ML011270196
| ML011270196 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/27/2001 |
| From: | Abney T Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| -RFPFR | |
| Download: ML011270196 (120) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 April 27, 2001 10 CFR Part 50, App E U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 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 is canceled; (2)
EPIP-1, Table of Content (TOC),
Revision 30; (3)
EPIP-1, Section 11-4.0, Revision 29; (4)
EPIP-I, Section 111-4.0, Revision 29, (5)
EPIP-2, Revision 22; (6)
EPIP-3, Revision 25; (7)
EPIP-4, Revision 24; (8)
EPIP-5, Revision 29; (9)
EPIP-8, Revision 13; and (10)
EPIP-14, Revision 16.
The EPIP Index revision date is April 6, 2001, while the revision date for the other changes (2 through 10) is March 31, 2001.
If you have any questions, please telephone me at (256) 729-2636.
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Manage icensin qTIndustry Affaii ss r4xb Printed on recycled paper
U.S. Nuclear Regulatory Commission Page 2 April 27, 2001 Enclosure cc (Enclosure):
NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 (Enclosure provided by BFN Document Control Unit)
Mr. Paul E. Fredrickson (2 Enclosures)
U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street SW, Suite 23T85 Atlanta, Georgia 30303-8931 Mr. William 0. Long, Senior Project Manager (w/o Enclosure)
U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852
ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 EMERGENCY PLAN IMPLEMENTING PROCEDURES (EPIP)
EPIP -1,
-2,
-3,
-4,
-5,
-8, and -14 (SEE ATTACHED)
GENERAL REVISIONS GENERIC FILING INSTRUCTIONS FILE DOCUMENTS AS FOLLOWS:
PAGES TO BE REMOVED EPIP INDEX (ALL)
EPIP-1,
- TOC, REVISION 29 (ALL)
EPIP-1, SEC 11-4.0, REV 28 (ALL)
(ALL)
EPIP-1, SEC 111-4.0, REV 28 (ALL)
(ALL)
EPIP-2 REVISION 21 (ALL)
EPIP-3 REVISION 24 (ALL)
EPIP-4 REVISION 23 (ALL)
EPIP-5 REVISION 28 (ALL)
EPIP-8 REVISION 12 (ALL)
EPIP-14 REVISION 15 (ALL)
PAGES TO BE INSERTED EPIP INDEX CANCELLATION SHEET EPIP-1,
- TOC, REVISION 30 (ALL)
EPIP-1, SEC 11-4.0, REV 29 EPIP-1, SEC 111-4.0, REV 29 EPIP-2 REVISION 22 (ALL)
EPIP-3 REVISION 25 (ALL)
EPIP-4 REVISION 24 (ALL)
EPIP-5 REVISION 29 (ALL)
EPIP-8 REVISION 13 (ALL)
EPIP-14 REVISION 16 (ALL)
EPIP INDEX CANCELLATION SHEET EPIP INDEX WAS CANCELLED ON APRIL 6, 2001
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-1 EMERGENCY CLASSIFICATION PROCEDURE REVISION 30 PREPARED BY: T. W. CORNELIJS RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS APPROVED BY: GILBERT LITTLE EFFECTIVE DATE: 03/31/2001 LEVEL OF USE: REFERENCE USE PHONE: 2038 DATE: 03/09/2001 QUALITY-RELATED
REVISION LOG Procedure Number:
EPIP-1 Revision Number 30 PagesAffected:
1.34, 127, 129. 131-134, 137, 138 Description of Change:
IC - 41 This revision is being conducted as a result of revised calculations effecting the stack noble gas release rate values. EDMS L63 010206 800 document the information utilized for making this revision.
Page 1 - Revised to update revision numbers Page 34 - Revised to update Tables 4.1-S and 4. 1-G. gaseous release rate, stack noble gas (WRGERMS) limits.
Page 131. 132. 133. 134 - Revised to update gaseous release rate, stack noble gas (WRGERMS) limits.
Page 127. 129. 132. 134. 137. 138 - Revised to update reference.
EPIP-1 EMERGENCY CLASSIFICATION PROCEDURE TABLE OF CONTENTS PAGE NUMBER REVISION TA BLE O F CON TEN T S............................................................................
1 30 SECTION I INTRODUCTION CLASSIFICATION INSTRUCTIONS............................................
3 29 GLOSSARY...............................................................................
5 29 EVENT CLASSIFICATION INDEX............................................
11 29 SECTION II EVENT CLASSIFICATION MATRIX 1.0 R E A C T O R..............................................................................
13 29A 2.0 PRIMARY CONTAINMENT.................................................
21 28 3.0 SECONDARY CONTAINMENT...........................................
29 29 4.0 RADIOACTIVITY RELEASES..............................................
33 29 5.0 LO SS O F POW ER..................................................................
39 29 6.0 H A Z A R D S..............................................................................
45 29 7.0 N ATURA L EV EN TS..............................................................
61 28 8.0 EMERGENCY DIRECTOR JUDGEMENT............................
67 29 SECTION III BASIS 1.0 R E A C T O R..............................................................................
75 29 2.0 PRIMARY CONTAINMENT.................................................
97 28 3.0 SECONDARY CONTAINMENT.........................................
116 29 4.0 RADIOACTIVITY RELEASE..............................................
126 29 5.0 LO SS OF POW ER................................................................
139 29 6.0 H A Z A R D S............................................................................
155 29 7.0 NATURAL EVENTS............................................................
183 28 8.0 EMERGENCY DIRECTOR JUDGEMENT..........................
190 29 PAGE 1 OF 207 REVISION 30
EPtP-1 EMERGENCY CLASSIFICATION PROCEDURE THIS PAGE INTENTIONALLY BLANK PAGE 2 OF 207 REVISION 30
EMERGENCY CLASSIFICATION "IDll)f%1/* 1* "nl T 11 1 EPIP-1 SECTION H 1FVWNT CIASSIFICATION MATRIX
~~EVN CLASSIFICATION~t MATRIX-4.0 RADIACTIVITY RELEASE RADIOACTIVITY RELEASES 4.0 4.0 RADIACTIVITY RELEASE PAGE 33 OF 207 REVISION 29 1
4.0 RADIACTIVITY RELEASE EPIP-1 SECTION II EVENT CLASSIFICATION MATRIX EMERGENCY CLASSIFICATION 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:
I. Actual field measurements exceed the limits in Table 4.1-U
- 2. SI 4.8.B. 1.a. I Release Fraction exceeds 2.0 IfnIither assessunt can be oa icted wtlint 60 minutes thfen the declaration must be n-ode on die valid WRGERMS rading 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 exceeds 200 Ithiether assesant can be cordiced. vNithin 15 minutes then the declaration must be made on the valid WRGERMS miding NOTE 4. 1-S Prior to making this emergency classification based upon the Gaseous Release Rate indication, assess the release by either of the Ibllowing methods:
- 1. Actual field measurements exceed the limits in Table 4.1-S.
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 making fltis emergency classification based upon the Gaseous Release Rate indication, assess the release by either of the following methods:
I. Actual field measurements exceed the limits in Table 4.1-G.
If neither assessment can be conducted within 15 minutes 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) 1 2.88 X 10 p.Cisec 1 HOUR GASEOUS RELEASE RATE S[4.8.B.l.a.1 RELEASE FRACTION 2.0 1 HOUR SITE BOUNDARY RADIATION READING FIELD ASSESSMENT TEAM 0.10 MREMHR -i-3 1 HOUR Table 4.1-A RELEASE LIMITS FOR ALERT TYPE MONITORING METHOD LIMIT DURATION GASEOUS RELEASE RATE STACK NOBLE GAS (WRGERMS) 2.88 X 1O0 itCi/sec 15 MINUTES GASEOUS RELEASE RATE S] 4.8.B.1.a.1 RELEASE FRACTION 200 15 MINUTES SITE BOUNDARY RADIATION READING FIELD ASSESSMENT TEAM 10 MREMi HR 7-15 MINUTES Table 4.1-S RELEASE LIMITS FOR SITE AREA EMERGENCY TYPE NIONITORING METHOD LIMIT DURATION GASEOUS RELEASE RATE STACK NOBLE GAS (WRGERMS) 5.9 X 10 9 LtCi, sec 15 MINUTES SITE BOLNDARY RADIATION READING FIELD ASSESSMENT TEAM 100 MREMN HR -- p1 tHOUR SITE BOUND.ARY IODINE-131 FIELD ASSESSMENT TEAM 3.9 X 10 -- f.CI.cm 1 1 HOUR Table 4.1-G RELEASE LIMITS FOR GENERAL EMERGENCY TYPE MONITORING METHOD LIMIT DURATION GASEOUS RELEASE RATE STACK NOBLE GAS (WRGERMS) 5.9 X 10 10 iiCiisec 15 MINUTES SITE BOUNDARY RADIATION RE.ADING FIELD ASSESSMENT TEA2VI 1000 MREMiHR 7 -
1 HOUR SITE BOUNDARY IODINE-131 FIELD ASSESSMENT TEAM 3.9 X 10.6 "CI Im 3
1 HOUR REVISION 29 PAGE 34 OF 207 4.0 RADIACTIVITY RELEASE
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION II EVENT CLASSIFICATION MATRIX 4.0 RADIOACTIVE RELEASE DESCRIPTION DESCRIPTION 4.1-U Gaseous release exceeds ANY limit and duration in Table 4.1-U.
4.2-U Main Steam Line break outside Primary Containment with isolation.
OPERATING CONDITION:
-Mode 1
-Mode 2
-Mode 3 z
C,'
z 4.1-A i ~
Gaseous release exceeds ANY limit and duration in Table 4. 1-A.
OPERATING CONDITION:
-All 4.1-S T b 4.2-S EITHER of the following conditions exists:
Unisolable Main Steam Line break outside Primary
"* Gaseous release exceeds or is expected to exceed Contaimnent.
ANY limit and duration in Table 4.1-S.
"* Dose assessment indicates actual or projected dose 0
consequences above 100 mirem TEDE or 500 mrem th-goid CDE.
"OPERATING CONDITION:
OPERATING CONDITION:
-Mode 1
-Mode 3
-All
-Mode 2 4.1-G
' K 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 mrern thyroid CDE.
OPERATING CONDITION:
-All 4.0 RADIACTIVITY RELEASE PAGE 35 OF 207 I
Kzvlailwll Ly
4.0 RADIACTIVITY RELEASE EPIP-1 SECTION H EVENT CLASSIFICATION MATRIX EMERGENCY CLASSIFICATION PROCEDURE NOTES:
CURVES/TABLES:
REVISION 29 PAGE 36 OF 207 4.0 RADIACTIVITY RELEASE PROCEDURE
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION H EVENT CLASSIFICATION MATRIX 4.0 RADIOACTIVE RELEASE LIQIDEFUN DESCRIPTION DESCRIPTION 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 AND Release duration exceeds or will exceed 15 minutes.
OPERATING CONDITION:
- All I
Uz z
z
-M PAGE 37 OF 207 4.0 RADIACTIVITY RELEASE 1R1EV ISION2 I
4.0 RADIACTIVITY RELEASE EPIP-1 SECTION I1 EVENT CLASSIFICATION MATRIX EMERGENCY CLASSIFICATION PROCEDURE THIS PAGE INTENTIONALLY BLANK REVISION 29 PAGE 38 OF 207 4.0 RADIACTIVITY RELEASE
EMERGENCY CLASSIFICATION DuDirnirTurI EPIP-1 SECTION III TECHNICAL BASIS 4.0 RADIOACTIVITY RELEASE RADIOACTIVITY RELEASE 4.0 4.0 RADIOACTIVTY RELEASE PAGE 126 OF 207 REVISION 29
EMERGENCY EPIP-1 CLASSIFICATION SECTION IH 4.0 RADIOACTIVITY 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> time period allows sufficient time to isolate any release after exceeding ODCM limits. Release continuing for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. 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-AU 1 example-i)
EDMS L63 010206 800 10CFR20 4.0 RADIOACTIVITY PAGE 127 OF 207 RELEASE REVISION 29
EMERGENCY CLASSIFICATION PD",ACI* IrhIT EPIP-1 SECTION III TECHNICAL BASIS 4.0 RADIOACTIVITY RELEASE GA¶ISEOUSEFFUERNT 41-UNUSUAL EVENT (CONTINUED)
CURVES/TABLES Table 4.1-UL RELEASE LIMITS FOR UNUSUAL EVENT TYPE MONITORING METHOD LIMIT DURATION GASEOUS RELEASE RATE STACK NOBLE GAS (WRGERMS) 2.88 X I0 7 'Ci/sec 1 HOUR GASEOUS RELEASE RATE SI 4.8.B.1.a.1 RELEASE FRACTION 2.0 1 HOUR SITE BOUNDARY RADIATION READING FIELD ASSESSMENT TEAM 0.10 MREM!HR
- 0 1 HOUR NOTES NOTE 4.1-U 4.0 RADIOACTIVITY RELEASE 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.
PAGE 128 OF 207 REVISION 29
EMERGENCY CLASSIFICATION PPACD1 IrfTRI?
EPIP-1 SECTION III TECHNICAL BASIS 4.0 RADIOACTIVITY RELEASE GASI16 R EOU ELENT u.1-A ALERT Gaseous release exceeds ANY limit and duration in Table 4.1-A.
OPERATING CONDITION BASIS REFERENCES All 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 10CFR20 limits.
Reg Guide 1.101 Rev. 3, (NUMARC-AA 1 example-i)
EDMS L63 010206 800 10CFR20 EPA 400 4.0 RADIOACTIVITY RELEASE PAGE 129 OF 207 REVISION 29
EMERGENCY CLASSIFICATION pRACEI).TITRE*
EPIP-1 SECTION III TECHNICAL BASIS 4.0 RADIOACTIVITY RELEASE GASEKOUSR DEFFLRUENT 4.1-ALERT (CONTINUED)
CURVES/TABLES TYPE MONITORING METHOD LIMIT DURATION GASEOUS RELEASE RATE STACK NOBLE GAS (WRGERMS) 2.88 X 10 9 jtCiisee 15 MINUTIES GASEOUS RELEASE RATE SI 4.8.B. l.a. 1 RELEASE FRACTION 200 15 MINUTES SITE BOLUNDARY RADIATION READING FIELD ASSESSMENT TEAM 10 MREM'HR 15 MINUTES NOTES NOTE 4.1-A 4.0 RADIOACTIVITY RELEASE 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 200 If neither assessment can be conducted within 15 minutes then the declaration must be made on the valid WRGERMS reading.
