ML20078F865
| ML20078F865 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/07/1983 |
| From: | Webb W TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20078F844 | List: |
| References | |
| PROC-830407, NUDOCS 8310110203 | |
| Download: ML20078F865 (168) | |
Text
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REVISION LOG SHEET Revision Date: PORC 4-7-83 (issued 6-16-83)
This log sheet must be retained as the last page of the Browns Ferry Nuclear Plant Implementing Procedures Document.
Date Inserted:
Inserted by:
New Pages to be Inserted Pages to be Removed Part Page Number Revision Part Page Number Revision List of I of 10 3-25-83 List of 1 of 10 6-16-83 Effective 2 of 10 3-25-83 Effective 2 of 10 6-16-83 Pages 3 ofilo 3-3-83 Pages 3 of 10 6-16-83 4 of 10 11-1-82 4 of 10 6-16-83 5 of 10 11-1-82 5 of 10 6-16-83 s
6 of 10 11-1-82 6 of 10 6-16-83 7 of 10 11-1-82 7 of 10 6-16-83 8 o f 10 2-4-83 8 of 10 6-16-83 9 of 10 3-3-83 9 of 10 6-16-83 10 of 10 11-1-82 10 of 10 6-16-83 Table of I of 1 2-8-83
' Table of I of 1 4-7-83 Contents Contents IP-1 1 of 11 10-19-82 IP-1 1 of 11 4-7-83 f
11 of 11 10-19-82h 11 of 11 4-7-83 IP-3 1 of 2 2-4-83 IP-3 1 of 2 4-7-83 2 of 2 2-4-83 2 of 2 4-7-83 IP-4 1 of 2 2-4-83 IP-4 1 of 3 4-7-83 l
2 of 2 2-4-83 2 of 3 4-7-83 3 of 3 4-7-83 l
IP-5 1 of 2 2-4-83 IP-5 1 of 3 4-7-83 2 of 2 2-4-83 2 of 3 4-7-83 3 of 3 4-7-83 i
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8310110203 831005 PDR ADOCK 05000259 PDR l
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REVISION LOG SHEET (Continued)
Subject:
BFN-IPD Revision Date: PORC 4-7-83 (issued 6-16-83)
Pages to be Removed New Pages to be Inserted Part Page Number Revision Part Page Number Revision IP-8 1 of 5 12-21-82 IP-8 1 of 3 4-7-83 2 of 5 12-21-82 2 of 3 4-7-83 3 of 5 12-21-82 3 of 3 4-7-83 4 of 5 12-21-82 5 of 5 12-21-82 Att. I 1 of 1 12-21-82 Att. I 1 of 1 4-7-83 IP-11 1 of 2 12-21-82 IP-11 1 of 2 4-7-83 2 of 2 10-6-81 2 of 2 4-7-83 IP-14 1 of 6 10-19-82 IP-14 1 of 5 4-7-83 2 of 6 10-19-82 2 of 5 4-7-83 3 of 6 10-19-82 3 of 5 4-7-83 4 df 6 10-19-82 4 of 5 4-7-83 t
5 of 6 10-19-82 5 of 5 4-7-83 6 of 6 10-19-82 IP-17 3 of 15 4-22-82 IP-17 3 of 15 4-7-83 IP-19 Cover Page 6-29-82 IP-19 Cover Page 4-7-83 1 of 2 10-19-82 1 of 9 4-7-83 2 of 2 10-19-82 2 of 9 4-7-83 3 of 9 4-7-83 4 of 9 4-7-83 5 of 9 4-7-83 6 of 9 4-7-83 7 of 9 4-7-83 8 of 9 4-7-83 9 of 9 4-7-83 IP-20 1 of 5 12-21-82 IP-20 1 of 3 4-7-83 2 of 5 12-21-82 2 of 3 4-7-83 3 of 5 12-21-82 3 of 3 4-7-83 4 of 5 12-21-82 5 of 5 12-21-82
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REVISION LOG SHEET (Continued)
Subject:
BFN-IPD Revision Date: PORC 4-7-83 (issued 6-16-83)
Pages to be Removed New Pages to be Inserted Part Page Number Revision Part Page Number Revision Att. B 1 of 1 12-21-82 Att. B 1 of 1 4-7-83 Att. C 1 of 1 6-29-82 Att. C 1 of 1 4-7-83 Att. E 1 of 1 4-7-83 Att. F 1 of 1 4-7-83 Att. G 1 of 3 4-7-83 2 of 3 4-7-83 3 of 3 4-7-83 Att. li 1 of 1 4-7-83 Att. I 1 of 1 4-7-83 Att. J 1 of 3 4-7-83 2 of 3 4-7-83 3 of 3 4-7-83 Att. K 1 of 1 4-7-83 Figure 1 1 of(1 12-21-82 Figure 1 1 of 1 4-7-83 Figure 2 1 of 1 12-21-82 Figure 2 1 of 1 4-7-83 IP-21 1 of 1 12-21-82 IP-21 1 of 1 4-7-83 Att. I 1 of 2 12-21-82 Att. I 1 of 2 4-7-83 Figure 1 1 of 1 12-21-82 Figure 1 1 of I 4-7-83 IP-22 I of 2 12-21-82 IP-22 1 of 1 4-7-83 2 of 2 12-21-82
.IP-23 1 of 5 12-21-82 IP-23 1 of 5 4-7-83 2 of 5 10-19-82 2 of 5 4-7-83 3 of 5 12-21-82 3 of 5 4-7-83 4 of 5 10-28-82 4 of 5 4-7-83 5 of 5 12-21-82 5 of 5 4-7-83 Att. A 1 of 1 12-21-82 Att. A 1 of 2 4-7-83 2 of 2 4-7-83 Att. C 1 of 1 6-29-82 Att. C 1 of 1 4-7-83 Att. E 1 of 1 2-8-83 Att. E 1 of 1 4-7-83 IP-25 Cover Page 4-7-83 1 of 2 4-7-83 2 of 2 4-7-83 t
BFN-IPD List of Effective Pages Page 1 of 10 06/16/83 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT IMPLEMENTING PROCEDURES DOCUMENT LIST OF EFFECTIVE PAGES 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 06/16/83 2 of 10 06/16/83 3 of 10 06/16/83 4 of 10 06/16/83 5 of 10 06/16/83 6 of 10 06/16/83 7 of 10 06/16/83 8 of 10 06/16/83 9 of 10 06/16/83 10 of 10 06/16/83 Table of Contents 1 of 1 04/07/83 IP-1 Coversheet 10/19/82 Preface 1 of 1 10/19/82 IP-1 1 of 11 04/07/83 2 of 11 10/19/82 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 li 10/19/82 10 of 11 12/06/82 11 of 11 04/07/83 IP-2 Coversheet 06/15/82 1 of 3 03/25/83 2 of 3 03/25/83 3 of 3 02/04/83 y
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BFN-IPD, List of Effective Pages Page 2 of 10 06/16/83 LIST OF EFFECTIVE PAGES (Con't)
Procedure Page Part Number Subdivision Number Date/Rev. No.
Coversheet 06/29/82 BFN IP-3 1 of 2 04/07/83 2 of 2 04/07/83 Table 1 1 of 1 10/19/82 Table 2 1 of 1 10/19/82 Coversheet 10/19/82 IP-4 1 of 3 04/07/83 2 of 3 04/07/83 3 of 3 04/07/83 Table 1 1 of 1 10/19/82 Table 2 1 of 1 10/19/82 Coversheet 06/29/82 IP-5 e
1 of 3 04/07/83 s
2 of 3 04/07/83 3 of 3 04/07/83 Table 1 1 of 1 10/19/82 Table 2 1 of 1 10/19/82 Coversheet 06/29/82 IP-6 1 of 1 04/22/82 1 of 4 03/25/83 2 of 4 03/25/83 3 of 4 03/25/83 4 of 4 02/14/83 Coversheet 06/29/82 1p_7 1 of 1 12/21/81 1 of 2 02/23/83 2 of 2 12/21/82 Coversheet 06/15/82 IP-8 1 of 3 04/07/83 2 of 3 04/07/83 3 of 3 04/07/83 Attachment i 1 of 1 04/07/83 q
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BFN-IPD List of Effective Pages Page 3 of 10 06/16/83
. LIST OF EFFECTIVE PAGES (Con't)
Procedure Page Part Number Subdivision Number Date/Rev. No.
BFN IP-9 Coversheet 06/15/82 1 of 1 12/21/82 IP-10 Coversheet 06/29/82 1 of 6 06/30/81 2 of 6 02/08/83 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. 0 1 of 1 Rev. O 1 of 1 Rev. 0 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 i
IP-11 Coversheet 06/15/82 1 of 2 04/07/83 2 of 2 04/07/83 i
IP-12 Coversheet 02/08/83 l
1 of 1 02/08/83 IP-13 1 of 2 06/16/81 2 of 2 06/16/81
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Page 4 of 10 06/16/83 LIST OF EFFECTIVE PAGES (Con't) c Procedure Page Part Number Subdivision Number Cate/Rev. No.
BFN IP-14 Coversheet 06/29/82 1 of 5 04/07/83 2 of 5 04/07/83 3' of 5 04/07/83 4 of 5 04/07/83 5 of 5 04/07/83 1 of 1 Rev. O 1 of 1 03/16/82 1 of 1 Rev. O 1 of 1 Rev. 0 l
1 of 1 Rev. O IP-15 Coversheet 06/15/82 1 of 4 Rev. 0 2 of 4 Rev. 0 3 of 4 Rev. 0 4 of 4 03/30/82 IP-16 Coversheet 06/15/82 1 of 2 04/22/82 2 of 2 Rev. O IP-17 Coversheet 06/15/82 1 of 15 01/26/82 2 of 15 03/16/82 3 of 15 04/07/83 4 of 15 03/16/82 5 of 15 01/26/82 1
6 of 15 07,08/82 7 of 15 01/26/82 I
8 o f 15 03/16/82 9 of 15 01/26/82 10 of 15 04/22/82 11 of 15 04/06/82
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BFN-IPD List of Effective Pages Page 5 of 10 06/16/83 2
LIST OF EFFECTIVE PAGES (Con't)
Procedure Page Part Number Subdivision Number Date/Rev. No.
3FN IP-17 '
(Con'd)
Figure 1 1 of 1 06/30/81 Figure 2 1 of 1 04/22/82 Figure 3 1 of 1 Rev. 0 l
IP-18 Coversheet 06/15/82 1 of 1 10/19/82 Title Page 1 of 1 Rev. 0 1
Table of Contents 1 of 1 04/07/81 List of Figures 1 of 4 07/21/81 2 of 4 07/21/81 3 of 4 07/21/81 1
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 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. 0 Figure 1.3 1 of 1 Rev. O Figure 1.4 1 of 1 Rev. 0 Figure 2.1 1 of 1 Rev. 0 Figure 2.2 1 of 1 Rev. 0 Figure 2.3 1 of 1 Rev. O Figure 2.4 1 of 1 Rev. O Figure 3 1 of 1 Rev. O Figure 4.1 1 of 1 Rev. O i
Figure 4.2 1 of 1 Rev. O Figure 4.3 I of 1 Rev. O Figure 4.4 1 of 1 Rev. 0
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BFN-IPD S
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List of Effective Pages f
Page 6 of 10 06/16/83 LIST OF EFFECTIVE PAGES (Con't)
Procedure Page Part Number Subdivision Number Date/Rev. No.
BFN IP-18 (Cont'd)
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. O Figure 5.4 1 of 1 Rev. O Figure 5.5 1 of 1 Rev. O Figure 5.6 1 of 1 Rev. 0 Figure 5.7 1 of 1 Rev. 0 Figure 5.8 1 of 1 Rev. O Figure 5.9 1 of 1 Rev. O Figure 5.10 1 of 1 Rev. O Figure 5.11 1 of 1 Rev. 0 Figure 5.12 1 of 1 Rev. O Figure 6.1 1 of 1 Rev. O Figure 6.2 1 of 1 Rev. O Figure 6.3 1 of 1 Rev. 0 Figure 6.4 1 of 1 Rev. 0 Figure 6.5 1 of 1 Rev. O Figure 6.6 1 of 1 Rev. 0 Figure 6.7 1 of 1 Rev. O l
Figure 6.8 1 of 1 Rev. O Figurc 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. 0 Figure 7.5 1 of 1 Rev. 0 i
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l Figure 7.12 1 of 1 Rev. O
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BFN-IPD List of Effective Pages Page 7 of 10 06/16/83 LIST OF EFFECTIVE PAGES (Con't)
Procedure Page Part Number Subdivision Number Date/Rev. No.
.BFN IP-19 Coversheet 04/07/83 1 of 9 04/07/83 2 of 9 04/07/83 3 of 9 04/07/83 4 of 9 04/07/83 5 of 9 04/07/83 6 of 9 04/07/83 7 of 9 04/07/83 8 of 9 04/07/83 9 of 9 04/07/83 1 of 18 06/29/82 2 o f 18 06/29/82 3 of 18 06/29/82 4 of 18 06/29/82 5 of 18 06/29/82 s
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 06/29/82 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 IP-20 Coversheet-06/29/82 l
1 of 3 04/07/83 2 of 3 04/07/83 3 of 3 04/07/83 Attachment A 1 of 3 12/21/82 2 of 3 12/21/82 3 of 3 12/21/82 Attachment B 1 of 1 04/07/83
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List of Effective Pages Page 8 of 10 06/16/83 LIST OF EFFECTIVE PAGES (Con't)
Procedure Page Part Number Subdivision Number Date/Rev. No.
BFN IP-20 (Cont'd)
Attachment C 1 of 1 04/07/83 Attachment D 1 of 1 10/19/82 Attachment E 1 of 1 04/07/83 Attachment F 1 of 1 04/07/83 Attachment G 1 of 3 04/07/83 2 of 3 04/07/83 3 of 3 04/07/83 Attachment H 1 of 1 04/07/83 Attachment I 1 of 1 04/07/83 Attachment J 1 of 3 04/07/83 2 of 3 04/07/83 3 of 3 04/07/83 Attachment K 1 of 1 04/07/83 Figure 1 1 of 1 04/07/83 2
1 Figure 2 1 of 1 04/07/83 IP-21 Coversheet 06/15/82 1 of 1 04/07/83 1 of 2 04/07/83 2 of 2 12/21/82 Figure 1 1 of 1 04/07/83 Figure 2 1 of 1 04/22/82 IP-22 Coversheet 06/15/82 1 of 1 04/07/83 IP-23 Coversheet 06/29/82 1 of 5 04/07/83 2 of 5 04/07/83 3 of 5 04/07/83 4 of 5 04/07/83 5 of 5 04/07/83 Attachment A 1 of 2 04/07/83 2 of 2 04/07/83 i
Attachment B 1 of 1 12/21/82 W
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BFN-IPD List of Effective Pages
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Page 9 of 10 06/16/83 LIST OF EFFECTIVE PAGES (Con't) i Procedure Page Part~
Number Subdivision Number Date/Rev. No.
BFN IP-23 (Cont'd)
Attachment C 1 of 1 04/07/83 Attachment D 1 of 1 12/21/82 Attachment E 1 of 1 04/07/83 IP-24 Coversheet 06/29/82 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 s
6 of 36 02/23/82 7 of 36 02/23/82 8 of 36 -
02/23/82 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 l
17 of 36 02/23/82
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18 of 36 02/23/82
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19 of 36 02/23/82 20 of 36 02/23/82 21 of 36 02/23/82 22 of 36 02/23/82 l
23 of 36 02/23/82 24 of 36 02/23/82 l
25 of 36 02/23/82 26 of 36 02/23/82 l
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
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BFN-IPD
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List of Effective Pages Page 10 of 10 06/16/63 LIST OF EFFEC 1.7VE PAGES (Con't)
Procedure Page Part Number Subdivision Number Date/Rev. No.
BFN IP-25 Coversheet 04/07/83 1 of 2 04/07/83 2 of 2 04/07/83
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BFN - IPD APR 071983 Table of Contents BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL EMERCENCY PROCEUTIRES IP-1 Emergency Plan Classification Logic IP-2 Notification of Unusual Event
'IP-3 Alert
'IP-4 Site Area Emergency IP-5 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 t
A.
IP-10 Medical Emergency Procedures IP-11 Security and Access Control IP-12 Local Recovery Center IP-13 Deleted
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IP-14 Health Physics Procedures IP-15 Emergency Exposure IP-16 Recovery Procedure IP-17 Emergency Equipment and Supplies IP-18 Potential Release Evalution Procedure IP-19 Operation of the Emergency Data Information System IP-20 Technical Support Center (TSC) Operation IP-21 Operations Support Center (CSC) Operation IP-22 Long Term Operation IP-23 Communication System IP-24 Earthquake Emergency Plan
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'IP-25 Radiochemical Laboratory Procedure
- Revision k
- MSL HICil RADIATION 3 X NORMAL FULL POWER BKG (Alarm & Isolation)
IP-3 ALERT
_ IP-2 NOTIFICATION OF AN OR>25 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' EVENT
- TOTAL > 50 GPM IDENTIFIED AND UNIDENTIFIED IP-3 ALERT LEAKAGE (SI 2)
EQUlit!ENT-
- r.
- DRYWELL UNIDENTIFIED LEAK RATE 2542 SCFH IP-2 NOTIFICATION OF AN PER SI 4.7 A.2.a UNUSUAL EVENT i
- PRESS (PI-64-67 or PR-64-50)>50 psig IP-5 CENERAL EMERGENCY PRIMARY CONTAINMENT e
- RX COOLANT ACTIVITY 3.2 uCi/gm 0F DOSE EQUIVALENT OF I-131, STEADY IP-2 NOTIFICATTON OF AN (RX CRITICAL)
STATE (SI 4.6.B.5), or 26 uCi/gm af ter power UNUSUAL EVENT transient (SI 4.6.B.4/SI 4.6. B.6)
- IODINE CONCENTRATION >300 uCi/gm IP-3 ALERT i
TECllNICAL SPECIFICATION IP-2 NOTIFICATION OF AN LCO OR SAFETY LIMIT REACllED UNUSUAL EVENT REQUIRING LOAD REDUCTION IN ANTICIPATION OF UNIT SIRITDOUN 3
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IP-2 NOTIFICATION OF AN
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-IP-3 ALERT 1
.- FIRE TilREATENING A VITAL AREA
- MAJOR FIRE AFFECTING VITAL SYSTDIS IP-4 SITE AREA DfERGENCY i
IP-2 NOTIFICATION OF AN FIRE EXPLOSION UITilIN SITE BOUNDARIES j~
OR UNUSUAL EVENT l
EXPLOSION IP-3 ALERT
- ONSITE (WITHIN PROTECTED AREA)
IP-3 ALERT
- DAMAGE INVOLVING NONVITAL STRUCTURES L
MAJOR DAMAGE INVOLVING VITAL STRUCTURES IP-4 SITE AREA DfERGENCY (POTENTIAL ESCALATION TO IP-5)
- FINDIABLE CAS OR IP-2 NOTIFICATION OF AN VAPORS UITilIN PLANT BOUNDARIES UNUSUAL EVENT
- WITllIN PLANT BUILDINGS IP-3 ALERT (POTENTIAL ESCALATION TO IP-4) 1
-IP-4 SITE AREA DfERCENCY UITilIN VITAL AREAS
~ STRIKE OR OTilER EVENTS TilAT PREVENT IP-2 NOTIFICATION OF AN UNUSUAL EVENT PROPER MANNING OTilER (1)
PLANT CONDITIONS UllICH REOUIRE IP-4 SITE AREA DfERGENCY I
3 0FFSITE RESPONSE "D.h MAJOR INTERNAL OR EXTERNAL EVENTS UllICll IP-5 GENERAL DIERGENCY Cy,m COULD CAUSE MASSIVE C0!DION DAMAGE TO p
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PLANT SYSTDIS (1) These itcus are based on Site Fnergency Director's professional judgment h
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'Page 1 of 2 BFN - IPD BFN, IP-3 i
Eggt APR 071983 1.0 Purnose 1.1 Provide for timely notification of appropriate individuals and organizations of an E ERI.
1.2 Provide for periodic reanalysis to determine whether the EZEI should be cancelled, continued, or upgraded to a more serious classification.
2.0 INSTRUCTIONS Initinln ling j
2.1 Shift Engineer notify Operations Duty Specialist (40- 200, 50-0200, or 51-0200) within 5 minutes of declaration of ALERT.
Give the following:
a.
Your name l
b.
Browns Ferry Nuclear Plant c.
EEBI.
z d.
Time of incident e.
Brief description of incident f.
Plant condition (whether stable or deteriorating) g.
Reactor (did/did n'ot) shut down at (time) h.
Unusual release of radioactivity (yes, no, or not known) 1.
If a radiation release:
a.
Ground level - airborne b.
Elevated airborne c.
Waterborne d.
Other j
- j. If yes, calculate release rate (s) in
//,Cisec from Table 1 and 2.
Release rate 44,Ci/s c.
k.
Direction wind is coming frcm (degrees) and speed (meters /second).
(Use 300 ft. info. if available).
l 1.
No protective action roccmmended m.
Any emergency actions underway onsite n.
Any offsite support that has been requested agevision N
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Pign 2 of 2 BFN - IPD BFN, IP-3 APR 071933 2.2 Operations Duty Specialist will return call to verify authenticity.
2.3 Shift Engineer will evaluate conditions. If required, initiate area (by public address) or total plant (by siren) evacuation.
Refer to IP-8.
2.4 Shift Engineer's Clerk will:
Notify other Shift Engineer (when assigned) of ALERT.
a.
b.
Notify STA (PAX 353/396/313) of the ALERT.
e c.
Notify Chem Lab Supervisor (PAX 367/368) of ALERT. Direct them to activate IP-25.
d.
Notify HP Shift Supervisor (PAX 300) of ALERT. Direct them to activate IP-14.
Notify Public Safety Supervisor (PAX 273) of ALERT. Direct e.
them to activate IP-11 (Control Rooms Only) and IP-7, 2.5 Shift Engineer's Clerk will:
a.
Initiate IP-6.
'2. 6 Shift Engineer will notify NRC of ALERT by red phone.
Give a brief description. Maintain an open line until released by NRC.
Note: NRC mal send a response team to the site.
2.7 Time permitting, the Shift Engineer will i=plement operation of the TSC (IP-20), to include activation of Dicension telephones and placing requ' ired desks in hall in front of TSC.
2.8 At least every two hours, or more frecuentiv if conditions warrant. the Shift Engineer / Site Emergency Director will reevalute the event using IP-1.
If the situation no longer exists or should be downgraded, a.
inform all personnel previously notified.
b.
If the condition warrants upgrading to a higher classification, initiate the appropriate procedure.
2.9 Refer to Table 1 for a quick esti=ato of maximum offsite dose for a stack release. and Table 2 for a quick estimate of the site boundary dose for building release.
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'Page 1 of 3 BFN - IPD BFN, IP-4 SITE AREA EMERGENCY 1.0 Purnose 1.1 Provide for timely notification of appropriate individuals and organizations of a SITE AREA EMERGENCY,
1.2 Provide for periodic reanalysis of the situation to determine whether the SITE AREA EMERGENCY should be cancelled, continued, or upgraded to a more sericus classification.
2.0 INSTEUCTIONS Initials Ilma 2.1 Shift Engineer notify Operations Duty Specialist (40- 200, 50-0200, or 51-0200) within 5 minutes of declaration of SITE JEEA EMERGENCY.
Give the following:
a.
Your name b.
Browns Ferry Nuclear Plant s
c.
EJIE AREA EMERGENCY d.
Time of incident e.
Brief description of incident
~
f.
Plant condit' ion (whether stable or deteriorating) g.
Reactor (did/did not) shut down at (tine) h.
Unusual release of radioactivity (yes, no, or not known) 1.
If a radiation release:
a.
Ground level - airborne b.
Elevated airborne c.
Waterborne d.
Other
- j. If yes, calculate release rate (s) in 42 Ci/sec frca Table 1 and 2.
Release rate
//C1/sec.
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k.
Direction wind is coming from (degrees) and speed (meters /second). (Use 300 ft. info. if available).
