.
The responsibility for actions to protect off-site individuals rests with the Commonwealth of Pennsylvania.
DEP/BRP is responsible for evaluating information obtained from SSES and other sources and recommending appropriate off-site protective actions to PEMA. Such recommendations include:
~ Shelter for affected populations
~ Evacuation of affected populations
~ Administration of thyroid prophylaxis
~ ~ Control of contaminated agricultural products
, The principal off-site local coordinating agency is LCEMA. Since the area and population inside the ten-mile EPZ are partially within Columbia County, parallel emergency response functions are provided by CCDES. Upon notification by PEMA of a situation which may require protective actions for off-site populations, LCEMA and CCDES initiate appropriate actions. If PEMA has lost communication or is otherwise unavailable, it is possible that the ED or Recovery Manager may contact LCEMA and CCDES directly with protective action recommendations. If time permits, LCEMA and CCDES obtain a review and verification by PEMA of recommendations made by the ED or Recovery Manager.
Rev. 24, 06/96 7-6
LCEMA and CCDES protective actions include:
~ Prompt alerting of the population within ten miles of the SSES through the use of the Public Notification System described in Section 8.0.
~ Transmission of specific instructions to potentially affected populations via the Emergency Alert'ystem.
~ A'ssistance for evacuation of the population within the ten-mile EPZ.
~ Reception and mass care centers for evacuated individuals.
'ppendix G includes the estimated times to evacuate all or segments of the population from the 10-mile EPZ, identifies potential problem areas and provides contingencies for dealing with adverse conditions. It was utilized in the development of detailed evacuation plans by PEMA, LCEMA, and CCDES.
All reasonable measures are taken to maintain the radiation exposure of emergency personnel who provide rescue, first aid, decontamination, ambulance, or medical treatment services within applicable limits specified in 10CFR20. Table 7.2 summarizes the emergency exposure criteria for entry or re-entry into areas for purposes of undertaking protective or corrective actions.
Methods and conditions for permitting volunteers to receive emergency radiation exposures are described in EP-PSs, and provide for 'expeditious decisions with consideration to known and reasonable balance of associated risks.
Personnel contamination in emergency situations is controlled to the extent feasible by the normal methods of using protective clothing and surveying for contamination following the removal of such clothing. Personnel decontamination areas are available in-plant and decontamination efforts involving significant amounts of contamination are performed under the direction of Health Physics personnel.
At least two persons who are qualified in first aid methods are on-site at all times. First aid to injured personnel can be performed in conjunction with any necessary decontamination methods.
However, if immediate treatment of the injury is vital, that treatment takes precedence over decontamination. This philosophy also extends to off-site emergency assistance involving radioactive contamination. For that purpose, measures are established to ensure timely off-site medical treatment.
Rev. 24, 06/96 7-7
Arrangements and agreements have been made for the transportation and treatment of patients from SSES, who may have injuries complicated with radioactive contamination or who may have been involved in a radiation incident.
Rev. 24, 06/96 7-8
Page)
CODE: Unusual Event 1 Alert 2
-Site Area Emergency 3 General Emergency 4
'ABLE 7.1
SUMMARY
OF IMMEDIATENOTIFICATIONAND RESPONSE FOR ALL CLASSIFICATIONS ON SITE OFFSITE IMMEDIATENOTIFICATIONS ACTIONS IMMEDIATENOTIFICATIONS ACTIONS Fire Brigade (1-4) Fight Fire (1R) Fire Units (1-4) Fight Fire (1-4)
Damage Control Team (1-4) Repairs (1-4)
First Aid/Rescue Team (1-4) Rescue (1-4) Rescue Assistance (1P) Rescue (1-4)
First Aid (1-4) Ambulance (1-4) Transport (14)
Hospital (1-4) Treatment (1-4)
Security Force (1A) Security Measures (1-4) PSP (1R) Assist Security (1-4)
Personnel Evaluation (1-4)
Dose Assessment Personnel (1-4) Dose Calculations (1-4 PP&L Headquarters (1A) Confirmatory Calculations (2-4)
Dose Assessment (1-4) Maintain Communications (2-4)
Field Monitoring Teams (1-4) Field Monitoring (1-4) Field Monitoring and Continuous Evaluation of Dose Projections (3,4)
All Other Station Personnel (14) Augment Shift PP&L Headquarters (1C) Alert Key Personnel (2}
Resources/Activate (cont'd.) Activate and Staff Offsite NERO TSC (2) (2,3,4)
Augment Resources/Activate Recommend Offsite Action (3,4)
Offsite NERO (2,3,4)
Personnel Evacuation (as appropriate } (3,4)
Rev. 24, 06/S6
Page 2 TABLE 7.1
SUMMARY
OF IMMEDIATENOTIFICATION AND RESPONSE FOR ALL CLASSIFICATIONS ONSITK OFFSITE IMMEDIATENOTIFICATIONS ACTIONS IMMEDIATENOTIFICATIONS ACTIONS Special Office of President/ Provide Info to Public via Media MOC (1P) (1-4)
LCEMA, CCDES, PEMA, NRC Place PNS 8 Procedures on (1-4) Standby (2)
Activate and Staff Response Centers (2-4)
Activate the Emergency
Response
Data System (2-4)
Implement Near-Site Protective Measures (3) implement Off-site Protective Measures (4)
NOTES: 1. Notification is required to LCEMA, CCDES, PEMA within 15 minutes of indication and verification of the event for Alert, Site, and General Emergency. Unusual Event notifications are timely, but not necessarily immediate.
- 2. Initial notification for all levels of emergencies are to LGEMA, GCDES, PEMA, and NRC.
Rev. 24, 06/96
S.O'. EMERGENCY FACILITIKSAND EQUIPMENT .
8,1 ON-SITE EMERGENCY CENTERS 8.1 I Station Control Room The Station Control Room is the primary location for the initial assessment and coordination of corrective actions for all emergency conditions. The Control Room is equipped with the display and controls for all critical plant systems, radiological and meteorological monitoring systems,, and all station communication systems. Reference Appendix D.
OfF-site emergency functions initially served by the Control Room are transferred to the TSC or EOF for a Site Area or a General Emergency as deemed appropriate by the ED. The primary consideration is to ensure that the number of personnel involved with the emergency in the Control Room shall not impair the safe and orderly shutdown of the reactor or the operation of plant safety systems.
8,1,2 0 erations Su ort Center The OSC is the primary on-site assembly area for operations support team personnel during an emergency. It occupies 340 square feet adjacent to the Control Room on El. 729'-1" of the control structure.
The OSC is utilized initially as the central location for the assembly, accountability, and dispatching of on-shift emergency team personnel required to perform such functions as: fire fighting, first aid, search and rescue, damage control, and on-site radiation monitoring. If and when the TSC is activated, all non-operations support team personnel assemble and are accounted for at their individual assembly areas. TSC personnel assess the need for emergency team personnel and based on this assessment, dispatch team personnel from their assembly area or via call-in to perform TSC team functions. Long term retention of additional personnel to support in-plant team functions will be in the Maintenance and I&C assembly areas. These areas will be monitored continuously for habitability. Ifthese areas become uninhabitable, retained personnel will be directed to alternate holding areas. Control and dispatch of these teams is the responsibility of the TSC Radioman. The OSC continues to manage operations support personnel, even after the TSC is activated.
Equipment required for these teams to perform their functions, as outlined in Appendix D is stored and maintained in the Control Room, Technical Support Center and Health Physics access control points.
During normal plant operations, this area serves as an operations stafF work area for shift changeover purposes as well as shift work assignment area. The Non-Emergency use of the OSC does not degrade its primary purpose.
Rev. 22, 04/95 8-1
8 1.2.1 Habitabilit 8.1.2.1.1 Allowable Post-Accident Radiation Doses OSC personnel are protected from radiological hazards, including direct shine and airborne activities for postulated accident conditions to the same degree as Control Room personnel.
Applicable criteria are specified in General Design Criterion 19, Standard Review Plan 6.4, and NUREG-0737, Item II.B.2.
8.1.2.1 2 Postulated Post Accident Radiation Doses The radiation dose to personnel occupying the OSC is the same as the Control Room personnel.
The doses from controlling accidents are summarized in Chapter 15.0 of the FSAR.
8 1 2 1.3 Radiation M nitorin To ensure adequate radiological protection of the OSC personnel, a commercial grade monitor alarms on high gross gamma radiation dose rates.
8.1.2.2 HVA The OSC HVAC system is a part of the Control Room HVAC system which is described in FSAR Section 9.4.1.
8.1 2 3 Shieldin Shielding requirement for the OSC is the same as for the Control Room for total dose to occupants from direct shine and airborne. Exposure does not exceed 5 Rem whole body for the duration of the accident. This is in accordance with General Design Criterion 19, USNRC Standard Review Plan 6.4, and NUREG-0737, Item II.B.2. Duration of occupancy and method of analysis is the same as that used for the Control Room.
8124 Occu ant Accomm d ion No toilet facilities are provided in the OSC. Facilities are available in the Control Room and at grade level of the control structure for washing and toilet accommodations.
8125 Comm nic ti n The OSC communication system includes priority access voice links-hotlines, the plant PA system and telephone lines tied through the plant switchboard.
8.1 2 5.1 Tel h n The normal telephone service for the OSC uses the plant ETN and CTN systems. Both systems have the capability to reach on- and off-site locations.
Rev. 22, 04/95 8-2
8.1.2.5.2 Hotlines Priority access voice communication links with automatic signaling is provided in the OSC. The OSC hotline connects with the TSC or the Control Room.
8.1.2.5.3 Public Address S stem" The PA system is part of the plant PA system. The system provides two-way communications at handset stations. Each station may originate and receive communications by switching to either a page channel or to one of five non-interfering party line channels.
8 1 3 Technical u rt enter The TSC is a controlled access area which provides working space and facilities for 25 NERO personnel. These personnel provide guidance to plant operations personnel for management of emergency conditions and accident mitigation.