PAGE 130 OF 207 REVISION 29 Table4*.1-A REL EASE LIMITS FOR ALERT
EMERGENCY EPIP-1 CLASSIFICATION SECTION 11 4.0 RADIOACTIVITY PROCEDURE TECHNICAL BASIS RELEASE GASE OUS EFFL111EUhEN 4.1-S 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 1 OCFR20 dose limit for a member of the public. Stack Noble Gas Release Rates of 5.9 X 109 gCi/sec for 15 minutes, site boundary radiation readings of 100 mrem/hr for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and Iodine 131 concentration of 3.9 X 0-7 lICi/cm3 for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> are indicative of dose consequences consistent with the limits described previously. The durations in Table 4.1-S are consistent with NJIARC 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 EP1P-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 U
RELEASE REVISION 29
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS 4.0 RADIOACTIVITY RELEASE 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-AS I example-1)
EDMS L63 010206 800 10CFR20 EPA 400 CURVES/TABLES Table 4.1-S RV1IR1ASE, LIMITS F~OR SITE AREA EMERGENCY TYPE MONITORING METHOD LIMIT DURATION GASEOUS RELEASE RATE STACK NOBLE GAS (WRGERMS) 5.9 X 10 9 itCi/sec 15 MINUTES SITE BOUNDARY RADIATION READING FIELD ASSESSMENT TEAM 100 MREM/HR y -
I HOUR SITE BOUNDARY IODINE-131 FIELD ASSESSMENT TEAM 3.9 X 10 -- ttCI icm 3 1 HOUR 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.
If neither assessment can be conducted within 15 minutes then the declaration must be made based on the valid WRGERMS reading.
PAGE 132 OF 207 REVISION 29 NOTES 4.0 RADIOACTIVITY RELEASE GASEOUS EFFLUENT 4.1-S
EMERGENCY CLASSIFICATION ODI'II.D TI EPIP-1 SECTION III TECHNICAL BASIS 4.0 RADIOACTIVITY RELEASE GASEU EFLET.-
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 CONDITION All 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 5.9 X 1010 [iCi/sec for 15 minutes, site boundary radiation readings of 1000 mrem/hr for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and Iodine-131 concentration of 3.9 X 10-6 pCi/cm3 for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> are indicative of dose consequences consistent with the limits described previously. The durations in Table 4. 1-G 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 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 RE RELEASE REVISION 29 BASIS
EMERGENCY CLASSIFICATION PRCEDIURE EPIP-1 SECTION HI TECHNICAL BASIS 4.0 RADIOACTIVITY RELEASE
-AEU EFFLUUEN T
4.1-G GENERAL EMERGENCY (CONTINUED)
REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-asl example-i)
EDMS L63010206 800 10CFR20 CURVES/TABLES Table 4.1-G RELEASE LIMITS FOR GENERAL EMERGENCY TYPE MONITORING METHOD LIMIT DURATION GASEOUS RELEASE RATE STACK NOBLE GAS (WRGERMS) 5.9 X 10 1o ttCi/sec 15 MINUTES SITE BOUNDARY RADIATION READING FIELD ASSESSMENT TEAM 1000 MREMiHR y -
1 HOUR SITE BOUNDARY IODINE-131 FIELD ASSESSMENT TEAM 3.9 X 10 -6 1el.l, c
3 1 HOUR NOTES NOTE 4.1-G 4.0 RADIOACTIVITY RELEASE 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.
If neither assessment can be conducted within 15 minutes then the declaration must be made based on the valid WRGERMS reading.
PAGE 134 OF 207 REVISION 29 H
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS 4.0 RADIOACTIVITY RELEASE UNUSUAL EVENT Main Steam Line break outside Primary Containment with isolation.
OPERATING CONDITION BASIS Mode l Mode 2 Mode 3 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 4.0 RADIOACTIVITY RELEASE Reg Guide 1.101 Rev. 3, (NUMARC-FU)
PAGE 135 OF 207 "REVISION 29 1
MAIN STEAM LINE BREAK 4.2-U
EMERGENCY CLASSIFICATION pRACi* IlI1ITR1' EPIP-1 SECTION III TECHNICAL BASIS 4.0 RADIOACTIVITY RELEASE SITE AREA EMERGENCY Unisolable Main Steam Line break outside Primary Containment.
OPERATINC CONDITION BASIS Mode l Mode 2 Mode 3 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 4.0 RADIOACTIVITY RELEASE Reg Guide 1.10 1 Rev. 3, (NUMARC-FS)
PAGE 136 OF 207 REVISION 29
-PROCEDURE MAIN STEAM LINE BREAK 4.2-S
EMERGENCY EPIP-1 CLASSIFICATION SECTION IH 4.0 RADIOACTIVITY PROCEDURE TECHNICAL BASIS RELEASE 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 IOCFR20 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, AOL, 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)
EDMS L63 010206 800 10CFR20 4.0 RADIOACTIVITY PAGE 137 OF 207 RELEASE REVISION 29
EMERGENCY CLASSIFICATION PROCEDURE EPIP-1 SECTION III TECHNICAL BASIS 4.0 RADIOACTIVITY RELEASE 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, E0I). 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 failure of the Reactor Coolant System pressure boundary and Primary Containment barrier.
REFERENCES Reg Guide 1.101 Rev. 3, (NUMARC-AA1 example-2)
EDMS L63 010206 800 4.0 RADIOACTIVITY RELEASE PAGE 138 OF 207 REVISION 29
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-2 NOTIFICATION OF UNUSUAL EVENT REVISION 22 PREPARED BY: TIM CORNELIUS RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS APPROVED BY:
GILBERT LITTLE PHONE: 2038 DATE: 03/09/2001 EFFECTIVE DATE: 03/31/2001 LEVEL OF USE: REFERENCE USE QUALITY-RELATED
REVISION LOG Procedure Number:
EPIP-2 Revision Number:
22 Pages Affected:2,7,8, 9, 10 Description of Change:
IC-27 This change is being conducted to incorporate the management of NRC Commitment changes as prescribed in the correspondence from site licensing RIMS R08000217713. to remove the Public Information Officer from the notification form and to human factor the notification and follow-up notification forms.
Page 2 - change to step 3.1.1 involves human factoring the Notification Form Title.
Page 7 - changes involves removing the "NRC Commitment Brackets to step requiring the review of PORC and the human factoring of applicable steps.
Page 7 - change involves human factoring attachment title.
Page 8 - change involves human factoring attachment title and modifying information to ensure consistency wxith NRC guidance.
Page 9 - change involves removing the Public Information Officer from the Attachment B notifications along with the NRC Commitment Brackets Page 10 - change involved adding a clarify statement concerning the appropriate use of 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 1 OF 10 REVISION 22
NOTIFICATION OF UNUSUAL EVENT EPIP-2 BROWNS FERRY 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 (Initial Notification Form).
3.1.2 Notify the ODS and Provide the information from 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 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 of information or state if contacted directly).
ODS Fax 5-751-8620 INITLALS TIME INITLALS TLAIE INITLALS TIME AL Rad Health 9-1-3-34-206-5387 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 directly).
INITL4,LS TmIE PAGE 2 OF 10 REVISION 22
NOTIFICATION OF UNUSUAL EVENT EPIP-2 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.2 NOTIFICATION OF SITE PERSONNEL 3.2.1 Provide the Unit 1, Unit Operator with a completed copy of Attachment A.
3.2.2 Direct the Unit 1, Unit Operator to make notifications from Attachment B (Unit 1, Unit Operator Notification), utilizing information from Attachment A.
3.2.3 Make the following plant P.A. announcement:
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.
INrTIALS TIME INITIALS TIME INITIALS TIME INITLALS TPME 3.3 OFFSITE DOSE ASSESSMENT 3.3.1 Evaluate the need for offsite dose assessment.
(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.
INITIALS TIME PAGE 3 OF 10 REVISION 22
NOTIFICATION OF UNUSUAL EVENT EPIP-2 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.4 NOTIFICATION OF THE NRC 3.4.1 Notify the NRC immediately or within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and if 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, by dialing 9-1 "The Ten Digit Number Listed on the ENS Telephones".
If the number is busy, Then select in order, the alternate numbers until a connection is achieved. No access codes are required.
INITIALS TnEE PAGE 4 OF 10 REVISION 22
NOTIFICATION OF BROWNS FERRY UNUSUAL EVENT EPIP-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 22
NOTIFICATION OF UNUSUAL EVENT EPIP-2 BROWNS FERRY 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 the state directly if the ODS cannot be contacted.
3.6.2 Notify the NRC of the termination of the emergency.
3.6.3 Notify the Plant Manager or Alternate of the termination of the emergency.
3.6.4 Complete Attachment A by providing the time and date of termination.
3.6.4 Notify the Unit 1, Unit Operator. Provide the Unit 1, Unit Operator with the termination time and date and direct the Unit 1, Unit Operator to notify the individuals contacted on Attachment B of the termination of the emergency.
INITLAS TIME INITLALS TIME INITIALS LNITLALS TIME TLME LNITIA.LS TIm PAGE 6 OF 10 REVISION 22
NOTIFICATION OF UNUSUAL EVENT EPIP-2 BROWNS FERRY 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, 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.
3.7.3 PORC Review Completed.
INITIALS TmIE IN"IALS TIME
/
PORC Chairman DATE 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.
INMTILJS TIME 4.0 ATTACHMENTS Attachment A - Initial Notification Form Attachment B - Unit 1, Unit Operator Notification Attachment C - Follow Up Information Form PAGE 7 OF 10 REVISION 22
NOTIFICATION OF BROWNS FERRY UNUSUAL EVENT EPIP-2 NUCLEAR PLANT ATTACHMENT A (Page 1 of 1)
INITIAL NOTIFICATION FORM NOTIFICATION OF UNUSUAL EVENT E-] THIS IS AN ACTUAL EVENT F-THIS IS AN EXERCISE This is NAME A NOTIFICATION OF UNUSUAL EVENT has been declared at Browns Ferry affecting:
F-Unit 1 F-- Unit 2
[-- Unit 3 El Common Event Declared:
Time:
Date:
EAL Designator:
Brief Description of the Event:
Radiological Conditions:
L-- No Abnormal Releases Offsite
[--
Airborne Release Offsite F--
Liquid Release Offsite F--
Release Information Not Known at this time F-There is no Protective Action Recommendation at this time.
F-E Ask,_"Please repeat the information you have received to ensure accuracy.
PAGE 8 OF 10 REVISION 22
NOTIFICATION OF UNUSUAL EVENT EPIP-2 BROWNS FERRY 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 Site Emergency Director.
INITIALS TIME Personnel1 Notifications Notify the Operations Manager (from the weekly duty list)
Notify the Vice President (from the weekly duty list)
Notify the REP manager (from the weekly duty list)
Notify the Nuclear Security Shift Supervisor.
Ext. 3150 or 2219 Notify the NRC Resident Ext.
2573, or 2572 or from the weekly duty list.
Initial Notifications Termination Notifications PersonnelNotifications Initials Time Initials Time Initials Time Initials Initials Time Time This is a Quality Assurance record with a retention of five years.
PAGE 9 OF 10 Initials Initials Initials Initials Initials Time Time Time Time Time REVISION 22
NOTIFICATION OF UNUSUAL EVENT EPIP-2 BROWNS FERRY NUCLEAR PLANT ATTACHMENT C (Page 1 of 1)
FOLLOW-UP INFORMATION FORM NOTIFICATION OF UNUSUAL EVENT E-THIS IS A REAL EVENT
[-] THIS IS A DRILL Note: This form is for conducting Follow-up Information only.
This is at Browns Ferry.
Name There has been a NOTIFICATION OF UNUSUAL EVENT declared at Browns Ferry affecting:
F--
Unit I F-Unit 2 F-- Unit 3 F-- Common The Reactor is F-Shutdown
- At Power Plant Conditions are F] Stable Fl Deteriorating "Follow-Up" Information (e.g., Key Events, Status Changes)
Current Radiological Conditions are:
F-- No Abnormal Releases Offsite F-- Airborne Release Offsite F-- Liquid Release Offsite F-- Release Information Not Known Additional Rad information: (e.g., release duration)
F-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 22
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-3 ALERT REVISION 25 PREPARED BY: TIM CORNELIUS RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS APPROVED BY: GILBERT V. LITTLE EFFECTIVE DATE: 03/31/2001 LEVEL OF USE: REFERENCE USE PHONE: 2038 DATE: 03/09/2001 QUALITY-RELATED
REVISION LOG Procedure Number:
EPIP-3 Revision Number:
25 Pages Affected: 2,6,7,9, 10 Description of Change:
IC-30 This change is being conducted to incorporate the management of NRC Commitment changes as prescribed in the correspondence from site licensing RIMS R08000217713, and to human factor the notification and followv-up notification forms.
Page 2 - change to step 3.2.1 involves human factoring the Notification Form Title.
Page 6 - changes involves removing the "NRC Commitment Brackets to step requiring the review of PORC and the human factoring of applicable steps.
Page 7 - change involves human factoring attachment title and modifying information to ensure consistency with NRC guidance.
Page 8 - change involves adding information regarding the support of the Unit I Operator in staffing the ERO.
Page 9 - Updated information for the Unit Operator to use during the ERO staffing process.
Page 10 - change involved adding a clarify statement concerning the appropriate use of the Follow-up Notification Form.
ALERT EBROWNS FERRY AEE I
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 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 REVISION25
ALERT EPIP-3 BROWNS FERRY 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.
Control Rooms D-Plant PA Announcement E
This is NAME. Site Emergency Director, an Alert has been declared at BFN. wýe are currently implementing EPIP-3. Standby for fuirther updates.
INITLAI.S TIMEF 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 (Initial Notification Form).
3.2.2 Direct the Unit 1, Unit Operator to make notifications from Attachment B (Unit 1, Unit Operator Notification) 3.2.3 Notify the ODS and Provide the information from 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.