1.
No protective action recommended Any emergency actions underway onsite m.
Any offsite support that has been requested n.
Operations Duty Specialist will return call to verify 2.2 authenticity.
Shift Engineer will evaluate conditions. If required, 2.3 initiate area (by public address) or total plant (by siren) evacuation. Refer to IP-8.
Precautionary site evacuation should be considered.
Note:
2.4 Shift Engineer's Clerk will:
Notify other Shif t Engineer (when assigned) of flIE a.
ARE& EMERGENCY t
i b.
Notify STA (PAX 353/396/313) of SITE AREA EMERGENCY
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Notify Chem Lab Supervisor (PAX 367/368) of flIE AREA 8
c.
EMERGENCY. Direct them to activate IP-25.
d.
Notify HP Shif t ' Supervisor (PAX 300) of SITE AEEA EMERGENCY.
Direct them to activate IP-14.
SITE Notify Public Safety Supervisor (PAX 273) of e.
AREA EMERGENCY. Direct them to activate IP-11 and IP-7 I
2.5 Shift Engineer's Clerk will:
l a.
Initiate IP-6.
I 2.6 Shif t Engineer will notify NRC of 20;]; AREA EMERGENCY by l
red phone. Give a brief description. Maintain an open line until released by NRC.
Note: NRC will probably send a response team to the site.
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'Page 3 of 3 BFN - IPD BFN, IP-4 APR 071983 2.7 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.
2.8 At least every two hours, su more frecuentiv JJC conditions warrant.
the Shift Engineer / Site Emergency Director will reevaluate the event using IP-1.
a.
If the sikaation no longer exists or should be downgraded, inform all personnel previously notified.
b.
If the condition warrants upgrading to a higher classification, initiate the appropriate procedure.
29 Refer to Table 1 for a quick estimate of maximum offsite sbuut for a stack release. and Table 2 for a quick estimate of 21.t.it boundarv f3utg for buildi ncr release.
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'Page 1 of 3 BFN-IPD BFN IP-5 APd 071983
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GENERAL EMERGENCY 1.0 Purnose Provide for timely notification of appropriate individuals and 1.1 organizations of a GENERAL EMERGENCY.
Provide for periodic reanalysis of the situation to determine 1.2 whether the GENERAL EMERGENCY should be cancelled or continued.
2.0 INSTRUCTIONS Initinim Time Shift Engineer notify Operations Duty Specialist (40-200, 2.1 50-0200, or 51-0200) within 5 minutes of declaration of GENERAL EMERGENCY.
Give the following:
a.
Your name b.
Browns Ferry Nuclear Plant GENERAL EMERGENCY
-s t
c.
d.
Time of incident Brief description of incident e.
Plant condition,(whether stable or deteriorating) f.
Reactor (did/did not) shutdown at (time) g.
Unsual release of radioactivity (yes, no, or not known).
h.
1.
If a radiation release:
a.
Ground level - airborne b.
Elevated airborne c.
Waterborne d.
Other b4 Ci/sec
- j. If yes, calculate release rate (s) in j
from Table 1 and 2.
,Li Ci/sec.
Release rate k.
Direction wind is ccming frco (degrees) and speed (Meters /second).
(Use 300 ft. Info. If available).
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Recommended initial protective actions for the public:
Activate warning system and advise public to take shelter, tune radio or TV to a local station, and await further instructions.
Any emergency actions underway onsite.
m.
-n.
Any offsite support that has been requested.
2.2 Operations Duty Specialist will return call to verify authenticity.
23 Shift Engineer will evaluate conditions. If required, initiate area (by public address) or total plant (by siren) evacuation. Refer to IP-8.
Note: Site evacuation is probable under these conditions.
2.4 Shift Engineer's Clerk will:
a.
Notify other Shift Engineer (when assigned) of GENERAL EMERGENCY b.
Notify STA (PAX 353/396/313) of GENERAL EMERGENCY o
c.
Notify Chem Lab Supervisor (PAX 367/368) of GENERAL EHEEEllG.I.
Direct them to activate IP-25 t
d.
Notify HP Shift Supervisor (PAX 300) of GENERAL EMERGENCY.
Direct them to activate IP-14.
e.
Notify Public Safety Supervisor (PAX 273) of GENERAL EMERGENCY.
Direct them to activate IP-11 and IP-7.
2.5 Shift Engineer's Clerk will:
a.
Initiate IP-6 2.6 Shift Engineer will notify NRC of GENERAL EMERGENCY by red phone. Give a brief description. Maintain an open line until released by NRC.
Note: NRC will pr;bably send a response team to the site.
27 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.
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BFN, IP-5 APR 071983 2.8 At least every two hours, or more frecuentiv if conditions warrant-the Shift Engineer / Site Emergency Director will reevaluate the event using IP-1.
If the situation no longer exists or should be downgraded, a.
inform all personnel previously notified.
2.9 Refer to Table 1 for a quick estimate of mavimum offsite dose for a stack release. and Table 2 for a quick estimate of the site boundary dose for buildina release.
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.APR 071983 PERSONNEL ACCOUNTABTLITY AND EVACUATION 1.0 PURPOSE 1.1 Provide for the accounting and orderly evacuation of plant personnel and visitors from an area, building, or site. Reentry guidelines are also described.
2.0 INSTRUCTIONS 2.1 It is the responsibility of the Site Emergency Director to make the decision concerning the necessity for area, building, and site evacuation.
2.2 AREA AND BUILDING EVACUATION (NOTIFICATION BY PUBLIC ADDRESS) 2.2.1 All personnel evacuate to a safe area and remain there for further instructions.
Caution:
Individuals in a "C" zone a.
Remove outer protective clothing b.
Walk at outer edge of normal passage route, c.
Avoid contact with others, d.
Request HP surveillance as soon as possible.
2.2.2 Senior individual report accountability to Site Emergency Director.
t 2.3 TOTAL SITE EVACUATION (NOTIFICATION BY PUBLIC ADDRESS AND SIREN) 2.3.1 Site Emersency Groups a.
TSC personnel previously notified by IP-6 report to TSC.
b.
OSC personnel previously notified by IP-7 report to OSC.
c.
TSC/OSC report accountability'to Site Emergency Director.
d.
Site E=ergency Director notify DNPEC Director of evacuation.
2.3.2 Operations Personnel a.
Secure any operations outside control rocm.
b.
Report to assigned control room.
c.
ASE will account for his personnel and report to Shift Engineer, d.
Shift Engineer report acccuntability to Site Emergency Directer.
233 HP Technicians a.
Proceed to HP lab (if habitable) b.
If HP lab uninhabitable, proceed to backup HP center in unit 3 control bay mechanical equipment roem (El 617).
c.
Report accountability to Site Emergency Directer.
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APR 071983 234 Public Safety Service Mcn assigned post until directed otherwise by PSS Shif t Supervisor.
a.
PSS Shift Supervisor assign officers to strategic locations as needed.
b.
PSS Shif t Supervisor notify construction (see Attachment 1).
c.
Perform check for visitors outside the protected area (see Section 2.5) d.
PSS Shift Supervisor make accountability check of PSS personnel.
e.
2.3 5 Radiochemical Laboratory Analysts Proceed to lab (if habitable).
a.
If lab uninhabital proceed to backup at intake in installed wire cage.
b.
Report accountabililty to Site Emergency Director.
c.
236 Nurse Proceed to health station (if habitable).
a.
b.
If uninhabitable, proceed to Shift Engineer's office..
Report accountability to Site Emergency Director.
c.
?.3 7 All Other Personnel Plant personnel evacuate to west parking lot.
a.
Field Services personnel evacuate to east parking lot.
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b.
Construction personnel in protected area evacuate to east or west lot and 1
c.
report to Public Safety, d.
Construction personnel not in protected area - See IP-9 If either parking lot is uninhabitable, personnel assigned Caution:
to that area will exit through their normal catehouse but then be directed by PSS to proceed to corosite earkine lot.
Caution!
Individuals in "C" zone Remove outer protective clothing.
a.
b.
Walk at outer edge of normal passage route.
c.
Avoid contact with others.
d.
Request HP surveillance as soon as possible.
2.4 Accountability Assembled personnel's names and badge numbers from control rooms, TSC, OSC, a.
health physics, radiochemical laboratory, public safety, and health station are forwarded to the Site Emergency Director.
Each foreman / supervisor will account for personnel assigned to them and b.
report any missing to PSS.
Visitor's escorts will account for their visitors and report to Public c.
Safety.
badged personnel will be accounted for by Public Safety.
Offsite d.
Construction Services personnel will be accounted fer by Public Safety.
e.
The portals will provide a listing of badge numbers and names of all f.
present in-plant personnel to Public Safety. This list, along with those from steps a thru e, will be sent to PSS Supervisor in TSC.
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'Page 3 of 3 BFN - IPD BFN IP-8 AP 071983 g3 With the listing from steps a - e, the Public Safety Service Supervisor in the TSC will subtract these from step f.
h.
The names and badge number of absent persons are returned to Public Safety to determine where persons may be.
- i. If required, Public Safety Service forms search parties, each having at least one HP technician.
2.5 Visitors Outside Plant Protected Area a.
PSS will dispatch officer (s) to search areas on TVA property outside the Protected Area Fence.
b.
All personnel located will be brought to west parking lot.
c.
P55 will obtain name, address, and phone number and forward to Site Emergency Director.
d.
Personnel will be surveyed and released as described i,n 2.6, below.
Note: Affected areas of Wheeler Lake will be evacuated by the Alabama Division of Water Safety, as defined in that section of the State Plan, through the CECC Emergency Director.
2.6 Release from Site a.
Site Emergency Director will determine which individuals will remain (additional TSC/OSC, engineering, craft, etc. personnel).
b.
HP sets up checkpoints coincident with PSS access control pointa.
c.
Personnel will be directed by PSS to proceed to their residences, to tune in TV/ radio for further information, and keep phone lines clear for possible recall.
d.
HP will survey all personnel and vehicles at the checkpoints before release.
Contaminated individuals will be evacuated to the Power Service Shops utility building at Wilson Hydro Plant. Site Emergency Director will
-notify DNPEC Director of any such individuals.
2.7 PLANT REENTRY l
As aron as possible after personnel evacuation has been accomplished, procedures will be initiated to restore the plant to nor=al conditions. Cc=plete radiation and contamination surveys will be made prior to plant personnel ( other than those required for emergency duty) reentering the evacuated areas.
The Site Emergency Director will authorize general personnel reentry only when he is assured that the emergency has been controlled and reentry is safe.
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1 Page 1 of 1 BFN - IPD BFN, IP-8 f-APR 071983 ATTACHMENT 1 M
M TIME CONTACTED Dave Montgomery 267/378 729-6204 or Preston Scott 321/267/378 729-6204 or 0
Bud Corder 321/267/378 729-6204 Give the following information:
"We have an emergency condition existing at the plant necessitating a site evacuation. Please assemble at the construction gatehouse, account for your personnel, and notify plant public safety when completed."
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sPage 1 of 2 BFll-IPD R
83 SECURITY AND ACCESS CONTROL 1.0 PURPOSE 1.1 Provide for implementation of a predetermined security and access control plan for an ALERT, SITE AREA EMERGENCY, or GENER AL EMERGENCY.
2.0 INSTRUCTIONS 2.1 PSS Shift Supervisor will, when notified by Shift Engineer or Shift Engineers Clerk:
Initials ling.
a.
Report immediately to CAS, make necessary assignments to PSS personnel, maintain communications with all PSS personnel.
b.
If an ALERT, dispatch officers to entrance of control rocms.
Officers will deny access except to those who:
- 1) Have solid red bar at bottom of picture badge
- 2) Have been authorized by Shift Engineer / Site Energency Director c.
If a SITE AREA EMERGENCY or GENERAL EMERGENCY, or at request of Site Emergency Director a) Dispatch officers as described in b, above b) Close all site access control points which control personnel entering or leaving the 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 by Site E=ergency Director, (2) accounted for by PSS, and (3) monitored by HP will be allowed to allowed to leave the site.
c) Dispatch officers to secure all exterior doors into the plant and all gates on the reservaition. d) Establish contact with POS Supervisor in TSC upon arrival.
2.2 If the evacuation alarm sounds, assign available officers to access portals, east and west. These officers will survey the empicyees badges, accountability card racks, and visitor log. Refer to IP-8, Sections 2 3.4, 2.4, 2.5, and 2.6 for further instructions.
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Page 2 of 2 DTN-IPD BFN, IP-11 7
APR 071983 0
23 Periodic radio or phone checks shall be cade to the PSS shift supervisor or his designee, by all officers assigned to a post.
o 2.4 At the end of the emergency, PSS will be relieved from the emergency duties by the Site Ezergency 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 during an emergency.
f.-.,
Person's picture with qWl red background F
l Red Bar
' 1U n t.. Gill!
U-@R.!
, q. ;,
ur h Below is an exe=ple of I.D. card authorized to gain access ensite during emergencies. They will be required to be shown to Public Safety officers at predetermined locations. (Example: County read, access road to plant, etc.)
This is to certify that
,d f
Terry L. Chinn 1 g
}* e.
is an employee cf the Tennessee Vattey Authority at r4, ~f the Browns Ferry Nuclear Plant eRevision Efmpiovee Signature" H. t.. Abercrombe G
Ptant Supermtencent
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'Page 1 of 5 BFN - IPD BFN, IP-14 APR 071983 HFAf.TH PHYSICS PROCEDURES 1.0 PURPOSE This procedure outlines the actions to be followed by Health Physics personnel during a radiological emergency. Natural phenomena, security threats, or other events not involving radiation could be the cause for the emergency. This procedure describes those HP actions required during an emergency involving radiological problems.
EQIEL Shift Engineer's clerk will initiate IP-14 by calling the Health Physics Shift Supervisor.
2.0 NOTIFICATION OF UNUSUAL EVENT 2.1 No offsite radiological problems are postulated during a NOTIFICATION OF UNUSUAL EVENT. This situation should not have any major impact on the health physics unit.
2.2 Although Health Physics will not automatically be called, should assistance be needed Health Physics will follow standard practices and procedures during any response work.
3.0 JUJJu; s
A limited release is possible during an ALERT situation. Significant loss of fuel cladding, small line breaks, fuel handling accidents, or high radiation levels are examples.
INITT A t3 s.
3.1 All HP technicians report to the HP lab.
32 HP will take 1 ion chamber survey instrument to the TSC and to OSC.
?.3 HP personnel will periodically survey the TSC and OSC.
34 A HP technician will accompany any personnel dispatched into areas of potential hazard.
35 An ALERT may require the evacuation of a certain plant area and/or building. HP will post these areas and have public safety restrict all unauthorized access.
3.6 Health Physics personnel will assist in the development of all recovery plans as necessary. Reco:cendations will be =ade to keep exposure as low as reasonably achievable and to recommend and approve any cleanup activities.
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'Page 2 of 5 BFN - IPD BFN, IP-14 APR 071983 4.0 SITE AREA EMERGENCY A SITE AREA EMERGENCY may require extensive HP response. A LOCA or major fuel handling accident are examples.
INITIALS 43 1 HP technicians report to the lab.
4.2 HP will take 1 ion chamber survey instrument to the TSC and to the OSC.
4.3 Health Physics personnel will periodically survey the TSC and OSC.
4.4 A health physics technician will accompany any personnel dispatched into areas of potential hazard.
4.5 Initial offsite enviromental assessment will be conducted perHPTSIL 20.
Report findings to the Site Emergency Director.
4.6 Dispatch HP Technician to the site access control point established by PSS personnel. Survey vehicles and personnel leaving tne, site using RM-14 friskers and smear techniques.
4.7 If requested by Site Emergency Director, perform site boundary survey, using the emergency van. Equipment listed in Attachment 1 should be transported to the van.
When instructed to do so, travel to the site boundary in the a.
down wind direction and measure the dose rate with an ionization chamber or similar adrvey instrument. If possible, air sampling should also be performed at the same time.
b.
Precautions must be taken to prevent overexposure if there are high concentrations of radioactive particulates or radioiodine being released.
c.
Record all survey results. All findings shall be reported to l
the TSC. If results indicate offsite contamination, the survey may need to be extended. Obtain further instructions and perform required surveillance.
d.
Arrangements can be made for manpower support and offsite surveys from Muscle Shoals I
4.8 If a site evacuation is ordered, see Section 6.0.
4.9 If HP lab must be evacuated, see Section 7 0.
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' Pag) 3 of 5 BFN - IPD BFN, IP-14 APR 071983 r
5.0 GENERAL EMERGENCY During a GENERAL EMERGENCY, there will probably be radiation releases to the environment requiring health physics response.
INITIALS 5.1 HP technicians report to lab.
5.2 HP will take 1 ion chamber survey instrument to the TSC and CSC.
53 Hcalth Physics personnel will periodically survey the TSC and OSC.
5.4 A health physics technician will accompany any personnel dispatched into areas of potential hazard.
5.5 Initial offsite enviremental assessment will be conducted per HPTSIL 20.
Report findings to the Site Emergency Director.
5.6 Dispatch a HP Technician to the site access control point established by PSS personnel. Survey vehicles and personnel leaving the site using RM-14 friskers and smear techniques.
57 If requested by Site Emergency Director, perform site boundary survey, using tne emergency van. Equipment listed in Attachment 1 should be transported to the van.
a.
When instructed to do so, travel to the site boundary in the down wind direction and measure the dose rate with an ionization chamber or similar survey instrument. If possible, air sampling should also be performed at the same time.
1 b.
Precautions must be taken to prevent overexposure if there are high concentrations of radioactive particulates or radiodine being released.
c.
Record all survey results. All findings shall be reported to the TSC. If results indicate offiste contamination, the survey may need to be extended. Obtain further instructions and perform required surveillance.
d.
Arrangements can be made for manpower support and equipment for offsite surveys from Huscle Shoals.
5.8 If a site evacuation is ordered, see Section 6.0.
5.9 If HP lab must be evacuated, see Section 7.0 6.0 SITE EVACUATION 6.1 HP technicians proceed to lab, if habitable. It uninhabitable, see Section 7 0.
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1 INITIALS 6.2 Report accountability to Site Emergency Director.
6.3 If any plant personnel are missing, PSS will form search parties, each having at least one HP technician.
6.4 HP will survey personnel and vehicles leat,ing the site at the PSS
^
access control point. Contaminated individuals will be evacuated to the Power Service Shops utility building at Wilson Hydro Plant. Notify Site Emerge.cy Director of any such individuals.
70 HP LAB UNINHABITABLE 7.1 HP technicians will secure equipment listed in Attachment 2, and proceed with equipment to mechanical equipment room, control bay, unit 3, elevation 617.
7.2 Report to Site Emergency Director.
i 8.0 TSSUANCE OF POTAMMIUM IODINE (ET) 8.1 If a responsible health physicist has reason to believe that a person's projected cumulative dose to the thyroid from inhalation 4
of radioactive iodine might exceed 10 rems (See Attachment 3) 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 insert 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 in the medical station to supply any personnel exposed to radioactive iodine. It is supplied in bottles which contain a full 10-day dose regime. Follow dosage 2
scheduled as outlined on the package insert accompanying each bottle of KI.
l 8.2 The potassium iodine is stored in 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.
8.3 A copy of the Food and Drug Administration approved package insert shall accompany each bottle of KI issued. Dosage scheduled and other pertinent infor=ation are outlined on the package and should be fellowed closely (Attachment 4).
8.4 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 physicict in a timely manner.
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BFN, IP-14 APR 071983 9.0 USE OF NRC ORANGE PHONE (HEALTH PHYSICS NETWORK) 9.1 This phone is located in the HP plant laboratory and the NRC Resident Inspector's office.
92 The phone is to be used by TVA personnel suibt 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 verify the 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.
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"h"ddi-583; 4.2.7 Rezero all emergency dosimeters to assure preper operation.
4.3 completion of Inventory Forms 4.3.1 If the particular items are present and in sufficient quantities and, when applicable, in good working condition, then check the YES column.
4.3 3 Under the remarks column, explain the corrective actions taken.
e RQIE All comments in the remarks column should be detailed enough to leave no doubt as to the actions taken. Cocments to the effect
" batteries missing" will not suffice. A simple check in the NO column will represent that a deficiency exists. Such comments do not allow a person to determine what, if any, action has been taken and will only lead to confusion. Comments should read as follcws: " Batteries replaced on March 25, 1980."
All deficiences must be corrected as soon as possible. If circumstances do not allow deficiences to be corrected, then the Shift Engineer shall be notified, 4.4 Upon activationof the Technical Support Center and Operations Support Cente'r, the equipment listed below will be carried to each center by the Health Physics Section.
1 Ion chamber survey instrument.
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e TENNESSEE VALLEY AUT110RITY BROWNS FERRY NUCLEAR PL\\NT RADIOLOGICAL EMERGENCY PLiN t
OPERATION OF THE EMERCENCY DATA INFORMATION SYSTDI BFN, IP-19 l
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- APR 07 583 General Revision M
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- Page 1 of 9 BFN-IP BFN, IP-19 fd)R 071983 OPERATION OF THE EMERGENCY DATA INFORMATION SYSTEM 1.0 EQUIPMENT AND LOCATION A CRT and a lineprinter are provided in the Technical Support Center for sending and receiving messages between emergency centers and for display of meteorological data.
2.0 INSTRUCTIONS Turn on power to CRT and lineprinter. The CRT switch is located at right rear 2.1 of console - Lineprinter switch is located approximately 10-inches BELOW (underneath) the keyboard on the left side of the machine and is colored white.
2.2 Enter on CRT: HELLO BFTSC. Return. The screen will respond - PASSWORD. Enter BFNP. Return. (The password will not be shown on the screen).
2.3 When logged in, the following menu will be shown:
FUNCTIOM KEY ACTION OP KEY f1 Exit the current module f2 Program Stop Display meteorological data f3 f4 List, edit, and review messages Release a message to another site f5 f6 Create a new message f8 Edit / display the next page f9 Edit / display the previous page Edit /save changes made to the current page f10 f11 Edit /re, fresh the current page If the program is not used, the computer will automatically log out af ter approximately 2 ninutes.
To select a menu action (function), press the corresponding function (F) key at 2.4 the top of the keyboard. (f7 key is not operable at this time). You do not have to press the return key after pressing a function key.
2.5 Description of menu functions:
i function key = ft, EXIT.
2.5.1 Exit the current module, The f1 key is used to exit the menu function or module that the program is presently in.
It will usually return the program menu on the screen.
2.5.2 Program stop, function key = f2, HALT.
Use this f2 key to log out of the program.
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- Page 2 of 9 BFN - IPD g-BFN, IP-19 JWPR 071983 2.5 3 Display meteorological data, function key F3, MET. Screen will respond - WHICH SITE (1-BFNP, 2 = SNP, 3 = WBNP). Select the site desired and return. Screen will respond - ENTER PREVIOUS HOURS (0-168). Enter the number of the hours for which you desire to see data, return. Screen will respond - DATA TO RECEIVE (1 = HOURLY ONLY, 2 = 15 MINUTE ONLY, 3 = ALL)
Select the time interval you desire, return. The line printer will then print meteorological data. Print out will appear similar to the following sample =
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT LATITUDE LONGTITUDE ELEVATION (MSL) DATE TIME 34,70083 87,108c6 5 96.
16-FEB-83 07:50:07 WIND SENS UIL DELTAT U-L DELTAT U-I DELTAT I-L TA TO PCP 92.6 45.7 10.4 89.6 10.0 89.6 45 3 45.3 10.0 10.0 10.2 1.0 LATITUDE AND LONGITUDE ARE GIVEN FOR THE METER 0 LOGICAL TOWER SENSOR HEIGHTS ARE HEIGHTS ABOVE TOWER BASE YYJJJHHMM WDU WDI WDL WSL STUSTISTL DTUL DTUI DTIL TAL TDL PCP 83 47 100 209 315. 18. 0.8 0 9 0 7 15. 7. 6.
