Text

Browns Ferry, Units 1, 2, and 3, Emergency Plan Implementing Procedure (EPIP) Revisions
	ML003694233
Person / Time
Site:	Browns Ferry
Issue date:	03/15/2000
From:	Abney T; Tennessee Valley Authority
To:	; NRC/OCIO/IMD/RMB
References
	-RFPFR
	Download: ML003694233 (203)
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{{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609 March 15, 2000 10 CFR Part 50, APP.E U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentleman: In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 1, 2, and 3 EMERGENCY PLAN IMPLEMENTING PROCEDURE (EPIP) REVISIONS TVA is submitting this notification in accordance with the requirements of 10 CFR Part 50, Appendix E, Section V, to provide NRC with the following EPIP revisions: (1) EPIP Index; (2) EPIP-1, Revision 28B; (3) EPIP-2, Revision 21A; (4) EPIP-3, Revision 24A; (5) EPIP-4, Revision 23A; (5) EPIP-5, Revision 28A; (7) EPIP-6, Revision 20A; (8) EPIP-7, Revision 18A; (9) EPIP-8, Revision 11A; (10) EPIP-II, Revision 8A; (11) EPIP-15, Revision 6A; and (12) EPIP-17, Revision 23A. The revision date for these EPIP changes is March 9, 2000.

U.S. Nuclear Regulatory Commission Page 2 March 15, 2000 At the time of issuing (1) EPIP Index; (2) EPIP-1, Revision 28A; (3) EPIP-2, Revision 21; EPIP-3, Revision 24; (5) EPIP-4, Revision 23; (6) EPIP-5, Revision 28; (7) EPIP-6, Revision 20; (8) EPIP-7, Revision 18;(9) EPIP-8, Revision 11; (10) EPIP-II, Revision 8; (11) EPIP-15, Revision 6; and (12) EPIP-17, Revision 23, typographical errors were corrected, resulting in an additional revision level for each document. Since the latter revisions include all changes (typographical and substantive), TVA is only submitting the latter EPIP revisions. The enclosed information is being sent by certified mail. Please sign and return the receipt signifying that you have received this information. If you have any questions, please telephone me at (256) 729-2636. -T. E. Abney Manager Licens ng and ndustry Aff irs cc (Enclos e): NRC Resi Inspector (Enclosure provided by Browns Ferry Nuclear Plant BFN Document Control 10833 Shaw Road Unit) Athens, Alabama 35611 Mr. P. E. Fredrickson (2 Enclosures) U.S. Nuclear Regulatory Commission Region II 61 Forsyth Street S.W. Suite 23T85 Atlanta, Georgia 30303 Mr. W. 0. Long, Project Manager (w/o Enclosure) U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 208K

ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 EMERGENCY PLAN IMPLEMENTING PROCEDURES (EPIP) EPIPs -1, 2, 3, 4, 5, 6, 7, 8, 11, 15, and 17 SEE ATTACHED

GENERAL REVISIONS GENERIC FILING INSTRUCTIONS FILE DOCUMENTS AS FOLLOWS: PAGES TO BE REMOVED PAGES TO BE INSERTED EPIP INDEX (ALL) EPIP INDEX (ALL) EPIP-1 REVISION 27 (AFFECTED EPIP-1 REVISION 28B (SUPPLIED) SECTIONS) SECTIONS) EPIP-2 REVISION 20 (ALL) EPIP-2 REVISION 21A (ALL) EPIP-3 REVISION 23 (ALL) EPIP-3 REVISION 24A (ALL) EPIP-4 REVISION 22 (ALL) EPIP-4 REVISION 23A (ALL) EPIP-5 REVISION 27 (ALL) EPIP-5 REVISION 28A (ALL) EPIP-6 REVISION 19 (ALL) EPIP-6 REVISION 20A (ALL) EPIP-7 REVISION 17 (ALL) EPIP-7 REVISION 18A (ALL) EPIP-8 REVISION 10 (ALL) EPIP-8 REVISION 11A (ALL) EPIP-II REVISION 7 (ALL) EPIP-I1 REVISION 8A (ALL) EPIP-15 REVISION 5 (ALL) EPIP-15 REVISION 6A (ALL) EPIP-17 REVISION 22 (ALL) EPIP-17 REVISION 23A (ALL)

1 Page Browns Ferry Nucli .ant pgl01cc Curator Procedures F4 Screen 03/09/00 status=ACTIVE ProcType=EPIP DL- Type=PROCEDURE Sorted by Num Eff Dt Group Unit Doc Stat Section REV Proc Number Doc Type Title unit Proc Type E -1....... ecti... I PROCEDURE CLASSIFICATION 11/04/1999 OTHER 028 EPIP EMERGENCY PLAN 0 EPIP-1/Section I ACTIVE REP LOGIC ACTIVE PROCEDURE CLASSIFICATION 11/04/1999 OTHER 028 EPIP EMERGENCY PLAN 0 EPIP-1/Section II-2.0 ACTIVE REP LOGIC ACTIVE PROCEDURE CLASSIFICATION 11/04/1999 OTHER 028 EPIP EMERGENCY PLAN 0 EPIP-1/Section 11-2.0 ACTIVE REP LOGIC ACTIVE PROCEDURE CLASSIFICATION 11/04/1999 OTHER 028 EPIP EMERGENCY PLAN 0 EPIP-1/Section 11-3.0 ACTIVE REP LOGIC ACTIVE PROCEDURE *CLASSIFICATION 03/09/2000 OTHER 028B EPIP EMERGENCY PLAN 0 EPIP-1/Section 11-4.0 ACTIVE REP LOGIC ACTIVE PROCEDURE CLASSIFICATION 11/04/1999 OTHER 028 EPIP EMERGENCY PLAN 0 EPIP-1/Section 11-5.0 ACTIVE REP LOGIC ACTIVE PROCEDURE ICLASSIFICATION 11/04/1999 OTHER 028 EPIP EMERGENCY PLAN 0 EPIP-1/Section 11-6.0 ACTIVE REP LOGIC ACTIVE PROCEDURE ICLASSIFICATION 11/04/1999 OTHER 028 EPIP EMERGENCY PLAN 0 EPIP-1/Section 11-7.0 ACTIVE REP LOGIC ACTIVE PROCEDURE ICLASSIFICATION 11/04/1999 OTHER 028 EPIP EMERGENCY PLAIN 0 EPIP-1/Section 11-8.0 ACTIVE REP LOGIC ACTIVE PROCEDURE I CLASSIFICATION 11/04/1999 OTHER 028 EPIP EPIP-I/Section III-lo0 EMERGENCY PLAN 0 LOGIC ACTIVE REP ACTIVE PROCEDURE N CLASSIFICATION 11/04/1999 OTHER 028 EPIP EMERGENCY PLAI 0 EPIP-1/Section 111-2.0 ACTIVE REP LOGIC ACTIVE PROCEDURE N CLASSIFICATION 11/04/1999 OTHER 028 EPIP EMERGENCY PLAN 0 EPIP-1/Section 111-3.0 ACTIVE REP LOGIC ACTIVE N CLASSIFICATION 03/09/2000 OTHER 028B 0 EPIP EPIP-1/Section 111-4.0 PROCEDURE EMERGENCY PLAl ACTIVE REP LOGIC ACTIVE

l.ant Page Browns Ferry Nucl pgl01cc Curator Procedures F Screen 03/09/00 status=ACTIVE ProcType=EPIP Duu Type=PROCEDURE Sorted by Num Eff Dt Group Doc Stat Section REV unit Proc Type Proc Number Doc Type Title 11/04/1999 OTHER 028 EPI P EMERGENCY PLAN CLASSIFICATION 0 EPIP-1/Section 111-5.0 PROCEDURE ACTIVE REP LOGIC ACTIVE 11/04/1999 OTHER 028 EPIP EMERGENCY PLAN CLASSIFICATION 0 EPIP-1/Section 111-6.0 PROCEDURE ACTIVE REP LOGIC ACTIVE 11/04/1999 OTHER 028 EPIP EMERGENCY PLAN CLASSIFICATION 0 EPIP-1/Section 111-7.0 PROCEDURE REP ACTIVE LOGIC ACTIVE 11/04/1999 OTHER 028 EPIP EMERGENCY PLAN CLASSIFICATION 0 EPIP-1/Section 111-8.0 PROCEDURE ACTIVE REP LOGIC ACTIVE 03/09/2000 OTHER 028B EPIP EMERGENCY PLAN CLASSIFICATION 0 EPIP-1/TOC PROCEDURE ACTIVE REP LOGIC ACTIVE 07/09/1998 OTHER 019 EPIP MEDICAL EMERGENCY PROCEDURE 0 EPIP-10 PROCEDURE ACTIVE REP ACTIVE 03/09/2000 OTHER 008A EPIP SECURITY AND ACCESS CONTROL 0 EPIP-11 PROCEDURE REP ACTIVE ACTIVE 11/04/1999 OTHER 007 EPIP RADIOCHEMICAL LABORATORY 0 EPIP-13 PROCEDURE ACTIVE REP PROCEDURE ACTIVE 11/04/1999 OTHER 014 EPIP RADIOLOGICAL CONTROL PROCEDURES 0 EPIP-14 PROCEDURE ACTIVE REP ACTIVE 03/09/2000 OTHER 006A EPIP EMERGENCY EXPOSURE 0 EPIP-15 PROCEDURE REP ACTIVE ACTIVE 11/01/1995 OTHER 003 EPIP TERMINATION AND RECOVERY 0 EPIP-16 PROCEDURE REP ACTIVE PROCEDURE ACTIVE 03/09/2000 OTHER 023A EPIP EMERGENCY EQUIPMENT AND SUPPLIES 0 EPIP-17 PROCEDURE ACTIVE REP (INVENTORY AND OPERABILITY ACTIVE PROCEDURE) 021A EPIP 03/09/2000 OTHER 0 EPIP-2 PROCEDURE NOTIFICATION OF UNUSUAL EVENT ACTIVE REP ACTIVE

Browns Ferry Nucl' lant Page pgl01cc Curator Procedures F\ Screen 03/09/00 status=ACTIVE ProcType=EPIP L,; Type=PROCEDURE Sorted by Num Eff Dt Group Doc Stat Section REV unit Proc Type Proc Number Doc Type Title 06/14/1996 OTHER 009 0 EPIP EPIP-20 PROCEDURE PLANT DATA REP ACTIVE ACTIVE 06/25/1997 OTHER 002 EPIP FIRE EMERGENCY PROCEDURE 0 EPIP-21 PROCEDURE ACTIVE REP ACTIVE 03/09/2000 OTHER 024A EPIP PROCEDURE ALERT 0 EPIP-3 ACTIVE REP ACTIVE 03/09/2000 OTHER 023A EPIP PROCEDURE SITE AREA EMERGENCY 0 EPIP-4 ACTIVE REP ACTIVE 03/09/2000 OTHER 028A EPIP PROCEDURE GENERAL EMERGENCY 0 EPIP-5 ACTIVE REP ACTIVE 03/09/2000 OTHER 020A EPIP PROCEDURE ACTIVATION AND OPERATION OF THE 0 EPIP-6 ACTIVE REP TECHNICAL SUPPORT CENTER (TSC) ACTIVE 03/09/2000 OTHER 018A EPIP PROCEDURE ACTIVATION AND OPERATION OF THE 0 EPIP-7 ACTIVE REP OPERATIONS SUPPORT CENTER (OSC) ACTIVE 03/09/2000 OTHER 011A EPIP PERSONNEL ACCOUNTABILITY AND 0 EPIP-8 PROCEDURE ACTIVE REP EVACUATION ACTIVE

Browns Ferry Nucl( lant Page 7 Curator Procedures ý Screen pglOlcc Type=PROCEDURE 03/09/00 status=ACTIVE ProcType=EPIP bu Sorted by Num Eff Dt Group Doc Type Title Doc Stat Section REV Unit Proc Type Proc Number Curator Procedures Issued Count 34 Total 34 Total records selected: 34

END OF REPORT * *
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-1 EMERGENCY CLASSIFICATION PROCEDURE REVISION 28B PREPARED BY: T. W. CORNELIUS PHONE: 2038 RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS DATE: 03/08/2000 APPROVED BY: T. W. CORNELIUS EFFECTIVE DATE: 03/09/2000 LEVEL OF USE: REFERENCE USE VALIDATION DATE: NOT REQUIRED QUALITY-RELATED

REVISION LOG Procedure Number: EPIP- 1 Revision Number 28B Pages Affected: 34.132 Description of Change: EC-38 This change is being conducted to human factor the Revision Log, Description of Change and added clarification to revision log effecting rev. 28A. EPIP 1 (rev. log) was changed to reflect current revision level. Page 34, EPIP 1, Event Classification Matrix, Section 4, Table 4.1-S was reviewed and found to contain a editorial error. The concentration for the Iodine Site Boundary Radiation Reading was corrected (3.0 X 10- changed to 3.0 X 107). Page 132, EPIP 1. Basis. Section 4, Table 4.1-S was reviewed and found to contain a editorial error. The concentration for the Iodine Site Boundarv Radiation Reading was corrected (3.0 X 10 9 changed to 3.0 X 107). Revision 28A corrected this error.

EPIP-1 EMERGENCY CLASSIFICATION PROCEDURE TABLE OF CONTENTS PAGE NUMBER REVISION TA BLE O F CONTEN TS ............................................................................ 1 28B SECTION I INTRODUCTION CLASSIFICATION INSTRUCTIONS ............................................ 3 28 GL O SSARY ................................................................................... 5 28 EVENT CLASSIFICATION INDEX ............................................ 11 28 SECTION II EVENT CLASSIFICATION MATRIX 1.0 R EA C T O R .............................................................................. 13 28 2.0 PRIMARY CONTAINMENT ................................................. 21 28 3.0 SECONDARY CONTAINMENT ........................................... 29 28 4.0 RADIOACTIVITY RELEASES .............................................. 33 28B 5.0 LO SS OF POW ER .................................................................. 39 28 6.0 H AZAR DS .............................................................................. 45 28 7.0 NATURAL EVENTS .............................................................. 61 28 8.0 EMERGENCY DIRECTOR JUDGEMENT ............................ 67 28 SECTION III BASIS 1.0 RE AC T O R .............................................................................. 75 28 2.0 PRIMARY CONTAINMENT ................................................. 97 28 3.0 SECONDARY CONTAINMENT ......................................... 116 28 4.0 RADIOACTIVITY RELEASE .............................................. 126 28B 5.0 LO SS O F POW ER ................................................................ 139 28 6.0 HAZ A RD S ............................................................................ 155 28 7.0 NATURAL EVENTS ............................................................ 183 28 8.0 EMERGENCY DIRECTOR JUDGEMENT .......................... 190 28 PAGE 1 OF 207 REVISION 28B

EPIP-1 EMERGENCY CLASSIFICATION PROCEDURE THIS PAGE INTENTIONALLY BLANK PAGE 2 OF 207 REVISION 28B

EMERGENCY EPIP-1 SECTION H 4.0 RADIACTIVITY CLASSIFICATION RELEASE iDiDnP'nF*TTD'P EVENT CLASSIFICATION MATRIX RADIOACTIVITY RELEASES 4.0 4.0 RADIACTIVITY PAGE 33 OF 207 REVISION 28B RELEASE

EPIP-1 EMERGENCY 4.0 RADIACTIVITY SECTION II CLASSIFICATION RELEASE EVENT CLASSIFICATION MATRIX PROCEDURE NOTES: NOTE 4.1-U Prior to making this emergency classification based upon the WRGERMS indication, assess the release by either of the follOWing: 1.Actual field measurements exceed the linits in Table 4. 1-U

2. SI 4.8.B.

B La. Release Fraction exceeds 2.0 If neitheriassent can be conducted ithin 60 minutes then the declaratimn must be iade n the valid WRGERMS reading NOTE 4.1-A Prior to making this emergency classification based upon the WRGERMS indicationi assess the release by either of the following: 1.Actual field measurements exceed the limits in Table 4.1-A

2. S14.8.B.l.a.1 Release Fraction exceeds 200 Itneihfeira nent can be cnuted within 15 mninuttes then the declaration must be inacd on the valid WRGERMS reading NOTE 4.1-S Prior to making this emergency classification based upon the Gaseous Release Rate indication, assess thie release by either of the folloling methods:

1. Actual field measurements exceed the linits in Table 4. 1-S.

2. Projected or Actual Dose Assessmnents exceed 100 nrenm TEDE or 500 nrem CDE.

If neither assessment can be conducted within 15 minutes then the declaration must be made based on the valid WRGERMS reading. NOTE 4.1-G Prior to nmaking this emergency classification based upon the Gaseous Release Rate indication, assess the release by either of the following methods: 1.Actual field measurements exceed the limits in Table 4.1-G.

2. Projected or Actual Dose Assessments exceed 1000 Wrem TEDE or 5000 mrem CDE.

ff neither assessment can be conducted wNithin 15 mninutes then the declaration must be made based on the valid WRGERMS reading. CURVES/TABLES: Table 4.1-U RELEASE LIMITS FOR UNUSUAL EVENT TYPE MONITORING METHOD LIMIT DURATION GASEOUS RELEASE RATE STACK NOBLE GAS (WRGERMS) 2.88 N 10 LLtCi sec 1 HOLUR GASEOUS RELEASE RATE SI 4.8.B.1.a.1 RELEASE FRACTION 2.0 1 HOUR SITE BOtUNDARY RADIATION READING FIELD ASSESSMENT TEAM 0.10 MREM HR - 1I HOUR Table 4.1-A RELEASE LIMITS FOR ALERT TYPE J MONITORING METHOD LIMIT DURATION GASEOUS RELEASE RATE STACK NOBLE GAS (WRGERMS) 2.88 X 10 9 pCiisec 15 MINUTES GASEOUS RELEASE RATE SI 4.8.B.I.a.1 RELEASE FRACTION 200 15 MINUTES SITE BOUN*DARY RADIATION READING FIELD ASSESSMENT TEAM 10 MRENI HR 15 MINUTES Table 4.1-S RELEASE LIMITS FOR SITE AREA EMERGENCY TYPE MONITORING METHOD LIMIT DUU-TION GASEOUS RELEASE RATE STACK NOBLE GAS (WRGERMS) 1.3 N 10' ,Ciisec 15 MINUTES SITE BOUN.DARY RADIATION READING FIELD ASSESSMENT TEAM 100 \IRE\I'HR 7 - I HOUR SITE BOUNDARY IODINE-131 FIELD ASSESSMENT TEAM 3.9 X 10 "tCI cm3 I HOUR Table 4.1-G RELEASE LIMITS FOR GENERAL EMERGENCY TYPE MONITORING METHOD LIMIT DURATION GASEOUS RELEASE RATE STACK NOBLE GAS (WRGERMS) 1.3 X 10 " utCi sec 15 MINUTES SITE BOUNDARY RADIATION READING FIELD ASSESSMENT TEA.I 1000 MREM HRy 1 HOUR SITE BOUNDARY IODINE-131 FIELD ASSESSMENT TEAM 3.9 X 10-6 ,tCI cm 1 HOUR REVISION 28B PAGE 34 OF 207 4.0 RADIACTIVITY RELEASE

EMERGENCY EPILP-1 SECTION H 4.0 RADIOACTIVE CLASSIFICATION RELEASE PROCEDURE EVENT CLASSIFICATION MATRIX DESCRIPTION DESCRIPTION 4.2-U Gaseous rele eds ANY limit and duration in z Table 4.1-U. Main Steam Line break outside Primary Containment with isolation. z OPERATING CONDITION: OPERATING CONDITION: -Model - Mode 3

-All 4.1-A Gaseous release exceeds ANY limit and duration in Table 4. 1-A.

OPERATING CONDITION:

-All 4.1-S                                                        4.2-S
                                                                 =

EITHER of the following conditions exists: Unisolable Main Steam Line break outside Primary

  "*Gaseous release exceeds or is expected to exceed           Containment.

ANY limit and duration in Table 4.1-S.

  "* Dose assessment indicates actual or projected dose consequences above 100 mrem TEDE or 500 mrem thyroid CDE.                                                                                                   Z OPERATING CONDITION:

OPERATING CONDITION: - Mode I - Mode 3

 -All                                                         - Mode 2 4.1-G7 EITHER of the following conditions exists:
  "* Gaseous release exceeds inor Table is expected to exceed

4. 1-G.

ANY limit and duration

  "* Dose assessment indicates actual or projected   dose consequences above 1000 mrem TEDE or 5000 mrem thyroid CDE.

OPERATING CONDITION:

 -All 4.0 RADIACTIVITY                                     PAGE 35 OF 207                                        REVISION 28B:1 RELEASE

EPIP-1 EMERGENCY 4.0 RADIACTIVITY SECTION H CLASSIFICATION RELEASE EVENT CLASSIFICATION MATRIX PROCEDURE NOTES: CURVES/TABLES: REVISION 28B PAGE 36 OF 207 4.0 RADIACTIVITY RELEASE

EMERGENCY EPIP-1 SECTION II 4.0 RADIOACTIVE CLASSIFICATION RELEASE PROCEDURE EVENT CLASSIFICATION MATRIX EFFLUENT -~~mFT~h LIUI DESCRIPTION Vlb* 3% lulg 1 l.%in 4.3-U Liquid release rate exceeds 20 times ECL as determined by chemistry sample AND Release duration exceeds or will exceed 60 minutes. OPERATING CONDITION:

- All 4.3-A Liquid release rate exceeds 2000 times ECL as determined by chemistry sample Release duration exceeds or will exceed 15 minutes.

OPERATING CONDITION:

- All 00 i                                               I 0

z 0 z _______I - - - - - .-,x ,C'fThT I 101 4.0 RADIACTIVITY PAGE 37 OF 207 WLv13d *LIN.0" j1 1 RELEASE

EPIP-1 EMERGENCY 4.0 RADIACTIVITY SECTION II CLASSIFICATION RELEASE EVENT CLASSIFICATION MATRIX PROCEDURE THIS PAGE INTENTIONALLY BLANK REVISION 28B PAGE 38 OF 207 4.0 RADIACTIVITY RELEASE

EMERGENCY EPIP-1 SECTION III 4.0 RADIOACTIVTY CLASSIFICATION TIECHNICAL BASIS RELEASE TECHNICAL BASIS RADIOACTIVITY RELEASE 4.0 4.0 RADIOACTIVITY PAGE 126 OF 207 REVISION 28B RELEASE

EMERGENCY EPIP-1 CLASSIFICATION SECTION 111 4.0 RADIOACTMITY PROCEDURE TECHNICAL BASIS RELEASE UNUSUAL EVENT Gaseous release exceeds ANY limit and duration in Table 4.1-U. OPERATING - All CONDITION BASIS Unplanned radioactivity releases that exceed Table 4.1-U limits and continue for 1 hour or longer represent an uncontrolled situation and potential degradation in the level of safety of the plant. The Offsite Dose Calculation Manual (ODCM) contains the site specific release limits and appropriate surveillance requirements which normally monitor these limits. Table 4.1-U is based on 2 times the ODCM limit. The release should not be averaged over 60 minutes. For example, a release of 4 times ODCM limits for 30 minutes does not meet the requirements for this event classification. The 1 hour time period allows sufficient time to isolate any release after exceeding ODCM limits. Release continuing for more than 1 hour represents inability to isolate or control the release. The Site Emergency Director should declare the event as soon as it is determined that the release duration has or will likely exceed 1 hour. The value of 0.10 mrem/hr at the site boundary is based on a proration of twice the 500 mrem/yr ODCM instantaneous release rate limit. Utilize Radiological Control for obtaining site boundary assessments. Escalation to Alert is based on radiation release rate which exceeds 200 times the ODCM limit. REFERENCES - Reg Guide 1.101 Rev. 3, (NUMARC-AU1 example-I)

                    -   RIMS L63 950502 800
                    -    10CFR20 4.0 RADIOACTIVITY                    PAGE 127 OF 207 RELEASE                                                                         REVISION 28B

EMERGENCY EPIP-1 SECTION III 4.0 RADIOACTIVITY CLASSIFICATION DD/qflC1 IDTPI* TECHNICAL BASIS RELEASE GASEOSEFFUEN 4.1-UL~ UNUSUAL EVENT (CONTINUED) CURVES/TABLES Table 4.1-U ___________RELEASE LIMITS FOR UNUSUAL EVENT TYPE MONITORING METHOD LIMIT DURATION STACK NOBLE GAS (WRGERMS) 2.88 X 10' 7Cisec 1 HOUR GASEOUS RELEASE RATE SI 4.8.B.I.a.1 RELEASE FRACTION 2.0 1 HOUR GASEOUS RELEASE RATE SITE BOUNDARY RADIATION READING FIELD ASSESSMENT TEAM 0.10 MREM.HR - 1 HOUR NOTES NOTE 4.1-U Prior to making this emergency classification based upon the WRGERMS indication, assess the release by either of the following:

1. Actual field measurements exceed the limits in Table 4.1-A

2. SI 4.8.B.1.a.1 Release Fraction 2.0 If neither assessment can be conducted within 60 minutes then the declaration must be made on the valid WRGERMS reading.

4.0 RADIOACTIVITY PAGE 128 OF 207 RELEASE REVISION 28B

EMERGENCY EPIP-1 CLASSIFICATION SECTION III 4.0 RADIOACTIVTY TQ9flNT"AT. RA I-- RELEASE EFLUEN GASEOS 4.1A ALERT Gaseous release exceeds ANY limit and duration in Table 4.1-A. OPERATING - All CONDITION BASIS This event escalates from Unusual Event by increasing the magnitude of the release by a factor of 100. The release limit is equivalent to 200 times the Offsite Dose Calculation Manual (ODCM) limit. The value of 10 mrem/hr at the site boundary is based on a proration of the 500 mrem/yr criteria for both time (8766 hr/yr) and the 200 multiplier. The required release duration is reduced to 15 minutes in recognition of the increased severity. Table 4.1-A contains the Alert limits and appropriate monitoring points for the releases. Utilize Radiological Control for obtaining site boundary assessments. Escalation to Site Area Emergency is based on radiation release which will yield a dose to a member of the public which exceeds IOCFR20 limits. REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-AA1 example-l) RIMS L63 950502 800 10CFR20 EPA 400 4.0 RADIOACTIVITY PAGE 129 OF 207 REVISION 28B RELEASE

EMERGENCY EPIP-1 SECTION III 4.0 RADIOACTIVITY CLASSIFICATION TECHNICAL BASIS RELEASE

        -                     fiIiKACIE IM                    R IDEA                        W ALERT (CONTINUED)

CURVES/TABLES Table 4. 1-A RELEASE lMIiTS FOR ALERT TYPE MONITORING METHOD LIMIT DURATION 9 GASEOUS RELEASE RATE STACK NOBLE GAS (WRGERMS) 2.88 X 10 iCi/sec 15 MINUTES GASEOUS RELEASE RATE SI 4.8.B.1.a.1 RELEASE FRACTION 200 15 MINUTES SITE BOUNDARY RADIATION READING FIELD ASSESSMENT TEAM 10 MREM!HR y- 15 MINUTES NOTES NOTE 4.1-A Prior to making this emergency classification based upon the WRGERMS indication, assess the release by either of the following:

1. Actual field measurements exceed the limits in Table 4.1-A

2. SI 4.8.B. L.a. 1 Release Fraction 200 If neither assessment can be conducted within 15 minutes then the declaration must be made on the valid WRGERMS reading.