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 state was contacted directly).
INITL-gLS TE INITLU.S Tntw INITIALS
'"nE INITLA.LS T"IME INITI*ALS TBiE PAGE 2 OF 10 CECC TSC OSC F-1 REVISION25
ALERT E
BROWNS FERRY I r-3 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.3 NOTIFICATION OF SITE PERSONNEL 3.3.1 Make the following plant P.A. announcement:
INrrIALS 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, activate the Accountability Alarm. (Reference EPIP-8)
I.NfL&LS TIMIE (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.
(N/A STEP IF NOT APPLICABLE)
INIALS TIME 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 REVISION25
ALERT EPIP-3 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.6 NOTIFICATION OF THE NRC 3.6.1 Notify the NRC immediately or within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and if 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, by dialing 9-1 "The Ten Digit Number Listed on the ENS Telephones".
If the number is busy, Then select in order, the alternate numbers until a connection is achieved. No access codes are required.
INITLALS TiME PAGE 4 OF 10 REVISION25
ALERT TBROWNS FERRY EPIP-3 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 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
"* NRC (ENS) 0 CONTROL Rooms
"* TSC 0
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 REVISION25
ALERT EPIP-3 BROWNS FERRY 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).
3.8.2 EP shall forward to the PORC Secretary the completed EPIP and all attachments for review by PORC.
3.8.3 PORC Review Completed.
INITIALS TIM INITLALS TwIE
/
PORC Chairman DATE 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 4.0 ATTACHMENTS INITAL S Attachment A - Initial Notification Form Attachment B - Unit 1, Unit Operator Notification Attachment C - Follow Up Information Form PAGE 6 OF 10 Tmwa REVISION25
ALERT EPIP-3 BROWNS FERRY NUCLEAR PLANT ATTACHMENT A (Page 1 of 1)
INITIAL NOTIFICATION FORM ALERT F-- THIS IS A REAL EVENT F-- THIS IS A DRILL This is An ALERT has been declared at Browns Ferry affecting:
-] Unit 1 Event Declared:
-] Unit 2 Time:
1-Unit 3 E] Common Date:
EAL Designator:
Brief Description of the Event:
Radiological Conditions:
F-- No Abnormal Releases Offsite F-D Airborne Release Offsite F-- Liquid Release Offsite D-Release Information Not Known at this time
-- There is no Protective Action Recommendation at this time.
F-1 Ask "Please repeat the information you have received to ensure accuracy."
PAGE 7 OF 10 REVISION25
ALERT BROWNS FERRY EPIr-3 NUCLEAR PLANT ATTACHMENT B (Page 1 of 2)
Unit 1, Unit Operator NOTIFICATION Date:
- 1. Activate the Automatic Paging System (APS).
INITIALS TIME Note: Monitor paging system terminal display. If a "NO" response is observed or if the position being paged has not responded within approximately 20 minutes, utilize the "Weekly Duty List" and attempt to contact the position representative. If contact can not be established, utilize the "Call-Out List" and attempt to contact an alternate position representative. Continue until all positions are filled.
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.
INITLALS TLME
- 3. Notify Nuclear Security Shift Supervisor and state "AN ALERT HAS BEEN DECLARED" and direct to LNITLALS TIME activate EPIP-1 1, 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 LNITIALS Tmf" 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 LNITLS TIME activate EPIP-14, Radiological Control Procedure.
Plant Extension 2300 or 3104 PAGE 8 OF 10 REVISION25
ALERT EPIP-3 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 2 of 2)
Unit 1, Unit Operator NOTIFICATION
- 6. Notify the "On-Call" NRC Resident and state "AN ALERT HAS BEEN DECLARED," per BFN-EPIP-03.
Plant Extension 2572 [Secretary]
from weekly duty list Date:
/
/
INITLALS TIME or
- 7. IF the APS did not operate properly, Make notifications from the current weekly duty list. If the individuals on the weekly duty list cannot be contacted, Make notifications from the Call Out List. Notify the SED of the condition.
PAGE 9 OF 10 INITLALS TIME REVISION25
ALERT EPIP-3 BROWNS FERRY NUCLEAR PLANT ATTACHMENT C (Page 1 of 1)
FOLLOW-UP INFORMATION FORM ALERT
-- THIS IS A REAL EVENT Fl-THIS IS A DRILL Note: This form is for conducting Follow-up Information only.
This is at Browns Ferry.
Name There has been a Alert declared at Browns Ferry affecting:
-] Unit I
-] Unit 2
-] Unit 3
-] Common The Reactor is --] Shutdown R] At Power Plant Conditions are [] Stable K-Deteriorating "Follow-Up" Information (e.g., Key Events, Status Changes)
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)
-- 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 REVISION25
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-4 SITE AREA EMERGENCY REVISION 24 PREPARED BY: TIM CORNELIUS RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS APPROVED BY: GILBERT V.LITTLE PHONE: 2038 DATE: 03/09/2001 EFFECTIVE DATE:03/31/2001 LEVEL OF USE: REFERENCE USE QUALITY-RELATED
REVISION LOG Procedure Number:
EPIP-4 Revision Number:
24 Pages Affected: 2,3,6,7,8,9,11 Description of Change:
IC-31 This change is being conducted to incorporate a manual method of evacuating on-site, non emergency response personnel during emergency situations. In addition changes to the procedure are being conducted to incorporate the management of NRC Commitment changes as prescribed in the correspondence from site licensing RIMS R08000217713, and to human factor the notification and followv-up notification forms.
Page 2 - change to step 3.2.1 involves human factoring the Notification Form Title.
Page 3- -changes to steps 3.4.1 - 3.4.5 involves information regarding steps for the SED to take when conducting an Accountably/Assembly and Evacuation.
Page 6 - changes involves removing the "NRC Commitment Brackets to step requiring the reviewx of PORC and the human factoring of applicable steps.
Page 7 - change involves human factoring attachment title.
Page 8 - change involves human factoring attachment title and modifying information to ensure consistency with NRC guidance.
Page 9 - change involves adding information for Unit 1 Operator regarding ERO staffing support.
Page 10 - updated information for the Unit Operator to use during the ERO staffing process.
Page 11 - change involved adding a clarifi-statement concerning the appropriate use of the Follow -up Notification Form.
SITE AREA BROWNS FERRY EMERGENCY EPIP-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 1 OF 11 REVISION 24
SITE AREA EMERGENCY EPIP-4 BROWNS FERRY 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.
Control Rooms D-Plant PA Announcement E
This is NAMIE. Site Emergency Director. an SAE has been declared at BFN, we are currently implementing EPIP-4. Standby for futrther updates.
INTIATLS TmIE 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 (Initial Notification Form).
3.2.2 Direct the Unit 1, Unit Operator to make notifications from Attachment B (Unit 1, Unit Operator Notification) 3.2.3 Notify the ODS and Provide the information from 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 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 the State of Alabama)(NA this step, if the state was contacted directly).
PAGE 2 OF 11 INITIALS TIME INITIALS TIME INITIALS Tu'tF INITIALS TiME INITIALS TErME REVISION 24 CECC TSC OSC D
D D
SITE AREA EMERGENCY EPIP-4 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.3 NOTIFICATION OF SITE PERSONNEL 3.3.1 Make the following plant P.A. announcement:
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 If Accountability has not been conducted Then, continue in this procedure. If Accountability has been conducted, Then continue in this procedure at step 3.4.4.
3.4.2 Prior to sounding the Accountability Alarm, Notify Nuclear Security. If the TSC is staffed Then notify the TSC Security Manager. I.f the TSC is not staffed or the TSC Security Manager position has not been filled Then call 3150 or 2219.
3.4.3 Activate the Accountability Alarm. (Reference EPIP-8) 3.4.4 When accountability is complete, Initiate the order for the Evacuation of non-emergency responders. Notify Nuclear Security to conduct an evacuation of non emergency responders and implement EPIP-8, step 3.4.3.
3.4.5 Notify the CECC Director of the Evacuation Order, If the CECC is not staffed, Then notify the ODS.
I INITIAS TIME INITIALS TIME INITIALS TIME INITIALS TIME INITIALS TIME PAGE 3 OF 11 REVISION 24
SITE AREA EMERGENCY EPIP-4 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.5 DOSE ASSESSMENT 3.5.1 Evaluate the need for offsite dose assessment.
(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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and if 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, by dialing 9-1 "The Ten Digit Number Listed on the ENS Telephones".
If the number is busy, Then select in order, the alternate numbers until a connection is achieved. No access codes are required.
INITLALS TLiE INITIL.LS TI PAGE 4 OF 11 REVISION 24
SITE AREA 4
BROWNS FERRY EMERGENCY LI*
-4 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 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 24
SITE AREA EMERGENCY EPIP-4 BROWNS FERRY 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
"* NRC (ENS)
"* TSC
"* OSC
"* CONTROL ROOMs
"* 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 Preparedness (EP).
3.8.2 EP shall Forward to the PORC Secretary the completed EPIP and all attachments for review by PORC.
3.8.3 PORC Review Completed.
INITLALS TrmLE INITUA.LS TmIE
/
PORC Chairman 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 TLNf PAGE 6 OF 11 DATE REVISION 24
SITE AREA EPIP BROWNS FERRY EMERGENCY NUCLEAR PLANT 4.0 ATTACHMENTS Attachment A - Initial Notification Form Attachment B - Unit 1, Unit Operator Notification Attachment C - Follow Up Information Form PAGE 7 OF 11 REVISION 24
SITE AREA 4
BROWNS FERRY EMERGENCY EPIP-4 NUCLEAR PLANT ATTACHMENT A (Page 1 of 1)
INITIAL NOTIFICATION FORM SITE AREA EMERGENCY F-- THIS IS A REAL EVENT F-- THIS IS A DRILL This is N,)-NIE An SITE AREA EMERGENCY has been declared at Browns Ferry affecting:
-- Unit I F-- Unit 2 F--
Unit 3
-- Common Event Declared:
Time:
Date:
EAL Designator:
Brief Description of the Event:
Radiological Conditions:
F--
No Abnormal Releases Offsite F-- Airborne Release Offsite F-1 Liquid Release Offsite F-- Release Information Not Known at this time F-- There is no Protective Action Recommendation at this time.
Meteorological conditions are:
Wind Speed:
mph.
Wind Direction From:
degrees F-- Ask "Please repeat the information you have received to ensure accuracy.
PAGE 8 OF 11 REVISION 24
SITE AREA EMERGENCY EPIP-4 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 1 of 2)
Unit 1, Unit Operator NOTIFICATION
- 1. Activate the Automatic Paging System (APS).
Note: Monitor paging system terminal display. If a "NO" response is observed or if the position being paged has not responded within approximately 20 minutes, utilize the "Weekly Duty List" and attempt to contact the position representative. If contact can not be established, utilize the "Call-Out List" and attempt to contact an alternate position representative. Continue until all positions are filled.
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.
- 3. Notify Nuclear Security Shift Supervisor and state "A SITE AREA EMERGENCY HAS BEEN DECLARED,"
and direct to activate EPIP-11, Security and Access Control.
Plant Extension 3150 or 2219
- 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 AREA EMERGENCY HAS BEEN DECLARED,"
and direct to activate EPIP-14, Radiological Control Procedure.
Plant Extension 2300 or 3104 Date:
INITIALS TAIE INITIALS T1NrE INITLALS TIME INITIALS TIaE INITIALS TMEU PAGE 9 OF 11 N
REVISION 24
SITE AREA EMERGENCY EPIP-4 BROWNS FERRY 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,"
per BFN-EPIP-04.
Plant Extension 2572 [Secretary]
from weekly duty list INITLALS or
- 7. IF the APS did not operate properly, Make notifications from the current weekly duty list. If the individuals on the weekly duty list cannot be contacted, Make notifications from the Call Out List. Notify the SED of the condition.
INITLALS TrIE PAGE 10 OF 11 TiME REVISION 24
SITE AREA EMERGENCY EPIP-4 BROWNS FERRY NUCLEAR PLANT
--I THIS IS A REAL EVE ATTACHMENT C (Page 1 of 1)
FOLLOW-UP INFORMATION FORM SITE AREA EMERGENCY ENT F1-THIS IS A DRILL Note: This form is for conducting Follow-up Information only.
This is at Browns Ferry.
Name There has been a Site Area Emergency declared at Browns Ferry affecting:
[-1 Unit 1 E] Unit 2 E-Unit 3
[- Common The Reactor is L-- Shutdown L-- At Power Plant Conditions are [I-Stable
-- Deteriorating "Follow-Up" Information (e.g., Key Events, Status Changes)
Current Radiological Conditions are:
-- No Abnormal Releases Offsite
-] Airborne Release Offsite F-Liquid Release Offsite F--
Release Information Not Known Additional Rad information: (e.g., release duration)
M 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 24
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-5 GENERAL EMERGENCY REVISION 29 PREPARED BY: TIM CORNELIUS RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS APPROVED BY: GILBERT V. LITTLE EFFECTIVE DATE: 03/31/2001 LEVEL OF USE: REFERENCE USE PHONE: 2038 DATE: 03/09/2001 QUALITY-RELATED
REVISION LOG Procedure Number:
EPIP-5 Revision Number:
29 Pages Affected:
2,3,4,6,7,8,9,12 Description of Change:
IC-37 This change is being conducted to incorporate a manual method of evacuating on-site, non emergency response personnel during emergency situations. In addition changes to the procedure are being conducted to incorporate the management of NRC Commitment changes as prescribed in the correspondence from site licensing RIMS R08000217713. and to human factor the notification and follow-up notification forms.
Page 2 - change to step 3.2.1 involves human factoring the Notification Form Title and revised telephone for Morgan County.
Page 3/4 - changes to steps 3.4.1 - 3.4.5 involves information regarding steps for the SED to take when conducting an Accountably/Assembly and Evacuation.
Page 6 - changes involves removing the "NRC Commitment Brackets to step requiring the review of PORC and the human factoring of applicable steps.
Page 7 - change involves human factoring attachment title.
Page 8 - change involves human factoring attachment title.
Page 9 - change involves adding information for Unit 1 Operator regarding ERO staffing support.
Page 10 - revised to update information supporting Unit I Operator actions regarding ERO staffing support.