3 9F 2.6F 5.4G 4.1 -2.2 0.0 WPU= 34. WPI= 28. WPL= 50. SLR= 0.00 TU=
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The codes for the above data are:
YY
= year JJJ
=julian date HH
= hour MM
= minute WDU
= wind direction (degrees) upper level WDI
= wind direction (degrees) intermediate level WDL
= wind direction (degrees) lower level WSU
= wind speed (m/s) upper level WSI
= wind speed (m/s) intermediate level WSL
= wind speed (m/s) lower level STU
= sigma theta (degrees) upper level STI
= sigma theta (degrees) intermediate level STL
= sigma theta (degrees) lower level l
DTUL
= temperature difference (C/100 m) upper-lower l
DTUI
= temperature difference (C/100 m) upper-intermediate i
TAL
= ambient temperature (C) lower level TDL
= dew point temperature (C) lower level PCP
= precipitation total (mm) ground level S
= stability class The screen will respond - PRESS CARRIAGE RETURN FOR MORE INFORMATICN, (f1) TO l
EXIT.
The return key will present which SITE (1 BFNP, 2=SNP, 3=WBNP) on the screen.
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- Page 3 of 9 BENP - IPD The following data points are only available on the hourly transmission:
NOTE essoALL HOURLY READINGS ARE HOURLY LVERAGESeses STU STI STL TDL PCP The following points arc included in the hourly transmission and will be on the next line with the heading preceeding each value.
UPU = wind direction persistence upper (%)
WPI = wind direction persistence intermediate (%)
WFL swind direction persistence lower (%)
SLR = solar radiaion (sm-cal /cm2--min)
= temperature (C) upper-level TI
= temperature (C) intermediate level If a particular data point is not available the display will include asterisks (eesse; rop the value, if an entire data record was not recieved the display will print DATA NOT RECEIVED.
Wind directions, wind speeds, differential temperatures, and precipitation are checked
' against set criteria to determine whether or not they should be considered questionable.
If a data point has failed one test it will appear in the display with question marks
(????) directly below it.
If the data point has failed two or more tests it will appear with plus signs (++++) directly below it.
If the stability class does not appear to agree with the temperature differeace displayed, this is due to round-off. This cordition indicates that the temperature difference is on the border between the two classes.
2.5.4 List, Edit, and Review =essages, function key F4, LIST. Screen will respond -
(if there are inbound messages which have not been reviewed)
" Number of messages waiting =
ne eeEnter 1 to review a waiting message
- Enter 2 to review a particular message 8'
Press Function Key (F1) to Exit this module
- Enter the action code **
Enter 1, return - will display a message.
When incoming messages are being reviewed, the (F1) key will terminate the edit message and begin the edit module for the next inccming message. When the last message has been reviewed, the (F1) key will cause the system to return to the function select module.
( All incoming messages must be viewed before key F1 will return the menu).
- /
l i
i
- Page 4 of 9 BFNP - IPD BFN, IP-19 APR 071983 If a 2 is entered, the screem will respond seENTER 1 FOR INBOUND MESSAGES, 2 FOR OUTBOUND MESSAGESee When 1 or 2, return, are entered, a listing of the messages will be shown. The screen heading is:
SFQ. NO./ TITLE MESSAGE DEST.
DATE If a messare is to be viewed - remember its Sec. No.
Pressing return shows the remainder of the list. When the last of the list is shown, continued pressing of return shows the last page of the list.
The Seq. No. may be enter ed to view a message.
Messages may be viewed with purpose of updating cr " refreshing" the original message. When the message is called up, the screen gives the options of sePRESS (F1) to EXIT, (F10) to SAVE PAGE, (F11) to REFRESH PAGE
If a page is " REFRESHED" the (F10) must be pressed to save or record the changes made. When (F10) is pressed, the rewritten message will be shown. If you are going to transmit the message - remember the Seq. No.
2.5.5 Release a Message to Another Site, function Key FS, REC. Screen will respond -
" ENTER 1 to RELEASE A MESSAGE CREATED AT THIS SITEse
- ENTER 2 to RELEASE A MESSAGE RECEIVED AT THIS SITE **
s Enter 1, return - screen will respond ' ENTER THE MESSAGE SEQUENCE NUMBER **
When the message sequence number is entered, the screen will respond -
1 "DNPEC" 2 " MSEC - CECC COMMUNICATOR
3 "KEC" l
4 "BFNP LRC" 5
"'ME*"
(F1) seENTER THE ACTION CODE **
l Select the number key for the destination desired, return. The message will then be automatically transmitted.
2.5.6 Create a New Message, Function Key F6, CRE IMPORTANT: Do not use cursor movement keys when in CREATE. Their use erases the message you type in.
The message text should be entered in normal keyboard fashion. Each line must be ter=inated by a carriage return. Corrections can be made to the current line by using the delete key (DEL) to move the cursor backwards. The backspace key and the cursor positioned keys can NOT be used to make corrections while the system is in the create module. Corrections can not be made to previous lines while the system is in the create module.
When the message text has filled the screen, the system will clear the screen and the user can continue to enter the message text on the next page. There is a maximu= of 5 pages for the standard cessage form.
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- Page 5 of 9
/.
BFNP -IPD IP-19 BFN, 071983 APR This will A message can be terminated at any time by pressing the (F1) key.
cause the system to exit the create module and enter the edit #sdule where changes and modifications can t.e made to the message before sending it, ocessesseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeesssene esTITLEse TEST FORM 2 ocPAGE NUMBER 1 16-FEB-83 10:13:41 CSTee SEQ. NO. 19 INBOUND DATE:
TIME:
INITIALS:
CALL VERIFIED:
SITE EMERGENCY DIRECTOR:
AFFECTED PLANT:
CLASSIFICATION:
TIME OF INCIDENT:
BRIEF DESCRIPTION (5 LINES):
PLANT CONDITION:
UNUSUAL RELEASE OF RADI0 ACTIVITY 7 e
.'IND DIRECTION:
' ~ WIND SPEED:
RECOMMENDED PROTECTIVE ACTION:
C8PAGE NUMBER 2 16 -FEB-83 10:13:41, CSTee SEO. NO. 19 INBOUND
.STOP.
casenessensenesseessoassenesesseesseessesseessessessessessenessessessee Number 3, BFNP emergency parameter list is shown below:
(Sample date, time and Seq. No.)
i 1
9 L
- Page 6 of 9 BFNP - IPD
""hR5/1983
.. TITLE..
BFNP EMERGENCY PARAMETER LIST
..PAGE NUMBER 1 16-FEB-83 08:52:42 CST **
SEQ. NO.
3 INBOUND PARAMETER INSTR. NO.
PANEL READING REACTOR LEVEL LI 3-53 (INCHES) 9-5 REACTOR LEVEL LI 3-62 (INCHES) 9-3 REACTOR LEVEL LI 3-46 A (INCHES) 9-5 REACTOR PRESSURE PI 3-54 (PSIA) 9-5 REACTOR COLLANT TEMPERATURE TR 68-2 LOOP A (DEG F) 9-4 LOOP B (DEG F) 9-4 DRYWELL PRESSURE PI 64-50A (PSIA) 9-3 PI 64-67B (PSIA) 9-3 DRYWELL TEMPERATURE TR 64-52 (DEG F) 9-3 DRYWELL HYDRGN CONCENTRATION H2R 76-37 OR 39 9-54,55 DRYWELL OIYGEN CONCENTRATION 02R 76-41 OR 43 9-54,55 TORUS TEMPERATURE TR 64-52 (EG F) 9-3 TORUS HYDROGEN CCNCENTRATION H2 76-37 OR 39 9-54,55 TORUS OIYGEN CONCENTRATION 02R 76-41 OR 43 9-54.55 TORUS WATERLEVEL LI 64-54A (INCHES) 9-3 EQUIPMENT DRAIN SUMP FLOW FR 77-16 (GPM) 9-4 FLOOR DRAIN SUMP FLOW,
FR 77-6 (GPM) 9-4 HPCI PRESSURE PI 73-31A (PSIG) 9-3 HPCI FLOW FI 73-33 (GPM) 9-3
- PAGE NUMBER 2 16-FEB-83 08:52:42 CST **
SEQ. NO.
3 INBOUND RCIC PRESSURE PI 71-35A (PSIG) 9-3 RCIC FLOW FI 71-36A (GPM) 9-3 RHR LOOP I PRESSURE PI 74-51 (PSIG) 9-3 RHR LOOP I FLOW FI 74-50 (GPM) 9-3 RHR LOOP II PRESSURE PI 74-65 (PSIG) 9-3 RHR LOOP II FLOW FI 74-64 (GPM) 9-3 CORE SPRAY LOOP I PRESSURE PI 75-20 (PSIG) 9-3 CORE SPRAY LOOP I FLOW FI 75-21 (GPM) 9-3 CORE SPRAY LOOP II PRESSURE PI 75-48 (PSIG) 9-3 CORE SPRAY LOOP II FLOW FI 75-49 (GPM) 9-3 EECW FLOW FI 67-3 (GPM) 9-20 FI 67-6 (GPM) 9-20 FI 67-9 (GPM) 9-20 l
FI 67-12 (GPM) 9-20 i
EECW HEADER PRESSURE PI 67-15 (PSIG) 9-20 PI 67-16 (PSIG) 9-20 PI 67-19 (PSIG) 9-20 PI 67-20 (PSIG) 9-20 PI 67-23 (PSIG) 9-20 PI 67-24 (PSIG) 9-20 I
y
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- Page 7 of 9 BFNP - IPD BFN, IP-19
. APR 071983 c:PAGE NUMBER 3 16-FEB-83 08:52:42 CST **
SEQ. NO.
3 INBOUND RHRSW PRESSURE PI 23-4 (PSIG) 9-3 PI 23-11 (PSIG) 9-3 PI 23-18 (PSIG) 9-3 PI 23-26 (PSIG) 9-3 CRD PRESSURE PI 85-13A (PSIG) 9-3 CRD FLOW FI 85-11A (GPM) 9-5 SBGTS FLOW FI 65-50 (SCFMX1000)9-25 FI 65-71 (SCFMX1000)9-25 SBGTS DELTA P PDI 65-5 (IN. WATER)9-25 PDI 65-27(IN. WATER)9-25 STACK FLOW FI 90-271 (SCFM) 1-9-57 DRYWELL RADIATION RM 90-272A (R/HR) 9-54 RM 90-273A (R/HR) 9-55 TORUS RADIATION RM 90-272B (R/HR) 9-54 RM 90-273B (R/HR) 9-55 STACK RADIATION RE 90-147 (CPS) 25-39 RE 90-148 (CPS) 25-39 RHRSW RADIATION (A&C)RM 90-133B(CPS)9-10 (B&D)RM 90-134B(CPS)9-10 esseeeeeeeeeeeeeeeeeeeeeeeeeeeeessenessessessesseessensenessesseeeeeeeeeeeeeeeeeeee When the message or data' entry is completed, pressing the F1 key will provide a screen response of the destination menu so the message can be transmitted.
2.5.7 Display Rad Data or Plant Data, Function Key F7.
This function is not presently used.
~~
2.5.8 Edit Function.
2.5.8.1 Edit /--Display the Next Page, function key F8, NEXT 2.5.8.2 Edit /--Display the Previous Page, function key F9, LAST 2 5.8.3 Edit /--Save Changes Made To The Current Page, Function Key F10, SAVE 2.5.8.4 Edit /--Refresh the Current Page, function key F11, REF.
When either the f6 or f4 menu function has been selected and Lessages are being edited these keys may be used for the following:
GM I
- Page 8 of 9 BFNP -IPD BFN, IP-19
'APR 071983 e
(F8) KEY This key is used to advance to the next page. When this key is used, the current page of the message will be removed from the screen and the next page will be printed on the screen. If the current page is the last page of the message, that page will be reprinted when the (F8) key is pressed.
(F9) KEY This key is used to return to the previous page. When this key is used, the current page of the message will be removed from the screen and the previous page will be printed on the screen. If the current page is the first page of the mesaage, that page will be reprinted when the (F9) key is pressed.
(F10) KEY This key is used to save changes made to the current page. This key must be used whenever changes are made to a page of the message. If changes are made the (F10)
KEY must be pressed before pressing any other function keys.
If thin is not done.
the chances made vill be lost.
(F11) KEY This key is used to refresh the current page. If undesirable changes have been
~
made to a page of the message, this key can be used to return the original message text.
2.5.9 MAKING CHANGES TO THE TEXT:
Changes can be made to the message text by overtyping the incorrect or undesired portion, and by using special edit keys available on the Televideo terminal. These keys and their funct, ions are listed below.
CURSOR POSITION KEYS These keys are used to move the cursor to the desired location. There are 4 cursor positioning keys at the lower right of the keyboard. Each key has an arrow to indicate the direction of cursor movement.
CHARACTER DELETE KEY 1
This key deletes the character at the current cursor pcsitien and shifts all l
remaining charactern in the line to the lef t one space.
CHARACTER INSERT KEY This key inserts a blank space at the current cursor position by shif ting all remaining characters in the line to the right one space.
LINE ERASE KEY j
This key will remove all characters in the line frcm the current position of l
the cursor to the end of the line.
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i 1
- Pags 9 of 9 BFN - IPD BFN, IP-19 APR 071983 2.6 MAINTENANCE Call the following BFN personnel for repairs and trouble shooting:
NAME PAX DIM HOME I
1.
Glen T. Gibson 382 205-766-6528 2.
Russell McNutt 264/109 879 205-232-2359 s
3.
Lawrence (Larry) Johnson 264/382 856 205-233-0417 Call the fo?. lowing DNP, Computer Engineering Section, 1300 CST 2-C on operating problems:
NAME D_AY SHIFT AFTER HOURS / WEEKENDS 1.
David Woodard 751-4811 615-622-4490 or 4812 2.
Chip Orman 751-4813 615-875-9543 3.
Steve Oaks 751-4804 615-344-7032 s
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f-ePage 1 of 3 BFN-IPD BFN, IP-20 TECHNICAL SUPPORT CENTER (TSC)
OPERATION 1.0 PURPOSE To establish the TSC organization and provide for TSC operation after it is manned.
2.0 INSTRUCTIONS 2.1 INITIAL ACTIVATION (Performed by Shif t Engineer and/or first individuals reporting to TSC - Confirmed by REP Communicator)
Tnitinia JJbut a.
Shift engineer (designated by schedule as Site Emergency Director) relocate to TSC, if possible.
b.
Activate TSC phones (See Attachment C).
c.
Establish communications with DNPEC.
d.
Establish log of events /co=munications.
s e.
Transfer names of TSC personnel from IP-6 data sheets to REP Organization Board.
f.
Establish communications with NRC via Red Phone (if required),
g.
Move desks and phones to hallway for recretary, Information Officer, and PSS Supervisor.
2.2 CCMPLETE ACTIVATICN (After majority of TSC personnel have arrived -
l Confirmed by REP Communicator).
a.
RCP Communicator assure TSC positions are filled.
b.
REP Communicator begin maintaining plant status board.
j c.
Site Emergency Director relieve Shift Engineer. Ot:ain log of events.
j d.
Secretary take over leg of events /ccm=unications.
l
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e.
REP Communicatcr establish communication with DNPEC Communicator.
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Red)sion
ePage 2 of 3 BFN-IPD BFN, IP-20 APR07TsB3 Yntt<m1= Tina f.
Technical Assessment Manager direct TSC Communicator to i
begin completing IP-20 data sheets (See Attachment A) every 1/2-hour.
Technical Assessment Manager establish communications g.
with TSC Communicator in control room using portable phone. (Unit 1-6,28, Unit 2 - 629, Unit 3 - 630) h.
Maintenance Engineers establish communications with OSC.
Designate individual in charge if Maintenance Unit Supervisor not available. Maintain log of activities.
PAX Numbers:
Mechanical 301/310/308/114/102/305/305/306 riactrinal 307/145/407 Tnntrn=.ntation 375/376/425/426/359/184/187 1.
Secretary activate Emergency Data Information system (See IP-19).
- j. Secretary begin operation of telefax machine (see Attachment F).
k.
NRC Communicator establish communications with NRC (if required).
1.
NRC Communicator begin maintaining area maps and off-site radiation status board.
Health Physicist begin maintaining in-plant radiation m.
status boards.
Radiochemical Engineer begin providing information to n.
KEC for projected dose calculations, Health physicist begin providing release information and o.
any plant field team data to MSEC for dose calculations.
Secretary (in hall) begin accountability of TSC p.
j.
personnel.
q.
Site Emergency Director will reevaluate emergency conditions in accordance with IP-1 every two hours or more often if conditions warrant.
2.3 OTHER I'1FOPMATION 1
Organization chart is show on Figure 1.
l a.
b.
Physical layout of TSC is shown on Figure 2.
Lunchroom (Swamp) is available for breaks and extra work 1_Y_
c.
spase.
~-
Revision
- Page 3 of 3 BFN-IPD BFN, IP-20 d.
Reference books for TSC use are listed on t c men D.
e.
Complete list of TSC Dimension Numbers - See Attachment B.
f.
See IP-23 for communication list.
g.
List of DNPEC/CECC Numbers - See Attachment E.
h.
Refer to Attachment K for Emergency Information Flow Diagram.
1.
River flows and/or predicted flows - In Shif t Engineer's Office.
J.
Complete list of TSC duties for each individual - See Attachment G.
2.4 CONTINQENCIES a.
Long-term operation - See IP-22.
b.
Loss of off-site communication by phons. Use PSO Radio - See Attachment H.
s c.
NRC order - The NRC role onsite is to observe, advise, and concur with licensee decisions and actions. If a situation arises where the NRC wants an action taken regarding plant operation that TVA does not agree with, the 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.
d.
Using HP VHF radio - See Attachment I.
e.
Evacuation - Relocate TSC to second level of Office Building. (See Attachment J) f.
Activity control - Activity control (Maintenance, etc. )
will remain as specified in plant instructions, unless revised by PORC and Plant Supt./ Asst Supt., or as modified by NRC order.
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r Page 1 of 1 BFN - IPD BFN, IP-20 Attachment B APR 071983 TECHNICAL SUPPORT CENTER - DIMENSION PHONE NUMBERS r
PHONE TITLE 771 Site Emergency Director 765 4
Operations Manager 769 REP Communicator 896
- NRC Communicator 761 Technical Assessment Manager 766 Maintenance Manager 767 Health Physicist 763 Health Physicist 768 Radiochemical Engineer 773 Hechanical Engineer 772 Electrical Engineer 774 I & C Engineer 775 Reactor Engineer 762 Systems & Test Engineer 764 Operations Specialist 770 Secretary 776 PSO Engineer 777 Secretary 855 NRC Site Director of Operations 851 NRC 852 NRC 853
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NRC 854 NRC 848 Secretary (Hallway) 849 PSS Supervisor 850 Public Information Officer PAX 493 (1)
Any (1) Rings at Secretary's desk (777 or 770) and can be transferred via dimension to l
any phone in ISC.
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Pzgs 1 of 1 BFN-IPD BFN, IP-20 Attachment C APR 071983 ACTIVATION OF TSC DIMENSION PHCNES
- 1. ' Obtain a telephone handset from supply cabinet in TSC or top right hand drawer of table behind Plant Superintendent's receptior.ist's desk in Office Building.
2.
Plug telephone handset into RIGHT side of console (located in Plant Superintendent's receptionist's area).
3 Press any idle LOOP BUTTON (a button not lit) 4.
Press START BUTTON: Dial tone is heard.
5.
Dial 22 (pause) 6.
Dial 0: Dial tone is heard.
7.
Dial 04: Confirmation tone is heard. (3 beeps) 8.
Press RELEASE BUTTON 9
To check activation, to to TSC, dial 30 or 31 (WATS lines). If dial tone is heard, the phones are activated.
DEACTIVATION OF PHCNES 1.
Repeat steps 1 thru 8 above except in step No. 6, dial 1
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'Page 1 of 1 BFN-IPD
- ~
BFN, IP-20 Attac@ ente 1983 APR CECC AND DNPEC TELEPHONE NUMBERS Extension Station (40 or 50 + Number)
(Note: It dialing on 50, use 50 + 0 + Number, i.e.
50 + O200) 200 Operations Duty Specialist Management Services 203 State Coordinator 205 NRC (DNPEC) 206 Technical Services 207 208 Electrical, Instrument & Controls 209 Field Services 212 Reactor Engineerings Mechanical Engineering 213 214 Plant Communicator 220 CECC Director 228 State Communicator NRC (CECC) 229 Information Office 230, 231, 232, 233, 234, 235, 236
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- Addendum 0 m
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'Page 1 of 1 BFN - IPD BFN, IP-20 Attachment F PANAFAX HV-3000 BASIC OPERATION A.
Initial Checks 1.
Verify the machine is plugged into an electrical outlet.
2.
Verify the power switch on left side of machine is turned "0N".
3.
Verify there is paper in the machine by looking through the paper indicator window on the top of the machine.
B.
To receive documents The Panarax HV-3000 is to receive documents automatically.
Therefore, no special procedures are necessary.
C.
To transmit documents 1.
Make sure the document is face up on the document tray.
2.
Insert the document so that the long axis of the paper is parallel to the long axis of the machine.
3 Adjust the document guides to the width of the document.
4.
Set the resolution button to " Fine" if the document is not clear or if it is hard to read, otherwise set to " Standard."
5.
Press the original button according to the density of the originals.
6.
Pick up the telephone handset and dial the number for the receiving party.
7.
Af ter hearing a " beep" tone press the "0N Lir.e" button.
8.
Check that the XHT lamp is lit and hang up the handset.
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i Addfndum t
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..92 1"
'Page 1 of 3 BFN-IPD BFN, IP-20 Attachment G TSC Organisation Dutie" APR 071983 Site Emereenev Director 1.
Directs activities of site emergency organization.
2.
Consults with DNPEC on important decisions.
Initiates protective actions onsite.
3 4.
Coordinates as necessary emergency actions with onsite NRC.
5.
Initiates long term operation.
Ooerations Mannaer Directs operational activities.
1.
Informs Site Emergency Director of plant status and operational problems.
2.
Performs damage assessment as necessary.
3 Recommends solutions and mitigating action for operational problems.
4.
Technteal Assessment Manneer 1.
Directs onsite radiological monitoring and effluent assessmer.t.
2.
Directs activities of technical assessment team.
3 Projects future plant status based on present plant conditions.
4.
Keeps assessment team informed on plant status.
5.
Provides infonmation, evaluations, and projections to Site Emergency Director.
6.
Coordinates assessment" activities with the DNPEC.
Maintenance Manarer 1.
Directs repairs and corrective actions.
2.
Performe damage assessment.
3.
Directs activities of cporational Suppcrt Center thru his engineers.
l 4.
Coordinates repair activities with the DNPEC.
EEP Communientor Advises site energency director regarding overall radiological e=ergency 1.
plan,. use of procedures, emergency equipment availability, and coordination with DNPEC, KEC, and MSEC.
l Evaluates plant ' status and performs principal communications with DNPEC.
l 2.
3 Maintains plant status board.
4.
Maintains REP Crganization Board.
5.
Confirms TSC set up and operating properly.
Secretaries 1.
Maintains log of events.
2.
Maintains accountability of TSC personnel.
3.
Answers telephones.
I 4.
Distributes IP-20, Attachment A data sheets.
5.
Other duties as assigned by Site Emer6ancy Director.
6.
Operates Panarax l
7 Operates Emergency Data Infonsation System.
T i
- Addendus:
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'Page 2 of 3 BFN - IPD BFN, IP-20 Attachment G APR 071983 TSC Communicator 1.
Provides infonnation from control rooms to Technical Assessment Manager.
2.
Completes IP-20, Attachment A data sheets.
Public Safety Services Sunervisor 1.
Directs activities of PSS personnel.
2.
Controls access to site and control rooms.
3 Reports on accountability in case of evacuation.
Radiochemical Enaineer 1.
Coordinates with MSEC assessment of radioactive effluents.
2.
Directs post-accident sampling activities.
3 Directs activities of the radiochemical laboratory.
4.
Determines impact of incident on radwaste and various effluent treatment systems.
5.
Coordinates assessment of radiological conditions offsite with MSEC.
6.
Provides meteorological and dose projection information.
Mechanical Enaineer 1.
Directs OSC (Mechanical) 2.
