ML20069P572
| ML20069P572 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| Issue date: | 11/01/1982 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20069P556 | List: |
| References | |
| PROC-821101-01, NUDOCS 8212080112 | |
| Download: ML20069P572 (76) | |
Text
/
s
~
TENNESSEE VALLEY AUTHORITY-BROWNS FERRY NUCLEAR PLANT IMPLEMENTING PROCEDURES DOCUMENT REVISION LOG SHEET
~
. s..
Issue Date: November 1,1982 This log sheet must be retained as the last page df the Brnwns Ferry Nuclear Plant I
Japlementing Procedures Documeq.
=
o Inserted by:
Date Inserted:
Pages to be Removed N w Pages to be Inserted Revision /
Revision /
~
_ Part Panet_ 'llumber Date Part Page Number Date s
List of Effective.-
List of Effective Pages*
1 of 10 10/06/82 Pages 1 of 10 11/01/82 2 of 10 10/06/82 2 of 10 11/01/82 3Jtilo
,10/06/82 3 of le 11/01/82- -
4 of 40 10/06/82 4 of 11/01/81 a
s%cf 10 10/06/82 5 of 19 11/01/82 6'of 10 10/06/82 6 of 10 11/01/82
~;
.s,7 of 10 10/06/82 7 of 10 11/01/82 8 ob 10 10/06/82 8 of 10 11/01/32 9 of 10 10/96/82 9 of 10 11/01/82 v
- 10. of 10 10/06/82 10 of 10 11/01/82 Table of w
w Table of contents 1 of 1 06/?9/82 Contents 1 of 1
,10/19/82 r
~: s I P.- 1 Cover Page 06/15/82
, IP-1 Cover Page 10/19/82" Preface 1 of 1 10/05/81 Preface 1 of 1 10/19/82 1 of,V 10/06/81 1 of 11
?0/19/82
? of 11' 0//02/81 2 of 11 20/13/82; 3 of*11 09/24/82 3 ns 11 10/19/82-4 o6 11 07/02/81 4 of 11 10/19/82 5 o f ' U$
03/31/81 5 of 11 10/19/82 6 of'11 12/21/81 6 of 11 10/19/82 7 of 11 07/02/81 7 of 11 10/19/82 j
8 of 11 07/02/81 8 of 11 10/19/82 9 of 11 07/02/81 9 of 11 10/19/82
~'
10 of 11 10/06/81 10 af 11 10/19/82 1).of11 07/02/81 11 of 11 10/19/82
~
x l%
'N
~
a
's Page 1 of 3
}7 i
8212080112 821202 h
PDR ADOCK 05000259 p
PDR w
h
BROWNS FERRY NUCLEAR PLANT IMPLEMENTING PROCEDURES DOCUMENT REVISION LOG SHEET Issue Date: November 1, 1982
~~
Pages to be Removed New Pages to be Inserted
^
Revision /
Revision /
Part Page Number Date Part Page Number Date IP-2 2 of 2 04/22/82 IP-2 2 of 2 10/19/82 IP-3 2 of 2 06/29/82 IP-3 2 of 2 10/19/82 1 Table 1 1 of 1 12/21/81 Table 1 1 of 1 10/19/82 Table 2 1 of 1 12/21/81 Table 2 1 of 1 10/19/82' IP-4 Cover Page 06/29/82 IP-4 Cover Page 10/19/82 '.
1 of 2 04/q2/82 1 of 2 10/19/82
'i 2 of 2 06/49/82 2 of 2 10/19/82 Table 1 1 of 1 12/21/81 Table 1 1 of 1 10/19/82 Table 2 1 of 1 12/21/81 Table 2 1 of 1 10/19/82
'l IP-5 2 of 2 06/29/82 IP-5 2 of 2 10/19/62 Table 1 1 of 1 12/21/81 Table 1 1 of 1 10/19/82 Table 2 1 of 1 12/21/81 Table 2 1 of 1
' 10/19/82 s
IP-6 IP-6 4,
Att. I 1 of 4 06/29/82 Att. I 1 of 4 10/19/82 s 2 of 4 06/29/82 2 of 4 10/19/82 1
3 of 4 04/22/82 3 of 4 10/13/82 1
.o 4 of 4 06/29/82 4 of 4 10/19/82's-,);
IP-7 IP-7 Att. I 1 of 1 07/08/82 Att. I 1 of 2 10/19/82 2 of 2 10/19/82 '
IP-8 2 of 4 04/22/82 IP-8 2 of 4 10/19/82 2a of 4 10/19/S2.
4 of 4 10/06/81 4 of 4 10/19/82 IP-11 1 of 2 10/06/81 IP-11 1 of 2 10/19/82 2 of 2 10/06/81 2 of 2 10/06/82 Page 2 of 3
\\
1
+
. fr
]
lu::
//.
a i'
. i.
n f.
4 bEOWNS FERRY NUCLEAR PLANT IMPIlhENTING' PROCEDURES DOCUMENT
, c, REVISION LOG SHEET
?
Issue Date: dovember 1, 1982 Pages to be Removed New Pages to be Inserted Revision /
Revision /
Part Page Number Date
'. Pa rt Page Number Datt.
i)
IP-14 1 of 5 06/29/82 IP-14 1 of 6 10/19/82
\\
2 of 5 04/22/82 j
2 of 6 10/19/82.,
3 of 5 12/21/81 3 of 6 10/19/82 ts 4 of 5 06/.9/81 4 of 6 10/19/82 5of5 06/19/82 5 of 6 10/17/82' lI 6 of 6 10/19/82 u
\\\\
y IP-18 1 of 1 Rev. O IP-18 1 of 1 10/19/S2 -
IP-19 1 of 2 06/29/82 IP-19 1 of 2 10/19/82' 2 of 2 06/29/82 2 of'2
-10/19/82 g
IP-20 1 of 5 08/26/82 IP-20 Iaf5 10/19/82 2 of 5 06/29/82 2 ','o f 5 g
10/19/82 3 of 5 08/10/82
(,
'3 of 5 10/19/82 e
4 of 5 04/22/82 3
4 of 5 10/19/82 5 of 5 05/25/82 3
5 of 5 10/19/82 i
. Att. B 1 of 1 04/22/82 Att. B, 1 of 1 10/19/82 i
$tt. D' 1 of 1 10/19/82 I
IP-21 1 of I' 04/22/82 IP-21 1 of 1 10/19/82 Att. 1,,
1 of 1 04/22/82 Art. 1 1 of 1 10/19/82 IP-22 1 of 2 08/26/82 IP-22 1 of 2 10/19/82 2 of 2 04/22/82 2 of 2 10/19/82 IP-23 1 of 5 06/29/82 IP-23 1 of 5.,
10/19/82 2 of 5 06/29/82 j 2 of 5 10/19/82 3 of 5 i 06/29/82 3 of 5 10/19/82 4 of 5 06/29/82
,,',it.
B i
4 of 5 10/19/82 5 of 5 04/22/82 5 of S 'j 10/19/82 All'. 4.
I of 1 06/29/82 A
1 of l' 10/19/82
')
t r
. ?
i r
~
1 s-
.o a
Page 3 of 3
/;'
a i~ '
a
/
ew BFN-IPD List of Effective Pages Page J of 10 11/01/82 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT IMPLEMENTING PROCEDURES DOCUMENT LIST OF EFFECTIVE PAGES Issue Date: November 1, 1982 This List of Effective Pages must be retained with the Browns Ferry Nuclear Plant Implementing Procedures Documents.
Procedure Page Part Number Subdivision Number Date/Rev. No.
BFN List of Effective Pages 1 of 10 11/01/82 2 of 10 11/01/82 3 of 10 11/01/82 4 of 10 11/01/82 5 of 10 11/01/82 6 of 10 11/01/82 7 of 10 11/01/82 8 of 10 11/01/82 9 of 10 11/01/82 10 of 10 11/01/82 Table of Contents 1 of 1 10/19/82 IP-1 Coversheet 10/19/82 Preface 1 of 1 10/19/82 IP-1 1 of 11 10/19/82 2 of 11 10/19/82 l
3 of 11 10/19/82 4 of 11 10/19/82 5 of 11 10/19/82 6 of 11 10/19/82 7 of 11 10/19/82 8 of 11 10/19/82 9 of 11 10/19/82 10 of 11 10/19/82 11 of 11 10/19/82 IP-2 Coversheet 06/15/82 1 of 2 04/22/82 2 of 2 10/19/82 l
L.
BFN-IPD List of Effective Pages Page 2 of 10 11/01/82 LIST OF EFFECTIVE PAGES (Con't)
Procedure Page Part Nweber Subdivision Number Date/Rev. No.
.BFN IP-3 Coversheet 06/29/82 1 of 2 04/22/82 2 of 2 10/19/82 Table 1 1 of 1 10/19/82 Table 2 1 of 1 10/19/82 IP-4 Coversheet 10/19/82 1 of 2 10/19/82 2 of 2 10/19/82 Table 1 1 of 1 10/19/82 Table 2 1 of 1 10/19/82 IP-5 Coversheet 06/29/82 1 of 2 04/22/82 2 of 2 10/19/82 Table 1 1 of 1 10/19/82 Table 2 1 of 1 10/19/82 IP-6 Coversheet 06/29/82 1 of 1 04/22/82 1 of 4 10/19/82 2 of 4 10/19/82 3 of 4 10/19/82 4 of 4 10/19/82 IP-7 Coversheet 06/29/82 1 of I 12/21/81 1 of 2 10/19/82 l
2 of 2 10/19/82-t IP-8 Coversheet 06/15/82-1 of 4 04/22/82 2 of 4 10/19/82 2a of 4 10/19/82 3 of 4 04/22/82 4 of 4 10/19/82 1 of 1 05/19/81 i
i IP-9 Coversheet 06/15/82 1 of 1 04/22/82
DFN-IPD List of Effective Pages Page 3 of 10 11/01/82 LIST OF EFFECTIVE PAGES (Con't)
Procedure Page Part Number Subdivision Number Date/Rev. No.
DFN IP-10 Coversheet 06/29/82 1 of 6 06/30/81 2 of 6 04/22/82 3 of 6 04/22/82 3a of 6 04/22/82 4 of 6 06/30/81 5 of 6 12/21/81 6 of 6 06/30/81 1 of 2 06/29/82 2 of 2 06/29/82 A 1 of 1 06/30/81 B 1 of 1 Rev. O 1 of 1 Rev. O 1 of 1 Rev. O 1 of 1 04/22/82 1 of 1 Rev. O 1 of 2 06/30/81 2 of 2 06/30/81 1 of 2 06/30/81 2 of 2 06/30/81 IP-11 Coversheet 06/15/82 l
1 of 2 10/19/82 2 of 2 10/06/81 IP-12 1 of 1 04/22/82 IP-13 1 of 2 06/16/81 2 of 2 06/16/81 IP-14 Coversheet 06/29/82 1 of 6 10/19/82 2 of 6 10/19/82 3 of 6 10/19/82 4 of 6 10/19/82 5 of 6 10/19/82 6 of 6 10/19/82
BFN-IPD List of Effective Pages i
Page 4 of 10 11/01/82 LIST OF EFFECTIVE PAGES (Con't)
Procedure Page Part Number Subdivision Number Date/Rev. No.
'IP-14 (Con't) 1 of 1 Rev. O 1 of 1 03/16/82 1 of 1 Rev. 0 1 of 1 Rev. 0 1
1 of 1 Rev. O IP-15 Coversheet 06/15/82 1 of 4 Rev. 0 2 of 4 Rev. O' 3 of 4 Rev. 0
+
4 of 4 03/30/82 IP-16 Coversbeet 06/15/82 1 of 2 04/22/82 2 of 2 Rev. 0 IP-17 Coversheet 06/15/82-1 of 15 01/26/82 2 of 15 03/16/82 3 of 15 04/22/82 4 of 15 03/16/82 5 of 15 01/26/82 6 of 15 07/08/82 l
7 of 15 01/26/82 l
8 of 15 03/16/82 9 of 15 01/26/82 10 of 15 04/22/82 11 of 15 04/06/82 12 of 15 01/26/82 13 of 15 01/26/82 14 of 15 01/26/82 t
15 of 15 01/26/82 l
Figure 1 1 of 1 06/30/81 Figure 2 1 of 1 04/22/82 i
l Figure 3 1 of 1 Rev. O i
^
BFN-IPD i
List of Effective Pages Page 5 of 10 11/01/82 LIST OF EFFECTIVE PAGES (Con't)
Procedure Page Part Number Subdivision Number Date/Rev. No.
BFN IP-18 Coversheet 06/15/82 (Con't) 1 of 1 10/19/82 Title Page 1 of 1 Rev. 0 Table of Contents 1 of 1 04/07/81 List of Figuces 1 of 4 07/21/81 2 of 4 07/21/81 3 of 4 07/21/81 4 of 4 07/21/81 Appendix 1 of 12 04/22/82 2 of 12 04/07/81 3 of 12 04/07/81 4 of 12 04/07/81 5 of 12 04/07/81 6 of 12 04/07/81 7 of 12 04/07/81 l
8 of 12 04/07/81 9 of 12 04/07/81 10 of 12 04/07/81 11 of 12 04/07/81 12 of 12 04/07/81 Figure 1.1 1 of 1 Rev. O Figure 1.2 1 of 1 Rev. O Figure 1.3 1 of 1 Rev. O Figure 1.4 1 of 1 Rev. O Figure 2.1 1 of 1 Rev. O Figure 2.2 1 of 1 Rev. O Figure 2.3 1 of 1 Rev. 0 Figure 2.4 1 of 1 Rev. O Figure 3 1 of 1 Rev. O Figure 4.1 1 of 1 Rev. 0
BFN-IPD List of Effective Pages Page 6 of 10 11/01/82 LIST OF EFFECTIVE PAGES (Con't)
Procedure Page Pa r t.
Number Subdivision Number Date/Rev. No.