The TSC is located in the existing Control Room mezzanine above the Control Room at elevation 741'-1" of the control structure and occupies approximately 2500 square feet. The TSC is within approximately two minutes travel time of the Control Room by elevator or stairs.
The TSC facilities may be used for normal daily activities which do not degrade TSC emergency preparedness. The TSC provides ofBce space for Operations and Technical personnel. The facilities may also be used as a research or reference area by other station personnel.
8.1 3.1 atial La out Descri tion The TSC includes areas for work, conferencing (NRC & PP&L), document control, and computer monitoring. Housed components are SPDS, UMC, video copier, RDAS (printer/terminal), and SPING monitor panel. (Reference Figure 8.2).
e 8.1 3.2 Fire Protection Automatic wet pipe sprinklers on an ordinary hazard pipe schedule are provided.
8 1 3.3 tru ral Desi Crit ri The TSC is part of the control structure which is a Seismic Category I structure, as defined in NRC Regulatory Guide 1.29. It is designed in accordance with Chapter 3.0 of the FSAR.
Rev. 22, 04/95 8-3
8.1.3 4 Habitabilit 8 1.3.4.1 Post-A cident Radiation Dose 8.1.3.4.1.1 Allowable TSC personnel are protected from radiological hazards, including direct shine and airborne activities for postulated accident conditions to the same degree as control room personnel.
Applicable criteria are specified in General Design Criterion 19, Standard Review Plan 6.4, and NUREG-0737, Item II.B.2.
8 1.3 4 1.2 Postulated The radiation dose to personnel is the same as the Control Room personnel. The doses from controlling accidents are summarized in Chapter 15.0 of the FSAR.,
81.3413 Radiai nMoni orin Commercial grade monitors are provided to alarm on high gross gamma radiation dose rates. In addition, airborne radioactivity concentrations are monitored by portable monitors. Iodine detection capability is provided.
8 1 3 4.2 HVA The TSC HVAC system is a part of the Control Room HVAC system which is described in FSAR Section 9.4.1.
8 1.3 4.3 Shi ldin Shielding is the same as for the Control Room for total dose to occupants from direct shine and airborne. Exposure will not exceed 5 Rem whole body for the duration of the accident. This is in accordance with General Design Criterion 19, USNRC Standard Review Plan 6.4, and NUREG-0737, Item II.B.2. Duration of occupancy and method of analysis is the same as for the control room.
81,34.4 Occu tAcc mm dation No sleeping accommodations or toilet facilities are provided. Use of the plant's existing facilities at grade level of the control structure for washing and toilet accommodations is available. There is a unit kitchen with appliances and sink. Self-contained breathing apparatus are available.
8 1 3 5 mmunication Link The TSC communications system is comprised of three telephone networks (ETN, CTN, and FTS), VHF and UHF radios, and the plant PA system, They provide reliable primary and back-np communication links to emergency response facilities on- and off-site.
Rev. 22, 04/95 84
8,1,3 5.1 Tele hones The TSC uses the CTN system as primary communications with the ETN system available at various locations and the FTS 2000 reserved for federal government agencies.
8.1,3.5.2 Radio The TSC has a four-channel 450 MHz UHF and a two-channel 150 MHz VHF radio system with digital voice privacy capability. The VHF radio is an emergency backup for communication with LCEMA, CEMA, and GOESC, and to communicate with the field monitoring teams. The UHF radio provides primary and backup security, emergency, operational and maintenance communication links.
81353 P li Addre tern The system provides two-way communications at handset stations. Each station may originate and receive communication by switching to either a pager channel or to one of five non-interfacing party-line channels.
8.1.3.6 Power Su 1 The TSC is part of the existing power block as described in Chapter 8.0 of the FSAR.
8.1.3.7 Instrumentati n The TSC utilizes the same field sensors and signal conditioning equipment which is provided to monitor plant systems. TSC instrumentation is identical to the field instrumentation used to operate the plant. A detailed description of this instrumentation is provided in Chapter 7.0 of the FSAR.
813.8 T DataPresen a ion The TSC includes human factors engineered man-machine capabilities to allow personnel to determine:
~ plant conditions during normal operation
~ plant steady-state conditions prior to an accident
~ transient conditions producing an initiating event
~ plant system dynamic behavior during an accident
~ projected behavior and effects of offsite airborne radioactivity releases.
The man-machine interface is provided by devices tied to the SPDS, PCS, and RDAS in the TSC monitoring area: (Reference Figure 8.2).
a) Two CRTs housed in the SPDS console.
Rev. 22, 04/95 8-5
b) Two PCS UMCs which have graphic and parameter displays depicting the conditions of the plant systems.
c) Video copiers for hard copy output of SPDS and PCS data.
d) RDAS printer/terminal for display of meteorological and vent data.
8.1,3.9 Records and Documents The TSC contains up-to-date records and references for use during emergency conditions.
(Reference Appendix D). Records are updated and managed by the DCS utilizing Plant Administrative Procedures.
3~1.3. 0 II The TSC is located within a plant vital area and is subject to the vital area access controls as identi6ed in FSAR Section 13.6.
82 PP&L FF- ITEEMER EN YCENTER 8.2 1 Medi ration en r Initially, the Susquehanna Energy Information Center, located on U.S. Route 11, is utilized as the Media Operations Center. When the number of reporters anticipated is greater then the comfortable limits of the Information Center, or if a General Emergency is likely, the Northeast Division Headquarters, located near Wilkes-Barre, will be activated as the Media Operations Center.
8.22 Emer en erati n Facili The EOF is an emergency response facility located near the site. The EOF provides continuous management of PP&L activities during radiological emergencies which may have oQsite impact.
The site location of the EOF is in North Central Pennsylvania in Luzerne County approximately 5-V4 miles north of the Borough of Berwick in Salem Township, approximately 2,500 feet southwest of the control structure (Reference Figure 8.1). The site fronts on County Road T-438. Direct access to the site is maintained over a 12'ide stoned roadway from Rt. T-438 to the 500kV Switchyard.
The non-emergency activities of the EOF are such that its main'function is not degraded. The EOF provides office space for the Nuclear Emergency Plannirig Group and computer maintenance personnel. Also, space is provided for training and operational support functions.
8.2.2 1 Architectur The 16,500 square feet, one-story building is a rectangular structure, 167'ong by 99'ide. The exterior walls are 12" reinforced concrete with a brick facing. The shed roof is a 9-1/2" Rev. 22, 04/95 8-6
reinforced concrete slab. The concrete was utilized to provide the required radiological protection.
Fifty parking stalls are provided at the EOF. In addition, parking space for five emergency response monitoring vans is provided at the side and rear of the building. Communication and power hookups are available for each van.
8.2.2.1.1 S atialLa outDescri tion The EOF is divided into three areas (Reference Figure 8.3):
'A. EMERGENCY OPERATI N RESPONSE This area is composed of offices for a receptionist, PP&;L emergency managers and support, NRC, and conferencing. There is also a central work area for 35 people.
B. PORT AREA FOR EMERGENCY RESPON E The areas provided are mechanical and electrical equipment, toilets, kitchen and eating facilities, storage areas and conference rooms.
C. COO MPhl RR A computer room supports SPDS and RDAS and ERDS. Also, an adjoining computer work room is used to operate and maintain the computer equipment.
8 2,2 1.2 Fire Prot ti n a) Automatic wet pipe sprinklers on an ordinary hazard pipe schedule are provided throughout the building except below the computer room floor and above ceilings where no combustible materials are present.
b) Computer Area A total flooding, automatic Halon 1301 system protects the room volumes and the volume of the spaces beneath the floors of the computer room and computer work room with a 5% concentration.
c) The Halon system is actuated by a cross-zoned product of combustion detection system.
8.222 ru ural las ificati n'he EOF is classified as a structure, the failure of which would not result in release of significant radioactivity, and is not required for reactor shutdown. This structure is classified as Non-Category I.
Rev. 22, 04/95 8-7
8.2.2.3 Habitabilit 8.2.2.3.1 Post Accident Radiation Shieldin
'he EOF is designed to provide sufficient shielding to reduce by a factor of more than 5 the gamma radiation shine from external post accident sources, including both direct shine from the reactor building and from airborne radioactivity outside the EOF which is released from the
- reactor building. The walls and ceilings are designed to provide a minimum thickness of nine inches of concrete. Based on the attenuation of 0.7 MeV gamma radiation, this concrete provides a protection factor of greater than 5. In addition, all entrances, exits and penetrations have a labyrinth design which prevents direct shine from outside sources into any part of the building which is normally occupied without passing through at least nine inches of concrete.
8.2.2.3.2 HVAC 8.2.2.3.2 1 Desi n Basis This system provides for control of environmental conditions in the EOF. It is designed to accomplish the following objectives:
a) Maintain a slightly positive pressure above atmosphere inside the EOF, in order to inhibit air leakage into the building. This is not applicable for operation during isolation mode.
b) Provide radiation protection from airborne fission products. The system may be manually transferred to one of two emergency modes. One mode provides for air circulation through HEPA Filters with intake from the outside; the other routes air through HEPA Filters with 100% recirculation.
c) Maintain airflow from areas of lesser to areas of greater potential radioactive contamination.
The equipment and the system components are not designed to meet seismic category I requirements or qualified as Engineered Safety Features. All HVAC equipment except HEPA filters are commercial grade quality. HEPA filters are suitable for nuclear application.
8.2.2.3.2 2 afe Evalua i n The system, as designed, meets the EOF functional requirements as stated in NUREG-0696. The system includes a tie connection between the two supply air system ducts so that partial cooling can be provided in the event one of the units is not functioning.
Rev. 22, 04/95 8-8
8.2.2.3.3 Radiation Monitorin a) Outside Air Intake Radiation Monitoring System.
This system consists of a radiation detector installed in the outside air intake duct and connected to electronic circuits which activate both audible and visual alarms when radiation levels of outside air exceed a preset trip point. The alarms can be heard in normally occupied areas of the EOF. When the alarm sounds, previously designated personnel will assess the need to place the HVAC System in an alternate mode of operation.
b) Iodine Sampling The concentration of airborne radioiodine is determined by use of a portable low volume air sampler with silver zeolite cartridges.