Performs damage and repair assessment.
~~
Reactor Freineer 1.
Performs evaluations as directed by Technical Assessment Manager.
Instrument & Controls Fneineer 1.
Directs OSC (Instrumentation) 2.
Performs der:3gi End repair assessment.
ElectricqL R fj;j r, 1.
Dirs3!s fih
'Jectrical) 2.
Perfqfss damage and repair assessment.
3 Maintains Maintenance Assessment Board.
Health Physicist 1.
Directs and/or performs assessment of inplant and onsite radiological conditions.
2.
Directs onsite HP activities.
3 Coordinates additional HP support with MSEC.
4.
Makes recommendations for protective actions for onsite personnel.
(__,,
5.
Coordinates effluent and offsite dose assessment with MSEC.
jL 6.
Maintains inplant radiation status board.
- Addendum:
'Page 3 of 3 BFN - IPD BFN, IP-20 Attachment G APR 071983 PSO Fneineer 1.
Directs OSC (PS0) 2.
Performs damage and repair assessment.
Systems & Test Fnaineer 1.
Performs evaluations as directed by Technical Assessment Manager.
2.
Maintains Technical Assessment Board.
NRC Cn==nnicator 1.
Acts as primary liason with onsite NRC personnel.
2.
Updates NRC personnel of plant status.
3.
Provides information requests from NRC to TSC personnel.
4.
Hans NRC red phone.
5.
Update area maps and off-site board.
Ooerations Soecialist 1.
Provides operational knowledge into status evaluation of all plant systems.
2.
Provides advice regarding technical specifications, system response, safety limits, etc. -
3 Assists in development of recommended solutions to developing problems.
Comeuter 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).
Quality Assurance 1.
Assure QA requirements are met.
2.
Provide relief (short term) to TSC personnel as needed.
Public Information Officer 1.
Coordinates press releases and briefings as required.
I
- Addendum:
0
'Page 1 of 1
~~~
PSO VHF RADIO INSTRUCTIONS BFN - IPD BFN - IP-20 LOCATIOM - REP Communicator's Desk in TSC Attachmen':. H APR 071983 TO OPERATE - Depress SPKR button on BRAMCO control box.
Switch toggle switch on radio-telephone to F1 position. Lift radio-telephone handset; depress touch tone buttons for touch tone number desired. First digit depressed must be held down long engugh to illuminate red light on radio-telephone to activate the radio. Depress hand button in' handset trip to transmit.
PSO Radio Locations / Numbers Radio Call Letters To Call Radio Call Letters Touch Tone Nurber Chatt. OPS Duty Off.
243 243 Bellefonte NP 250 250 Browns Ferry NP 290 290 Chickamauga LD 237 037 Chickamauga LD 204 004 Chattanooga A0 237 537 Chattanooga WC 237 837 Chattanooga LD 201 101 Guntersville Hydro 203 303 Huntsville A0 201 501 Huntsville A0 207 507 Madison Sub.
207 707 Madison Sub.
201 701 Huscle Shoals A0 1
200 500 Scottsboro PSC 204 904 Trinity Sub 282 782 Wilson LD 200 000 Wilson WC 200 800 Wilson LD 201 001 Wilson LD 207 007 Widows Creek Stm Plt.
204 404 I
Croup Call (Hold A ::;c r.d; First Digit y
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OPage 1 of 1 BFN-IPD BFN, IP-20 Attachment I Health Physics VHF Radio Instructions TO Talk:
1.
Depress the first black button on the left (See A in figure below).
2.
Lift the receiver.
3.
Depress the receiver button (See B) 4.
Talk into the receiver.
To Listen:
Release the receiver button Station Call Letters 1.
Mobile HP van - KIF 9133 2.
BFN Meterological Tower - KIF-254 3.
Muscle Shoals Emergency Center - KIF-253
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- Page 1 of 3 BFN-IPD BFN, IP-20 Attachment J Operation With TSC Relocated and/or OSC To Office Building (See Sketch) 1.
Site Emergency Director relocate to Plant Superintendent's Office.
2.
Operations Manager relocate to Assistant Plant Superintendent's (Maintenance) Office.
3 Maintenance Manager relocate to Electrical Maintenance Office.
4.
Technical Assessment Manager relocate to Ccmpliance Staff Office.
5.
REP Communicator and NRC Communicator relocate to reception area.
6.
a.
One secretary relocate to Plant Superintendent's Office, b.
One secretary relocate to reception area, c.
One secretary relocate to outside reception area for maintaining accountability.
7.
TSC Communicator remain in Control Room or Backup Control Room.
8.
Radiochemical Engineer, Reactor Engineer, Systems & Test Engineer, and Operations Specialist relocate to Compliance Staff Office.
t
_ 9.
PSO, Electrical, I & C, Hechanical Engineer, and Quality Assurance Representative relocat to Electrical Maintenance Office.
- 10. Health Physicists relocate to Engineering Section Office.
- 11. Public Safety Supervisor relocate to outside reception area. Set up access controls to relocated TSC.
Phone Numbers 1
I Positien 21H 2AX l
Site Emergency Director 703/704 212 Operations Manager 707/708 221 l
Maintenance Man'aser 7 97 235/207 Technical Assessment Manager 786 405/406 REP Communicator 701 202 l
NRC Communicator 701 202 Secretaries 701 202 TSC Communicator 628 (U-1) 191/192 (U-1) 629 (U-2) 291/292 (U-2) 630 (U-3) 391/392 (U-3)
Radiochemical Engineer 788 405/406 Operations Specialist 788 405/406 i
eAddendum h8/'
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Page 2 of 3 BFN-IPD r'
BFN. IP-20 Attachment J APR 071983 POSITION M
M Reactor Engineer 865 405/406 Systems & Test Engineer 865 405/406
'207/235 PSO Engineer
'891 Electrical Engineer 890 207/235 Hechanical Engineer 799 207/235 7 97 207/235 Quality Assurance Health Physicist 784 208/215 Health Physicist 785 208/215 202 PSS Supervisor 701 241 OSC (Elec) 790 618 206 03C (Mech)
OSC (I&C) 794 214 OSC (PS0) 793
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cpega 1 or.1 BFN-IPD BFN, IP-21 APR 071983 OPERATIONS SUPPORT CENTER. (OSC) OPERATIONS 1.0 PURPOSE To provide for OSC operation after it is manned. 2.0 INSTRUCTIONS NOTE: Refer to Figure 1 of IP-20 for Radiological Emergency Organisation. 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) PSO - Same as Electrical 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 (See IP-17 for additional supplies) 2.3 The Maintenance Manager in the TSC will direct the OSC through the respective engineers in the TSC. 2.4 Maintenance Unit Supervisor or individual designated by Maintenance Manager will supervise the 3 OSC areas. They will maintain a log of activities. 2.5 Individual in charge of OSC arca will maintain accountability for his personnel. 2.6 The primary role of OSC is damage *and repair assessment. Any inspections must be coordinated with Health Physics. Teams will be briefed as to conditions prior to disptch. 2.7 In events lasting longer than 12 hours, long-term operations will be undertaken as described in IP-22. 2.8 Should evacuation of the OSC be necessary, the office building, second floor, will act as backup (See IP-20, Attachment J). 2.9 See Attachment 1 for TSC Dimension and PAX phone nu=bers. \\ ' Revision G - f) L 2"' 9
Page 1 of 2 BFN - IPD BFN, IP-21 APR 071983 TECHNICAL SUPPORT CENTER - DIMENSION PHONE NUMBERS PHONE TITLE 771 Site Emergency Director 765 Operations Manaager 769 REP Communicator 896 eNRC Communicator 761 Technical Assessment Manager 766 Maintenance Manager 767 Health Physicist 763 Health Physicist 768 Radiochemical Engineer 773 Hechanical Engineer 772 Electrical Engineer 774 I & C Engineer 775 Reactor Engineer 762 Systems & Test Engineer 764 Operations Specialist 770 Secretary 776 PSO Engineer 777 Secretary 855 NRC Site Director of Operations 851 NRC 852 NBC 853 NRC 854 NRC ' Revision k ~ -y a
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- EFN-IPD BFN, IP-22 APR 071983 LONG TERM OPERATION 1.0 PURPOSE To provide for operation during a ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY which exists or is projected to exist for more than 12 hours.
2.0 INSTRUCTIONS INITTALS 2.1 Site Emergency Director notify DNPEC of decision to begin long-term operation. DNPEC can make arrangements necessary for food, clothing, cots, and other supplies requested. 2.2 Meal periods in the plant lunchroom will be scheduled by the Site Emergency Director. PSS Supervisor will provide for control of the area during these periods. 23 Sleeping facilities will be established as necessary in the second floor of the Office Building. PSS Supervisor will provide access control. (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). 2.4 The lunchroom in the control bay at elevation 3C (Swamp) will serve as an assembly room for meetings, etc. The plant assembly room can also be used if additional space is needed and radiological conditions permit. 2.5 Additional personnel will be called in by the Site Emergency Director to provide coverage in the following areas as necessary: a. Drawing Control Center b. Document Control c. Administration d. Additional clerical support 2.6 Site Emergency Director establish 12 hour or shorter shif ts in the TSC. Additional personnel will be called from IP-6 as necessary. The Maintenance Mana6er,.through the designated engineers, will 2.7 The establish 12-hour (or shorter) shifts for the OSC personnel. OSC personnel will, in turn, establish 12-hour (or shorter) shifts for their craft personnel onsite and call in additional personne1 as necessary.
- Rsvision U
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- Page 1 of 5 BFN-IPD BFN, IP-23 COMMUNICATIONS SYSTEMS 1.0 PURPOSE Provide a ready reference of onsite communication capabilities and key telephone and pager numbers on and offsite.
2.0 INSTRUCTIONS 2.1 Shift Enrineers Offies a. PAX (213/190) b. NRC red phone (GPO-1488) c. Bell (Dimension) system (750/751) d. Repeater radio (F1, F2) e. Paging system (beeper). See Attachment B f. PAX / Dimension executive right-of-way g. Turret extension (receiver only) h. Rin'g-down to/from superintendent's office 2.2 Technical Suocort Center a. PAX 288 (lunchroom or relay room) b. PAX 493 (5 lines). c. Bell (Dimension) System d. Private circuit with Chattancoga, Muscle Shoals, Knoxville - For TSC use (see IP-20 for numbers). e. NRC red phone (GPO 1488) f. PSO VHF radio - For PSO or Site Emergency Director use. (See Attachment E for operating instructions and nu=bers) g. Cordless telephone for TSC Ccm=unicator use (stered in TSC cabinet) h. Emergency Data Information System (CRT Lineprinter) ' Revision \\dbOI 0 -g
Page 2 of 5 BFN - IPD BFN. IP-23 ' APR 071983 ~ (~ 23 Doerations Succort Center e a. Mechanical - PAX 301/310/308/114/102/305/304/306 Dimension 620/625 b. Electrical & PSO - PAX 307/145/407 Dimension 619/612 c. Instrumentation - PAX 376/426/425/375/359/184/187 Dimension 634/635 2.4 Kev Onsite Numbers Location Phone (PAX) DIMENSION Assembly Room 167 Central Alarm Station 219 828/829/830 a' Chemical Laboratory 367/368 808 Code Call 270 (plus code) Code Call (Answer) 279 ,~ Communications room 257/283 821 Construction (CSB) Bell 729-6204 PAX 267/378 Document Control 203/421 842 J Drawing Control 149/419 879 East Oatehouse 112 Fire 199/299/399 Health Station 113/117 805/806/807 Health Physics Laboratory 300 803/804 Lunchroom 166 Medical Emergency 199/299/399 Meteorological Tower 182 Bell 729-6917 NRC (onsite) 346 627/877 Bell 729-6196 729-6197
- R evis ion I
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Pags 3 of 5 BFN - IPD BFN, IP-23 APR 071983 Operations 205/214 794 .QB.C. Mechani cal 301/310/308/114 620 102/304/305/306 Electrical & PSo 307/145/407 619/612 Instrumentation 376/426/425/375 634/635 359/184/187 Field Services 701/715 712 Paging System 3 87 Plant Superintendent's Office 212/221/202 701 Ring-down to/from SE's office Power Stores 217/268 754 PSS shift supervisor 273 829 Shift engineer's office 213/190 75~0 Shift technical advisor 353/396/313 g TSC 493 777/775 288 (lunchroom) TVA ambulance 273 829 West Gatehouse 271/280 828/829/830 2,4 Kev Offsite Numbers { Location Phone l Ambulances AAA Southend (Decatur) 205-355-3844 Athens Limestone Hospital 205-232-4141 Metro Shoals Emergency Hospital l Serviced (Florence) 205-766-8600 eRevision hvN l L { I
t Page 4 of 5 BFN - IPD BFN, IP-23 e APR 071983 Hosnitals Athens-Limestone 205-232-4141 Colonial Manor (Florence) 205-766-5091 Decatur General (205) 522-0175/522-0174 REAC/TS (Oak Ridge, TN) 615-576-3131 Private circuit from TSC e KEC (615) 533-5344/5345 Dimension 50-124-7690/7691 7692/7693 Private circuit from TSC MSEC (205) 386-2534/2767 FAX 5-310-1385/1384 Nat'l Earthquake Information Center (303) 234-3994 NRC (Atlanta) (404) 221-4503 (After 4 p.m., rings in Washington) (404) 221-5085 NRC Bethesda-via HPN Orange phone-Dini 22 NRC Operations Center (Bethesda) (202) 951-0550 (Co=mercial, used upon a failure of the Emergency Notification System) NRC (G. L. Paulk) (205) 350-5613 Beeper (205) 552-8929 Operations Duty Specialist, CECC Dimension 40+200 PAX 5-211-2495 (615) 751-2495 \\
- Revision )b#
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Page 5 of 5 BFN-IPD BFN, IP-23 APR 071983 2.6 Information on plant communications systems (Normal and alternate power supplies, etc.) is shown on Attachment A. 2.7 NRC Orange Phone (HP Network) - This phone is located in the HP plant laboratory and the NRC Resident Inspectors Office. The ph'one is to be used by TVA personnel sudbt 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 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. t w. l l oRevision IIkD Y m.hM 9 m l
=. - APR 011983 OPage 1 ot 2 BFN, IPD I BFN, IP-23 t Attachment A FOUIPMFNT COkBfENTS NORMAL POWER SUPPLY ALTERNATE POWER SUPPLY i r j ' PAX 48V DC Battery charged by 480V control bay vent 4801 common board 1 battery charger board A (1) I 480h Rx mov bd 2B (1) 480V comrcon board 1 Spare battery charger r I so,. 4kV common bd A 4kV common board B Two-way portable Lt bd 2C radios F1 channel (4) Lt bd 2A - F2 channel (4) 4kV common bd A 4kV common board B Instrument & Control A 4kV Sd bd 8 (1) 4kVSd bd C (1) (Batt bd 2) F3 480V : o bd 2A Sound powered Emergency shutdown N/A N/A phones control (self powered) Sound powered llP - Radiological N/A N/A phones emergency (self powered) Sound powered Self powered N/A N/A jacks UllF Radio Instrutnent & Control A 4kV sd bd B (1) 4kV sd bd C (1) i i S ta t ion (batt bd 2) - 480V SD bd 2A (1) 4 ~1Nacuation alarm Fuse. panel A 41(V sd bd A (1) 4kV sd bd B (1) ( 480V diesel aux bd A Fuse Panel B 4kV sd bd D (1) 4kV sd bd B (1) (see notes on page 2) 480V diesel aux bd B
- Revision </ %
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i APR 071933_'
- Pa c e 2 o't 2 BFN, IPD BFN, IP-23 Attachment A EQUIPMENT COMMENTS NORMAL POWER SUPPLY ALTERNATE POWER SUPPLY Code call Various lighting panels (2) 4kV common bd A or B 4kV common bd B or 1 r
Intercom system various lighting panels (5) 4kV common bd A or B .4kV common bd B or 1 Paging system ' Non-preferred MG set (3) (lighting bd 3B) (Lighting bd 3B 4kV common bd A 4-kV common bd B NRC, llP, REP Panel 9-9 bkr 621 Unit preferred (U2) Unit preferred (U3) phones (Unit 2) (Batt bd 2 bkr 117) (1) (Batt bd 3 bkr 1102) Microwave radio (24V batteries) 480V sd bd kA (1) 480V common bd A and power line battery charger control carrier for PAX bay vent bd A phones (24V batteries) 480V com bd 3 480V sd bd 3B (1) battery chacger control bay vent bd B Dimension phones LC #205, BKR #1 LOC R12N (IC Ctr1. Bay) Notes: 1. Diesel backed 2. DCR P2437 Diesel backed power. 3. DCR P2438 Diesel backed power. 4. DCR P2420 Diesel backed power. 5. DCR P2440 Diesel backed power.
- Addendum q
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- Page 1 of 1 BFN - IPD BFN, IP-23 Attachment C APR 071983 DELETED "e
+ aRevision 0
GP:g2 1 of 1 BFN - IPD BFN, IP-23 f-Attachment E APR 071983 DELETED eRevision ~0 'M ~
.r- - T------- l 1 I e 1 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL EMERGENCY PLAN RADI0 CHEMICAL LABORATORY PROCEDURE BFN IP - 25 1 ~ Approved: h Plant S'u erintendent Doe,, APR 071983 l s ~. 7,> ~ ~, - _.,,
O Pzgs 1 of 2 BFN - IPD BFN, IP-25 APR 071983 RADI0 CHEMICAL LABORATORY PROCEDURE 1.0 PURPOSE This procedure outlines the actions to be followed by Radiochemical Laboratory personnel during an emergency involving radiochemical problems. Natural phenomena, security threats, or other events not involving radiochemistry could be the cause for the emergency. This procedure describes those Radiochemical Laboratory actionsrequired during an emergency involving radiochemical problems. NOTE: Shif t Engineer's c!.erk will initiate IP-25 by calling the Radiochemical Shift Supervisor. 2.0 NOTIFICATION OF UNUSUAL EVENT 2.1 No offsite radiochemical problems are postulated during a NOTIFICATION OF UNUSUAL EVENT. This situation should not have any major impact on the Radiochemical Laboratory. 2.2 Although the lab will not automatically be called, should assistance be needed, RLAS will follow standard practices and procedures during any response work. 30 ALERT General A limited release is possible during an ALERT situation. Significant loss of fuel cladding, small line breaks, fuel handling accidents, or high radiation, levels are examples. INITTAtR 3.1 All RLAS report to the radiochemi_ cal lab. 32 Prepare to implement RLM Radiological Emergency Sampling and Analysis Procedures. 33 verify proper operation of laboratory assigned survey instruments. 3.4 An ALERT may require the evacuation of a certain plant area and/or building. If the lab must be evacuated, See Section 7.0. l l 4.0 SITE AREA EMERGENCY General A SITE AREA EMERGENCY may require extensive Radiochemical Laboratory response. A LCCA or major fuel handling accident are exa=ples of a SITE AREA EMERGENCY. 1 4.1 RLAS report to the lab. I 4.2 Prepare to implement RLM Radiological Emergency Sampling ano Analysis Procedures. 43 Verify proper operation of laboratory assigned survey instruments. -ht r l
cPegt 2 of 2 BFN - IPD BFN, IP-25 APR 071983 TNITTALS 4.4 If a site evacuation is ordered, see Section 6.0. 4.5 If the Radiochemical Laboratory must be evacuated, see Section 7 0. 5.0 GENERAL EMERGENCY General During a GENERAL EMERGENCY, there will probably be radiochemical problems requiring radiochemical laboratory response. 5.1 RLAS report to the lab. 5.2 Prepare to implement RLM Radiological Emergency and Sampling Procedures. 53 Verify proper response of laboratory assigned survey instruments. 5.4 If a site evacuation is ordered, see Section 6.0. If the Radiochemical Laboratory must be evacuated, see Section 7 0. 5.5 6.0 SITE EVACUATION 6.1 RLAS proceed to lab, if habitable. If uninhabitable, see Section 7.0. c 6.2 Report accountability to Site Emergency director. 70 RADI0 CHEMICAL LABORATORY UNINHABITABLE 7 1 Move equipment as shown in RLM 2106 to establish a laboratory at the intake in the installed wire cage. This cage would be equipped with all the necessary gamma counting instrume_ntation needed to perfor= a minimum of radiochemistry sampling and analyses required during an emergency. 7 2 Report to Site Emergency Director. ,,e.._,
9 r Revision Log Sheet Revision Date: JUN O 3 una This log sheet must be retained as the last page of the Division of Nuclear Power Emergency Center Implementing Procedures Document. Date Inserted: Inserted by: Pages to be Removed New Pages to be Inserted Part Page Number Revision Part Page Number Revision IP-2 Cover Page 4 IP-2 Cover Page 5 Att. I 1 of 2 4 Att. I 1 of 2 5 2 of 2 4 2 of 2 5 Att. 2 1 of 2 4 Att. 2 1 of 2 5 2 of 2 4 2 of 2 5 IP-3 Cover Page 5 IP-3 Cover Page 6 1 of 3 5 1 of 4 6 2 of 3 5 2 of 4 6 3 of 3 5 3 of 4 6 4 of 4 6 Att. 1 I of 2 5 Att. I 1 of 2 6 2 of 2 5 2 of 2 6 Att. 2 1 of 2 5 Att. 2 1 of 2 6 2 of 2 5 2 of 2 6 IP-4 Cover Page 5 IP-4 Cover Page 6 1 of 3 5 1 of 4 6 2 of 3 5 2 of 4 6 3 of 3 5 3 of 4 6 4 of 4 6 Att. I 1 of 2 5 Att. I 1 of 2 6 2 of 2 5 2 of 2 6 Att. 2 1 of 2 5 Att. 2 1 of 2 6 2 of 2 5 2 of 2 6 4 a ~ ;
3 . (' REVISION LOG SHEET (Continued)
Subject:
DNPEC-IPD Revision Date: tilN 0 314R3 Pages to be Removed New Pages to be Inserted Part Page Number Revision Part Page Number Revision IP-5 Cover Page 5 IP-5 Cover Page 6 1 of 3 5 1 of 4 6 2 of 3 5 2 of 4 6 3 of 3 5 3 of 4 6 4 of 4 6 Att. I 1 of 2 5 Att. 1 1 of 2 6 2 of 2 5 2 of 2 6 Att. 2 1 of 2 5 Att. 2 1 of 2 6 2 of 2 5 2 of 2 6 IP-6 Cover Page 3 IP-6 Cover Page 4 1 of 9-3 1 of 5 4 2 of 9 3 2 of 5 4 ' 3 of 9 3 3 of 5 4 4 of 9 3 4 of 5 4 5 of 9 3 5 of 5 4 6 of 9 3 7 of 9 3 8 of 9 3 9 of 9 3 Att. 1 1 of 1 3 Att. I 1 of 5 4 2 of 5 4 3 of 5 4 4 of 5 4 5 of 5 4 Att. 2 1 of 1 3 Att. 2 1 of 1 4 Att. 3 1 of 1 4 Att. 4 1 of 1 4 e M_
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s_ REP-IPD DNPEC - IP-2 OPERATIONS DUTY SPECIALIST PROCEDURE FOR NOTIFICATION OF UNUSUAL EVENT Prepared By: W. E. Webb, Jr. Approved By: w Date: /2s/a1 " J i Rev. No. Date Revised Pages Rev. No. Date Revised Pages All 3 2/3/83 2 0 9/11/,,81 MAR 171983 1 3/10/82 2 4 in JUN 0 31983 4 _ 7 2 OCT 2 6 882 All 5 Rev. No.
- Date, Revised Pages Rev. No.
Date Revised Pages ~ ,a ^~ i The last page of this t rocedure is 7 s
DNPEC-IPD IP-2 ( Page 1 of 2 Rev. 5 BROWNS FERRY /BELLEFONTE NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM Turn on recording equipment Date Time Initials Call verified Site Emergency Director NOTIFICATION TO STATE OF ALABAMA /TVA EMERGENCY CENTER My name is TVA, Operations Duty Specialist.
