ML20199E253
| ML20199E253 | |
| Person / Time | |
|---|---|
| Issue date: | 01/12/1999 |
| From: | Klementowicz S NRC (Affiliation Not Assigned) |
| To: | Chris Miller NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9901200359 | |
| Download: ML20199E253 (11) | |
Text
January 12, 1999 4
MEMORANDUM TO: Charles L. Miller, Chief Emergency Preparedness and Radiation Protection Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:
Stephen P. Klementowicz, Health Physicist original signed by:
Emergency Preparedness and Environmental Health Physics Section Emergency Preparedness and Radiation Protection Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF WORKSHOP WITH THE NUCLEAR ENERGY INSTITUTE (NEI) REGARDING PERFORMANCE INDICATORS FOR ASSESSING RADIATION PROTECTION PROGRAMS On November 13,1998, representatives of the Nuclear Energy Institute (NEI) met with representatives of the Nuclear Regulatory Commission (NRC) at the NRC's offices in Rockville, Maryland. Attachment 1 provides a list of workshop attendees.
The purpose of the workshop was to continue discussion and development of performance indicators (PI) to be used by the NRC to help assess radiation protection programs at power reactors.
There was a general discussion about the appropriate threshold values for Pls to be used in the assessment process. More data from inspection reports and from licensee issued reports needs to be reviewed to develop a meaningful threshold for the Pls. Additionally, a clear distinction needs to be made about Pis and their relationship to violations of NRC requirements and the level of NRC inspection that is needed.
NEl presented some draft data (see Attachment 2) from their working group member plants to attempt to verify and validate draft Pls against historical events, plant operating experience, and regulatory violations. The data in the occupational area presents the number of licensee reported events in relation to the NRC's Systematic Assessment of Licensee Performance (SALP) score. The data in the public area presents the number of licensee reported events, including abnormal releases and radiation monitors that were out of service. Additional data will be obtained so that this effort can continue to be refined further in future meetings.
The meeting closed with plans to meet and continue Pl development at the NRC office on November 17,1998.
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cc w/att: See next page qc)
DISTRIBUTION: See attached page 9
DOCUMENT NAME:G:\\MTGSUM13 OFFICE PERB g SC:Pg BC:PERB Bb h CMiller/-/t, pk NAME Klementowicz DATE 1/ ff /99 1/ll /99 1/ /t.-/99 y \\ r" f
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9901200359 990112 PDR REVGP ERGNUMRC f
4 DISTRIBUTION:
SMagruder SKlementowicz EM. Ail TEssig REmch JWhite, R1 KBarr, R2 GShear, R3 BMurray, R4 GKuzo RPedersen JWigginton AMadison 200037
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9 DISTRIBUTION:
Hard Coov PUBLIC PERB R/F SMagruder SKlementowicz EMail TEssig REmch JWhite, R1 KBarr, R2 GShear, R3 i
BMurray, R4 GKuzo RPedersen JWigginton AMadison l
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January 12, 1999 MEMORANDUM TO: Charles L. Miller, Chief Emergency Preparedness and Rsdiation Protection Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:
Stephen P. Klementowicz, Health Phyt.nt original signed by:
Emergency Preparedness and Environmental Health Physics Section Emergency Preparedness and Radiation Protection Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF WORKSHOP WITH THE NUCLEAR ENERGY INSTITUTE (NEI) REGARDING PERFORMANCE INDICATORS FOR ASSESSING RADIATION PROTECTION PROGRAMS On November 13,1998, representatives of the Nuclear Energy institute (NEI) met with representatives of the Nuclear Regulatory Commission (NRC) ai the NRC's offices in Rockville.
Maryland. Attachment 1 provides a list of workshop attendees.
The purpose of the workshop was to continue discussion and development of performance indicators (PI) to be used by the NRC to help assess radiation protection programs at power reactors.
There was a general disc'Jssion about the appropriate threshold values for Pls to be used in the sesessment process. More data from inspection reports and from licensee issued reports needs to be reviewed to develop a meaningful threshold for the Pls. Additionally, a clear distinction needs to be made about Pis and their relationship to violations of NRC requirements and the level of NRC inspection that is needed.