8.2.2.4'mmunications The EOF communications system is comprised of three telephone networks (ETN, CTN, and FTS), VHF and UHF radios, and a PA system. They provide a reliable primary and back-up communications network.
8.2241 T 1 h ne The EOF uses a combination of the CTN and ETN systems with the FTS system available for federal governmental agencies.
8.2.2.4.2 Radio The EOF has both a four-channel 450 MHz UHF and a two-channel 150 MHz VHF radio system.
The VHF system is used as an emergency backup to the telephone system and to communicate with the field monitoring teams. The UHF radio allows EOF personnel to monitor security, emergency, operational, and maintenance communication links.
8225 PowerR liabili 8.2 2.5.1 Emer en nerat r The standby diesel generator is sized for complete operation of the facility. On loss of utility power, automatic transfer is made to the standby diesel generator which will accept load within ten seconds.
Rev. 22,,04/95 8-9
8.2 2.5.2 ninterru table Power Su I S The UPS system is completely static design with rectifier, batteries and inverter being the main components. The system is sized to carry all critical loads, which include computer equipment, security, emergency lighting, telephone and radio systems.
8,2.2,6 E F Data Presentation The EOF includes human factors engineered man-machine interface capabilities to allow personnel to:
~ access environmental conditions
~ coordinate radiological monitoring activities
~ recommend implementation of oF-site emergency plans
~ monitor Emergency Response Data System The system is designed to provide the interface to the following devices:
a) Separate CRTs for display of SPDS, PCS, and ERDS Data Link status.
b) Separate printers for hard copy output of PCS, SPDS and meteorological and vent data.
c) A color copier for hard copy output of SPDS.
8.2.2.7 Record and Document The EOF contains up-to-date references and records. Documents are managed by DCS using plant administrative procedures.
8 2.2.8 Securit EOF access during an emergency is limited to authorized personnel. Intrusion detection devices monitor the EOF during unoccupied periods.
82.3 Ba ku Emer en er i n F cili 8.2 3 1 Function The BEOF provides space and facilities for maintaining the continuity of primary EOF functions, dose projection and senior management decision making capability, during emergency conditions that require EOF personnel to evacuate the primary EOF or ifthe primary EOF is inaccessible.
8.2.3 2 Location The location for the Backup EOF is 13 air miles from SSES, at the PP&L Hazleton Service Center auditorium on 344 South Poplar Street, Hazleton, PA. (Reference Figure 8.4)
Rev. 22, 04/95 8-10
8.2.3.3 EOF Evacuation/Backu EOF Activation 8,2.3,3,1 Evacuati n riteria The Interim Radiation Support Manager or the Radiation Support Manager recommends evacuation of the EOF if one or more of the following radiological conditions is realized and verified:
a) Rad survey in EOF indicates whole body dose rate greater than 500 mrem/hr.
'b) Personnel frisk and smears indicate widespread unmanageable contamination in and near the EOF.
c) Air sample readings in the EOF read greater than 75 DAC.
823 3.2 Fun i n n inui Durin Evaluati n The Recovery Manager ensures a transfer of the following functions to the TSC until the Backup EOF is activated and operational:
a) Dose calculations b) Field monitoring team direction c) Communications, (except DER-Technical) d) Dose assessment and protective actions.
The Recovery Manager also ensures that technical assessment capability and communications with DER-Technical are transferred to the GOESC.
8.2 3.4 Staffin In order to perform the functional requirements mentioned above, the minimum staf6ng consists of the Recovery Manager, the Radiation Support Manager, the Site Support Manager, the Administrative Support Manager and their staffs.
The task functions of the minimum staff'personnel required to ensure continuity of functions at the Backup EOF are the same as the normal EOF minimum stafBng described in Section 6.0.
8.23.5 S atialLa outDescri tion The available space at the Backup EOF can be set up in a configuration allowing access and coordination of information necessary to carry on the function of the EOF. Being located in a main PP&L Service Center provides for access to support facilities that may be needed in an emergency situation.-
Rev. 22, 04/95 8-11
8.2.3.6 Communication The BEOF communication system consists of normal telephone lines capable of reaching outside numbers and PP&L system extensions via the ETN.
Radio communication with the field monitoring teams is maintained with portable two-channel 150 mhz VHF radio units. These portable units also provide a backup means of communication with the TSC, GOESC, LCEMA and CEMA.
8.2.3.7 Data Evaluation All pertinent data and evaluations will be transmitted to the BEOF and GOESC via telecopy and telephone.
8.2.3.8 Rec rds and Do m nt The following records are transported from the primary EOF to the Backup EOF upon activation:
~ Emergency Plan Position Specific Procedures
~ SSES Preparedness, Prevention and Contingency Plan
~ SSES Hazardous Material Off-site Response Plan
~ Radiological Records
~ Plant Technical Specifications
~ Current Emergency Plans for PP&L.
8.2.4 General ffice En ineerin Su ort enter GOESC Located in Allentown, activated at the discretion of the Emergency Director/Recovery Manager or automatically at a Site Area Emergency. Upon activation, provides Nuclear Plant Engineering resources in support of technical problem resolution.
8'3 sufhcient YAND TATEEMER EN Y ENTER 83 1 oun Emer en nter Both LCEMA and CEMA have EOCs which meet or exceed the minimum Federal criteria for space, communications, warning systems, self-sufficiency in supplies and accommodations and radiological protection factor. Both counties maintain full-time employees, providing 24-hour per day coverage at their EOC, to coordinate emergency planning and evaluation. "CTN" telephone connections exist between SSES and each County EOC.
Location of the county EOCs:
~ Luzerne County Wilkes-Barre, Pennsylvania
~ Columbia County Court House Bloomsburg, Pennsylvania-Rev. 22, 04/95 8-12
8.3.2 State Emer enc enter The State.EOC is located at the PEMA headquarters, in the Transportation Building, in Harrisburg. This center is equipped with a reliable communications system which includes "CTN" telephone connections between the EOC and SSES, and ties to all area and county EOCs. During an emergency, representatives from appropriate State agencies will assemble at the State EOC to manage and support the emergency response activities. Facilities are also available at the EOF for PEMA personnel.
8 4 AS ESSMENT CAPABILITIES 8.4.1 Radiation Monitorin S stem
. This on-site system, consisting of ARMs, CAMs, and process monitors, contributes to personnel
'rotection, equipment monitoring and accident assessment by measuring and recording radiation
. levels and concentrations at selected locations throughout the station. Reference Appendix D..
=;, .,84 2 Fire Dete i n Fire protection at SSES is provided by a complete network of fire suppression and extinguishing systems. These systems and associated fire alarms are activated by a variety of fire and smoke detection devices throughout the plant. Types of detectors include combustion product, smoke, thermal, and flame. For more detail, reference the SSES FSAR and Fire Protection Review Report.
8.4.3 'atural Phenomena Monitors Monitors are provided for detecting and recording natural phenomena events that could result in plant damage due to ground motion or structural vibration. Reference Appendix D.
8.44 Environmental M nitorin This program establishes the pre-operational background levels, detects any gradual buildup of long-lived radionuclides, and verifies that operation of the plant has no detrimental e6ect on the health and safety of the public or the environment. Reference Appendix D.
8.4.5 Emer n Moni rin Team E ui men Reference Appendix D.
8,5 PROTE TIVE FA ILITIE 8.5.1 Contr 1R m Protective features (Reference the SSES FSAR):
a) Adequate shielding by concrete walls.
Rev. 22, 04/95 8-13
b) CREOASS..
c) ARM system indications.
d) Emergency and essential lighting and power..
e) Basic protection equipment for emergency teams (Appendix D), and listings/locations of additional emergency supplies/equipment.
f) Communications systems.
852 Stai nA em I Area Specific locations are designated for assembly and accountability of all station personnel. They are located on the basis of logical access routes and physical separation from likely areas of radiation and/or airborne radioactivity. Reference the EP-PSs.
8.53 Remote A sem l Areas Upon declaration of a Site Evacuation, the ED may send personnel to their homes or to Remote Assembly Areas. These areas are designated for assembly of personnel which can be used to augment the plant staff Locations were selected on the basis of:
a) Space availability for all personnel who may be within the exclusion area at the time of an evacuation.
b) Assurance of a controlled area for contamination surveys and for possible establishment of decontamination stations.
8.5.4 Public Notification stem A PNS consisting of sirens with ratings ranging from 107 db to 125 db exists within the ten-mile EPZ around SSES. Siren location was determined by a detailed study including field surveys, actual determination of average background noise level, and consideration of population distribution within the 10-mile EPZ.
Activation of the PNS is via radio control from either the LCEMA Emergency Operations Center or the PP&L Emergency Operations Facility and by telephone from the CEMA Emergency Operations Center. The Nuclear Emergency Alert signal is a steady 3-5 minute wail. Public response to this signal is to proceed indoors and tune their radio or television to the Emergency Broadcast System Network serving their local area for additional information.
Testing of the system takes place annually and includes verification of the system's ability to alert the general public. Reference Figure 8.6.
Rev. 22, 04/95 8-14
8.6 ADDITIONALCO CATIONS SYSTEMS 8.6.1 ommonwealth/Bell Tele hone S stem Two independent telecommunications networks exist to provide primary and backup telephone communications between ERFs and offsite agencies. These systems are the Centrex Telephone Network (CTN) and Electronic Tandem Network (ETN).
CTN extension locations include: Control Room, TSC, EOF, MOC, SOP, DER/BRP, GOESC, PEMA, LCEMA, and CEMA. This is the primary system for emergency communications.
8.6,2 Plant Emer en Alarm S stem A plant emergency alarm system provides audible warning of emergency conditions to plant personnel. The system consists of a multi-tone generator, tone selector switch, area selector switch, and message tape recorder. The Emergency Alarm System is integral to the PA System and is powered via the Vital AC UPS. The Plant Emergency Alarm System is tested at least weekly.