- The Browns Ferry Bellefonte Nuclear Plant, Unit declared a:
Notification of Unusual Event Alert s Site Area Emergency General Emergency at CST (time of incident) on (date).
- (Initially, provide the above information. Request State Radiological Health Staff duty officer to call you back for detailed information.)
- ~::::::::::::::::::::::::::::~ ::::::::~ :~:::::::::::::::::::::~ ~
Brief description of the incident is: The plant condition is: Stable Deteriorating The reactor (did/did not) shut down at CST on (date)
- Revision
--rg s i 2" ' i
. ~ DNPEC-IPD IP-2 Page 2 of 2 / Rev. 5 (Continued) BROWNS FERRY /BELLEFONTE NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM The emergency situation: (a) Does Not Involve a Radiation Release from the Plant (b) Involves a Radiation Release From the Plant (c) Radiation Release Information is Not Known The radiation release is: (a) Ground Level - Airborne (b) Elevated - Airborne (c) Waterborne (d) Other The radiation release rate is: (a) Microcuries/Second (assumes noble gas / radio-(b) None iodine mix with 0.11% I131) (c) Unknown The wind direction is from
- (degrees)
Wind speed m/s (meters per second) We recommend this protective action: (a) No protective action is recommended at this time (Notification of Unusual Event, Alert, Site Area Emergencies). (b) Activate the warning system and tune radio or TV to a local station. Advise the public to take shelter, and await further instructions (General Emergency). Emergency actions underway onsite are: (i.e., plant evacuation) l l Onsite support needed from offsite organization is: l i I General Revision 9 O '~ e l ! I L
ONPEC-IPD IP-2 Attacheent 2 Page 1 of 2 Rev. 5 SEQUOYAH/ WATTS BAR NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM Turn on recording equipment Date Time Initials Call verified Site Emergency Director NOTIFICATION TO STATE OF TENNESSEE /TVA EMERGENCY CENTEZ My name is , TVA, Operations Duty Specialist.
- The Browns Ferry Bellefonte Nuclear Plant, Unit declared a:
Notification of Unusual Event Alert Site Area Emergency General Emergency s at CST (time of incident) on (date). (Initially, prcvide the above information. Request State duty officer to call you back for detailed information.)
- ~ ::::~ ::::::::::::::::
Brief description of the incident is:
- Revision M
~ ~ %qn me DNPEC-IPD IP-2 / Page 2 of 2 Rev. 5 (Continued) SEQUOYAH/ WATTS BAR NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM The plart condition is: Stable Deteriorating The emergency situation: (a) Does Not Involve a Radiation Release from the Plant (b) Involves a Radiation Release From the Plant (c) Radiation Release Information is Not Known The radiation release is: (a) Ground Level - Airborne (b) Elevated - Airborne (c) Waterborne (d) Other The wind direction is from
- (degrees)
Wind speed mi/h (miles per hour) We recommend this protective action: (a) No protective action is recommended at this time (Notification of Unusual Event, Alert, Site Area Emergencies). (b) Activate the warning system and tune radio or TV to a local. station. Advise the public to take shelter, and await further instructions (General Emergency). 4 General Revision
.m j / REP-IPO DNPEC - IP-3 OPERATIONS DUTY SPECIALIST PROCEDURE FOR ALERT ~ Prepared By: W. E. We_bb, Jr. Approved By: kM M Da te: 9/2s/81 U J s Rev. No. Date Revised Pages Rev. No. Da te Revised Pages All 3 2/3/83 2 0 9/_21181 1 3/10/82
- 2. 3 4 _
2/24/83 3 MAR 17_1983 2 OCT P.d j982 All 5 311 2. Rev. No. Date Revised Pages Rev. No._ Date Revised Pages JUN 031983 311 6 i i i l The last,page of this p,rocedure is 8 ,,s. { {
] DNPEC-IPD IP-3 Page 1 of 4 Rev. 6 OPERATIONS DUTY SPECIALIST PROCEDURE FOR ALERT 1.0 PURPOSE This procedure is designed to direct the ODS during an alert to ensure consistent, accurate, and timely ' response in the event of an emergency. 2.0 SCOPE This procedure covers anticipated requirements of the ODS during an alert. This procedure does not cover additional actions to be taken prior or subsequent to an emergency or drill, nor does it cover the requirements of the ODS under a Site Area Emergency, or General Emergency, or Notification of Unsual Event.
3.0 REFERENCES
Radiological Emergency Plan. 4.0 ABBREVIATIONS AND DEFINITIONS L EDO - Emergency Duty Officer ODS - Operations Duty Specialist DNPEC - Division of Nuclear Power Emergency Center CECC - Central Emergency Control Center MSEC - Muscle Shoals Emergency Center KEC - Knoxville Emergency Center 5.0 RESPONSIBILITIES 5.1 *Upon notification by the Site Emergency Director that an alert exists, the ODS is responsible for recording the preliminary report of infor-mation (attachment 1 for Browns Ferry /Bellefonte or attachment 2 for Sequoyah/ Watts Bar) concerning the incident.
- The ODS is responsible for notifying the appropriate State agency.
DNP EDO, CECC Director, DNPEC Director, MSEC Director, KEC Duty The ODS Officer, Load Coordinator, and key CECC and DNPEC staff. is also responsible for notifying technical support personnel at the discretion of the DNPEC Director. 6.0 PROCEDURE REQUIREMENTS 6.1
- Actions to be Taken for an Alert The ODS performs the following tasks:
- Revision WW
DNPEC-IPD IP-3
- Page 2 of 4 Rev. 6 Note: When making notifications of an emergency situation, provide only the information contained on the appropriate attachment.
Avoid any unnecessary explanation, interpretation, or elabora-tion of the information. Timeliness and accuracy is of the utmost importance. (Time / Initials) / 6.1.1 Upon receiving a call from the Site Emergency Director: 1. Turn on recording equipment. 2. Receive information from the Site Emergency Director. 3. Log information on the appropriate attachment. 4. Conduct verification call to originating plant. / 6.1.2 Notify the appropriate State agency by direct line. For the initial notification, provide only the basic information as indicated on the appropriate attachment. Request that the State make a verification callback, and at that time provide them the remainder of the attachment information. After hours, the Alabama phone will be answered by the Department of Public Safety. Provide the officer with the basic information as indicated on attachment 1. Request that he contact the Radiological Health Staff and have them call the ODS for additional information. Provide the remainder of the attachment 1 information when the call is returned. Alternate telephone numbers for these agencies are listed in the TVA Radiological Emergency Notification Directory. Note: Notification to the State shall be made as soon as possible such that in all cases it is made within five minutes from when call is first received from the plant. Under this emergency classification, the ODS is the " primary contact" with the State. The ODS is relieved of this function by the CECC State Communicator once the CECC is staffed. / 6.1.3 Notify the DNP EDO. (See the DNP Notification Board.) / 6.1.4 Notify the MSEC Director. (See the DNP Notification Board.) / 6.1.5 Notify the CECC Director and have him report to the center. (See the DNP Notification Board.)
- Revision
~Z$ ~ -t- --.+-p -yy., - + r y - + -
DNPEC-IPD IP-3 Page 3 of 4 Rev. 6 / 6.1.6 Notify the DNPEC Director and have him report to the
- center. Ask the DNPEC Director who should be contacted
- as DNPEC Technical Communicator; Electrical and Instrument
- and Controls or Mechanical Branch representative.
Determine if the DNPEC Director considers it necessary to call any technical support personnel at this time. If requested to do so, notify them last (see section 6.1.10). (See the DNP Notification Board.) / 6.1.7 Notify the KEC Duty Officer and have him activate the KEC, if required. (See the DNP Notification Board.) / 6.1.8 Notify the Load Coordinator of the condition. / 6.1.9 Notify the key DNPEC staff (see the DNP Notification
- Board).
Key DNPEC Staff
- 1 Assistant Director (a DNPEC Director alternate) 1 Reactor Engineering
- 1 Technical Communicator (designated by the DNPEC Director as either Electrical and Instrument and Controls or Mechanical Branch)
- 1 Plant Communicator
- 1 Assessment Team Leader (BWR - Browns Ferry, PWR -
Sequoyah or Watts Bar) Emergency Preparedness and Protection 1
- 2,3 Mechanical (if primary representative was contacted as Technical Communicator, contact the designated alternate)
- 2 3 Electrical and Instrument and Controls (if primary representative was contacted as Technical Communi-cator, contact the designated alternate) 2 Field Services
- 2 Management Services (request that he provide appropriate clerical support and an electronic board writer for the DNPEC and CECC)
Request these individuals to report to the DNPEC. 1
- NOTE:
Request these individuals to report to the 2 appropriate branch office. If the primary contact was not reached, and the 3 alternate was contacted to serve as Technical Communicator, then request the alternate to designate a Technical Support contact to respond to the appropriate branch office. Contact that person and have him respond.
- Revision
- Deletion
- Addendum ve
- Deletion
?.. 2" .- ~ -.,.,, - r ,.m
DNPEC-IPD IP-3 Page 4 of 4 Rev. 6 / 6.1.10 Notify the designated technical support personnel to report to the DNPEC if requested by the DNPEC Director. (See the DNP Notification Board.) s 1 l \\ l l 1 1 1 .p5 ~- f - i
DNPEC-IPD IP-3 Page 1 of 2 Rev. 6 BROWNS FERRY /BELLEFONTE NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM d Turn on recording equipment Date Time Initials Call verified Site Emergency Director NOTIFICATION TO STATE OF ALABAMA /TVA EMERGENCY CENTER My name is, , TVA, Operations Duty Specialist.
- The Browns Ferry Bellefonte Nuclear Plant, Unit declared a:
Notification of Unusual Event Alert s Site Area Emergency General Emergency at CST (time of incident) on (date).
- (Initially, provide the above information. Request State Radiological Health Staff duty officer to call you back for detailed information.)
Brief description of the incident is: The plant condition is: Stable Deteriorating The reactor (did/did not) shut down at CST on (date)
- Revision 4
O DNPEC-IPD IP-3 Page 2 of 2 Rev. 6 , (Continued) BROWNS FERRY /BELLEFONTE NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM The emergency situation: (a) Does Not Involve a Radiation Release from the Plant (b) Involves a Radiation Release From the Plant (c) Radiation Release Information is Not Known The radiation release is: (a) Ground Level - Airborne (b) Elevated - Airborne (c) Waterborne (d) Other The radiation release rate is: (a) Microcuries/Second (assumes noble gas / radio-(b) None iodine mix with 0.11% I:33) (c) Unknown Thewindqirectionisfrom
- (degrees)
Wind sp,eed m/s (meters per second) We recommend this protective action: (a) No protective action is recommended at this time (Noti-fication of Unusual Event, Alert, Site Area Emergencies). (b) Activate the warning system and tune radio or TV to a local station. Advise the public to take shelter, and await further instructions (General Emergency). Emergency actions underway onsite are: (i.e., plant evacuation) s Onsite support needed from offsite organization is: l General Revision 1 -<y ~ ,,w.
4 i DNPEC-IPD IP-3 4 i Pt.. 1 of 2 Rev. 6 1 1 t SEQUOYAH/ WATTS BAR NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM -s Turn on recording equipment Date Time Initials 5 Call verified Site Emergency Director NOTIFICATION TO STATE OF TENNESSEE /TVA EMERGENCY CENTER i - My name is , TVA, Operations Duty Specialist.
- The Sequoyah Watts Bar Nuclear Plant, Unit declared a:
Notification of Unusual Event Alert s Site Area Emergency General Emergency at CST (time of incident) on (date).
- (Initially, provide the above information. Request State duty officer to call you back for detailed information.)
i Brief description of the incident is: i t i-i e i ~m Z~ ~
- Revision,
,+,,+,~e - g rv-r--r
,,--,e,,,.,y---.,,,.,m:.,,,,-..,w,,,,,-.,--..-y.
,,,,..,,.,.w ,,rw----y3 - rr e m, c~- e,-w.~,
,. ~... - DNPEC-IPD IP-3 Page 2 of 2 Rev. 6 (Continued) SEQUOYAH/ WATTS BAR NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST lNCIDENT FORM The plant condition is: Stable Deteriorating The emergency situation: (a) Does Not Involve a Radiation Release from the Plant (b) Involves a Radiation Release From the Plant (c) Radiation Release Information is Not Known The radiation release is: (a) Ground Level - Airborne (b) Elevated - Airborne (c) Waterborne (d) Other The wind direction is from
- (degrees)
Windspeek mi/h (miles per hour) We recommend this protective action: (a) No protective action is recommended at this time (Noti-fication of Unusual Event, Alert, Site Area Emergencies). (b) Activate the warning system and tune radio or TV to a local station. Advise the public to take shelter, and await further instructions (General Emergency). ~ General Revision n_,- _g_
REP-IPD DNPEC - IP-4 OPERATIONS DUTY SPECIALIST PROCEDURE FOR SITE EMERGENCY t W. E. Webb, Jr. Prepared By: kA LL1]h Approved By: Date: 9/25/81 U sg Rev. No. Date Revised Pages Rev. No. Da te Revised Pages All 3 2/3/83 2 0 9/2.5.Lg1 1 3/10/82 2, 3 4 2/24/83 _ 2 MAR 17]SS3 n1 2 OCT PJLS82 ni s Rev. No. Date Revised Pages Rev. No. Date Revised Pages JUN 031983 n1 4 i The last page of this procedure is 8 u 9
n DNPEC-IPD IP-4 Page 1 of 4 Rev. 6 OPERATIONS DUTY SPECIALIST PROCEDURE FOR SITE AREA EMERGENCY 1.0 PURPOSE This procedure is designed to direct the ODS during a Site Area Emergency to ensure consistent, accurate, and timely response in the event of an emergency. 2.0 SCOPE This procedure covers anticipated requirements of the ODS during a Site Area Emergency. This procedure does not cover additional actions to be taken prior or subsequent to an emergency or drill, nor does it cover the requirements of the ODS under a General Emergency, Notification of Unusual Event or Alert.
3.0 REFERENCES
Radiological Emergency Plan. 4.0 ABBREVIATIONS AND DEFINITIONS EDO - Emergency Duty Officer ODS - Operations Duty Specialist DNPEC - Division of Nuclear Power Emergency Center CECC - Central Emergency Control Center MSEC - Muscle Shoals Emergency Center KEC - Knoxville Emergency Center 5.0 RESPONSIBILITIES 5.1 Upon notification by the Site Emergency Director that a Site Area Emergency exists, the ODS is responsible for recording the preliminary report of information (attachment I for Browns Ferry /Bellefonte or attachment 2 for Sequoyah/ Watts Bar) concerning the incident. The ODS is responsible for notifying the appropriate State agency, DNP EDO, CECC Director, DNPEC Director, MSEC Director, KEC Duty Officer, Load Coordinator, and key CECC and DNPEC staff. The ODS is also responsible for notifying technical support personnel at the discretion of the DNPEC Director. 6.0 PROCEDURE REQUIREMENTS 6.1
- Actions to be Taken for a Site Area Emergency
- Revision
~ ~ . I
DNPEC-IPD IP-4
- Page 2 of 4
,~ Rev. 6 The ODS performs the following tasks: Note: When making notifications of an emergency situation, provide only the information contained on the appropriate attachment. Avoid any unnecessary explanation, interpretation, or elabora-tion of the information. Timeliness and accuracy is of the utmost importance. (Time / Initials) / 6.1.1 Upon receiving a call from the Site Emergency Director: 1. Turn on recording equipment. 2. Receive information from the Site Emergency Director. 3. Log information on the appropriate attachment. 4. Conduct verification call to originating plant. For / 6.1.2 Notify the appropriate State agency by. direct line. the initial notification, provide only the basic information as indicated on the appropriate attachment. Request that the State make a verification callback, and at that time s provide them the remainder of the attachment information. After hours, the Alabama phone will be answered by the Department of Public Safety. Provide the officer with the basic information as indicated on attachment 1. Request that he contact the Radiological Health Staff and have them call the ODS for additional information. Provide the remainder of the attachment 1 information when the call is returned. Alternate telephone numbers for these agencies are listed in the TVA Radiological Emergency Notification Directory. Note: Notification to the State shall be made as soon as possible such that in all cases it is made within five minutes from when call is first received from the plant. Under this emergency classification, the ODS is the " primary contact" with the State. The ODS is relieved of this function once the CECC is staffed. / 6.1.3 Notify the DNP EDO. (See the DNP hotification Board.) / 6.1.4 Notify the MSEC Director and have him activate the MSEC. (See the DNP Notification Board.)
- Revision
-:9;s y.
DNPEC-IPD IP-4 Page 3 of 4 Rev. 6 / 6.1.5 Notify the CECC Director and have him report to the center. (See the DNP Notification Board.) / 6.1.6 Notify the DNPEC Director and have him report to the
- center. Ask the DNPEC Director who should be contacted
- as DNPEC Technical Communicator; Electrical and Instrument
- and Controls or Mechanical tranch representative.
Determine if the DNPEC Director considers it necessary to call any technical support personnel. If requested to do so, notify them last (see section 6.1.10). (See the DNP Notification Board.) / 6.1.7 Notify the KEC Duty Officer and have him activate the KEC. (See the DNP Notification Board.) / 6.1.8 Notify the Load Coordinator of the condition. / 6.1.9 Notify the key DNPEC staff (see the DNP Notification
- Board).
Key DNPEC Staff
- lAssistant Director (a DNPEC Director alternate) 1 Reactor Engineering
- 1 Technical Communicator (designated by the DNPEC Director s
as either Electrical and Instrument and Controls or Mechanical Branch)
- 1 Plant Communicator
- tAssessment Team Leader (BWR - Browns Ferry, PWR -
Sequoyah or Watts Bar) 1Emergency Preparedness and Protection
- 2,aMechanical (if primary representative was contacted as Technical Communicator, contact the designated alternate)
- 2 3 Electrical and Instrument and Controls (if primary representative was contacted as Technical Communicator, contact the designated alternate) 2 Field Services
- 2 Management Services (request that he provide appropriate clerical support and an electronic board writer for the DNPEC and CECC)
- NOTE:
1 Request these individuals to report to the DNPEC. 2Request these individuals to report to the appropriate branch office. 3If the primary contact was not reached and the alternate was contacted to serve as Technical Communicator, then request the alternate to designate a Technical Support contact to respond to the appropriate branch office. Contact that person and have him respond.
- Revision
- Deletion
- Addendum
- Deletion
~~r4> 2" L ? "Aq + i s DNPEC-IPD IP-4 I Page 4 of 4 Rev. 6 l-si / 6.1.10 Notify the designated technical support personnel to l report to the DNPEC if requested by the DNPEC Director. l (See the DNP Notification Board.) .i 1 a 4 1 i if 1 1 i i i i s. 4 r i J l 1 } s. i. A,~pd 1 t ~ 7' s T, i i wam .c. .w-.,-c-4_-.,w,.,,,-,, .,u-.,-m,-..,,,,,wn,,w-p,,ny,=-w..,,,- g..y%,y,,w,ww., 4 g w p., g-t T r
DNPEC-IPD IP-4 Page 1 of 2 Rev. 6 BROWNS FERRY /BELLEFONTE NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM Turn on recording equipment Date Time Initials Call verified Site Emergency Director NOTIFICATION TO STATE OF ALABAMA /TVA EMERGENCY CENTER My name is , TVA, Operations Duty Specialist.
- The Browns Ferry Bellefonte Nuclear Plant, Unit declared a:
Notification of Unusual Event Alert s Site Area Emergency General Emergency at CST (time of incident) on (date).
- (Initially, provide the above information. Request State Radiological Health Staff duty officer to call you back for detailed information.)
- ~ :::::::::::::::::::::::::::::::: ~2:::::::::::::~
Brief description of the incident is: The plant condition is: Stable Deteriorating The reactor (did/did not) shut down at CST on (date)
- Revision
T7, a' i '~
DNPEC-IPD IP-4 Page 2 of 2 Rev. 6 (Continued) BROWNS FERRY /BELLEFONTE NUCLEAR PLANTS ~ OPERATIONS DUTY SPECIALIST INCIDENT FORM The emergency situation: (a) Does Not Involve a Radiation Release from the Plant (b) Involves a Radiation Monitor From the Plant (c) Radiation Release Information is Not Known The radiation release is: (a) Ground Level - Airborne (b) Elevated - Airborne (c) Waterborne (d) Other The radiation release rate is: (a) Microcuries/Second (assumes noble gas / radio-(b) None iodine mix with 0.11% I333) (c) Unkncwn The wind direction is from
- (degrees)
Wind speed m/s (meters par second) We recommend this protective action: (a) No protective action is recommended at this time (Noti-fication of Unusual Event, Alert, Site Area Emergencies). (b) Activate the warning system and tune radio or TV to a local station. Advise the public to take shelter, and await further instructions (General Emergency). I Emergency actions underway onsite are: (i.e., plant evacuation) i i Onsite support needed from offsite organization is: i General Revision 'cEvg l 1.
\\ DNPEC-IPD IP-4 Page 1 of 2 Rev. 6 SEQUOYAH/ WATTS BAR NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM Turn on recording equipment Date Time Initials Call verified Site Emergency Director NOTIFICATION TO STATE OF ALABAMA /TVA EMERGENCY CENTER My name is , TVA, Operations Duty Specialist.
- The Sequoyah Watts Bar Nuclear Plant, Unit declared a:
Notification of Unusual Event Alert Site Area Emergency General Emergency at CST (time of incident) on _ (date).
- (Initially, provide the above information. Request State Radiological Health Staff duty officer to call you back for detailed information.)
- ~ :::::::::::::::::::::::::::::::::::::::::::::::::~ :::::::::::::::~
Brief description of the incident is: -.f
- Revision DNPEC-IPD IP-4 Page 2 of 2 Rev. 6 (Continued)
SEQUOYAH/ WATTS BAR NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM The plant condition is: Stable Deteriorating The emergency situation: (a) Does Not Involve a Radiation Release from the Plant (b) Involves a Radiation Release From the Plant (c) Radiation Release Information is Not Known The radiation release is: (a) Ground Level - Airborne (b) Elevated - Airborne (c) Waterborne (d) Other The wind direction is from
- (degrees) s Wind speed mi/h (miles per hour)
We recommend this protective action: (a) No protective action is recommended at this time (Noti-fication of Unusual Event, Alert, Site Area Emergencies). (b) Activate the warning system and tune radio or TV to a local station. Advise the public to take shelter, and await further instructions (General Emergency). I l l I i General Revision =g - l
o REP-IPD DNPEC - IP-5 OPERATIONS DUTY SPECIALIST PROCEDURE FOR GENERAL EMERGENCY i Prepared By: W. E. Webb, Jr. n Approved By: Date: 9/25/81 v u Rev. No. Date Revised Pages Rev. No. Date Revised Pages n 9/25/81 All 3 2/3/83 2 1 3/10/82 2,' 3 A 2/2.4483 1 OCT 23_2 m 5 MAR 171983 All 2 Rev. No. Date Revised Pages Rev. No. Date. Revised Pages 6 JUN 031983 All i The last page of this procedure is 8 ~. ~ ?] g .s.
DNPEC-IPD IP-5 Page 1 of 4 Rev. 6 OPERATIONS DUTY SPECIALIST PROCEDURE FOR GENERAL EMERGENCY l 1.0 PURPOSE This procedure is designed to direct the ODS during a General Emergency to ensure consistent, ar urate, and timely response in the event of an emergency. 2.0 SCOPE This procedure covers the action of the ODS during a General Emergency. This procedure does not cover additional actions to be taken prior or subsequent to an emergency or drill, nor does it cover the requirements of the ODS under a Notification of Unusual Event, Alert, or Site Area Emergency.