I BFN IP-18 Figure 4.2 1 of 1 Rev. 0 (Con't)
(Con't)
Figure 4.3 1 of 1 Rev. O Figure 4.4 1 of 1 Rev. O Figure 4.5 1 of 1 Rev. O Figure 4.6 1 of 1 Rev. O Figure 4.7 1 of 1 Rev. O Figure 4.8 1 of 1 Rev. O Figure 4.9 1 of 1 Rev. O Figure 4.10 1 of 1 Rev.'O Figure 4.11 1 of 1 Rev. O Figure 4.12 1 of 1 Rev. O Figure 5.1 1 of 1 Rev. O Figure 5.2 1 of 1 Rev. O Figure 5.3 1 of 1 Rev. 0 Figure 5.4 1 of 1 Rev. O Figure 5.5 1 of 1 Rev. O i
Figure 5.6 1 of 1 Rev. O Figure 5.7 1 of 1 Rev. O Figure 5.8 1 of 1 Rev. O Figure 5.9 1 of 1 Rev. O b
Figure 5.10 1 of 1 Rev. O Figure 5.11 1 of 1 Rev. 0 1
3
BFN-IPD List of Effective Pages Page 7 of 10 11/01/82 LIST OF EFFECTIVE PAGES (Con't)
Part Number Subdivision Number Date/Rev. No.
BFN IP-18 Figure 5.12 1 of 1 Rev. 0 (Con't)
(Con't)
Figure 6.1 1 of 1 Rev. O Figure 6.2 1 of 1 Rev. O Figure C.3 1 of 1 Rev. O Figure 6.4 1 of 1 Rev. 0 Figure 6.5 1 of 1 Rev. O Figure 6.6 1 of 1 Rev. 0
.'igure 6. 7 1 of 1 Rev. O Figure 6.8 1 of 1 Rev. O Figure 6.9 1 of 1 Rev. O Figure 6.10 1 of 1 Rev. O Figure 6.11 1 of 1 Rev. O Figure 6.12 1 of 1 Rev. O Figure 7.1 1 of 1 Rev. O Figure 7.2 1 of 1 Rev. O Figure 7.3 1 of 1 Rev. O Figure 7.4 1 of 1 Rev. O Figure 7.5 1 of 1 Rev. O Figure 7.6 1 of 1 Rev. O Figure 7.7 1 of 1 Rev. O Figure 7.8 1 of 1 Rev. O Figure 7.9 1 of 1 Rev. 0
BFN-IPD List of Effective Pages Page 8 of 10 11/01/82 LIST OF EFFECTIVE PAGES (Con't)
Procedure Page Part Number Subdivision Number Date/Rev. No.
BFh IP-18 Figure 7.10 1 of 1 Rev. 0 (Con't)
(Con't)
Figure 7.11 1 of 1 Rev. O Figure 7.12 1 of 1 Rev. O BFN IP-19 Coversheet 06/29/82 1 of 2 10/19/82 2 of 2 10/19/82 1 of 18 06/29/82 2 of 18 06/29/82 3 of 18 06/29/82 4 of 18 06/29/82 5 of 18 06/29/82 6 of 18 06/29/82-7 of 18 06/29/82-8 of 18 06/29/82 9 of 18 06/29/82 10 of 18 06/29/82 11 of 18
.06/2S/82 12 of 18 06/29/82 13 of 18 06/29/82 14 of 18 06/29/82 15 of 18 06/29/82 16 of 18 06/29/82 17 of 18 06/29/82 18 of 18 06/29/82 BFN IP-20 Coversheet 06/29/82 1 of 5 10/19/82 2 of 5 10/19/82
~;
3 of 5 10/19/82 4 of 5 10/19/82 5 of 5 10/19/82 Attachment A 1 of 3 12/21/81 2 of 3 12/21/81 3 of 3 12/21/81 Attachment B 1 of 1 10/19/82
HFN-IPD List of Effective Pages Page 9 of 10 11/01/82 LIQT CF EFFECTIVE PAGES (Con't)
Procedure Page j
Part Number Subdivision N'wbe r Date/Rev. No.
Blii IP-20 (Cont'd)
Attachment C 1 of 1 06/29/82 Attachment D 1 of 1 10/19/82 Figure 1 1 of 1 04/22/82 Figure 2 1 of 1 04/22/82 IP-21 Coversheet 06/15/82 1 of 1 10/19/82 1 of 1 10/19/82 Figure 1 1 of 1 04/22/82 Figure 2 1 of 1 04/22/82 IP-22 Coversheet 06/15/82 1 of 2 10/19/82 2 of 2 10/19/82 IP-23 Coversheet 05/29/82 1 of 5 10/19/82 2 of 5 10/19/82 3 of 5 10/19/82 4 of 5 10/19/82 5 of 5 10/19/82 Attachment A 1 of 1 12/21/81 Attachment B 1 of 1
.10/19/82 Attachment C 1 of 1 06/29/82 Attachment D 1 of 1 04/22/82 l
l l
l l
l l
l
BFN-IPD List of Effective Pages Page 10 of 10 11/01/82 LIST OF EFFECTIVE PAGES (Con't)
Procedure Page Part Number Subdivision Number Date/Rev. No.
BFN IP-24 Coversheet 06/29/82 (Con't) 1 of 2 02/23/82 2 of 2 02/23/82 Attachment A 1 of 36 02/23/82 2 of 36 02/23/82 3 of 36 02/23/82 4 of 36 02/23/82 5 of 36 02/23/82' 6 of 36 02/*'/82 7 of 36 02/. 12 8 of 36 02/2L,82 9 of 36 02/23/82 10 of 36 02/23/82 11 of 36 02/23/82 12 of 36 02/23/82 13 of 36 02/23/82 14 of 36 02/23/82 15 of 36' 02/23/82 16 of 36 02/23/82 17 of 36 02/23/82 18 of 36 02/23/82 19 of 36 02/23/82 20 of 36 02/23/82 21 of 36 02/23/82 22 of 36 02/23/82 23 of 36 02/23/82 24 of 36 02/23/82 25 of 36 02/23/82 26 of 36 02/23/82 i
27 of 36 02/23/82 28 of 36 02/23/82 29 of 36 02/23/82 30 of 36 02/23/82 31 of 36 02/23/82 l
32 of 36 02/23/82 33 of 36 02/23/82 34 of 36 02/23/82 35 of 36 02/23/82 36 of a6 02/23/82
Page 1 of 1 BFN-TPD
- BFN, Table of Contents OCT19M BROWNS FERRY NUCLEAR PLANT
' RADIOLOGICAL EMERGENCY PROCEDURES IP-1 Emergency Plan Classification Logic IP-2 Notification of Unusual Event IP-3 Alert IP-4 Site Area Emergency IP-3 General Emergency IP-6 Activation of the Technical Support Center IP-7 Activation of the Operations Support Center IP-8 Personnel Accountability and Evacuation IP-9 Evacuation of Construction Services Personnel IP-10 Medical Emergency Procedures IP-11 Security and Access Control IP-12 Deleted IP-13 Deleted IP-14 Health Physics Procedures IP-15 Emergency Exposure IP-16 Recovery Procedure IP-17 Emergency Equipment and Supplies i
IP-18 Potential Release Evaluation Procedure j
IP-19 Operation of the Emergency Data Information System IP-20 Technical Support Center (TSC) Operation
(
IP-21 Operations Support Center (0SC)' Operation
?
l IP-22 Long Term Operation IP-23 Communications System IP-24 Earthquake Emergency Plan l
- Revis ion <9b
.-.. - -..... _ - ~. - ~.
- - ~. - --.
..--..~.
_. ~.
+
s 1
i i
1 i
- i a
3
~
f TENNESSEE VALI.EY AUTIIORITY
{-
BROWNS FERRY NUCI. EAR l'1. ANT '
b d
e I
[
i.
I e
i RAD 10I.0CICAL EMERGENCY l'I.AN EMERGENCY PLAN CLASSIFICATION LOGIC
.BFN, IP-1~
i t
1 1
t l
I i
[.
$f Approved:
i p
j iiYt S ic Mit endent -
(
l L
OCT 91982 ne<e.
i i
General Revision t
i I
i r
1
!,._._...,_..~..._., _. -
.m
Page 1 of 1 BFN-IPD i.
BFN, IP-1
-. Preface PLAN Cf.AMMIFICATION LOGIC Classification System TVA ' utilizes the following ca;ergency classifications:
1.
Notification of Unusual Event 2.
Alert 3
Site Area Emergency 4.
General Emergency This system of classification is consistent with ths systems used by NRC, State and local emergency organizations.
Therefore, all communications must be made using.QDAY. these four classifications exactly.
IP-1 classifies various events into these four categories.
However, it is impossible to list every possible initiating event.
The Site Emergency Director will use his professional judgement in classifying any events not listed into the proper category, based on the general guidance listed below.
Notification of Unusual Event This class provides early and prompt notification of minor events which could develop into, or be indicative of more serious conditions which are not yet fully realized.
Alert An alert class is indicated when events are in progress or 1. ave occurred j
which involve an actual or potential substantial degradation of the level of safety of the plant.
Site Area Emergency l
^ Site Area Emergency is declared when events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public.
General Emermancy l
A General Emergency is declared when events are in progress or have occurred which involve actual or imminent substantial core failure with potential for loss of containment integrity.
~
I 1
l l
-MSL HIGH RADIATION 3 X NORMAL FULL POWER BKG (Alarm & Isolation)
IP-3 ALERT
->5 GPM UNIDENTIFIED LEAKAGE IP-2 NOTIFICATION OF AN OR 725 GPM IDENTIFIED AND UNIDENTIFIED (SI-2)
UNUSUAL EVENT
-PRIMARY SYSTDI LEAKAGE--SAFETY OR RELIEF VALVE OPENING AND FAILING
_IP-2 NOTIFICATION OF AN TO RECLOSE AS EXPECTED UNUSUAL EVEhT
_ TOTAL >50 GPM. IDENTIFIED AND UNIDENTIFIED IP-3 ALERT LEAKAGE (SI 2)
EQUIPMENT DRYWELL UNIDENTIFIED LEAK RATE 2547 SCFH-IP-2 NOTIFICATION OF.G
~
PER SI 4.7.A.2.a UNUSUAL EVENT
_ PRESS (PI-64-67 or PR-64-50) APPROACHING IP-5 GENERAL EMERGENCY 62 PSIG e
--PRIMARY CONTAINMENT RX COOLANT ACTIVITY 3.2 uCi/gm 0F DOSE EQUIVALENT OF I-131, STEADY IP-2 NOTIFICAT, ION OF AN (RX CRITICAL)
. STATE (SI 4.6.B.5), or 26 uCi/gm after power UNUSUAL EVENT '
transient (SI 4.6.B.4/SI 4.6.B.6)
IODINE CONCEhTRATION >300 <Ci/gm
-IP-3 ALERT TECHNICAL SPECIFICATION IP-2 NOTIFICATION OF AN
~
LCO OR SAFETY LIMIT REACHED UNUSUAL EVENT REQUIRING LOAD REDUCTIOU IN ANTICIPATION OF UNIT SHUTDOWN O o to t
O E ES
-at L a M G ai ~
(o 1 O
N
ECCS INITIATION OCCURS (HPCI & RCIC)
IP-2 NOTIFICATION OF AN (SMALL BREAK)
UNUSUAL EVENT MAIN STEAM.LINE BREAK WITHOUT ISOLATION
. IP-4 SITE AREA EMERGENCY ECCS INITIATION OCCURS (RHR & CS)
IP-4 SITE AREA EMERGENCY 4 RI COOLANT BREAK ECCS FAILURES (RHR & CS-INITIAL OR SUBSEQUENT IP-5 GENERAL EMERGENCY (LOCA)
TO START)
CREATER THAN MAKEUP PUMP CAPACITY IP-5 GENERAL EMERGENCY (RHR-CS-HPCI-RCIC)
ADS INITIATIO!!
IP-4 SITE AREA EMERGENCY SMALL BREAK e
EQUIPME~ tit-WUTDOWN C00LINC LOSS OF SHUTDOWN COOLING CAPABILITY-IP-3 ALERT (POTENTIAL OR ABILITY TO GET TO COLD SHUTDOWN ESCALATION TO IP-4 OR IP-5)
-RPS FAILURE TO INITIATE OR COMPLETE A SCRAM IP-3 (POTENTIAL TO BRING RX SUBCRITICAL ESCALATION TO IP-4 or IP-5)
-INABILITY TO MAINTAIN HltI OR RCIC REQUIRED TO MAINTAIN RX WATER IP-2 (NOTIFICATION OF RX WATER LEVEL LEVuL UNUSUAL EVENT)
-INABILITY TO MAINTAIM ADS Ih'TIATION REQUIRED IP-3 ALERT (POTENTIAL RX WATER LEVEL ESCALATION TO IP-4 or IP-5)
-INABILITY TO MAINTAIt!
!iANUAL START OF CORESPRAY OR IP-3 ALERT (POTENTIAL RX WATER LEVEL LPCI SYSTEMS REQUIRED ESCALATION TO IP-4 or IP-5) ce to 5 0 EN (p
.o
(&
CD
~
l inSS OF OFFSITE OR ONSITE AC POWER IP-2 NOTIFICATION OF CAPABILITY OF ANY UNIT UNUSUAL EVENT AC POWER LOSS OF OFFSITE AND ONSITE AC POWER IP-3 ALERT- (POTENTIAL SUPPLY TO ANY UNIT ESCALATION TO IP-4) iDSS OF OFFSITE AND ONSITE POWER TO IP-4 SITE AREA EMERGENCY ANY UNIT FOR MORE THAN 15 MIN.