8.7 ON- ITE FIR T AID AND MEDICALFACILITIES A first aid treatment facility, equipped with normal industrial first aid supplies, is located on the first floor of the S&A Building. Standard first aid kits are at designated locations throughout the station. Inventories are performed regularly.
8 8 DAMA E NTROL E MENT Damage control equipment consists of normal and special purpose tools and devices used for maintenance functions throughout the station. The ED has access to keys for maintenance tool cribs, shops and other locations where damage control equipment is stored. Inventories are performed regularly.
89 INF RMATI N Y TEM 8.9.1 Saf P et r Dis la em The purpose of the SPDS is to provide a continuous indication of the safety status of the plant.
SPDS data aids the control room, and TSC staff in rapidly detecting abnormal operating
.conditions, by enabling the staff to achieve a timely status assessment without surveying the entire Control Room.
SPDS includes sensors and signals, data acquisition equipment, data preparation equipment, and a data display device. SPDS consists of three separate sofbvare/hardware systems: separate systems serving the control room and the TSC for each unit, and a third serving the EOF. Data for Unit 1 and Unit 2 is collected separately by dedicated Data Acquisition Systems.
Rev. 22, 04/95 8-15
8.9.1.1 Data In The SPDS I
The SSES emergency procedures were developed from the BWR Emergency Procedure Guidelines (EPGs). The EPGs were developed by GE and BWR Owner's Group to comply with Task Action Plan Item I.C.1 item 3 as clarified by NUTMEG-0737. The Owner's Group performed a comprehensive study to identify a minimum set of EPGs which provide'coverage of plant safety functions and FSAR Chapter 15 events. Table 8-1 presents a list of parameters which have been derived from the plant emergency procedures and form the safety parameter set for the SPDS.
Where available, inputs are taken from redundant sensors. This allows SPDS to validate critical parameters on a real-time basis. The accuracy of the data acquired is consistent with accuracy needed to perform the various emergency functions. The time resolution of each sensor signal depends on the potential transient behavior of the variable being measured, and the scan rate for each variable is determined accordingly. One sample per second is the fastest that any given variable is scanned.
All signal interfaces to safety systems utilize isolation devices to prevent interference, degradation, or damage to any element of those safety systems as specified in 10 CFR 50 General Design Criteria 22, 23 and 24, and in IEEE Standard 279-1971 Sec. 4.7.
8912 D Ac ui iti n Because the SPDS contains a small computer dedicated to performing data acquisition, data processing, and data display functions solely for the SPDS, data scan and monitoring of the safety parameters is independently achieved.
Data acquisition hardware is designed to achieve maximum scanning communication availability.
Expandability criteria is also factored into the data acquisition design.
8.9.1 3 Da a Pre aration Once the data has been acquired, it is prepared and then output to the SPDS display. Data from the data acquisition system is stored in memory and processed before it is presented to personnel.
Sofbvare provides for data acquisition, preparation, and presentation. The data base includes raw data converted to engineering units, validated data, and calculated data, which is used for trends or time derivatives.
8 9 1 4 Data Presentati n The SPDS display is responsive to transient conditions and is sufBcient to indicate the plant status. A simple primary display, using human factors engineering criteria, gives an overall system status, and includes as a minimum the following parameters: Reactivity control, reactor core cooling and heat removal from primary system, reactor coolant system integrity, radioactivity control and containment integrity. The display is easily accessible and visible. An audible notification is included in the Control Room to alert personnel of an unsafe operating condition.
Rev. 22, 04/95 8-16
8.9 1 5. Availabilit This system has an availability in the 99% area above cold shutdown, and 80% area during cold shutdown. Availability calculations are performed on a regular basis.
The availability of the system is enhanced by a comprehensive maintenance program and with built-in facilities. Power supplies for SPDS are shown on Figure 8.5.
8,9.2 Plant om ut r s em The PCS is used for emergency data configuration for the following reasons:
~ It contains CRT graphic and trending capabilities.
~ It provides for historical data recording and retrieval.
~ It has flexibilityto permit interfacing to additional IJO equipment.
~ It has a proven high degree of reliability.
~ It is capable of scanning and processing all of the data needed in the EOF and TSC that is not provided in SPDS.
~ It is located in a secure area within the control structure.
8 92 1 Data Ac uisition The data acquisition employed by the PCS contains most parameters required by the ERF. The ERF data acquired by the PCS undergoes the normal validity and error checking applied to all PCS inputs. Isolation is applied to all safety-related signals.
8.9.22 D aPre aration Display formats needed by the ERF are generated and stored within the PCS using the existing format generators. The system to manage the data is designed such that input/output processing overhead is minimized.
Proven system and application software has been developed which performs data display and system security. The data base includes raw data, data converted to engineering units, data checked on a real-time basis, and various types of calculated data. The system determines the data that is displayed and the available output format.
User interaction with the system is also determined by the sofbvare. Although identical, the VO processes for data display in the TSC function independently of those for EOF.
8.9 2 3 Data Presentati n Two CRTs tied to the PCS provide for display functions in the TSC. Procedures and methods for keyboard call-up and error indication of TSC functions are identical to those in use in the control room. There are also two CRT's in the EOF which are functionally identical to those in the TSC.
Rev. 22, 04/95 8-17
Data is presented in formats which are easy to understand and interpret. Variables not in a normal condition are presented with an indication of that condition. Alarms are represented by using the same color coding techniques as the control room computer. Output formats are designed according to human factors engineering criteria, and include pattern and coding techniques.
8 9.2.4 Availabilit A minimum system availability of 97% can be guaranteed, based upon analytical calculations.
89.3 Rem te Data Anal sis S tern The RDAS is used to provide meteorological and vent data for the following reasons:
~ Flexible architecture to allow efficient interfacing to other data sources
~ Proven high degree of reliability
~ Located in EOF computer area
~ Redundant computer system design
~ Duplicate system console and controls reside in PCS room in plant.
8 9.3 1 D a A uisition I
Data is acquired over a fiber optic data link from the PCS. This includes the meteorological, mode switch parameters, and radiological release data. All data inputs and outputs are retained in historical files for archive or later recall and analysis.
8.9,3,2 Da a Presentati n The data can be printed in the EOF and TSC.
8.9.3 3 Availabili Based on previous system experience and two years of RDAS operational data, it is expected that the system should be able to achieve an availability of 98% or higher.
89.4 Emer en Res nseData m The purpose of ERDS is to transmit a limited set of plant performance parameters from the site to the Nuclear Regulatory Commission during an Alert or higher emergency classification.
8.9.4.1 Data Ac ui iti n Data required to support ERDS is acquired &om plant process computer system data bases which include SPDS, PCS and vent monitor systems.
Rev. 22, 04/95 8-18
8.9.4.2 Data Presentation ERDS does not have any capability for local data presentation of the parameters being transmitted to the NRC beyond what already exists for the SPDS, PCS and RDAS computers.
8.9.4.3 Avail ilit Based on previous system experience, it is expected that the system should be able to achieve an availability of 98% or higher.
Rev. 22, 04/95 8-19
8.0 EMERGENCY FACILITIES AND EQUIPMENT The Station Control Room is the primary location for the initial assessment and coordination of corrective actions for all emergency conditions. The Control Room is equipped with the display and controls for all critical plant systems, radiological and meteorological monitoring systems, and all station communication systems. Reference Appendix D.
Off-site emergency functions initially served by the Control Room are transferred to the. TSC or EOF for a Site Area or a General Emergency as deemed appropriate by the ED. The primary consideration is to ensure that the number of personnel involved with the emergency in the Control Room shall not impair the safe and orderly shutdown of the reactor or the operation of plant safety systems.
The OSC is the primary on-site assembly area for operations support team personnel during an emergency. It occupies 340 square feet adjacent to the Control Room on El. 729'-1" of the control structure.
The OSC is utilized initially as the central location for the assembly, accountability, and dispatching of on-shift emergency team personnel required to perform such functions as: fire fighting, first aid, search and rescue, damage control, and on-site radiation monitoring. If and when the TSC is activated, all non-operations support team personnel assemble and are accounted for at their individual assembly areas. TSC personnel assess the need for emergency team personnel and based on this assessment, dispatch team personnel from their assembly area or via call-in to perform TSC team functions. Long term retention of additional personnel to support in-plant team functions will be in the Maintenance and IAC assembly areas. These areas will be monitored continuously for habitability. If these areas become uninhabitable, retained personnel will be directed to alternate holding areas. Control and dispatch of these teams is the responsibility of the TSC Radioman. The OSC continues to manage operations support personnel, even after the TSC is activated.
Equipment required for these teams to perform their functions, as outlined in Appendix D is stored and maintained in the Control Room, Technical Support Center and Health Physics access control points.
During normal plant operations, this area serves as an operations staff work area for shift changeover purposes as well as shift work assignment area. The Non-Emergency use of the OSC does not degrade its primary purpose.
Rev. 24, 06/96 8-1
OSC personnel are protected from radiological hazards, including direct shine and airborne activities for postulated accident conditions to the same degree as Control Room personnel.
Applicable criteria are specified in General Design Criterion 19, Standard Review Plan 6.4, and NUREG-0737, Item II.B.2.
The radiation dose to personnel occupying the OSC is the same as the Control Room personnel.
The doses from controlling accidents are summarized in Chapter 15.0 of the FSAR.
To ensure adequate radiological protection of the OSC personnel, a commercial grade monitor alarms on high gross gamma radiation dose rates.
The OSC HVAC system is a part of the Control Room HVAC system which is described in FSAR Section 9.4.1.
Shielding requirement for the OSC is the same as for the Control Room for total dose to occupants from direct shine and airborne. Exposure does not exceed 5 Rem whole body for the duration of the accident. This is in accordance with General Design Criterion 19, USNRC Standard Review Plan 6.4, and NUREG-0737, Item II.B.2. Duration of occupancy and method of analysis is the same as that used for the Control Room.