4.0 RADIOACTIVITY PAGE 130 OF 207 RELEASE REVISION 28B

EMERGENCY EPIP-1 CLASSIFICATION SECTION I1 4.0 RADIOACTIVITY TECHNICAL BASIS RELEASE PROCEDURE SITE AREA EMERGENCY EITHER of the following conditions exists:

Gaseous release exceeds or is expected to exceed ANY limit and duration in Table 4.1-S.
Dose assessment indicates actual or projected dose consequences above 100 mrem TEDE or 500 mrem thyroid CDE OPERATING - All CONDITION BASIS The limits in this event classification are based on 10 percent of the EPA Protective Action Guidelines or the 10CFR20 dose limit for a member of the public. These limits also provide a desirable gradient between Alert, Site Area Emergency, and General Emergency.

Table 4.1-S limits for stack and field surveys measurements are consistent with 10 percent of the EPA Protective Action Guidelines or the I OCFR20 dose limit for a member of the public. Stack Noble Gas Release Rates of 1.3 X 1010 [aCi/sec for 60 minutes, site boundary radiation readings of 100 mrem/hr for 1 hour, and 3 Iodine-131 concentration of 3.9 X 10- lgCi/cm for 1 hour are indicative of dose 7 consequences consistent with the limits described previously. The durations in Table 4.1-S are consistent with NUMARC recommendations and industry standards. If analyses indicated a longer or shorter duration for this period in which the substantial portion of the activity is released these dose rates should be adjusted. Utilize Radiological Control for obtaining site boundary. Dose projection assessments should be requested through the CECC by the implementation of CECC EPIP-8, if the CECC is not staffed utilize site Radiological Control for dose projection assessments through the implementation of BFN EPIP-14. 4.0 RADIOACTIVITY PAGE 131 OF 207 l REVISION 28B RELEASE

EMERGENCY EPIP-1 SECTION III 4.0 RADIOACTIVITY CLASSIFICATION TrtK'ITWirAT RA 1I0 RELEASE PROCED URKE ,u*....

        -                 GASEOUS EFFLNWUENTI                                       4.

SITE AREA EMERGENCY (CONTINUED) The 500 mrem thyroid CDE limit was established in consideration of the 1 to 5 ratio of the EPA Protective Action Guidelines for TEDE and thyroid CDE. Escalation to General Emergency is based on actual or projected dose exceeding 1000 mrem TEDE or 5000 mrem thyroid CDE. REFERENCES - Reg Guide 1.101 Rev. 3, (NUMARC-AS1 example-i)

                   -     RIMS L63 950502 800
                   -     10CFR20 EPA 400 CURVES/TABLES I

NOTES NOTE 4.1-S Prior to making this emergency classification based upon the Gaseous Release Rate indication, assess the release by either of the following methods:

1. Actual field measurements exceed the limits in Table 4.1-S.

2. Projected or Actual Dose Assessments exceed 100 mrem TEDE or 500 mrem CDE.

If neither assessment can be conducted within 15 minutes then the declaration must be made based on the valid WRGERMS reading. 4.0 RADIOACTIVITY PAGE 132 OF 207 REVISION 28B RELEASE

EMERGENCY EPIP-1 SECTION LII 4.0 RADIOACTIVITY CLASSIFICATION RELEASE Pnrv flh1R. TECHNICAL BASIS GASEO ih1'US EFLUN ~ N 4.1-GiRh GENERAL EMERGENCY EITHER of the following conditions exists:

              "* Gaseous release exceeds or is expected to exceed ANY limit and duration in Table 4.1-G.
              "* Dose assessment indicates actual or projected dose consequences above 1000 mrem TEDE or 5000 mrem thyroid CDE OPERATING         -     All CONDITION BASIS       The limits in this event classification are based on the EPA Protective Action Guidelines which require public protective actions if dose consequences of 1000 mrem TEDE or 5000 mrem thyroid CDE are indicated. These limits also provide a desirable gradient between Alert, Site Area Emergency, and General Emergency and represent the upper level of the gradient.

Table 4.1 -G limits for stack and field surveys measurements are consistent with the EPA Protective Action Guidelines for dose limits requiring public protective actions. Stack Noble Gas Release Rates of 1.3 X 101" pCi/sec for 60 minutes, site boundary radiation readings of 1000 mrem/hr for 1 hour, and Iodine-131 concentration of 3.9 X 10-6 [tCi/cm3 for 1 hour are indicative of dose consequences consistent with the limits described previously. The durations in Table 4. 1-G are consistent with NUTMARC recommendations and industry standards. If analyses indicated a longer or shorter duration for this period in which the substantial portion of the activity is released these dose rates should be adjusted. Utilize Radiological Control for obtaining site boundary assessments. Dose projection assessments should be requested through the CECC by the implementation of CECC EPIP-8, if the CECC is not staffed utilize site Radiological Control for dose projection assessments through the implementation of BFN EPIP- 14. The 5000 mrem thyroid CDE limit was established in consideration of the 1 to 5 ratio of the EPA Protective Action Guidelines for TEDE and thyroid CDE. Actual meteorology is used in dose assessment calculations to achieve the most accurate dose assessment possible. 4.0 RADIOACTIVITY PAGE 133 OF 207 89 RELEASE REVISION 28

EMERGENCY EPIP-1 SECTION III 4.0 RADIOACTIVITY CLASSIFICATION TWIvF-NTCAI. RAss RELEASE 0 W ku ~LA v Ud GENERAL EMERGENCY (CONTINUED) REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-asl example-i) RIMS L63 950502 800 10CFR20 CURVES/TABLES NOTES NOTE 4.1-G Prior to making this emergency classification based upon the Gaseous Release Rate indication, assess the release by either of the following methods:

1. Actual field measurements exceed the limits in Table 4.1 -G.

2. Projected or Actual Dose Assessmnets exceed 1000 mrem TEDE or 5000 mrem CDE.

If neither assessment can be conducted within 15 minutes then the declaration must be made based on the valid WRGERMS reading. 4.0 RADIOACTIVITY PAGE 134 OF 207 REVISION 28B RELEASE

EMERGENCY EPIP-1 CLASSIFICATION SECTION III 4.0 RADIOACTIVITY TECHNICAL BASIS RELEASE PROCEDURE MAIN STEAM LINE BREAK 4.2-U UNUSUAL EVENT Main Steam Line break outside Primary Containment with isolation. OPERATING Mode 1 CONDITION Mode 2 Mode 3 BASIS This event classification is intended to address the puff release associated with a Main Steam Line break outside Primary that isolates by PCIS Logic as required or can be isolated from the Main Control Room. Regardlessly of whether the break is in the Turbine Building or the Reactor Building a ground level release should be anpicipated due to the blowout panels between the two buildings. Design basis analysis shows that even if MSIV closure occurs within design limits, dose consequences from a "puff' release should be expected. Thus this event classification is included due to the posibility of offsite exposures from the "puff' release. This event is detected by instrumentation which inputs to the PCIS Logic circuitry. Main Steam Line high flow, Reactor low pressure with the mode switch in "Run", And Turbine Building Main Steam Space high temperature are all symptoms of the event and should be evaluated to determine if an actual break has occurred. Escalation to Area is based on radiation release rate event classifications. REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-FU) 4.0 RADIOACTIVITY PAGE 135 OF 207 RELEASE REVISION 28B

EMERGENCY EPIP-1 SECTION III 4.0 RADIOACTIVITY CLASSIFICATION D C1*.1*1fTR 1i TECHNICAL BASIS RELEASE Elm MAIN STEAM LINE BREAK 4.2-S SITE AREA EMERGENCY Unisolable Main Steam Line break outside Primary Containment. OPERATING - Mode 1 CONDITION - Mode 2

                       -      Mode 3 BASIS              This event classification applies to Main Steam Line Break that cannot be isolated by PCIS Logic or from the Main Control Room. Regardless of whether the break is in the Turbine Building or the Reactor Building a ground level release is expected due to the blowout panels between the two buildings. This event classification represents a loss of two of the three fission product barriers.

Main Steam Line high flow, Reactor low pressure with the mode switch in "Run", and Turbine Building Main Steam Space high temperature are all symptoms of the event. This event is anticipatory to 4.1-S and the threshold for leakage outside Primary and Secondary Containment should be considered to be any continuous discharge of steam through the break that, in the opinion of the Site Emergency Director, could result in exceeding the limits outlined in 4.1-S. Escalation to General Emergency is based on loss of the Fuel Clad barrier or radioactivity release event classifications. REFERENCES - Reg Guide 1.101 Rev. 3, (NUMARC-FS) 4.0 RADIOACTIVITY PAGE 136 OF 207 RELEASE REVISION 28B

EMERGENCY EPLP-1 SECTION I1I 4.0 RADIOACTIVITY CLASSIFICATION TECHNICAL BASIS RELEASE PROCEDURE UNUSUAL EVENT Liquid release rate exceeding 20 times ECL as determined by chemistry sample AND Release duration exceeds or will exceed 60 minutes. OPERATING - All CONDITION BASIS Liquid release rates are determined using Surveillance Instructions which utilize liquid samples rather than instrument readings for activity determination. Effluent Concentration Limits (ECL) are those annual concentrations given in 10CFR20 Appendix B, Table 2, Column 2. 10 times ECL is equivalent to the instantaneous ODCM limit. Unplanned radioactivity releases that exceed 20 times ECL (2 times ODCM limit) and continue for 60 minutes or longer represent an uncontrolled situation and potential degradation in the level of safety of the plant. The release should not be averaged over 60 minutes. For example, a release of 40 times ECL for 30 minutes does not meet the requirements of this event classification. The 60 minute time period allows sufficient time to isolate any release after exceeding ECL. Greater than 60 minutes represents inability to isolate or control the release. The Site Emergency Director should declare the event as soon as it is determined that the release duration has or will likely exceed 60 minutes. The Chemistry Department determines the magnitude of the release by sample procedure for any release as required by initiating procedures (i.e., SI, ARP, AO, EOI). The sample results are reported to the Site Emergency Director as a fraction or multiple of ECL. Escalation to Alert is based on release in excess of 2000 times ECL for greater than 15 minutes. REFERENCES - Reg Guide 1.101 Rev. 3, (NUMARC-AU1 example-2)

                     -    RIMS L63 950502 800
                     -    10CFR20 4.0 RADIOACTIVITY                   PAGE 137 OF 207 REVISION 28B RELEASE

EMERGENCY EPIP-1 CLASSIFICATION SECTION II1 4.0 RADIOACTIVITY 1DDnrr"V*IIR7F TECHNICAL BASIS RELEASE L[IQUIDUEFFLU~EN4.- 7 ALERT Liquid release rate exceeding 2000 times ECL as determined by chemistry sample AND Release duration exceeds or will exceed 15 minutes. OPERATING All CONDITION BASIS This event escalates from Unusual Event by increasing the magnitude of the release by a factor of 100. The required release duration is reduced to 15 minutes in recognition of the increased severity. The Chemistry Department determines the magnitude of the release by sample procedure for any release as required by initiating procedures (e.g., SI, ARP, AOI, EOL). The sample results are reported to the Site Emergency Director as a fraction or multiple of ECL. 10 times ECL is equal to the ODCM limit; therefore, 200 times the ODCM limit is equivalent to 2000 times ECL. Escalation to Site Area Emergency is based on event classifications indicative of Containment failure of the Reactor Coolant System pressure boundary and Primary barrier. REFERENCI -S Reg Guide 1.101 Rev. 3, (NUMARC-AA1 example-2)

                     -     RIMS L63 950502 800 4.0 RADIOAC] mrIVITY PAGE 138 OF 207 RELEASE                                                                       REVISION 28B

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP- 2 NOTIFICATION OF UNUSUAL EVENT REVISION 21A T.W. CORNELIUS PHONE: 2038 PREPARED BY: RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS DATE: 03-08-2000 APPROVED BY: TIM CORNELIUS EFFECTIVE DATE: 03-09-2000 LEVEL OF USE: REFERENCE USE VALIDATION DATE: NOT REQUIRED QUALITY-RELATED

REVISION LOG Procedure Number: EPIP-2 Revision Number: 21A Pages Affected:5,7,9,i0 Description of Change: EC-25 This change is being conducted to human factor the Revision Log, Description of Change and added clarification to revision log effecting rev. 21. EPIP 2 was revised primarily as a part of the site standardization process. EPIP 2 (rev. log) wvas changed to reflect the current revision level. Page 5, was revised to add the follow up notification form into the body of the instruction. Page 7, adds the follow-up notification attachment to the procedure attachment listing. Page 9, was revised to update Nuclear Security telephone extension number. Page 10, was revised to add the follow up notification form.

NOTIFICATION OF BROWNS FERRY UNUSUAL EVENT EPIP-2 NUCLEAR PLANT 1.0 PURPOSE 1.1 Provide for timely notification of appropriate individuals or organizations when the Shift Manager has determined by EPIP- 1 that an incident has occurred which is classified as a NOTIFICATION OF UNUSUAL EVENT. 1.2 Provide for periodic analysis of the current situation by the Shift Manger/Site Emergency Director (SED) to determine whether the NOTIFICATION OF UNUSUAL EVENT should be terminated, continued, or upgraded to a more serious classification. 2.0 SCOPE This procedure applies to emergency events that are classified as a Notification of Unusual Event by EPIP-1, Emergency Classification Procedure. PAGE I OF 10 REVISION 21A

NOTIFICATION OF BROWNS FERRY UNUSUAL EVENT EPIP-2 NUCLEAR PLANT 3.0 INSTRUCTIONS 3.1 Notification of the Operations Duty Specialist (ODS) Note: The ODS should be notified within 5 minutes after the emergency event is declared. Date: / / 3.1.1 Complete Attachment A (Notification Information). INITIALS T, E 3.1.2 Notify the ODS and Provide the information from Attachment A. INITIALS T"1"En Note: Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct. ODS Telephone Numbers 5-751-1700 5-751-2495 If the ODS cannot be reached within 10 minutes, Then contact the State of Alabama directly by requesting the Rad Health Duty Officer at: Day Shift 8 a.m. - 5 p.m. 9-1-334-206-5391 Holidays-Weekends-Offshifts 9-1-334-242-4378 3.1.3 Fax a copy of Attachment A to the ODS for confirmation INITIALS TIME of information or state if contacted directly). ODS Fax AL Rad Health 5-751-8620 9-1-334-206-5387 3.1.4 Receive confirmation call from the ODS (to verify notification of the State of Alabama) (NA this step if the State was contacted INITIALS TTME directly). PAGE 2 OF 10 REVISION 21A

BROWNS FERRY NUCLEAR PLANT NOTIFICATION OF UNUSUAL EVENT EPIP-2 3.0 INSTRUCTIONS (CONTINUED) 3.2 NOTIFICATION OF SITE PERSONNEL 3.2.1 Provide the Unit 1, Unit Operator with a completed INrITALS TIME copy of Attachment A. 3.2.2 Direct the Unit 1, Unit Operator to make notifications INrITALS TIME from Attachment B ( Unit 1, Unit Operator Notification), utilizing information from Attachment A. 3.2.3 Make the following plant P.A. announcement: INIrIALS TIME THIS IS (NAME), SHIFT MANAGER. A NOTIFICATION OF UNUSUAL EVENT HAS BEEN DECLARED ON UNIT . I HAVE ASSUMED THE DUTIES OF SITE EMERGENCY DIRECTOR. 3.2.4 Notify the Plant Manager or alternate. INMALS TIME 3.3 OFFSITE DOSE ASSESSMENT 3.3.1 Evaluate the need for offsite dose assessment. INITIALS TIME (N/A STEP IF NOT APPLICABLE) 3.3.1.1 When offsite dose assessment is required obtain the information from the CECC when operational. 3.3.1.2 If the CECC is not operational, contact the TSC, when staffed or the RADCON Shift Supervisor and request the implementation of EPIP 14, for dose assessment. PAGE 3 OF 10 REVISION 21A

NOTIFICATION OF BROWNS FERRY UNUSUAL EVENT EPIP-2 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUJED) 3.4 NOTIFICATION OF THE NRC 3.4.1 Notify the NRC immediately or within 1 hour and if requested by the NRC maintain an open and continuous INITIALST communications channel. Note: Utilize the Emergency Notification System (ENS) when making this notification. Dial the first number listed on the sticker affixed to the ENS telephone, using all 10 digits. If the number is busy, Then select in order, the alternate numbers until a connection is achieved. Note: If the ENS phones are out-of-service, Then dial direct utilizing the TVA phone system by dialing 9-1-the number listed on the ENS telephones. No access codes are required. PAGE 4 OF 10 REVISION 21A

NOTIFICATION OF BROWNS FERRY UNUSUAL EVENT -2 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.5 PERIODIC EVALUATION OF THE EVENT 3.5.1 Continue to Evaluate the event by using EPIP-1 as conditions warrant. 3.5.2 If other EAL conditions exist indicating the current emergency classification or significant changes in plant conditions have occurred since the last update to the ODS, and the CECC is not staffed, Then, Complete the "Follow-Up" Notification Form (Attachment C), notify the ODS and provide the new information. Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct. ODS 751-2495, 1700 Note If the ODS cannot be reached, Then contact the State of Alabama directly by requesting the Rad Health Duty Officer at: Day Shift 8 a.m. - 5 p.m. 9-1-334-206-5391 Holidays-Weekends-Offshifts 9-1-334-242-4378 3.5.3 If the conditions warrants upgrading to a higher classifications, Then initiate the appropriate EPIP. 3.5.4 If the conditions warrant termination of the classification, Then enter the Termination section of this procedure at step 3.6. 3.5.5 Re-enter this procedural section as conditions warrant at step 3.5.1 or until directed to exit this procedure by steps 3.5.3 or 3.5.4. PAGE 5 OF 10 REVISION 21A

NOTIFICATION OF BROWNS FERRY UNUSUAL EVENT EPIP-2 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.6 TERMINATION OF THE EVENT If the situation no longer exists terminate the event and notify the following: Date: 3.6.1 Notify the ODS of the termination of the emergency or INITL4.LS TLnaE the state directly if the ODS cannot be contacted. 3.6.2 Notify the NRC of the termination of the emergency. TIME INITIALS 3.6.3 Notify the Plant Manager or Alternate of the termination of the emergency. LNTrIALS TLmE 3.6.4 Complete Attachment A by providing the time and date of termination. LNITLA.LS "IIME 3.6.4 Notify the Unit 1, Unit Operator. Provide the Unit 1, Unit Operator with the termination time and date and INITIALS TIME direct the Unit 1, Unit Operator to notify the individuals contacted on Attachment B of the terminatior of the emergency. PAGE 6 OF 10 REVISION 21A

BROWNS FERRY NOTIFICATION OF UNUSUAL EVENT EPIP-2 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.7 CLOSURE OF THE NOTIFICATION OF UNUSUAL EVENT 3.7.1 Upon termination of the Notification of Unusual Event, INITIALS TIME the Shift Manager shall send the completed EPIP-2 and all attachments to Emergency Preparedness (EP). 3.7.2 EP shall forward to the PORC Secretary the completed EPIP and all attachments for review by PORC. INITIALS TIME 3.7.3 PORC Review Completed.

PORC Chairman DATE [NRC/C85/28]. 3.7.4 After PORC review is completed the PORC secretary shall forward the signed EPIP-2 with all attachments to EP for documentation storage. INITIALS TIME 4.0 ATTACHMENTS Attachment A - Notification Information Attachment B - Unit 1, Unit Operator Notification Attachment C - Follow Up Information Form PAGE 7 OF 10 REVISION 21A

NOTIFICATION OF BROWNS FERRY UNUSUAL EVENT EPIP-2 NUCLEAR PLANT ATTACHMENT A (Page 1 of 1) NOTIFICATION INFORMATION

-] THIS IS A REAL EVENT                     F]-  THIS IS A DRILL This is                                                      at Browns Ferry.

Name There has been a NOTIFICATION OF UNUSUAL EVENT declared at Browns Ferry affecting: F-- Unit 1 F] Unit 2 F]- Unit 3 E] Common EAL Designator: Brief Description of the Event: Plant Conditions: F] Stable L-- Deteriorating Radiological Conditions: F- No Abnormal Releases Offsite F]- Airborne Release Offsite F]- Liquid Release Offsite Fl- Release Information Not Known Event Declared: Time: Date: Event Terminated: Time: Date: K]- There is no Protective Action Recommendation at this time. Please repeat the information you have received to ensure accuracy. REVISION 21A OF 10 PAGE 88 OF 10 REVISION 21 A

NOTIFICATION OF BROWNS FERRY UNUSUAL EVENT EPIP-2 NUCLEAR PLANT ATTACHMENT B (Page 1 of 1) UNIT 1, UNIT OPERATOR NOTIFICATIONS Date: / / Note: All notifications should be made utilizing the information located on EPIP 2, Attachment A Received a completed copy of EPIP 2, Attachment A from the INITIALS TiME Site Emergency Director. Personnel Notifications Initial Notifications Termination Notifications PersonnelNotifications Notify the Operations Manager Time Initials Time Initials (from the weekly duty list) Notify the Vice President Initials Time Initials Time (from the weekly duty list) Notify the REP manager Initials Time Initials Time (from the weekly duty list) [NRC/C] Notify the Emergency Initials Time Initials Time Public Information Officer (from the weekly duty list) Notify the Nuclear Security Shift Supervisor. Time Initials Time Initials Ext. 3150 or 2219 Notify the NRC Resident Ext. 2573, or 2572 or from the weekly Initials Time Initials Time duty list. This is a Quality Assurance record with a retention of five years. PAGE 9 OF 10 REVISION 21A

NOTIFICATION OF BROWNS FERRY UNUSUAL EVENT EPIP-2 NUCLEAR PLANT ATTACHMENT C (Page 1 of 1) FOLLOW-UP INFORMATION FORM Notification of Unusual Event F-- THIS IS A REAL EVENT F-- THIS IS A DRILL This is at Browns Ferry. Name There has been a NOTIFICATION OF UNUSUAL EVENT declared at Browns Ferry affecting:

-] Unit 1              F-- Unit 2             -- Unit 3            FZ Common The Reactor is F-- Shutdown           F-- At Power Plant Conditions are F-- Stable       F-- Deteriorating "Follow-Up" Information (e.g., Key Events, Status Changes)

Current Radiological Conditions are: F-- No Abnormal Releases Offsite D- Airborne Release Offsite FD Liquid Release Offsite F] Release Information Not Known Additional Rad information: (e.g., release duration) FD There is no Protective Action Recommendation at this time. Please repeat the information you have received to ensure accuracy. The time for this follow up is: Time: Date: SIGNATURE: LAST PAGE PAGE 10 OF 10 REVISION 21A

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-3 ALERT REVISION 24A PREPARED BY: TIM CORNELIUS PHONE: 2038 RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS DATE: 03/08/2000 APPROVED BY: TIM CORNELIUS EFFECTIVE DATE: 03/09/2000 LEVEL OF USE: REFERENCE USE VALIDATION DATE: NOT REQUIRED QUALITY-RELATED

REVISION LOG Procedure Number: EPIP-3 Revision Number: 24A Pages Affected: 2,4,5,6,8,10 Description of Change: EC-28 This change is being conducted to human factor the Revision Log, Description of Change and added clarification to revision log effecting rev. 24. EPIP 3 was revised primarily as a part of the site standardization process and to improve general procedure progression. EPIP 3 (rev. log) was changed to reflect the current revision level. Page 2 and 4, was revised to modify and move the logic step regarding center notifications (due to this change procedure step numbers were revised without revision indications). Page 5, was revised to add the follow up form information into the body of the instruction. Page 6, adds the follow up notification form attachment to the procedure attachment listing. Page 8, was revised to update Nuclear Security telephone extension number. Page 10. was revised to add the follow up notification form.