ELECTRICAL EQUIPMENT LC LOSS OF ALL DC POWER ON ANY UNIT IP-3 ALERT (POTENTIAL POWER I
ESCALATION TO IP-4)
ANNUNCIATOR LOSS OF ALL ANNUNCIATORS IN GROUP I OR Il BELOW:
GROUP'I - 3A,3B, 3C, 3D, 3E, 3F CRONP II - 4A, 4B, 5A, SB IP-3 ALERT ANNUNCIATOR - LOSS OF ALL CONTROL ROOM IP-4 SITE AREA EMERGENCY ANNUNCIATOR PANELS FOR 15 MINUTES IF l'OT IN COLD SHUTDOWN LOSS OF VITAL DC POWER TO ANY UNIT FOR IP-4 SITE AREA EMERGENCY MORE THAN 15 MINUTES
'% % E' h '?"%
i i
M e
a
' c@c M
- LOSS OF INSTRUMENTATION THAT MONITORS IP-2 NOTIFICATION OF AN DRYWELL AND TORUS ATMOSPHERE (SI-2)
UNUSUAL EENT M OS3 0F COMPUTER REQUIRING SHUTDOWN IP-2 NOTIFICATION OF AN 19 UNUSUAL EVEX
-LOSS OF ALL METER 0 LOGICAL INSTRUMENTATION
- IP-2 NOTIFICATION OF AN (SI-2)
UNUSUAL EVD I INSTRUMENTATION
-LOSS OF RPIS IP-2 NOTOTICATION OF'AN UNUSUAL EVENT LOSS OF EFFLUENT MONITORS FEQUIRING SHUTDOWN IP-2 NOTIFICATION OF UNUSUAL EVENT
-LOSS OF REQUIRED NEUTRON MONITORINC IP-2 NOTIFICATION OF UNUSUAL EVENT
-LOSS OF PAX SYSTEM IP-2 NOTIFICATION OF UNUSUAL EVENT EQUIPMENT-CONTROL ROOM
- EVACUATION OR ANTICIPATED EVACUATION IP-3 ALERT
- EVACUATION AND CONTROL FROM BACKUP IP-4 SITE AREA DIERGENCY CONTROL ROOM NOT ESTABLISHED WITHIN 15 MINUTES TURBINE &
RAPID SHUTDOWN DUE TO SUSPECTED FAILURE IP-2 NOTIFICATION OF CONDENSER OF TURBINE ROTATING COMPONENT UNUSUAL EVENT
~ TURBINE CASING FAILURE IP-3 ALERT ges 5 U R ? ?i LO L R a
LOSS OF-FUEL. POOL COOLING >0NE HOUR IP-2 NOTIFICATION OF UNUSUAL EVENT-DAMAGED / DROPPED FUEL BUNDLE WITH IP-3 ALERT RELEASE OF RADIOACTIVE MATERIALS EQUIPMENT FUEL HANDLING W OR DAMAGE TO SPENT FUEL /OR IP-4 SITE AREA INERGENCY FUEL POOL e
o a
e 5
e G
c7 g% gT'ut.
--g - i.
._,.L A CO
Page 6 of 11 BFN-IPD BFN IP-2 NOTIFICATION OF AN UNUSUAL 191982
-EXCEEDING TECH SPECS (3.8.A.1., 2, or 5)
LIQUID _
. RADICACTIVFm EITLUENTS RA)10II)GICAL GASE00.i.__. EXCEEDING TECH SPECS IP-2 NOTIFICATION OF AN UNUSUAL EVENT UNEXPLAINED ISOLATION OFF GAS IP-2 NOTIFICATION OF SYSTEM DUE ID POST TREAINENT MONITOR UNUSUAL EVENT (RR-90-265)
(1) STACK RELEASE RATE (>3.5 Ed EI/SEC)
IP-3 ALERT OR BUILDING RELEASE RATE (>1.2 E+4 UCI/SEC)
(Corresponds to 2.5 mrem /hr thyroid frm noble gas and iodine mix)
(1) STACK RELEASE RATE (79 3 E+7 BCI/SEC)
_IP-4 SITE AREA EMERGENCY FOR 1/2 HOUR DURATION OR BUILDING RELEASE RATE (>17 E+5 4CI/SEC)
FOR 1/2 HOUR DURATION (Corresponds to 250 mrem /hr thyroid fr a fr m noble gas and iodine mix)
(1) STACK RELEASE RATE (79.3 E+8 UCI/SEC)
IP-4 SITE AREA EMERGENCY FOR 2 MINUTE DURATION OR 6
BUILDING RELEASE RATE (71.7 x 10 EI/SEC FOR 2 MINUIE DURATION -(Corresponds to 2500 mrem /hr thyroid fr a noble gas and iodine mix)
(1) STACK RELEASE RATE (71.8 E+9 QCI/SEC)
IP-5 GENERAL EMERGENCY OR BUILDING RELEASE RATE (73 4 E+6 4CI/SEC)
(Corresponds to 5000 mrem /hr thyroid fr a noble gas and iodine mix)
(1) Based on calculations from SI 4.8.B.l.a
~.-
-RADIATION UNEXPECTEDLY ABNORMAL IP-3 ALERT 3-
> 1000mR/hr (ALARM /HP CONFIRR\\ TION) i AREA RADIATION
-RADIATION UNEXPECTEDLY ABNORMAL AIRBORNW FOR IP-3 ALERT A CONTROLLED AREA 7100 MCP" (CAM ALARM /HP CONFIRMATION)
RADIOLOGICAL 1
- PERSONNEL INDIVIDUAL kEQUIRING EXTENSIVE ONSITE IP-2 NOTIFICATION OF UECONTAMINATION OR OFFSITE ASSISTANCE UNUSUAL EVENT e.
MPC, + MPC for controlled area O
t 9
l tz to
- tt CD' L R
I m
8
CIVIL DISTURBANCES IP-2 NOTIFICATION OF AN UNUSUAL EVENT ATTEMPTED ENTRY IP-2 NOTIFICATION OF AN t
i*
UNUSUAL EVENT
-' U SECURITY UNAUTHORIZED PERSONNEL INSIDE PLANT IP-3 ALERT THREAT SECURITY BOUNDARIES ENTRY UNAUTHORIZED PEPSONNEL THREATENINC IP-4 SITE AREA-EMERGENCY PHYSICAL CONTROL OF FACILITY LOSS OF PHYSICAL CONTROL OF FACILITY IP-5 GENERAL EMERGENCY ATTEMPTEC IP-2 NOTIFICATION OF AN UNUSUAL EVENT SABOTAGE ACTUAL IP-3 ALERT SECURITY LOSS OF PLANT SECURITY SYSTEMS IP-2 NOTIFICATION OF aN UNUSUAL EVENT BOMB THREAT IP-2 NOTIFICATION OF AN UNUSUAL EVENT MISSILES (AIR OR' CRASH ON SITE (RESERVATION)
IP-2 NOTIFICATION OF AN SURFACE OR UNUSUAL ACTIVITY OVER UNUSUAL EVENT CRAFT)
FACILITY O
4 ::,,
CRASH INVOLVING PLANT STRUCTURES IP-3 ALERT (POTENTIAL
.E hf OR SWITCHYARD ESCALATION TO IP-4) g 'I #
@ ~~
2 CRASH INVOLVING VITAL AREAS IP-4 SITE AREA EMERGENCY a
__.~
4 l
1
?
i i-I 1
=
-INJURIES CONTAMINATED INDIVIDUAL TRANSPORTED IP-2 NOTIFICATION OF AN TO OFFSITE HOSPITAL UNUSUAL EVENT MEDICAL-NEAR OR ONSITE IP-2-NOTIFICATION OF AN UNUSUAL EVENT
-T0XIC WITHIN PLANT BUILDINGS IP-3 ALERT GASES 4
WITHIN VITAL, AREA 0 IP-4 SITE AREA DfERGENCY e
L c3 I
R*Qj
? = =,:.
CD i
a
~
CO I%7 4
e
-TRIAXIAL OPERATION 70.01 IP-2 NOTIFICATION OF AN 5
UNUSUAL EVENT (Refer also EARTHQUAKE--
to IP-24)
-BIAXIAL OPERATION > 0.IE IP-3 ALERT-(Refer also to' i-IP-24)
-RESERVOIR LEVELE561' IP-2 NOTIFICATION OF AN UNUSUAL EVENT FLOOL RESERVOIR LEVELZ563.5' IP-3 ALERT
-RESERVOIR LEVEL.2: 565' IP-4 SITE AREA MERGENCY NATURAL PHENOMENA
" REPORTED BY PLANT PERSONNEL IP-2 NOTIFICATION OF AN UNUSUAL EVENT TORNADG
'-STRIKING PLANT IP-3 ALERT IIIGH WINDS SUSTAINED WINDS >90 MPH IP-4 SITE AREA DfERGENCY LOW RESERVOIR LEVEL-BREACH OF WHEELER DAI-i IP-4 SITE AREA DiERGENCY e
O,,,.,
S ',.i!i
- mas to L
o d
2 co i
N l
LASTING LONGER THAN 10 MINUTES
-IP-2 NOTIFICATION OF AN UNUSUAL EVENT FIRE THREATENING A VITAL AREA IP-3 ALERT HAJOR FIRE AFFECTING VITAL SYSTDIS IP-4 SITE AREA DfERGENCY ~
(POTENTIAL ESCALATION TO IP-5)
FIPI FJPLOSION-
-WITHIN SITE BOUNDARIES IP-2 N0'i1FICATION OF AN OR UNUSUAI EVENT EXPLOSION M NSITE (ON RESERVATICN)
IP-3 ALERT M AMAGE INVOLVING NONVITAL STRUCTURES IP-3 ALERT
---MMOR DAMAGE INVOLVING VITAL STRUCTURES IP-4 SITE AREA DIERGENCY (POTENTIAL ESCALATION TO IP-5 FLAMMABLE GAS OR VAPORS WITHIN PLANT BOUNDARIES IP-2 NOTIFICATION OF AN UNUSUAL EVENT WITHIN PLANT BUILDINGS IP-3 ALERT (POTENTIAL ESCALATION TO IP-4)
W ITHIN VITAL AREAS IP-4 SITE AREA DIERCENCY STRIKE OR OTHER EVENTS THAT PREVENT IP-2 NOTIFICATION OF AN PROPER MANNING UNUSUAL-EVENT OTHER (1)
PLANT CONDITIONS WHICH REQUIRE IP-4 SITE AREA DIERGENCY OFFSITE RESPONSE
!:AJOR IMTERNAL OR EXTERNAL EVENTS WHICH IP-5 GENERAL DIERGENCY O*
COULD CAUSE MASSIVE COFDION DAMAGE TO f 8' $ F PLANT SYSTEMS
. ?$
p G-(1) These. items are based on Site Emergency Director's professional judgement (O
7O~
l y ~
CD N
~
P ga 2 er 2 BFN-IPD
- BFN, IP-2 GQT19%82 C.
The Shift Engineer or shift Enginoer's Clerk will notify the following individuals of the incident:
Contact the individual directiv : the only message that should be left is for the individual to call the plant. Use PAX phone, home phone, plant paging system, or pocket pager as applicable. State that this is " NOTIFICATION OF UNUSUAL __ EVENT" and a brief description. The individual does nni -have to report to the plant.
( Initials )
+
a.
Other Shift Engineer. (when assigned)
-Y b.
Shif t Technical Advison' s_
o.
Operations Section Supervisor R. Hur.kapillar Decatur i
DR Operations Supervisor Tommy Jordan o
Muscle Shoals DR Operations Supervisor A. Burnette Florence Plant Superintendent G.i. Jones Decatur DR Assistant Plant Superintendent E. R.
Ennis Decatur DR Assistant Plant Superintendent J. R. Pittman Decatur i
Public Information Officer R. C. Boyer Decatur
~
D.
Notify the NRC by ring-down of plan activation. Specify NOTIFICATION OF UNUSUAL EVENT. Maintain an open line until released by NRC.
2.2 At least every two hours, or more frecuentiv. if conditions warrant, the shif t engineer will reevaluate the event using IP-1.
The shift engineer on the unaffected unit (s) will handle additional communications.
a.
If the situation no longer exists, inform the per;onnel notified in step 2.1.
b.
If the condition warrants upgrading to a higher classification, initiate the appropriate proceduro for the more serious conditions.
e 's'
v s
s s'
y m
A Page 2.of 2 s
e g
C
't FFN
.IPD f
,g 4E44, IP.3 w
EF 6bij91982 Unuspalretcaseofradioncthity(yesor,no).
e g.
s 3
'. cs J., -
h.
Di raction wind is coming f rom Dandspeed_
.Q r-a e
w
.s W
A
- E.
The Spif t Engineer or Shif t Engineer's Cierl/ will,, notify tfic, fol-t,,. f
&4 s
s lowing individuals of the incident.
u
~
a Hesdage: This is an ALERT. This is not a drill. Give a brihT" y'
e y dascription.
's t.
,, " +. 4 j:
n a
~
(whep.sf e,ned}- Jd p 7.N(
a.
Other Shift Engineer w
b.
Shif t Technical Advisor,
.g
(
c,,
Chemical Laboratory, PAX s
/
- \\
- N' t'
m.
s,
.5
~
s F.
~
9 n
Jh.Shif t Engineer's Clerk will notify tb3 persdonel listed in 'IP-6.
g
, :e r
v G. ' Notify t$e. NRC by ring-down phone of plan activation.
J, Mai;n ta.i.s'T'kn S pec. i fy, t.ha t this is an ALERT and a brief description.
m-s open line until released by the NRC.
6 '\\of (,$.
st
...y
, ,. hg.
q Note: N Q may,sund a reisponse team to the site..*
7, i
4 y'. '
,g w
o.
.\\
c%
N *- w
- H.
Tim ting,%cle (hif( Erigineer will implebnt operation 'of the
~
w.
TS(
v), to'incluNetfvyti,% of Dimensioy telephones and hl 4
, placing required desk.4,in liall in f ront "df-'tSC{
Q v
y g
{,
t x
.\\
e
, t 's
\\
's 2.2 At least every two hours,' phore frenthntly if xtsnditions warrant;
</
\\ '{
thy Shifc' Engineer will fe0(11uate the event'using IP-1.
'\\
/
\\
t
.s C-a.
If the situar. ion no longer exists or should be down graded, a
(
inforn the personnel notified in st"p 2.1.
i g
s, s
w t
\\
g g
l f-
-.b.