No toilet facilities are provided in the OSC. Facilities are available in the Control Room and at grade level of the control structure for washing and toilet accommodations.
The OSC communication system includes priority access voice links-hotlines, the plant PA system and telephone lines tied through the plant switchboard.
The normal telephone service for the OSC uses the plant ETN and CTN systems. Both systems have the capability to reach on- and off-site locations.
Rev. 24, 06/96 8-2
Priority access voice communication links with automatic signaling is provided in the OSC. The OSC hotline connects with the TSC or the Control Room.
The PA system is part of the plant PA system. The system provides two-way communications at handset stations. Each station may originate and receive communications by switching to either a page channel or to one of five non-interfering party line channels.
The TSC is a controlled access area which provides working space and facilities for 25 NERO personnel. These personnel provide guidance to plant operations personnel for management of emergency conditions and accident mitigation.
The TSC is located in the existing Control Room mezzanine above the Control Room at elevation 741'-I" of the control structure and occupies approximately 2500 square feet. The TSC is within approximately two minutes travel time of the Control Room by elevator or stairs.
The TSC facilities may be used for normal daily activities which do not degrade TSC emergency preparedness. The TSC provides office space for Operations and Technical personnel. The facilities may also be used as a research or reference area by other station personnel.
The TSC includes areas for work, conferencing (NRC Ec PP8cL), document control, and computer monitoring. Housed components are SPDS, UMC, PICSY SDS, video copier, RDAS (printer/terminal), and SPING monitor panel. (Reference Figure 8.2).
Automatic wet pipe sprinklers on an ordinary hazard pipe schedule are provided.
The TSC is part of the control structure which is a Seismic Category I structure, as defined in NRC Regulatory Guide 1.29. It is designed in accordance with Chapter 3.0 of the FSAR.
Rev. 24, 06/96 8-3
TSC personnel are protected from radiological hazards, including direct shine and airborne activities for postulated accident conditions to the same degree as control room personnel.
Applicable criteria are specified in General Design Criterion 19, Standard Review Plan 6.4, and NUREG-0737, Item II.B.2.
The radiation dose to personnel is the same as the Control Room personnel. The doses from controlling accidents are summarized in Chapter 15.0 of the FSAR.
Commercial grade monitors are provided to alarm on high gross gamma radiation dose rates. In addition, airborne radioactivity concentrations are monitored by portable monitors. Iodine detection capability is provided.
The TSC HVAC system is a part of the Control Room HVAC system which is described in FSAR Section 9.4.1.
Shielding is the same as for the Control Room for total dose to occupants from direct shine and airborne. Exposure will not exceed 5 Rem whole body for the duration of the accident. This is in accordance with General Design Criterion 19, USNRC Standard Review Plan 6.4, and NUREG-0737, Item II.B.2. Duration of occupancy and method of analysis is the same as for the control room.
No sleeping accommodations or toilet facilities are provided. Use of the plant's existing facilities at grade level of the control structure for washing and toilet accommodations is available. There is a unit kitchen with appliances and sink. Self-contained breathing apparatus are available.
The TSC communications system is comprised of three telephone networks (ETN, CTN, and back-FTS), VHF and UHF radios, and the plant PA system. They provide reliable primary and up communication links to emergency response facilities on- and off-site.
Rev. 24, 06/96 8-4
The TSC uses the CTN system as primary communications with the ETN system available at various locations and the FTS 2000 reserved for federal government agencies.
The TSC has a four-channel 450 MHz UHF and a two-channel 150 MHz VHF radio system with digital voice privacy capability. The VHF radio is an emergency backup for communication with LCEMA and CCDES, and to communicate with the field monitoring teams. The UHF radio provides primary and backup security, emergency, operational and maintenance communication links.
The system provides two-way communications at handset stations. Each station may originate and receive communication by switching to either a pager channel or to one of five non-interfacing party-line channels.
The TSC is part of the existing power block as described in Chapter 8.0 of the FSAR.
The TSC utilizes the same field sensors and signal conditioning equipment which is provided to monitor plant systems. TSC instrumentation is identical to the 'field instrumentation used to operate the plant. A detailed description of this instrumentation is provided in Chapter 7.0 of the FSAR.
The TSC includes human factors engineered man-machine capabilities to allow personnel to determine:
~ plant conditions during normal operation
~ plant steady-state conditions prior to an accident
~ transient conditions producing an initiating event
~ plant system dynamic behavior during an accident
~ projected behavior and effects of offsite airborne radioactivity releases.
The man-machine interface is provided by devices tied to the SPDS, PCS, PICSY, and RDAS in the TSC monitoring area: (Reference Figure 8.2).
a) Two CRTs housed in the SPDS console.
Rev. 24, 06I96 8-5
b) Two PCS UMCs which have graphic and parameter displays depicting the conditions of the plant systems.
c) Video copiers for hard copy output of SPDS, PICSY, and PCS data d) RDAS printer/terminal for display of meteorological and vent data.
The TSC contains up-to-date records and references for use during emergency conditions.
(Reference Appendix D). Records are updated and managed by the Susquehanna Records Management System (SRMS) utilizing Plant Administrative Procedures.
The TSC is located within a plant vital area and is subject to the vital area access controls as identified in FSAR Section 13.6.
For an Unusual Event, the Susquehanna Energy Information Center, located on U.S. Route 11, is utilized as the Media Operations Center. For other event classifications, the East Mountain Business Center, Plains Township, will be activated as the Media Operations Center.
The EOF is an emergency response facility which provides continuous management of PP&L activities during radiological emergencies which may have offsite impact.
The EOF is located on East Mountain Road in Plains Township, off PA Route 115 (five miles north of exit 36 of the Northeast Extension of the Pennsylvania Turnpike and one mile south of exit 47A of Interstate 81). As the EOF is located beyond 10 miles from the site, the NRC Commission approval was required prior to the relocation. This was granted April 17, 1996 (see REFERENCES, Section 3.19).
The non-emergency activities of the EOF are such that its main function is not degraded. The EOF provides office space for PP&L Marketing Department.
The EOF is a one-story, rectangular structure. The building was constructed using standard building codes.
Rev. 24, 06/96 8-6
Reference Figure 8.3.
a) Automatic wet pipe sprinklers on an ordinary hazard pipe schedule are provided throughout the building.
The EOF is classified as a structure, the failure of which would not result in release of significant radioactivity, and is not required for reactor shutdown. This structure is classified as Non-Category I.
The EOF is located outside the EPZ, therefore, no special habitability needs are required.
The EOF communications system is comprised of three telephone networks (ETN, CTN, and FTS), VHF and UHF radios, and a PA system. They provide a reliable primary and back-up communications network.
The EOF uses a combination of the CTN and ETN.systems with the FTS system available for federal governmental agencies.
The EOF has both a four-channel 450 MHz UHF and a two-channel 150 MHz VHF radio system.
The VHF system is used as an emergency backup to the telephone system and to communicate with the field monitoring teams. The UHF radio allows EOF personnel to monitor security, emergency, operational, and maintenance communication links.
Power is supplied to the EOF via two independent underground power lines which supply the industrial park complex.
Rev. 24, 06/96 8-7
The EOF includes human factors'engineered man-machine interface capabilities to allow personnel to:
~ access environmental conditions
~ coordinate radiological monitoring activities
~ recoinmend implementation of off-site emergency plans
~ monitor Emergency Re'sponse Data System The EOF contains up-to-date references and records. Documents are managed by DCS using plant administrative procedures.
EOF access during an emergency is limited to authorized personnel. Intrusion detection devices monitor the EOF during unoccupied periods.
Both LCEMA and CCDES have EOCs which meet or exceed the minimum Federal criteria for sufficient space, communications, warning systems, self-suFiciency in supplies and accommodations and radiological protection factor. Both counties maintain full-time employees, providing 24-hour per day coverage at their EOC, to coordinate emergency planning and evaluation. "CTN" telephone connections exist between SSES and each County EOC.
Location of the county EOCs:
~ Luzerne County Wilkes-'Barre, Pennsylvania
~ Columbia County Court House Bloomsburg, Pennsylvania The State EOC is located at the PEMA headquarters, in the Transportation Building, in Harrisbur'g. This center is equipped with a reliable communications system which includes "CTN" telephone connections between the EOC and SSES, and ties to all area and county EOCs.
During an emergency, representatives from appropriate State agencies will assemble at the State EOC to manage and support the emergency response activities. Facilities are also'vailable at the EOF.for PEMA personnel.
Rev. 24, 06/96 S-3
This on-site system, consisting of ARMs, CAMs, and process monitors, contributes to personnel protection, equipment monitoring and accident assessment by measuring and recording radiation levels and concentrations at selected locations throughout the station. Reference Appendix D.
Fire protection at SSES is provided by a complete network of fire suppression and extinguishing systems. These systems and associated fire alarms are activated by a variety of fire and smoke detection devices throughout the plant. Types of detectors include combustion product, smoke, thermal, and flame. For more detail, reference the SSES FSAR and Fire Protection Review Report.
Monitors are provided for detecting and recording natural phenomena events that could result in plant damage due to ground motion or structural vibration. Reference Appendix D.
This program establishes the pre-operational background levels, detects any gradual buildup of long-lived radionuclides, and verifies that operation of the plant has no detrimental eQect on the health and safety of the public or the environment. Reference Appendix D.
Reference Appendix D.
Protective features (Reference the SSES FSAR):
a) Adequate shielding by concrete walls.
b) CREOASS.
c) ARM system indications.
d) Emergency and essential lighting and power.
Rev. 24, 06/96 8-9
e) Basic protection equipment for emergency teams (Appendix D), and listings/locations of additional emergency supplies/equipment.
f) Communications systems.
Specific locations are designated for assembly and accountability of all station personnel. They are located on the basis of logical access routes and physical separation from likely areas of radiation and/or airborne radioactivity. Reference the EP-PSs.