ALERT BROWNS FERRY EPIP-3NUCLEARPLANT 1.0 PURPOSE 1.1 Provide for timely notification of appropriate individuals or organizations when the Shift Manager/Site Emergency Director (SED) has determined by EPIP-1 that an incident has occurred which is classified as an ALERT. 1.2 Provide for periodic evaluation of the current situation by the Shift Manager/SED to determine whether the ALERT should be terminated, continued, or upgraded to a more serious classification. 2.0 SCOPE This procedure applies to emergency events that are classified as Alert by EPIP-1, Emergency Classification Procedure. PAGE 1 OF 10 REVISION 24A

ALERT BROWNS FERRY EPIP-3 NUCLEAR PLANT 3.0 INSTRUCTIONS Date: / / 3.1 If all Emergency Centers ARE STAFFED, Then notify the following that an ALERT Emergency Classification has been issued and EPIP 3 is being implemented, and continue in this procedure at Step 3.4. If all Emergency Centers ARE NOT STAFFED, Then N/A this step and continue in this procedure. CECC FJ Control Rooms LI1 INITIALS TIME TSC F] Plant PA Announcement E OSC El This is NAME. Site Emergency Director, an Alert has been declared at BFN. we are currently implementing EPIP-3. Standby for fitrther updates. 3.2 Notification of the Operations Duty Specialist (ODS) & Emergency Responders Note, The ODS should be notified within 5 minutes after the emergency event is declared. 3.2.1 Complete Attachment A (Notification Information). INITLALS TrIE 3.2.2 Direct the Unit 1, Unit Operator to make notifications from Attachment B (Unit 1, Unit Operator Notification) INITIALS T"FIE 3.2.3 Notify the ODS and Provide the information from INTM-ALS "FnmI Attachment A. Note: Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct. ODS Telephone Numbers 751-1700,or 2495 If the ODS cannot be reached within 10 minutes, Then contact the State of Alabama directly by requesting the Rad Health Duty Officer at: Day Shift 8 a.m. - 5 p.m. - Holidays-Weekends-Offshifts 9-1-334-206-5391 9-1-334-242-4378 3.2.4 Fax a copy of Attachment A to the ODS for confirmation of information or state if the state was contacted directly. INITLLS TmE ODS Fax AL Rad Health Fax 5-751-8620 9-1-334-206-5387 3.2.5 Receive confirmation call from the ODS (to verify notification of the State of Alabama)(NA this step, if the INITLALS TI'E state was contacted directly). PAGE 2 OF 10 REVISION 24A

BROWNS FERRY ALERT EPIP-3 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.3 NOTIFICATION OF SITE PERSONNEL 3.3.1 Make the following plant P.A. announcement: lITIALS TIME THIS IS (NAME), SHIFT MANAGER. An ALERT HAS BEEN DECLARED ON UNIT __. I HAVE ASSUMED THE DUTIES OF SITE EMERGENCY DIRECTOR. REPORT TO YOUR ASSIGNED EMERGENCY RESPONSE FACILITY AT THIS TIME! 3.4 ACCOUNTABILITY CAUTION: Do not initiate an Accountability if the Alert is due to a Tornado or other severe weather condition. 3.4.1 If the emergency situation warrants an Accountability, INITIALS TIME activate the Accountability Alarm. (Reference EPIP-8) (N/A STEP IF NOT APPLICABLE) Note: If the emergency situation does not warrant an Accountability at this time, continue to assess the situation and activate the Accountability Alarm when necessary. 3.5 OFFSITE DOSE ASSESSMENT 3.5.1 Evaluate the need for offsite dose assessment. INITALS TIME (N/A STEP IF NOT APPLICABLE) 3.5.1.1 When offsite dose assessment is required obtain the information from the CECC when operational. 3.5.1.2 If the CECC is not operational, contact the TSC, when staffed or the RADCON Shift Supervisor and request the implementation of EPIP 14, for dose assessment. PAGE 3 OF 10 REVISION 24A

ALERT BROWNS FERRY EPIP-3 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.6 NOTIFICATION OF THE NRC 3.6.1 Notify the NRC immediately or within 1 hour and if requested by the NRC maintain an open and continuous INITIALS TmIE communications channel. Note: Utilize the Emergency Notification System (ENS) when making this notification. Dial the first number listed on the sticker affixed to the ENS telephone, using all 10 digits. If the number is busy, Then select in order, the alternate numbers until a connection is achieved. Note: If the ENS phones are out-of-service, Then dial direct utilizing the TVA phone system by dialing 9-1-the number listed on the ENS telephones. No access codes are required. PAGE 4 OF 10 REVISION 24A

ALERT FBROWNS FERRY EPIP-3 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.7 PERIODIC EVALUATION OF THE EVENT 3.7.1 Continue to Evaluate the event using EPIP-1 as conditions warrant. 3.7.2 If plant conditions warrant the need for follow up information, Complete the Follow Up Notification Form, Attachment C. Note: Conditions that warrant this evaluation are as a minimum when other EAL conditions exist indicating the current emergency classification or significant changes in plant conditions have occurred. 3.7.3 If the CECC is not staffed, Then notify the ODS and provide follow up information from the completed Attachment C form. Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct. ODS 751-2495, 1700 Note: If the ODS cannot be reached, Then contact the State of Alabama directly by requesting the Rad Health Duty Officer at: Day Shift 8 a.m. - 5 p.m. Holidays-Weekends-Offshifts 9-1-334-206-5391 9-1-334-242-4378 3.7.4 If the conditions warrant upgrading to a higher classification, Then initiate the appropriate EPIP. 3.7.5 If the conditions warrants termination of the classifications, Then enter EPIP- 16, Termination and Recovery Procedure. 3.7.6 After the evaluation has been completed, if staffed, Notify the following of the status:

               "* CECC

OSC

               "* NRC (ENS)

CONTROL ROOMS

               "* TSC

PLANT PA ANNOUNCEMENT 3.7.7 Re-enter this procedural section as conditions warrant at step 3.7.1 or until directed to exit this procedure by steps 3.7.4 or 3.7.5.

PAGE 5 OF 10 REVISION 24A

ALERT BROWNS FERRY EPIP-3 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.8 CLOSURE OF THE ALERT 3.8.1 Upon termination of the Alert, send the completed EPIP 3 and all attachments to Emergency Preparedness (EP). INITIALS TIME 3.8.2 EP shall forward to the PORC Secretary the completed EPIP and all attachments for review by PORC. INIT-ALS TIME 3.8.3 PORC Review Completed. PORC Chairman DATE [NRC/C85/28]. 3.8.4 After PORC review is completed the PORC secretary shall forward the signed EPIP-3 with all attachments to EP for documentation storage. INITIALS TIME 4.0 ATTACHMENTS Attachment A - Notification Information Attachment B - Unit 1, Unit Operator Notification Attachment C - Follow Up Information Form PAGE 6 OF 10 REVISION 24A

BROWNS FERRY ALERT EPIP-3 NUCLEAR PLANT ATTACHMENT A (Page 1 of 1) NOTIFICATION INFORMATION F-- THIS IS A REAL EVEN] F- THIS IS A DRELL This is at Browns Ferry. Name There has been a ALERT declared at Browns Ferry affecting:

 -- Unit 1             [-  Unit 2             [- Unit 3             E-  Common EAL Designator:

Brief Description of the Event: Plant Conditions:

        -- Stable       -- Deteriorating Radiological Conditions:

n- No Abnormal Releases Offsite

        -- Airborne Release Offsite
          -1 Liquid Release Offsite E- Release Information Not Known Event Declared:                Time:                         Date:

Event Terminated: Time: Date: F-- There is no Protective Action Recommendation at this time. Please repeat the information you have received to ensure accuracy. 10 REVISION 24A PAGE 7 OF 10 REVISION 24A

ALERT EPIP-3 BROWNS FERRY NUCLEAR PLANT ATTACH!MENT B (Page 1 of 2) Unit 1, Unit Operator NOTIFICATION Date: / /

1. Activate the Automatic Paging System (APS).

INrITALs TNIME Note: See Instructions in EPIP-6 Callout List (List will be maintained by the EP Manager) Important: If the APS does NOT activate, Call the ODS (5-751-1700 or 5-751-2495) to activate and noti4 the SED immediately.

2. Notify the Unit Supervisors on shift.

INITIALS TIm

3. Notify Nuclear Security Shift Supervisor and state "AN INITLALS TMEE ALERT HAS BEEN DECLARED" and direct to activate EPIP- 11, Security and Access Control.

0 Plant Extension 3150 or 2219

4. Notify the Chemistry Lab Supervisor and state "AN ALERT HAS BEEN DECLARED" and direct to activate LNITLALS Tnn EPIP- 13, Radiochemical Laboratory Procedure.

0 Plant Extension 2367 or 2368

5. Notify the RADCON Shift Supervisor and state "AN ALERT HAS BEEN DECLARED" and direct to activate EPIP-14, Radiological Control Procedure.

LNITLALS TIME

Plant Extension 2300 or 3104 PAGE 8 OF 10 REVISION 24A

BROWNS FERRY ALERT EPIP-3 NUCLEAR PLANT ATTACHMENT B (Page 2 of 2) Unit 1, Unit Operator NOTIFICATION Date: / /

6. Notify the "On-Call" NRC Resident and state "AN ALERT INIYTLUS TIEW HAS BEEN DECLARED," per BFN-EPIP-03.

Plant Extension 2572 [Secretary] or from weekly duty list

7. IF the APS did not operate properly, Make notifications from the current duty list. If the individuals on the duty INITIALS TuE list cannot be contacted, Make notifications from the EPIP-6 Call Out List. Notify the SED of the condition.

PAGE 9 OF 10 REVISION 24A

BROWNS FERRY ALERT EPIP-3 NUCLEAR PLANT ATTACHMENT C (Page 1 of 1) FOLLOW-UP INFORMATION FORM ALERT FI THIS IS A REAL EVENT FI- THIS IS A DRILL This is at Browns Ferry. Name There has been a Alert declared at Browns Ferry affecting: F-- Unit 1 -- Unit 2 F-- Unit 3 0I Common The Reactor is -] Shutdown F-- At Power Plant Conditions are -] Stable -7 Deteriorating "Follow-Up" Information (e.g., Key Events, Status Changes) Current Radiological Conditions are: F-- No Abnormal Releases Offsite LI Airborne Release Offsite F-- Liquid Release Offsite F-- Release Information Not Known Additional Rad information: (e.g., release duration) F1- There is no Protective Action Recommendation at this time. Please repeat the information you have received to ensure accuracy. The time for this follow up is: Time: Date: SIGNATURE: LAST PAGE PAGE 10 OF 10 REVISION 24A

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-4 SITE AREA EMERGENCY REVISION 23A PREPARED BY: TIM CORNELIUS PHONE: 2038 RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS DATE: 03/08/2000 APPROVED BY: TIM CORNELIUS EFFECTIVE DATE: 03/09/2000 LEVEL OF USE: REFERENCE USE VALIDATION DATE: NOT REQUIRED QUALITY-RELATED I-

REVISION LOG Procedure Number: EPIP-4 Revision Number: 23A Pages Affected: 2,4,3,5,7,9,11 Description of Change: EC-29 This change is being conducted to human factor the Revision Log, Description of Change and added clarification to revision log effecting rev. 23. EPIP 4 was revised primarily as a part of the site standardization process and to improve general procedure progression. EPIP 4 (rev. log) was changed to reflect the current revision level. Page 2 and 4. was revised to move and modify the logic step regarding center notifications. (due to this change, step numbers were revised without revision indications) Page 3. a note was formalized to ensure Nuclear Security is notified prior to sounding the evacuation alarms. Page 5. was revised to add the follow up form information into the body of the instruction. Page 7. adds the follow up notification form attachment to the procedure attachment listing. Page 9. was revised to update Nuclear Security telephone extension number. Page 11. -,as revised to add the follov up notification form.

SITE AREA BROWNS FERRY EMERGENCY EPIP-4 NUCLEAR PLANT 1.0 PURPOSE 1.1 Provide for timely notification of appropriate individuals or organizations when the Shift Manager/Site Emergency Director (SED) has determined by EPIP-1 that an incident has occurred which is classified as a SITE AREA EMERGENCY (SAE). 1.2 Provide for periodic evaluation of the current situation by the Shift Manager/SED to determine whether the SAE should be terminated, continued, or upgraded to a more serious classification. 2.0 SCOPE This procedure applies to emergency events that are classified as Site Area Emergency by EPIP-1, Emergency Classification Procedure. PAGE I OF 11 REVISION 23A

SITE AREA BROWNS FERRY EMERGENCY EPIP-4 NUCLEAR PLANT 3.0 INSTRUCTIONS Date: / / 3.1 If all Emergency Centers ARE STAFFED, Then notify the following that a SITE AREA EMERGENCY Emergency Classification has been issued and EPIP 4 is being implemented, and continue in this procedure at Step 3.4. If all Emergency Centers ARE NOT STAFFED, Then N/A this step and continue in this procedure. CECC D D Control Rooms 1NINTrL4LS TiMN-E TSC Plant PA Announcement OSC D This is NANIE. Site Emergency Director. an SAE has been declared at BFN. we are currently implementing EPIP-4. Standby for further updates. 3.2 Notification of the Operations Duty Specialist (ODS) & Emergency Responders Note: The ODS should be notified within 5 minutes after the emergency event is declared. 3.2.1 Complete Attachment A (Notification Information). INITLAS TIMF 3.2.2 Direct the Unit 1, Unit Operator to make notifications from Attachment B (Unit 1, Unit Operator Notification) INITLALS T'E 3.2.3 Notify the ODS and Provide the information from INITLULS TIME Attachment A. Note: Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct ODS Telephone Numbers 5-751-1700, 2495 If the ODS cannot be reached within 10 minutes, Then contact the State of Alabama directly by requesting the Rad Health Duty Officer at: Day Shift 8 a.m. - 5 p.m. - Holidays-Weekends-Offshifts 9-1-334-206-5391 9-1-334-242-4378 3.2.4 Fax a copy of Attachment A to the ODS for confirmation INITIALS TmIE of information or if the sate is contacted directly. ODS Fax AL Rad Health Fax 5-751-8620 9-1-334-206-5387 3.2.5 Receive confirmation call from the ODS (to verify notification of INITL-US TrInE the State of Alabama)(NA this step, if the state was contacted directly). PAGE 2 OF 11 REVISION 23A

SITE AREA BROWNS FERRY EMERGENCY EPIP-4 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.3 NOTIFICATION OF SITE PERSONNEL 3.3.1 Make the following plant P.A. announcement: INITIALS TIME THIS IS (NAME), SHIFT MANAGER. A SITE AREA EMERGENCY HAS BEEN DECLARED ON UNIT __ I HAVE ASSUMED THE DUTIES OF SITE EMERGENCY DIRECTOR. REPORT TO YOUR ASSIGNED EMERGENCY RESPONSE FACILITY AT THIS TIME! 3.4 ACCOUNTABILITY AND EVACUATION OF NON-EMERGENCY RESPONDERS 3.4.1 Prior to sounding the Evacuation Alarm, Notify Nuclear INITIALS TIaE Security. If the TSC is staffed notify the TSC Security Manager. If the TSC is not staffed or the TSC Security Manager position has not been filled then call 3150 or 2219. 3.4.2 Activate the Accountability Alarm, if not previously INITIALS TmIE sounded. (Reference EPIP-8) (N/A STEP IF NOT APPLICABLE) 3.4.3 When accountability is complete, Conduct evacuation of 1NIT*ALS TINE non-emergency responders by activating the Evacuation Alarm. PAGE 3 OF 11 REVISION 23A

SITE AREA BROWNS FERRY EMERGENCY EPIP-4 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.5 DOSE ASSESSMENT 3.5.1 Evaluate the need for offsite dose assessment. INITIA-Ls TniME (N/A STEP IF NOT APPLICABLE) 3.5.1.1 When offsite dose assessment is required obtain the information from the CECC when operational. 3.5.1.2 If the CECC is not operational, contact the TSC, when staffed or the RADCON Shift Supervisor and request the implementation of EPIP 14, for dose assessment. 3.6 NOTIFICATION OF THE NRC 3.6.1 Notify the NRC immediately or within 1 hour and if requested by the NRC maintain an open and continuous INITILS TLwE communications channel. Note: Utilize the Emergency Notification System (ENS) when making this notification. Dial the first number listed on the sticker affixed to the ENS telephone, using all 10 digits. If the number is busy, Then select in order, the alternate numbers until a connection is achieved. Note: If the ENS phones are out-of-service, Then dial direct utilizing the TVA phone system by dialing 9-1-the number listed on the ENS telephones. No access codes are required. PAGE 4 OF I11 REVISION 23A

SITE AREA 4 BROWNS FERRY EMERGENCY EPIP-4 NUCLEARPLANT 3.0 INSTRUCTIONS (CONTINUED) 3.7 PERIODIC EVALUATION OF THE EVENT 3.7.1 Continue to Evaluate the event using EPIP-1 as conditions warrant. 3.7.2 If plant conditions warrant the need for follow up information, Complete the Follow Up Notification Form, Attachment C. Note: Conditions that warrant this evaluation are as a minimum when other EAL conditions exist indicating the current emergency classification or significant changes in plant conditions have occurred. 3.7.3 If the CECC is not staffed, Then notify the ODS and provide follow up information from the completed Attachment C form. Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct. ODS 751-2495, 1700 Note: If the ODS cannot be reached, Then contact the State of Alabama directly by requesting the Rad Health Duty Officer at: Day Shift 8 a.m. - 5 p.m. Holidays-Weekends-Offshifts 9-1-334-206-5391 9-1-334-242-4378 3.7.4 If the conditions warrants upgrading to a higher classifications, Then initiate EPIP-5, General Emergency. 3.7.5 If the conditions warrant termination of the classification, Then enter EPIP-16, Termination and Recovery Procedure. PAGE 5 OF 11 REVISION 23A

SITE AREA BROWNS FERRY EMERGENCY EPIP-4 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.7 PERIODIC EVALUATION OF THE EVENT (CONTINUED) 3.7.6 After the evaluation has been completed, if staffed, Notify the following of the status:

             "* CECC                  "* OSC
             "* NRC (ENS)             "* CONTROL RooMs
             "* TSC                   "* PLANT PA ANNOUNCEMENT 3.7.7 Re-enter this procedural section as conditions warrant at step 3.7.1 or until directed to exit this procedure by steps 3.7.4 or 3.7.5.

3.8 CLOSURE OF THE SITE AREA EMERGENCY 3.8.1 Upon termination of the Site Area Emergency, Send the completed EPIP-4 and all attachments to Emergency INITLALS TInif Preparedness (EP). 3.8.2 EP shall Forward to the PORC Secretary the completed EPIP and all attachments for review by PORC. INITLALS [U*IE 3.8.3 PORC Review Completed.

PORC Chairman DATE [NRC/C85/28]. 3.8.4 After PORC review is completed the PORC secretary shall forward the signed EPIP-4 with all attachments to EP for documentation storage. INITLALS TaME PAGE60OF 11 REVISION 23A

SITE AREA BROWNS FERRY EMERGENCY EPIP-4 NUCLEAR PLANT 4.0 ATTACHMENTS Attachment A - Notification Information Attachment B - Unit 1, Unit Operator Notification Attachment C - Follow Up Information Form PAGE 7 OF I11 REVISION 23A

SITE AREA BROWNS FERRY EMERGENCY NUCLEAR PLANT ATTACHMENT A (Page 1 of 1) NOTIFICATION INFORMATION [- THIS IS A REAL EVENT -] THIS IS A DRILL This is at Browns Ferry. Name There has been a SITE AREA EMERGENCY declared at Browns Ferry affecting: F-- Unit 1 F-- Unit 2 F1- Unit 3 F-- Common EAL Designator: Brief Description of the Event: Plant Conditions: F-- Stable [- Deteriorating Radiological Conditions: F-- No Abnormal Releases Offsite D Airborne Release Offsite F-- Liquid Release Offsite F-- Release Information Not Known Event Declared: Time: Date: Event Terminated: Time: Date: F-- There is no Protective Action Recommendation at this time. The Meteorological conditions are: Wind Speed: Wind Direction From: Please repeat the information you have received to ensure accuracy. REVISION 23A OF 11 PAGE 88 OF I11 REVISION 23A

SITE AREA BROWNS FERRY EMERGENCY EPIP-4 NUCLEAR PLANT ATTACHMENT B (Page 1 of 2) Unit 1, Unit Operator NOTIFICATION Date:

1. Activate the Automatic Paging System (APS). INITIALS TIME Note: See Instructions in EPIP-6 Callout List (List will be maintained by the EP Manager)

Important: If the APS does NOT activate, Call the ODS (5-751-1700 or 5-751-2495) to activate and notify the SED immediately.

2. Notify the Unit Supervisors on shift. INrLALS TIME

3. Notify Nuclear Security Shift Supervisor and state "A SITE INITIALS TIME AREA EMERGENCY HAS BEEN DECLARED,"

and direct to activate EPIP- 11, Security and Access Control.

Plant Extension 3150 or 2219 INUTL4JS TIME

4. Notify the Chemistry Lab Supervisor and state "A SITE AREA EMERGENCY HAS BEEN DECLARED,"

and direct to activate EPIP- 13, Radiochemical Laboratory Procedure.

Plant Extension 2367 or 2368

5. Notify the RADCON Shift Supervisor and state "A SITE INITIALS TIME AREA EMERGENCY HAS BEEN DECLARED,"

and direct to activate EPIP- 14, Radiological Control Procedure. 0 Plant Extension 2300 or 3104 PAGE 9 OF 11 REVISION 23A

SITE AREA BROWNS FERRY EMERGENCY EPIP-4 NUCLEAR PLANT ATTACHMENT B (Page 2 of 2) Unit 1, Unit Operator NOTIFICATION Date: / /

6. Notify the "On-Call" NRC Resident and state "A SITE AREA EMERGENCY HAS BEEN DECLARED," INITLALS TIE per BFN-EPIP-04.

Plant Extension 2572 [Secretary] or from weekly duty list

7. IF the APS did not operate properly, Make notifications from the current duty list. If the individuals on the duty INITLALS TImE list cannot be contacted, Make notifications from the EPIP-6 Call Out List. Notify the SED of the condition.

PAGE 10 OF I R REVISION 23A

SITE AREA BROWNS FERRY EMERGENCY - NUCLEAR PLANT ATTACHMENT C (Page 1 of 1) FOLLOW-UP INFORMATION FORM Site Area Emergency F-1 THIS IS A REAL EVENT [- THIS IS A DRILL This is at Browns Ferry. Name There has been a Site Area Emergency declared at Browns Ferry affecting: F Unit 1 r-- Unit 2 L--Unit 3 El Common The Reactor is F1 Shutdown F- At Power Plant Conditions are E] Stable F-- Deteriorating "Follow-Up" Information (e.g., Key Events, Status Changes) Current Radiological Conditions are:

       -- No Abnormal Releases Offsite LI Airborne Release Offsite LI Liquid Release Offsite LI Release Information Not Known Additional Rad information: (e.g., release duration)

F-1 There is no Protective Action Recommendation at this time. Please repeat the information you have received to ensure accuracy. The time for this follow up is: Time: Date: SIGNATURE: LAST PAGE PAGE 11 OF 11 REVISION 23A

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-5 GENERAL EMERGENCY REVISION 28A PREPARED BY: TIM CORNELIUS PHONE: 3336 RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS DATE: 03/08/2000 APPROVED BY: TIM CORNELIUS EFFECTIVE DATE: 03/09/2000 LEVEL OF USE: REFERENCE USE VALIDATION DATE: NOT REQUIRED QUALITY-RELATED

REVISION LOG Procedure Number: EPIP-5 Revision Number: 28A Pages Affected: 2,3,5,6,7,9,12 Description of Change: EC-35 This change is being conducted to human factor the Revision Log., Description of Change and added clarification to revision log effecting rev. 28. EPIP 5 was revised primarily as a part of the site standardization process and to improve general procedure progression. EPIP 5. (rev. log) was changed to reflect the current revision level. Page 2, was revised to modify, the logic step regarding center notifications (due to this change, step numbers were revised without revision indications). Page 3. a note was formalized to ensure Nuclear Security is notified prior to sounding the evacuation alarms. Page 5, was revised to add the follow up form information into the body of the instruction. Page 7, adds the notification form attachment to the procedure attachment listing. Page 9. was revised to update Nuclear Security telephone extension number. Page 12, was revised to add the follow up notification form.

GENERAL BROWNS FERRY EMERGENCY Ir -5 NUCLEAR PLANT 1.0 PURPOSE 1.1 Provide for timely notification of appropriate individuals or organizations when the Shift Manager/Site Emergency Director (SED) has determined by EPIP-1 that an incident has occurred which is classified as a GENERAL EMERGENCY (GE). 1.2 Provide for periodic evaluation of the current situation by the Shift Manager/SED to determine whether the GE should be terminated, or continued. 2.0 SCOPE This procedure applies to emergency events that are classified as General Emergency by EPIP-1, Emergency Classification Procedure. PAGE 1 OF 12 REVISION 28A

GENERAL BROWNS FERRY EMERGENCY EPIP-5 NUCLEAR PLANT 3.0 INSTRUCTIONS Date: / / 3.1 If all Emergency Centers ARE STAFFED, Then notify the following that a GENERAL EMERGENCY Emergency Classification has been issued and EPIP 5 is being implemented, and continue in this procedure at Step 3.4. If all Emergency Centers ARE NOT STAFFED, Then N/A this step and continue in this procedure. CECC D Control Rooms F- INITIALS TIME TSC Plant PA Announcement 0 OSC D- This is NAME. Site Emergency Director. an GE has been declared at BFN. we are currently implementing EPIP-5. Standby for further updates. 3.2 Notification of the Operations Duty Specialist (ODS) & Emergency Responders Note. The ODS should be notified within 5 minutes after the emergency event is declared. 3.2.1 Complete Attachment A (Notification Information). INITIALS TmF, 3.2.2 Direct the Unit 1, Unit Operator to make notifications IN7ITLALS TIME from Attachment B (Unit 1, Unit Operator Notification) 3.2.3 Notify the ODS and Provide the information from INITLALS TiMtE Attachment A. Note: Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct. ODS Telephone Numbers 5-751-1700, 2495 If the ODS cannot be reached within 10 minutes, Then contact the following and Provide the information from Attachment A.

1. Limestone County: 9-232-0111 INITLUS TmIE

2. Morgan County: 9-1-256-353-2515 INITLALS TImE

3. Lawrence County: 9-1-256-974-7641 INITLALS TLXIE

4. Lauderdale County: 9-1-256-760-9117 INITLXLS TLME

5. State of Alabama Rad Health Duty Officer:

1NITALUS TimE Day Shift 8 a.m. - 5 p.m. 9-1-334-206-5391 Holidays-Weekends-Offshifts 9-1-334-242-4378 PAGE 2 OF 12 REVISION 28A

GENERAL BROWNS FERRY EMERGENCY EPIP-5 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.2.4 Fax a copy of Attachment A to the ODS for confirmation INMALS TIME of information or the state if contacted directly. ODS Fax AL Rad Health 5-751-8620 9-1-334-206-5387 3.2.5 Receive confirmation call from the ODS (to verify TIME INITL4LS notification of the State of Alabama), (N/A this step if the State was contacted directly). 3.3 NOTIFICATION OF SITE PERSONNEL 3.3.1 Make the following plant P.A. announcement: INITIALS TIME THIS IS (NAME), SHIFT MANAGER. A GENERAL EMERGENCY HAS BEEN DECLARED ON UNIT __ I HAVE ASSUMED THE DUTIES OF SITE EMERGENCY DIRECTOR. REPORT TO YOUR ASSIGNED EMERGENCY RESPONSE FACILITY AT THIS TIME! 3.4 ACCOUNTABILITY AND EVACUATION OF NON-EMERGENCY RESPONDERS 3.4.1 Prior to sounding the Evacuation Alarm, Notify Nuclear INITIALS TIME Security. If the TSC is staffed notify the TSC Security Manager. If the TSC is not staffed or the TSC Security Manager position has not been filled then call 3150 or 2219. 3.4.1 Activate the Accountability Alarm, if not previously INITIALS TIaE sounded. (Reference EPIP-8) (N/A STEP IF NOT APPLICABLE) 3.4.2 When accountability is complete, Conduct evacuation of TIME INMALS non-emergency responders by activating the Evacuation Alarm, if not previously sounded. (N/A STEP IF NOT APPLICABLE) PAGE 3 OF 12 REVISION 28A

GENERAL BROWNS FERRY EMERGENCY EPIP-5 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.5 DOSE ASSESSMENT 3.5.1 Evaluate the need for offsite dose assessment. INITI-LS TLME (N/A STEP IF NOT APPLICABLE) 3.5.1.1 When offsite dose assessment is required Obtain the information from the CECC when operational. 3.5.1.2 If the CECC is not operational, Contact the TSC, when staffed or the RADCON Shift Supervisor and Request the implementation of EPIP 14, for dose assessment. 3.6 NOTIFICATION OF THE NRC 3.6.1 Notify the NRC immediately or within 1 hour and if INITIALS TnIE requested by the NRC maintain an open and continuous communications channel. Note: Utilize the Emergency Notification System (ENS) when making this notification. Dial the first number listed on the sticker affixed to the ENS telephone, using all 10 digits If the number is busy, Then select in order, the alternate numbers until a connection is achieved. Note: If the ENS phones are out-of-service, Then dial direct utilizing the TVA phone system by dialing 9-1-the number listed on the ENS telephones. No access codes are required. PAGE 4 OF 12 REVISION 28A

BROWNS FERRY GENERAL EMERGENCY EPIP-5 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.7 PROTECTIVE ACTION RECOMMENDATION 3.7.1 If the CECC is not staffed, Then make a Protective INITIALS TIME Action Recommendation (PAR) using Attachment C. (This PAR shall be made only by the SED.) (N/A STEP IF NOT APPLICABLE) 3.8 PERIODIC EVALUATION OF THE EVENT 3.8.1 Continue to Evaluate the event using EPIP-1 as conditions warrant. 3.8.2 If plant conditions warrant the need for follow up information, Complete the Follow Up Notification Form, Attachment D. Note: Conditions that warrant this evaluation are as a minimum when other EAL conditions exist indicating the current emergency classification or significant changes in plant conditions have occurred. 3.8.3 If the CECC is not staffed, Then notify the ODS and provide follow up information from the completed Attachment D form. Utilize the direct ring-down ODS phone when making this notification or as applicable dial direct. ODS 751-2495, 1700 Note: If the ODS cannot be reached, Then contact the State of Alabama directly by requesting the Rad Health Duty Officer at: Day Shift 8 a.m. - 5 p.m. Holidays-Weekends-Offshifts 9-1-334-206-5391 9-1-334-242-4378 PAGE 5 OF 12 REVISION 28A

GENERAL BROWNS FERRY EMERGENCY EPIP-5 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.8 PERIODIC EVALUATION OF THE EVENT(CONTINUED) 3.8.4 If the conditions warrant termination of the classification, Then enter EPIP-16, Termination and Recovery Procedure. 3.8.5 After the evaluation has been completed, if staffed, Notify the following of the status:

             "* CECC                  "* OSC
             "* NRC(ENS)              "* CONTROL RooMis
             "* TSC                   "* PLANTPA ANNOLuNCEMENT 3.8.6 Re-enter this procedural section as conditions warrant at step 3.8.1 or until directed to exit this procedure by steps 3.8.4.