Page 11 - revised Protective Action Recommendation Flowchart.
Page 12 - change involved adding a clarifr' statement concerning the appropriate use of the Follow-up Notification Form.
GENERAL BROWNS FERRY EMERGENCY EPIP-)
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 29
GENERAL EMERGENCY EPIP-5 BROWNS FERRY 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.
F1 F
Control Rooms
[-
Plant PA Announcement E
This is NANME. Site Emergency Director. an GE has been declared at BFN. we are currently implementing EPIP-5. Standby for firther updates.
INITLALS Tm 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 (Initial Notification Form).
3.2.2 Direct the Unit 1, Unit Operator to make notifications from Attachment B (Unit 1, Unit Operator Notification) 3.2.3 Notify the ODS and Provide the information from 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
- 2. Morgan County:
- 3. Lawrence County:
9-1-256-432-2143 9-1-256-974-7641
- 4. Lauderdale County:
9-1-256-760-9117
- 5. State of Alabama Rad Health Duty Officer:
Day Shift 8 a.m. - 5 p.m.
9-1-334-206-5391 Holidays-Weekends-Offshifts 9-1-334-242-4378 INITLALS TIME INTITLNLS TumE 1.NrT L--'LS TLNEF INITLALS TIME INITIALS TIMlE INITLiiLS TNME INITLALS TLmE INITIALS TBE PAGE 2 OF 12 REVISION 29
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.2.4 Fax a copy of Attachment A to the ODS for confirmation of information or the state if contacted directly.
ODS Fax 5-751-8620 AL Rad Health 9-1-334-206-5387 3.2.5 Receive confirmation call from the ODS (to verify 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:
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 If Accountability has not been conducted Then, continue in this procedure. If Accountability has been conducted, Then continue in this procedure at step 3.4.4.
3.4.2 Prior to sounding the Accountability Alarm, Notify Nuclear Security. If the TSC is staffed Then 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.
3.4.3 Activate the Accountability Alarm. (Reference EPIP-8)
INITIALS TIME INITIALS TiME INITLILS TIME INrTIALS TBIE PAGE 3 OF 12 INITIALS TBIiE INITIALS TIME REVISION 29
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.4 ACCOUNTABILITY AND EVACUATION OF NON-EMERGENCY RESPONDERS (CONTINUED) 3.4.4 When accountability is complete, Initiate the order for the Evacuation of non-emergency responders. Notify Nuclear Security to conduct an evacuation of non emergency responders and implement EPIP-8, step 3.4.3.
3.4.5 Notify the CECC Director of the Evacuation Order, If the CECC is not staffed, Then notify the ODS.
3.5 DOSE ASSESSMENT 3.5.1 Evaluate the need for offsite dose assessment.
(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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and if 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, by dialing 9-1 "The Ten Digjt Number Listed on the ENS Telephones".
If the number is busy, Then select in order, the alternate numbers until a connection is achieved. No access codes are required.
INITLALS TnME INTrIALS TIm INITLALS TI"151.
INITLALS
- TIMEf, PAGE 4 OF 12 REVISION 29
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.7 PROTECTIVE ACTION RECOMMENDATION 3.7.1 If the CECC is not staffed, Then make a Protective Action Recommendation (PAR) using Attachment C.
(This PAR shall be made only by the SED.) (N/A STEP IF NOT APPLICABLE)
INITIALS TIME 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.
9-1-334-206-5391 Holidays-Weekends-Offshifts 9-1-334-242-4378 PAGE 5 OF 12 REVISION 29
GENERAL EMERGENCY EPIP-5 BROWNS FERRY 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
"* NRC (ENS)
"* TSC
"* OSC
"* CONTROL RooMs
"* PLANT PA ANNOUNCEMENT 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 Preparedness (EP).
3.9.2 EP shall Forward to the PORC Secretary the completed EPIP and all attachments for review by PORC.
3.9.3 PORC Review Completed.
INITULS Tmw INvTi ulS TIME PORC Chairman 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 DATE REVISION 29
GENERAL BROWNS FERRY EMERGENCY Ir
-5 NUCLEAR PLANT 4.0 ATTACHMENTS Attachment A - Initial Notification Form Attachment B - Unit 1, Unit Operator Notification Attachment C - Protective Action Recommendations Attachment D - Follow Up Information Form PAGE 7 OF 12 REVISION 29
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT ATTACHMENT A (Page 1 of 1)
INITIAL NOTIFICATION FORM GENERAL EMERGENCY F] THIS IS A REAL EVENT F-1 THIS IS A DRILL This is There has been a GENERAL EMERGENCY declared at Browns Ferry affecting:
D-- Unit I
-] Unit 2 Event Declared:
F-- Unit 3 Time:
Common Date:
EAL Designator:
Brief Description of the Event:
Radiological Conditions:
No Abnormal Releases Offsite Airborne Release Offsite
[
Liquid Release Offsite F-- Release Information Not Known at this time The following Protective Action Recommendation is provided Recommendation I - Evacuate 2 mile radius and 10 miles downwind and shelter remainder of 10 mile EPZ.
F-- Recommendation 2 - Evacuate 2 mile radius and 5 miles downwind and shelter remainder of 10 mile EPZ.
Meteorological Conditions are:
Wind Speed:
m.p.h.
Wind Direction From:
degrees D Ask, "Please repeat the information you have received to ensure accuracy."
PAGE 8 OF 12 REVISION 29
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 1 of 2)
Unit 1, Unit Operator NOTIFICATION
- 1. Activate the Automatic Paging System (APS).
Note: Monitor paging system terminal display. If a "NO" response is observed or if the position being paged has not responded within approximately 20 minutes, utilize the "Weekly Duty List" and attempt to contact the position representative. If contact can not be established, utilize the "Call-Out List" and attempt to contact an alternate position representative. Continue until all positions are filled.
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.
- 3. Notify Nuclear Security Shift Supervisor and state "A GENERAL EMERGENCY HAS BEEN DECLARED," and direct to activate EPIP-11, Security and Access Control.
Plant Extension 3150 or 2219
- 4. Notify the Chemistry Lab Supervisor and state "A GENERAL 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 GENERAL EMERGENCY HAS BEEN DECLARED," and direct to activate EPIP-14, Radiological Control Procedure.
Plant Extension 2300 or 3104 Date:
INITIALS TIME INITIALS TalE INITIALS TaIE INITIALS TIME INITIALS TIUE PAGE 9 OF 12 REVISION 29
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 2 of 2)
Unit 1, Unit Operator NOTIFICATION
- 6. Notify the "On-Call" NRC Resident and state "A GENERAL EMERGENCY HAS BEEN 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 weekly duty list. If the individuals on the weekly duty list cannot be contacted, Make notifications from the Call Out List. Notify the SED of the condition.
Date:
/
/
INITLALS TMIE INITIALS TwE PAGE 10 OF 12 REVISION 29
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT ATTACHMENT C (Page 1 of 1)
PROTECTIVE ACTION RECOMMENDATIONS Note 1: If conditions are unknown utilizing the flowchart, then answer NO.
General Emergency CONTINUE AI DEcla d
I
- Modify protectiv A.
_!n IV
_1II Imonitorii
- Locate air hot spots.
or beyond 5 miles is the ProjectedN or Measured Dose Greater than PAG Table 1 Limits YES SSESSMENT e actions based ie plant anu iielu ig information.
id evaluate localized I~
PAGE 11 OF 12 RECOMMENDATION 1 EVACUATE 2 miles radius and 10 miles downwind AND SHELTER remainder of 10 mile EPZ RECOMMENDATION 2 EVACUATE 2 mile radius and 5 miles downwind AND SHELTER remainder of 10 mile EPZ TABLE 1 Protective Action Guides TYPE LIMIT Measured 3.9E-6 micro Ci/cc of Iodine 131 or 1 REM/hr External Dose Projected 1 REM TEDE or 5 REM Thyroid CDE k.-:
I Nil fllVflll Iflll A
A A
A REVISION 29
GENERAL EMERGENCY EPIP-5 BROWNS FERRY NUCLEAR PLANT ATTACHM/ENT D (Page I of 1)
FOLLOW-UP INFORMATION FORM GENERAL EMERGENCY ElTHIS IS A REAL EVENT F-1 THIS IS A DRILL Note: This form is for conducting Follow-up Information only.
This is at Browns Ferry.
Name There has been a General Emergency declared at Browns Ferry affecting:
F-- Unit 1 El Unit 2 F-- Unit 3 El Common The Reactor is E-l Shutdown Plant Conditions are F-- Stable El At Power E-l Deteriorating "Follow-Up" Information (e.g., Key Events, Status Changes, Status of any Plant Evacuations)
Current Radiological Conditions are:
R--
No Abnormal Releases Offsite F-- Airborne Release Offsite F-1 Liquid Release Offsite E-- 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:
F-- Recommendation I F-- Recommendation 2 Please repeat the information you have received to ensure accuracy.
The time for this follow up is:
SIGNATURE:
Time:
Date:
LAST PAGE PAGE 12 OF 12 REVISION 29
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-8 PERSONAL ACCOUNTABILITY AND EVACUATION REVISION 13 PREPARED BY:
TIM CORNELIUS RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS APPROVED BY: GILBERT LITTLE PHONE: 2038 DATE: 03/09/2001 EFFECTIVE DATE: 03/31/2001 LEVEL OF USE: REFERENCE USE QUALITY-RELATED
REVISION LOG Procedure Number:
EPIP-8 Revision Number:
13 Pages Affected:
All Pagination Pages:
None Description of Change:
IC-16 This revision is being conducted to incorporate a manual method of evacuating on-site, non-emergency personnel during emergency situations. This revision will eliminate the 3-minute steady siren for evacuation purposes.
Page 1 - Revise the purpose and scope to more accurately describe the intent of the procudure.
Page 2 - Revised to manage personnel being escorted for the purposes of evacuation.
Page 3 - Human factored terms to more accurately address intent.
Page 4 - Delete the information regarding the use of the 3-minute steady siren for evacuation purposes and provide information for managing non-emergency responders utilizing the manual evacuation process.
Page 5 - Revise information regarding use of exit card readers. Revise responsibilities of SED, and Nuclear Security.
Page 6 - Revise listing of Assembly Areas outside the protected area and title of attachment.
Page 7 - Revised the title of attachment.
Page 9. 10 - Created new attachment "Evacuation Checklist". which defines the process for the manual evacuation.
PERSONNEL ACCOUNTABILITY 8
BROWNS FERRY AND EVACUATION EPIP-0 NUCLEAR PLANT 1.0 PURPOSE The purpose of this procedure is to provide a means for administering a protective action response such as the capability to account for all individuals onsite within the "Protective Area (PA)" and for the evacuation of all on-site non-emergency personnel. The procedure is written to prescribe the actions and responsibilities necessary to account for all personnel inside the PA and evacuate non-emergency personnel located within the owner controlled area during an emergency situation.
2.0 SCOPE The scope of this procedure includes employees having and not having emergency assignments, visitors, contractor and construction personnel and other persons who may be within the owner controlled area during an emergency situation.
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 1 OF 10 REVISION 13
PERSONNEL ACCOUNTABILITY BROWNS FERRY AND EVACUATION E rIP-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 Public Address (PA) announcement similar to - "Attention All Personnel, conditions in the (area to 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, PA Announcement or See associated Strobe Lights, 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 a Plant Evacuation is ordered. See step 3.4.1.2 for instructions regarding Plant Evacuation.
3.3.1.3 Emergency Responders, upon hearing the Assembly and Accountability Siren PA Announcement or associated Strobe Lights, shall proceed immediately to their designated assembly area as listed on Attachment B.
Upon arriving at the designated assembly area swipe your badge into the Accountability Card Reader and Sign the Accountability Roster Form, Attachment C. If you are a emergency responder and have escort responsibilities, please take the applicable steps to have the visitor transferred to a non-emergency responder and re-located to an appropriate assembly area. If a Plant Evacuation is ordered, all Emergency Responders will remain in their designated assembly area.
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 10 REVISION 13
PERSONNEL ACCOUNTABILITY BROWNS FERRY AND EVACUATION EPIr-0 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 re-locate personnel from designated assembly areas to other assembly 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.
3.3.3 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 officer(s) 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 10 REVISION 13
PERSONNEL ACCOUNTABILITY BROWNS FERRY AND EVACUATION EPIP-8 NJCLEARPLANT 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 Site Evacuation will be conducted upon an order by the SED to initiate a Site Evacuation.
3.4.1.2 All Non-Emergency Responder Assembly Areas will be evacuated in an orderly manner. Non-Emergency Responders should remain in their designated assembly area until released to evacuate either by plant public address announcement or Nuclear Security personnel. For non emergency personnel assembled within the protected area, when released, proceed to the appropriate protected area exit portal. Swipe your 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. For non emergency personnel assembled outside the protected area, proceed to your vehicle and evacuate from the site to your place of residence. All personnel exiting the site area should anticipate that site area checkpoints will be established and that Radcon will be monitoring vehicles as they exit, if conditions warrant. Additionally exit routes may be suggested by Nuclear Security, please follow all guidance provided by appropriate site personnel during the conduct of a site evacuation. Upon exiting the owner controlled area follow all guidance at this time of state and local authorities, where applicable.
3.4.1.3 Emergency Responders, shall remain in designated assembly areas.
PAGE 4 OF 10 REVISION 13
PERSONNEL ACCOUNTABILITY AND EVACUATION EPIP-8 BROWNS FERRY NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.4 Site Evacuation (continued) 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 for any reason the Exit Card Reader will not acknowledge acceptance your badge indicated by receiving the green indicator light, call Nuclear Security at extension 3238 or 2219.