Upon declaration of a Site Evacuation, the ED may send personnel to their homes or to Remote Assembly Areas. These areas are designated for assembly of personnel which can be used to augment the plant staff. Locations were selected on the basis of:
a) Space availability for all personnel who may be within the exclusion area at the time of an evacuation.
b) Assurance of a controlled area for contamination surveys and for possible establishment of decontamination stations.
A PNS consisting of sirens with ratings ranging from 107 dB to 125 dB exists within the ten-mile EPZ around SSES. Siren location was determined by a detailed study including field surveys, actual determination of average background noise level, and consideration of population distribution within the 10-mile EPZ.
Activation of the PNS is via radio control from either the LCEMA Emergency Operations Center or the PP&L Emergency Operations Facility and by telephone from the CCDES Emergency Operations Center. The Nuclear Emergency Alert signal is a steady 3-5 minute wail. Public response to this signal is to proceed indoors and tune their radio or television to the Emergency Alert System Network serving their local area for additional information.
Testing of the system takes place annually and includes verification of the system's ability to alert the general public. Reference Figure 8.6.
Two independent telecommunications networks exist to provide primary and backup telephone communications between ERFs and offsite agencies. These systems are the Centrex Telephone Network (CTN) and Electronic Tandem Network (ETN).
Rev. 24, 06/96 8-10
CTN extension locations include: Control Room, TSC, EOF, MOC, SOP, DEP/BRP, PEMA, (
LCEMA, and CCDES. This is the primary system for emergency communications.
A plant erne'rgency alarm system provides audible warning of emergency conditions to plant personnel. The system consists of a multi-tone generator, tone selector switch, area selector switch, and message tape recorder. The Emergency Alarm System is integral to the PA System and is powered via the Vital AC UPS. The Plant Emergency Alarm System is tested at least weekly.
A first aid treatment facility, equipped with normal industrial first aid supplies, is located on the first floor of the S&A Building. Standard first aid kits are at designated locations throughout the station. Inventories are performed regularly.
Damage control equipment consists of normal and special purpose tools and devices used for maintenance functions throughout the station. The ED has access to keys for maintenance tool cribs, shops and other locations where damage control equipment is stored. Inventories are performed regularly.
The purpose of the SPDS is to provide a continuous indication of the safety status of the plant.
SPDS data aids the control room, and TSC staff in rapidly detecting abnormal operating conditions, by enabling the. staff to achieve a timely status assessment without surveying the entire Control Room.
SPDS includes sensors, signals, data acquisition equipment, data preparation equipment, and data display devices. Data for Unit 1 and Unit 2 is collected separately by dedicated Data Acquisition Systems. Unit 1 data is available in the Control Room and TSC via SPDS. Unit 2 data is transmitted to the Unit 2 PICSY and is available on any PICSY SDS'located in the Control Room, TSC, EOF, MOC, General OQice, or Simulator. Unit 1 SPDS data will be installed on the PICSY SDS during the second quarter of 1998., This section will be revised after the installation of PICSY on Unit 1.
The SSES emergency procedures were developed from the BWR Emergency Procedure Guidelines (EPGs). The EPGs were developed by GE and BWR Owner's Group to comply with Task Action Plan Item I.C.1 item 3 as clarified by NUREG-0737. The Owner's Group performed Rev. 24, 06/96 8-11
a comprehensive study to identify a minimum set of EPGs which provide coverage of plant safety functions and FSAR Chapter 15 events. Table 8-1 presents a list of parameters which have been derived from the plant emergency procedures and form the safety parameter set for the SPDS.
Where available, inputs are taken from redundant sensors. This allows SPDS to validate critical parameters on a real-time basis. The accuracy of the data acquired is consistent with accuracy needed to perform the various emergency functions. The time resolution of each sensor signal depends on the potential transient behavior of the variable being measured, and the scan rate for each variable is determined accordingly. One sample per second is the fastest that any given variable is scanned.
All signal interfaces to safety systems utilize isolation devices to prevent interference, degradation, or damage to any element of those safety systems as specified in 10 CFR 50 General Design Criteria 22, 23 and 24, and in IEEE Standard 279-1971 Sec. 4.7.
Once the data has been acquired, it is prepared and then output to the SPDS display. Data from the data acquisition system is stored in memory and processed before it is presented to personnel.
Sofbvare provides for data acquisition, preparation, and presentation. The data base includes raw data converted to engineering units, validated data, and calculated data, which is used for trends or time derivatives.
The SPDS display is responsive to transient conditions and is sufficient to indicate the plant status. A simple primary display, using human factors engineering criteria, gives an overall system status, and includes as a minimum the following parameters: Reactivity control, reactor core cooling and heat removal &om primary system, reactor coolant system integrity, radioactivity control and containment integrity. The display is easily accessible and visible. An audible notification is included in the Control Room to alert personnel of an unsafe operating condition.
This system has an availability in the 99% area, above cold shutdown, and 80% area during cold shutdown. Availability calculations are performed on a regular basis.
The availability of the system is enhanced by a comprehensive maintenance program and with built-in facilities. Power supplies for SPDS are shown on Figure 8.5.
The PCS is used for Unit 1 emergency data configuration for the following reasons:
Rev. 24, 06/96 8-12
~ It contains CRT graphic and trending capabilities.
~ It provides for historical data recording and retrieval.
~ It has fiexibilityto permit interfacing to additional I/O equipment.
~ It has a proven high degree of reliability.
~ It is capable of scanning and processing all of the data needed in the EOF and TSC that is not provided in SPDS.
~ It is located in a secure area within the control structure.
The data acquisition employed by the Unit 1 PCS contains most parameters required by the ERF.
The ERF data acquired by the Unit 1 PCS undergoes the normal validity and error checking applied to all PCS inputs. Isolation is applied to all safety-related signals.
Display formats needed by the ERF are generated and stored within the PCS using the existing format generators. The system to manage the data is designed such that input/output processing overhead is minimized.
Proven system and application software has been developed which performs data display and system security. The data base includes raw data, data converted to engineering units, data checked on a real-time basis, and various types of calculated data. The system determines the data that is displayed and the available output format.
Two CRTs tied to the Unit 1 PCS provide for display functions in the TSC. Procedures and methods for keyboard call-up and error indication of TSC functions are identical to those in use in the control room.
Data is presented in formats which are easy to understand and interpret. Variables not in a normal condition are presented with an indication of that condition. Alarms are represented by using the same color coding techniques as the control room computer. Output formats are designed according to human factors engineering criteria, and include pattern and coding techniques.
A minimum system availability of 97% can be guaranteed, based upon analytical calculations.
The RDAS is used to provide Unit 1 meteorological and vent data for the following reasons:
~ Flexible architecture to allow efficient interfacing to other data sources Rev. 24, 06/96 8-13
~ Proven high degree of reliability
~ 'edundant computer system design
~ Duplicate system console and controls reside in PCS room in plant.
Unit 1 data is acquired over a fiber optic data link from the PCS. This includes the meteorological, mode switch parameters, and radiological release data. All data inputs and outputs are retained in historical files for archive or later recall and analysis.
The data can be printed in the TSC.
Based on previous system experience and two years of RDAS operational data, it is expected that the system should be able to achieve an availability of 98% or higher.
The purpose of ERDS is to transmit a limited set of Unit 1 plant performance parameters from the site to the Nuclear Regulatory Commission during an Alert or higher emergency classification.
Data required to support ERDS is acquired from Unit 1 plant process computer system data bases which include SPDS, PCS and vent monitor systems.
ERDS does not have any capability for local data presentation of the parameters being transmitted to the NRC beyond what already exists for the SPDS, PCS and RDAS computers.
Based on previous system experience, it is expected that the system should be able to achieve an availability of 98% or higher.
The PICSY is used for emergency data configuration for the following reasons:
~ It contains CRT graphic and trending capabilities.
~ It provides for historical data recording and retrieval.
Rev. 24, 06/96 8-14
~ It has fiexibilityto permit interfacing to additional I/O equipment and other sources of data.
~ Its design provides for a high degree of reliability.
~ It is capable of scanning and processing all of the data needed in the EOF'and TSC.
~ It is located in a secure area within the control structure.
~ It has a redundant system design.
~ The ERDS and SPDS functions are integrated into its design.
~ All of the PICSY data and functions are easily made available at locations remote from SSES.
Data is acquired from I/O hardware in the plant as well as over data interfaces to various other plant equipment. All data is checked for validity and errors before being displayed to the user.
Isolation is applied to all safety-related inputs. All data is archived. Both short term and long term data are available for retrieval at any PICSY SDS. Long term data is available for at least the previous fuel cycle.
Display formats needed by the ERF are generated and stored within the PCS using standard proven PICSY software. A configuration management software system is employed to track changes to all formats and the data base itself.
Proven system and application software has been developed which performs data display and system security. The data base includes raw data, data converted to engineering units, data checked on a real-time basis, and various types of calculated data.
User interaction from the PICSY SDS is independent from each station and controlled by multiple copies of the identical software.
Three SDSs will be available in the TSC for display of Unit 2 data. Procedures and methods for call-up and error indications of TSC function are identical to those used in the control room with one exception. Control Room CRTs are usually fitted with touch screens in lieu of track balls
'nd keyboards.
Data is presented in formats which are easy to understand and interpret. Variables not in a normal condition are presented with an indication of that condition. Alarms are represented by using the same color coding techniques as in the control room. Output formats are designed according to human factors engineering criteria, and include, pattern and coding techniques.
A minimum system availability of 99% or greater can be guaranteed, based on analytical calculations.
Rev. 24, 06/96 8-15
CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9607050280 DOC.DATE: 96/06/28 NOTARIZED:,NO DOCKET I FACIL:50-387 Susquehanna Steam Electric Station, Unit 1, Pennsylva 05000387 50-388 Susquehanna Steam Electric Station, Unit 2, Pennsylva 05000388 AUTH. NAME AUTHOR AFFILIATION BYRAM,R.G. Pennsylvania Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards Rev 24 to "SSES Emergency Plan," incorporating C changes associated w/EOF move (approved by NRC staff),
organizational & administrative changes.