3.9 CLOSURE OF THE GENERAL EMERGENCY 3.9.1 Upon termination of the General Emergency Send the completed EPIP-5 and all attachments to Emergency INITIALS TME Preparedness (EP). 3.9.2 EP shall Forward to the PORC Secretary the completed EPIP and all attachments for review by PORC. INITIAIS 'FE 3.9.3 PORC Review Completed.

PORC Chairman DATE [NRC/C85/28]. 3.9.4 After PORC review is completed the PORC secretary shall Forward the signed EPIP-5 with all attachments to EP for documentation storage. INITIALS TIME PAGE 6 OF 12 REVISION 28A

GENERAL BROWNS FERRY EMERGENCY EPIP- NUCLEAR PLANT 4.0 ATTACHMENTS Attachment A - Notification Information Attachment B - Unit 1, Unit Operator Notification Attachment C - Protective Action Recommendations Attachment D - Follow Up Information Form PAGE 7 OF 12 REVISION 28A

GENERAL BROWNS FERRY EMERGENCY EPIP-5 NUCLEAR PLANT ATTACHMENT A (Page 1 of 1) NOTIFICATION INFORMATION E- THIS IS A REAL EVENT -- THIS IS A DRILL This is at Browns Ferry. Name There has been a GENERAL EMERGENCY declared at Browns Ferry affecting: F-1 Unit 1 [-- Unit 2 E-I Unit 3 -] Common EAL Designator: Brief Description of the Event: Plant Conditions: F- Stable [-] Deteriorating Radiological Conditions: F- No Abnormal Releases Offsite F1I Airborne Release Offsite

         -] Liquid Release Offsite
        -] Release Information Not Known Event Declared:                 Time:                        Date:

Event Terminated: Time: Date: The following Protective Action Recommendation (PAR) is provided (PAR Required for General Emergency). L--Recommendation 1 - Evacuate 2 mile radius and 10 miles downwind and shelter remainder of 10 mile EPZ. E1 Recommendation 2 - Evacuate 2 mile radius and 5 miles downwind and shelter remainder of 10 mile EPZ.

        -- Recommendation 3 - Evacuate 2 mile radius and shelter remainder of        10 mile EPZ.

F-- Recommendation 4 - Shelter 2 mile radius and shelter 5 miles downwind. The Meteorological Conditions are: Wind Speed: Wind Direction From: Please repeat the information you have received to ensure accuracy. REVISION 28A OF 12 PAGE 8 OF 12 REVISION 28A

BROWNS FERRY GENERAL EMERGENCY EPIP-5 NUCLEAR PLANT ATTACHMENT B (Page 1 of 2) Unit 1, Unit Operator NOTIFICATION Date:

1. Activate the Automatic Paging System (APS). INITIALS TIME Note: See Instructions in EPIP-6 Callout List (List will be maintained by the EP Manager)

Important: If the APS does NOT activate, Call the ODS (5-751-1700 or 5-751-2495) to activate and notify the SED immediately.

2. Notify the Unit Supervisor's on shift. INITIALS TIME

3. Notify Nuclear Security Shift Supervisor and state "A INITLULS TEVIE GENERAL EMERGENCY HAS BEEN DECLARED," and direct to activate EPIP-11, Security and Access Control.

                    &       Plant Extension 3150 or 2219 INITIALS      TIME

4. Notify the Chemistry Lab Supervisor and state "A GENERAL EMERGENCY HAS BEEN DECLARED," and direct to activate EPIP-13, Radiochemical Laboratory Procedure.

0 Plant Extension 2367 or 2368

5. Notify the RADCON Shift Supervisor and state "A INITIALS TnIEE GENERAL EMERGENCY HAS BEEN DECLARED," and direct to activate EPIP-14, Radiological Control Procedure.

Plant Extension 2300 or 3104 PAGE 9 OF 12 REVISION 28A

GENERAL BROWNS FERRY EMERGENCY EPIP-5 NUCLEAR PLANT ATTACHMENT B (Page 2 of 2) Unit 1, Unit Operator NOTIFICATION Date: / /

6. Notify the "On-Call" NRC Resident and state "A GENERAL EMERGENCY HAS BEEN INUTALS TIME DECLARED," per BFN-EPIP-05.

Plant Extension 2572 [Secretary] or from weekly duty list

7. IF the APS did not operate properly, Make notifications from the current duty list. If the individuals on the duty INITIALS TmE list cannot be contacted, Make notifications from the EPIP-6 Call Out List. Notify the SED of the condition.

PAGE 10 OF 12 REVISION 28A

GENERAL BROWNS FERRY EMERGENCY EPIP-5 NUCLEAR PLANT ATTACHMENT C (Page 1 of 1) PROTECTIVE ACTION RECOMMENDATIONS enrlEmergency Declared@ IF Conditions Are not known, Then Answer No. ( CONTINUE ASSESSMENT. Modify protective actions based on available plant and field monitoring infomation. Locate and evacuate additional localized hot spots. When Dose Assessment Projections OR Actual Measured Exposures are not known, a stack release rate of> 1.3 El1 uCi/sec noble gas can be utilized to meet the condition of 1 Rem/hr External Dose at the site boundary. PAGE I11 OF 12 REVISION 28A

GENERAL BROWNS FERRY EMERGENCY EPIP-5 NUCLEAR PLANT ATTACHMENT D (Page 1 of 1) FOLLOW-UP INFORMATION FORM General Emergency F-1 THIS IS A REAL EVENT [[ THIS IS A DRILL This is at Browns Ferry. Name There has been a General Emergency declared at Browns Ferry affecting: [-1 Unit I F-- Unit 2 [- Unit 3 El Common The Reactor is LF Shutdown [- At Power Plant Conditions are [- Stable -- Deteriorating "Follow-Up" Information (e.g., Key Events, Status Changes, Status of any Plant Evacuations) Current Radiological Conditions are:

        -- No Abnormal Releases Offsite         -- Airborne Release Offsite

[- Liquid Release Offsite -- Release Information Not Known Additional Rad information: (e.g., release duration) The current meteorological conditions from the site are: Wind Speed _ , Wind Direction from The following Protective Action Recommendation is provided: F1- Recommendation 1 FI Recommendation 3 I] Recommendation 2 F- Recommendation 4 Please repeat the information you have received to ensure accuracy. The time for this follow up is: Time: Date: SIGNATURE: LAST PAGE PAGE 12 OF 12 REVISION 28A

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-6 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER (TSC) REVISION 20A PREPARED BY: TIM CORNELIUS PHONE: 3666 RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS DATE: 03-08-2000 APPROVED BY: TIM CORNELIUS EFFECTIVE DATE: 03-09-2000 LEVEL OF USE: REFERENCE USE VALIDATION DATE: NOT REQUIRED QUALITY-RELATED

REVISION LOG Procedure Number: EPIP-6 Revision Number: 20A Pages Affected: 10,14 Pagination Pages: NONE Description of Change: EC-24 This change is being conducted to human factor the Revision Log, Description of Change and added clarification to revision log effecting rev. 20. EPIP 6 revised the TSC RADCON Manager and Nuclear Security Checklists. EPIP 6, (rev. log) was changed to reflect the current revision level. Page 10, was revised to clarify the responsibility of the TSC Radcon Manager regarding the collection and distribution of radiological information. Page 14, added checklist items from EPIP 11 regarding actions taken routinely by TSC Nuclear Security Manager.

ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT EPIr-6 NUCLEAR PLANT CENTER ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER (TSC) 1.0 PURPOSE The purpose of this procedure is to describe the activation of the Technical Support Center (TSC), and provide for TSC operation once it has been staffed. The TSC is staffed during an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY. 2.0 SCOPE This procedure covers the emergency response from the TSC to support the shift operations staff during a radiological emergency, and direct the onsite response to the emergency. 3.0 INSTRUCTIONS 3.1 The TSC will be staffed by qualified members reporting to the TSC upon hearing the Site Accountability Alarm, Plant Public Address System, activation of the Automated Paging System (APS) or upon being called for duty by the Unit 1, Unit Operator. 3.2 The Emergency Preparedness (EP) Manager will maintain the EPIP-6 Callout List. It will be issued on white paper with each page dated for revision control. The list will be provided to the SHIFT MANAGER. Revisions to the callout list will not require PORC approval. 3.3 Required Actions for activation and operation of the TSC.

All members of the TSC staff complete the appropriate attachment for your position.

3.4 Other Information

A list of emergency organizational telephone numbers are contained in the Radiological Emergency Notification Directory (REND).

PAGE 1 OF 28 REVISION 20A

ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT EPIP-6 NUCLEARPLANT CENTER 3.5 CONTINGENCIES 3.5.1 NRC order - The NRC role onsite is to observe, advise, and concur with licensee decisions and actions. If a situation arises where the NRC wants an action taken regarding plant operation that TVA does not agree with, the SED shall require the NRC to sign a written order directing TVA to take the action before the SED will comply. 3.5.2 Evacuation - Relocate TSC to second level of office building. (Plant Manager's Office Area) 3.5.3 Reasonable action which departs from any NRC or TVA requirement (e.g., Technical Specifications, License conditions, rules, regulations, or written plant procedures) may be taken in an emergency situation when this action is immediately needed to protect the public health and safety and no action consistent with license condition or Technical Specifications that can provide adequate or equivalent protection is immediately apparent. Plant emergency procedures may depart from Technical Specifications under these conditions. 3.5.4 During Site Emergency conditions when a Site Emergency Director is in charge, he may make the decision to allow departure from any NRC or TVA requirement (as stated above). In such an event, if the SED does not hold an SRO license, concurrence shall be obtained by a Senior Reactor Operator, preferably the on-duty SHIFT MANAGER, or other SRO Licensed Operations Management, prior to the action. Additional requirements are contained in SSP-12. 1, Section 3.16.1. PAGE 2 OF 28 REVISION 20A

ACTIVATION AND OPERATION 6 BROWNS FERRY OF THE TECHNICAL SUPPORT EPIP-0 NUCLEAR PLANT CENTER 4.0 LONG TERM OPERATION 4.1 Long-term operation will be put into effect during an Alert, Site Area Emergency, or General Emergency which exists or is projected to exist for more than 12 hours. 4.2 The SED will notify the CECC of the decision to begin long-term operation. 4.3 Meal periods will be scheduled at the request of the SED. 4.4 Sleeping facilities will be established as necessary in the second floor of the Plant Administrative Building (outside the gatehouse). Nuclear Security (NS) Supervisor will provide access control. (If radiological or other conditions do not permit this area to be used, provisions will be made through the CECC for near-site lodging, or for other sleeping area onsite.) 4.5 The Operations Lunch Room in the control bay at Elevation 3C will serve as an assembly room for meetings, etc. The plant assembly room can also be used if additional space is needed and radiological conditions exist. 4.6 Additional personnel will be called in at the request of the SED to provide coverage or to ensure 12-hour or shorter shifts in the TSC. 4.7 The SED, through the OSC Director, will establish 12-hour (or shorter) shifts for their craft personnel onsite and call in additional personnel as necessary. 4.8 Following the immediate actions required for mitigating the accident, the need for additional actions for long-term operation should be appraised. Actions required for long-term operation shall include evaluation of the following:

       "*  Diesel Generator fuel oil levels and usage rates
       "*  Containment Atmosphere Dilution nitrogen tank level
       "*  Reactor Building basement (and other Class I structures) for water accumulation
        "*  Standby Gas Treatment filter/charcoal replacement needs PAGE 3 OF 28                            REVISION 20A

ACTIVATION AND OPERATION" TD L BROWNS FERRY OF THE TECHNICAL SUPPORT CENTER EPIP~ ~ -6 NUCLEAR PLANT 5.0 ATTACHMENTS Attachment A - Operations Initial Activation of TSC Checklist Attachment B - Site Emergency Director Checklist Attachment C - Operations Manager Checklist Attachment D - RADCON Manager Checklist Attachment E - Technical Assessment Manager Checklist Attachment F - Maintenance Manager Checklist Attachment G - Chemistry Manager Checklist Attachment H - Nuclear Security Manager Checklist Attachment I - Emergency Preparedness Manager Checklist Attachment J - NRC Coordinator Checklist Attachment K - TSC Communicator Checklist Attachment L - Technical Assessor # 1 (Reactor Engineer) Checklist Attachment M - Technical Assessor # 2 (I&C Engineer) Checklist Attachment N - Technical Assessor # 3 Checklist Attachment 0 - Operations Specialist Checklist Attachment P - Assistant RADCON Manager Checklist Attachment Q - Site Vice President Checklist Attachment R - Status Board Writer Checklist Attachment S -Technical Assessment Team Leader Checklist Attachment T - Site Engineering Manager Checklist Attachment U - Control Room Communicator Checklist Attachment V - Technical Support Center Clerk Checklist PAGE 4 OF 28 REVISION 20A

ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT EPIP-6 NUCLEAR PLANT CENTER ATTACHMENT A (Page 1 of 1) OPERATIONS INITIAL ACTIVATION OF TSC Initials/Time Initial TSC Activation

    /           Swipe into Accountability Card Reader.
    /           Sign the Operations Accountability Log Sheet.
    /           Unlock TSC.

I Unlock TSC Supply Cabinet. (Key in SHIFT MANAGER Key Box.) I Post and Maintain Plant conditions on affected Unit Status Board. (Obtain updates from control room personnel.) _ Emergency Classification Initiating Conditions Current unit status. NOTE: Remain in TSC, until initial personnel arrive to man the TSC, report to SHIFT MANAGER for assigned duties. PAGE 5 OF 28 REVISION 20A

ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT EP P-6 NUCLEARPPLANT CENTER ATTACHMENT B (Page 1 of 3) SITE EMERGENCY DIRECTOR CHECKLIST NOTE: (1) Maintain a log of activities and communications. Initials/Time_ Initial TSC Activation

    /         Swipe into Accountability Card Reader.
    /         Sign TSC Accountability Log Sheet.
    /         Sign in on the Staffing Board.
    /         Obtain complete turnover from the SHIFT MANAGER / SED (in the Control Room).

Obtain copy of the SHIFT MANAGER / SED Log.

Verify the TSC and OSC are ready for operation (when the following positions are staffed): TSC

              "*  Site Emergency Director
              "*  Maintenance Manager
              "*  Radcon Manager
              "*  Operations Manager
              "*  Technical Assessment Manager
              "*  Control Room Communicator
              "*  Chemistry Manager OSC
              "*  OSC Director
              "*  Electrical Supervisor
              "*  Mechanical Supervisor
              "*  Instrument and Control Supervisor
              "*  Radcon Manager
              "*  OSC Operations Manager PAGE 6 OF 28                       REVISION 20A

ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT EPIP-6 NUCLEAR PLANT CENTER ATTACHMENT B (Page 2 of 3) SITE EMERGENCY DIRECTOR CHECKLIST (Continued) Initials/Time Initial TSC Activation

    /        Assume responsibility as SED from SHIFT MANAGER/SED.
    /        Make the following announcement over the Emergency Center P.A. System.

This is NAME , I have assumed the responsibility of the Site Emergency Director. I am declaring the TSC and OSC activated at TIME This is an actual emergency (or exercise - if an exercise, we need to treat this exercise seriously as if it were a real emergency and take complete advantage of this exercise as a learning experience).

Give plant status update.

    /        Have a plant wide P.A. announcement made that you have assumed responsibility.
    /        Establish communications with the CECC utilizing the direct ring-down phone or by dialing the director at 5-751-1614.

NOTE: (1) Maintain a log of activities and communications. PAGE 7 OF 28 REVISION 20A

ACTIVATION AND OPERATION TTh BROWNS FERRY OF THE TECHNICAL SUPPORT EPIP-0 NUCLEAR PLANT CENTER ATTACHMENT B (Page 3 of 3) SITE EMERGENCY DIRECTOR CHECKLIST (Continued) Initial TSC Activation Operational Responsibilities Follow appropriate EPIP steps for current Emergency Classification:

1. EPIP-2, "Notification of Unusual Event"

2. EPIP-3, "Alert"

3. EPIP-4, "Site Area Emergency"

4. EPIP-5, "General Emergency" Directs onsite emergency accident mitigation activities.

Consult with CECC Director and Site Vice President on significant events and their related impacts. Establish and maintain site priorities for accident mitigation. Initiates onsite protective actions. Turn over SED Log to TSC Clerk. Coordinates accident mitigation actions with the NRC Initiates long term 24-hour accident mitigation operations. Responsible for the declaration of emergency classifications Authorize Emergency Radiation Exposures (EPIP-15) Makes final approval on entries into radiologicallly hazardous areas when Radcon recommends against entry. Periodic Requirements:

1. Reevaluate the event by using EPIP-1 at least every TWO HOURS or more frequently if conditions warrant.

2. Ensure update announcements to TSC and Control Room staffs (periodically and as conditions warrant).

3. Ensure update announcements to plant workers over P.A. System (periodically and as conditions warrant)

4. Ensure update status to OSC Director (periodically and as conditions warrant).

5. If CECC is not activated, make Protective Action Recommendations as needed.

When Severe Accident Management Guidelines are entered, assume decision maker duties (If Qualified). PAGE 8 OF 28 REVISION 20A

ACTIVATION AND OPERATION EPIP-O 6 BROWNS FERRY NUCLEAR PLANT OF THE TECHNICAL SUPPORT CENTER ATTACHMENT C (Page 1 of 1) OPERATIONS MANAGER CHECKLIST NOTE: (1) Maintain a log of activities and communications. Initials/Time Initial TSC Activation

    /          Swipe into Accountability Card Reader.
    /          Sign TSC Accountability Log Sheet.
    /          Sign in on the Staffing Board.
    /          Establish communications with the Shift Manager in the Control Room.
    /          Establish communications with Operations OSC Manager in the OSC.
    /          Provide someone (SRO preferred) to establish and maintain communications with the NRC via the Emergency Notification System (ENS) - as required.

Operational Responsibilities Directs operational activities. Performs damage assessment and recommends solutions and mitigating action for operational problems Provide current update status from the Control Room to the SED and the TSC Staff. Provide direction and control interface from the TSC to the Control Room. Provide assistance to the SED as needed. Provide status updates to the OSC Operations Manager. Ensure the Unit Status Boards and Equipment Status Board are maintained. Routinely update the SHIFT MANAGER and discuss priorities and status of OSC repair teams. When Severe Accident Management Guidelines are entered assume evaluator duties (If Qualified). PAGE 9 OF 28 REVISION 20A

ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT nrIr-6 NUCLEAR PLANT CENTER ATTACHMENT D (Page lof 1) RADCON MANAGER CHECKLIST NOTE: (1) Maintain a log of activities and communications. Initials/Time Initial TSC Activation

    /         Swipe into Accountability Card Reader.
    /         Sign TSC Accountability Log Sheet.
    /         Sign in on the Staffing Board.
    /         Establish communications with RADCON OSC Manager.
    /         Establish communications with plant monitoring van (if dispatched and CEOC or CECC is not staffed).
    /         Provide someone to communicate with NRC on the Health Physics Network (HPN) phone, as required.
    /         Assign a RADCON Status Board writer.

Operational Responsibilities Directs and/or performs assessment of inplant and onsite radiological conditions Directs onsite RadCon activities. Coordinates additional RadCon support with the CECC Radiological Communicator. Make recommendations for protective actions for onsite personnel. Coordinates assessment of radiological conditions offsite with CECC Radiological Communicator. Makes final recommendation to SED for entries into radiological hazardous areas. Collects and Provides plant radiological data to Emergency Facilities as applicable. Provide assistance to the SED, as needed. Provide status update to the SED. Provide updates to the RADCON OSC Manager. Ensure maintenance of the RADCON Status Maps/Boards in the TSC. PAGE 10 OF 28 REVISION 20A

ACTIVATION AND OPERATION EP I BROWNS FERRY OF THE TECHNICAL SUPPORT nrIr-o NUCLEAR PLANT CENTER ATTACHMENT E (Page lof 1) TECHNICAL ASSESSMENT MANAGER CHECKLIST NOTE: (1) Maintain a log of activities and communications. Initials/Time Initial TSC Activation

    /          Swipe into Accountability Card Reader.
    /          Sign TSC Accountability Log Sheet.
    /          Sign in on the Staffing Board.
    /          Establish communication with the Technical Assessment Team Leader.
    /          Assign a Technical Assessment Team member as a TSC Board Writer.

I Direct the TSC communicator to begin Monitoring SPDS and support status board collection or begin completing applicable portions of EPIP-20, Plant Data if SPDS is inoperable. Operation Responsibilities Provide information, evaluations, and projects to the SED. Directs onsite effluent assessment. Keeps assessment team informed of plant status. Directs activities of the Technical Assessment Team. Communicate with the CECC Plant Assessment Manager. Coordinates assessment activities with the CECC plant assessment team. Ensures that Plant Status and Trend Boards are maintained.. Projects future plant status based on present plant conditions. Provide assistance to the SED, as needed When Severe Accident Management Guidelines are entered assume evaluator duties (If Qualified). PAGE 11 OF 28 REVISION 20A

ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT CENTER EPIP-6 NUCLEAR PLANT ATTACHMENT F (Page lof 1) MAINTENANCE MANAGER CHECKLIST NOTE: (1) Maintain a log of all activities and communications. Initials/Time Initial TSC Activation

    /           Swipe into Accountability Card Reader.
    /           Sign TSC Accountability Log Sheet.
    /           Sign in on the Staffing Board.
    /          Establish Communication with OSC Team Manager, OSC Director and Assistant Director.
    /          Obtain a turnover of damage assessment and repair activities.

Operational Responsibilities Directs repairs and corrective actions. Performs damage assessment Directs activities of the Operation Support Center. Make team assignments to OSC Team Manager. Provide update OSC status to the SED. Provide assistance to the SED as needed. Provide status to the OSC Director Ensure OSC and TSC status boards are consistent. Provide TSC personnel with a debriefing summary for each returning OSC team. Communicate with the Assistant OSC director on matters concerning equipment and/or plant assessments. PAGE 12 OF 28 REVISION 20A

ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT Ir -6 NUCLEAR PLANT CENTER ATTACHMENT G (Page lof 1) CHEMISTRY MANAGER CHECKLIST NOTE: (1) Maintain a log of activities and communications. Initials/Time Initial TSC Activation

    /           Swipe into Accountability Card Reader.
    /           Sign TSC Accountability Log Sheet.
    /           Sign in on the Staffing Board.
    /           Establish communication with the Chemistry Manager in the OSC.
    /           Establish communication with the CECC Rad Assessment Coordinator.
    /           Confirm the Emergency Data Information System is in operation.

Operational Responsibilities Coordinates assessment of radioactive effluents with CECC Plant Assessment Team.. Collect Meteorological Data. Maintain Release Status Board (jointly with RADCON). Provide direction of Post Accident Sampling Activities. NOTE: Ensure that plant configurations that are prerequisite to performing sampling have been completed prior to requesting a sample. The three hour time requirement begins upon a sample request, however, a request to prepare a team for sampling does not initiate the clock. Sampling teams should not be assigned a tracking number until the team is officially requested. Provide assistance to the SED as needed. Provide status updates to the SED. Directs activities of the radiochemical laboratory and provides status update to the Chemistry Manager in the OSC. Determines impact of incident on environment, radwaste, various effluent treatment systems. PAGE 13 OF 28 REVISION 20A

ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT ErIr -6 NUCLEAR PLANT CENTER ATTACHMENT H (Page lof 1) NUCLEAR SECURITY MANAGER CHECKLIST NOTE: (1) Maintain a log of activities and communications. Initials/Time Initial TSC Activation

     /          Swipe into Accountability Card Reader.
     /          Sign TSC Accountability Log Sheet.
     /          Sign in on the Staffing Board.

I Obtain status of site accountability.

     /          Ensure accountability status is reported to the SED within 30 minutes of initiating accountability.
     /          Assist in organizing search teams if needed.
    /           Restrict access to the protected area except for personnel whose name appears on the Emergency Access List or as authorized by the SED.

I Close all site access control points, which control personnel entering or leaving the site. Only personnel authorized by the Emergency Access List or the SED will be allowed to enter.

    /           When SAE or GE level emergencies have been declared no personnel except those who have; (1) been authorized by the SED, (2) accounted for by Nuclear Security and, (3) monitored by RADCON will be allowed to leave the site.

Operational Responsibilities Directs activities of Nuclear Security personnel. Controls Access to Site and Control Rooms. Reports on site accountability / evacuation as defined in BFN-EPIP's. Provide update status to Security Shift Supervisors. Provide update status to SED. Provide assistance to SED as needed. PAGE 14 OF 28 REVISION 20A

ACTIVATION AND OPERATION 1 BROWNS FERRY OF THE TECHNICAL SUPPORT EPIP- NUCLEAR PLANT CENTER ATTACHMENT I (Page lof 1) EMERGENCY PREPAREDNESS MANAGER CHECKLIST NOTE: (1) Maintain a log of activities and communications. Initials/Time Initial TSC Activation

    /          Swipe into Accountability Card Reader.
    /          Sign TSC Accountability Log Sheet.
    /          Sign in on the Staffing Board.
    /          Call Clerical Support personnel.
    /          Confirm all TSC and OSC positions are filled and SED informed. (Notify the Unit 1, Unit Operator when TSC and OSC are staffed).
    /          Correct any activation problems.
    /          Confirm all "Initial TSC Activation" items are completed for all TSC positions.