3.4.2 When required the SED shall:
3.4.2.1 Initiate the Site Evacuation Order.
3.4.2.2 Notify Nuclear Security to implement EPIP-8 steps 3.4.3.
3.4.3 Upon the notification of the Order to conduct a Site Evacuation, Nuclear Security shall:
3.4.3.1 Complete Attachment D.
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 Attachment B Attachment C Attachment D -
Non-Emergency Responder Assembly Areas Emergency Responder Emergency Facility/Assembly Areas Accountability Roster Form Evacuation Checklist PAGE 5 OF 10 REVISION 13
PERSONNEL ACCOUNTABILITY AND EVACUATION EPIP-8 BROWNS FERRY NUCLEAR PLANT ATTACHMENT A Page 1 of 1 NON EMERGENCY RESPONDERS ASSEMBLY AREAS Designated Assembly Area Maintenance Shop Plant Assembly Room Maintenance Building Plant Engineering Building West Access Portal Exit East Access Portal Exit Plant Managers Office Foyer Area Reporting Organizations Maintenance Production personnel (except for IM)
Maintenance Program Support personnel Work Control Center personnel Work Control/Outage personnel Instrument Mechanic (IM) Shop personnel Maintenance Support personnel Site Engineering - System Engineering personnel Radwaste personnel All other organizations not listed and the west portal is your regular entry point.
All other organizations not listed and the west portal is your regular entry point.
Plant Manager's office staff Operations office staff Maintenance office staff RADCON office staff Outage Office Staff 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
"* Common Maintenance Building
"* BFN Training and Visitor Center
"* Materials Procurement Complex
"* Modifications Fabrication Shop
"* Modifications Administration Building PAGE 6 OF 10 REVISION 13
PERSONNEL ACCOUNTABILITY 8
BROWNS FERRY AND EVACUATION EPIP-8 NUCLEARPLANT ATTACHMENT B Page 1 of 1 EMERGENCY RESPONDERS EMERGENCY FACILITY/ASSEMBLY AREAS Designated Assembly Area 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 10 REVISION 13
PERSONNEL ACCOUNTABILITY AND EVACUATION EPIP-8 BROWNS FERRY NUCLEAR PLANT ATTACHMENT C Page 1 of 1 ACCOUNTABILITY ROSTER Emergency Response Facility Supervisor In Charge Name (Last, First MI)
ERO Position Filled (Staging Area Personnel, OSC Board Writer, etc.)
+
+
.1-t
+
1-
+
+/-
+
+/-
+
+/-
- 1-
+/-
- 1
1-1 1
.1 4
1 4
.9 4
I
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PAGE 8 OF 10 SSN Ext.
4-r REVISION 13
PERSONNEL ACCOUNTABILITY AND EVACUATION EPIP-8 BROWNS FERRY NUCLEAR PLANT ATTACHMENT D Page 1 of 2 EVACUATION CHECKLIST The following checklist shall be utilized by the TSC Nuclear Security Manager or if unavailable the Shift Nuclear Security Supervisor for the purpose of conducting a Site Evacuation when ordered by the SED.
Initials/Time
/
_______________/_____________
______________/____________
Evacuation Checklist Item Control All Protected Area Access, restricting access except for Designated or SED Authorized Emergency Response Personnel.
Establish Owner Controlled Property Road Blocks, On-Site Traffic Controls and Evacuation Checkpoints.
Notify TSC Radcon Manager or if unavailable the on-shift Radcon Shift Supervisor to provide support at Evacuation Checkpoints (if conditions warrant).
TSC Radcon Manager On-Shift Radcon Supervisor 3767 2300
______________/____________
_______________/_____________
Determine evacuation route for personnel exiting the owner controlled property.
- Consult with Radcon concerning off-site environmental radiological hazards (potential plume pathways).
- Consider, if applicable, Local Weather Information to determine hazardous weather conditions.
Suggested Evacuation Route is:
I Shaw Road (North)
Nuclear Plant Road (East)
Shaw Road or Nuclear Plant Road PAGE 9 OF 10 REVISION 13
PERSONNEL ACCOUNTABILITY AND EVACUATION EPIP-8 BROWNS FERRY NUCLEAR PLANT ATTACHMENT D ATTACHMENT D Page 2 of 2 EVACUATION CHECKLIST Initials/Time
/
/
Evacuation Checklist Item All prior items in this listing have been completed.
Utilizing Security Personnel begin the evacuation of "Outside the Protected Area" Assembly Areas.
I-1 F-1 D
D D
BFN Training and Visitor Center Administration Building Materials and Procurement Buiding Common Maintenance Building Modifications Fabrication Shop Modifications Administration Building
_________________/_______________
Utilizing the Plant Public Address System, or Security Personnel begin the evacuation of Assembly Areas within the Protective Area.
I-1
-1:
0 Maintenance Shop Area Plant Assembly Room Maintenance Building Plant Engineering Building Plant Managers Office Foyer Area
_______________/______________
______________/_____________
Evacuation Completed Time Date Notify the SED upon completion of Site Evacuation and request the SED to inform the CECC.
LAST PAGE PAGE 10 OF 10 REVISION 13
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-14 RADIOLOGICAL CONTROL PROCEDURES REVISION 16 PREPARED BY:
T. W. CORNELIUS RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS APPROVED BY: GILBERT LITTLE EFFECTIVE DATE: 03/31/2001 LEVEL OF USE: REFERENCE USE PHONE: 2038 DATE: 03/09/2001 QUALITY-RELATED
REVISION LOG Procedure Number:
EPIP-14 Revision Number:
16 Pages Affected:
6, 7,
11-27 Pagination Pages:
None Description of Change:
IC-20 The revision is being conducted to revise the manual method for calculating total effective dose equivalent and include a method for calculating thyroid committed dose equivalent.
Page 6 Revised the instruction portion of the procedure to include thyroid CDE and add a statement to ensure that Attachment F is completed..
Page 7 Revised to update the title of attachments and the instruction section header.
Page 11-27 Revised to update the method for calculating and reporting the results for TEDE dose projection and include a method for calculating and reporting the results for Thyroid CDE.
RADIOLOGICAL BROWNS FERRY CONTROL PROCEDURES EPIP-NCLEAR PLANT 1.0 PURPOSE The purpose of this procedure is to describe actions and responsibilities of Radiological Controls (RADCON) personnel during a radiological emergency at Browns Ferry.
2.0 SCOPE EPIP-14 will be initiated when RADCON Shift Supervisor or designee receives indications that the Emergency Plan has been activated or information regarding processes contained within this procedure are required.
EPIP-14 contains instructions for RADCON during the implementation of the Emergency Plan event classifications. The procedure additionally contains instructions for RADCON during Site Assembly and Evacuation, RADCON Lab Habitability, Issuance of Potassium Iodide, the use of the Health Physics Network, the Alternate Personnel Decontamination Facility and methods for Projecting Total Effective Dose Equivalent (TEDE) from airborne radioactivity releases.
The method for projecting TEDE from airborne radioactivity releases may be requested by operations to support emergency classification and/or protective action recommendations. The use of this method should only be utilized in the absence of more sophisticated dose models, when the Central Emergency Control Center (CECC) is not activated.
3.0 INSTRUCTIONS 3.1 Notification of Unusual Event 3.1.1 No offsite radiological problems are postulated during a Notification of Unusual Event. (NOUE). This situation should not have any major impact on RADCON.
3.1.2 Although RADCON will not automatically be called, should assistance be needed, RADCON will follow standard practices and procedures during response activities.
PAGE 1 OF 27 REVISION 16
RADIOLOGICAL BROWNS FERRY CONTROL PROCEDURES EPIP-1 4 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.2 Alert 3.2.1 When a Site Assembly is conducted, (see Section 3.4) all RADCON personnel will report to their assigned assembly areas.
3.2.2 If radiological conditions warrant, RADCON personnel will periodically take radiation, airborne (particulate and iodine), and contamination surveys of all assembly areas inside the protected area (Refer to EPIP-8, Attachment "A" and "B" for list of assembly areas).
3.2.3 A RADCON technician will accompany any personnel dispatched into areas of potential radiological hazard.
3.2.4 RADCON personnel will assist in the development of recovery plans as deemed necessary by the recovery organization. Recommendations will be made to keep exposure as low as reasonable achievable and to recommend and approve any clean up activities.
3.3 Site Area Emergency or General Emergency 3.3.1 RADCON technicians report to the lab as directed by their Shift Supervisor or designee. A site evacuation will be conducted at the SAE or GE classification, if not already completed (see Section 3.5).
3.3.2 RADCON personnel will periodically take radiation, contamination and airborne surveys as necessary to ensure no radiological hazards exist in occupied Emergency Response Facilities, (TSC, OSC, Staging Area, RADCON Lab, Chemistry Lab, Control Rooms, or other Operations areas).
3.3.3 A RADCON technician will accompany any personnel dispatched into areas of potential radiological hazard.
3.3.4 Equipment listed in CECC-EPIP-9, Attachment J, Section 1.0 may need to be transported to the environmental monitoring van. Nuclear Security (NS) will allow equipment to be removed from the protected area.
PAGE 2 OF 27 REVISION 16
RADIOLOGICAL BROWNS FERRY CONTROL PROCEDURES EPIP-14 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.3 Site Area Emergency or General Emerciency (continued) 3.3.5 Initial offsite environmental assessment will be conducted per CECC-EPIP-9.
3.3.6 Dispatch RADCON technician to the site access control point established by NS personnel. Survey vehicles and personnel leaving the site using RM-14 friskers (or equivalent) and smear techniques, if radiological conditions warrant.
3.4 Site Assembly and Evacuation 3.4.1 RADCON technicians proceed to the RADCON Lab and read your badge into the accountability reader. If uninhabitable, see Section 3.5.
3.4.2 Sign the Accountability Roster.
3.4.3 If any plant personnel are unaccounted for, NS will form search teams, each having at least one RADCON technician as a part of the team.
3.4.4 RADCON will survey personnel and vehicles leaving the site at the NS access control point, if radiological conditions warrant. Contaminated individuals will be evacuated to the Power Service Shop No. 4 Locker Room at Muscle Shoals Reservation, as directed by the OSC.
3.4.5 Should conditions exist that RADCON cannot survey all people and vehicles leaving the site, RADCON will set up a monitoring station as directed by the SED.
3.5 Radioloaical Control Lab Habitability 3.5.1 [NRC/C] When conditions within the Radcon Lab become uninhabitable the RADCON technicians will proceed to mechanical equipment room, control bay, Unit 3, elevation 617. [NRC/C 81-19-17]
3.5.2 [NRC/C] Report location to the RADCON Manager in the TSC.
[NRC/C 81-19-17]
PAGE 3 OF 27 REVISION 16
RADIOLOGICAL BROWNS FERRY CONTROL PROCEDURES EPIP-14 NUCLEAR PLANT 3.6 Issuing Potassium Iodide (KI) 3.6.1 If the TSC RADCON Manager has reason to believe that a person's projected cumulative dose to the thyroid from inhalation of radioactive iodine might exceed 10 reins (see Attachment A), the exposed person should be started immediately on a dose regimen of KI. This decision shall be immediately communicated to the SED.
3.6.1.1 If the TSC is not staffed or the RADCON Manager position has not been filled, then the senior onsite RADCON Supervisor has the authority to issue KI utilizing the bases describe in step 3.6.1.
3.6.1.2 The initial dose of KI should be not delayed since thyroid blockage requires 30 to 60 minutes. Anyone authorized to initiate KI shall be familiar with the Food and Drug Administration approve package insert and be sure that each recipient is similarly informed.
3.6.1.3 Prior to issuing KI to an individual, the person should be asked if he/she is allergic to iodine. If the person indicates a possible sensitivity to iodine they should not be issued KI.
3.6.2 KI is stored in the plant RADCON supply cage and the REP Van instrument kits.
3.6.3 RADCON normally will not dispense a container or package of KI to TVA Personnel involved in activities to support a radiological emergency.
RADCON will however dispense a single individual dose of KI to team members dispatched from the OSC.
3.6.4 Follow the dosage outlined on the package insert (Attachment B). A copy of the Food and Drug Administration approved package insert shall accompany the issuance of KI. If KI is distributed in individual doses, verbal instructions of the significant information on the package insert by a knowledgeable individual is sufficient.
3.6.5 Complete the KI Issue Report (Attachment C) or an RWP time sheet as appropriate for issuance of KI. An RWP time sheet may be used for this documentation instead of completing the Attachment C. If the RWP time sheet is used to document distribution of the KI, note the time of KI distribution on the back of the time sheet.
PAGE 4 OF 27 REVISION 16
RADIOLOGICAL BROWNS FERRY CONTROL PROCEDURES EPIP-14 NUCLEAR PLANT 3.7 Use of the NRC Health Physics Network (HPN) 3.7.1 The HPN contact with the NRC will be made by the RADCON group.
3.8 Browns Ferry Alternate Personnel Decontamination Facility 3.8.1 The BFN alternate personnel decontamination facility is located at the Power Service Shop No. 4 Locker Room on the Muscle Shoals Reservation. It will be activated when the BFN personnel decontamination facility is inaccessible or incapable of handling the number of contaminated personnel.
3.8.2 When the decision is made to transport contaminated personnel to the alternate decontamination facility, BFN RADCON shall make notifications to the CECC, and the Power Service Shops.
The notification to the CECC shall include all available information at that time. Interface with state and local authorities (i.e., transportation route considerations) will be made available via the CECC.
The notification to the Power Service Shops shall include a request that the Shop 4 sewer lift station sump be emptied, followed by tagging out the power supply to the two pumps. (The sump and control panel are located adjacent to the North East corner of the Gas and Diesel Building, approximately 500 feet east of Shop 4). In the event a volume of effluent in excess of 1800 gallons is anticipated, additional containment capabilities will need to be arranged. The primary point of contact is the Supervisor, Maintenance Group, with the back-up being the Mechanical Supervisor. Notification phone numbers are listed in the Radiological Emergency Notification Directory (REND).
PAGE 5 OF 27 REVISION 16
RADIOLOGICAL BROWNS FERRY CONTROLPROCEDURES EPIP-14 NUCLEARPLANT 3.0 INSTRUCTIONS (CONTINUED) 3.8 Browns Ferry Alternate Personnel Decontamination Facility (continued) 3.8.3 Browns Ferry RADCON is responsible for the following:
Providing appropriate personnel and equipment to operate the alternate decontamination facility.
Calculating the amount of radioactive material in the decontamination effluent. Effluent releases will be in accordance with Standard Program and Process (SPP) - 5.1.
Documenting appropriate records on all contaminated personnel.
0 Ensuring the alternate decontamination facility is secured following decontamination activities and assisting in recovery efforts.