If thecondition wprrants. pgrading to a higher elagstfication -
u m
initiate thy c.pprppripta. procedure for the more s hous. conditions, I
- i t
- t #: N*~,
g 3.,,,
s 2.3 tefer to Tabic 1 for a yttick estimates of maximen of fsith 4cse for a stack j~
relsase, and Tabl.s % for'S guick estimate of the site'bo;indary dose for building release.\\
A
%s t -
i g
a C
g
~
+
'k
'\\
\\
k D. '%g i
f*
g
,g 3
p i
n s
s.
['
y
s q*\\
a'
'A g
s
- ~
r
't
~
3
_\\
',7 m
t 3
< i -'
d
{ '.
4 y
l
% p,7 y
O s
1 3,_
~ cy, if \\
, a-t
'N h
g
-4
- Rev sion j N
~
i si s
s
(,."
A4
, L. L'
\\
4
'(f Q -_
wN,,
- 'g
,s t
k i
,*y 4"
'i l s'
i W$
1 s a p; j
4, N'
1 o
ss
! t M'
l 4
4. '. '
[
s-s i
b,
[
's i
A (V
\\~
s '
'gT,'
t f
a
_t,
'j s
s
,,f v
s q
g
( aj
'l y'
s, p,. J rt l'
.~ 6 -
b j'
A
P ga 1'cf 1 BFN-IPD D,IP-3 Tabie 1 3
.m l
Maximum Offsite Doses Corresponding to Noble Oas Release Rates (1) (2) through the Stack at BFN Noble Gas Maximum Offsite Release Rate (1)
Thyroid Dose Rate (uci/s)
(arem/h)
Comments 4
1 X 10 ---------------------------- 0. 007------------- Av erage me t eorology 4
5 X 1 0 ---------------------------- 0. 0 3 5 assumed. Maximum dose 5
1 X 10 ----------------------------- 0.07 rate is at 17,CO0s.
5 X 10l---------------- O. 5 1 X 10
- 0. 0 6
2 X 10 ---------------- 1.
6 3. 5 X 10 ---------------------------- 2. 5--------------
AL ER T 6
5 X 10 -----------------------------14.----------------Adverse meteorology assumed 6
X 1 0 ---------------------------- 1 9.
for this and larger releases 7
X10-----------------------------2'.
2 X 1 0 ---------------------------- 5 [l.
Maximum dose rate at 8,000 m 7
7 4 X 10 ---------------- 1 10.
7 X 10 ----------------------------160.
7 X 1 0 --------------------------- 2 2 0.
(33.g i igL _ _- _- _- _- - _- _- _- - _- 3 0.210.----------------If expected to persist over s,(
e 9
e 30 minutes-31TE 4REi EMrRcEu,
8 o.
- 1. 6 X 10 -------,----------- gO.
8 EMERGENCY 2. 0 X 10 ---------------- g 80.2.5 X 10h-~~-
~ ~~
-810.
3.0 X 10
~
~
1,400.
1 6.0 X 10
' 0 X 10
,900.
$* ! lg
-- -2,500.-------- '--------If exk.eeted to peraist over 8
jh
g,000 -----------------GENER AL EMERGENCY
,200.
2 m nutes-SITE AREA EMERGENC) 100.
1:i3X10 ------------------------ 5 4 0 0.
X 10
5, 2.0 X 10 4.0 X 10 -------- ------ 1 1, 0 0 0.
16,000.
(0X10
_------ ------------22 o x 3 0 0--------------27,000.
1.0 X 10
,000.
(1) Release rates are equated to offsite dose rates assuming a noble gas and iodine mix. (Raf. Nov. 3,1981 memorandum from M. D. Matheny to Radiolo61 cal Hygiene Branch Files entitled " Relation of Radioactivity Rates to Emergency Classifications")
(2) Stack release rate (SRR) calculated as follows:
SRR = (RH 90-147) X(FI 90-271)X2 93 E -3 (3) Release rates larger than this cannot be measured by using stack monitors (instruments off-scale high). Request radiochemical laboratory personnel to use TI 67 to estimate release rates by measuring dose rates on SBGTs effluent ducts.
- Revision I
.~
Page 1 of 1 1
BFN-IPD BFN, IP-3 1
. Table 2 ff9hh Table 2 Site Boundary (1) Doses Corresponding to Noble Gas Release Rates (2) other than through the Stack at BFN
)
Noble Gas Site Boundary Release Rate (2) (3)
Thyroid Doso Rate
+
(uC1/s)
(arem/h)
Comme <,1 2
1 X 10 ------------------------------0.02---------------Average meteorology assumed 2
0.11 5 X 10 ----------------------------- 0.22 1 X 10 ------------------------------
5 X 10 ----~~~-~~~~------------------I l 1
- 2 X 10 ~ ~~~~ ~~~ ~ ~~ -- ~ ~ ~ ~ ~ ~ ~~~ " -------- 2.'
5----------------AL ERT 2 X 10 ----------------------------
O.0.-----------------Adverse meteorology assum'ed 4
4 4 X 10 ---------------------------- 90.
for this and larger release 4
6 x 10 ----------------------------150.
5 1 X 10 --------------------------- 250.-----------------If expr ted to 5
erstat over 1*
X 10 --------------------------- 600.
30 mL utes-SI E AREA EMERGENC 5
X 10 --------------------------- 900.
6 X 10 --------------------------1,500.
1 X 10 ------------------------- 2,000 X 10 --------------------------
500.-----------------If ex ected to ersist over 1*
6 2 m nutes-SIT AREA DiERGENCS X 10 -----,----------------,
6 X 10 -------------------------
,500.
6 X 10 -------------------------
, 0 00. -----------.-----G ENER AL EMERG EN CY 3
6 4 X 10 -------------------------
,000.
6 500.
X 10 --------------------------7,000.
6 9,
X 10 -------------------------12,000.
6 X 10 -------------------------
7 1 X 10 -------------------------15,000.
7 I
2 X 10 -------------------------
,000 7
90,000.
4 X 10 -------------------------
,000.
6 X 10 ------------------------150,000.
1 X 10 ------------------------
't (1) These values are for a ground level location at a distance of 1,000 meters.
g (2) Release rates are equated to off-site dose rates assuming a noble gas and iodine dix (Ref. November 3, 1981 memorandum from M. D. Matheny to Radiological Hygiene Branch Files entitled " Relation of Radioactivity Rates tof Emergency Classifications"). Either a
estimates of off-site dose rates will be provided by MSEC.
(3) k'elease rate calculated from building (reactor, turbine, radwaste) CAMS in accordance with SI 4.8.D.1.a.
't 4
O
' Revision I
i
)
~.. - ~....... _.....
i l
1 ~
I TENNCSSEE VALLEY AUTil01;lTY liROWNS FERRY NUCLEAR Pl. ANT f
4 l.
i i -
i i
1 i
RADIOLOGICAL EMERGENCY PLAN I
SITE AREA iMERGENCY BFN, IP-4 4
?
. 4
+
1 4
?
I S.
i pl f
Approved:
i
+
.zw Finnt/ yup 6tendent w.
Dato:
i General Revision n
l l
e t
r*
w ow-ewt--*-'-
w-sm--=+w
,t wre i re--a se-e~a,to--ete--*
t--we-e-
-er-met
-ee--eve-=-+'ee--t*-
a v w, v + e sr +* rv = w
=*se-m ee w -e -w sr-w -
we**++--er--rw-- w e e
=r es - w- + e m = se - ere e-err r re a r e,
we-
Raga 1 of 2 UFN-IPD BFN, IP li SITE AREA EMERGENCY 1.0 PURPOSE 1.1 To provide a method for timely notification of appropriate individuals when the shift engineer had determined by IP-1 f. hat an incident has occurred which is classified as a SITE AREA NWiENCY.
1.2 To provide a method for periodic reanalysis of the currect situation to determine whether theSITE AREA DfERGENCY action should be cancelled, continued, upgraded, or downgraded to another
'l classification.
2.0-INSTRUCTIONS 2.1 Upon determining by IP-1 that a W_HyA D1ERGENCY exists:
The shift engineer will:
Initials Time A.
ifave the shift engineer's clerk notify the Public Safety Shift Supervisor, state that this is a " SITE AREA DIERCENCY" and direct him to activate the following procedures:
a.
IP-11, Security and Access Control.
b.
IP-7, Activation of the Operations Support Center.
c.
If any personnel are injured, initiate IP-10, Medical Emergency Procedures.
B.
Have the shift' engineer's clerk notify the Health Physics Shift Suoervisor, state this is a " SITE AREA D1ERGENCY" and direct him to activate the following procedure:
IP-14. llealth Physics Procedure.
C.
Evaluate plant conditions, and, if conditions warrant, initiate either or both IP-8 or IP-9 (activate emergency sirens for personnel assembly).
D.
Notify the Operations Duty Specialist bv direct dimension-phone 40-200, alternate Chattanooga 50-0200 and state the following:
a.
Your name.
b.
Browns Ferry Nuclear Plant.
c.
SITE AREA EMERGENCY d.
Time of incident.
e.
Brief description of incident.
f.
Plant condition (whether stable or deteriorating).
Page 2 of 2 BFN - IPD BFN, IP-4 g.
Unusual release of radioactivity (yes or no) h.
Direction wind is coming f rom,_
and speed _f E.
The Shift Engineer or Shift Engineer's Clerk will notify the following individuals of the incident.
Message: "This is a SITE AREA EMERGENCY, this is not a drill." Give a brief description.
a.
Other Shift Engineer.
(when assigned) b.
Shift Technical Advisor, PAX /
/
c.
Chemical laboratbry, PAX F.
The Shif t Engineer's clerk will notify the personnel listed in IP-6.
G.
Notify the NRC by ring-down phone of plan activation. Specifty this is a SITE AREA EMERGENCY and a brief description. Maintain an open line until released by the NRC.
Note:
NRC should arrive onsite in approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
H.
Time permitting, the Shif t Engineer will implement operation of the TSC (IP-20), to include activation of Dimension telephones and placing required desks in hall in front of TSC.
2.2.
At least every two hours, or more frequently if conditions warrant, the Shift Engineer will reevaluate the event using IP-1.
a.
If the situation no longer exists or should be downgraded, inform the personnel notified in step 2.1.
b.
If the condition warrants upgrading to a higher classification, initiate the appropriate procedure for the more serious conditions.
NOTE: Precautionary site evacuation should be considered.
2.3 Refer to Table 1 for a quick estimate of maximum offsite dose for a stack release, and Table '2 for a quick estimate of the site boundary dose for a building release.
t 8
P;g3 1 of 1 BFN-IPD BFN, IP 4
..'Sa.Me 1 0h b
82 Table 1 Maximum Offsite Doses Corresponding to Noble Gas Release Rates (1) (2) through the Stack at BFN Nobic Gas Maximum Offsite Release Rate (1)
Thyroid Dose Rate (uCi/s1 (mrem /h1 haggata 4
1 X 1 0 - -------- ----------------- -- 0. 0 07 - -------------Average meteorology 4
0.035 assused. Maximum dose 5 x 10 ---------------------------- 0.07 rate is at 10,000m.
5 1 X 10 -------------- --------------
5 X 10l---------------------------- 0 3 5 1 X 10 ----------------- 0 7 0 6
1.4 2 X 10 ---------------------------- 2 5--------------- ALERT 6
2
- 5 X 10 ---------------------------- 14. ----------------- Adverse me teorology assumed 6
5 X 10 ---------------------------- 19.
for this and larger release 6
}X10----------------------------27.
Maximum dose rate at 8,000 7
X 10 ---------------------------- 54.
7 2 X 10 ----------------------------110.
7 4 X 10 --------------------------- 160.
7 6 X 10 --------------------------- 220.
7 8 X 10 ----------------------------
k ! !bL ' ~-- ~~~~ ~- ~~----- ~-
---250.-----------------If expected to hersist over
~~~~ ~ -~ 80.
30 minutes-SI E AREA EMERGENC
- 1. 6 X 10 ------ -----------}A
- (3)
~
8 2. 0 X 10 ------.---------
g 0.
8 O.
- 2. 5 X 10 -------------- g 80.
8 8----------------------------810.
$,* o y l o 8-------------------------- 1,9 0 0.
400.
8 1
7'3x39-------------------------3,2C0.0X10-------------------------2,500--------.--------Ifexpec 8
9:
9 2 m nutes-SITE AREA EMERGENCY X10-----------------------..-
3 9
X 10 ------------------------- 4 1 0 0.
1:c8 x 1 0 --------- ---------------- 5, 0 0 0 -----------------GENERAL EMERGENCY i
5, 4. 0 X 10 ---------------- 1 1, 4 0 0.
2.0 X 10 16,000.
i 6. 0 X 10 ----------------------- 2 2, 0 0 0.
9----------------------
8. 0 X 10 0-----------------------27
, 0 0 0.
1.0 X 101
,000.
(1) Release rates are equated to offsite dose rates assuming a noble gas and iodine i
mix. (Ref. Nov. 3,1981 memorandum from M. D. Matheny to Radiological Hygiene Branch l
Files entitled " Relation of Radioactivity Ratos to Emergency Classifications")
(2) Stack release rate (SRR) calculated as follows:
SRR = (RM 90-147)X (FI 90-271)X2 93 E -3 (3) Release rates larger than this cannot be measured by using stack monitors (instruments off-scale;high). Request radiochemical laboratory personnel to use TI 67 to estimate release rates by measuring dose rates on SBGTs effluent ducts.
l
\\
l l
1 l
l
Page 1 of 1 BFN-IPD BF!l, IP.4 wTable 2 fjQ T_able 2 Site Boundary (1) Doses Corresponding to Noble Gas Release Rates (2) other than through the Stack at BFN Noble Gas Site Boundary Release Rate (2) (3)
Thyroid Dose Rate fuci/s)
(mree/h) gggggqta 2
1 X 10 ------------------------------0.02----
Average meteorology assumed.