Operational Responsibilities Advises SED regarding overall radiological emergency plan, use of implementing procedures, emergency equipment availability, and coordination with CECC. Confirms site emergency centers are operating properly. Provide assistance to the SED as needed. Deactivation of the TSC

Collect all logs and information forms from all staff members in the TSC.
Place the TSC in a ready state.

PAGE 15 OF 28 REVISION 20A

ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT EPIP-6 NUCLEAR PLANT CENTER ATTACHMENT J (Page lof 1) NRC COORDINATOR CHECKLIST NOTE: (1) Maintain a log of activities and communications. Initials/Time Initial TSC Activation

    /         Swipe into Accountability Card Reader.
    /         Sign TSC Accountability Log Sheet.
    /         Sign in on the Staffing Board.

Operational Responsibilities Acts as primary liaison with onsite NRC personnel. Update NRC Personnel on plant status. Provide information requests from NRC to TSC personnel. PAGE 16 OF 28 REVISION 20A

ACTIVATION AND OPERATION 6 BROWNS FERRY OF THE TECHNICAL SUPPORT EPIr- NUCLEAR PLANT CENTER ATTACHMENT K (Page lof 1) TSC COMMUNICATOR CHECKLIST Initials/Time Initial TSC Activation

    /         Swipe into Accountability Card Reader.
    /         Sign TSC Accountability Log Sheet.
    /         Sign in on Staffing Board.
    /         Ensure operability of SPDS in the TSC.

Operational Responsibilities Maintain the Main SPDS terminal in the TSC in support of staff needs. Support the status board writers in maintaining parameter and parameter trend board information. Provides information from the control room to the Technical Assessment team as needed. If SPDS is inoperable or becomes inoperable then, completes plant data sheets, Attachment 1, 2, or 3 of EPIP-20 every one-half hour or more frequently if required. PAGE 17 OF 28 REVISION 20A

ACTIVATION AND OPERATION ]D'D I BROWNS FERRY OF THE TECHNICAL SUPPORT .Ir -0 NUCLEARPLANT CENTER ATTACHMENT L (Page lof 1) TECHNICAL ASSESSOR # 1 CHECKLIST (REACTOR ENGINEER) NOTE: (1) Maintain a log of activities and communications. Initials/Time Initial TSC Activation

    /          Swipe into Accountability Card Reader.
    /          Sign TSC Accountability Log Sheet.
    /          Sign in on Staffing Board.

I Obtain needed documents and set up in the Technical Assessment Team Area. Operational Responsibilities Completes trend graphs as needed. Provides the TSC staff and CECC Plant Assessment Team with current assessments on plant conditions. Project future plant status based on current conditions. Provide Technical Support as needed. When Severe Accident Management Guidelines are entered report to the TSC and assume evaluator duties (If Qualified). PAGE 18 OF 28 REVISION 20A

ACTIVATION AND OPERATION EPIP BROWNS FERRY OF THE TECHNICAL SUPPORT ErIr-6 NUCLEAR PLANT CENTER ATTACHMENT M (Page lof 1) TECHNICAL ASSESSOR # 2 CHECKLIST (INSTRUMENTATION AND CONTROL ENGINEER) NOTE: (1) Maintain a log of activities and communications. Initials/Time Initial TSC Activation

     /          Swipe into Accountability Card Reader.
     /          Sign TSC Accountability Log Sheet.
     /          Sign in on Staffing Board.
     /          Obtain needed documents and set up in the Technical Assessment Team Area.

Operational Responsibilities Completes trend graphs as needed. Provides the TSC staff and CECC Plant Assessment Team with current assessments on plant conditions. Project future plant status based on current conditions. Provide Technical Support as needed. When Severe Accident Management Guidelines are entered report to the TSC and assume evaluator duties (If Qualified). PAGE 19 OF 28 REVISION 20A

ACTIVATION AND OPERATION r BROWNS FERRY OF THE TECHNICAL SUPPORT ErIr-6 NUCLEAR PLANT CENTER ATTACHMENT N (Page lof 1) TECHNICAL ASSESSORS #3 CHECKLIST NOTE: (1) Maintain a log of activities and communications. Initials/Time Initial TSC Activation

     /         Swipe into Accountability Card Reader.
     /         Sign TSC Accountability Log Sheet.
     /         Sign in on Staffing Board.

I Obtain needed documents and set up in the Technical Assessment Team Area. Operational Responsibilities Completes trend graphs as needed. Provides the TSC staff and CECC Plant Assessment Team with current assessments on plant conditions. Project future plant status based on current conditions. Provide Technical Support as needed. Provide information to the Plant Assessment Team member (Board Writer) for TSC Status Boards. NOTE: To obtain current plant parameters, monitor the operations communications bridge as assigned by the team leader. NOTE: If assigned as the TSC status Technical Status Board writer follow these instructions. Report to TSC

                 "* Monitor communications via the operations party line.
                 "* Maintain the following status boards Affected Unit Trend Boards Technical Assessment Parameter PAGE 20 OF 28                      REVISION 20A

ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNCAL SUPPORT EPIP-0 NUCLEAR PLANT CENTER ATTACHMENT 0 (Page lof 1) OPERATIONS SPECIALIST CHECKLIST NOTE: (1) Maintain a log of activities and communications. Initials/Time Initial TSC Activation

    /         Swipe into Accountability Card Reader.

I Sign TSC Accountability Log Sheet.

    /         Sign in on Staffing Board.
    /         Establish communications with Control Room Communicator in the Control Room and OSC Operations Manager via party line.

Operational Responsibilities Provides operational knowledge for status evaluation of plant systems. Provides advice regarding technical specifications, system response, safety limits, etc.. Assists in development of recommended solutions to developing problems. Provide plant data to the TSC Staff and to the Shift Manager. (Use party line) Provide Assistance to the SED as needed. When Severe Accident Management Guidelines are entered assume evaluator duties (If Qualified). PAGE 21 OF 28 REVISION 20A

ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHINICAL SUPPORT ErIr-6 NUCLEAR PLANT CENTER ATTACHMENT P (Page lof 1) ASSISTANT RADCON MANAGER CHECKLIST NOTE: (I) Maintain a log of activities and communications. Initials/Time Initial TSC Activation

    /         Swipe into Accountability Card Reader.
    /         Sign TSC Accountability Log Sheet.
    /         Sign in on Staffing Board.
    /        Begin providing information for the TSC RADCON Status Board writer.

Operational Responsibilities Provide Radiological Data to the RADCON Manager. Assist the Chemistry Manager in maintaining the Release Status Board. PAGE 22 OF 28 REVISION 20A

ACTIVATION AND OPERATION E BROWNS FERRY OF THE TECHNICAL SUPPORT It -6 NUCLEAR PLANT CENTER ATTACHMENT Q (Page lof 1) SITE VICE PRESIDENT CHECKLIST NOTE: (1) Maintain a log of activities and communications. Initials/Time Initial TSC Activation

    /           Swipe into Accountability Card Reader.
     /          Sign TSC Accountability Log Sheet.
     /           Sign in on Staffing Board.

Operational Responsibilities Provides TVA policy direction to the Site Emergency Director (SED). Directs the site resources to support the SED in the accident mitigation activities. Interface with News Media through the Information Officer. (7698 or from Weekly Duty List) Assist the SED as needed. At his discretion, may provide interface at the appropriate offsite location on the overall site response activities with; State and local agencies, NRC region/corporate, and Joint Information Center. Provide direct interface on overall site response activities with NRC, FEMA, or other Federal organizations responding to the site. Provides direct interface on overall site response activities with the CECC Director and onsite media. Provides support to the other emergency operation centers as necessary. PAGE 23 OF 28 REVISION 20A

ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT CENTER EPIP-6 NUCLEAR PLANT ATTACHMENT R (Page lof 1) STATUS BOARD WRITER CHECKLIST (Unit/Equipment Boards) Initials/Time Initial TSC Activation

    /                    Swipe into Accountability Card Reader.
    /                    Sign TSC Accountability Log Sheet.
    /                    Sign in on Staffing Board.
    /                    Establish communications with OSC status Board writers.

Operational Responsibilities Maintain the following Status Boards:

   "* Equipment Problems
   "* Unaffected Unit
   "* Team Tracking PAGE 24 OF 28                      REVISION 20A

ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT EPIP-6 NUCLEAR PLANT CENTER ATTACHMENT S (Page lof 1) TECHNICAL ASSESSMENT TEAM LEADER CHECKLIST NOTE: (1) Maintain a log of activities and communications. Initials/Time Initial TSC Activation

    /         Swipe into Accountability Card Reader.
    /         Sign the TSC Accountability Log Sheet.
    /         Sign in on the Staffing Board.
    /         Report to Technical Assessment Team Area.
    /         Establish communications with the Plant Assessment Team in the CECC.
     /        Assign a technical assessor position to monitor the operation communication bridge.

Operational Responsibilities Performs systems assessment as directed by Technical Assessment Manager. Determines condition of Reactor and Nuclear Fuel Acts as Plant Assessment Team Leader Provide updated information to the Plant Assessment Team. Provide detailed technical assessments and recommendations to the TSC. When Severe Accident Management Guidelines are entered remain in technical assessment team area and assume evaluator duties (If Qualified). PAGE 25 OF 28 REVISION 20A

ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT EPIP-6 NUCLEAR PLANT CENTER ATTACHMENT T (Page lof 1) SITE ENGINEERING MANAGER CHECKLIST NOTE: (1) Maintain a log of activities and communications. Initials/Time Initial TSC Activation

    /         Swipe into Accountability Card Reader.
    /         Sign the TSC Accountability Log Sheet.
    /         Sign in on the Staffing Board.

I Report to the Technical Assessment Team Area. Operational Responsibilities Serves as the primary interface with Engineering. Serve as a member of the Technical Assessment Team. Provide Engineering Support to TSC. PAGE 26 OF 28 REVISION 20A

ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT EPIP-6 NUCLEAR PLANT CENTER ATTACHMENT U (Page lof 1) CONTROL ROOM COMMUNICATOR CHECKLIST Initials/Time Initial TSC Activation

    /         Swipe into Accountability Card Reader.
    /         Sign the TSC Accountability Log Sheet.
    /         Sign in on the Staffing Board.
    /         Report to the affected Unit Control Room.
    /         Establish Communications with the Operations Specialist (use party line).

Operational Responsibilities Provide updated plant parameters and status over the telephone to the Operations Specialist, Technical Assessment team areas and OSC operations personnel When Severe Accident Management Guidelines are entered remain in the control room and assume evaluator duties (If Qualified). PAGE 27 OF 28 REVISION 20A

ACTIVATION AND OPERATION BROWNS FERRY OF THE TECHNICAL SUPPORT .Ir -6 NUCLEARPLANT CENTER ATTACHMENT V (Page 1 of 1) TECHNICAL SUPPORT CENTER CLERK CHECKLIST NOTE: Maintain a log of activities and communications. Initials/Time Initial TSC Activation

    /          Swipe into Accountability Card Reader.
    /          Sign the TSC Accountability Log Sheet.
    /          Sign in on the Staffing Board.
    /          Check the operability of the copy machine.

Operational Responsibilities Maintain log of events. Answer telephones. Operate facsimile machine. Other duties as assigned by the Site Emergency Director. Provide clerical support to the TSC Staff. Maintain official SED Log. LAST PAGE PAGE 28 OF 28 REVISION 20A

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT-EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-7 ACTIVATION AND OPERATION OF THE OPERATIONS SUPPORT CENTER (OSC) REVISION 18A PREPARED BY: TIM CORNELIUS PHONE: 2038 RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS DATE: 03/08/2000 APPROVED BY: TIM CORNELIUS EFFECTIVE DATE: 03/09/2000 LEVEL OF USE: REFERENCE USE VALIDATION DATE: NOT REQUIRED QUALITY-RELATED

REVISION LOG Procedure Number: EPIP-7 Revision Number: 18A Pages Affected: 1,4,5.6,7,9,11,14,20,21,27,28 Pagination Pages: All Description of Change: EC-21 This change is being conducted to human factor the Revision Log, Description of Change and added clarification to revision log effecting rev. 18. EPIP 7 revised and combined the Team Briefing/Debriefing Form and the Team Tracking Form, added checklist for planners and document control, removed the customer group checklist, revised existing checklists and removed the management of the call-out list which is contained in EPIP- 17. EPIP 7 (rev. log) was changed to reflect the current revision level. Page 1, was revised to remove information concerning maintenance of the "Call-Out" List. Information regarding the "Call-Out" list is contained in EPIP- 17 (removal of this step resulted in a change to procedural steps which are not marked as revisions. Page 4/5, revised Attachment A (Team Tracking Form) incorporating Attachment B, Delete Attachment B (Briefing/De-Briefing Form). (Combining Attachment A and Attachment B resulted in changing the alpha designator for the remaining Attachments, which were not designated with revision indications) Page 6, revised maintenance superintendent title to maintenance manager. Page 7, removed checklist item to contact Document Control personnel, now a paged position. Revised maintenance superintendent title to maintenance manager. Page 9, revised Radcon superintendent title to Radcon manager, clarified responsibility ensuring radcon coverage for all teams to as applicable. Page 11, revised responsibility to allow Staging Area Fire Protection Personnel to assist on donning SCBA's. Page 14, deleted customer group attachment. Page 20, re-titled checklist header. Page 21. revised to remove OSC Staging Area Manager responsibility from reporting to the OSC, the revision allows the OSC Staging Area Manager to report directly to staging area. Page 27, added OSC Planner Checklist. Page 28. added OSC Document Control Checklist. Page 29, removed customer group for OSC Diagram.

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT Em Ir-7 NUCLEAR PLANT CENTER (OSC) 1.0 PURPOSE 1.1 The purpose of this procedure is to describe the activities of the Operations Support Center (OSC) and the assessment and repair activities during a radiological emergency. 2.0 Scope 2.1 The procedure covers the emergency response from the OSC during an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY. 3.0 INSTRUCTIONS 3.1 The OSC will be staffed by qualified members reporting to the OSC and staging area upon hearing the Site Accountability Alarm, Plant Public Address System, upon activation of the Automated Paging System (APS), or upon being called for duty by the Unit 1, Unit Operator. NOTE: Refer to EPIP-8, Personnel Accountability and Evacuation. 3.2 The OSC is located in two locations.

             "* The OSC is located on elevation 580' Service Building.
             "* The OSC staging area located on elevation 565' of the Service Building Maintenance Lunch Room area.

NOTE: If necessary to evacuate the OSC, relocate to the second level of the Plant Office Building (Plant Manager's Office area). PAGE I OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT - NUCLEAR PLANT CENTER (OSC) 3.0 INSTRUCTIONS (CONTINUED) 3.3 Operation of The OSC 3.3.1 Normal plant maintenance procedures will be followed whenever possible. Should a situation arise where normal procedures would be inappropriate, maintenance will be performed as determined by the SED. If a situation is encountered in the field that threatens the safety of any team member, the Team Leader shall take appropriate action to prevent injury. 3.4 Required Actions for Activation and Operation of the OSC 3.4.1 All members of the OSC staff complete the appropriate attachment for your position. 4.0 LONG -TERM OPERATION 4.1 Upon receiving information from the TSC that emergency operation is expected to extend past 12 hours, the OSC Director will arrange to set up shift rotations. NOTE: Calling in additional personnel may be necessary. PAGE 2 OF 29 REVISION 18A

BROWNS FERRY ACTIVATION AND OPERATION OF THE OPERATIONS SUPPORT EPIP-7 NUCLEAR PLANT CENTER (OSC) 5.0 Attachments Attachment A Team Tracking Form Attachment B OSC Director Checklist Attachment C RADCON OSC Manager Checklist Attachment D Fire Protection OSC Manager Checklist Attachment E Chemistry OSC Manager Checklist Attachment F Operations OSC Manager Checklist Attachment G Instrumentation and Controls OSC Supervisor Checklist Attachment H Mechanical OSC Supervisor Checklist Attachment I Electrical OSC Supervisor Checklist Attachment J RADCON Lab Supervisor Checklist Attachment K Fire Protection Shift Captain Checklist Attachment L Chemistry Lab Supervisor Checklist Attachment M OSC Engineer's Check List Attachment N OSC Staging Area Manager Attachment 0 Assistant OSC Director Attachment P OSC Clerk Checklist Attachment Q Status Board Writer Attachment R OSC Team Manager Attachment S Materials Coordinator Attachment T OSC Planners Checklist Attachment U OSC Document Control Checklist Attachment V- OSC Configuration PAGE 3 OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT CENTER (OSC) EPIP-7 NUCLEAR PLANT ATTACHMENT A (Page 1 of 2) TEAM TRACKING FORM TEAM DESIGNATOR (A, B, C, etc.) TEAM PRIORITY (NA, 1, 2,3, etc.) Team Team Task: Manager I Associated TSC Priority: initials Time Task Location: UNIT [-]1 F-2 [-13 -]Common 0i Reactor Bldg., Elev. _ _ Control Bay, Elev. _ _ Diesel Bldg., Elev. El Turbine Bldg., Elev. _ _ OTHER (Be Specific) Elev. Assist. Responsible El Electrical Li I&C Li RADCON Director Section: Di Mechanical El Operations Li Fire/Medical [I OTHER (Be Specific)

        /        1E  OSC Center Announcement:

Initials Time Let me have your attention, Team (Use Designator)has been requested from the TSC to (DescribeTask). (Section Rep) has been assigned to plan this task. Section Rep Team Members Team Leader Section:

        /                                _Section:

Initials Time Section: Section: Section: Briefing Checklist E] Description of Problem E3 Key(s) Needed for Task "13Effected System Status E3 Hazards to/from Work Site "13Procedures to be Used E3 Safety Evaluation [1 Drawings to be Used 13 Operations Support E1 Tools/Equipment Needed El RADCON Support F1 Clearances Needed E3 RWP Required/Brief 13 Route to/from Work Site 13 Return as a team for De-Briefing Communications: El Hand-Held Radio, Channel LI Telephone, provide OSC Number LI Other RADCON RWP Utilized D]Yes F]No If yes, RWP#

        /        Emergency Exposures Utilized                 EjYes E]No (If Yes Approval Required, EPIP 15)

Initials Time Potassium Iodine Utilized -]Yes 1]No (If Yes Approval Required, EPIP 14) OSC Director Final Approval By OSC Director

        /        13 OSC Center Announcement:

Initials Time "Is there any reason that Team (Use Designator)should not be released at this time". PAGE 4 OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT EPIP-7 NUCLEAR PLANT CENTER (OSC) ATTACHMENT A (Page 1 of 2) TEAM TRACKING FORM TEAM DESIGNATOR (A, B, C, etc.) TEAM PRIORITY (NA, 1, 2,3, etc.) Section Rep De-Briefing Summary Information i F-1 Assignment Completed F- YES n NO [-- CANCELLED Initials Time R-I Equipment Status "As Left": F-- Hazards Encountered (Actual or Potential) F-D Equipment Clearance Status

                   - Unusual Sounds, Additional Radiological Information, Other Task Applicable Information DE-BRIEFING CLOSURE E] Inform OSC Director of Team De-Briefing Summary

[] Direct Personnel to OSC STAGING AREA or Other 13 Update OSC Team Tracking Board OSC Director ITSC Notified. Team results provided to the TSC Maintenance Manager i Initials Time 8 PAE5OI9RVSO PAGE 5 OF 29 REVISION 18A

ACTIVATION AND OPERATIONI TI 7 BROWNS FERRY OF THE OPERATIONS SUPPORT -NUCLEAR PLANT CENTER (OSC) ATTACHMENT B (Page 1 of 3) OSC DIRECTOR CHECKLIST NOTE: Maintain a log of activities and communications. NOTE: Operations Personnel initially activating the OSC, when relieved by the on-call OSC Director will assume the duties of the Operations OSC Manager (See Attachment 7). Initials/Time Initial OSC Activation

     /                  Swipe into Accountability Card Reader.
     /                  Sign the OSC Accountability Log Sheet.
     /                  Sign in on the staffing board.
     /                  Set up the OSC (assign any available personnel to assist)
                        "O Configure OSC area an arrangement similar to EPIP-7, Attachment V "o Clear tables "o Ensure telephones are in proper location and operating.
                        "O Open OSC supply cabinet "o Place notebooks in the proper position in the OSC.
                        "O Obtain needed documents Inform the SHIFT MANAGER/SED of your location and status Unit 1 2191/2192 Unit 2 2291/2292 Unit 3 2391/2392 Establish communication with the Maintenance Manager (TSC) (phone #

3766). Establish communication with the OSC Staging Area Manager (phone # 2244). Confirm the OSC is staffed (Notify the Maintenance Manager) (phone # 3766). PAGE 6 OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT EPIP-7 NUCLEAR PLANT CENTER (OSC) ATTACHMENT B (Page 2 of 3) ATTACHMENT B (Page 2 of 3) OSC DIRECTOR CHECKLIST (Continued) Initials/Time Initial OSC Activation (Continued)

     /                 Make the following remarks prior to activating the OSC.

This is an actual emergency (or exercise - if an exercise, we need to treat this exercise seriously as if it were a real emergency and take complete advantage of this exercise as a learning experience). Be Professional

                                 "* Keep legible logs of all your activities.
                                 "* Be clear and precise in transfer of information.
                                 "* Make sure you are accurate with units as data are transferred.
                                  "* Keep noise level down as low as possible.

Ensure that the Team Manager: E- Tracks any team(s) dispatched prior to OSC activation. F Form initial response teams (see note below). Operational Responsibilities Provide Maintenance Manager with a debriefing summary for each returning repair/damage team. Direct OSC activities through the Assistant OSC Director. Communication with the SED as needed to ensure effective performance of the OSC. Approve the dispatching of all teams. Provide updates to the OSC personnel. PAGE 7 OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT CENTER (OSC) EPIP-7 NUCLEAR PLANT ATTACHMENT B (Page 3 of 3) OSC DIRECTOR CHECKLIST (Continued) Operational Responsibilities (Continued) Provide updates to the OSC staging area personnel (approximately every one-half hour or as conditions warrant). Ensure that all teams returning from assigned tasks are debriefed utilizing Attachment A of this procedure. NOTE: Initial response teams are as a minimum:

1. One Medical Emergency/Fire Response Team.

2. Two RADCON Survey Teams.

3. One Post Accident Sampling Team.

4. Two repair teams (each consists of at least one Mechanical, one Electrical, one Operations, and one RADCON).

5. Turbine Building el. 565' Tool Room.

NOTE: If AREA is determined to be not habitable by Radcon discontinue this team #5. PAGE 8 OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT EPIP-7 NUCLEAR PLANT CENTER (OSC) ATTACHMENT C (Page 1 of 2) RADCON OSC MANAGER CHECKLIST NOTE: Maintain a log of activities and communications. Initials/Time Initial Activation of the OSC

     /                  Swipe into Accountability Card Reader.

I Sign the OSC Accountability Log Sheet.

     /                  Sign in on the staffing board.
     /                  Establish communication with the RADCON Manager in the TSC.
     /                  Establish communication with the RADCON Lab Supervisor.
     /                  Ensure adequate RADCON staff available for OSC support.
     /                  Assign a RADCON Technician to the MERT.
     /                  Assign a RADCON status board writer.
      /                 Complete "Team Tracking Forms" (Attachment A) for all RADCON personnel dispatched prior to the OSC activation and give to the Assistant OSC Director.

Operational Responsibilities Direct RADCON personnel in the RADCON lab. Ensure all RADCON teams are dispatched through the OSC. Provide assistance to the OSC Director, as needed. Ensure as applicable that teams have RADCON coverage. Brief the OSC Director of RADCON status. Brief the RADCON Superintendent in the TSC on status. PAGE 9 OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT nrIr-7 NUCLEAR PLANT CENTER (OSC) ATTACHMENT C (Page 2 of 2) RADCON OSC MANAGER CHECKLIST (Continued) Operational Responsibilities (Continued) Complete and update "Team Tracking Forms" (Attachment A) for RADCON teams you are assigned. Ensure that all predressed OSC staging area teams are issued proper dosimetry and have been evaluated for radiological access (i.e. watch list) Ensure technical briefing to OSC teams of radiological conditions prior to dispatch. PAGE 10 OF 29 REVISION 18A

ACTIVATION AND OPERATION 7 BROWNS FERRY OF THE OPERATIONS SUPPORT EPI I- NUCLEAR PLANT CENTER (OSC) ATTACHMENT D (Page 1 of 1) FIRE PROTECTION OSC MANAGER CHECKLIST NOTE: Maintain a log of activities and communications. Initials/Time Initial OSC Activation

     /                    Swipe into Accountability Card Reader.
     /                    Sign the OSC Accountability Log Sheet.
     /                    Sign in on the staffing board.
     /                    Establish communications with the Site Fire Protection Shift Captain and staff Complete "Team Tracking Forms" (Attachment A) for all Fire Protection Personnel dispatched prior to OSC activation and give to the Assistant OSC Director.

Operational Responsibilities When possible allow Staging Area Fire Protection personnel to assist team in donning SCBAs. Provide and coordinate site Fire Protection resources as necessary to support the OSC Director. Assist in technical briefings of OSC teams as necessary. Provide evaluations and projections on emergency air supplies. Complete and update "Team Tracking Forms" (Attachment A) for MERT and fire fighting teams you are assigned. Provide industrial safety support to the OSC Director as needed. Brief teams on industrial hazards as needed. PAGE I1I OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT - NUCLEAR PLANT CENTER (OSC) ATTACHMENT E (Page 1 of 1) CHEMISTRY OSC MANAGER CHECKLIST NOTE: Maintain a log of activities and communications. Initials/Time Initial Activation of the OSC

     /                  Swipe into Accountability Card Reader.
     /                  Sign the OSC Accountability Log Sheet.
     /                  Sign in on the staffing board.
     /                 Establish communication with the Chemistry Lab Personnel. If no Chemistry Shift Supervisor is available in the lab, appoint a lead technician and call in the next shift Chemistry Supervisor.
     /                 Ensure adequate Chemistry staff is available to support the OSC.
     /                 Complete "Team Tracking Forms" (Attachment A) for all Chemistry Personnel dispatched prior to OSC activation, and give to the Assistant OSC Director.