3.9 Method for Projecting Total Effective Dose Equivalent (TEDE) and Thyroid Committed Dose Equivalent (CDE) from Airborne Radioactivity Releases The method for Projecting TEDE and Thyroid CDE from Airborne Radioactivity Releases is by manual method through the application of matrix tables and calculations.
3.9.1 Manual Method for Projecting TEDE and Thyroid CDE from Airborne Radioactivity Releases 3.9.1.1 The Radcon Shift Supervisor/designee or the TSC Radcon representative is responsible for completing Attachment D of this procedure when releases involves a stack release or Attachment E when the release involves a building or ground level release.
The results of the completed attachment "D" and "E" should then be summarized on attachment "F" and forwarded to the Shift Manager I Site Emergency Director.
3.9.1.2 This method for projecting the TEDE and Thyroid CDE from airborne radioactivity releases should only be utilized in the absence of more sophisticated dose models.
3.9.1.3 This method may be requested by the Shift Manager prior to any emergency classification declaration. Results of this method may be utilized to classify emergency conditions, make protective action recommendations or by TSC personnel conducting evaluations of current plant conditions.
PAGE 6 OF 27 REVISION 16
RADIOLOGICAL BROWNS FERRY CONTROLPROCEDURES PIP-14 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.9 Method for Projecting Total Effective Dose Equivalent (TEDE) and Thyroid Committed Dose Equivalent (CDE) from Airborne Radioactivity Releases 3.9.1.4 When requested the appropriate attachment of this procedure should be completed immediately and the results reported to the Shift Manager or SED.
4.0 ATTACHMENTS Attachment A - Occupational Dose From Inhalation of Iodine-1 31 Attachment B - Patient Package Insert Attachment C - Potassium Iodide Issue Report Attachment D - Projecting Total Effective Dose Equivalent (TEDE) and Thyroid Committed Dose Equivalent (CDE) from Stack Airborne Radioactivity Releases Attachment E - Projecting Total Effective Dose Equivalent (TEDE) and Thyroid Committed Dose Equivalent (CDE) from Ground Level Airborne Radioactivity Releases Attachment F - Projected TEDE and Thyroid CDE Assessment Survey Form PAGE 7 OF 27 REVISION 16
RADIOLOGICAL CONTROL PROCEDURES EPIP-14 BROWNS FERRY NUCLEAR PLANT ATTACHMENT A (Page 1 of 1)
OCCUPATIONAL DOSE FROM INHALATION OF IODINE-131 1
10 Exposure Time (hours) 100 PAGE 8 OF 27 1.OOE-03 1.OOE-04 0
E 0
U
,I U
0 1._
4 0
1.OOE-05 1.OOE-06 1.OOE-07 1.OOE-08 1.OOE-09 0.1 REVISION 16
RADIOLOGICAL CONTROL PROCEDURES EPIP-14 BROWNS FERRY NUCLEAR PLANT ATTACHMENT B (Page 1 of 1)
PATIENT PACKAGE INSERT IOSAT Tablets (POTASSIUM IODIDE TABLETS, U.S.P.)
(pronounced poe-TASS-e-um EYE-oh-dyed)
(Abbreviated KI)
TAKE POTASSIUM IODIDE ONLY WHEN PUBLIC HEALTH OFFICIALS TELL YOU IN A RADIATION EMERGENCY, RADIOACTIVE IODINE COULD BE RELEASED INTO THE AIR. POTASSIUM IODIDE (A FORM OF IODINE) CAN HELP PROTECT YOU IF YOU ARE TOLD TO TAKE THIS MEDICINE, TAKE IT ONE TIME EVERY 24 HOURS. DO NOT TAKE IT MORE OFTEN. MORE WILL NOT HELP YOU AND MAY INCREASE THE RISK OF SIDE EFFECTS. DO NOT TAKE THIS DRUG IF YOU KNOW YOU ARE ALLERGIC IODIDE.
(SEE SIDE EFFECTS BELOW.)
INDICATIONS THYROID BLOCKING IN A RADIATION EMERGENCY ONLY.
DIRECTIONS FOR USE Use only as directed be State or local public health authorities in the event of a radiation emergency.
Dose ADULTS AND CHILDREN ONE YEAR OF AGE OR OLDER:
One (1) tablet once a day. Crush for small children.
BABIES UNDER ONE YEAR OF AGE: One half (1/2) tablet once a day. Crush first.
DOSAGE: Take tablets 10 days unless directed otherwise by State or local public health authorities.
Store at controlled room temperature between 150 and 300C (59) to 860F). Keep package dry and foil packets intact.
WARNING POTASSIUM IODIDE SHOULD NOT BE USED BY PEOPLE ALLERGIC TO IODIDE. Keep out of the reach of children. In case of overdose or allergic reaction, contact a physician or the public health authority.
DESCRIPTION Each IOSATTm TABLET contains 130 mg of potassium iodide.
HOW POTASSIUM IODIDE WORKS Certain forms of iodine help your thyroid glands work right.
Most people get the iodine they need from foods, iodized salt or fish. The thyroid can "store" or hold only a certain amount of iodine.
In a radiation emergency, radioactive iodine may be released in the air. This material may be breathed or swallowed, it may enter the thyroid gland and damage it. The damage would probably not show itself for years. Children are most likely to have thyroid damage.
If you take potassium iodide, it will fill up your thyroid gland.
This reduces the change that harmful radioactive iodine will enter the thyroid gland.
WHO SHOULD NOT TAKE POTASSIUM IODIDE The only people who should not take potassium iodide are people who know they are allergic to iodide. You may take potassium iodide even if you are taking medicines for a thyroid problem (for example, a thyroid hormone or antithyroid drug).
Pregnant and nursing women and babies and children may also take this drug.
HOW AND WHEN TO TAKE POTASSIUM IODIDE Potassium Iodide should be taken as soon as possible after public health officials tell you. you should take one dose every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. More will not help you because the thyroid can "hold" only limited amounts of iodine. Larger doses will increase the risk of side effects. You will probably be told not to take the drug for more than 10 days.
SIDE EFFECTS Usually, side effects of potassium iodide happen when people take higher doses for a long time. You should be careful not to take more than the recommended dose or take it for longer than you are told. Side effects are unlikely because of the low dose and the short time you will be taking the drug.
Possible side effects include skin rashes, swelling of the salivary glands, and "iodism" (metallic taste, burning mouth and throat, sore teeth and gums, symptoms of a head cold, and sometimes stomach upset and diarrhea).
A few people have an allergic reaction with more serious symptoms. These could be fever and joint pains, or swelling of parts of the face and body and at times severe shortness of breath requiring immediate medical attention.
Taking iodide may rarely cause overactivity of the thyroid gland, underactivity of the thyroid gland, or enlargement of the thyroid gland (goiter).
WHAT TO DO IF SIDE EFFECTS OCCUR If the side effects are severe or if you have an allergic reaction, stop taking potassium iodide. Then, if possible, call a doctor or public health authority for instructions.
HOW SUPPLIED IOSATT" TABLETS (Potassium Iodide Tablets, U.S.P.)
packages of 14 tablets (NDC 51803-001-01). Each white, round, scored tablet contains 130 mg potassium iodide.
Distributed by ANBEX, INC.
15W. 7 5 th St., New York, N. Y. 10023 PAGE 9 OF 27 REVISION 16
RADIOLOGICAL CONTROL PROCEDURES EPIP-14 BROWNS FERRY NUCLEAR PLANT ATTACHMENT C (Page 1 of 1)
POTASSIUM IODIDE ISSUE REPORT NAME SSN Time of Time of Package Issue Agent Exposure Initial KI Insert Dose Issued
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
- 10.
- 11.
- 12.
- 13.
- 14.
- 15.
- 16.
- 17.
- 18.
- 19.
- 20.
- 21.
- 22.
- 23.
- 24.
- 25.
- 26.
- 27.
- 28.
- 29.
30.
PAGE 10 OF 27 REVISION 16
RADIOLOGICAL BROWNS FERRY CONTROL PROCEDURES EPIP-14 NUCLEARPLANT ATTACHMENT D (Page 1 of 8)
PROJECTING TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) FROM STACK AIRBORNE RADIOACTIVITY RELEASES CAUTION: USE THIS ATTACHMENT FOR STACK RELEASES ONLY DETERMINE RELEASE PATHWAY Contact the affected unit, Unit Supervisor to obtain information regarding the release pathway. The two pathway options for a stack release are; (1) stack (filtered) and (2) stack (unfiltered). Remember that when multiple pathways such as, Stack and Ground-Level, are experienced, both pathway calculations should be conducted and the results summed and recorded on Attachment F, the projected TEDE Thyroid CDE assessment survey form.
Record data on page 5 of this attachment.
DETERMINE ESTIMATED RELEASE START TIME AND RELEASE DURATION Contact the affected unit, Unit Supervisor to obtain information regarding the release start time and duration. Record release duration in hours. If the release duration can not be determined by operations, then a default duration of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> should be utilized.
Record data on page 5 of this attachment.
DETERMINE NOBLE GAS RELEASE RATE IN ItCl/SECOND The Noble Gas Release Rate should be calculated utilizing data obtained from the SPDS terminals under the screen name "MISCRAD". From this screen use the "F5" key to view a tabular form of the instruments utilized by the previous screen. Collect data described as "WIDE RANGE GASEOUS EFFL RAD MON and STACK FLOW".
If the value for the "WIDE RANGE GASEOUS EFFL RAD MON" is equal to or less than 0.00, then discontinue the dose assessment and report that there are no off-site TEDE concerns for the stack release.
Utilize SPDS history to obtain the highest release concentration for the incident. It is recommended that data be reviewed from history approximately thirty (30) minutes prior to the estimated start time as referenced in the preceding step. Place the data in the applicable calculation fields. The completed calculation provides the Noble Gas Release Rate. Record and utilize this rate for the dose assessment calculations.
If SPDS is unavailable, notify affected unit, operations personnel, to gain the information utilizing control room instrumentation, or if unavailable notify the Shift Manager/Site Emergency Director that TI 67, "Determination of Stack and Hardened Wetwell Vent Release Rates" (backup method), procedure must be performed by Radcon and Chemistry personnel.
The following conversion chart can be utilized to convert curies to microcuries.
To CONVERT MULTIPLY BY To OBTAIN Ci 1.0 X 10 6 ptCI Record data on page 5 of this attachment.
PAGE 11 OF 27 REVISION 16
RADIOLOGICAL BROWNS FERRY CONTROL PROCEDURES EPIP-14 NUCLEAR PLANT ATTACHMENT D (Page 2 of 8)
DETERMINE RELEASE TYPE Contact the Plant Assessment Team, Core Damage Assessor (5-751-1633) in the CECC to determine the applicable release type. If the Core Damage Group in the CECC can not be contacted, then use the default release type, "Type 2". The four release type options are; (1) "Type 1", Reactor Coolant System Leakage Release, (2) "Type 2" Fuel Cladding GAP Release, (3) "Type 3", Fuel Over Temperature Release, and (4) "Type 4", Fuel Melt.
Some release types have an additional "F" indicator, this implies that the release type has a filtered release pathway.
Record data on page 5 of this attachment.
DETERMINE METEOROLOGICAL DATA Met data should be obtained from the SPDS terminals under screen name "METDATA" or by accessing the "Met Data Terminal" located in the Technical Support Center.
For stack releases record measurements at the 91 meter instrument readings.
If all Met Data Collection Methods are unavailable contact the National Weather Service by dialing 9-1 205-621-5650. The National Weather Service will provide wind speed and wind direction.
The default value for stability class with no met data available is "D" for stack releases.
The default value for wind speed with no met data available is 4.0 meters/second for the stack.
Record the following data on page 5 of this attachment.
STABILITY CLASS Note: Stability Class may be electronically displayed as 1,2,3.... This corresponds to A,B,C....
WIND SPEED IN METERS/SECOND The following conversion chart can be utilized for conversions to meters/second.
To CONVERT MULTIPLY BY To OBTAIN MILES/H 0.45 METERS/SEC METERS/SEC 2.2 MILES/H KNOTS 0.5 METERS/SEC WIND DIRECTION IN DEGREES PLUME DIRECTION IN DEGREES NOTE: To OBTAIN PLUME DIRECTION, ADD 1800 TO WIND DIRECTION IF < 1800 OR SUBTRACT 18001F WIND DIRECTION IS > 1800.
PAGE 12 OF 27 REVISION 16
RADIOLOGICAL BROWNS FERRY CONTROL PROCEDURES EPIP-14 NUCLEARPLANT ATTACHMENT D (Page 3 of 8)
DETERMINE THE TEDE FACTOR In determining the TEDE Factor you must know the stability class and the wind speed.
Locate the "TEDE Factor" table that corresponds to the applicable stability class located on page 7 of this attachment.
Locate the column within the table that corresponds to the applicable wind speed. If wind speed falls between the two column variables choose the lower value, this is the more conservative factor.
Determine data for the 0.62, 2 and 5 mile distances.
Record data on page 5 of this attachment.
DETERMINE THE TEDE RATIO In determining the TEDE Ratio you must know the release pathway and the release type.
Locate the "TEDE Ratio" table that corresponds to the applicable release pathway located on page 8 of this attachment.
Locate the column within the table that corresponds to the applicable release type. Recall that the "F" indicator for some release types simply indicate that the release type is filtered.
Determine data for the 0.62, 2 and 5 mile distances.
Record data on page 5 of this attachment.
DETERMINE THE THYROID CDE RATIO In determining the Thyroid CDE Ratio you must know the release pathway and the release type.
Locate the "Thyroid CDE Ratio" table that corresponds to the applicable release pathway located on page 8 of this attachment.
Locate the column within the table that corresponds to the applicable release type. Recall that the "F" indicator for some release types simply indicate that the release type is filtered.
Determine data for the 0.62, 2 and 5 mile distances.
Record data on page 5 of this attachment.
PAGE 13 OF 27 REVISION 16
RADIOLOGICAL BROWNS FERRY CONTROL PROCEDURES EPIP-1 NUCLEAR PLANT ATTACHMENT D (Page 4 of 8)
Complete CALCULATIONS AND ATTACHMENT F Input data into applicable calculation fields and calculate. Use caution to input correct factors and ratios for the different mile indications.