2 5 X 10 ------------------------------0.11 1 X 10 ------------------------------0.22 5 X 10 -----------~~---------~~------l*1 1'2 X 10 ------------------------------2.5----------------ALERT 4
2 X 10 -----------------------------30.-----------------Adverse meteorology assumed 4
4 X 10 -----------------------------60.
for this and larger releaces 4
6 X 1 0 ----------------------- ------ 9 0.
5 1 X 10 ----------------------------150.
5 1 * { X 10l5---------------------------
2 50. -----------------If ex pecte d to hE AR EA EMERG EN(
X 10 ----------------------------
ersict over 600.
30 minutes-SI 6 x 1 0 - --------------------------- l 0 0.
00.
1X10--------------------------1,500.-----------------Ifex $ectedtokersistover
2,000.
2X]O--------------------------3,500.
2 m nutes-SIT AREA EMERGENC' 6
3 X 10 --------- ----------------4 3 4 X 10 -------------------------- 5,, 00 0. -----------------G EN ER AL EMERG EN CY 6
6 4 X 10 --------------------------6,000.
6 X 1 0 - ------------------------, 5 0 0.
6 X 10 -------------------------
, 0 0 0.
6 X 10 ------------------------- I, 0 0 0.
7 1 X 10 -------------------------15,000.
7 000.
2 X 10 -------------------------30,0 0 0.
7 4 X 1 0 ------------------------- 6 0 6 X 10 -------------------------90,000.
7 8
1 X 10 ------------------------150,000.
(1) These values are for a ground level location at a distance of 1,000 meters.
(2) Release rates are equated to off-aite dose rates assuming a noble gas and iodine mix (Ref. November 3, 1981 memorandum from H. D. Matheny to Radiological Hygiene Branch Files entitled " Relation of Radioactivity Rates to Emergency Classifiestions ).
Either a
estimates of off-site dose rates will be provided by MSEC.
(3) Release rate calculated from building (reactor, turbine, radwaste) CAMS in accordance with SI 4.8.B.1.a.
l l
0 84 l
t
J Page 2 of 2 BFN - IPD EES, IP-5 00T191982-f.
Plant condition (whether s' tabic or deteriorating).
g.
Unusual release of radioactivity (yes or no).
h.
Direction wind is coming from and speed 1.
Recommended initial protective actions for the public:
(Activate the warning systems and advise the public to take e.
shelter, tune radio or TV to a local station, and await further instructions.)
E.
The Shif t Engineer or Shif t Engineer's Clerk will notify the follow-ing individuals of the incident.
Message: This is a CENERAL EMERCERNCY, This is not a drill. Give a brief description.
a.
Other Shift Engineer. (when assigned) b.
Shift Technical Advisor, PAX t
c.
Chemical Laboratory, PAX F.
The Shift E'ngineer's Clerk will notify the people listed in IP-6 C.
Notify the NRC by ring-down phone of plan activation. Specify that this is a GENERAL EMERGENCY and a brief description.. Maintain an open line until released by the NRC.
l H.
Time permitting, the Shif t Engineer will implement operation of the TSC (IP-20), to include activation of Dimension telephones and placing required desks in hall in front of the TSC.
Note: NRC should arrive onsite in approxf;sately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
- 2. 2 At least every two hours, or more f requently if conditions warrant, the Shift Engineer will reevaluate the event using IP-1.
The Shift Engineer on the unaffected unit (s) will handle additional communications.
If the situation no longer exists or should be downgraded, inform a.
the personnel notified in step 2.1.
NOTE:
Site evacuation is probable under these conditions.
2.3 Refer to Table 1 for a quick estimate of maximum offsite dose for a stack relcane, and Table 2 for a quick estimate of the site boundary dose for building release.
l
- Revision
Page 1 n 1 BFN-IPD BFN, IP-5
-Table 1 00T1952 Table 1 Maximum Offsite Donos Corresponding to Noble Gas Release Rates (1) (2) through the Stack at BFN Noble Gas Maximum Offsite Release Rate (1)
Thyroid Dose Rate (uci/s)
(arem/h1 Comments 4
1 X 10 ---------------------- 0. 0 07------------- Average meteorology 4
5 X 10 ---------------------------- 0. 0 3 5 assumed. Maximum dose 5
1 X 10 ---------------------------- 0. 07 rate is at 10.000m.
5X10l-----------------------------035 2 X 10 ----------------- 1.{0 1 X 10
0.
6 6
3 ' 5 X 10 ----------------------------- 2 5--------------
AL ER T 6
S X 10 --- ------------- ----------- 14.---------------- Adv erse me t eorology a ssumed 6
0 -----------------------------19.
for this and larger release X
,fX,10.7-_---_----_----_-_-----_-----21 Maximum dose rate at 8,000 x o 7_
_- 5 7
4 X 10 --------------- 1 10.
7 6 X 10 ----------------------------160.
7 8 X 10 ----------------------------220.
l y s h
---2 0.-----------------If expected to persist over
( 3 ) [ 6 X 10 h--------~~~--~~~~----~~~glO 0.
30 minutes-SITE AREA EMERGENC 1.
0.
2.0 X 10 8
- 2. 5 X 10 ---------------- 80.
8
- 10.
3. 0 X 10 ------------- 1,4 0 0.
5.0 X 10
- 0 X 10 ~~------------ 1 900.
, j y $9-------------------------
g,,2 0 0.-------------------------2,500.--------------,-Ifexkectedtokers 2 m nutes-SIT AREA EMERGENCY-9 X 1 0 -------- - ~ ~ ~ --- 100.
1*
X 10 ------------------------- 5,0 0 0. ---------------- GEN ER AL EMER G EN CY 9
1.
9 2. 0 X 10 ------------------------- 5, 4 0 0.
9 6. 0 X 10 ------------------------ 1 o,0 0 0.
4. 0 X 10 --------------------- 1 J 9
8. 0 X 10 ------------------------22, 0 0 0.,000.
9 I
1.0 X 101 0 ----------------------- 2 7, 0 0 0.
l l
(1) Release rates are equated to offsite dose rates assuming a noble gas and iodine mix. (Ref. Nov. 3,1981 memorandum from M. D. Matheny to Radiological Hygiene Branch Files entitled " Relation of Radioactivity Rates to Emergency Classifications")
(2) Stack release rate (SRR) calculated as follows:
l SRR = (RM 90-147)X(FI 90-271))(2 93 E -3 (3) Release rates larger than this car'ot be measured by using stack monitors (instrumer.ta off-scale high). Request radiochemical laboratory personnel to use TI 67 to estimate release rates by measuring dose rates on SBGTs effluent ducts.
A
~
e Page 1 cf 1 BFN-IPD BFN, IP-5 Wahle. 2 Yf9j Table 2 Site Boundary (1) Doses Corresponding to Noble Gas Release Rates (2) other than through the Stack at BFN Noble Gas Site Boundary Release Rats (2) (3)
Thyroid Dose Rate (uci/s)
(arem/h)
Comments 1 X 10 ------------------------------0.02---------------Average meteorology assumed' 2
e 2
5 X 10 ------------------------------0.11 t
1 X 10 ------------------------------D.22 5 X 10 ------------------------------1.1 1. 2 X 1 0 ------------- ----------------- 2.
5---------------- AL ERT ffl04-----------------------------60.4-----------------------------30.-----------------Adverse meteorology assumed for this and larger release 4
90.
6 X 10 ----------------------------150.
5 l*[fl05----------------------------600.1 X 10 ---------------------------
250.-----------------If expected to persist over 5----------------------------
e 30 minutes-SITE AREA EMERGEh 6 X 10p--------------------------1',500.
-900.
0 l X 10 ------------------------- 2 6
2 X 10 --------------------------3,500,-----------------If expected to persist over j*
X 10 --------------------------
o 6
000.
2 minutes-SITE AREA EMERGENCY 3.hh10--------J----------------4,,500.
6 6
10 -------------------------- 5 00 0. --------- --------G ENER AL EMERG ENCY 4 X 10 --------------------------6,000.
6 6
X 10 -------------------------
,500.
6 X 10 -------------------------
,000.
6 X 10 -------------------------1 1 X 10 -------------------------15,000.
7 2X10--~~~~~~~~~-~~~--~~~-~~~~f0,000.0,000.
7 7
000.
4 X 10 ------------------------ 90,,000.
6 X 101------------------------150,000.
i 1 X 100------------------------
(1) These values are for a ground le el location at a distance of 1,000 meters.
l (2) Release rates are equated to off-site dose rates assuming a noble gas and iodine mix l
(Ref. November 3, 1981 memorandum from M. D. Matheny to Radiological Hygiene Branch l
Files entitled " Relation of Radioactivity Rates to Emergency Classifications"). Either catimates of off-site dose rates will be provided by MSECC.
(3) Release rate calculated from building (reactor, turbine, radwaste) CAMS in accordance with SI 4.8.B.1.a.
l e
4 S
Revision,__/\\
l
- INITIAI, TIME CONTACTED fAK EIMENSION jiQME
/
Bob Metke Athens Dwight Mims Decatur f
R. McPherson Decatur REP COORDINATOR / COMMUNICATOR (Contact 1)
Terry Chinn Athens Bill Roberts Athens Carrol Rozear Decatur PUBLIC SAFETY _ SERVICE SUfERVISOR (Contact 1)
Ralph Jackson Killen t
James Brazell Athens i
k Glenn Lard Florence l
NRCCOORDINATOR(ContaIll
.l Bob Smith Decatur i
Bill Roberts Athens I
I Carrol Rozear L Decatur HEALTH PHYSICS (Contact 1)
Allen Sorrell Florence Ed Cargill Athens Wayne Simpkins 3
Athens V
_RADI0 CHEMICAL ENGINEER (Contact 1)
.m Bill Themison Decatur i
Ausic Clement Athens Weaver Burton Decatur L-m
- Revision M
PAGE 1 of Il BFN - IPD BFN, IP-6 00T191882 ATTACHMEffr 1 Contact one or more (as noted below) from each category by name_. Do not leave a message.
It form each person contacted of the position he was contacted to fill.
MESSAGE: "We have a/an (ALERT) (SITE AREA EMERGENCY) (GENERAL EMERGENCY) condition -
existing at the plant. This is not a drill. Please report to the Technical Support Center immeciately.
SITE EMERGENCY DIRECTOR (Contact 1)
INITIAL TIME CONTACTED flX DIMENSION llQtiE
-George Jones Decatur John Pittman Decatur Eddie Ennis Decatur Ray Hunkpillar k
Decatur
~'
g OPERATION MANAGER (Contact 1) 7 Ray Hunkpillar Decatur Tommy Jordan Muscle Shoals l
A. L. Burnette Florence l
f TECHNICAL ASSESSMENT MANAGER (Contact 1)
Terry Chinn Athens l
f Decatur i
Bill 1homison i
Bob Metke Athens
~
I!AINTENANCE MANAGER (Contact 1)
John Pittman Decatur Jim Swindell Decatur
- R ev is io n thl w
INITIAL TIME CONTACTED flX DIMENSION 11QtiE Tink Haney
)
Athens if h
1,f '
Dwight Mims Decatur R. McPherson Decatur 3
L-
--;~
(
IL.ECTRICAL ENGINEER (Contact 1)
D. Thompson Athens k
Wayne Percle Decatur i
Stan Solley A
Rogersville i
INSTRUMENT & CONTROLS ENGINEER (Contact 1)
Ron Burns Decatur Gary Shanker Woodville Bob Irby Pulaski, TN REACTOR ENGINEER (Contact 1)
Earl Nave Huntsville (Backup provided by shirt technical advisor)
PSO ENGINEER (Contact 1 i
Leonard Bynum Huntsville i
Lee Haygood Kilen SECRETARY (Contact 3)
G. Harrison Athens C. McChristian I
Athens i
o
. Betty Riley Athens Brenda Owens Athens Cindy Car. lisle Huntsville PUBLIC INFORMATION OFFICEh Bob Boyer Decatur
- Revision Ad
,A_ttachment 1 00T191fS2 1
OPERATIONS SPECIALIST (Contact 1)
JRLTJAL TIME CONTACTED IAX DIMENSION jiQE S. Burnette Florence Tomy Jordan Muscle Shoals' Roy Smallwood Killen b
j NSSS SITE ENGINEER (Contact T1 Vacant COMPUTER SPECIALIST (Contact 1)
I
~
Dan Phillips Huntsville Larry Johnson Athens Russ McNutt Athens 3
w 1
4 I
ll 4
l l
l
- Revision
/\\jk i
I
- Page 1 Of 2 BFN-IPD BFN, IP-7 00T191982 ATTACHMEfff 1 Request each person by name by stating " Browns Ferry calling (name)" and indicate the time each person was contacted in the left margin.
Message:
"We have a/an (ALERT) (SITE AREA EMERGENCY) (GENERAL EMERGENCY) condition exsisting at the plant.
Please report to the Operations Support Center irrmediately.
4 Initials Time Contacted Hagg IAX DJ11 HOME O
INSTRUMENT MAINTENANCE (CONTACT '4) n
~
Alton McCaleb
- Athens, Gene Hartsfield Atheno J. D. Thompson Decatt f
Guy Thompson Decattr C
Keh Montgomery Rogersville A
I i
Ron Turberville Athensi i
ELECTRICAL MAINTENANCE (
4) l Mike Jackson Athend i
k John Killen Florence s
Julian Bass Rogersville l
(
\\
\\
Pete McLemore i Rogersvilla Billy Thompkins
\\ Tuscumbi<a.
Jim Fowler Lexington Jim Thompson Decatur
- Revision /\\h i
- Page 2 Of 2 BFN-IPD' BFN, IP-7 T9 M
- JnRiajp, Time Contacted Ham fel DJE HOM8
- MECHANICAL MAINTENANCE (CONTACT JO John Whitt Athens Athens [
Carlos Jones I
i r
i Bobby Laurence Lexington John Beck Town CrgJe Tom Marshall Hartsell*
. Charles Wages Sheffield i
Jimmy Walker Athens 1
-l I
4 3
CAddendum ?