Operational Responsibilities Direct Chemistry assignments in the Chemistry lab. Ensure all Chemistry teams are dispatched through the OSC. Provide assistance to the OSC Director as needed. Brief the OSC Director of Chemistry status. Complete and update "Team Tracking Forms" (Attachment A) for Chemistry teams you are assigned. Obtain necessary post accident samples (as directed by the OSC Director). The three hour time requirement begins upon a sample requested by the SED, however, a request to prepare a team for sampling does not start the time period. Sampling teams should not be assigned a tracking number until the sample is officially requested. PAGE 12 OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT EPIP-r NUCLEARPLANT CENTER (OSC) ATTACHMENT F (Page 1 of 1) OPERATIONS OSC MANAGER CHECKLIST NOTE: Maintain a log of activities and communications. Initials/Time Initial OSC Activation

     /                 Swipe into Accountability Card Reader.
     /                 Sign in on the staffing board.
     /                Notify the OSC Director and Shift Manager (affected unit Control Room) upon arrival to the OSC.
     /                 Establish communications with the Operations Communicator utilizing the operations communications bridge.
     /                 Establish communications with supporting OSC Operations personnel (staging area).
      /                Complete "Team Tracking Forms" (Attachment A) for all Operations Personnel dispatched prior to OSC activation, and give to the Assistant OSC Director. (EOI Activities)

Operational Responsibilities Provide and coordinate operations personnel to support the OSC Director. Provide operations support to OSC teams that are dispatched into the field. Perform any operations actions that may be required while in the field. Keeps the SHIFT MANAGER apprised of OSC team activities while in the field. Complete and update "Team Tracking Forms" (Attachment A) for Operations teams you are assigned. Ensure the responsiveness of EOI field teams. PAGE 13 OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT EPIP-7NUCLEAR PLANT CENTER (OSC) ATTACHMENT G (Page 1 of 1) INSTRUMENT AND CONTROL (I&C) SUPERVISOR CHECKLIST NOTE: Maintain a log of activities and communications. Initials/Time Initial OSC Activation

     /                    Swipe into Accountability Card Reader.
     /                    Sign the OSC Accountability Log Sheet.
     /                    Sign in on the staffing board.
     /                   Notify the OSC Director upon arrival.
     /                   Establish communications with the supporting OSC I&C staff (staging area).
     /                   Complete "Team Tracking Forms" (Attachment A) for all I&C Personnel dispatched prior to OSC activation and give to the Assistant OSC Director.

Operational Responsibilities Provide and coordinate I&C resources necessary to support the OSC Director and teams. Provide technical assistance with I&C problems. Perform damage and repair assessments. Assist in technical briefings of OSC teams as necessary. Complete and update "Team Tracking Forms" (Attachment A) for I&C teams you are assigned. PAGE 14 OF 29 REVISION 18A

ACTIVATION AND OPERATION EPIP 7 BROWNS FERRY OF THE OPERATIONS SUPPORT - NUCLEAR PLANT CENTER (OSC) ATTACHMENT H (Page 1 of 1) MECHANICAL OSC SUPERVISOR CHECKLIST NOTE: Maintain a log of activities and communications. Initials/Time Initial OSC Activation

     /                    Swipe into Accountability Card Reader.
     /                    Sign the OSC Accountability Log Sheet.
     /                    Sign in on the staffing board.
     /                    Notify OSC Director upon arrival.
     /                    Establish communications with appropriate supporting OSC Mechanical staff (Staging Area).

I Complete "Team Tracking Forms" (Attachment A) for all Mechanical Personnel dispatched prior to OSC activation and give to the Assistant OSC Director. Operational Responsibilities Provide and coordinate Mechanical Maintenance resources necessary to support OSC Director and teams. Provide technical assistance with mechanical system problems. Perform damage and repair assessments. Assist in technical briefings of OSC teams as necessary. Complete and update "Team Tracking Forms" (Attachment A) for mechanical maintenance teams you are assigned. PAGE 15 OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT _PIP- NUCLEAR PLANT CENTER (OSC) ATTACHMENT I (Page 1 of 1) ELECTRICAL OSC SUPERVISOR CHECKLIST NOTE: Maintain a log of activities and communications. Initials/Time Initial OSC Activation

     /                   Swipe into Accountability Card Reader.
     /                   Sign the OSC Accountability Log Sheet.
     /                   Sign in on the staffing board.
     /                   Notify OSC Director upon arrival.
     /                   Establish communications with appropriate supporting OSC Electrical staff (staging area).
     /                   Complete "Team Tracking Forms" (Attachment A) for all Electrical Personnel dispatched prior to OSC activation.

Operational Responsibilities Provide and coordinate Electrical Maintenance resources necessary to support OSC Director and teams. Provide technical assistance with electrical system problems. Perform damage and repair assessments. Assist in technical briefings of OSC teams as necessary. Complete and update "Team Tracking Forms" (Attachment A) for Electrical Maintenance teams you are assigned. PAGE 16 OF 29 REVISION 18A

ACTIVATION AND OPERATION 7BROWNS FERRY OF THE OPERATIONS SUPPORT JIF-F NUCLEAR PLANT CENTER (OSC) ATTACHMENT J (Page 1 of 1) RADCON LAB SUPERVISOR (RADCON LAB) CHECKLIST NOTE: Maintain a log of activities and communications. Initials/Time Initial OSC Activation

     /                 Swipe into Accountability Card Reader.
     /                 Sign RADCON lab Accountability Log Sheet
     /                 Establish communications with appropriate supporting RADCON Lab staff.

Operational Responsibilities Provide and coordinate RADCON personnel necessary to support the OSC teams. Maintains an interface with the OSC RADCON Manager related to the radiological conditions in the plant. Ensure that adequate dosimetry is maintained for OSC teams. PAGE 17 OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT CENTER (OSC) EPIr-7 NUCLEAR PLANT ATTACHMENT K (Page 1 of 1) FIRE PROTECTION SHIFT CAPTAIN (STAGING AREA) CHECKLIST NOTE: Maintain a log of activities and communications. Initials/Time Initial OSC Activation

     /                  Swipe into Accountability Card Reader.
     /                  Sign the OSC staging area Accountability Log Sheet.
     /                  Ensure all ESTS sign the OSC Staging area Accountability Log Sheet.
     /                  Notify Fire Protection Manager (OSC) upon arrival.
     /                  Establish communications with the site Fire Protection staff.

Operational Responsibilities Monitor status of site Fire Protection/Life Safety systems and keep OSC Fire Protection Manager apprised. Acts as Medical Emergency Response Team (MERT) Leader if EPIP- 10 is implemented. Keeps Fire Protection OSC Manager apprised as to status of emergency air supplies. Directs the Fire Protection staffs activities when required to dispatch into the field for fire, medical, or other necessary support. PAGE 18 OF 29 REVISION 18A

ACTIVATION AND OPERATION E BRONS FERRY OF THE OPERATIONS SUPPORT jIr-7 NUCLEAR PLANT CENTER (OSC) ATTACHMENT L (Page 1 of 1) CHEMISTRY LAB SUPERVISOR (CHEMISTRY LAB) CHECKLIST NOTE: Maintain a log of activities and communications. Initials/Time Initial OSC Activation

     /                    Swipe into Accountability Card Reader.
      /                   Sign the Chemistry Lab Accountability Log Sheets
      /                   Ensure the condensate oxygen injection system has been isolated if installed on the affected unit.
      /                   Establish communications with appropriate supporting Chemistry staff.
      /                   Ensure dose-rate monitoring instruments are functioning properly.
      /                   Have on-duty technicians review emergency sampling/analysis procedures and prepare for implementation.

Operational Responsibilities Provide and coordinate Chemistry Lab necessary to support the OSC teams. Assist in technical briefings of OSC teams as necessary. Obtain necessary post accident samples and performs analysis of samples (as directed by the OSC Director). The three hour time requirement begins upon a sample request by the SED, however, a request to prepare a team for sampling does not start the time period. Sampling teams should not be assigned a tracking number until the sample is officially requested. Maintains an interface with the Chemistry OSC Manager and provides results of sample analysis in a timely manner. PAGE 19 OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT CENTER (OSC) EPIP-7 NUCLEAR PLANT ATTACHMENT M (Page 1 of 1) OSC ENGINEER'S CHECKLIST (ELECTRICAL - MECHANICAL - INSTRUMENTATION AND CONTROLS) NOTE: Maintain a log of activities and communications. Initials/Time Initial OSC Activation

     /                Swipe into Accountability Card Reader.
     /                Sign the OSC Accountability Log Sheet.
     /                Sign in on the staffing board.

Operational Responsibilities Provide engineering support to the OSC staff. PAGE 20 OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT EPIP-7 NUCLEAR PLANT CENTER (OSC) ATTACHMENT N (Page 1 of 1) ATTACHMENT N (Page I of 1) OSC STAGING AREA MANAGER Initials/Time Initial OSC Activation

     /                 Swipe into Accountability Card Reader.
     /                 Sign the OSC Staging Area Accountability Log Sheet.
     /                 Assign a foreman to set up the OSC staging area, include the following:

F-D Ensure all personnel in the OSC staging area card into the Accountability Card Reader. M Ensure all personnel in the OSC staging area sign the Accountability Log Sheet.

                         - Unlock Supply Cabinet
                          - Install the OSC Staging Area Telephones.

Operational Responsibilities Maintain control in the OSC staging area Assemble personnel and direct them to the OSC when requested. Ensure adequate man-power exist in the OSC staging area. (i.e. Radcon, AUO's, Electrical, etc. personnel) Inform OSC manager of all time delays in team assembly. PAGE 21 OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT Jh -7 NUCLEAR PLANT CENTER (OSC) ATTACHMENT 0 (Page 1 of 1) ASSISTANT OSC DIRECTOR CHECKLIST Initials/Time Initial OSC Activation

     /                 Swipe into Accountability Card Reader.
     /                 Sign the OSC Accountability Log Sheet.
     /                 Sign in on the staffing board.
     /                 Call Maintenance Planner.
     /                 Collect any completed Team Tracking Forms from OSC managers and route to OSC Team Manager.

Operational Responsibilities Ensure status boards are kept current. Assign tasks to appropriate OSC managers when directed by OSC Team Manager. Keep the OSC Director informed of task status. Ensure the responsiveness of all personnel assigned to assemble and dispatch field teams. PAGE 22 OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT EPIP- NUCLEAR PLANT CENTER (OSC) ATTACHMENT P (Page 1 of 1) OSC CLERK CHECKLIST NOTE: Maintain a log of activities and communications. Initials/Time Initial OSC Activation

     /                 Swipe into Accountability Card Reader.
     /                 Sign the Accountability Log Sheet.
     /                 Sign in on the staffing board.

Operational Responsibilities Maintain a log for the OSC Director. Provide clerical support for the OSC and OSC Staging Area. PAGE 23 OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT CENTER (OSC) EPIP-7 NUCLEAR PLANT ATTACHMENT Q (Page 1 of 1) ATTACHMENT Q (Page 1 of 1) STATUS BOARD WRITER CHECKLIST Initials/Time Initial OSC Activation

     /                 Swipe into Accountability Card Reader.
     /                 Sign OSC Accountability Log Sheet.
     /                 Sign in on Staffing Board.

Operational Responsibilities Maintain the following Status Boards (As assigned)

     "* Affected Unit
     "* Equipment Problems
     "* Team Tracking Obtain up-to-date plant data from the OSC Operations Communicator.

PAGE 24 OF 29 REVISION 18A

ACTIVATION AND OPERATION T'Th7BROWNS FERRY OF THE OPERATIONS SUPPORT EPIP-I NUCLEAR PLANT CENTER (OSC) ATTACHMENT R (Page 1 of 1) OSC TEAM MANAGER NOTE: Maintain a log of activities and communications. Initials/Time Initial OSC Activation

     /                  Swipe into Accountability Card Reader.
     /                  Sign the Accountability Log Sheet.
     /                  Sign in on Staffing Board.
     /                  Track any team(s) dispatched prior to the OSC activation.

I Establish communications with the TSC maintenance manager (#3766). Operational Responsibilities Initiate team Tracking Forms as requested by TSC Maintenance manager and forward to Assistant OSC Director upon acknowledgment by the OSC director. Ensure that the team tracking board is consistent and accurate and that the information is being transferred in a timely manner to the TSC team tracking board writer. PAGE 25 OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT -NUCLEAR PLANT CENTER (OSC) ATTACHMENT S (Page 1 of 1) MATERIALS COORDINATOR NOTE: Maintain a log of activities and communications. Initials/Time Initial OSC Activation

     /                  Swipe into Accountability Card Reader.
     /                  Sign the Accountability Log Sheet.
     /                  Sign in on Staffing Board.
     /                  Track activities conducted prior to the OSC activation and report to director.
     /                  Establish communications with Power Stores representative at Extension
                        #2608.

Operational Responsibilities Provide and coordinate material support resources necessary to support the Operation Support Center. Provide technical assistance as applicable in regards to material acquisition, substitution, and availability. PAGE 26 OF 29 REVISION 18A

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT Ir -7 NUCLEAR PLANT CENTER (OSC) ATTACHMENT T (Page 1 of 1) OSC PLANNERS CHECKLIST NOTE: Maintain a log of activities and communications. Initials/Time Initial OSC Activation

     /                 Swipe into Accountability Card Reader.
     /                  Sign the Accountability Log Sheet.
     /                  Sign in on the staffing board.

Operational Responsibilities Provide support to the OSC Staff as applicable. Support in the Planning and briefing preparation for OSC Team Complete and update "Team Tracking Forms" for teams you are assigned PAGE 27 OF 29 REVISION 18A

ACTIVATION AND OPERATION -liTTI BROWNS FERRY OF THE OPERATIONS SUPPORT EIiri -i NUCLEAR PLANT CENTER (OSC) ATTACHMENT U (Page 1 of 1) OSC DOCUMENT CONTROL NOTE: Maintain a log of activities and communications. Initials/Time Initial OSC Activation

     /                  Swipe into Accountability Card Reader.
     /                  Sign the Accountability Log Sheet.
     /                  Sign in on the staffing board.

Operational Responsibilities Provide document control support for the OSC and OSC Staging Area. Ensure that documents/drawings are maintained as utilized by OSC members. Ensure timely availability of procedures and drawings as requested by OSC members. PAGE 28 OF 29 REVISION 18A I

ACTIVATION AND OPERATION BROWNS FERRY OF THE OPERATIONS SUPPORT EPIP-7 NUCLEAR PLANT CENTER (OSC) ATTACHMENT V (Page I of 1) OSC CONFIGURATION 0 Chernistry Radcon (Di 2(V C) 8 a) uJ a) 8 13 t3 T) 2 (V 2 (V E GD 0 I-Assislant os3c OSC Dir. Dire tr Celerk G ©D eAn* Status Boan lo) G D- I (m PAGE 29 OF 29 REVISION 18A I

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-8 PERSONAL ACCOUNTABILITY AND EVACUATION REVISION IlA PREPARED BY: TIM CORNELIUS PHONE: 3666 RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS DATE: 03/08/2000 APPROVED BY: TIM CORNELIUS EFFECTIVE DATE: 03/09/2000 LEVEL OF USE: REFERENCE USE VALIDATION DATE: NOT REQUIRED QUALITY-RELATED

REVISION LOG Procedure Number: EPIP-8 Revision Number: 11A Pages Affected: All Pagination Pages: None Description of Change: EC-14 This change is being conducted to human factor the Revision Log, Description of Change and added clarification to revision log effecting rev. 11. EPIP 8 was revised to incorporate the information contained in SSP-1.52 for personnel accountability and evacuation. SSP 1.52 was canceled. EPIP 8 (rev. log) was changed to reflect the current revision level. Pages 1-8. was revised to include information concerning site accountability and evacuation that was contained in SSP 1.52. This is a general revision.

PERSONNEL ACCOUNTABILITY BROWNS FERRY AND EVACUATION EP.UIP - NUCLEAR PLANT 1.0 PURPOSE To describe the actions and responsibilities necessary to account for plant personnel inside the protected area during an emergency situation. 2.0 SCOPE This procedure outlines the responsibilities of emergency responders during an accountability and/or evacuation situation of Browns Ferry. 3.0 INSTRUCTIONS 3.1 General 3.1.1 All individuals entering the protected area shall:

               "* Swipe their badge into the Entry Card Reader.
               "* Enter the protected area in accordance with security procedures.

3.1.2 All individuals leaving the protected area shall:

               "* Swipe their badge into the Exit Card Reader in the appropriate exit portals.
               "* Exit the protected area in accordance with security procedures.

NOTE: These "Entry and Exit" Card Readers function as accountability card readers. 3.2 Particular Area Evacuation 3.2.1 The Public Address (PA) System will be used to announce the evacuation of a particular area of the plant. 3.2.2 Personnel in the affected areas upon hearing the PA announcement shall do the following:

               "* If working in a contaminated zone, exit the zone in accordance with Radiological Control (RADCON) procedures, unless instructed otherwise by RADCON.
               "* Exit the affected area in an orderly manner.
               "* Personnel not in the affected area should continue assigned task if not instructed otherwise.

NOTE: Personnel should not enter the affected area until the "All Clear" has been announced or directed through emergency response processes. PAGE I OF 8 REVISION 11A

PERSONNEL ACCOUNTABILITY BROWNS FERRY AND EVACUATION EPIP-8 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.2 Particular Area Evacuation (continued) 3.2.3 Shift Manager/Site Emergency Director (SED) shall: Make a PublicAddress (PA) announcement similar to - "Attention All Personnel, conditions in the (areato be evacuated) warrant an evacuation of the area. Leave the (area to be evacuated)immediately. 3.3 Site Assembly and Accountability 3.3.1 General 3.3.1.1 A 3 minute undulating siren (Assembly and Accountability Siren) will sound when an emergency condition exists requiring assembly and accountability of site personnel. 3.3.1.2 Non-Emergency Responders, upon hearing the Assembly and Accountability Siren, shall proceed immediately to their designated assembly areas as listed on Attachment A. Upon arriving at the assembly area, swipe your badge into the Accountability Card Reader and remain in the designated assembly area until released by the Site Emergency Director (SED) or the Plant Evacuation Alarm is sounded. See step 3.4.1 for instructions regarding Plant Evacuation. 3.3.1.3 Emergency Responders, upon hearing the Assembly and Accountability Siren, shall proceed immediately to their assigned Emergency Response Facility as listed on Attachment B. Upon arriving at the Emergency Facility swipe your badge into the Accountability Card Reader and Sign the Accountability Roster Form, Attachment C. 3.3.1.4 Visitors remain with escorts and swipe your badge into the appropriate Accountability Card Reader. 3.3.1.5 If you cannot reach your designated assembly area within 20 minutes, go to the nearest Accountability Card Reader and swipe your badge. See Attachment A and B. 3.3.1.6 If the Accountability Card Reader will not accept your badge, or if your cannot access a reader, call Nuclear Security at extension 3238 or 2219. PAGE 2 OF 8 REVISION 11A

PERSONNEL ACCOUNTABILITY 8 BROWNS FERRY AND EVACUATION EPIP-r NUCLEARPLANT 3.0 INSTRUCTIONS (CONTINUED) 3.3 Site Assembly and Accountability (continued) 3.3.2 When required the Shift Manager/SED shall: 3.3.2.1 Activate the Assembly and Accountability Alarm (3-minute undulating siren). Reactivate as necessary. 3.3.2.2 Use guidelines listed below to evacuate personnel from designated assembly areas to alternate areas.

                         "* radiation dose rate > 2 mrem/hr
                         ", airborne radioactivity > 10CFR 20.1201 DAC Limits 3.3.2.3 Make PA announcement, use Emergency Dispatches and or instruct Nuclear Security to inform the affected personnel.

3.2.3 Upon the activation of Site Assembly and Accountability Nuclear Security (NS) shall: 3.3.3.1 Restrict access to the Protected Area to personnel listed on the Emergency Response Access List or as authorized by the SED. 3.3.3.2 Dispatch officers to search areas on TVA properly outside the protected area. NOTE: For any person found on the owner controlled area and are not TVA personnel or contractors, NS will obtain name, address, phone number. RADCON will survey the individuals if conditions warrant. 3.3.3.3 Report results of accountability within 30-minutes after the assembly and accountability alarm has sounded. 3.3.3.4 If necessary, form a search team to locate missing individual(s) 15-minutes after accountability deadline has passed. 3.3.3.5 Each team will be accompanied by a RADCON technician. 3.3.3.6 Provide assistance to the SED/Shift Manager in movement and informing personnel. PAGE 3 OF 8 REVISION 11A

PERSONNEL ACCOUNTABILITY BROWNS FERRY AND EVACUATION EPIP-8 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.3 Site Assembly and Accountability (continued) 3.3.4 Upon the activation of Site Assembly and Accountability RADCON shall: 3.3.4.1 Survey all assembly areas (including the Emergency Centers), if radiological conditions warrant. 3.3.4.2 Support any search teams. 3.4 Site Evacuation 3.4.1 General 3.4.1.1 A 3-minute steady siren (Site Evacuation Siren) will sound when an emergency condition exists requiring a plant evacuation. 3.4.1.2 Non-Emergency Responders, proceed to the appropriate protected area exit portal. Swipe you badge into the Exit Card Reader or as instructed by Nuclear Security. Exit the protected area in accordance with security procedures. Proceed to your vehicle and evacuate from the site to your place of residence. Follow all guidance at this time of state and local authorities, where applicable. 3.4.1.3 Emergency Responders, proceed to your assigned emergency response facility. Sign the Accountability Roster, Attachment C, if not already completed. Swipe your badge into the Accountability Card reader if not already completed. 3.4.1.4 Visitors remain with escorts and swipe your badge into the appropriate Exit Card Reader or as instructed by Nuclear Security. 3.4.1.5 If the Exit Card Reader will not accept your badge, call Nuclear Security at extension 3238 or 2219. PAGE 4 OF 8 REVISION I1A

PERSONNEL ACCOUNTABILITY BROWNS FERRY AND EVACUATION EPIP-8 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.4 Site Evacuation (continued) 3.4.2 When required the Shift Manager/SED shall: 3.4.2.1 Activate the Site Evacuation Alarm (3-Minute steady siren). 3.4.2.2 Reactivate as necessary. 3.4.2.3 Notify the Central Emergency Control Center - (If not staffed Notify the Operation Duty Specialist). 3.4.3 Upon the activation of Site Evacuation Nuclear Security shall: 3.4.3.1 Close site access points. 3.4.3.2 Assist in movement of traffic and personnel. 3.4.4 Upon the activation of Site Evacuation RADCON shall: 3.4.4.1 If radiological condition warrants, set up control check points which coincide with NS access control points. 3.4.4.2 Ensure personnel and vehicles are decontaminated before being released from the owner controlled area. 3.4.4.3 If necessary, provide decontamination support to the Muscle Shoals Service Shop #4. (Offsite decontamination facility) 4.0 ATTACHMENTS Attachment A - Non-Emergency Responder Assembly Locations Attachment B - Emergency Responder Emergency Facility/Assembly Locations Attachment C - Accountability Roster Form PAGE 5 OF 8 REVISION 11A

PERSONNEL ACCOUNTABILITY BROWNS FERRY AND EVACUATION EPIP-8 NUCLEAR PLANT ATTACHMENT A Page 1 of I NON EMERGENCY RESPONDERS ASSEMBLY LOCATIONS Location Reporting Organizations Maintenance Shop Maintenance Production personnel (except for IM) Maintenance Program Support personnel Work Control Center personnel Plant Assembly Room Plant Manager's office staff Operations office staff Maintenance office staff RADCON office staff Work Control/Outage personnel Maintenance Building Instrument Mechanic (IM) Shop personnel Maintenance Support personnel Plant Engineering Building Site Engineering - System Engineering personnel Radwaste personnel West Access Portal Exit All other organizations not listed and the west portal is your regular entry point. East Access Portal Exit All other organizations not listed and the west portal is your regular entry point. NOTE: If your organization is not listed on this attachment and your are exiting, utilizing the east or west portal then swipe your badge into the Exit Card Reader at the portal and go inside one of the following Buildings

Administration Building
Contractor Facility Complex
BFN Training and Visitor Center
Materials Procurement Complex
Modifications Fabrication Shop
Modifications Administration Building PAGE 6 OF 8 REVISION I IA

PERSONNEL ACCOUNTABILITY 8 BROWNS FERRY AND EVACUATION EPIP NUCLEARPLANT APPENDIX B Page 1 of 1 EMERGENCY RESPONDERS EMERGENCY FACILITY/ASSEMBLY LOCATIONS Location Reporting Organizations Unit 1 and 2 Control Rooms All operations personnel in Control Bays, Unit 1/2 Unit 3 Control Room All operations personnel in Control Bays, Unit 3 Technical Support Center TSC staff Operations Support Center OSC staff Document Control and Records Management, personnel from plant office building information center. OSC Staging Area Maintenance personnel assigned to staging area Fire Protection ESTs Tool Room personnel Radiological Control RADCON Field Operations personnel (RADCON) Radiochemistry Laboratory Chemistry Control personnel PAGE 7 OF 8 REVISION 11A

PERSONNEL ACCOUNTABILITY BROWNS FERRY AND EVACUATION EPIP-8 NUCLEAR PLANT APPENDIX C APPENDIX C Page 1 of 1 ACCOUNTABILITY ROSTER Emergency Response Facility Supervisor In Charge Ext. SSN Name (Last, First MI) ERO Position Filled (Staging Area Personnel, OSC Board Writer, etc.) t I. t I. I I. I I. i i. i i. i i. I I. I I. I I. i i.

I.

I I. LAST PAGE PAGE 8 OF 8 REVISION 11A

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-11 SECURITY AND ACCESS CONTROL REVISION 8A PREPARED BY: TIM CORNELIUS PHONE: 2038 RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS DATE: 03-08-2000 APPROVED BY: TIM CORNELIUS EFFECTIVE DATE: 03-09-2000 LEVEL OF USE: REFERENCE USE VALIDATION DATE: NOT REQUIRED QUALITY-RELATED

REVISION LOG Procedure Number: EPIP-I1 Revision Number: 8A Pages Affected: All Pagination Pages: NONE Description of Change: EC-1 1 This change is being conducted to human factor the Revision Log, Description of Change and added clarification to revision log effecting rev. 8. EPIP 11 was revised re-format procedure and remove Security Checklist items, placing them into EPIP-6. EPIP 11 (rev. log) was changed to reflect the current revision level. Pages 1-2. revised Shift Operations Supervisor title to Shift Manager and Shift Operations Supervisor Clerk to Unit 1 Unit Operator. Additionally incorporated checklist items from procedure to EPIP-6, Activation and Operation of the Technical Support Center. This is a general revision to EPIP- 11.

SECURITY AND ACCESS BROWNS FERRY CONTROL EPIP- 1I NUCLEAR PLANT SECURITY AND ACCESS CONTROL 1.0 PURPOSE To provide access control for the Browns Ferry Site during a Radiological Emergency. 2.0 SCOPE Provide for implementation of a predetermined security and access control plan for an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY. 3.0 INSTRUCTIONS 3.1 General 3.1.1 NS Shift Supervisor, when notified by the Shift Manager or Unit 1 Unit Operator that an emergency has been declared will report immediately to the Technical Support Center (TSC) and fill the position of Nuclear Security Manager until relieved by the on-call manager. 3.1.2 During an Alert, Site Area Emergency, General Emergency or as directed by the Site Emergency Director, Nuclear Security will:

               "* Restrict access to the protected area except for personnel whose name appears on the Emergency Response List or as authorized by the SED.
               "* Close all site access control points which control personnel entering or leaving the site. No personnel except those pre-authorized by the Emergency Response List or as authorized by the SED will be allowed to enter.
               "* Close all site access control points which control personnel entering or leaving the site.
               "* Conduct periodic radio or telephone checks with Nuclear Security Shift Supervisor or his designee, by all officers assigned to a post.