NEl presented some draft data (see Attachment 2) from their working group member plants to attempt to verify and v6tidate draft Pls against historical events, plant operating experience, and regulatory violations. The data in the occupational area presents the number of licensee reported events in relation to the NRC's Systematic Assessment of Licensee Performance (SALP) score. The data in the public area presents the number of licensee reported events.
including abnormal releases and radiation monitors that were out of service. Additional data will be obtained so that this effort can continue to be refined further in future meetings.
The meeting closed with plans to meet and continue Pl development at the NRC office on November 17,1998.
Attachments: As stated cc w/ttt: Ses next F. age DISTRIBUTION: See attached page DOCUMENT NAME:G:\\MTGSUM13 OFFICE PERB g SC:@
BC:PERB NAME Klementow!cz Bh CMillergh DATE 1/ s /99 illl/99 1/ /v/99
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- ,,,*g January 12, 1999 MEMORANDUM TO: Charles L. Miller, Chief Emergency Preparedness and Radiation Protection Branch Division of Reactor Program Management
/
l 3
Office of Nuclear Reactor Regulation Q{JP FROM:
Stephen P. Klementowicz, Health Physicist Emergency Preparedness and Environmental Health Physics Section Emergency Preparedness and Radiation Protection Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF WORKSHOP WITH THE NUCLEAR ENERGY INSTITUTE (NEI) REGARDING PERFORMANCE INDICATORS FOR ASSESSING RADIATION PROTECTION PROGRAMS On November 13,1998, representatives of the Nuclear Energy Institute (NEI) met with representatives of the Nuclear Regulatory Commission (NRC) at the NRC's offices in Rockville, Maryland. Attachment 1 provides a list of workshop attendees.
The purpose of the workshop was to continue discussion and development of performance indicators (PI) to be used by the NRC to help assess radiation protection programs at power reactors.
There was a general discussion about the appropriate threshold values for Pls to be used in the assessment process. More data from inspection reports and from licensee issued renorts needs to be reviewed to develop a meaningful threshold for tbs Pls. Additionally, a clear l
distinction needs to be made about Pls and their relationship to violations of NRC requirements and the level of NRC inspection that is needed.
NEl presented some draft data (see Attachment 2) from their working group member plants to attempt to verify and validate draft Pts against historical events, plant operating experience, and regulatory violations. The data in the occupational area presents the number of licensee j