Page 2 of 4 BFN-IPD
~BFN. IP-8 00T19182 2.1.2.2 Goerators If outside the control room, secure.the operation in which they are engaged and proceed to the control room for further instructions and accountability. If within the control room, remain there for instructions and accountability. Each assistant shift engineer will account for operating personnel assigned to his unit and report to the shift engineer. The shift engineer will forward these listings to the Site Emergency Director.
2.1.2.3 Health Physics Technicians Proceed to the Health Physics lab (if habitable) and make an accountability report to the Site Emergency Director, and standby for instructions. If the HP lab is uninhabitable, proceed to the backup HP center in the unit 3 mechanical equipment room, control bay, elevation 617, and report to the shift engineer or the Site Emergency Director and standby for instrumentation.
2.1.2.4 Public Safety Service Emnlovees Man assigned post until instructed otherwise by the Public Safety Service shift supervisor. The PSS shift supervisor, after consultation with the Site Emergency Director, will assign' PSS officers at strategic locations, as needed, compatible with IP-11, Security Access Control. The Public Safety Service shift supervisor will notify construction of the evacuation using attacbaent 1.
2.1.2.5 All Persons Within Plant controlled Areas If he deems it necessary, or if radiation levels would cause a radiation exposure of 100 mrem in unrestricted areas, or if airborne radioactivity is in excess of MPC for uncontrolled 4
areas, the Site Emergency Director, using the public address systems and siren, will order evacuation to the west and east employee parking lots adjacent to the front and rear portals for accountability and additional instructions. If radiological conditions are such that one parking lot is unsuitable for an assembly area, the other lot will act as a backup. Personnel would then exit through their nonnal gatehouse but then proceed l
to the other parking lot.
All plant employees (except those assigned emergency duties) and visitors will proceed to the parking lot adjacent to the front portal for accountability and further instructions. During off shiits, the emergency director appoints and dispatches an accounting officer to this locaticn.
I
- Revision f(
i
~. -
W I
O Page 2a of 4
.BFN - IPD W N.-IP-8 Fieldservicespersonnel,constructionservicespersonnelwQthinCT the protected area, and all.others who entered through the east i
portal will proceed to the parking lot adjacent to the east portal for accountability and further instructions.
t 4
5
- a.
.1 l
i e
i i
a i
t i.
- Addendum _/
I i
tL.
4 Pag 3 4 of 4 UPN-IPD BFN, IP-8 1.
!!calth Physics chockpoints ro'inddent with the PSS accesa control point for survey prior to being released.
If radiation icycla at both employee parking lots are unsafe for occupancy, the assembly point will be moved to a location specified by the Site Emergency Director.
Instructions will* be given by the Site Emergency Director, based on local radiation and contamination conditions, l!c may recall evacuated people as needed.
2.1.2.6 DIVISIOM OF CONSTRUCTION Refer to IP-9 Notification will be made by Public Safety au dear:ritad in 2.1.2.4 2.1.2 7 CONTAMINATED INDIVIDUA[J1
~
Contaminated individuals will be evacuated to the Vilson flydro Plant utility building. The Site Emergency Director will notify the CEC Director and provide for transportation, sheltering, and decontamination through the CEC Director.
The Site Emergency Director will recall individuals through the CEC Director.
2.1 3 VISITORS OUTSIDE PLANT CONTROLLED AREAS Upon hearing the emergency siren, the Public Safety Officer on duty at the gate will lock.all gates to ensure controlled entrance and exit.
Using the Public Safety Scryice radio system, he will summon additional Public Safety officers to assist in evacuation of all visitors from TVA land and adjacent water areas outside the fenced area, lic will then assemble all nonescorted visitors an the de.miF.nated area in the parking lot and account for them to the Sito fmergency furector.. Vinitor'n namen and addrennes will bo recorded and they will be encorted to the main gate, wherc !!calth Physica personnel will check all people and vehicles for contamination prior to their release. Affected areas of Wheeler Lake will be evacuated by the Alabama Divinion of Water Safety, as defined in that section of the State Plan, through the Divicion Emergency Director.
If only a particular area is cleared, the Public Safety officers will rostrict entry to nonescorted visitors and request any who may be in the office area to leave.
2.1.4 ELANT_REERIM An soon as ponnible after pernunnot evacuation han been accomplinhed, procedurca will be inttiated to rentore the plant to normal conditioun.
Complete radiation *ind contamination surveya wil be made prior to plant personnel reentering ovacuated ai can.
The Site Emergency Director will authorize reentry only when he is assured that the caergency has been controlled and reentry is sarc.
eRevision sAi
(
1
l 1
l Page 1 of 2 BFN-IPD I
JFN,IP-11 l
007 191982 SECURITY AND ACCESS CONTROL 1.0 EUSPOSE 1.1 To provide a method for implementation of a predetermined security and access control plan for a plant emergency as declared by the
)
shif t engineer.
2.0 INSTRUCTIONS On notification of a plant emergency by the shift engineer, the shift engineer's clerk or by the undulating siren, the PSS shift supervisor will initiate the following steps:
2.1 Report immediately to the Central Alaru Station. He will take charge of the assignments to the PSS personnel, supervise accountability procedures and maintain comunications with all l
onsite PSS personnel 2.2 If it is a SITE AREA EIERGENCY or GENERAL EMERGENCY, or at the l
request of the 3ite Emergency Director, close all site access I
control points which control personnel entering or leaving the i
site. No personnel except those preauthorized by identification card or authorized by the Site Emergency Director will be allowed to enter. No personnel except those who have (1) been authorized i
by the Site Emergency Director, (2) accounted for by PSS, and (3) monitored by HP will be allowed to leave the site.,
I 2.3 Notify the PSS unit supervisor of the emergency condition.
2.4 Dispatch officers to secure all exterior doors into the plant and all gates on the reservation.
2.5 If it is an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY, or at the request of the Site Emergency Director, dispatch access control officers to the entrance of control rooms. These officers will deny access to the control room of all personnel without the required picture badge with solid red bar at the bottom of the badge. The Site Emergency Director can give authorization for l
other persons to enter the control rooms, if required.
1 2.6 Assign available officers to access portals, east and west. These officers will survey the employees badge, accountability card racks, and visitor ler,.
These officers will then make an accountability by bacge nurricer of all personnel in the plant that, entered these access portals. This list will then be taken to and compared with the Site Emergency Director's assembly area I
accountability list.
- Revision J l
1
Page 7 of 2 liFil-I PD BFN, IP-ll OCT 061981
- 2.7 At the direction of the Site Eciergency Director, the PSS shif t supervisor will assign PSS officers to strategic locations, as needed, and will remain there until the emergency is over.
- 2.8 Periodic radio or phone checks shall be made to the PSS shift supervisor or his designee, by all post assigned officers.
- 2.9 At t he-cud of the emergency, PSS will be relieved from the emergency duties by the Site Emergency Director or the PSS supervisor by radio.
At this time, Public Safety officers will resume their normal duties.
Below is an example of picture badge authorized for access to the control room duricg an emergency.
'\\
f C _2 l
l Person's picture with red background l
TEF3 L. Oi!*
337 lG2421 112%
NLc Pn llelow is an example of I.D.
card authorized to gain access onsite during emergencies.
They will be required to be shown to Public Safety of ficers at predetermined locations.
(Example:
County road, access road to plant etc.)
t
(:
1.
~,
This le to certify that k.y f"{ry L. Olinn a
i:a.e-,
e Tennessee Valley Authority at j.
i -
,a the Browns Ferry Nuclear Plant l
~
asz AffAd f4nployee S.enetw's H.L. Aberareenhee Plant superhetendent
' Revision h I
1 l\\ _
Page 1 of 6 BFN-IPD
-BEN,IP-111 0071eM2 miau m a2Rxrows 1.0 ERPME
'Ihis procedure outlines the actions to be followed by Health Physics personnel during a plant emergency.
2.0 DENERAL 2.1 The magnitude of the response by health physics is dependent on the type of emergency existing. This can range from no response at all to a total manpower mobilization.
2.2 It is possible that for a given emergency no radiological problems will be encountered. Natural phenomena, security threats, or other events not involving radiation could be the cause for the emergency alert. This procedure describes those HP actions required during an emergency involving radiological problems.
2.3 NOTE: Shift Engineer's clerk will initiate TP-ill by calling the Health Physics Shift Supervisor QAX
..f (Initials) notifying the Shift Supervisor that there is an NOTIFICATION OF USUSUAL EVENT, ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY and that health physics is to initiate IP-111.
3.0 MIJElCATlD1LOF_llMI.!MlVENI 31 No offsite radiological problems are postulated during a NOTIFICATION OF UNUSUAL EVENT. Transportation of a contaminated injured individual to a hospital, a fire lasting more than 10 minutes, or if radiological effluent technical specifications are exceeded are all examples of an unusual event.
3.2 These events require a certain notification to be made to an offsite agency. These events will not have any major impact on the health physics unit.
3.3 It shall be noted that in many cases Health Physics will not even know that a NCiIFICATION OF UNUSUAL EVENT occurred. Notification is made when health physics response is required.
3. 11 Health physics will follow standard practices and procedures during any response work.
14. 0 ALERI l
4.1 A limited release is possible during an alert situation. Onsite
- Revistm.J)_
emergency teams may be activated and offsite agencies contacted.
l Severe loss of fuel cladding, or high radiation levels (e.g.,
l
Page 2 cf 6 BFN-IPD increase of factor of 1000 in direct radiation readings) are examples of an ALERT' situation.
4.2 All health physics technicians should report to the HP lab unless directed otherwise by the Site Emergency Director. Upon activation of the TSC and OSC, the following equipment will be carried to each center by the health physics section:
1 Ion chamber survey instrument, i
Health physics personnei will periodically servey the TSC and OSC.
i A health physics technician will accompany any personnel dispatched into areas of potential hazard.
4.3 It should be noted that an ALERT situation may require the evacuation of a certain plant area and/or building. Health physics will ensure that* these areas are properly posted and that arrangements are made with public safety to restrict all unauthorized access to the affected area (s).
4.4 Health physics personnel will assist in the development of all recovery plans as necessary. Reconsnendations will be made to keep i
exposures as low as reasonably achievabic and to reconrE*1 and approve any cleanup activites.
4.5 Health physics technicians will survey all vehicles and personnel I
with RM.-14 friskers and smear techniques prior to release from the ~
site.
5.0 SITE ARFA EMERCFNCY 5.1 During a SITE AREA EMERGENCY there may be releases to the environment requiring health physics response. A degraded core, or a large object dropped onto the spent fuel storage area are j
examples of a site area emergency situation. Initial offsite environmental assessment will be conducted per HPSIL 56.
i 5.2 A SITE AREA EMERGENCY may require the evacuation of a plant building and/or buildings.
5.3 Personnel will be called to assemble for. accountability as described in IP-8 and IP-9.. Health physics personnel shall secure work in a safe manner and proceed to the health physics laboratory l
if habitable. If not, go to the mechanical equipr.ent room in the control bay, elevation 617, unit 3.
Upon activation of the TSC and OSC, the following equipment will be carried to each center by the health physics section:
1 Ion chamber survey instrument.
Health physics personnel will periodically survey the TSC and OSC.
A health physics technician will accompany any personnel dispatched l
into areas of potential hazard.
hik' 5.4 An accountability report will be made to the Site Emergency
- Revisten
Page 3 of 6 BFN-IPD Director.
At this time, information should be gathered describing the emergency situation and health physics representatives should be sent to the assembly areas to determine if any workers were in the affected plant areas at the time of the event. These people should be separated from other plant workers and personnel contamination surveys initiated for all personnel.
5.5 As reports become available regarding the details of the emergency, health physics personnel shall prepare all necessary equipment needed during recovery and ready a survey team (s) for entry into the affected area (s).
~
5.6 Upon notification from the Site Emergency Director, the survey team may proceed to the specified area. It should be noted that depending on the type of accident, this initial survey may be performed within hours or days or perhaps even longer. In this event, procedures may be developed describing the reentry steps to be followed.
Other essential personnel may be required to assist in reentry surveys.
5.7 A site boundary survey may be required. This survey should not be done without prior conpultation with, and approval of the Site Emergency Director.
5.8 The emergency van will be utilized during site boundary surveys.
The van is already equipped with numerous supplies; however, the equipnent listed in attachment 1 should te transported to the van.
59 When instructed to do so, travel to the site boundary in the down wind direction and measure the dose rate with an ionizaton chamber or similar survey instrument. If possible, air sampling should also be performed at the same time.
5.10 Precautions must be taken to prevent overexposure if there are high concentrations of radioactive particulates or radioiodine being released.
5.11 Record all survey results. All findings shall be reported to the emergency control center. If results indicate offsite contamination, the survey may need to be extended. Obtain further instructions and perform required surveillance.
5.12 Arrangements have been made for manpower support and equipment for offsite surveys for Muscle Shoals.
5.13 A monitoring station will be set up at the site access control points established by Public Safety Service personnel for the purpose of surveying equipment and personnel leaving the site.
Health physics technicians will survey all vehicles and personnel with RM-14 friskers and smear techniques prior to release.
- Revision M
Page 4 of 6 BFN-IPD DFN, IP-14 00T191982 6.0 fEdiUXJEERGENC1 6.1 During a GENERAL EFERGENCY, there may be radiation releases to the environment requiring health physics response. 'these releases may require evacuation procedures to be implemented as described in IP-8 and IP-9.
Initial offsite environmental assessment will be conducted per HPSIL 56.
6.2 An extensive health physics response will probably be required during a general emergency. Upo.n activation of the TSC and OSC,.
the following equipment will be carried to each center by the health physics section:
1 Ion chamber survey instrument.
Ilealth physics personnel will periodically survey the TSC and OSC.
A health physics technician will accompany any personnel dispatched into areas of potential hazard.
6.3 The actions described under SITE AREA EMERGENCY (paragraphs 5.3 to 5.11) will be applicable to a GENERAL EMERGENCY condition as well.