3.0 REFERENCES
Radiological Emergency Plan. r 4.0 ABBREVIATIONS AND DEFINITIONS EDO - Emergency Duty Officer ODS - Operations Duty Specialist DNPEC - Division of Nuclear Power Emergency Center CECC - Central Emergency Control Center MSEC - Muscle Shoals Emergency Center KEC - Knoxville Emergency Center 5.0 RESPONSIBILITIES 5.1 Upon notification by the Site Emergency Directo.r that a General Emergency exists, the ODS is responsible for recording the preliminary report of information (attachment I for Browns Ferry /Bellefonte or attachment 2 for Sequoyah/ Watts Bar) concerning the incident. The ODS is responsible for notifying the appropriate State and local agencies, DNP EDO, CECC Director, DNPEC Director, MSEC Director, KEC Duty Officer, Load Coordinator, and key CECC and DNPEC staff. The ODS is responsible for notifying technical support personnel at the discretion of the DNPEC Direc*.or. 6.0 PROCEDURE REQUIREMENTS 6.1
- Action to be Taken for a General Emergency The ODS performs the following tasks:
~r> ~
- R,evision l
DNPEC-IPD IP-5 Page 2 of 4 Rev. 6 Note: When making notifications of an emergency situation, provide only the information contained on the appropriate attachment. Avoid any unnecessary explanation, interpretation, or elabora-tion of the information. Timeliness and accuracy is of the utmost importance. (Time / Initials) / 6.1.1 Upon receiving a call from the Site Emergency Director: 1. Turn on recording equipment. 2. Receive information from the Site Emergency Director. 3. Log information on the appropriate attachment. 4. Conduct verification call to originating plant. / 6.1.2 Notify the appropriate State agency by direct line. For the initial notification, provide only the basic information as indicated on the appropriate attachment. Request that the State make a verification callback, and at that time provide them the remainder of the attachment information. After hours, the Alabama phone will be answered by the Departa at of Public Safety. Provide the officer with the basic information as indicated on attachment 1. Request that he contact the Radiological Health Staff and have them call the ODS for additional information. Provide the remainder of the attachment 1 information when the call is returned. Alternate telephone numbers for these agencies are listed in the TVA Radiological Emergency Notification Directory. Note: Notification to the State shall be made as soon as possible such that in all cases it is made within five minutes from when call is first received from the plant. Under this emergency classification,,the ODS is the " primary contact" with the State. The ODS is relieved of this function the CECC is staffed. / 6.1.3 Notify the appropriate local Civil Defense Agencies. (See the TVA Radiological Emergency Notification Directory.) Give the following message. "This is the TVA Operations Duty Specialist. We have a General Emergency existing at nuclear plant. Please activate your emergency organization. You will receive further instructions frcm the appropriate State agency."
- Revision
~ f# L f
DNPEC-IPD IP-5 Page 3 of 4 Rev. 6 Ensure the following recommended protective action is given: "TVA recommends that you activate the warning system and advise the public to take shelter, tune radio or TV to a local station, and await further instructions." / 6.1.4 Notify the DNP EDO. (See the DNP Notification Board.) / 6.1.5 Notify the MSEC Director and have him activate the MSEC. (See the DNP Notification Board.) / 6.1.6 Notify the CECC Director and have him report to the center. (See the DNP Notification Board.) / 6.1.7 Notify the DNPEC Director and have him report to the
- center. Ask the DNPEC Director who should be contacted as
- DNPEC Technical Communicator; Electrical and Instrument and
- Controls or M2chanical Branch representative. Dete rmine if the DNPEC Director considers it necessary to call any
- technical support personnel at this time.
If requested to
- do so, notify them last (see section 6.1.11).
(See the DNP Notification Board.) / 6.1.8 Notify the KEC Duty Officer and have him activate the KEC. (See the DNP Notification Board.) / 6.1.9 Notify the Load Coordinator of the condition. / 6.1.10 Notify the key DNPEC staff (see the DNP Notification
- Board).
Key DNPEC Staff
- 1 Assistant Director (a DNPEC Director alternate) 1 Reactor Engineering
- 1 Technical Communicator (designated by the DNPEC Director as either Electrical and Instrument and Controls or Mechanical Branch)
- 1 Plant Communicator
- 1 Assessment Team Leader (BWR - Browns Ferry, PWR - Sequoyah or Watts Bar)
Emergency Preparedness and Protection 1
- 2 3 Mechanical (if primary representative was contacted as Technical Communicator, contact the designated alternate)
- 2 3 Electrical and Instrument and Controls (if primary representative was contacted as Technical Communicator, contact the designated alternate) 2 Field Services Management Services (request that he prcvide appropriate
- 2 clerical support and an electronic board writer for the DNPEC and CECC)
- Revision
- Deletion e
2~
- Addendam DNPEC-IPD IP-5 Page 4 of 4 Rev. 6
- NOTE:
1 Request these individuals to report to the DNPEC. 2 Request these individuals tc report to the appropriate branch office. 3If the primary contact was not reached and the alternate was contacted to serve as Technical Communicator, then request the alternate to designate a Technical Support contact to respond to the appropriate branch office. / 6.1.11 Notify the designated technical support personnel to report.to the DNPEC if requested by the DNPLC Director. (See the DNP Notification Board.) 9 9 9' y. _4_ - _. - -.. _ _.. _ -.. _, ~ _ _. _,,. _..... _
DNPEC-IPD IP-5 ( Page 1 of 2 Rev. 6 BROWNS FERRY /BELLEFONTE NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM Turn on recording equipment Date Time Initials Call verified Site Emergency Director NOTIFICATION TO STATE OF ALABAMA /TVA EMERGENCY CENTER My name is TVA, Operations Duty Specialist.
- The Browns Ferry Bellefonte Nuclear Plant, Unit
( declared a: Notification of Unusual Event Alert Site Area Emergency General Emergency at CST (time of incident) on (date).
- (Initially, provide the above information. Request State Radiological Health Staff duty officer to call you back for detailed information.)
- ~ ::::::~::::::::::::::::::::::::~:!'*::::::::::::::::~ :~ ::::~
Brief description of the incident is: The plant ceadition is: Stable Deteriorating The reactor (did/did not) shut down at CST on (date)
- Revis. ion
- ~-
s-
~ _5_
DNPEC-IPD IP-5 Page 2 of 2 Rev. 6 (Continued) BROWNS FERRY /BELLEFONTE NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM The emergency situation: (a) Does Not Involve a Radiation Release from the Plant (b) Involves a Radiation Release From the Plant (c) Radiation Release Information is Not Known The radiation release is: (a) Ground Level - Airborne (b) Elevated - Airborne (c) Waterborne (d) Other The radiation release rate is: (a) Microcuries/Second (assumes noble gas / radio-(b) None iodine mixtwith 0.11% I at) (c) Unknown t The wind direction is from
- (degrees)
Wind speed m/s (meters per second) We recommend this protective action: (a) No protective action is recommended at this time (Noti-fication of Unusual EYent, Alert, Site Area Emergencies). (b) Activate the warning system and tune radio or TV to a local station. Advise the public to take shelter, and await further instructions (General Emergency). Emergency actions underway onsite are: (i.e., plan _t evacuation) Onsite support needed from offsite organization is: General Revision
- 3. ~~3
?- +
a DNPEC-IPD IP-S Page 1 of 2 Rev. 6 SEQUOYAH/ WATTS BAR NUCLEAR PIANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM Turn on recording equipment Date Time Initials Call verified Site Emergency Director NOTIFICATION TO STATE OF ALABAMA /TVA EMERGENCY CENTER My name is , TVA, Operations Duty Specialist.
- The Sequoyah Watts Bar Nuclear Plant, Unit t
declared a: Notification of Unusual Event Alert Site Area Emergency General Emergency at CST (time of incident) on (date).
- (Initially, provide the above information. Request State Radiological Health Staff duty officer to call you back for detailed infarmation.)
- ~2 :::::::: ~ ~22 :::::::::~! 2::~ ~ ::: ~ :~~ !!!!!!!!!!!!~!!~
Brief description of the incident is: $d 'I 2~'
- Revision -
4 DNPEC-IPD '^ IP-5 Page 2 of 2 Rev. 6 (Continued) SEQUOYAH/ WATTS BAR NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM The plant condition is: Stable Deteriorating The emergency situation: (a) Does Not Involve a Radiation Release from the Plant (b) Involves a Radiation Release From the Plant (c) Radiation Release Information is Not Known The radiation release is: (a) Ground Level - Airborne (b) Elevated - Airborne (c) Waterborne (d) Other The wind direction is from
- (degrees)
Wind speed mi/h (miles per hour) We recommend this protective action: (a) No protective action is recommended at this time (Noti-fication of Unusual Event, Alert, Site Area Emergencies). (b) Activate the warning system and tune radio or TV to a local station. Advise the public to take shelter, and await further instructions (General Emergency). General Revision ~8- --y y a .. _ ~. -- ,._u
AEP-IPO DNPEC - IP-6 DIVISION OF NUCLEAR POWER EMERGENCY CENTER PROCEDURE FOR ALERT, SITE EMERGENCY, AND GENERAL EfiERGENCY Prepared By: W. E. Webb, Jr. _ /\\ A\\ j Aw, Approved By: Date: 25/81 1V U Rev. No. Date Revised Pages Rev. No. Date Revised Pages MAR 2 41983 0 9/25/81 All 3 Au JUN 0 31983 AH 1 3/10/82 2,3,4 4 2 OCT 2.6_S82 All 13 The last page of this procedure is Number _W ,n..--. -n.-, --,.,n
,m DNPEC-IPD IP-6 Page 1 of 5 Rev. 4 1 DIVISION OF NUCLEAR POWER EMERGENCY CENTER PROCEDURE FOR ALERT, SITE AREA EMERGENCY, AND GENERAL EMERGENCY 1.0 PURPOSE This procedure is designed to direct the DNPEC Director and staff to ensure a consistent, accurate, and timely response in the event of an accident. This procedure further serves to identify the necessary information which the DNPEC must provide the CECC Director to ensure that prompt, accurate, public-protective action recommendations can be made by the CECC to appropriate State authorities. 2.0 SCOPE This procedure covers the actions of the DNPEC Director and staff during an Alert, Site Area Emergency, or General Emergency.
3.0 REFERENCES
Radiological Emergency Plan. 4.0 ABBREVIATIONS AND DEFINITIONS
- CECC - Central Emergency Control Center
- DNPEC - Division of Nuclear Power Emergency Center
- EDO - Emergency Duty Officer
- KEC - Knoxville Emergency Center
- NCO - Nuclear Central Office
- NUC PR - Division of Nuclear Power
- 0DS - Operations Duty Specialist l
- POTC - Power Operations Training Center
- SRO - Senior Reactor Operator
- REND - Radiological Emergency Notification Directory l
- TSC - Technical Support Center
,g 5.0 RESPONSIBILITIES 5.1 In the event of a radiological emergency classified as an Alert, Site Area Emergency, or General Emergency, the ODS calls the NUC PR EDO to act as DNPEC and CECC Director until he is relieved by the permanent CECC Director and DNPEC Director. The ODS is also responsible for contacting the DNPEC staff and having them report to the DNPEC. After contacting the EDO, the ODS contacts the DNPEC Director and requests that he report to the DNPEC.
- Addendum
^ -g l 1 I l l
.-.._,_....,m_ DNPEC-IPD IP-6 Page 2 of 5 Rev. 4 Upon his arrival at the DNPEC, the DNPEC Director relieves the EDO of his duties as acting DNPEC uirector. The DNPEC Director is responsibile for committing the support efforts of NUC PR to the affected plant. If NUC PR cannot fulfill the needs of the affected plant, the DNPEC Director has the authority to seek help from other divisions within TVA. The DNPEC Director is
- responsible for ensuring that the CECC is provided with periodic summaries of information needed for overall accident assessment.
5.2 DNPEC Staff The DNPEC staff is responsible for assisting the DNPEC Director in carrying out the DNPEC responsibilities in providing NCO technical support to the affected plant and to the CECC. An
- assignment of positions and duties of this staff as well as a
- description of augmenting support groups is described in
- attachment 1.
6.0 PROCEDURE REQUIREMENTS NOTE: The EDO will follow this procedure until relieved by the
- permanent DNPEC Director or his assistant. The permanent DNPEC Direc~ tor debriefs the EDO and continues with the procedure where the EDO left off.
6.1 Notifications 6.1.1 Verify that the ODS has contacted any requested technical support personnel. If technical support personnel are to be sent to the site by aircraft, verify that the ODS has made appropriate arrangements. 6.1.2 Notify the Site Emergency Director that the DNPEC is activated and obtain a current status report. 6.1.3 Review the emergency condition with the CECC Director. 6.1.4
- Ensure that the DNPEC Technical Communicator has
- established communications with the KEC and the division
- branch positions appropriately.
6.2 Accident Assessment 6.2.1 Verify that the electronic blackboard is manned and operational and is being kept current with the synoptics
- of the emergency.
- Revision
- Deletion
~ ? 2-' ~ 2
DNPEC-IPD IP-6 Page 3 of 5 Rev. 4 6.2.2 Verify that the key plant parameter lists are being transmitted to the DNPEC via telecopy, and are promptly distributed to the DNPEC staff, plant assessment team,
- and CECC (Plant Communicator's responsibility).
6.2.3
- Verify that the Plant Communicator is constructing and maintaining a current chronological key sequence of events. Ensure this information is transmitted to the CECC and KEC.
6.2.4
- Verify that the assessment team continually performs plant accident assessments and that they make prompt
- reports to the assistant DNPEC Director. Evaluations must be keyed to specific plant parameters.
- 6.2.5 The DNPEC Director shall ensure that accident assessment information is provided to the CECC on a frequent basis,
- (at a minimum, hourly). These assessments shall provide
- summary information on these items listed in attachment 2
- based on the last data transmittal from the plant.
- 6.2.6
- Ensure that current offsite assessment information is t *being provided by the CECC and transmitted to the TSC
- (EP&P Branch Representative's responsibility).
- 6.2.7 Potential Release Evaluation If after consultation with the CECC, the CECC Director requests that a predictive release avaluation be performed based on the potential for significant changes in plant conditions, the DNPEC shall provide the KEC the appropriate assumptions to be made pertaining to plant status for performing the necessary calculations. The areas to be considered are as follows:
a. Increased fuel failure (changes in primary coolant activity levels). b. Anticipated changes in primary coolant leakage rates or break sizes. c. Anticipated changes in containment leakage rates (i.e., changes in containment pressure and/or changes in size of containment ruptures or holes).
- Revision
- Deletion
-Qg h E 3
DNPEC-IPD IP-6 Page 4 of 5 ~ Rev. 4 6.3 General Operation 6.3.1 During the course of an emergency, should the accident upgrade, downgrade, or terminate, the DNPEC Director shall notify the KEC and CECC Directors immediately. 6.3.2 The DNPEC Director shall conduct periodic briefings for the entire DNPEC staff to update the emergency situation. 6.3.3 If available personnel and equipment of NUC PR are not enough to cope with the emergency, contact the designated representative of other TVA divisions, as necessary, to supply adequate resources to recover from the accident. Log the organizations called for assistance. A descrip-tion of services available and emergency contacts are available in the TVA Radiological Emergency Notification Directory (REND). 6.3.4 For a Site Area or General Emergency, the site should be reminded that additional technical personnel are available from the DNPEC to upgrade the technical support capability at the TSC. The DNPEC Director should discuss the need for this upgraded capability with the Site Emergency Director. Based upon this discussion, selected technical ssupport personnel may be dispatched by ground or air transportation.
- 6.3.5 For a Site Area or General Emergency the CECC Director will dispatch a senior division management representative to the site to act as Senior Advisor to the Site Emergency Director. This individual will advise the Site Emergency Director on TVA policy matters and act as an additional interface with the NRC as necessary. He will not control events or operations at the site.
- 6.3.6 The DNPEC Director will coordinate with the CECC Director i
the selection of one person to serve as a Technical Advisor to the Power Information Duty Officer in the CECC. The person will be responsible for providing a l nontechnical interpretation of the event for the CECC Information Office Staff. i I l
- 6.3.7 Relief of Duties--Should the accident be expected to last for an extended period, the DNPEC Director originates a schedule for relief. The duties of DNPEC Director should l
only be passed on to individuals identified as alternates for the DNPEC Director's position. However, for short periods of time, the DNPEC Director may delegate the
- Revision
- Addendum n!I 4
-e e., w DNPEC-IPD IP-6 Page 5 of 5 Rev. 4 7-authority of DNPEC Director to a member of the DNPEC staff until an alternate DNPEC Director can arrive. The DNPEC Director also directs his staff to prepare a schedule for their relief to ensure the necessary staff of the DNPEC is
- available for the duration of the emergency.
- 6.3.8 The DNPEC Director and staff will support the CECC Director as required for carrying out recovery efforts from the accident.
- 6.3.9 Upon termination of the emergency, the DNPEC Director and staff shall make themselves available for review of the accident.
i 1 T
- Revision
- Deletion
- O t
~ 5
DNPEC-IPD IP-6 Attac'hment 1 Page 1 of 5 t Rev. 4 ATTACHMENT 1
- DNPEC STAFF POSITIONS / SUPPORT FUNCTIONS 1.0 DNPEC STAFF 1.1 DNPEC Director 1.
Provides support services to the plant by utilizing all of the necessary manpower and equipment under the control of the division. 2. Ensures that employees who may be required to go to the affected plant are fully briefed prior to leaving, and know to whom they are to report. 3. Keeps the Site Emergency Organization informed of personnel ordered to the site and expected time of arrival. 4. Maintains periodic status reports and summaries of key events from the plant and provide this information to the CECC Director and other support organizations as needed. 5. Responsible to the CECC Director to ensure that he is kept periodically briefed (at a minimum, hourly) and provide the information pertaining to plant status described in attachment 2. This information will be used by the CECC for overall accident assessment (see attachment 4). 6. Requests assistance from other divisions, local agencies, government installations, or vendors, as needed. 7. Maintains contact with the Site Emergency Director and ensures that necessary support is provided. 8. Ensures that a sequence of key events is being maintained. This sequence of events is to be updated hourly. 1.2 Assistant DNPEC Director Responsible for managing the overall activities of the DNPEC 1. assessment team. ~W
- Addendum T.
6 .~.
DNPEC-IPD IP-6 Page 2 of 5 Rev. 4 ATTACHMENT 1 (Continued)
- DNPEC STAFF POSITIONS / SUPPORT FUNCTIONS 2.
Ensures that overall plant assessments are being periodically provided to the DNPEC Director. This assessment shall address, as a minimum, the conditions as shown in attachment 2 and shall be keyed to the last data transmittal from the plant. Protec-tive action recommendations shall be made to the DNPEC Director in accordance with the criteria established in attachment 2. The DNPEC Director will use the assessments and recommendations to brief the CECC Director. 3. Responsible for coordinating overall activities of the DNPEC and other division support activities as required. 1.3 Reactor Engineering Branch i 1. Directs Reactor Engineering Branch activities in support of the plant. 2. Responsible for providing periodic assessments of plant conditions to the DNPEC Director and Assistant Director. t 3. Provides logistics support as required to the DNPEC. 1.4 Technical Communicator (Position filled by either the Electrical and Instrument and Control or Mechanical Branch representative or their alternate.) 1. Maintains communications with other NUC PR technical branch representatives to keep them briefed of the emergency conditions and coordinates obtaining support from them as necessary. 2. Maintains communications with the KEC to keep them briefed of the emergency conditions and obtains support from the KEC as necessary. 3. Assists the DNPEC Director in other communications needs as necessary. 4. Responsible for ensuring the electronic board writer is kept current with a general sequence of events relevant to the incident.
- Addendum
'*Tb2 y l 7
DNPEC-IPD IP-6 Page 3 of 5 / Rev. 4 ATTACHMENT 1 (Continued)
- DNPEC STAFF POSITIONS / SUPPORT FUNCTIONS 1.5 Assessment Team 1.
The assessment team shall be made up of the following: Team leader - Reactor Engineering Branch Supervisor, a. NSSS Engineering and Analysis. b. Nuclear engineers (two minimum). At the discretion of the REB Representative and team leader: c. mechanical engineer, electrical engineer, Field Services engineer, instrument engineer, and/or an SRO from the POTC. 2. The assessment team leader will be activated automatically. He is responsible for activating the remainder of the required team members. 3. The assessment team shall provide a periodic assessment of sthe situation and input back to the site as appropriate via the DNPEC Director. 4. Shall develop for the DNPEC Director a periodic assessment of the items described in attachment 2. This assessment shall be updated hourly (minimum) for the DNPEC Director to brief the CECC Director. The assessment will be based on the last data transmittal from the plant. 5. Material, documents, etc. shall be available in the DNPEC for use by the assessment team. A list of this material is provided in attachment 3. 1.6 Plant Communicator 1. Maintain continuous communications with the site TSC. 2. Responsible for ensuring that the DNPEC assessment team is kept updated with the current plant conditions and coordinates obtaining additional information from the TSC as necessary for the assessment team. 3. Responsible for maintaining a detailed sequence of events during the emergency. This sequence of events shall be updated and provided to the DNPEC and CECC hourly.
- Addendum
~:P ~ 8 t
-. - ~. -. -. - DNPEC-IPD IP-6 Page 4 of 5 Rev. 4 ATTACHMENT 1 (Continued)
- DNPEC STAFF POSITIONS / SUPPORT FUNCTIONS 4.
Responsible for ensuring that information received via the telecopy machine, (i.e., plant parameter lists, etc.) is promptly distributed to the DNPEC Director, DNPEC staff, assessment team and the CECC as appropriate. 5. Assists the DNPEC with other communication needs with the site as necessary. 1.7 Emergency Preparedness and Protection (EP&P) Branch Representative 1. Directs the EP&P Branch activities in support of the plant. 2. Supports the DNPEC Director as required in coordinating emergency support actions with the site. 3. Assists, as necessary, the TSC Health Physics and Rad-Chem Supervisors in coordinating the performance of the predictive release rate model with the KEC and MSEC. 4. Responsible for providing current of fsite information, as provided by the CECC, to the TSC and for notifying the DNPEC Director when such information is updated. 5. Provides logistics support as required to the DNPEC. 1.8 Clerical Support 1. Operate CRT terminals. 2. Maintain log of events. 3. Operate Dimension Telephone System. 4. Maintain DNPEC organization board. 5. Operate telecopy machine. 6. Performs other duties as required by the DNPEC staff. 1.9 ODS 1. Provides for initial notification of all of fsite emergency organizations upon declaration of an emergency classifi-cation.
- Addendum Y
L 7' g
DNPEC-IPD IP-6 Page 5 of 5 Rev. 4 ATTACHMENT I (Continued)
- DNPEC STAFF POSITIONS / SUPPORT FUNCTIONS 2.
Notifies key DNPEC and CECC staff members which are required to report to the DNPEC and CECC. 3. Performs notifications to other organizations or personnel as requested by the DNPEC or CECC Directors. 1.10 Supporting NUC PR Branches Other branches within the division will be activated to support the DNPEC. These include: Electrical and Instrument and Controls Branch, Mechanical Branch, Field Services Branch, and Management Services Staff. Representatives from these branches will be activated along with activation of the DNPEC Staff. They will be requested to man their respective branch offices to coordinate support as required within their areas of expertise. 1.11 Technical Support The technical support group is composed of skilled professionals trained to provide plant support. The group consists of TVA central office employees in NUC PR. The technical support members provide expertise in reactor systems and core engineering, electrical engineering, mechanical engineering, chemical engineering, chemistry, shielding, transient analysis, fire protection, electrical distribution (inplant), security, metallurgy, radwaste, and instrumentation. The DNPEC Director delegates to the Technical Communicator the job of contacting these designated individuals by phone or through their respective branch contacts as needed. If necessary, technical support personnel may be sent to the plant. Transportation may be provided by helicopter or fixed-wing aircraft. 1.12 Supporting D'ivision If necessary, the DNPEC Director may obtain assistance from other divisions within TVA. 34
- Adde 6dum
{ 10
.. -,...., _ _..,. _-,..~. _ _. _.. DNPEC-IPD IP-6
- Attachment 2 Page 1 of 1 Rev. 4
- ATTAC10fENT 2 ACCIDENT ASSESSMENT CECC STATUS BOARD 1.