reported events in relation to the NRC's Systematic Assessment of Licensee Performance l
(SALP) score. The data in the public area presents the number of licensee reported events, i
including abnormal releases and radiation monitors that were out of service. Additional data will l
be obtained so that this effort can continae to be refined further in future meetings.
l l
The meeting closed with plans to meet and continue 6 development at the NRC office on I
November 17,1998.
Attachments: As stated cc w/att: See next page
~
Nuclear Energy Institute Project No. 689 cc:
Mr. Ralph Beedle Ms. Lynnette Hendricks, Director Senior Vice President Plant Support and Chief Nuclear Officer Nuclear Energy Institute Nuclear Energy Institute Suite 400 Suito 400 1776 i Street, NW 1776 l Street, NW Washington, DC 20006-3708 Washington, DC 20006-3708 Mr. Steven Driscol Radiation Protection INPO 700 Galleria Parkway 1
Mr. Alex Marion, Director Atlanta, Georgia 30339-5957 Prograrns Nuclear Energy Institute Suite 400 1776 l Street, NW Washington, DC 20006-3708 j
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- Attachment 1 Radiation Protection Performance Indicator Meeting
{
11/13/98 i
List of Attendees Name Oraanization Steve Klementowicz USNRC
[
George Kuzo USNRC Niodh Shah USNRC Roger Pedersen USNRC Janes Wigginton USNRC Rt.iph Anderson NEl Paul Genoa NEl i
I l
l i
i l
l i
l l
1 3
4 6
A\\ttach9tiefiT~2 Public Radiation Safety -
She:11
[
. Efflueitts (A!! Sitis)
IQ
/
A B
C D
E F
G H l l
1 LER98 LER97 LER96 LERTOT 97 A/R 97 MON 2 M 2
12 8
22 0
9 3 M 1
2 4
7 0
12 4
M 4
3 0
7 5
M 0
0 3
3 0
0 6
S 0
1 2
3 0
0 7
S 0
1 2
3 8 M 1
1 1
3 9 M 1
0 2
3 0
0 10 M 2
1 0
3 0
12 11 M 0
1 1
2 12 M 0
1 1
2 13 M 1
1 0
2 14 S
0 2
0 2
0 0
15 S
0 1
1 2
16 S
0 1
1 2
0 1
17 S 1
0 1
2 0
0 18 M 1
0 0
1 0
0 19 M 0
1 0
1 20 M
1 0
0 1
0 0
21 S
0 1
0 1
2 4
22 S
1 0
0 1
0 3
23 M 1
0 0
1 24 M 0
1 0
1 25 S
0 1
0 1
26 S
0 0
1 1
27 M 0
0 0
0 0
0 28 M 0
0 0
0 29 M 0
0 0
0 1
0 30 S
0 0
0 0
~
31 M
0 0
0 0
32 S
0 0
0 0
0 2
33 M 0
0 0
0 34 S
0 0
0 0
0 0
35 S
0 0
0 0
36 M 0
0 0
0 37 S
0 0
0 0
38 M 0
0 0
0 0
0 39 S
0 0
0 0
0 0
40 S
0 0
0 0
41 S
0 0
0 0
42 S
0 0
0 0
4 0
.3 S
0 0
0 0
44 S
0 0
0 0
0 1
45 S
0 0
0 0
0 2
48 M 0
0 0
0 1
2 47 M 0
0 0
0 1
1 48 S
0 0
0 0
0 0
49 M 0
0 0
0 0
1 60 M 0
0 0
0 0
1 A/R = Abnormal Releases MON = Monitor Out of Service Page 1
l
, Public' Radiation Sif tty -
Sh::t1 IA Effluents (All Sites) l A
B C
D E
F G
H I
$1 S
0 0
0 0
1 1
l 52 M 0
0 0
0 53 M 0
0 0
0 M M 0
0 0
0 3
0 l
l 55 S
0 0
0 0
0 0
l 56 M 0
0 0
0 2
1 l
57 M 0
0 0
0 2
M 0
0 0
0 59 S
0 0
0 0
60 M 0
0 0
0 61 S
0 0
0 0
0 0
62 M 0
0 0
0 63 M 0
0 0
0 3
0 64 S
0 0
0 0
2 8
65 S
0 0
0 0
3 1
66 S
0 0
0 0
67 68 17 32 28 77 23 41 l
t i
NR - Abrormal Releases MON. Monitor Out of Seivice Page 2