Note, to complete the Thyroid CDE calculation, the TEDE calculation must be completed and the TEDE value utilized.
Also use caution when inserting values into the calculations. Use correct terms, i.e. meters/second verses miles/hour.
COMPLETE ATTACHMENT F, PROJECTED TEDE AND THYROID CDE ASSESSMENT SURVEY FORM, AND FORWARD TO THE SHIFT MANAGER OR THE SITE EMERGENCY DIRECTOR. ENTER TEDE VALUES IN REM/HR ON ARROWS FOR APPLICABLE MILEAGE RINGS. SHOW PLUME DIRECTION ON SURVEY MAP BY THE USE OF AN ARROW.
PAGE 14 OF 27 REVISION 16
RADIOLOGICAL CONTROL PROCEDURES EPIP-14 BROWNS FERRY NUCLEAR PLANT ATTACHMENT D (Page 5 of 8)
Stack Release Data Collection and Calculation Worksheet RELEASE PATHWAY El STACK (FILTERED)
[:1 STACK (UNFILTERED)
ESTIMATED RELEASE START TIME ESTIMATED RELEASE DURATION NOTE: IF AN ESTIMATED RELEASE DURATION IS UNKNOWN USE 4 HOURS AS THE DEFAULT RELEASE DURATION.
NOBLE GAS RELEASE RATE _
ItCI/SECOND NOBLE GAS CONCENTRATION
_,CI/CC FLOW RATE SCFM
( _.LCI/CC)
X (
SCFM) X (
472
) =_
IJ.LCI/SECOND RELEASE CONC.
FLOW RATE CONVERSION FACTOR RELEASE RATE RELEASE TYPE LI TYPE 1F (FILTERED)
LI TYPE 2F (FILTERED)
L. TYPE 3F (FILTERED)
LI TYPE 4F (FILTERED)
NOTE: TYPE 2 IS THE DEFAULT RELEASE TYPE.
STABILITY CLASS WIND!
[] TYPE 1 (UNFILTERED)
LI TYPE 2 (UNFILTERED)
LI TYPE 3 (UNFILTERED) r-TYPE 4 (UNFILTERED)
SPEED METERSISECOND WIND DIRECTION DEGREES PLUME DIRECTION DEGREES TEDE FACTOR TEDE RATIO 0.62 MILES 2.0 MILES 5.0 MILES 0.62 MILES 2.0 MILES 5.0 MILES THYROID CDE RATIO 0.62 MILES 2.0 MILES 5.0 MILES PAGE 15 OF 27 REVISION 16
RADIOLOGICAL CONTROL PROCEDURES EPIP-14 BROWNS FERRY NUCLEAR PLANT ATTACHMENT D (Page 6 of 8)
Stack Release Data Collection and Calculation Worksheet TEDE DOSE ASSESSMENT CALCULATIONS 0.62 - 1.99 MILES
(
) X
( _
CI/S) X (
HOURS) X ( __)
TEDE FACTOR RELEASE RATE RELEASE DURATION TEDE RATIO TEDE REM 2.00 - 4.99 MILES
(
_)X(
)
_.t_
s)X(
HOURS)X(
X
=
TEDE REM TEDE FACTOR RELEASE RATE RELEASE DURATION TEDE RATIO 5.00 - 10.00 MILES
(
) X
(
_CI/s)X(
HOURS)X(
X
=
TEDE REM TEDE FACTOR RELEASE RATE RELEASE DURATION TEDE RATIO THYROID CDE DOSE ASSESSMENT CALCULATIONS 0.62 - 1.99 MILES
( T D R x (
) =
TEDE REM THYROID CDE RATIO THYROID CDE REM 2.00 - 4.99 MILES
( TD R x (
) =
TEDE REM THYROID CDE RATIO THYROID CDE REM 5.00 - 10.00 MILES
(
)x(
) =
TEDE REM THYROID CDE RATIO COMPLETE ATTACHMENT F AND FORWARD TO SM/SED.
THYROID CDE REM PAGE 16 OF 27 REVISION 16
RADIOLOGICAL CONTROL PROCEDURES EPIP-14 BROWNS FERRY NUCLEAR PLANT ATTACHMENT D (Page 7 of 8)
TEDE Factor (remlh per RCils) from a BFN Stack Release Stability A
wind speed miles 1 m/s 2 m/s 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s 8 m/s 9 m/s 10 m/s 0.62 mi 1.1E-09 6.0E-10 4.8E-10 3.6E-10 2.4E-10 2.2E-10 1.9E-10 1.7E-10 1.4E-10 1.2E-10 2 mi 4.4E-10 2.2E-10 1.8E-10 1-3E-10 8.7E-11 7.8E-11 7.OE-11 6.1E-11 5.2E-11 4.4E-11 5 mi 7.4E-11 5.2E-11 4.8E-11 4.4E-11 4.OE-11 3.6E-11 3.2E-11 2.8E-11 2.4E-11 2.OE-11 Stability B
wind speed miles 1 m/s 2 m/s 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s 8 m/s 9 m/s 10 m/s 0.62 2.3E-09 1.1E-09 9.3E-10 7.1E-10 4.9E-10 4.4E-10 3.9E-10 3.4E-10 2.9E-10 2.4E-1 2
6.5E-10 3.3E-10 2.7E-10 2.OE-10 1.3E-10 1.2E-10 1.1E-10 9.4E-11 8.OE-11 6.6E-11 5
9.9E-11 6.8E-11 6.6E-11 6.5E-1I 6.4E-11 5.8E-11 5.E-11 4.5E-11 3.9E-11 3.2E-11 Stability C
wind speed miles 1 m/s 2 m/s 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s 8 m/s 9 m/s 10 m/s 0.62 2.0E-09 1.1E-09 9.2E-1C 7.OE-10 4.8E-10 4.4E-10 3.9E-10 3.4E-10 2.9E-10 2.5E-1 2
1.4E-09 8.1E-10 6.5E-1C 4.9E-10 3.3E-10 3.OE-10 2.7E-10 2.3E-10 2.OE-10 1.7E-l1 5
1.6E-10 1.1E-10 1.1E-10 1.1E-10 1.1E-10 1.0E-10 9.OE-11 7.9E-11 6.7E-11 5.5E-11I Stability D
wind speed miles 1 m/s 2 m/s 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s 8 m/s 9 m/s 10 m/s 0.62 1.7E-09 1.1E-09 8.9E-10 6.7E-10 4.6E-10 4.1E-10 3.7E-10 3.2E-10 2.8E-10 2.3E-1C 2
1.9E-09 1.2E-09 9.8E-10 7.6E-10 5.3E-10 4.7E-10 4.2E-10 3.7E-10 3.2E-10 2.6E-1C 5
4.0E-10 3.OE-10 3.1E-10 3.1E-10 3.2E-10 2.9E-10 2.6E-10 2.2E-10 l.9E-1i i.6E-1i Stability E
wind speed miles 1 m/s 2 m/s 3 m/s 4 m/s 5m/s 6m/s 7 m/s 8m/s 9m/s l0m/s 0.62 1.7E-09 1.2E-09 9.7E-10 7.4E-10 5.1E-10 4.6E-10 4.1E-10 3.6E-10 3.1E-10 2.6E-1 2
2.1E-09 1.3E-09 1.1E-09 8.OE-10 5.5E-10 5.0E-10 4.4E-01 3.9E-10 3.4E-10 2.8E-1C 5
6.0E-10 4.3E-10 4.4E-10 4.5E-10 4.6E-10 4.2E-10 3.7E-10 3.2E-10 2.8E-10 2.3E-1 C Stability F
wind speed miles 1 m/s 2 m/s 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s 8 m/s 9 m/s 10 m/s 0.62 1.5E-09 9.9E-10 8.OE-10 6.1E-10 4.2E-10 3.8E-16 3.4E-10 2.9E-10 2.5E-10 2.1E-1l 2
1.8E-09 1.2E-09 9.8E-10 7.6E-10 5.4E-10 4.9E-10 4.4E-10 3.8E-10 3.3E-10 2.8E-1C 5
6.7E-10 4.9E-10 5.1E-10 5.2E-10 5.4E-10 4.9E-10 4.4E-10 3.8E-10 3.3E-10 2.8E-1C Stability G
wind speed miles 1 m/s 2 m/s 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s 8 m/s 9 m/s 10 m/s 0.62 1.5E-09 9.OE-10 7.3E-10 5.5E-10 3.8E-10 3.4E-10 3.OE-10 2.7E-10 2.3E-10 1.9E-1i 2
1.6E-09 9.8E-10 8.1E-10 6.3E-10 4.6E-10 4.2E-10 3.7E-10 3.3E-10 2.8E-10 2.4E-iC 5
5.4E-10 4.OE-10 4.3E-10 4.5E-10 4.8E-10 4.4E-10 3.9E-10 3.5E-10 3.OE-10 2.6E-l(
PAGE 17 OF 27 REVISION 16
RADIOLOGICAL CONTROL PROCEDURES EPIP-14 BROWNS FERRY NUCLEAR PLANT ATTACHMENT D (Page 8of 8)
TEDE RATIOS FOR VARIOUS PATHS AND RELEASE TYPES (STACK Release)
STACK (unfiltered) mi Typel Type2 Type3 Tye4 0.62 1.9 1.9 2.4 5.3 2
2.4 2.4 3.3 8.8 5
3.5 3.5 4.8 13.5 Stack (Filtered) mi Type IF Type 2F Type 3F Type 4F 0.62 1.0 1.0 1.1 1.2 2
1.0 1.0 1.0 1.1 5
1.0 1.0 1.0 1.1 THYROID CDE RATIOS FOR VARIOUS ACCIDENTS AND RELEASE TYPES (STACK Release)
Stack (Filtered) mi Type 1F Type 2F Type 3F Type 4F 0.62 1.6 E-03 1.6 E-03 7.6 E-03 1.4E-02 2
4.4 E-02 4.4 E-02 1.7 E-02 3.0E-02 5
6.9 E-02 6.9 E-02 2.7E-02 4.6E-02 S7ACK (unfiltered) mi Type e Type 2 Type 3 Type 4 0.62 1.1E+00 1.1E+00 3.6E-01 3.1E-01 2
1.8E+00 1.8E+00 5.2E-01 3.7E-01 5
2.OE+00 2.OE+00 5.8E-01 3.7E-01 PAGE 18 OF 27 REVISION 16
RADIOLOGICAL BROWNS FERRY CONTROL PROCEDURES EPIP-14 NUCLEAR PLANT ATTACHMENT E (Page 1 of 8)
PROJECTING TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) AND THYROID CDE FROM GROUND-LEVEL RADIOACTIVITY RELEASES CAUTION: USE THIS ATTACHMENT FOR GROUND-LEVEL RELEASES ONLY DETERMINE RELEASE PATHWAY Contact the affected unit, Unit Supervisor to obtain information regarding the release pathway. The two pathway options for a ground level release are; (1) Containment Bypass (CTM) and (2) Main Steam Line Break (MSLB). Remember that when multiple pathways such as, Stack and Ground-Level, are experienced, both pathway calculations should be conducted and the results summed and recorded on Attachment F, the projected TEDE and Thyroid CDE assessment survey form.
Record data on page 5 of this attachment.
DETERMINE ESTIMATED RELEASE START TIME AND RELEASE DURATION Contact the affected unit, Unit Supervisor to obtain information regarding the release start time and duration. Record release duration in hours. If the release duration can not be determined, then a default duration of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> should be utilized.
Record data on page 5 of this attachment.
DETERMINE NOBLE GAS RELEASE RATE IN gCIISECOND To obtain the Total Noble Gas Release Rate for a building/ground level release the collection of rates from several building exhaust continuous air monitors (CAM) will be required. The Noble Gas Release Rate data should be obtained from a SPDS terminal under the screens "U1CAMS, "U2CAMS", and "U3CAMS". When you reach the applicable window press the "F5" key to retrieve a tabular set of CAM data. Collect all CAM data as petitioned by page 4 of this attachment. Sum all rates together to obtain a Total Building Noble Gas Release Rate. Record and utilize this rate for the dose assessment calculations. Utilize SPDS history to assist in obtaining the highest release rate for the incident. It is recommended that data be reviewed from approximately thirty (30) minutes prior to the estimated start time as referenced in the preceding step.
If SPDS is unavailable, notify affected unit operations personnel to gain the information utilizing control room instrumentation, or through the completion of 0-SI-4.B.1.a.1, Attachment 11.
The following conversion chart can be utilized to convert curies to microcuries.
To CONVERT MULTIPLY BY To OBTAIN Ci 1.0 X 106 l.CI Record data on page 5 of this attachment.
PAGE 19 OF 27 REVISION 16
RADIOLOGICAL BROWNS FERRY CONTROLPROCEDURES EPIP-14 NUCLEARPLANT ATTACHMENT E (Page 2 of 8)
DETERMINE RELEASE TYPE Contact the Plant Assessment Team, Core Damage Assessor (5-751-1633) in the CECC to determine the applicable release type. If the Core Damage Group in the CECC can not be contacted, then use the default release type, "Type 2". The four release type options are; (1) "Type 1", Reactor Coolant System Leakage Release, (2) "Type 2" Fuel Cladding GAP Release, (3) "Type 3", Fuel Over Temperature Release, and (4) "Type 4", Fuel Melt.
Some release types have an additional "F" indicator, this implies that the release type has a filtered release pathway.
Record data on page 5 of this attachment.
DETERMINE METEOROLOGICAL DATA Met data should be obtained from the SPDS terminals under screen name "METDATA" or by accessing the "Met Data Terminal" located in the Technical Support Center.
For ground-level releases record measurements at the 46 meter instrument readings.
If all Met Data Collection Methods are unavailable contact the National Weather Service by dialing 9-1 205-621-5650. The National Weather Service will provide wind speed and wind direction.
The default value for stability class with no met data available is "D" for ground level releases.
The default value for wind speed with no met data available is 2.0 meters/second for ground level releases.
Record the following data on page 5 of this attachment.
STABILITY CLASS Note: Stability Class may be electronically displayed as 1,2,3.... This corresponds to A,B,C....
WIND SPEED IN METERS/SECOND The following conversion chart can be utilized for conversions to meters/second.