6.4 During a general emergency (and perhaps during a SITE AREA EMERGENCY), conditions in the health physics laboratory may be such that evacuation is warranted. If this situation developed, a health physics laboratory would need to be established in the mechanical equipnent room in the control bay, elevation 617, unit 3.
This lab would be equipped with all necessary supplies and instrumentation needed to perform minimtzn radiological surveys and analyses required during an emergency.
6.5 If it is necessary to evacuate the !!P Jab, then the llP technicians stationed in the lab will secure the equipnent listed in Attachment 2.
This equipment will be brought to the mechanical equipnent room, control bay, elevaton 617, unit 3 by health physics. This list is a minimtzn and if time permits and manpower allows, then efforts should be made to transport additional equipment and supplies. The Site Emergeny Director shall be informed when it l
becomes necessary to evacuate the HP lab.
I f
6.6 All subsequent offsite activites must be coordinated with all i
offsite support agency survey teams. Make the best use of available manpower. Report all survey results as soon as possible to the emergency center so they can make reconsnendations to the proper agencies to initiate any required protective actions.
6.7 A monitoring station will be set up at the site access control points established by Public Safety Service personnel for the purpose of surveying equipnent and personnel leaving the site.
Health physics technicians will survey all vehicles and personnel with RM-14 friskers and smear techniques prior to release.
[
- Revision AI l
I
Page 5 of 6 BFN-IPD BFN, IP-14 007 191982 7.0 ISSUANCE OF POTASSIUM IODINE (KI)
If a responsible health physicist or other knowledgeable individual has reasons to believe that a person's projected cumulative dose to the thyroid from inhalation of radioactive iodine might exceed '3 rems, the exposed person should be started immediately on a dose regimen of potassium iodine (KI). Anyone authorized to initiate KI shall be familiar with the Food and Drug Administration approved package fnsert and be sure that each proposed recipient is similarly informed. The initial dose of KI should not be delayed and those who begin therapy should continue the 10-day course of KI unless their thyroid dose is determined not to have exceeded 10 rem. An adequate supply of KI is stored at each nuclear facility to supply any personnel exposed to radioactive iodine. It is supplied in bottles which contain a full a
1C-day dose regime. Follow dosage scheduled as outlined on the package insert accompanying each bottle of KI.
7.2 Projected cumulative doses to the Lnyroid from inhalation of radioctive iodine can be determined using the chart Occupational Dose from Inhalation of Iodine-131 (Attachment 3).
7.3 The potassium iodine is stored ir$ the plant medical station. KI has an approved shelf-life with the expiration date listed on each bottle. To ensure that the KI supply is valid, these dates will be inspected during the emergency medical supply inventory and the bottles replaced as necessary.
7.4 A copy of the Food and Drug Administration approved package insert shall accompany each bottle of KI issued. Dosage scheduled and other pertinent information are outlined on the package and should be followed closely (Attachment 4).
7.5 The issuing agent shall complete the Potassium Iodine Issue Report (attachment 5) for each bottle of KI issued. A copy of this report will be routed to the plant health physicist in a timely manner.
8.0 USE OF NRC ORANGE PHONE (HEALTH PHYSICS NEWORK) 8.1 Tnis phone is located in the HP plant laboratory and the NRC Resident Inspector's office.
8.2 The phone is to be used by TVA personnel _qnly under the following circumstances:
a.
Jncoming call from NRC.
b.
Incoming call from another reactor site, if call is made at request of NRC at that site. Individual answering phone should verify that incoming call is made at NRC request.
Outgoing call to another reactor site at request of NRC at c.
Brom:s Ferry i
- Revision Jt,
i 1
J
(
- Page 6 of 6 i.
BFN-IPD l
TFN, IP-14 8lI;T191992 d.
Outgoing call to the two numbers (NRC) ]isted on the phone.-
This is to be'used in the event of an emergency, or as a third.
backup to the ENS (red phone) and Bell system during an j
emergency.
i l
I
)
i
- i-4
)
i l
4 1
i I
I, I
l l
i t
}.
/
- Addendum -Al
_-... _ _ _ _. - _ _,_,._.._..,_ ___,_._._,_,. ~.__. __.- _ __._ --.., _.__ _ _ _ _ _. _ --- _ -_ __ __ _ _.___
W6., ~
i ve,e
'N
,J
~
ye y3 j
,s t_
5
?
t
'Page 1 of 1 v.
1 BFN-IPD Q
+
!WN, IP-18 CDT191862 POTENTIAL BFfRASE EVALUATION PROCEDURE q
1.0 PURPOSE
(
To provide the methodology for estimating actual or potential V
's radionuclide relases in gaseous effluents in the event of a loss-of*. coolant accident.
2.0 SCOPE a"
,,y f
Thest. procedures are to be used for calculating total'nhble gas and total.
/
iodine release rates from the stack and turbine building ~in the event of a small to medaum break loss-of-coolant accident. Glis will incidde (1)
- a projection based on current (actual) plant operating data pad,(2) a'n evaluation of potential' release rates based on assumed furt.her ' O 'i y
j degradation of plant conditions.
g q
- 2.0 RESPONSIBILITI5S C
4 Upon indication at the site that an emergency situaticr exists, site s
personnel will 0e responsible for data collection; and ?cle% rate 1
o calculatfor.a until the KEC is staffed. Once staffed,'othe FIC will assume lead respohsibility 'for the calculation of release potentia). Data for
?
the KECievaluation will be updated on a 30-minute interval'by designated site perfonnel.. After the KEC results end assumptions,han baen o
coordinated with and approved 'by the TSC, KEC will transmit the rscults o
o to the MSEC for subsequent off site dose. calculations.
l' s
s i
s 4.0 REQUIREMENT
$}
4 g
Y Implement the model described in the_ Appendix. ~.
s
~
a
, }l_ j 4 v
i kj
' p
,s
&j y O
,g y
>~
,3 o
a
- ~
J s
ci 4
g.
m us
~
r
- lh'Vi s ion g
\\
.L
,S-
+
Page 1 of 2 BFN-IPD BFN, IP-19 00T1919f12 OPERATION OF THE EMERGENCY DATA INFORMATION SYSTEM 1.0 PURPOSE 1.1 To provide instructions for operation of the Emergency Data Information System CRT and lineprinter located in the Technical Support Center.
2.0 INSTRUCTIONS 2.1 The Emergency Data Information System is a message switching system which provides a means of creating, editing, and sending messages to other sites. The user comunicates with the system through a Televideo terminal located in the T.S.C.
2.2 System Start-up: To use the system, the user must first log on the system with the following procedure:
2.2.1. Enter
HELLO BFTSC 2.2.2.
The sy' stem will respond with " PASSWORD":
2.2.3 Enter EfJf and type a return.
The password will not be typed on the screen as it is entered.
2.2.4.
The system vill respond by printing a list of available options for the message switching program.
NOTE: If the account name or PASSWORD is entered incorrectly, the system will print an error message and the procesu must be repeated.
2.3 After correctly logging in, the user will celect required syster l
function and make necessary keyboard entries for the selected l
function as listed below. Functions available to the user are:
l l
Function Function Key Exit the current module F1 i
Program stop F2 Display meteorological data F3 List, edit, and review messages F4 i
Release a message to another site F5 Create a new message F6 Edit / display the next page F8 Edit / display the previous page F9 Edit /save changes made to the current page F10 Edit / refresh the current page F11
" Revision A
- Page 2 of 2 BFN-IPD BFN, IP-19 007 191962 2.0 INSTRUCTIONS (cont.)
2.4 To select a function, press the corresponding function key. The function keys are on the top row of the Televideo terminal keyboard. -Each of the functions and their uses are described'in the attached user manual.
2.5 Modules Available 2.5.1 Create module.'
2.5.2 Edit module.
2.5.3 Release module.
2.5.4 List module.
2.5.5 Display Met Data Module Use of each module is described in detail in the attached user manual.
J 4
f 1
i 7
k.
P2ge 1 cf 5 BFN-IPD BFN, IP-20 GOT191982 TECHNICAI. SUPPORT CENTER (TSC)
OPERATION 1.0 filf E SE To establish the TSC organization and proide for TSC operation after it is manned. This should begin within 30-minutes to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after plan activation. Activation of the TSC in required only during an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY.
1.0 INSTRUCTIONS Note:
. Refer to Figure 1 of IP-20 for Radiological Emergency Organization Chart.
2.1 As soon as possible after the shift engineer has begun plan activiation the TSC should be established. See Attachment 2 for activating TSC phones.
2.2 The shift engineer designated by the schedule will assume the duties of the Site Emergency Director and man the TSC until relieved. When relieved, he will continue to act as the principal comunicator with DNPEC until relieved by the REP Coordinator / Communicator. If a second shift engineer is assigned to the shift, he will direct activites on the affected unit.
2.3 Establish communications with the Division of Nuclear Power Emergency Center (DNPEC) dimension phone or alternate means as listed in IP-23.
(Duty will be assumed by REP Coordinator /Comunicator notified in IP-6 upon arrival at the TSC).
2.4 Shif t engineer will maintain log of events and communications.
(Duty will be assumed by secretary notified in IP-6 upon arrival at the ECC.)
2.5 Site Emergency Director will verify that all positions in the Emergency Organization (Figure 1) are filled, or will call in additional personnel from the call list in IP-6.
2.6 Site Emergency Director will reevalute emergency conditions in accordance with IP-1 every two hours or more often if conditions warrant.
2.7 Maintenance Unit Supervisor or individual designated by the Maintenance Manager will direct each area of the OSC and will communicate with the Maintenance Manager. The Site Emergency Director will communicate with OSC through these indlykluals. OSC PAX numbers are: Ecchanical\\
ELestrJsnLL htsLtzumnL.aLL%
- Revision
/\\
f
- Pane 7 of 5 BFN-IPD
-BFN, IP-20 00Ti919f72 2.8 Technical Assessmt'.c Manager will direct the technical staff in the TSC.
2.9 The TSC is located on the 3C level of the control bay, between the units 1 and 2 and unit 3 control rooms. Physical layout of the TSC is shown in Figure 2 of this procedure. The lunchroom, located between the relay room and units 1 and 2 control room is available for extra working space.
Note: Additional communications for the TSC are available in the shift engineer's office.
2.10 The T3C communicator will keep the TSC informed of plant conditions, especially information required for use in IP-18.
2.11 Responsibilities of positions in. the TSC and individuals assigned these positions are as listed below:
2.12 Reference books available for TSC use during an emergency are listed on Attachment D.
Site Emergency Director 1.
Directs activities of site emergency organization.
2.
Consults with CECC on important decisions 3.
Initiates protective actions onsite 4.
Coordinates as necessary emergenc:
with onsite NRC.
Operations Manager 1.
Directs operational activities.
2.
Informs Site Emergency Director of plant status and operational problems.
3.
Performs damage assessment as necessary.
4.
Recommends solutions and mitigating action for operational problems.
Technical Assessment Manager 1.
Directs onsite radiological monitoring and effluent assessment.
2.
Directs activities of system status evaluators.
l 3.
Projects future plant status baccd on present plant conditions.
4.
Kecps assessment team informed on plant status.
5.
Provides information, evaluations, and projections to Site Emergency Director.
Maintenance Manatic 1.
Directs repairs and corrective actions.
2.
Performs damage assessment.
3 Directs activities of Operational Support Center.
4.
Coordinates repair activities with the nuclear central office, n
- Revision /\\l f
t
- Page 3 of 5 BEN-IPD BEN, IP-20 00T ?.902 1EP CDobdinatorEDymunLentpx 1.
Advises site emergency director regarding overall radiological emergency plan, use of procedures, emergency equipment availability, and coordination with DNPEC, KEC, and MSEC.
2.
Evaluates plant status and performs principal connunications with DNPEC.
3.
Maintains plant status board in TSC.
~
Secretaries 1.
Maintains log of events.
2.
Maintains accountability of TSC personnel.
3.
Answers telephones.
4.
Other duties as assigned by Site Emergency Director.
5.
Maintains REP Organization Board.
TSC Communicator 1.
Provides data from control rooms to Technical Assesssment Manager.
Eghlic Safety Services Sucervisor.
1.
Directs activities of public safety services personnel.
2.
Controls access to site and centrol rooms.
3.
Reports on accountability in case of evacuation.
Eastiochemical Ennineer 1.
Coordinates with MSEC assessment of radioactive effluents.
2.
Directs post-accident campling activities.
3.
Directs activities of the radiochemical laboratory.
4.
Determines impact of incident on radwaste and various effluent treatment systems.
5.
Maintains status maps and coordinates assessment of radiological conditions offsite with MSEC.
6.
Provides meteorological and dose protection information.
liqchanical Ennineer 1.
Determires the status of SDGT, control bay ventilation, reactor building ventilation, RHRSW, EECW, HPCI, RCIC, diesels, and emergency breathing air.
Reggipr Ennineer 1.
Determines the status of core, RHR, core spray, and CRD hydraulic.
Instrument & Controls Ennineer 1.
Determines status of computer systems, HPS, and control room instrumentation.
0 Revision Ap l
- Page 4 of 5 BFN-IPD BFF, IP-20 007 191962 E, lac _tr.ical Ennincer 1.
Determines status of 161 and 4KV systems, DC systems and batteries, diesel generators, communications systems, and lighting systems.
11ealth Physicist 1.
Directs and/or performs assesment of inplant and onsite radiological conditions.
2.
Directs onsite HP actvities.
3 Coordinates additional HP support with H3EC.
4.
Makes reconmendaticns for protective actions for onsite personnel.
S.- Coordinates effluent and offsite dose assessment with MSEC.
6.
Maintains inplant radiation status board.
HQ_hnail19SI 1.
Determines status of 500 KV and 161 KV syste;ns, and communications.
NSSS EnRineer 1.
Advise on all NSSS systems.
NRC Coordinator 1.
Acts as primary liason with onsite NRC personnel.
2.