HEAT REMOVAL CAPABILITY: t i II. FUEL INTEGRITY: l III. RADIOACTIVITY IN CONTAINMENT: ? s IV. CONTAINMENT INTEGRITY: V. OVERALL ASSESSMENT: 1 i'
- Revision T'
L 3 11 .h 1 pr q.,., ---,,-,.mme,, ,,.w,, gr,. en.,, ,n .-,m-
-a DNPEC-IPD IP-6 Page 1 of 1 Rev. 4
- ATTACHMENT 3 DNPEC ASSESSMENT TEAM REFERENCE MATERIAL / EQUIPMENT Sequoyah FSAR Technical Specifications Emergency Operating Procedures Abnormal Operating Instructions PWR Systems Manuals Controlled Diagrams - Mechanical, Electrical, Logic, Piping Layout Offsite Dose Calculation Manual Browns Ferry FSAR Technical Specifications 1
Emergency Operating Procedures Abnormal Operating Instructions (These will be available when the new E0Ps are implemented) BWR Systems. Manuals Controlled Diagrams - Mechanical, Electrical, Logic, Piping Layout Technical Instruction - 47 Browns Ferry GEKs Common 10 CFR Steam Tables 2 HP 41 VC Calculators, 2 Card Readers, 2 Extra Chargers Key to Document Control Supplies - Paper, Pencils, Pencil Sharpener
- Adden.dum 9.
el .~,3 12
~.. _ DNPEC-IPD IP-6 Page 1 of 1 Rev. 4
- ATTACHMENT 4 INPUT FOR CECC ACCIDENT ASSESSMENT HEAT REMOVAL CAPABILITY FUEL SOURCE TERMS
- INTEGRITY CONTAINMENT INTEGRITY MET DATA RADIOACTIVITY IN CONTAINMENT FIELD SURVEY DATA w PLANT ASSESSMENT DOSE ASSESSMENT H KEC4-TSC IP-18 v v DNPEC MSECC h hd SITE EMERGENCY CECC DIRECTOR DIRECTOR v PROTECTIVE ACTION RECOMMENDATIONS mz '~ -~
- Revision 13
[ ~. Revision Log Sheet Revision Date: JUN 071983 This log sheet must be retained as the last page of the Division of Nuclear Power Emergency Center Implementing Procedures Document. Date Inserted: Inserted by: Pages to be Removed New Pages to be Inserted r-z Part Page Number Revision Part Page Number Revision IP-4 IP-4 Att. 2 1 of 2 6 Att. 2 1 of 2 7 IP-5 IP-5 Att. 2 1 of 2 6 Att. 2 1 of 2 7 l e O
DNPEC-IPD IP-4 Page 1 of 2 (~ Rev. 7 SEQUOYAH/ WATTS BAR NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM Turn on recording equipment Date Time Initials Call verified Site Emergency Director
- NOTIFICATION TO STATE OF TENNESSEE /TVA EMERGENCY CENTER My name is
, TVA, Operations Duty Specialist. The Sequoyah Watts Bar Nuclear Plant, Unit Notificat'on of Unusual Event Alert declared a: i Site Area Emergency General Emergency at CST (time of incident) on (date).
- (Initially, provide the above information. Request State duty officer to call you back for detailed information.)
Brief description of the incident is:
- Revision v,-
L 3? 2"
DNPEC-IPD IP-5 / Page 1 of 2 Rev. 7 SEQUOYAH/ WATTS BAR NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM Turn on recording equipment Date Time Initials __ Call verified Site Emergency Director
- NOTIFICATION TO STATE OF TENNESSEE /TVA EMERGENCY CENTER
, TVA, Operations Duty Specialist. My name is The Sequoyah Watts Bar Nuclear Plant, Unit declared a: Notification of Unusual Event Alert s ~ Site Area Emergency General Emergency at CST (time of incident) on (date).
- (Initially, provide the above information. Request State duty officer to call you back for detailed information.)
- ~ ::::::::::::::::::::::::::::::::::~::::::~::::: ~ ::::::~ ::::~~ :~
Brief description of the incident is:
- Revision ms t.
- r-
REP-IPD DNPEC IP-4 OPERATIONS DUTY SPECIALIST PROCEDURE FOR SITE EMERGENCY Prepared By: W. E. Webb, Jr. r-Approved By: k Il \\_Lw Date: 9/2s/81 .u s Rev. No. Da te Revised Pages Rev. No. Da te Revised Pages All 3 o _. __ 9/2JJJ1._ 2/3/83 2 1 , 3(10/82 __,2,,3 4 2/24/83 2 ??"i ' 'f q3 2 OCT 2 6. 08CA11 5 311 Rev. No. Date Revised Pages Rev. No. Date Revised Pages JUN 0 31383 311 g JUN 071983 Act. 2, p. 1 7 The last page of this procedure is 8 4
me 9 hr+-w$ REP-IPD DNPEC - IP-5 OPERATIONS DUTY SPECIALIST PROCEDURE FOR GENERAL EMERGENCY Prepared By: W. E. Webb, Jr.3 Approved By: Date: 9/25/81 u JJ Rev. No. Date _Revjsed Pages Rev. No. Date Revised Pages 9/25/81 All 3 2/3/83 2 n 1 3/10/82 2, 3 __ _t. 2124283._. 1 2 OCT 21$82 m 5 U R 17i?03 ni Rev. No. Date Revised Pages Rev. No. Date Revised Pages 6 JUN 031983 n1 JUN0? EAct. 2, p. 1 7 The last page of this procedure is 8 m: ?,
( Revision Log Sheet Revision Date: JUL 071983 This log sheet must be retained as the last page of the Division of Nuclear Power Emergency Center Implementing Procedures Manual. Inserted by: Date Inserted: Pages to be Removed New Pages to be Inserted Part PagetNumber Revision Part Page Number Revision s Table of 1 of 1 1 Table of 1 of 1 2 Contents Contents IP-2 Cover Page 5 IP-2 Cover Page 6 Att. 2 1 of 2 5 Att. 2 1 of 2 6 IP-3 Cover Page 6 IP-3 Cover Page 7 3 of 4 6 3 of 4 7 IP-4 Cover Page 7 IP-4 Cover Page 8 3 of 4 6 3 of 4 8 IP-5 Cover Page 7 IP-5 Cover Page 8 3 of 4 6 3 of 4 8 IP-6 Cover Page 4 IP-6 Cover Page 5 3 of 5 4 3 of 5 5 Att. I 2 of 5 4 Att. 1 2 of 5 5 4 of 5 4 4 of 5 5 Att. 5 1 of 1 5 IP-7 Cover Page (reflects IP-7 Cover Page O deletion) 1 of 2 0 2 of 2 0 Att. 1 1 of 1 0 Att. 2 1 of 1 0 Att. 3 1 of ' 0 'E L -?
DNPEC-IPD Table of Contents Page 1 of 1 Rev. 2 / TABLE OF CONTENTS DIVISION OF NUCLEAR POWER EMERGENCY CENTER PROCEDURES IP-1 Operations Duty Specialist - Transportation Accident Involving a Shipment of Radioactive Waste from a TVA Facility IP-2 Operations Duty Specialist - Notification of an Unusual Event IP-3 Operations Duty Specialist - Alert IP-4 Operations Duty Specialist - Site Area Emergency IP-5 Operaticas Duty Specialist - General Emergency IP-6' Division of Nuclear Power Emergency Center - Alert, Site Area Emergency, or General Emergency IP-7
- Performance of Assessment Team Function IP-8 Division of Nuclear Power Emergency Center (DNPEC) Training Requirements l
l l k L 2"
REP-IPD DNPEC - IP-2 OPERATIONS DUTY SPECIALIST ~ PROCEDURE FOR NOTIFICATION OF UNUSUAL EVENT Prepared By: W. E. Webb, Jr. Approved By: sw Da te: /2s/s1 " J s Rev. No. Da te Revised Pages Rev. No. Date Revised Pages 0 9/15181 All 3 2/3/83 2 1 3/10/82 2 4 MAR 171983 n1 2 OCT ?.61982 All s JUN 0 31983 4 - 7 Rev. No. Date Revised Pages Rev. No. Date Revised Pages JUL 071983 Act. 2-o. 1 6 , +- -
DNPEC-IPD IP-2 Page 1 of 2 Rev. 6 f'- ' SEQUOYAH/ WATTS BAR NUCLEAR PLANTS OPERATIONS DUTY SPECIALIST INCIDENT FORM Turn on recording equipment Date Time Initials Call verified Site Emergency Director NOTIFICATION TO STATE OF TENNESSEE /TVA EMERGENCY CENTER My name is , TVA, Operations Duty Specialist.
- The Sequoyah Watts Bar Nuclear Plant, Unit declared a:
Notification of Unusual Event Alert Site Area Emergency General Emergency at CST (time of incident) on (date). (Initially, provide the above information. Request State duty officer to call you back for detailed information.)
- ~ ::::::::::::::::::::::~ :::::~ 2~ :::::::::::
Brief description of the incident is: l I l l l l t I i
- Revision l
---*4 2"* I i l
i s REP-IPD DNPEC - IP-3 OPERATIONS DUTY SPECIALIST PROCEDURE FOR ALERT Prepared By: W. E. We_bb, Jr. Approved By: kM b Da te: g/2s/si v v s Rev. No. Da te Revised Pages Rev. No. Date Revised Pages All 3 2/3/83 2 0 9/_2.2131 1 3/10/82 '2. 3 4 2/24/83 3 2 OCT 2EJ982 AH 3 MAR 171983 411 Rev. No. Date Revised Pages Rev. No. Date Revised Pages JUN 0 31983 Au 6 7 JUL 071983 3 v,s y / \\ w, v-
DNPEC-IPD IP-3 Page 3 of 4 Rev. 7 f' t / 6.1.6 Notify the DNPEC Director and have him report to the center. Ask the DNPEC Director who should be contacted as DNPEC Technical Communicator; Electrical and Instrument and Controls or Mechanical Branch representative. Determine if the DNPEC Director considers it necessary to call any technical support personnel at this time. If requested to do so, notify them last (see section 6.1.10). (See the DNP Notification Board.) / 6.1.7 Notify the KEC Duty Officer and have him activate the KEC, if required. (See the DNP Notification Board.) / 6.1.8 Notify the Load Coordinator of the condition. / 6.1.9 Notify the key DNPEC staff (see the DNP Notification
- Board). Tell each person contacted what position he is
- reporting for.
Key DNPEC Staff 2Management Services (request that he provide appropriate clerical support and an electronic board writer for the DNPEC and CECC) 1 Plant Communicatcr 1 Assistant Director (a DNPEC Director alternate) 1Reactor Engineering t 1Technical Communicator (designated by the DNPEC Director as either Electrical and Instrument and Controls ar Mechanical Branch) 1A::essment Team Leader (BWR - Browns Ferry, PWR - Sequoyah or Watts Bar) 1Emergency Preparedness and Protection 2.sMechanical (if primary.epresentative was contacted as Technical Communicator, contact the designated e alternate) 2 sElectrical and Instrument and Controls (if primary representative was contacted as Technical Communi-cator, contact the designated alternate) 2 Field Services NOTE: 1Request these individuals to report to the DNPEC. 2 Request these individuals to report to the appropriate branch office. 3 If the primary contact was not reached, and the alternate was contacted to serve as Technical Communicator, then request the alternste to designate a Technical Support contact to respond to the appropriate branch office. Contact that person and have him resporvi.
- Revision u
Wp e' h ( n - - - - -, -, ~.- .------e ---,,-s
REP-IPD DNPEC - IP-4 OPERATIONS DUTY SPECIALIST PROCEDURE FOR SITE EMERGENCY ~ Prepared By: W. E. Webb, Jr. ApprovedBy:k 1]h Date: 9/25/81- " V t Rev. No. Da te Revised Pages Rev. No. Da te Revised Pages All 3 2/3/83 _2 0 9/JJfjl 1 3/10/82 2, 3 - 4 2/24/83 2 ER 1,71983 n 2 OCT ?JLS82 All 5 Rev. No. Date Revised Pages Rev. No. Date Revised Pages JUN 031983 n1 a JUN 071983 Act. 2, o. 1 7 JUL 071983 3 s m e
DNPEC-IPD IP-4 Page 3 of 4 Rev. 8 l / 6.1.5 Notify the CECC Director and have him report to the center. (See the DNP Notification Board.) / 6.1.6 Notify the DNPEC Director and have him report to the center. Ask the DNPEC Director who should be contacted as DNPEC Technical Communicator; Electrical and Instrument and Controls or Mechanical Branch representative. Determine if the DNPEC Director considers it necessary I to call any technical support personnel. If requested to do so, notify them last (see section 6.1.10). (See the DNP Notification Board.) / 6.1.7 Notify the KEC Duty Officer and have him activate the KEC. (See the DNP Notification Board.) / 6.1.8 Notify the Load Coordinator of the condition. / 6.1.9 Notify the key DNPEC staff (see the DNP Notification
- Board). Tell each person contacted what position he is
- reporting for.
Key DNPEC Staff 2 Management Services (request that he provide appropriate clerical support and an electronic board writer for s DNPEC and CECC) 1 Plant Communicator 1 Assistant Director (a DNPEC Director alternate) 1 Reactor Engineering 1 Technical Communicator (designated by the DNPEC Director as either Electrical and Instrument and Controls or Mechanical Branch) 1 Assessment Team Leader (BWR - Browns Ferry, PWR - Sequoyah or Watts Bar) 1 Emergency Preparedness and Protection 2 sNechanical (if primary representative was contacted as Technical Communicator, contact the designated i alternate) 2 sElectrical and Instrument and Controls (if primary representative was contacted as Technical Communicator, contact the designated alternate) 2 Field Services NOTE: 1Request these individuals to report to the DNPEC. 2 Request these individuals to report to the appropriate branch office. 8If the primary contact was not reached and the alternate was contacted to serve as Technical Communicator, then request the alternate to designate a Technical Support contact to respond to the appropriate branch office. Contact that person and have him respond.
- Revision i
t "L< ~ [ ~.. _ _. _., _ _ _ _., -. _
REP-IPD DNPEC - IP-) OPERATIONS DUTY SPECIALIST PROCEDURE FOR GENERAL EMERGENCY Prepared By: W. E. Webb. Jr. n Approved By: \\..I Date-9/25/81 g u Rev. No. Date Revised Pages Rev. No. Date Revised Pages 9/25/81 All 3 2/3/83 2 n 1 3/10/82 2, 3 2424483 1 2 OCT 2 8 m m 5 MAR 17 883 All Rev. No. Date Revised Pages Rev. No. Date Revised Pages 6 JUN 031983 All JUN 0 7,g83 ee. 2, p. 4 1 7 JUL 071983 3 8 ml
DNPEC-IPD IP-5 Page 3 of 4 Rev. 8 Ensure the following recommended protective action is given: "TVA recommends that you activate the warning system and advise the public to take shelter, tune radio or TV to a local station, and await further instructions." / 6.1.4 Notify the DNP EDO. (See the DNP Notification Board.) / 6.1.5 Notify the MSEC Director and have him activate the MSEC. (See the DNP Notification Board.) / 6.1.6 Notify the CECC Director and have him report to the center. (See the DNP Notification Board.) / 6.1.7 Notify the DNPEC Director and have him report to the center. Ask the DNPEC Director who should be contacted as DNPEC Technical Communicator; Electrical and Instrument and Controls or Mechanical Branch representative. Determine if the DNPEC Director considers it necessary to call any technical support personnel at this time. If requested to do so, notify them last (see section 6.1.11). (See the DNP Notification Board.) / 6.1.8 Notify the KEC Duty Officer and have him activate the KEC. (See the DNP Notification Board.) / 6.1.9 i Notify the Load Coordinator of the condition. / 6.1.10 Notify the key DNPEC staff (see the DNP Notification
- Board). Tell each person contacted what position he is
- reporting for.
Key DNPEC Staff 2 Management Services (request that he provide appropriate clerical support and an electronic board writer for the DNPEC and CECC) 1 Plant Communicator 1 Assistant Director (a DNPEC Director alternate) 1Reactor Engineering 1 Technical Communicator (designated by the DNPEC Director as either Electrical and Instrument and Controls or Mechanical Branch) 1 Assessment Team Leader (BWR - Browns Ferry, PWR - Sequoyah or Watts Bar) 1Emergency Preparedness and Protection 2,3 Mechanical (if primary representative was contacted as Technical Communicator, contact the designated alternate) 2,3 Electrical and Instrument and Controls (if primary representative was contacted as Technical Communicator, contact the designated alternate) 2 Field Services 3
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,e i REP-IPD ONPEC - IP-6 DIVISION OF NUCLEAR POWER EMERGENCY CENTER PROCEDURE FOR ALERT, SITE EMERGENCY, AND GYNERAL EMERGENCY Prepared By: W. E. Webb, Jr., Approved By: AA\\ j s A w, Date: 25/8_1 U U Rev. No. Da te s Revised Pages Rev. No. Date Revised Pages 0 9/25/81 All MAR 241983 3 n1 1 3/10/82 2,3,4 4 JUN 031983 nr 2 nCT 2 E_S82 All 5 3, Att. 1--p.2,4; Att. 5--p. 1 ma
DNPEC-IPD IP-6 Page 3 of 5 Rev. 5 6.2.2 Verify that the key plant parameter lists are being transmitted to the DNPEC via telecopy, and are-promptly distributed to the DNPEC staff, plant assessment team, and CECC (Plant Communicator's responsibility). 6.2.3 Verify that the Plant Communicator is constructing
- and maintaining a current chronological sequence of
- events. Ensure this information is updaced and transmitted
- to the DNPEC, CECC, and KEC staffs, hourly.
- 6.2.4 The Reactor Engineering Branch representative is responsible for identifying and maintaining a sequence of " key" events.
This sequence of key events shall be updated and transmitted to the CECC, hourly. He also assists the DNPEC director in identifying "significant" events which will be provided to the CECC sooner than hourly.
- 6.2.5 Verify that the assessment team continually performs plant accident assessments and that they make prompt reports to the assistant DNPEC Director. Evaluations must be keyed to specific plant parameters.
- 6.2.6 The DNPEC Director shall ensure that accident assessment information is provided to the CECC on a frequent basis, (at a minimum, hourly). These assessments shall provide
'~ sammary information on these items listed in attachment 2 based on the last data transmittal from the plant.
- 6.2.7 Encu're that current offsite assessment information is being provided by the CECC and transmitted to the TSC (EP&P Branch Representative's responsibility).
- 6.2.8 Potential Release Evaluation If after consultation with the CECC, the CECC Director requests that a predictive release evaluation be performed based on the potential for significant changes in plant conditions, the DNPEC shall provide the KEC the appropriate assumptions to be made pertaining to plant status for performing the necessary calculations. The areas to be considered are as follows:
Increased fuel failure (changes in primary coolant a. activity levels). b. Anticipated changes in primary coolant leakage rates or break sizes. f Anticipated changes in containment leakage rates I c. (i.e., changes in containment pressure and/or changes in size of containment ruptures or holes).
- Revision
- Addendum v,:
2"
DNPEC-IPD IP-6 Page 2 of 5 (~ Rev. 5 ATTACHMENT 1 (Continued) DNPEC STAFF POSITIONS / SUPPORT FUNCTION,S i 2. Ensures that overall plant assessments are being periodically provided to the DNPEC Director. This assessment shall address, as a minimum, the conditions as shown in attachment 2 and shall be keyed to the last data transmittal from the plant. Protec-tive action recommendations shall be made to the DNPEC Director in accordance with the criteria established in attachment 2. The DNPEC Director will use the assessments and recommendations to brief the CECC Director. 3. Responsible for coordinating overall activities of the DNPEC and other division support activities as required. 1.3 Reactor Engineering Branch I 1. Directs Reactor Engineering Branch activities in support of the plant.
- 2.
Maintains a sequence of " key" events. Ensures this sequence is updated hourly and provided to the CECC. Items of " significance" will be provided to the CECC sooner than hourly.
- 3.
Responsible for providing periodic assessments of plant conditions to the DNPEC Director and Assi'stant Director.
- 4.
Provides logistics support as required to the DNFEC. 1.4 Technical Communicator (Position filled by either the Electrical and Instrument and Control or Mechanical Branch representative or their alternate.) 1. Maintains communications with other NUC PR technical branch representatives to keep them briefed of the emergency + conditions and coordinates obtaining support from them as necessary. 2. Maintains communications with the KEC to keep them briefed of the emergency conditions and obtains support from the KEC as necessary. 3. Assists the DNPEC Director in other communications needs as necessary. 4. Responsible for ensuring the electronic board writer is kept carrent with a general sequence of events relevant to the incident.
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--,j
- Addendum g
. -.. - = -
DNPEC-IPD IP-6 Page 4 of 5 g-Rev. 5 ATTACHMENT 1 (Continued) DNPEC STAFF POSITIONS / SUPPORT FUNCTIONS 4. Responsible for ensuring that information received via the telecopy machine, (i.e., plant parameter lists, etc.) is promptly distributed to the DNPEC Director, DNPEC staff, assessment team and the CECC as appropriate. 5. Assists the DNPEC with other communication needs with the site as necessary. 1.7 Emergency Preparedness and Protection (EP&P) Branch Representative 1. Directs the EP&P Branch activities in support of the plant. 2. Supports the DNPEC Director as required in coordinating emergency support actions with the site. 3. Assists, as necessary, the TSC Health Physics and Rad-Chem Supervisors in coordinating the performance of the predictive release rate model with the KEC and MSEC. 4. Responsible for providing current offsite information, as provided by the CECC, to the TSC and for notifying the DNPEC Director when such information is updated. 5. Provides logistics support as required to the DNPEC.
- 6.
Notifies property or liability insurance carrier contact for Alert, Site Area Emergency.. General Emergency, and during any nuclear emergency exercise (see attachment 5). 1.8 Clerical Support 1. Operate CRT terminals. 2. Maintain log of events. 3. Operate Dimension Telephone System. 4. Maintain DNPEC organization board. 5. Operate telecopy machine. 6. Performs other duties as required by the DNPEC staff. 1.9 ODS 1. Provides for initial notification of all offsite emergency organizations upon declaration of an emergency classifi-cation. 4 y T
- Addendum i
r,,. -,1-
DNPEC-IPD IP-6 /.. Page 1 of I Rev. 5 s
- Attachment 5 Insurance Carrier Contact The Emergency Preparedness and Protection Branch Representative should call the appropriate ANI insurance carrier in the event of a reportable accident.
An accident is reportable when an Alert, Site Area Emergency, or General Emergency has been declared. The carrier should also be notified of any nuclear piant emergency exercise. Browns Ferry: . Property Insurance Carrier Contact - (non-nuclear accident) (809) 295-5447 Nuclear Mutual Limited Liability Insurance Carrier Contact - (nuclear accident) (203) 677-7305 American Nuclear Insurers Sequoyah: Property Insurance Carrier Contact - (non-nuclear accident) (800).243-3172 American Nuclear Insurers [ Liability Insurance Carrier Contact - (nuclear accident) (203) 677-7305 American Nuclear Insurers Watts Bar: Liability Insurance Carrier Contact (nuclear accident) (203) 677-7305 American Nuclear Insurers Bellefonte: Liability Insurance Carrier Contact (nuclear accident) (203) 677-7305 American Nuclear Insurers
- Addendum 9
r REP or IPD Cover Page DNPEC - IP-7 Ph0CEDURE FOR PERFORMANCE OF ASSESSMENT TEAM FLHCTION Prepared by: R. E. Alaun Approved by: W. u
== 'JUL 0 h1983 Date: Rev. No. Date Revised Pages s \\.. W, J 9 T c ,,,-..---ge,---,
DNPEC-IPD IP-7 Page 1 of 2 Rev. 0 ( .s DIVISION OF NUCLEAR POWER EMERGENCY CENTER PROCEDURE FOR PERFORMANCE OF ASSESSMENT TEAM FUNCTION 1.0 PURPOSE This procedure is designed to outline in general terms the role of the assessment team during an Alert, Site Area Emergency, or General Emergency. 2.0 SCOPE This procedure covers the notification of and the actions taken by the assessment team.