3.1.3 All emergency vehicles and personnel including the RADCON monitoring van will be permitted immediate access. 3.1.4 Following the termination of the emergency, Nuclear Security will be relieved from emergency duties by the Site Emergency Director or the Shift Supervisor at which time, officers will resume their normal duties. PAGE 1 OF 2 REVISION 8A

SECURITY AND ACCESS BROWNS FERRY CONTROL EPIP- 11 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.2 Site Area Emergency/General Emergency 3.2.1 When a Site Area Emergency or General Emergency has been declared no personnel except those who have (1) been authorized by Site Emergency Director, (2) accounted for by NS, and (3) monitored by RADCON if radiological conditions exist will be allowed to leave the site. 3.2.2 After Site Area Emergency or General Emergency has been declared site egress will be restricted and authorized only after RADCON completes a survey or as granted by the Site Emergency Director through the NS representative in the TSC. 3.3 Accountability and Evacuation 3.2.1 If Accountability or Evacuation is conducted, security shall monitor the processes and report information in accordance with EPIP-8, "Personnel Accountability and Evacuation Procedure." 4.0 ATTACHMENTS None LAST PAGE PAGE 2 OF 2 REVISION 8A

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-15 EMERGENCY EXPOSURE REVISION 6A PREPARED BY: T. W. CORNELIUS PHONE: 2038 RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS DATE: 03-08-2000 APPROVED BY: TIM CORNELIUS EFFECTIVE DATE: 03-09-2000 LEVEL OF USE: REFERENCE USE VALIDATION DATE: NOT REQUIRED QUALITY-RELATED

REVISION LOG Procedure Number: EPIP-15 Revision Number: 6A Pages Affected: 2 Pagination Pages: NONE Description of Change: EC-08 This change is being conducted to human factor the Revision Log, Description of Change and added clarification to revision log effecting rev. 6. EPIP 15 was revised to change a procedural reference. The revision was considered as a non-intent change. EPIP 15 (rev. log) was changed to reflect the current revision level. Pages 2, revised Radiological Control Instruction 3.1 procedure title to Standard Programs and Processes (SPP) 5.10.

EMERGENCY BROWNS FERRY EXPOSURE EPIP- 15 NuCLEAR PLANT 1.0 PURPOSE This procedure provides guidance for authorizations of personnel dose limits under emergency conditions, consistent with EPA-400, "Manual of Protection Action Guides and Protective Actions for Nuclear Incidents". 2.0 SCOPE These limits apply only to emergency exposure authorizations and not to spontaneous reactions by individuals attempting to mitigate an emergency situation. This procedure provides guidance for the approval and administration of radiation exposures received during emergencies in excess of 10 CFR 20.1201 entitled "Occupational Dose Limits for Adults." This procedure does not provide direction for the approval and administration for exposures received during other activities involving radiation dose to individuals. Note: For the purposes of this implementing procedure, radiation exposure as expressed in units of R/hr and submits, thereof, are equivalent to dose (rad) and dose equivalent (rem) based on ANSI N 13.11 development and terminology. Any acute dose greater that 10 rem is generally denoted in units of rad, since that level is considered as the accident range of personnel exposure. Any dose less than that level is considered as the protective range of personnel exposure. For purposes of this procedure the assumptions of 1 rad = 1 rem is assumed for all levels of exposure. 3.0 INSTRUCTIONS 3.1 RADCON Group The Radiological Control group is responsible for performing radiological surveys or other assessments to estimate the radiation doses. 3.2 SITE EMERGENCY DIRECTOR 3.2.1 The Site Emergency Director (SED), shall provide authorization for all emergency radiation doses that may exceed 10 CFR 20.1201 entitled "Occupational Dose Limits for Adults." 3.2.2 The documentation of authorization may be accomplished by log entry. The entry should include the task for which the approval was authorized. PAGE 1 OF 7 REVISION 6A

EMERGENCY BROWNS FERRY EXPOSURE Iir-15 NUCLEARIPLANT 3.3 GUIDANCE FOR ALL EMERGENCY DOSE LIMITS 3.3.1 The exposure of personnel during emergency operations shall be maintained As Low As Reasonably Achievable (ALARA). 3.3.2 Internal exposure should be minimized by the use of respiratory protection equipment. Respiratory Protection Factors are provided Standard Programs and Processes (SPP) 5.10. If a projected dose to the thyroid is expected to exceed 10 rem during emergency conditions, Potassium Iodine (KI) should be issued. EPIP 14 contains information regarding issuance and precautions for the use of KI. 3.3.3 Protective clothing should be used to minimize personnel contamination. 3.3.4 Personnel undertaking an emergency operation in which the dose will exceed 10 CFR 20.1201 entitled "Occupational Dose Limits for Adults" limits shall do so on a voluntary basis and with full awareness of the risks involved, including the numerical levels of dose at which acute effects of radiation will be incurred and numerical estimates of the risk of delayed effects as depicted on Attachment A. Acknowledgment of this decision shall be documented on Attachment B of this procedure by the individual involved in this activity. 3.3.6 Other factors being equal, older volunteers should be selected first. 3.3.7 Other factors being equal, selection of female volunteers capable of reproduction should be avoided. 3.3.8 Exposures under these conditions shall be limited to a once in a lifetime. Personnel who have received previous accident or emergency exposures in excess of 25 rem TEDE shall not participate in further emergency exposure assignments. 3.3.9 Personnel shall not enter any area where dose rates are unknown or not measurable with instruments and dosimetry immediately available. PAGE 2 OF 7 REVISION 6A

EMERGENCY BROWNS FERRY EXPOSURE EPIP-15 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.3.9 Until isotopic assessments of airborne radioactivity are available, and administrative correction factor of 2 should be used to estimate TEDE exposures in airborne activity areas: Estimated TEDE = Dosimeter Reading X 2 Note: The above value corresponds to the ratio of external (measured) dose rate to estimate TEDE dose, in accordance with default values in TVA's Dose Assessment model. When accident specific nuclide assessment are available, more definitive dose assessments should be performed to adjust the correction factors. 3.4 DOSE LIMITS FOR WORKERS DURING EMERGENCIES 3.4.1 Doses to all workers during emergencies should, to the extent practicable be limited to 10 CFR 20.1201 limits. There are however, some emergency situations for which higher emergency exposures may be justified. Whenever these situations are justified and ALARA considerations have been evaluated the following limits can be administered. 3.4.2 Dose Limits for the Protection of Valuable Property DOSE RECEPTOR LIMIT (REM) WHOLE BODY (TEDE) 10 LENS OF THE EYE 30 ALL OTHER ORGANS 100 PAGE 3 OF 7 REVISION 6A

EMERGENCY BROWNS FERRY EXPOSURE EPIP- 15 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.4 DOSE LIMITS FOR WORKERS DURING EMERGENCIES (CONTINUED) 3.4.3 Dose Limits for Lifesaving Activities and the Protection of Large Populations. DOSE RECEPTOR LIMIT (REM) WHOLE BODY (TEDE) 25 LENS OF THE EYE 75 ALL OTHER ORGANS 250 3.4.4 Dose Limits Greater Than 25 Rem for Lifesaving Activities or to Avoid Extensive Exposures to Large Populations. 3.4.4.1 Situations may occur in which a dose in excess of 25 rem would be required in order to carry out lifesaving operations or to avoid extensive exposures to large populations. It is not possible to prejudge the risk that one person should be allowed to take to save the life of others. 3.4.4.2 Personnel made knowledgeable of the risks involved with radiation exposures through training or briefings utilizing the information contained within Attachment A and selected on a voluntary basis may be allowed to exceed the 25 rem emergency dose exposure limit for the purpose of lifesaving activities or to avoid extensive exposures to large populations. 3.4.4.3 Acknowledgment of this decision shall be documented on Attachment B of this procedure by the individual involved in this activity. PAGE 4 OF 7 REVISION 6A

EMERGENCY BROWNS FERRY EXPOSURE EPIP- 15 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.5 POST-EXPOSURE ACTIVITIES 3.5.1 Personnel receiving emergency doses should be restricted from further occupational exposures pending the outcome of exposure evaluations, and if necessary, medical surveillance. 3.5.2 Radcon shall conduct post exposure dose assessments for exposed individuals, with particular attention to determining the adequacy of administrative dosimeter correction factors for TEDE doses resulting from internal and external exposures. 3.5.3 Any exposures above 5 rem TEDE shall be reported to a TVA physician. It is the responsibility of the physician to determine appropriate medical evaluations and required care. Cross reference guidance in EPIP-10. 3.5.4 Any emergency exposures shall be reported to the Radcon Superintendent as soon as possible. PAGE 5 OF 7 REVISION 6A

EMERGENCY BROWNS FERRY EXPOSURE EPIP- 1 NUCLEAR PLANT ATTACHMENT A (Page 1 of 1) EPA EMERGENCY EXPOSURE RISK INFORMATION I. Health Effects Associated with Whole Body Adsorbed Doses Received Within A Few Hours'. Whole Body Early Fatalities2 Whole Body Prodromal Effects' Absorbed Dose (rad) (Percent) Adsorbed Dose (rad) (Percent) 140 5 50 2 200 15 100 15 300 50 150 50 400 85 200 85 460 95 250 98

   'Risks will be lower for protracted exposure periods.

2 Supportive medical treatment may increase the dose at which these frequencies occur by approximately 50 percent. 3Forewarning symptoms of more serious health effects associated with large doses of radiation. II. Approximate Cancer Risk to Average Individuals from 25 rem Effective Dose Equivalent Delivered Promptly. Age at Exposure (years) Risk of Premature Death Average years of life lost if (deaths per 1,000 persons premature death occurs exposed) (Years) 20 to 30 9.1 24 30 to 40 7.2 19 40 to 50 5.3 15 50 to 60 3.5 11 Note: Tables referenced from the Environmental Protection Agency's "manual of Protective Action Guides and Protective Actions for Nuclear Incidents", (EPA-400), October 15, 1991, page 2-18. PAGE 6 OF 7 REVISION 6A

EMERGENCY BROWNS FERRY EXPOSURE EPIP-15 NUCLEAR PLANT ATTACHMENT B (Page 1 of 1) GREATER THAN 10 CFR 20.1201 EXPOSURE LIMIT ACKNOWLEDGMENT READ THE FOLLOWING STATEMENT BEFORE SIGNING THIS FORM: I acknowledge by signature on this form that I am volunteering for exposures in excess 10 CFR 20.1201 limits and that I have been made aware through training or a briefing of the risks involved through a review of the material presented on Attachment A of the procedure. The persons listed below have acknowledged and volunteered to receive Dose Limits in excess of 10 CFR 20.1201 limits. Authorization is required by the Site Emergency Director to administer any emergency exposure limit. This form does not represent the authorization of the Site Emergency Director. Name SSN Signature Time/Date (Please print Last, First. MI)

2. /

3. /

"4. /

5. /

6. /

7. /

8. /

9. /

10. - - /

11. - - /

12. - /

13. - - /

14 15 / 16 / 17 / 18 / 19 /

20 LAST PAGE PAGE 7 OF 7 REVISION 6A

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-17 Emergency Equipment and Supplies (Inventory and Operability Procedure) REVISION 23A PREPARED BY: TIM CORNELIUS PHONE: 2038 RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS DATE: 03/08/2000 APPROVED BY: TIM CORNELIUS EFFECTIVE DATE: 03/09/2000 LEVEL OF USE: REFERENCE USE VALIDATION DATE: NOT REQUIRED QUALITY-RELATED

REVISION LOG PROCEDURE NUMBER: EPIP-17 REVISION NUMBER: 23A PAGES AFFECTED: 3,7,8,20-23,27-28,35 DESCRIPTION OF CHANGES: EC-26 This change is being conducted to human factor the Revision Log, Description of Change and added clarification to revision log effecting rev. 23. EPIP 17 was revised in support of the site standardization process, to revise the agreement hospital and off site decontamination facility inventories, and revise procedure references. EPIP 17 (rev. log) was changed to reflect the current revision level. Page 3. was revised to change procedure title SSP 3.14 to SPP 3.1. Page 3. revised section 3.3.1-3.3.3, to remove reference to the Inventory Deficiency/Resolution Form. Page 7. removed reference SSP 1.52, requirements incorporated in EPIP-17. Page 8. added drawing and/or procedure inventory information in support of the TSC inventory list. Pages 20-23, revised Technical Support Center inventories, incorporating procedures and drawing listing. Pages 27-28, revised hospital inventories. Page 35, revised off-site decontamination facility inventory.,. Page 36, deleted Inventory Deficiency/Resolution Form.

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP- 17 NUCLEAR PLANT Operability Procedure) 1.0 PURPOSE The purpose of this procedure is to provide a listing of equipment and supplies, along with storage locations, available for emergency response during the activation of the Radiological Emergency Plan and Emergency Plan Implementing Procedures. This procedure will ensure the availability and readiness of emergency equipment at BFN through the performance of periodic inventories and operability checks. 2.0 SCOPE This procedure provides information pertaining to equipment and supplies available for use during emergencies at the Browns Ferry Nuclear Plant. This procedure additionally provides instructions to personnel performing checks of equipment and supplies in regards to frequencies, responsibilities, acceptance and record management. 3.0 INSTRUCTIONS 3.1 Responsibilities and Frequency 3.1.1 Inventories and operability checks shall be conducted in accordance with frequencies provided in Attachment 1. In addition with this frequency schedule, special inventories shall be required when items or equipment maintained by this procedure have been affected by a drill, exercise or training. This special inventory shall be performed at a reasonable time following the activity. This special inventory may also be used as the routine inventory. 3.1.2 Conduct of inventories and operability checks shall be the responsibility of the organization provided in Attachment 1 3.1.3 The Manager, Emergency Preparedness (EP), is responsible for ensuring the overall state of readiness of supplies and equipment identified in the procedure. PAGE I OF 35 REVISION 23A I

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and Operability Procedure) EPIP- 17 NUCLEAR PLANT 3.1 Responsibilities and Frequency (Continued) 3.1.4 Individuals performing work within this procedure shall be familiar with all procedural guidance and testing requirements applicable to their assigned task. By initialing the item listing on the task form, the individual performing tasks within this procedure is responsible for ensuring the item is present, in the specified quantity and functional for its intended purpose. 3.1.5 Equipment inventories and operability of the site environmental monitoring vans shall be conducted in accordance with CECC-EPIP-9. Routine and special inventory/operability checks involving the site environmental monitoring vans are the responsibility of RADCON. Training personnel will be responsible for inventory and operability checks following training activities. 3.1.6 Personnel performing inventories and operability checks shall ensure that upon completion of task, seals or locking devices are in place to ensure the integrity of the equipment or supplies. Areas requiring these measures are listed on Attachment 2. 3.1.7 Personnel conducting inventories and operability checks in accordance with this instruction will ensure that the latest revision of this procedure is utilized. 3.1.8 Definition for annual and quarterly shall be as noted in the Radiological Emergency Plan. Terms such as once every calendar quarter or month invokes that the task should be conducted within the timeframe of a physical quarter or month. 3.2 Records Management 3.2.1 Personnel conducting tasks within this procedure will provide legible documentation of results on applicable forms. 3.2.2 Upon completion of applicable task(s), originals with signatures, shall be forwarded to the Manager, EP for review and concurrence. Originals should be forwarded as soon as possible, but no later than the end of the current quarter. PAGE 2 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP-17 NUCLEAR PLANT Operability Procedure) 3.1 Records Management(Continued) 3.2.3 The Manager, EP shall review all task forms and concur with results by signature. 3.2.4 EP shall maintain all procedure records for a minimum retention period of 1 year. These records are considered NON-QA. 3.3 Task Deficiencies Deficient items as discussed within this procedure do not relate to those described in SPP 3.1, "Corrective Action Program". Any deficient item identified within this procedure which does meet the requirements of SPP 3.1 shall be documented in accordance with SPP 3.1. 3.3.1 All task deficiencies shall be noted on the applicable task form. 3.3.2 All task deficiencies shall be corrected as soon as possible. If circumstances do not allow prompt correction the Manager, EP, shall be notified. When deficiencies have been corrected, the applicable task form shall be signed. 3.3.3 For failures of the NRC FTS-2000, Emergency Telecommunications System (ETS) deficiencies will be reported immediately in accordance with the instructions provided on the applicable task form. PAGE 3 OF 35 REVISION 23A I

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP- 17 NUCLEAR PLANT Operability Procedure) 3.4 Specific Instructions for Inventories, Operability Checks, Administrative Checks and Reviews 3.4.1 SCBA's Self Contained Breathing Apparatus (SCBA) units are inventoried per this procedure for inventory purposes only. Inspections/equipment maintenance and operability checks are conducted in accordance with applicable Fire Protection Instructions. 3.4.2 Radiological Control Instrumentation 3.4.2.1 On-Site - Survey instrumentation, counting equipment, air samplers, dosimeters and other radiological control equipment listed on applicable forms are for inventory purposes only. Instrument readiness is a process of the on-site radiological control organization. As a function of this inventory calibration due dates and instrumentation physical appearance will be observed to help ensure operability. 3.4.2.2 Off-Site - Survey instrumentation and dosimeters referenced as offsite by this procedure are considered those maintained by EP at the BFN - Agreement Hospitals. Survey instrumentation operability shall be maintained by the Western Area Radiological Laboratory, Instrumentation Section. Electronic dosimeters shall be exchanged according to response dates not to exceed calibration due dates. Electronic dosimetry should be observed for physical damage to help ensure operability. 3.4.3 Telecommunications 3.4.3.1 Nuclear Regulatory Commission - Emergency Notification System telephones. Lift the receiver and listen for a dial tone; after receiving a dial tone, dial the first number listed on the sticker located on the telephone instrument, using all 10 digits. If the first number is busy, proceed on with the second, etc. Confirm acceptable voice quality between parties conducting the test with all extensions off hook. Request a call-back be made to single phone and confirm acceptable voice quality. PAGE 4 OF 35 REVISION 23A I

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP- 17 NUCLEAR PLANT Operability Procedure) 3.4 Specific Instructions for Inventories, Operability Checks, Administrative Checks and Reviews (Continued) 3.4.3 Telecommunications (Continued) 3.4.3.2 All other telecommunications tested by this procedure. Conduct the test by lifting receiver and listen for a dial tone; after receiving a dial tone, place a local call and request a call-back be made. Confirm acceptable voice quality between telephones being tested. 3.4.4 TSC & OSC Intercom System Activate the intercom system in the TSC or OSC. Assign someone to monitor the test in the applicable locations. The TSC PA services the TSC, OSC and the Technical Assessment Team Area while the OSC PA services the OSC and OSC Staging Area. 3.4.5 EP Clocks Verify the correct operation of the TSC and the OSC clock by logging onto the clock program and making classification changes using the program. Return the system to the "No Classification" display. 3.4.6 Telecopiers (TSC & OSC) Verify operability by faxing a test message to another telecopier. Fax a test message back to the telecopier being tested. Check telecopier paper and physical condition. Ensure legibility of test messages. 3.4.7 Telephone Headsets Configure headset as applicable. Make call and confirm acceptable voice quality using the microphone and ear piece. 3.4.8 Ring down Phones (CECC/TSC, TAT/Plt Assessment, ODS/Control Rooms 1/2 & 3) Contact Corporate EP, have someone man the telephone in the CECC/ODS areas. Place a call to the CECC/ODS by lifting the receiver and receive a call form the CECC/ODS. PAGE 5 OF 35 REVISION 23A I

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP- 17 NUCLEAR PLANT Operability Procedure) 3.4 Specific Instructions for Inventories, Operability Checks. Administrative Checks and Reviews (Continued) 3.4.9 Meteorological (MET) Data Terminal and Printer Log onto the MET terminal. Request information in printed format. Verify that the printer has a supply of paper and that the print is legible. Log off system. 3.4.10 OSC Computer & Printer (OSC) Ensure the operability of the OSC computer by performing a task such as the activation of the word processing program. Check the response of the printer by requesting a print task via the computer, observe the action of the printer and print quality. 3.4.11 Copiers (TSC/OSC) Verify operability by copying a test message through the copier. Make copies using the sorter and verify legibility of copies, check copy paper supply and physical condition of copier. 3.4.12 Batteries All batteries shall be observed for physical damage such as indentations, leaking or rust. Batteries shall be tested to determine effectiveness by battery tester. Batteries sealed by the manufacture with an affixed label indicating a "shelf life" can be exempted from the individual battery test and accepted as is, as long as the current date does not exceed the "shelf life" date. Sealed batteries which have a "shelf life" date that is exceeded by the current date can be utilized, but must pass a battery test utilizing the battery testor. 3.4.13 Zetron Radio Control Units (RCU) Observe the unit to ensure that the time is displayed on the face plate. Verify that a green indicator light appears by one of the radio frequency selector buttons. The RCU should be tested by contacting a normally manned station. PAGE 6 OF 35 REVISION 23A I

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP-17 NUCLEAR PLANT Operability Procedure) 3.4 Specific Instructions for Inventories, Operability Checks, Administrative Checks and Reviews (Continued) 3.4.14 Hand Held 2-Way Radios Observe the unit for physical damage, then assemble one of the battery packs to the radio. Make radio contact with another hand held unit and verify acceptable voice quality. 3.4.15 Control Room Conference Bridge (101/102) Activate the "2-Way" bridge by dialing 101 on two plant telephones. Verify acceptable voice quality. Then test the "Listen Only" bridge by having someone activate the "2-Way" bridge by dialing 101 and someone activate the "Listen Only" bridge by dialing 102. Verify that the 102 is a "listen Only" system. 3.4.16 ERO Logbooks Utilize EPIP-6 or 7, position attachments to identify what ERO logbooks are intended for use in the applicable centers. Review the logbooks to unsure that each contains: (1)The latest revision of the applicable EPIP Attachment (2)An adequate supply of log sheets 3.4.17 Calculators, Flashlights, etc. Verify functional by observing anticipated response. 3.4.18 Emergency Procedure Telephone Number Review and Update Certain EPIP's and site procedures contain telephone numbers utilized by response personnel. Once per calendar quarter these numbers will be reviewed to ensure accuracy and updates are made as applicable. Changes will be conducted in accordance with site instructions. PAGE 7 OF 35 REVISION 23A I

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP- 17 NUCLEAR PLANT Operability Procedure) 3.4 Specific Instructions for Inventories. Operability Checks, Administrative Checks and Reviews (Continued) 3.4.19 Review of Emergency Procedures In accordance with the Radiological Emergency Plan (REP) the REP, REP Appendices and the EPIPs shall be reviewed annually. Changes concerning the REP will be forwarded to the corporate EP staff for consideration and implementation as applicable. Changes noted concerning the EPIPs shall be considered and if applicable revisions conducted in accordance with site instructions. 3.4.20 Emergency Response List The Emergency Response List contains individuals which are allowed access to the protected area during an emergency at BFNP for the purposes of serving within the emergency response organization. This listing is updated quarterly and copies distributed to Nuclear Security. The list will be issued on white paper and will not require PORC review. 3.4.21 Call-Out List This list contains active Emergency Responders by emergency positions. This list is utilized as a tool for the call-out of emergency responders. The list is updated quarterly and will be issued on white paper. The call out list will not be PORC reviewed. 3.4.22 Procedures and/or Drawings Controlled Procedures and/or drawings listed on applicable forms are for inventory purpose only. Procedure and Drawing inspection/maintenance process is conducted through applicable site instructions. PAGE 8 OF 35 REVISION 23A I

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP-17 NUCLEAR PLANT Operability Procedure) 4.0 ATTACHMENTS 4.1 Attachment 1 Inventory Matrix Table 4.2 Attachment 2 Locked/Sealed Cabinet Listing 4.3 Attachment 3 Radcon Emergency Equipment - Service Building 565' 4.4 Attachment 4 Radcon Emergency Equipment - Control Building 617" 4.5 Attachment 5 Staging Area C-Zone Dress-Out Clothing - Service Building 565' 4.6 Attachment 6 Emergency Use SCBA Inventory 4.7 Attachment 7 Maintenance Emergency Tool Box Inventory, Clean Tool Room - Service Building 565' 4.8 Attachment 8 Technical Support Center Inventory/Operability Check 4.9 Attachment 9 Operations Support Center Inventory/Operability Check 4.10 Attachment 10 OSC Staging Area Inventory/Operability Check 4.11 Attachment 11 Huntsville/Decatur General Hospital Inventory/Operability Checks 4.12 Attachment 12 ETS Communications Operability Checks 4.13 Attachment 13 Local Recovery Center Inventory/Operability Checks 4.14 Attachment 14 EP Quarterly Administrative Checks and Reviews 4.15 Attachment 15 EP Once per Calendar Quarter Administrative Checks and Reviews 4.16 Attachment 16 EP Annual Administrative Checks and Reviews 4.17 Attachment 17 Alternate Decontamination Facility 4.18 Attachment 18 Inventory-Operability Deficiency/Resolution Form PAGE 9 OF 35 REVISION 23A I

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP-17 NUCLEAR PLANT Operability Procedure) Attachment 1 Inventory Matrix Table EPIP Description Responsible Frequeicv Specific Attachment Section Instructions Number Provided 3 Radcon Emergency Equipment - Service Building 565' Radcon Once every calendar quarter Yes 4 Radcon Emergency Equipment - ControlBuilding 617' Radcon Once every calendar quarter Yes 5 Staging Area C-Zone Dress-OutClothing Service Building 565' Radcon Once every calendar quarter Yes 6 Emergency Use SCBA Inventory Operations Once every calendar quarter Yes 7 AMaintenance Emergency Tool Box Inventory, Clean Tool Room Maintenance Once every calendar quarter Service Building 8 Technical Support Center Inventoty/Operability Check EP Once every calendar quarter Yes 9 OperationsSupport Center Inventoiy/OperabilityCheck EP Once every calendar quarter Yes 10 OSC Staging Area Inventoiy/Operabiliiy Check EP Once every calendar quarter Yes 11 Huntsville/DecaturGeneralHospitalInventoty/Operability Checks EP Once every calendar quarter Yes 12 ENS Monthly Communications Operability Check EP Once monthly Yes 13 Local Recovery Center Inventoty/Operability Check EP Once every calendar quarter Yes 14 EP QuarterlyAdministrative Checks and Reviews EP Once quarterly Yes 15 EP Once per CalendarQuarterAdministrative Checks and Reviews EP Once every calendar quarter Yes 16 EP Annual Administrative Checks and Reviews EP Once annually Yes 17 Alternate DecontaminationFacility EP Once every calendar quarter PAGE 10 OF 35 REVISION 23A ( (