DISTRISUTION CODE: R045D COPIES RECEIVED:LTR TITLE: OR Submittal: Emergency Preparedness g
Plans, ENCL g SIZE:
Implement'g AII8 Procedures, C T
E NOTES: 05000387 G
RECIPIENT COPIES RECIPIENT COPIES 0 ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-2 PD 1 1 POSLUSNYPC 1 1 INTERNAL FILE CENTER.l 2 2 NRR/DRPM/PERB 1 1 S-A'BSTRACT 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 NOTES: 1 1 D
N NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTETH CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 9
Pennsylvania Power 8 Light Company Two North. Ninth Street ~ Allentown, PA 18101-1179 ~ 610/774-5151 Robert G. Byram Senior Vice President-iVuclear 610/774-7502 Fax: 610/774-5019 J l."28 896 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P 1-137
'Washington, DC 20555-SUSQUEHANNA STEAM ELECTRIC STATION NOTIFICATIONOF TRANSFER OF EMERGENCY FUNCTIONS TO THE NEW EMERGENCY OPERATIONS FACILITYIN WILKES-BARRE Docket Nos. 50-387 and 50-388 Pennsylvania Power & Light Company will be implementing the move of its Emergency Operations Facility (EOF) from directly west of the plant on Confers Lane to the East Mountain Business Center off Exit 47A of Interstate 81 near Wilkes-Barre. The implementation will take place on July 1, 1996. Attached is Revision No. 24 to the Emergency Plan for Susquehanna SES Units 1 and 2 which incorporates the changes associated with the EOF move (approved by the NRC staff) and other organizational and administrative changes that do not decrease the effectiveness of the Emergency Plan.
The only noticeable effect will be to those offsite agencies who would report to the new EOF location during an emergency. For all others the change will be unnoticeable. Phone numbers will be transferred and remain the same.
Ifyou have any comments or questions, please contact Ms. Cynthia A. Smith at (717) 542-3233.
Very truly yours, R. G yra Attachment
.. ~,(~-t -'
960628 C'607050280 PDR ADOCK 05000387 PDR F
FILE R41-2 PLA-4474 Document Control Desk copy:NRC Region I Ms. M. Banerjee NRC Sr. Resident Inspector-SSES Mr. R. Keimig Section Chief-Region I Mr. C. Poslusny, Jr. NRC Sr. Project Manager-OWFN Mr. J. Syracuse Luzerne County Emergency Management Ms. I. Miller Columbia County Department of Emergency Services Mr. C. Wynne PEMA
SUMMARY
OF CHANGES SSES EMERGENCY PLAN REYlSlON 24 1.0 DEFINITlONS Section 1.5 Changed Columbia County Emergency Management Agency (CCEMA) to Columbia County Department of Emergency Services (CCDES).
Section 1.7 Changed Corporate Management Committee (CMC) to Corporate Leadership Council (CLC).
Section 1.9 Changed Department of Environmental Resources/Bureau of Radiation Protection (DER/BRP) to Department of Environmental Protection/Bureau of Radiation Protection (DEP/BRP).
Section 1.19 Changed the location of the Emergency Operations to read "co-located with the Media Operations Center in Plains Township, Penna."
Section 1.23 Changed Emergency Plan Position Specific Procedures to Emergency Plan Position Specific instructions.
Deleted definition for General Office Engineering Support Center (GOESC) and renumbered remaining sections.
2.0 ACRONYlNS Section 2.5 Changed CCEMA to CCDES.
Section 2.11 Changed DER/BRP to DEP/BRP.
Deleted the acronyms BUEOF (Backup EOF) and GOESC (General Office Engineering Support Center) and renumbered remaining sections.
3.0 REFERENCES
Section 3.1 Changed CCEMA to CCDES.
Section 3.2 Changed DER/BRP to DEP/BRP.
Section 3.19 Added NRC Letter dated April 17, 1996 granting approval to move the Emergency Operations Facility to Plains Township facility.
Page 1 of 8
4,0 SCOPE AND CONTENTS Section 4.2.1 Changed CCEMA to CCDES and DER/BRP to DEP/BRP.
5.0 EMERGENCY CONDITIONS No changes.
6.0 ORGANIZATIONALCONTROL OF EMERGENCIES Under ~age, paragraph f), changed Vice President-Nuclear Operations'to Plant Manager-Susquehanna SES.
Under ~~,
Susquehanna SES.
changed Vice President-Nuclear Operations to Plant Manager-Under ~~gJQ, revised section to discuss manning requirements of "new" EOF.
Deleted reference to preparing the "otd" EOF for activation by the Interim Staff and one hour manning. Deleted reference to General Office Engineering Support Center.
(Note: the MOC is now part of the EOF organization.)
Section 6.2.1 Changed Vice President-Nuclear Operations to Plant Manager-Susquehanna SES.
Under j), deleted reference to EOF Support Manager and Engineering Support Manager. These positions have been eliminated.
Under m), changed DER/BRP to DEP/BRP.
Section 6.2.2 Revised the first paragraph to read: "position filled by Day Shift Supervisor, or a designated alternate. Typical alternates are SRO qualified personnel."
Section 6.2.5 Under a), revised section to reflect dose calculations remaining in the TSC.
Under d), changed Radiation Support Manager to Dose Assessment Supervisor. Deleted reference to Interim Radiation Support Manager.
Page 2 of 8
V Section 6.2.5 Under e), changed DER/BRP to DEP/BRP anr'adiation Support Manager to Dose Assessment Supervisor.
Under i) and j), added information to reflect new philosophy of dose calculations remaining in the TSC. Changed Radiation Support Manager to Dose Assessment Supervisor.
Section 6.2.6 Changed paragraph to read position is filled by "Systems Engineering supervisory personnel."
Under f), deleted reference to GOESC.
Under g), changed DER/BRP to DEP/BRP. Deleted reference to Lead Technical Support Staffer and Site Support Manager (positions eliminated).
Section 6.2.8 Deleted c), providing traffic control for the "old" EOF, Section 6.2.10 Changed first paragraph to read "position filled by Maintenance Supervisor personnel."
Section 6.3 Changed paragraphs 2 and 3 to address revised EOF activation, which is now automatic at the Alert classification. Deleted reference to the Interim Radiation Support Manager and Interim Recovery Manager.
Section 6.3.1.1 Under h), changed DER/BRP to DEP/BRP. Deleted reference to Interim Recovery Manager.
Section $ .3.1.2 Added Assistant Recovery Manager responsibilities. This position is appointed "as necessary."
Section 6.3.1.3 Defined the responsibilities for the new position of Engineering Support Supervisor, which combines the responsibilities of the Lead Tech Support Staffer from the "old" EOF organization, and the Engineering Support Manager from the GOESC.
Section 6.3.1.4 Added responsibilities for the position of EOF Support Supervisor, which replaces the Site Support Manager position in the "old" EOF organization.
Section 6.3.1.5 Added responsibilities for the position of Dose Assessment Supervisor, which replaces the Radiation Support Manager. Under d), changed DER/BRP to DEP/BRP.
Page 3 of 8
Section 6.3.1.6 Revised section to read "position is normally filled by engineering disciplines.".
Section 6.3.1.7 Added responsibilities for the position of Liaison Support Supervisor.
Section 6.3.2 Changed to reflect the Public Information Manager reporting to the Recovery Manager.
Section 6.3.3. Revised to reflect "Letters of Agreement" located in Attachment A.
Changed CCEMA to CCDES.
Section 6.4.1 Changed CCEMA to CCDES.
Section 6.4.2 Changed DER/BRP to DEP/BRP.
Section 6.4.3 Changed DER/BRP to DEP/BRP.
Section 6.5 Changed Corporate Management Committee to Corporate Leadership Council; changed DER/BRP to DEP/BRP; changed Manager Radiological Control to Radiological Manager; cha'nged Construction Manager to Maintenance Manager.
Deleted section on Administrative Support Manager in the EOF.
Deleted references to General Office Engineering Support Center.
Table 6.2 Under Technical Assessment, changed Site Support Manager to EOF Support Manager.
Deleted support for assessment from the GOESC. (GOESC eliminated, support supplied by EOF with assessment available from Nuclear Engineering located in Allentown) and address availability.
Under Rad/Accident Assessment at the EOF, changed Rad Support Manager to Dose Assessment Supervisor, changed Rad Assessment Team to Rad Assessment Staff, and address availability.
Table 6.3 Clarified reporting location.
Figure 6.1 Revised to reflect current organization.
Figure 6.2 Revised to reflect new EOF organization.
Figure 6.2a Deleted figure (staff no longer utilized).
Page 4 of 8
Figure 6.2b Deleted figure (staff no longer utilized).
Figure 6.4 Deleted figure (MOC staff moved to EOF organization).
Figure 6.5 Deleted figure (facility eliminated, function transferred to EOF).
Figure 6.6 Changed Plant Operations Manager to Plant Manager; changed Manager of Rad Assessment to Radiological Manager; changed Construction Manager to Maintenance Manager, all due to reorganization of EOF.
Figure 6.7 Changed Lead Tech Staffer to Engineering Support Supervisor; changed Rad Support Manager to Radiological Liaison; changed Site Support Manager to Liaison Support Supervisor, all due to relocation/reorganization of EOF.
7.0 EMERGENCY MEASURES Section 7.1.1 Deleted reference to Interim Radiation Support Manager (position eliminated).
Section 7.1.1.1 Changed southeast to east southeast. Added new weather information contacts.
Section 7.3.1.4 Added old to EOF to distinguish from "new" EOF.
Section 7.3.2 Changed CCEMA to CCDES, changed DER/BRP to DEP/BRP, changed EBS to EAS.
Section 7.4.2 Deleted reference to using EOF for decontamination facility. Due to relocation of facility, this is no longer appropriate.
Table 7.1 Added code 2 to "augment resources/activate offsite NERO."