Updates NRC personnel of plant status.
3.
Provides infonnation requests from NRC to TSC personnel.
DAemt.1_oALlipssialik.t 1.
Provides operational knowledge into status evaluation of all plant systems.
I 2.
Provides advice regarding technical specifications, system response, safety limits, etc. to system status evaluators.
3.
Assists in development of recommemded solutions to developing problems.
Computer Engineer 1.
Provides assistance to TSC by maintaining computer, repairing hardware, software development, etc.
2.
Troubleshoot, maintain, and repair TSC computer systems and peripheries (when installed).
2.13 Key emergency communication systems and numbers are listed in IP-23 for t>oth onsite and offsite conmunications.
2.14 In events lasting longer than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, long term operations will be undertaken as described in IP-22.
2.15 Calculations made in accordance with IP-18 will be forwarded to DNPEC, KEC, MSEC via dimension phone or by alternate conrcunications A
- Revision.h p,as described in IP-23.
j
O Page 5 of 5 BFN-IPD
. BFN, IP-20 b 0 b. )
2.16 Communicationn of other technical information will be via dimension phone or alternate cm nunicat,lonh a:: described in IP-23 to the DNPEC, KEC, or ICEC, as appropriate.
2.17 Ringdown with Chattanooga, Muscle Shoals, and Knoxville via dimension is operated as follows:
Number Jocation 22 + 200 DNPEC 23 + 361 Sequoyah TSC
~
2 11 MSEC 25 KEC 26 BFNP TSC 99 All (Conference) 2.18 The llRC role on.,ite is to observe, advise, and concur with licensee decisions and actions. If a situation arises where the NRC wants an action taken regarding plant operation that TVA does not, agree with, the Site Emergency Director shall require the NRC to sign a Written Order (per 10 CFR 2) directing TVA to take the action before the Site Emergency Director will comply.
2.19 should it be necessary to evacuate the TSC, the comunications room will act as the alternate TSC.
2.20 Refer to Attachment B for TSC dimension phone numbers.
Page 1 of 1 BFN-IPD BFN, IP-20 Attachment B
[h. 3k k TECHNICAL SUPPORT CENTER - DIMENSION PHONE NUMBERS TITLE f.lLONE m-Site Emergency j
i
-Operations Manger f
REP Coordinator /Conrnunicator
}
NRC Coordinator Technical Assessment Manager Maintenance Manager i
Health Physicist Radiochemical Engineer Mechanical Engineer Electrical Enginee.
I & C Engineer Reactor Engineer NSSS Site Engineer Operations Specialist Secretary PSO Engineer i
Secretary NRC Site Director of Operations NRC NRC
\\
NRC NRC 1
Any G
PAX l
1Rinlm at Secretary'n denk
, and can be transferred via dimennion to any phone in TSC.
'i: v is tim f]Jf, _
Pegs 1 BFN-IPD BFN, IP-20 REFERENCE BOOK LIST Reference Where Available 1.
Chemical Rubber Company (CRC) Handbook of Chemical Unit Chemistry and Physics 2.
Cameron Hydraulic Data (Ingersoll-Rand)
Engineering Test Unit 3.
Steam Tables; Keenan, Kayes, Hall & Moore Engineering Test Unit (John Wiley & Son, Inc.)
4.
Compressed Air and Gas Data Book Engineering Test Unit (Ingersoll-Rand) 5.
American Electricians Handbock; Craft, Electrical Maintenance Carr, Watt; (McGraw-Hall Book Co.)
6.
Flow of Fluids (Crane Tech Paper 410)
IM Supervisor's Office or Chemical Unit or Engineering Test Unit 7
CRC Hanobook of Radioactive Nuclides Chemical Unit 8.
Radiological Health Handbook IM Supervisor's Office 9.
Table of Isotopes Engineering Test Unit or Chemical Unit
- 10. Standard Handbook for Mechanical Engineers Compliance Staff
- 11. Dangerous Properties of Industrial Materials Chemical Unit
- 12. Chemical Engineers Handbook (McGraw-Hal1}
Chemical Unit
- Addendu N a
Page 1 of 1 BFN-IPD BFN, IP-21 OPERATIONS SUPPORT CENIER (OSC) hh[19jhhh OPERATION 1.0 PURPOSE To provide for OSC operation after it is manned. This should begin within 30-minutes to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after plan activation. Activation is re aired only during an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY.
s 2.0 INSTRUCTIONS NOTE:
Refer to Figure 1 of IP-20 for Radiological Emergency Organization.
2.1 The OSC is located in three maintenance shop offices as follows:
Mechanical - Mechanical maintenance shop office, elevation 565 service building.
(Figure 1)
Electrical - Electrical maintenance shop office, elevation 565 service building.
(Figure 1)
Instrumentation - Instrument maintenance shop office, elevation 580 service building.
(Figure 2) 2.2 Any necessary emergency supplies for the OSC can normally be found in the shop areas, but a cabinet in the Central Alarm Station can be used as necessary.
2.3 The Maintenance Manager located in the TSC will direct the overall OSC effort. The maintenance unit supervisors (mech, elec, inst.)
or other individual designated by the Maintenance Manager will supervise their respective areas. They will be in communication with the TSC. These individuals will also assume responsibility for OSC peronnel accoutability in their area, and will log individual in/out.
2.4 The Maintenance Manager will keep the OSC informed of plant conditions.
2.5 In events lasting lor,ger than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, long-term operations will be undertaken as descrlbed in IP-22.
2.6 Should evacuation of the OSC be necessary, the Control Bay Hallway, elevation 1C, will act as backup.
2.7 See Attachment 1 for Limension and PAX phone numbers.
0 Revision /T
P ga 1 cf 1 BFN - IPD BFN, IP-21
_ TECHNICAL SUPPORT CENTER - DIMENSION PHONE NUMBERS s
00T191982 TITLE PHONE I
Site Emergency Director Operations Manager REP Coordinatcr/Comunicator NRC Coordinator Technical Assessment Manager Maintenance Manager Health Physicist Radiochemical Engineer Mechanical Engineer Electrical Engineer I & C Engineer,
i Reactor Engineer NSSS Site Engineer i
Operations Specialist Secretary l
PS0 Engineer
{
Secretary i
j NRC Site Director of Operations NRC NRC NRC NRC e
Any RAX v
1 Rings at secretary's desk and can be transferred via dimension l
to any phone.
i
- Revision /Yl/
i r i
- Page 1 of 2 BFN-IPD
- BFN, IP-22 007191982 LONG TERM OPERATION 1.0 PURPOSE To provide for operation with emergency conditions categorized as ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY which exist or are projected to exist for more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
2.0 INSTRUCTIONS 2.1 When an emergency condition has existed or in the Site Emergency Director's judgement will exist for greater than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, he will take the steps outlined for long-term operations.
2.2 Notify DNPEC of decision to begin long-tenn operation.
DNPEC will make arrangements necessary for food, clothing, and other supplies requested.
2.3 Food is immediately available in the, plant and outage lunchrooms.
The Site Emergency Director, through the DNPEC, will arrange for delivery of meals to the plant at specified times. The plant lunchroom will serve as dining facilities for all emergency personnel.
2.4 The upper level of the office building will serve as the primary sleeping area. If radiological or other conditions do not permit this area to be used, provisions will be made through the DNPEC for near-site lodging, or for other sleeping areas onsite.
2.5 The lunchroom in the control bay at elevation 3C will serve as an assembly room for meetings, etc. The plant assembly roan can also be used if additional space is needed and radiological conditions permit.
2.6 Additional personnel can be called in by the Site Emergency Director to provide coverage in the following areas:
a.
Drawing Control Center b.
Document Control c.
Administration d.
Additional clerical support 2.7 The Techical Support Center will be placed on 12-hour shifts. The Site Emergency Director will establish the 12-hour shifts and provide for calling in additional personnel from IP-6 to fill key positions in the Radiologeal Emergency Organization.
0 Revision /YI V
F l
- Page 2 of 2 BFN-IPD
- BFN, IP-22 00T191982 2.8 The Maintenance Manager, through the designated individuals in charge of the OSC will establish 12-hour shifts for the OSC personnel. The OSC personnel will, in turn, establish 12-hour shifts for their craft personnel onsite and call in additional personnel as necessary.
29 During long-term operation, all key positions shown in Figure 1 of IP-20 will be filled to the extent possible.
2.10 If additional personnel are needed in particular areas, they will be filled with onsite personnel or offsite personnel, dependent on the situation.
O e
- Revision d M (A
Page 1 of 5 BFN-IPD BFN, IP-23 OCT19B8P-COMMUNICATIONS SYSTEMS 1.0 PURPOSE To provide a ready reference of onsite connunication capabilities and key telephone and pager nanbers on and offsite.
It also specified which lines of communication are assigned to which individual or group.
2.0 INSTRUCTIONS 2.1 Communications in shift engineer's office m
a.
, - For shift engineer use.
b.
NRC ring-down (GPO-1488) - For initial use by TVA, until NRC arrives onsite.
Bell (dimension) system (
, - For Site Emergency Director c.
and TSC use, d.
Repeater radio (F1, F2) - For operations or PSS use.
e.
Paging system (beeper) - For shif t engineer use. S.ee Attachment B.
f.
PAX executive right-of-way - For Site Emergency Director use.
g.
Turret extension (receiver only) - For shift engineer use.
h.
Ring-down to/from superintendent's office - For shif t engineer use.
2.2 Communications in Technical Support Center a.
PAX lunchroom or relay room) - For TSC use.
b.
PAX lines) - For TVA and NRC use.
c.
Bell (Dimension) System - For TVA & NRC use - See Attachment D for numbers.
d.
Private circuit with Chattanooga, Muscle Shoals, Knoxville -
For TSC use (see IP-20 for numbers).
e.
NRC ring-down (GPO 1488) - For NRC use, f.
PSO ViiF radio - For PS0 or Site Emergency Director use.
- Revtsion /td 1
r
- Page 2 of 5 BEN-IPD
-BFN, IP-23 00T191982 g.
Emergency Data Infonnation System (CRT/Lineprinter).
2.3 Communications in ooerations suooort center a.
Mechanical - PAX Dimension.
b.
Electrical - PAX (;
Dimension, c.
Instrumentation - PAX g.
2.4 Kev Onsite Numbers Location Phone (PAX)
DIMENSION Assembly Room Ce'ntral Alarm Station Chemical Laboratory Code Call Code Call (Answer)
\\
\\
Comr.unications room Construction (CSB) i Document Control Drawing Control j
f East Gatehouse I
Fire i
llb Health Station
- l Health Physics Laboratory Lunchroom onevision_gA{
Medical Emergency Meteorological Tower NRC (onsite)
Page 3 of 5 BFN-IPD BFN, IP-23 00T191982 Bell Operations DE Mechanica_1_
\\'
Electrical 1
Jpstrumentation Field Services Paging System Plant Superintendent's Office Power Stores PSS shif t supervisor Shif t engineer's office Shift technical advisor 1
TSC TVA ambulance West Catehouse 2.4 Kev Offsite Numbers Loca_ tion fAqng lehplpm i
AAA Southend (Decatur)
\\
Athens Limestone Hospital l
l Metro Shoals Emergency Hospital Serviced (Florence)
- Revision AN 4
~ -. - -
Page 4 of 5 BFN-IPD
'BFN, IP-23 00T191962 Hosoitals Athens-Limestone Colonial Manor (Florence)
I Decatur General
[
REAC/TS (Oak Ridge, TN)
CECC (Operations Duty Specialist)
AX KEC Pr,1 atA circuit,_from TSC 3
~.
s PAX Dimension.
k MSEC Private cireti Q om TSC s
g
[.
PAX NRC (Atlanta)
/
(After 4 p.m., rings in
/
Washington) l NRC Bethesda-via HPN Orange phone-Dia2
__ s NRC Operations Center (Bethesda) s j (Comercial, useo upon'a' failure of the Emergency Notification System)
NRC (G. L. Paulk)
Beeper s
Operations Duty Specialist, DNPEC, Dimension #
[
2.6 Information on plant comunications systems (Normal and alternate power supplies, etc.) is shown on Attachment A.
2.7 NRC Orange Phone (HP Network) - his phone is located in the HP l
plant laboratory and the NRC Resident Inspectors Office. he phone is to be used by 'IVA personnel snly under the following circumstances:
a.
Incoming call from NRC.
b.
Incoming call from another reactor site, if call is made at request of NRC at that site. Individual answering phone should
- Revision AI
- Page 5 of 5 BFN-IPD BFN, IP-23 007 191982 b.
Incoming call from another reactor site, if call is made at request of NRC at that site. Individual answering phone should verify that incoming call is made at NRC request.
c.
Outgoing call to another reactor site at request of'NRC at Browns Ferry.
d.
Outgoing call to the two numbers (NRC listed on the phone.
This is to be used in the event of_an emergency, or as a third backup to the ENS (red phone) and Bell system during an emergency.
2.8 To ensure proper pager operation, a monthly functional test of personnel pagers will be conducted in accordance with BF Standard Practice 19.25 using Attachment B.
2.9 Refer to Attachment C for procedure to activate TSC phones.
2.10 Refer to Attachment D for TSC dimension phone numbers.
O l
l I
ORevision AO
- i
Pzgs 1 cf 1 BFN-IPD BFN, IP-23 Attachment B BFNP PERSONNEL PAGER MONTHLY FUNCTIONAL TEST Date PAGER HOME PHONE SECTION NUMBER NUMBER
- AME Superintendent G. T. Jones EM T. D. Cosby EM J. M. Jackson HP A. W. Sorrell Assistant Superintendent J. R. Pittman MM M. W. Haney MM J. B. Walker l
MM f
R. L. Thigpen I
NR Shift Technical Adv Spare j
Spare OPS Spare OPS R. Hunkapillar Field Services J. Miller Spare Spare i
IM R. E. Burns i
Field Services J. E. Swindell
/)
Pager check on the following numbers was unsuccessful:
Signature Remarks Operations Section Supervisor 1
-