To CONVERT MULTIPLY BY To OBTAIN MILES/H 0.45 METERS/SEC METERS/SEC 2.2 MILES/H KNOTS 0.5 METERS/SEC
"* WIND DIRECTION IN DEGREES PLUME DIRECTION IN DEGREES NOTE: To OBTAIN PLUME DIRECTION, ADD 1800 TO WIND DIRECTION IF < 1800 OR SUBTRACT 180°1F WIND DIRECTION IS > 1800.
PAGE 20 OF 27 REVISION 16
RADIOLOGICAL BROWNS FERRY CONTROL PROCEDURES EPIP-14 NUCLEAR PLANT ATTACHMENT E (Page 3 of 8)
DETERMINE THE TEDE FACTOR In determining the TEDE Factor you must know the stability class and the wind speed.
Locate the "TEDE Factor" table that corresponds to the applicable stability class located on page 7 of this attachment.
Locate the column within the table that corresponds to the applicable wind speed. If wind speed falls between the two column variables choose the lower value, this is the more conservative factor.
Determine data for the 0.62, 2 and 5 mile distances.
Record data on page 6 of this attachment.
DETERMINE THE TEDE RATIO In determining the TEDE Ratio you must know the release pathway and the release type.
Locate the "TEDE Ratio" table that corresponds to the applicable release pathway located on page 8 of this attachment.
Locate the column within the table that corresponds to the applicable release type. Recall that the "F" indicator for some release types simply indicate that the release type is filtered.
Determine data for the 0.62, 2 and 5 mile distances.
Record data on page 6 of this attachment.
DETERMINE THE THYROID CDE RATIO In determining the Thyroid CDE Ratio you must know the release pathway and the release type.
Locate the "Thyroid CDE Ratio" table that corresponds to the applicable release pathway located on page 8 of this attachment.
Locate the column within the table that corresponds to the applicable release type. Recall that the "F" indicator for some release types simply indicate that the release type is filtered.
Determine data for the 0.62, 2 and 5 mile distances.
Record data on page 6 of this attachment.
PAGE 21 OF 27 REVISION 16
RADIOLOGICAL BROWNS FERRY CONTROL PROCEDURES EPIP-14 NUCLEAR PLANT ATTACHMENT E (Page 4 of 8)
Complete CALCULATIONS AND ATTACHMENT F Input data into applicable calculation fields and calculate. Use caution to input correct factors and ratios for the different mile indications.
Note, to complete the Thyroid CDE calculation, the TEDE calculation must be completed and the TEDE value utilized.
Also use caution when inserting values into the calculations. Use correct terms, i.e. meters/second verses miles/hour.
COMPLETE ATTACHMENT F, PROJECTED TEDE AND THYROID CDE ASSESSMENT SURVEY FORM, AND FORWARD TO THE SHIFT MANAGER OR THE SITE EMERGENCY DIRECTOR.
ENTER TEDE VALUES IN REM/HR ON ARROWS FOR APPLICABLE MILEAGE RINGS. SHOW PLUME DIRECTION ON SURVEY MAP BY THE USE OF AN ARROW.
PAGE 22 OF 27 REVISION 16
RADIOLOGICAL CONTROL PROCEDURES EPIP-14 BROWNS FERRY NUCLEAR PLANT ATTACHMENT E (Page 5 of 8)
Ground-Level Release Data Collection and Calculation Worksheet RELEASE PATHWAY Rl CTM BYPASS El MAIN STEAM LINE BREAK ESTIMATED RELEASE START TIME ESTIMATED RELEASE DURATION NOTE: IF AN ESTIMATED RELEASE DURATION IS UNKNOWN USE 4 HOURS AS THE DEFAULT RELEASE DURATION.
NOBLE GAS RELEASE RATE _-CI/SECOND DESCRITPTION U0 CAM-RB VENT EXH BETA GAS Ul CAM-RB VENT EXH BETA GAS Ul CAM-TB VENT EXH BETA GAS Ul CAM-TB VENT EXH BETA GAS DESCRITPTION U2 CAM-RB VENT EXH BETA GAS U2 CAM-TB VENT EXH BETA GAS U2 CAM-TB VENT EXH BETA GAS DESCRITPTION U3 CAM-RB VENT EXH BETA GAS U3 CAM-TB VENT EXH BETA GAS U3 CAM-TB VENT EXH BETA GAS TOTAL NOBLE GAS RELEASE RATE CURRENT VALUE
__CI/SEC 4CI/SEC
__CI/SEC
_CI/SEC CURRENT VALUE
__CI/SEC
__CI/SEC
__LCI/SEC CURRENT VALUE
_pCI/SEC
_._CI/SEC
__CI/SEC
_ JCI/SEC RELEASE TYPE El TYPE 1 (UNFILTERED)
El TYPE 2 (UNFILTERED)
[] TYPE 3 (UNFILTERED)
[J TYPE 4 (UNFILTERED)
NOTE: TYPE 2 IS THE DEFAULT RELEASE TYPE.
STABILITY CLASS WIND SPEED METERS/SECOND WIND DIRECTION DEGREES PLUME DIRECTION DEGREES PAGE 23 OF 27 SPDS "Ul CAMS" "FY" "HISTORY" SPDS "U2CAMS" "F5" "HISTORY" SPDS "U3CAMS" "F5" "HISTORY" POINT ID 90-252c0 90-250c0 90-251 cl 90-249cl POINT ID 90-250c2 90-251 c2 90-249c2 POINT ID 90-250c3 90-251 c3 90-249c3 REVISION 16
RADIOLOGICAL CONTROL PROCEDURES EPIP-14 BROWNS FERRY NUCLEAR PLANT ATTACHMENT E (Page 6 of 8)
TEDE FACTOR TEDE RATIO 0.62 MILES 2.0 MILES 5.0 MILES 0.62 MILES 2.0 MILES 5.0 MILES THYROID CDE RATIO 0.62 MILES 2.0 MILES 5.0 MILES TEDE DOSE ASSESSMENT CALCULATIONS 0.62 - 1.99 MILES
( _)X(
.Cl/S) X (
HOURS) X ( __)
TEDE FACTOR RELEASE RATE RELEASE DURATION TEDE RATIO 2.00 - 4.99 MILES
(
)X(
)
iLCl/S) X (
HOURS)X(
X (
TEDE FACTOR RELEASE RATE RELEASE DURATION TEDE RATIO TEDE REM TEDE REM 5.00 - 10.00 MILES
(
) X (
__Cl/s)
X (HOURS)X(
X)=
TEDE REM TEDE FACTOR RELEASE RATE RELEASE DURATION TEDE RATIO THYROID CDE DOSE ASSESSMENT CALCULATIONS 0.62 - 1.99 MILES (T)x(
) =
TIEDE REM THYROID CDE RATIO THYROID CDE REM 2.00 - 4.99 MILES
( T D R x (
) =
TEDE REM THYROID CDE RATIO THYROID CDE REM 5.00 - 10.00 MILES
(_)_
X(
)
_=_THYROID CDE REM TEDE REM THYROID CDE RATIO COMPLETE ATTACHMENT F AND FORWARD TO SM/SED.
PAGE 24 OF 27 REVISION 16
RADIOLOGICAL CONTROL PROCEDURES EPIP-14 BROWNS FERRY NUCLEAR PLANT ATTACHMENT E (Page 7 of 8)
A TEDE FACTOR (reml/hr per g~Cils) FROM A GROUND-LEVEL RELEASE A
1 m/sE1 1.6E-091 5.5E-101 7.5E-11I B
1 m/s 7.5E-09 7.2E-10 9.9E-1 1 C
1 m/s
-2.2E-08
ý_2.9E-09!
1.9E-10 D
1 mis 6.3E-081 1.0E-081 1 8.3E-101 E
1 m/s 1.1E-07 2.1 E-08=
1.8E-09 F I m/s 1
2.2E-071 4.9E-081 4.6E-091 G
1 m/s 1
4.8E-071 1.1 E-07
- 1. 1E-081 2 m/s 8.OE-10 2.8E-10 5.2E-1 1 2 m/s 3.7E-09 3.6E-10 6.8E-1 1 2 m/s1
- 1. 1E-08 1.4E-09 1.311-101 2 m/s 3.2E-08 5.4E-09 5.8E-1 0 2 m/s 5.5E-08 1.0E-08 1.2E-09 2 m/s 1.OE-07 2.5E-08 3.2E-09 2 m/s 2.3E-071 5.1 E-081 7.5E-091 wind speed 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s 8 m/s 6.4E-10 4.8E-10 3.2E-101 2.9E-10 2.5E-10 2.2E-10 2.2E-101 1.7E-10 1.11E-101 1.0E-10 9.OE-11 7.8E-11 5.2E-1 1 5.1 5.1 E-1 1 4.6E-11 4.0E-1 1 3.5E-1 1 wind speed 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s 8 m/s 3.OE-09 2.2E-09 1.4E-09 1.3E-09 1.2E-09 1.0E-09 2.9E-10 2.2E-10 1.4E-1 0 1.3E-1 0 1.2E-10 1.OE-10 6.7E-1 1 6.7E-1 1 6.6E-1 1 6.OE-1 1 5.3E-1 1 4.6E-1 1 wind speed 3 m/s 4 m/s 5 m/s 6 m/s 7 mi/s 8 m/s 9.0E-09 6.7E-09 4.3E-09 3.9E-09 3.5E-09 3.0E-09 1.2E-09 8.8E-10 5.9E-10 5.3E-10 4.7E-101 4.1E-10 1.3E-10 1.3E-10 1.3E-10 1.2E-10 1.iE-1O 9.3E-11 wind speed 3 m/s 4 m/s 5 m/s 6 m/s 7m/s 8m/s 2.6E-08 1.9E-08 1.2E-08 1.1 E-08 1.OE-08 8.8E-09 4.3E-09 3.2E-09 2.2E-09 1.9E-09 1.7E-09 1.5E-09 5.7E-10 5.6E-10 5.6E-10 5.0E-10 4.5E-10 3.9E-10 wind sped 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s 8 m/s 4.4E-08 3.3E-08 2.2E-08 2.0E-08 1.8E-08 1.6E-08 8.3E-09 6.3E-09 4.2E-09 3.8E-09 3.4E-09 2.9E-09 1.2E-09 1.2E-091 1.2E-09 1.1 E-09 9.8E-10 8.6E-10 wind speed 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s 8 m/s 8.3E-08 6.3E-08 4.2E-08 3.8E-08 3.4E-08 3.OE-08 2.OE-08 1.5E-08 9.7E-09 8.8E-09 7.8E-09 6.8E-09 3.1E-09 3.1E-09 3.OE-09 2.7E-09 2.4E-09 2.1 E-09 wind speed 3 m/s 4 m/s 15 ms 6 m/s 7 m/s 1
m/s 1.8E-071 1.4E-07 9.0E-08 8.1 E-08 7.2E-08 6.3E-08 4.OE-08 3.OE-08 2.OE-08 1.8E-081 1.6E-08 1.4E-08 7.3E-09 7.2E-09 7.OE-09 6.3E-09 5.6E-09 4.9E-09 9 m/s1 10 rn/s 6.7E-1 1 5.5E-1 3.0E-1 1 2.5E-1I 9 m/s 10 miis 8.7E-1 1 7.2E-1 1 4.0E-1 11 3.3E-11i 9 m/s 10 rn/s 3.5E-101 29E-1 0 7.9E-111 6.5E-1 1 9m/s lOin/s 9m/s 10 ms 7.5E-09 6.3E-09 1.3E-09 1.0E-09 3.4E-10 2.8E-10 9 m/s 1o10Lm 2.5E-091 2.1 E-09 7.3E-101 6_0E-10 9 m/s 10 m/s 2.6E-08 2.2E-08 5.8E-091 4.9E-09 1.8E-09 15E-00 9 m/s l lm/s 5.4E-08 4.6E-081 1.2E-08 1.OE-08 4.1 E-09 3.4E-09 PAGE 25 OF 27 Stability miles 0.62 mi 2 mi 5 mi Stability miles 0.62 2
5 Stability miles 0.62 2
Stability miles 0.6 2
5 Stability miles 0.62 2
Stability miles 0.62 2
Stability miles 0.62 2
5 REVISION 16 1.2E-091 5
5
RADIOLOGICAL CONTROL PROCEDURES EPIP-14 BROWNS FERRY NUCLEAR PLANT ATTACHMENT E (Page 8 of 8) mi Type 1 0.62 23 2
23 5
55 CTM i Type 2 5.9 6.0 13 TEDE RATIOS FOR VARIOUS PATHS AND RELEASE TYPES ass AISLB Type 3mi Type 4
Type 2 Type 3 7.6 22 0.62 10 10 8.9 7.6 21 2
11 11 9.2 17 52 5
23 23 I
21 Type 4 24 25 59 THYROID CDE RATIOS FOR VARIOUS ACCIDENTS AND RELEASE TYPES CTAI B ass MSLB Type 2 Type 3 Type 4 mi Type e Type 2 Type 3 Type 4 6.2E+00 2.OE+00 1.4E+00 0.62 1.1E+01 1.1E+01 4.8E+00 3.3E+00 6.2E+00 2.OE+00 1.4E+00 2
1.1E+01 1.1E+01 4.8E+00 3.3E+00 6.2E+00 2.OE+00 1.4E+00 5
1.1E+01 1.1E+01 4.8E+00 3.3E+00 PAGE 26 OF 27 mi 0.62 2
5 Type 1 LIE-01 1iE-01 1lE-01 REVISION 16 i
RADIOLOGICAL CONTROL PROCEDURES EPIP-14 BROWNS FERRY NUCLEAR PLANT ATTACHMENT F (Page 1 of 1)
PROJECTED TEDE and Thyroid CDE ASSESSMENT SURVEY FORM
[--
STACK RELEASE
-- GROUND-LEVEL RELEASE TIME OF ASSESSMENT RELEASE RATE CI/s WIND SPEED MILES/HR WIND DIRECTION PREPARED BY STABILITY CLASS PLUME DIRECTION DATE 00 "5
Miles Rem TEDE Rem Thyroid CDE Rem TEDE Rem Thyroid CDE Rem TEDE Rem Thyroid CDE 1800 LAST PAGE PAGE 27 OF 27 2700.
REVISION 16