Changed CCEMA to CCDES.
8.0 EMERGENCY FACILITIES AND EQUIPMENT Section 8.1.3.5.2 Changed CCEMA to CCDES.
Section 8.1.3.9 Changed DCS to Susquehanna Records Management System (SRMS).
Page 5 of 8
Section 8.2.1 Changed Northeast Division Headquarters to East Mountain Business Center, Plains Township.
Section 8.2.2 Revised description of EOF location and added reference to NRC approval to relocate. Revised third paragraph to reference other inhabitants of the facility.
Section 8.2.2.1 Revised building description.
Section 8.2.2.1.1 Revised to reflect new facility, Section 8.2.2.1.2 Revised to reflect new facility.
Section 8.2.2.3 Revised to reflect the deletion of special environmental needs with the location of the EOF outside the EPZ.
Section 8.2.2.5 Revised. New facility is located in an "ultra service Business Park" and is supplied by two independent power sources.
Section 8.2.2.5.2 Deleted section.
Section 8.2.2.6 Deleted paragraph addressing PCS, SPDS, ERDS Data Link, and Gulton color copiers.
Section 8.2.3 Deleted section. New facility is located outside the EPZ.
Section 8.2.4 Deleted section. Facility has been eliminated.
Section 8.3.1 Changed.CCEMA to CCDES.
Section 8.5.4 Changed CCEMA to CCDES and Emergency Broadcast System to Emergency Alert System.
Section 8.6.1 Changed CCEMA to CCDES, changed DERIBRP to DEP/BRP, and deleted reference to GOESC.
Section 8.9.1 Revised second paragraph to reflect current status of PICSY project.
Section 8.9.2.2 Deleted third paragraph explaining IIO process.
Section 8.9.2.3 Deleted reference to identical CRTs in the TSC and EOF.
Section 8.9.3 Deleted reference to EOF location.
Section 8.9.3.2 Deleted reference to RDAS printer located in the EOF.
Page 6 of 8
I Figure 8.1 Revised to reflect deletion of old EOF.
Figure 8.3 Pevised to reflect new EOF floor layout.
Figure 8.4 Intentionally blank (deleted Backup EOF).
Sections 8.2.2.3.1, 8.2.2.3.2, 8.2.2.3.2.2, and 8.2.2.3.3 were deleted.
9.0 MAINTAININGEMERGENCY PREPAREDNESS Section 9.1.1 Changed DER/BRP to DEP/BRP.
Section 9.1.2 Eliminated annual radio drills (radio drills are performed as part of our two full scale drills conducted annually).
Section 9.1.3 Deleted reference to Manager-Nuclear Department Support for assuring operational readiness of GOESC. Deleted BUEOF. These two facilities have been eliminated. Added reference to Plant Manager-Susquehanna SES.
Section 9.4.1 Changed CCEMA to CCDES.
APPENDIX A - LETTERS OF AGREEMENT Added letters of agreement for the following:
Department of Environmental Protection/Bureau of Radiation Protection U.S. Department of Commerce National Oceanic and Atmospheric Administration National Weather Service Deleted letter of agreement for Helgeson Scientific.
Changed DCS to Nuclear Records-SSES.
APPENDIX C - SSES EMERGENCY PLAN POS)TION SPECIFIC PROCEDURES Deleted thirty-eight procedures and added eight procedures.
APPENDIX D - EQUIPMENT INFORMATION LISTINGS Deleted source check under Typical Field Monitoring Team Equipment.
Page 7 of 8 Deleted microfilm and reader under Typical Emergency Operations Facility Equipment. Deleted section titled EOF HP Decontamination Equipment and Supplies (not utilized in new facility).
Deleted section titled GOESC. The facility has been eliminated.
Changed CCEMA to CCDES.
APPENDIX'J - NUREG4654 PLANNlNG STANDARD CROSS REFERENCE Section E, 1., defeted partial list of procedures.
Deleted titfes of old positions and added titles new positions throughout the document.
Page 8 of 8
PENNSYLVANIAPOWER & LIGHT COMPANY SUSQUEHANNA STEAN ELECTRIC STATION Q7g ~O
~wsc s~"
EMERGENCY PLAN THIS DOCUMENT HAS BEEN UPDATED TO INCI UDE REVISIONS THROUGH ~4 DATED
SUSQUEHANNA STEAM ELECTRIC STATION EMERGENCY PLAN, REVISION 24 REMOVE AND INSERT INSTRUCTIONS REMOVE INSERT Cover Page, PORC Mtg. ¹95-117 Cover Page, PORC Mtg. ¹96-059 Title Page, Revision 23, Title Page, Revision 24 List of Effective Pages, List of Effective Pages, pages LEP-1 to LEP-8, Rev. 23 pages LEP-1 to LEP-8, Rev. 24 Section 1.0, DEFINITIONS Section 1.0, DEFINITIONS pages 1-1 to 1-5, Rev. 22 pages 1-1 to 1-5, Rev. 24 Section 2.0, ACRONYMS Section 2.0, ACRONYMS pages 2-1 to 2-2, Rev. 23 pages 2-1 to 2-2, Rev. 24 Section 3.0, REFERENCES Section 3.0, REFERENCES page 3-1, Rev. 22 page 3-1, Rev. 24 Section 4.0, SCOPE AND CONTENTS Section 4.0, SCOPE AND CONTENTS page 4-1 to 4-2, Rev. 22 page 4-1 to 4-2, Rev. 24 Section 6.0, ORGANIZATIONAL Section 6.0, ORGANIZATIONAL CONTROL OF EMERGENCIES CONTROL OF EMERGENCIES pages 6-1 to 6-19, Rev. 22 pages 6-1 to 6-17, Rev. 24 Table 6.2, MINIMUMON-SITE AND OFF- Table 6.2, MINIMUMON-SITE AND OFF-SITE EMERGENCY ORGANIZATIONAL SITE EMERGENCY ORGANIZATIONAL CAPABILITIES CAPABILITIES pages 1, 2, 3, 4, Rev. 22 pages1,2,3,4, Rev. 24 Table 6.3, ADDITIONALASSISTANCE Table 6.3, ADDITIONALASSISTANCE FROM OUTSIDE PP8L FROM OUTSIDE PP&L page 1, Rev. 15 page 1, Rev. 24 Figure 6.1, SUSQUEHANNA SES Figure 6.1, SUSQUEHANNA SES ORGANIZATION ORGANIZATION Rev. 22 Rev. 24 Revision 24, 06/96
REliU <'!- INSERT Figure 6.2a, EOF ORGANIZATION (One Hour Activation) Figure 6.2, EOF ORGANIZATION Rev. 19 Rev. 24 Figure 6.2b, EOF ORGANIZATION (Fully Staffed)
Rev. 16 Figure 6.4, MOC ORGANIZATION Rev. 19 Figure 6.5, GENERAL OFFICE EMERGENCY ORGANIZATION Rev. 21 Figure 6.6, LONG TERM RESTORATION Figure 6.6, LONG TERM RESTORATION ORGANIZATION ORGAhtlZATION Rev. 11 Rev. 24 Figure 6.7, COMMUNICATIONS Figure 6.7, COMMUNICATIONS INTERFACE WITH OFF-SITE INTERFACE WITH OFF-SITE AGENCIES AGENCIES Rev. 15 Rev. 24 Section 7.0, EMERGENCY MEASURES Section 7.0, EMERGENCY MEASURES pages 7-1 to 7-7, Rev. 23 pages 7-1 to 7-8, Rev. 24 Table 7.1;
SUMMARY
OF IMMEDIATE Table 7.1,
SUMMARY
OF IMMEDIATE NOTIFICATIONAND RESPONSE FOR NOTIFICATIONAND RESPONSE FOR ALL CLASSIFICATIONS ALL CLASSIFICATIONS pages 1,2, Rev. 18 pages 1,2, Rev. 24 Section 8.0, EMERGENCY FACILITIES Section 8.0, EMERGENCY FACILITIES AND EQUIPMENT AND EQUIPMENT pages 8-1 to 8-20 Rev. 23 pages 8-1 to 8-15, Rev. 24 Figure 8.1, MAP OF THE Figure 8.1, MAP OF THE SUSQUEHANNA SES EMERGENCY SUSQUEHANNA SES EMERGENCY FACILITIES FACILITIES Rev. 11 Rev. 24 Revision 24, 06/96 REMOVE INSERT
. Figure 8.3, EMERGENCY OPERATIONS Figure 8.3, EMERGENCY OPERATIONS FACILITYFLOOR PLAN FACILITYFLOOR PLAN Rev. 11 Rev. 24 Section 9.0, MAINTAINING Section 9.0, MAINTAINING EMERGENCY PREPAREDNESS EMERGENCY PREPAREDNESS page 9-1 to 9-5, Rev. 22 page 9-1 to 9-5, Rev. 24 Appendix A, LETTERS OF AGREEMENT Appendix A, LETTERS OF AGREEMENT pages A-1 to A-3, Rev. 22 pages A-1 to A-3, Rev. 24 Appendix C, SSES EMERGENCY PLAN Appendix C, SSES EMERGENCY PLAN POSITION SPECIFIC PROCEDURES POSITION SPECIFIC PROCEDURES (TYPICAL) (TYPICAL) pages C-1 to C-3, Rev. 22 pages C-1 to C-2, Rev. 24 Appendix D, EQUIPMENT Appendix D, EQUIPMENT INFORMATION LISTINGS INFORMATION LISTINGS pages D-1 to D-17, Rev. 21 pages D-1 to D-16, Rev. 24 Appendix J, NUREG-0654 PLANNING Appendix J, NUREG-0654 PLANNING STANDARD AND EVALUATION STANDARD AND EVALUATION CRITERIA CROSS REFERENCE TO CRITERIA CROSS REFERENCE TO SSES EMERGENCY PLAN SSES EMERGENCY PLAN pages J-1 to J-13, Rev. 15 pages J-1 to J-13, Rev. 24 Revision 24, 06/96