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP-17 NUCLEAR PLANT Operability Procedure) Attachment 2 Locked/Sealed Cabinet Listing Cabinet Location Equipment and Supplies Cabinet Technical Support Center Equipment and Supplies Cabinet Operations Support Center Equipment and Supplies Cabinet OSC Staging Area Equipment and Supplies Cabinet Local Recovery Center Equipment and Supplies Cabinet Service Building 565' (Radcon) Equipment and Supplies Cabinet Control Building 617' (Radcon) Equipment and Supplies Cabinet Decatur General "Emergency Room" (Hospital) Equipment and Supplies Cabinet Huntsville Hospital "Emergency Room" (Hospital) Equipment and Supplies Cabinet Power Service Shop # 4 (Alternate Decontamination Facility) TVA Muscle Shoals Reservation PAGE I11 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP-17 NUCLEAR PLANT Operability Procedure) Attachment 3 Radcon Emergency Equipment - Service Building 565' Location: Service Building 565' Behind Radiolo ical ControlLab Equipment QTY INV OPER INIT Radiolo2ical Survey Instrumentation High Range Survey Meters 2 Ion Chambers 4 GM Survey Meters (Friskers) 2 Neutron Survey Meter 1 Silver Zeolite Cartridges 10 Alpha Survey Meter 1 Mini-Scaler 1 Hi-Volume Air Sampler 2 Low-Volume Air Sampler 1 Shielded Detector "Pig" (Located in Radcon Area, Service Building, 565)' 1 Dosimetry Dosimetry Chargers 2 Whole Body TLD's 10 Multi-Badge Sets 10 Extremity TLD Badge Sets 30 0-200 mr Pocket Chambers 10 0-500 mr Pocket Chambers 10 0-1500 mr Pocket Chambers 10 0-5 R Pocket Chambers 10 0-20 R Pocket Chambers 10 0-100 R Pocket Chambers 10 Miscellaneous Calculator (Hand Held) 1 Y N Batteries (D-Cell) 16 Y N Log Book 1 Flashlights 8 Y N Box of Pens 1 Particulate Air Filters (Box) 2 Disc Smears (Box) 1 KI Tablets Expiration Date (Radcon 2000 Supply Cage)(Tablets) Si2natures: Supervisor, Radcon: Date: Manager, EP: _____Date: Retention Period is 12 months - - Non-QA Record PAGE 12 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP-17 NUCLEARPLANT Operability Procedure) Attachment 4 Radcon Emergency Equipment - Control Building 617' Location: ControlBuilding 61 7'MechanicalEquipment Room Equipment QTY INV OPER 1NIT Radiolo2ical Survey Instrumentation High Range Survey Meters 2 Ion Chambers 4 GM Survey Meters (Friskers) 2 Neutron Survey Meter 1 Silver Zeolite Cartridges 10 Alpha Survey Meter 1 Mini-Scaler 1 Hi-Volume Air Sampler 2 Low-Volume Air Sampler 1 Shielded Detector "Pig" 1 Dosimetry Dosimetry Chargers 2 Whole Body TLD's 10 Multi-Badge Sets 10 Extremity TLD Badge Sets 30 0-200 mr Pocket Chambers 10 0-500 mr Pocket Chambers 10 0-1500 mr Pocket Chambers 10 0-5 R Pocket Chambers 10 0-20 R Pocket Chambers 10 0-100 R Pocket Chambers 10 Miscellaneous Calculator (Hand Held) 1 Y N Batteries (D-Cell) 16 Y N Log Book 1 Flashlights 8 Y N Box of Pens I Particulate Air Filters (Box) 2 Disc Smears (Box) 1 Signatures: Supervisor, Radcon: Date: Manager, EP: Date: Retention Period is 12 months - - Non-QA Record PAGE 13 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and Operability Procedure) EPIP-17 NUCLEAR PLANT Attachment 5 Staging Area C-Zone Dress-Out Clothing - Service Building 565' Location: Service Building Column 6, G-line Hallway behindMechanicalMaintenance Offices Equipment QTY INV INIT Coveralls (Pairs) 40 Based upon size availability an alternate distribution may be acceptable at the discretion of the Radcon Supervisor and the EP Manager, noted by signature of completed form. Size 46 Size 48 10 Size 50 10 Size 52 5 Size 54 5 Size 58 5 5 Hood covers 25 Shoe Covers (Pairs) 25 Sur2eon Caps 25 Rubber Gloves (Pairs) 25 Booties (Pairs) 25 Cotton Glove Inserts (Pairs) 25 Maskin2 Tape (Rolls) 8 Supervisor, Radcon: Date: Signatures:I Manager, EP: _ _Date: Retention Period is 12 months - - Non-QA Record PAGE 14 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP-17 NUCLEAR PLANT Operability Procedure) Attachment 6 Emergency Use SCBA Inventory Description Location I QTY I INV [Nil INITI Unit 1 Control Room 5 Self Contained Breathing Apparatus Unit 2 Control Room 5 Self Contained Breathing Apparatus Unit 3 Control Room 5 Self Contained Breathing Apparatus Service Building 15 45 cu. ft. Air Cylinder Elevation 565, Service Shop Hallway Fire Equipment Cabinet 10 Self Contained Breathing Apparatus and 10 additional cylinders Turbine Building - 557'

                                                                                  *5 Self Contained Breathing Apparatus             4kV Shutdown Bd Rm "C" 3A Electrical Board Room           5 Self Contained Breathing Apparatus Fire Equipment Cabinet              4 Self Contained Breathing Apparatus Stairwell - RB 1&2 El. 565' Fire Equipment Cabinet             4 Self Contained Breathing Apparatus Stairwell - RB 2&3 El. 565' Radcon Emergency Cart              2 Self Contained Breathing Apparatus Fire Truck                         4 Self Contained Breathing Apparatus

_______________________________ _______________________ I ______ (*) Required for by 10 CFR 50 Appendix R Support Signatures: Supervisor, FIREPROTECTION: Date: Manager, EP: Date: Retention Period is 12 months - - Non-QA Record PAGE 15 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and Operability Procedure) EPIP-17 NUCLEAR PLANT Attachment 7 (Page 1 of 4) Maintenance Emergency Tool Box Inventory Electrical Tool Box Number of Boxes 2 -- Number of Boxes Inventoried Tool Description QTY INV INIT Pliers, Needle Nose, 6" 2 Pliers Diagonal, 6" 2 Tester, Circuit, 24.0" 2 Rule, Folding, Carpenters, Outside Reading, 6' 2 Pliers, Tongue & Groove, 10", #430 Channel Locks 2 Screwdriver, STD Tip, .25" Tip, X 8.0" Long 2 Screwdriver, STD Tip, .3 13" Tip, X 4.0" Long 2 Screwdriver, STD Tip,. 125" Tip, X 6.0" Long 2 Pliers, Lineman's, 9.0" 2 Screwdriver, STD Tip, .25" Tip, X 6.0" Long 2 Screwdriver, Phillips Tip, #2 Tip, 4" Blade 2 Screwdriver, Holding, .25" X 6" (Klein) 2 Wrench, Adjustable, 10.0" 2 PAGE 16 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP-17 NUCLEAR PLANT Operability Procedure) Attachment 7 (Page 2 of 4) Maintenance Emergency Tool Box Inventory I&C Tool Box Number of Boxes 2 -- Number of Boxes Inventoried __ Tool Description QTY INV 1NIT Pliers, Tongue & Groove, 9, #42 Channel Locks 1 Screwdriver, STD Tip, .25" Tip, X 6.0" Long 1 Screwdriver, Jewelers, Set of Six, .25"-. 100" Mfg. Starrett 1 _ Screwdriver, Holding, .25" X 6" (Klein) 1 Cord, Extension, 110 V 100' 1 Wrench Set, Hex Key (Allen), Folding, 0.050"-0.187" 1 Wrench, Ignition, Set 1 Wrench, Valve Wheel, Number 0, 8.0"X.50"X.656" 1 Socket, Set, 1/4" DR., SL/DW, 3/16" to 9/16" 1 Driver, Nut, Set, Fractional 1/4" to 1/2" 1 Wrench, Set, Hexkey, .028" to 5/8" 1 Cutter, Tube, .125" to .625" 1 Cutter, Tube, .125" to 1.125" 1 Pliers, Diagonals, 6" 1 Pliers, Lineman, 7" 1 Pliers, Needle Nose, 7" 1 Pliers, Tounge & Groove, #430 CL. 1 File, Half Round, 4" Smooth 1 File, Round, 6" Smooth 1 Puller, Fuse, Midget 1 Puller, Fuse, 1OOA-250V 1 Screwdriver, Philips, #1x3" 1 Screwdriver, Phillips, #2x4" 1 Screwdriver, Flat, 1/8x2.25" 1 Screwdriver, Flat, 1/4x6" 1 Screwdriver, Flat, 1/4x4" 1 Screwdriver, Flat, 5/16x6" 1 Screwdriver, holding, SM/pocket Clip 1 Screwdriver, Holding, 3/16x6" 1 Screwdriver, holding, 1/4x8" 1 Wrench, Adjustable, 4" 1 Wrench, Adjustable, 6" 1 Wrench, Adjustable, 8" 1 ___________________________________________________________ J __________ PAGE 17 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP- 17 NUCLEAR PLANT Operability Procedure) Attachment 7 (Page 3 of 4) Maintenance Emergency Tool Box Inventory I&C Tool Box (CONTINUED) Tool Description QTY INV INIT Wrench, Combo, 3/8" 1 Wrench, Combo, 7/16" 1 Wrench, Combo 1/2" 1 Wrench, Combo, 9/16" 1 Wrench, Combo,5/8" 1 Wrench, Combo, 11/16" 1 Wrench, Combo, 3/4" 1 Wrench, Flare Nut, 1/2"-9/16" 1 Wrench, Flare Nut, 5/8"-1 1/16" 1 Wrench, Flare Nut, 3/4"-1" 1 Wrench, Flare Nut, 7/8-1 1/8" 1 Snoop, Bottle, 8 oz 1 Note: The following items are supplied by the I&C Shop Tube Fitting, 1/4"M NPT to 3/8" tube comp 2 Tube Fitting, 1/4"F NPT to 1/4" tube comp 2 Tube Fitting, 3/8" comp to 3/8" comp 2 Tube Fitting, 1/4" comp to 1/4" comp 2 Tube Fitting, Tee, 1/4" comp 2 Tape, Electrical, Scotch 33 Black 1 Leads, Test, 4' 1 Jumpers, Banana, 2' orange w/clips 2 Tywraps, 3/16"x8" 1PK Tywraps, 1/8"x4" 1PK Valve Wrench, Custom Made, I&C Specs. 1 PAGE 18 OF 35 REVISION 23A

BROWNS FERRY EMERGENCY EQUIPMENT AND SUPPLIES (Inventory and EPIP-17 NUCLEAR PLANT Operability Procedure) Attachment 7 (Page 4 of 4) Maintenance Emergency Tool Box Inventory Mechanical Tool Box Number of Boxes 2 -- Number of Boxes Inventoried Tool Description QTY INV INIT Flux, Soldering I Chisel, Cold, .4375" Cut 1 Wrench Set, Combo, 0.250"-1.250" 1 Wrench Set, Hex Key (Allen), 0.187"-0.375" 1 Wrench Set, Hex Key (Allen), Folding, 0.050"-0. 187" 1 Socket Set, .375" 1 Hammer, Ball Pein, 12 oz 1 Punch, Pin, .188" 1 Punch, Pin, .125" 1 Pliers, Tongue & Groove, 9" #420 Channel Locks 1 Screwdriver, Phillips Tip, Round Shank, #2 Tip X 4.0" 1 Blade Screwdriver, Phillips Tip, Round Shank, #2 Tip X 1.50" 1 Blade Screwdriver, STD Tip, .25" Tip X 6.0" Long 1 Screwdriver, STD Tip, .25" Tip X 12.0" Long 1 Wrench, Pipe, 12" 1 Wrench, Adjustable, 12.0" 1 Pliers, Slip Joint, 10" 1 Pliers, Needle Nose, W/Side Cutter, 8" 1 Signatures: Supervisor, Tool Room: Date: Manager, EP: Date: Retention Period is 12 months - - Non-QA Record PAGE 19 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP- 17 NUCLEAR PLANT Operability Procedure) Attachment 8 (Page 1 of 4) Technical Support Center Inventory/Operability Check Equipment QTY INV OPER INIT In the Technical Support Center Telecopier 2 Y N Telecopier (TAT Area) 1 Y N TSC Intercom System 1 Y N TSC Zetron Radio System 1 Y N Copier 1 Y N EP Clock 1 Y N Control Room Conference Bridge Headset 2 Y N Met Data Terminal & Printer 1 Y N ERO Logbooks

Accountability Roster 1 ICS Terminal (TSC Area) 4 Y N ICS Terminal (TAT Area) 1 Y N In TSC Equipment & Supply Cabinet Calculators, (Scientific) 6 Y N Flashlights 12 Y N Batteries (D-Cells) 24 Y N Batteries (AA) 24 Y N Telephone Headsets (Spares) 3 Y N Staplers 1 Pens (Black Ink) 24 Pencils 12 Tape Dispensers w/tape 1 "Post-it-notes" Pads 12 Message Pads 12 Note Pads (8.5"x 11") 12 Board Cleaner (Bottles) 1 Paper Towels (Rolls) 1 Grease Pencils 12 Dry Erase Markers 12 Copier Paper (Packs) 4 Spare Phones for NRC ETS 6
Utilize EPIP-6, position attachments to identify what ERO logbooks are intended for use in the TSC.

PAGE 20 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP-17 NUCLEARPLANT Operability Procedure) Attachment 8 (Page 2 of 4) Technical Support Center Inventory/Operability Check Procedures/Drawings QTY INV OPER INIT In the Technical Support Center

REP 4

*BFN EPIP's                                              11
*CECC EPIP's                                              2
*Severe Accident Management Guidelines Flowcharts                                     1 Set
*Technical Support Guidelines                          1 Set
*Emergency Operating Instruction (EOI)

Flowcharts 1 Set

*EOI Program Manual                                    1 Set
*Radiological Control Instructions                     1 Set
*Abnormal Operating Instructions                       1 Set
*REND                                                     2
*AI Radiological Emergency Response Plan                  1
*Multi-Jurisdictional Radiological Emergency Response Plan TEMA                               1
*Alarm Response Procedures                              1 Set
*Operating Instructions                                 1 Set
*Technical Specifications                               1 Set
*Technical Requirements                                 1 Set
*Safe Shutdown Instructions                             1 Set
*Fire Protection Report                                 1 Set
*Final Safety Analysis Report                           1 Set
*User Manual Meteorological Data Display Program CECC                                      1
 *User Manual Nuclear Power (NP) Sites Emergency Paging System (EPC) CECC                1
 *FRED Forecast Radiological Emergency Dose                1
 *User Manual Meteorological Data Print Program                                           1
 *Plant Drawings                                        1 Set Radcon Survey Maps                                     1 Set EP 10-Mile Sample Point Map                               2 EP 2-Mile Sample Point Map                                 1 EP 50 Mile Sample Point Map                                1 EP 10 Mile Evacuation Sector Map                           1 Operators Manual Zetron Radio Console                      1
  "*Controlled Documents or Drawings PAGE 21 OF 35                      REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and Operability Procedure) EPIP- 17 NUCLEAR PLANT Attachment 8 (Page 3 of 4) Technical Support Center Inventory/Operability Check Procedures/Drawings QTY INV OPER INIT In the Technical Assessment Team Area

REP 1
BFN EPIP's 2
REND 1
Operating Instructions 1 Set
Technical Specifications 1 Set
Technical Requirements 1 Set
UMMI 1 Set
UEMI 1 Set
EMI 1 Set
Unit 2 E0I Appendices 1
Unit 3 EOI Appendices 1
SAMG EOI Appendices 1
SPCC Plan 1
Plant Drawings 1 Set A __________ .1.

PAGE 22 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP-17 NUCLEAR PLANT Operability Procedure) Attachment 8 (Page 4 of 4) Technical Support Center Inventory/Operability Check Support Center Telephones Technical niil Telephone Number I Operable Initials Telephone Number I 1 Operable initials T IJ* Initials 1 Y N 2305 Y N 3777 Y N 3734 Y N 3730 Y N 3733 Y N 3771 Y N 3736 Y N 3770 Y N 3735 Y N 3732 Y N 3744 Y N 3764 Y N 3756 Y N 3761 Y N 3745 Y N 3765 Y N 3738 Y N 3767 Y N 3740 Y N 3766 Y N 3762 w/Headset Y N 3768 Y N 3769 w/Headset Y N 3763 Y N 3737 w/Headset Y N 3779 Y N CECC Ringdown Y N 3782 (Node 2 Jack Only) Y N 101/102 Bridge Y N 3784 (Node 2 Jack Only) 103 Radcon Bridge Y N ___________________ I I _________ Control Rooms Telephone Number Operable Initials Telephone Number Operable Initials ODS Unit 1/2 Ringdown Y N ODS Unit 3 Ringdown Y N Unit 1/2 Bridge Headset Y N Unit 3 Bridge Headset Y N Unit 1/2 Fixed Satellite Unit 3 Fixed Satellite Telephone Y N Telephone Y N Manager, EP: Date: Retention Period is 12 months - - Non-QA Record PAGE 23 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP-17 NUCLEAR PLANT Operability Procedure) Attachment 9 (Page lof 2) Operations Support Center Inventory/Operability Check Equipment QTY INV OPER INIT In the Operational Support Center Telecopier 1 Y N OSC Intercom System 1 Y N Copier 1 Y N EP Clock 1 Y N Computer Terminal 1 Y N Printer for Computer 1 Y N Accountability Roster 1 OSC Zetron Radio System 1 Y N RADCON Zetron Radio System 1 Y N ICS Terminals 2 Y N In OSC Equipment & Supply Cabinet Calculators, (Scientific) 6 Y N Flashlights 12 Y N Batteries (D-Cells) 24 Y N Batteries (AA) 24 Y N Telephone Headsets (Spares) 2 Y N Staplers 3 Pens (Black Ink) 24 Pencils 12 Tape Dispensers w/tape 1 "Post-it-notes" Pads 12 Message Pads 12 Note Pads (8.5"x 11") 12 Board Cleaner (Bottles) 1 Paper Towels (Rolls) 1 Grease Pencils 12 Dry Erase Markers 12 Copier Paper (Packs) 4 Hand Held 2-Way Radios 10 ERO Logbooks *

Utilize EPIP-7, position attachments to identify what ERO logbooks are intended for use in the OSC.

PAGE 24 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP-17 NUCLEAR PLANT Operability Procedure) Attachment 9 (Page 2of 2) Operations Support Center Inventory/Operability Check Operations Support Center Telephones Manager, EP: Date: Retention Period is 12 months - - Non-QA Record PAGE 25 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and Operability Procedure) EPIP-17 NUCLEAR PLANT Attachment 10 OSC Staging Area Inventory/Operability Check Equipment QTY INV OPER INIT In the OSC Staging Area Eauipment & SuDDlv Cabinet Calculators, (Scientific) 1 V N Flashlights 12 V N Batteries (D-Cells) 24 V N Staplers 1 Pens (Black Ink) 24 Pencils 12 Tape Dispensers 1 "Post-it-notes" Pads 12 Message Pads 12 Note Pads (8.5 "x 11 ") 12 Accountability Roster 1 ERO Logbooks In the OSC Staging Area Ice Vests 12 Ice Packs for vests 72 Operations Support Center Staging Area Telephones Telephone Number Operable Initials Telephone Number Operable Initials 2244 Y N 2115 Y N 2309 Y N 2215 Y N 2303 Y N

Utilize EPIP-7, position attachments to identify what ERO logbooks are intended for use in the OSC Staging Area.

Manager, EP: Date:_ _ Retention Period is 12 months - - Non-QA Record PAGE 26 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP- 17 NUCLEAR PLANT Operability Procedure) Attachment 11 (Page 1 of 2) Huntsville/Decatur General Hospital Inventory/Operability Check (Circle One) Hospital Equipment & Supply Cabinet QTY INV OPER INIT Personnel Dress-Out Clothing "Booties" (Pairs) 10 Dress Out Packages 10 Surgical Gloves (Pairs) 50 Surgical Gowns 3 Surgical tape for dressout (Rolls) 4 Rad Monitoring Instruments & Dosimetry Bicron Surveyor 50 (GM) or equivalent 2 Y N Bicron RSO 5 (Ion Chamber) or equivalent 1 Y N TLD's 10 Electronic Dosimeters 10 Wound Probe w/Cable 1 Zone, Survey & Contamination Control Supplies Floor Covering (Set) 1 Duct Tape (Rolls) 2 Rad Posting Signs 8 Contamination Smears 100 Step-Off-Pads 2 Rad Ribbon or rope (Rolls) 1 Massilin Mop 1 Massilin Cloths 20 Rad Emblem Tape (Rolls) 1 Flexible Funnel w/ drain hose 1 Fluid Collection Bottle (2 Gallon min.) 1 3ft. Wide Paper (Feet) 20 Cotton Swabs 12 Radioactive Material Tags 12 Traffic Cones (set) 1 ____________________________________ .1 L _______ A PAGE 27 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and Operability Procedure) EPIP-17 NUCLEAR PLANT Attachment 11 (Page 2 of 2) Huntsville/Decatur General Hospital Inventory/Operability Check Zone, Survey & Contamination Control QTY INV OPER INIT Supplies (Continued) Scissors 1 Plastic Bags (Large) 10 Plastic Bags (Medium) 10 "Zip Lock" Plastic Bags 24 Skin Decon Media (Container) 1 Sample Bag Labels 12 Hospital Response Booklet (HospitalSpecific) 1 Wall Poster ("Care of ContaminationPatients") 1 NCRP Report # 65 (IssuedDate - April 15, 1980) 1 Decontamination Table, bottle and Backboard 1 Manager, EP: Date: Retention Period is 12 months - - Non-QA Record PAGE 28 OF 35 REVISION 23A

K (K BROWNS FERRY EMERGENCXý EQUIPMENT AND NUCLEAR PLANT SUPPLIES (Inventory and EPIP-17 Operability Procedure) Attachment 12 mI 1L.1 OPE I I*IT Description Location Telephone Number OPER Ir XT IF'V TSC (NRC Area) (700) 221-7996 Y N Reactor Safety Counterpart Link (RSCL) TSC (NVRC Area) (700) 221-7997 Y N Protective Measures Counterpart Link (PAICL) TSC (NRC Area) (700) 221-7995 Y N Management Counterpart Link (MCL) TSC (NRC Area) (700) 221-7994 Y N Local Area Network (LAN) Access (Check this line by use of a telephone instrument) (700) 221-7992 Y N Health Physics Network (HPN) TSC (NRC Area) (700) 221-7992 Y N TSC (TVA Area) Health Physics Network (HPN) (700) 221-7991 Y N

      *Emergency Notification System (ENS)                        TSC (NRC Area)

(700) 221-7991 Y N

      *Emergency Notification System (ENS)                        TSC (TV4 Area)

(700) 221-7991 Y N

      *Emergency Notification System (ENS)                     Unit 1/2 Control Room (700) 221-7991             Y   N
      *Emergency Notification System (ENS)                      Unit 3 Control Room

Notify the Shift Manager prior to beginning the ENS telephone checks (The NRC may Note: IMMEDIATELY, Report Failures to (1) the Shift Manager, and (2) the NRCOC at 9-1-301-951-0550 from a TVA telephone.

request that Browns Ferry conduct repairs.) the SOS and the NRCOC. Note: Upon Completion of repairs, perform a test of the affected telephones. If test is satisfactory, inform Manager, EP: Date:__ Retention Period is 12 months - - Non-QA Record PAGE29 F 35REVSION23AI REVISION 23AI PAGE 29 OF 35

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP- 17 NUCLEARPLANT Operability Procedure) Attachment 13 (Page 1 of 2) Local Recovery Center Inventory/Operability Check Equipment QTY INV OPER INIT In the LRC Area Met Data Terminal 1 Y N Printer for Met Data Terminal 1 Y N ICS Terminal 1 Y N In LRC Equipment & Suply Cabinet Calculators, (Scientific) 4 Y N Flashlights 12 Y N Batteries (D-Cells) 24 Y N Staplers 1 Pens (Black Ink) 24 Pencils 12 Tape Dispensers 1 "Post-it-notes" Pads 12 Message Pads 12 Note Pads (8.5"x 11") 12 Board Cleaner (Bottles) 2 Paper Towels (Rolls) 1 Dry Erase Markers 12 L L I I PAGE 30 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP-17 NUCLEAR PLANT Operability Procedure) Attachment 13 (Page 2 of 2) Local Recovery Center Inventory/Operability Check Telephone Number Operable Initials Telephone Number Operable Initials 2038 Y N 2692 Y N 3666 Y N 2460 Y N 3636 Y N 2064 Y N 3656 Y N 3647 Y N 3645 Y N Portable Satellite Telephone Y N Manager, EP: Date: Retention Period is 12 months - - Non-QA Record PAGE 31 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and Operability Procedure) EPIP- 17 NUCLEAR PLANT Attachment 14 EP Quarterly Administrative Checks and Reviews QTY INV DATE INIT Emergency Response List Update

Nuclear Security 5 Shift Supervisor's Office (5-Copies)

Call-Out List

Shift Manager 1

                                                        .1.       1         1         __________

Manager, EP: Date:_ _ Retention Period is 12 months - - Non-QA Record PAGE 32 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and EPIP-17 NUCLEAR PLANT Operability Procedure) Attachment 15 EP Once per Calendar Quarter Administrative Checks and Reviews QTY INV DATE INIT Emergency Procedure Telephone Number Review and Update 0 BFNP Emergency Preparedness ALL Implementing Procedures

BFN Site Standard Practice SSP-1.52

____ ___ ____ ____ __ ___ __I Manager, EP: Date: Retention Period is 12 months - - Non-QA Record PAGE 33 OF 35 REVISION 23A

EMERGENCY EQUIPMENT AND BROWNS FERRY SUPPLIES (Inventory and Operability Procedure) EPIP- 17 NUCLEAR PLANT Attachment 16 EP Annual Administrative Checks and Reviews QTY INV DATE INIT Review Emergency Procedures

   "* Radiological Emergency Plan                           NA
   "* Browns Ferry, Emergency Plan                          NA Implementing Procedures Manager, EP:                                                   Date:_     _

Retention Period is 12 months - - Non-QA Record PAGE 34 OF 35 REVISION 23A

BROWNS NUCLEARFERRY PLANT EMERGENCY EQUIPMENT AND SUPPLIES (Inventory and EPIP-17 Operability Procedure) Attachment 17 Alternate Decontamination Facility Power Service Shop # 4 - TVA, Muscle Shoals Reservation QTY INV INIT Equipment Supply Cabinet 2 PKG Cotton Tipped Swabs 1 Box Square Gauze 1 Box Detergent 12 Surgical Brush 2 Cans Waterless Hand Cleaner 2 BTL Shampoo 100 Paper Bath Towels 12 Small Coveralls 12 Medium Coveralls 12 Large Coveralls 12 Small Tennis Shoes 12 Large Tennis Shoes Signatures:D Date: Inventoried/Inspected by Manager, EP: Date: Retention Period is 12 months - - Non-QA Record LAST PAGE REVISION 23A PAGE 35 OF 35}}

ML003694233

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