3.0 REFERENCES
Radiological Emergency Plan s 4.0 ABBREVIATIONS AND DEFINITIONS ATL - Assessment Team Leader BWR E&A - Boiler Water Reactor Engineering and Analysis Section CECC - Central Emergency Control Center HDNPEC - Division of Nuclear Power Emergency Center EDO - Emergency Duty Officer PWR E&A - Pressurized Water Reactor Engineering and Analysis Section REB - Reactor Engineering Branch TSC - Technical Support Center 5.0 RESPONSIBILITIES 5.1 In the event of a radiological emergency classified as an Alert, Site Area Emergency, or General Emergency, either the PWR E&A or the BWR E&A ATL will be notified, depending on which plant is affected. The ATL will determine if other REB nuclear engineers are required and refer to the duty team roster as needed. He will also contact other branch representatives as needed for their support. f 2"*
DNPEC-IPD IP-7 Page 2 of 2 Rev. 0 5.2 Once the ATL and/or the Assessment Team are assembled in the DNPEC they will evaluate all previous telecopied information, the electronic blackboard, and discuss the key plant events with the Plant Communicator and REB representative (if he has arrived at the DNPEC) or the EDO or DNPEC director (if REB representative has not arrived at the DNPEC) to ensure they have received all the information necessary to provide the initial plant assessment. Attachment 1 (to be determined) provides a methodology to be used as guidance in performing this assessment. This assessment is formalized by completing attachment 2. 5.3 Preparation of the plant assessment shall be keyed to the specific plant parameters listed on telecopies from the plant TSCs. The assessment team will draw on their knowledge of FSAR, E0Is, owners' group work, analytical basis for accident analyses, and communications between the TSC and plant communicator in preparation of the plant assessment. provides a list of reference material / equipment which is maintained in the DNPEC-Assessment Team area. A TSC communicator shall be available to answer all the Assessment Team's questions at all times. The plant assessment serves to inform the DNPEC Director with the plant status. It also enables the DNPEC director to communicate with the CECC Director in planning offsite emergency actions with the intent of informing the State through the CECC of the status of the plant and the implications of that status. 5.4 Subsequent to the initial plant assessment, plant evaluations shall be completed using the latest telecopied information from the TSC. These assessments shall be updated hourly (minimum). To the extent possible, the Assessment Team will serve as an engineering reference for the plant. They will reply to plant inquiries to the best of their ability based on the telecopied plant parameters and information provided by the TSC Communicator. Gross predictive actions may be required for offsite emergency planning. If possible, the l change in plant status will be addressed (e.g., the plant's status is improving or the plant's status is degrading). [ l 1 l l I
DNPEC-IPD IP-7 c Page 1 of 1 Rev. O Sample of Methodology That can be Used by Assessment Team (To be determined) 1 \\ -98 T,
DNPEC-IPD IP-7 [. Page 1 of 1 Rev. O ATTACHMENT 2 ACCIDENT ASSESSMENT CECC STATUS BOARD I. HEAT REMOVAL CAPABILITY: II. FUEL INTEGRITY: / III. RADIOACTIVITY IN CONTAINMENT: IV. CONTAINMENT INTEGRITY: i V. OVERALL ASSESSMENT: l d L amv. +- -,y-e-w.- em- -.,,-,a w + t--- w-- t e -e--. e-m -- - - -- -- r -r- - - - -
l DNPEC-IPD IP-7 /* Page 1 of 1 Rev. O ATTACHMENT 3 DNPEC ASSESSMENT TEAM REFERENCE MATERIAL / EQUIPMENT Sequoyah FSAR Technical Specifications Emergency Operating Procedures Abnormal Operating Instructions PWR Systems Manuals Controlled Diagrams - Mechanical, Electrical, Logic, Piping Layout Offsite Dose Calculation Manual Browns Ferry 'FSAR Technical Specifications Emergency Operating Procedures Abnormal Operating Instructions (These will be available when the new E0Ps are implemented) BWR Systehs Manuals Controlled. Diagrams - Mechanical, Electrical, Logic, Piping Layout Technical Instruction - 47 Browns Ferry GEKs Comunen 10 CFR Steam Tables 2 HP 41 VC Calculators, 2 Card Readers, 2 Extra Chargers Key to Document Control Supplies - Paper, Pencils, Pencil Sharpener G Y ? L i . - ~
.. _ -._ _ ~ -... _.. 4 b REVISION LOG SilEET Revision Date: JUL 011983 ,s [ Tli ts log,8heet must he retained ar. tlic la:a i.a; e of the Knoxville Emergency Center Implementing Procedures Document. Inserted by: Date inserted: =- I Pages to be Removed New Pages to be Inserted t \\ ....--. t e..N.u.:a.b_er Revi s t.an Pa Part --.Pa t e. Number Rev.i.n t..on... Part 3-3 of 3 0 3 of 3 0 Appendix A 1 of 79 0 Appendix A 1 of 79 1 s Appendix B 1 of 53 0 Appendix B 1 of 53 0 2 of 53 0 2 of 53 1 5 of 53 0 5 of 53 0 6 of 53 0 6 of 53 1 l. Appendix C 2 of 50 0 Appendix C 2 of 50 0 3 of.50 0 3 of 50 1 i 5 ef 50 0 j 6 of 50 0 7 of 50 0 7 of 50 1 12 of 50 0 12 of 50 1 1 13 of 50 0 13 of 50 0 i I 6 l 4 i I 1 i I l ...g. s i. q i r, .,. _. _,.. -, -. -,, - ~ ~.... -..,. -., -.. _,. _,..... - -.., _ _ _ .-.....,,,-.--,-m .--.w..
l I EC-IPD KEC IP-6 K_EC OPERATING PROCEDURES Prep. red by: M*.I.,/ Mol [ Reviewed by: A Approved by JFEB 2 31983 D.te: Revision Log Rev No. Date Revised Pages JUL 011983 Appendix A - 1 of 79, Appendix B - 2 and 6 1 C3. AnnonA4v c-1 7 mna 12 of 50 s s. 4
KEC-IpD IP-6 Page 3 of 3 Rev. O g 2. CONTAINMENT LEAKAGE Radioactive gas leakage from containment can be expected to vary with the pressure drop across the containment walls. Containment leak tests are not considered adequate to establish this relationship, nor is it likely that a simple relationship would be found even if adequate data were available. For purposes of this plan, it is assumed that containment leakage is described by a simple orifice equation; the curves shown for containment leak rate versus pressure are based on this equation. These curves are included only for making predictions, since the calculated releases assume a leak rate from containment. 3. SAFETY SYSTEMS The final step in determinin3 the radioactivity releases following an accident considers the operation of engineered safety features. The calculations in this procedure take account of the possible locations where leakage could occur, as well as airflow patterne established af ter these e. -tred safety features start operation. METHODOLOGY The TVA method for predicting releases of radioactivity to the environment is based on evaluation of plant conditions (actual, suspected, or postulated) and comparison with a range of calculated resulta for certain assumed conditions. (The assumed conditions range from a best estimate or expected value to a '5 worst case" value.) The parameters examined are primary coolant E# activity, radioactivity dis:harge to containment, and Icakage from containment. The effects of engineered safety features on releases are taken into account. The calculated results are reduced to graphical form which facilitates interpolation and projection. l L 3 y
KEC-IPD IP-6 Appendix A Page 1 of 79 Rev. 1 TVA Predictive Model Appendix A - BFN 1.0 PLANT PARAMETERS REQ'JIRED FOR RELEASE RATE CALCULATION 1.1 Determine which isotope spectrum to use based on the latest primary coolant measurement. 1.1.1 On worksheet 1-A record the latest measured primary coolant activity (per SI 4.6.B or postaccident measurement) and calculate the activity ratios. 1.1.2 On Table 1.1, circle the entries corresponding to the ratios calculated in 1.1.1. Circle the isotope spectrum on the line with the most circled entries. 1.1.3 Check the spectrum circled in step 1.1.2. This isotope spectrum will be used in all steps of 1.0 and 2.0 of this procedure. IMPORTANT: A POWER CHANGE OF MORE THAN 15 PERCENT WIT 111N 2-3 HOURS BEFORE THE PRIMARY COOLANT SAMPLE WAS TAKEN INVALIDATES THE RATIOS INVOLVING IODINE (I). IN SUCH A CASE, RELY ON THE C/S RATIO. 1.2 Determins normalization factor The information labeled "NUREG-0016" is based on that amount of
- failed fuel which produces an off-gas release rate of 30,000 pCi/s at 30 minute decay. The " Modified TID-14844" information is based on 1.0 x 10 6 percent of the total radioactivity inventory of an equilibrium reactor core.
1.2.1 On worksheet 1-A, circle the column of calculated specific activities for the isotopes I-131, CS-137, and Sr-92 given in Table 1.2 for the isotope spectrum chosen in step 1.1.3. 1.2.2 Calculate anc record the ratio of the measured specific activity (from step 1.1.1) to the circled calculated values in Table 1.2. 1.2.3 Select a normalization factor corresponding most closely to two of the three ratios. Record this on worksheet 1-A, step 1.2.3. 1 1.3 Determine primary system break size Use worksheet 1-B. Record the readings of radiation monitors RE-90-171A and RE-90-273A (drywell radiation) and RE-9G-272B and RE-90-273B (torus radiation). Also record date and time at which readings were taken. It should be noted that all radiation monitor readings are assumed to be background subtracted before being used in this predictive model. Readings taken immediately prior to tne accident should be used as the background values if available. This applies to effluent as well as area monitors. -jf xRevisfon
KEC-EPD IP-6 Appendix B Page 1 of 53 /~ Rev. 0 auf TVA Predictive Model Appendix B - SQN 1.0 P1 ANT PARAMETERS REQUIRED FOR RELEASE RATE CALCULATION 1.1 Determine which isotope spectrum to use based on the latest primary coolant measurement. 1.1.1 On Worksheet 1-A record the latest measured primary coolant activity (per SI-54 or postaccident measurement) and calculate the activity ratios. 1.1.2 on Table 1.1, circle the entries corresponding to the ratios calculated in 1.1.1. 1.1.3 On Table 1.1, circle the isotope spectrum on the line with the most circled entries. This isotope spectrum will be used in all steps of 1.0 and 2.0 of this procedure. IMPORTANT: A POWER CHANGE OF MCRE THAN 15 PERCENT WITHIN 2-8 HOURS BEFORE THE PRIMARY COOLANT SAMPLE WAS TAKEN INVALIDATES THE RATIOS INVOLVING IODINE (1). IN SUCH A CASE, RELY ON THE C/R RATIO. 1.2 Determine Normalisation Factor ar 8 The information labeled " Expected" and " Design" is based on 1 percent failed fuel; the " Modified TID-14844" information is based on 1 percent of the total radioactivity inventory of an equilibrium reactor core. 1.2.1 On Worksheet 1-A, circle the calculated specific activities for each of the isotopes (I-131, Cs-137, Rb-88) given in Table 1.2 for the isotope spectrum chosen in 1.1.3. 1.2.2 Calculate and record the ratio of the measured specific activity (from step 1.1.1) to the circled calculated values of Table 1.2. 1.2.3 Select a normalization factor corresponding most closely to two of the three ratios. Record this on worksheet 1-A, step 1.2.3. Notes For " Expected" and " Design" isotope spectra, the normalization factor corresponds to the failed fuel fraction; for the " Modified TID-14844" spectrum, the normalization factor corresponds to the percentage of equilibrium core inventory. 1.3 Determine primary coolant leak rate into containment. Use worksheets 1-B and 1-C. Record readings of radiation monitors RM-90-100, RM-90-112, RM-90-106. If RM-90-112 and/or RM-90-106 readings are off-scale, record RM-90-2. Record the time the readings are taken. It should be noted that all radiation monitor readings are assumed to be background subtracted before being used in this predictive model. Readings taken immediar.ely prior to the accident should be used as the background values if available. This applies to effluent as well as area monitors. f:3
, - ~. -... -.. -... - - _., KEC-IPD IP-6 Appendix B Page 2 of 53 Rev. I 1.3.1
- Convert CPM readings to pCi/cc by multiplying the monitor
- readings by the conversion factor of 2.8 x 10 8 pCi/ce/ cpm.
1.3.2 Calculate the elapsed time from reactor shutdown to the reading of monitor readings. If both radiation monitors RM-90-112 and RM-90-5D6 readings are 1.3.3 off-scale, skip to 1.3.7; otherwise, continue with 1.3.4. 1.3.4 From the latest detector efficiency verification (TI-18, Worksheet 18-C-1B) calculate the ratio of Xe-133 cpm to total cpm for RM-90-112, RM-90-106. 1.3.5.a Calculate the Xe-133 specific activity in upper containment by multiplying radiation monitor RM-90-106 reading by its Xe-133/ total ratio. 1.3.5.b Calculate the Xe-133 specific activity in lower containment by multiplying radiation monitor RM-90-106 reading by its Xe-133/ total ratio. 1.3.6 Determine the primary coolant leak rate into Icwer containment as follows: \\ a. For isotopic spectrum: Expected - Use Figure B.1-a. Design - Use Figure B.1-b. Modified TID-14844 - Use Figure B.1-c. b. Normalize the measured Xe-133 epecific activity by dividing by the normalization factor determined in step 1.2.3. Using the elapsed time from step 1.3.2, estimate a primary c. coolant leak rate by visually interpolating between the curves in Figure B.1. Record on worksheet 1-C the value of the specific activity from the curves above and below the normalized measured value. d. If the reading from RM-90-106 only is off-scale, use Figures B.2-a, B.2-b, or B.2-c and the RM-90-112 reading. Then repeat steps 1.3.6 a through c. e. Record on Worksheet 1-C the estimated primary coolant leak rate. 1.3.7 If the readings for both RM-90-106 and RM-90-112 are off-scale, do the following: Select Figure B.3-a, B.3-b, or B.3-c depending on the isotope a. 2-spectrun' chosen.
- Revision
KEC-IPD IP-6 Appendix B Page 5 of 53 Rev. O r W If the isotope spectrum is " Design," do not increase the normalisation factor to more than 15; instead, change the spectrum to " Modified TID-14844." 3.2 For a different postulated containment leak rate 3.2.1 For an anticipated change in containneent pressure with no additional containment degradation, use Figure, B.5 with the equivalent hole size determined in Step 1.4.5 3.2.2 For anticipated containment degradation, use Figure B.5 with an appropriately chosen hole size. 3.2.3 Determine the new containment leak rate from Figure B.S. 3.3 For an anticipated dearadation of the primary coolant loop. Change the primary coolant leak rate to containment. 3.4 For the postulated changed plant parameters, recalculate future vent releases using the methods given in part 2.0. NOTE: Part 2.0 is based on unchanged plant parameters. If the postulated conditions are more severe than those determined to exist in part 1.0, the part 2.0 methods with the changed parameters will result in release rates which are too high; conversely, in the unlikely event that the postulated conditions are less severe, the estimated release rates will be too low. k v w Nj A ~
KEC-IPD IP-6. Appendix B Page 6 of 53 Rev. 1 A GASEOUS RELEASES WORKSHEET 1-A 1.1 Determination of Isotopic spectru 1.1.1 I = I-131 specific activity pCi/g C" = Cs-137 specific activity pC1/g R" = Rb-88 specific activity pCi/g C /R I /C = I /R = = a a a a a a
- TABLE 1.1 Selection cf Isotope Spectrum Appropriate Isotope C
Spectrum J EC, IjR_ C 8.5 < I/C < 18.5 1.0 < I/R 1 10 C/R < 0.18 Expected I/C $ 8.5 I/R < 1.0 0.18 < C/R < 1.0 Design I/C > 18.5 I/R > 10 C/R > 1.0 Modified TID-14844 l 1.1.3 Chosen distribution is (check one): " Expected" " Design" " Modified TID-14844" l 1.2 Determination of severity of fuel failure: { 1.2.1 TABLE 1.2 Specific Activity in Primary Coolant (Prior to Incident) j for Three Isotopic Spectra Specific Activity Level (uCi/g) i Isotope Expected Design Modified TID-14844 i 3 2.3 2.5 3.57 x 10 I, = I-131 2 C = Cs-137 0.16 1.0 1.59 x 10 1 R = Rb-88 1.9 3.7 9.09 x 10 c I
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l
~. KEC-IPD IP-6 Appendix C Page 2 of 50 '~ Rev. O syv 1.3.1 Calculate the elapsed time from reactor shutdown to the time at which the monitor readings were taken. 1.3.2 sacord the normalisation factor F, determined in 1.2.3. 1.3.3 Normalise the measured dose rates by dividing by the normalization factor. The terminology used ist MDR = measured dose rate; MDgN = normalized measured dose rate. 1.3.4.a The primary coolant leak rate will be determined using the normalized values of the upper containment area monitors (i.e., RM-90-59 and RM-90-60). Select the greater of the two normalized upper containment monitor readings determined by 1.3.3. Note that these two monitors should have similar readings. Large deviations may imply that one of the monitors is not operating properly, in which case only the reading from the operating monitor should be used. Record the normalised monitor reading which was selected as the MDRN (upper containment) in 1.3.4.s on worksheet 1-B. If the upper containment area monitors cannot be used, skip to 1.3.5. 1.3.4.b Choose the appropriate figure to be used for visual interpolation based on the reactor coolant source spectrum determined in 1.1.3: Espected Spectrum: Figure C.1-a Design Spectrum Figure C.1-b TID-14844 Spectrum Figure C.1-c 8' Record the figure number selected on 1.3.4.b, worksheet 1-B. Using the elapsed time t /hr) from 1.3.4.a. estimate a primary 1.3.4.c from 1.3.1, and the normalized upper containment radiation (mR coolant leak rate (gpa) by visually interpolating between the curves on the figure selected in 1.3.4.b. Record in 1.3.4.c on worksheet 1-B the value of the calculated monitor reading and associated primary coolant leak rate from the curves above and below the normalized measured value. 1.3.4.d Record the estimated primary coolant leak rate in 1.3.4.d on worksheet 1-B and proceed to 1.4. 1.3.5 The primary coolant leak rate will be determined using the normalized value of the accident monitor outside the personnel hatch (i.e., RM-90-2). This monitor should be used only if the upper containment area monitors cannat be used. 1.3.5.s Choose the appropriate figure to be used for visual interpolation based on the reactor source spectrum determined in 1.1.3: Expected Spectrum: Figure C.2-a Design Spectrum Figure C.2-b TID-14844 Spectrum Figure C.2-c Record the figure number selected on 1.3.5.a, worksheet 1-B. v %W m /Y T
~ -- KEC-IPD IP-6 Appendix C Page 3 of 50 Rev. 1 1.3.5.b Using the elapsed time t from 1.3.1 and the normalized radiation level (mR/hr) Outside the personnel hatch from 1.3.3, estimate a primary coolant leak rate (gpm by visually interpolating between the curves on the figure selected in 1.3.5.a. Record in 1.3.5.b on worksheet 1-B the value of the calculated monitor reading and associated primary coolant leak 'dete from the curves above and below the normalized measured value. 1.3.5.c Record the estimated primary coolant leak rate in 1.3.5.c on worksheet 1-B. Proceed to 1.4. 1.4 Determine containment leak rate. Use worksheet 1-C. Record the readings of radiation monitor RM-90-100B (shield building vent - gross radioactive gas channel) and flow element FE-30-242 (shield building vent total flow). Record the time and date the readings were taken. Note: If the readings of the shield building vent monitor are not significantly greater than normal background count rate, the containment leak rate cannot be determined analytically. For this situation, the containment leah rate will be assumed to
- be 268 scfh (0.25 percent per day of primary containment free volume at 12.0 psig).
If this assumption is made, skip to 2.0. 1.4.1
- Calculate the noble gas specific activity (pCi/cc) in the shield building vent by multiplying the monitor reading (cpm by the
- conversion factor of 2.8 x 10 8 pCi/cc/ cpm Vent Concentration = Monitor epm x 2.8 x 10 8 1.4.2 Calculate the noble gas release rate (pci/s) by multiplying the specific activity (pCi/cc) determined in 1.4.1 by the vent flow (cfm) from FE-30-242 and by 472 (unit conyersion factor):
Release rate = 472 x specific activity x vent flow 1.4.3 Calculate the elapsed time from reactor shutdown to the time at which the shield building vent radiation monitor reading was taken. 1.4.4 Record the normalization factor F, determined in 1.2.3. 1.4.5 Normalize the measured noble gas release rate by dividing by the normalization factor. The terminology used is: VRRN = normalized vent noble gas release rate. 1.4.6 Select from figure C.4, the figure to be used for visual interpolation based on the reactor coolant source spectrum determined in 1.1.3 and the primary coolant leak rate determined in 1.3.4.d o,r 1.3.5.c. Record the figure number selected on 1.4.6 workgheet 1-C. ~-jg s
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KEC-IPD IP-6 Appendix C I Page 6 of 50 Rev. O O 3.4 For the postulated changed plant parameters, recalculate future vent releases usina the methods given in part 2.0. NOTE: Part 2.0 is based on unchanged plant parameters. If the postulated conditions are more severe than those determined to exist in part 1.0, the part 2.0 methods with the changed j parameters will result in release rates which are too hight conversely, in the unlikely event that the postulated conditions are less severe, the estimated release rates will be too low. t W \\ W m< .~ ~~ i41
J. 1 _ -.;,...... J ~ ~ ~ ~ ^ ~ ^~ '-~ ^ ^ .. m _... s 4 KEC-IPD -IP-6 Appendix C ~ Page 7 of 50 Rev. 1 GASEOUS RELEASES WORKSHEET 1-A 1.1 ' Determination of Isotopic spectrum 1.1.1 I = I-131 specific activity -pCi/g C" = Cs-137 specific activity pCi/g R" = RB-88 specific activity pCi/g j m C /R I /C = I /R = = m a a a a m
- TABLE 1 1 Selection of Isotope Spectrum Appropriate Isotope I[C I/R C[R Spectrum i
8.5 < I/C i 18.5 1.0 < I/R 3 10 C/R $ 0.18 Expected I/C $ 8.5 I/R i 1.0 0.18 < C/R $ 1.0 Design 4 I/C > 18.5 I/R > 10 C/R > 1.0 Modified l i TID-14844 1.1.3 Chosen distribution is (check one): " Expected" " Design" " Modified TID-14844" 1.2 Determination of seve:Aty of fuel failure: l l 1.2.1 TABLE 1.2 Specific Activity in Primary Coolant (Prior to Incident) for Three Isotopic Spectra Specific Activity Level (pCi/g) Isotope Expected Design Modified TID-14844 3 2.3 2.5 3.57 x 10 I,= I-131 2 C = Cs-137 0.16 ~ 1. 0 1.59 x 10 c R = Rb-88 1.9 3.7 9.09 x 101 c
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m.. t KEC-IPD IP-6 Appendix C f-Page 12 of 50 Rev. 1 GASEOUS RELEASES WORKSHEET 2-A Containment Noble Gas Release Rate 2.1.2 From Figure C.3 (Record figure used) LR(U) = scfh LR(L) = scfh
- where: LR = Containment leak rate used in Step 1.4.7.
A Containment Leak Rate from Worksheet 1-C, step 1.4.5: LRD = scfh 2.1.3 Time elapsed since reactor shutdown t: = hours 2.1.4 Interpolation Fraction: IF = LRD - LR(L) LR(U) - LR(L) =( )-( ) ( )-( ) ~ s From Figure C.3, at t, determine CRR(U) corresponding to LR(U): CRR(U) = pCi/s From Figure C.3, at t, determine CRR(L) corresponding to LR(L): CRR(L) = pCi/s Normalization factor (from 1.2.3, worksheet 1-A) F = Future acble gas release rate = [IF x (CRR(U) - CRR(L) + CRR(L)] x F =[ x( )+ ]x pCi/s = NOTE: Same nomenclature as on worksheet 1-0
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_... ~,.. -_. KEC-IPD IP-6 Appendix C Page 13 of 50 Rev. 0 ? GASEOUS RELEASES WORKSHEET 2-B Interpolation Fraction from Worksheet 2-As IF = 2.2.1 From Figure C.5 _ (Same nomenclature as worksheet 2-A). CRR(L) = C1/s CER(U) = Ci/s Normalization Factor F, = Future iodine release rates CBR(L)) x F hF x (CRR(U) - CRR(L)) + ]. g ,( ). = j Ci/s = l l s I ~ em., h V .}}