e P
V
' Occupational Radiation Sheet 1 Q
Safety (36 Sites) 1996,1997,3 Otrs 1998 A
B C
D E
F G
H I
J K
L M
N O
1 96L 96V 96D 97L 97V 97D 98L 98V 98D TOT SALP1 SALP2 2
M 5
0 0
1 0
0 0
0 0
6 2
2 3
M 0
0 0
2 1
1 0
0 1
5 1
3 4
M 3
0 0
0 0
0 1
0 0
4 2
2 5
M 1
0 0
2 0
0 0
0 0
3 1
1 6
S 3
0 0
0 0
0 0
0 0
3 2
1 7
M o
0 0
3 0
0 0
0 0
3 2
2 8
M 2
0 0
0 0
0 0
1 0
3 1
1 9
M 0
1 0
0 0
1 0
0 0
2 2
2 10 M
2 0
0 0
0 0
0 0
0 2
3 2
11 M
0 0
0 1
0 0
1 0
0 2
1 2
12 S
1 0
0 1
0 0
0 0
0 2
2 2
13 S
0 0
0 1
0 0
1 0
0 2
2 2
14 M 0
0 0
1 0
0 0
0 0
1 1
1 15 S
0 0
0 1
0 0
0 0
0 1
1 1
16 S
0 0
0 1
0 0
0 0
0 1
2 2
17 S
0 0
0 0
0 0
1 0
0 1
1 1
18 M
0 0
0 1
0 0
0 0
0 1
1 1
19 S
0 0
0 1
0 0
0 0
0 1
1 1
20 S
0 0
0 0
0 0
1 0
0 1
1 1
21 S
1 0
0 0
0 0
o 0
0 1
2 2
22 S
0 0
0 0
0 0
1 0
0 1
1 2
23 M
o 0
0 0
0 0
1 0
0 1
1 1
24 M
0 0
0 1
0 0
0 0
0 1
1 1
25 M
0 0
0 0
0 0
0 1
0 1
2 1
26 S
1 0
0 0
0 0
0 0
0 1
1 1
27 M 0
0 0
0 0
0 0
0 0
0 1
2 28 M
0 0
0 0
0 0
0 0
0 0
2 1
29 M
0 0
0 0
0 0
0 0
0 0
1 1
30 M 0
0 0
0 0
0 0
0 0
0 2
2 31 S
0 0
0 0
0 0
0 0
0 0
,1 1
32 M 0
0 0
0 0
0 0
0 0
0
_1 1
33 M o
0 0
0 0
0 0
0 0
0 1
1 34 S
0 0
0 0
0 0
0 0
0 0
2 1
M M
0 0
0 0
0 0
0 0
0 0
1 1
36 M
o 0
0 0
0 0
0 0
0 0
1' 1
37 M
0 0
0 0
0 0
0 0
0 0
1 1
38 39 19 1
0 17 1
2 7
2 1
50 40 41 AN 20 20 11 l
L = LOCKCD HI RAD AREA V = VERY HI RAD AREA D - UNINTENDED DOSE Page1
n-Partial Data Sheet 1 fN 4
' Occ Rad Safety Includes HRA Postino Errors A
B C
D E
F G
H IlJ K
L M
N O
P Q
1 96H 96L 96V 96D 97H 97L 97V 97D'98H 98L 98V 9BD TOT S1 S2 2
M 1
0 0
0 1
2 1
1 1
0 0
1-8 1
3 3
M 1
3 0
0 1
0 0
0 0
1 0
0 6
2 2
l 4
M 0
5 0
0 0
1 0
0 0
0 0
0 6
2 2
l 5
M 0
2 0
0 0
0 0
0 1
0 1
0 4
1 1
l 6
S 0
1 0
0 1
1 0
0 1
0 0
0 4
2 2
7 S
1 0
0 0
0 1
0 0
1 1
0 0
4 2
2 8
M 0
1 0
0 0
2 0
0 0
0 0
0 3
1 1
l 9
S 0
3 0
0 0
0 0
0 0
0 0
0 3
2 1
l 10 M-1 2
0 0
0 0
0 0
0 0
0 0
3 3
2 11 M
0 0
0 0
0 3
0 0
0 0
0 0
3 2
2 l
12 S
0
-0 0
0 0
1 0
0 1
0 0
0 2
1 1
13 S
0 0
0 0
0 0
0 0
1 1
0 0
2 1
2
(
14 M
0 0
1 0
0 0
0 1
0 0
0 0
2 2
2 t
15 M 0
0 0
0 0
1 0
0 0
1 0
0 2
1 2
16 M 0
0 0
0 0
1 0
0 0
0 0
0 1
1 1
17 S
0 0
0 0
0 1
0 0
0 0
0 0
1 1
1 18 M 1
0 0
0 0
0 0
0 0
0 0
0 1
1 1
19 S
0 0
0 0
0 1
0 0
0 0
0 0
1 2
2
(
M S
0 0
0 0
0 0
0 0
0 1
0 0
1 1
1 21 M 0
0 0
0 0
1 0
0 0
0 0
0 1
1 1
22 S
0 0
0 0
0 0
0 0
0 1
0 0
1 1
1 l
23 S
0 1
0 0
0 0
0 0
0 0
0 0
1 2
2 l
24 M
0 0
0 0
0 0
0 0
0 1
0 0
1 1
1 l
25 M
0 0
0 0
0 1
0 0
0 0
0 0
1 1
1 26 S
o 1
0 0
0 0
0 0
0 0
0 0
1 1
1 29 M
1 0
0 0
0 0
0 0
0 0
0 0
1 1
1 30 M
0 0
0 0
0 0
0 0
0 0
1 0
1 2-1 31 M
o 0
0 0
0 0
0 0
0 0
0 0
0 1
2 32 M 0
0 0
0 0
0 0
0 0
0 0
0 0
2 1
33 M 0
0 0
0 0
0 0
0 0
0 0
0 0
2 2
M S
0 0
0 0
0 0
0 0
0 0
0 0
0 1
1 35 M 0
0 0
0 0
c.
0 0
0 0
0 0
0 1
1 M
S.
0 0
0 0
0 o~
0 0
0 0
0 0
0 2
1 37 M o
0 0
0 0
0 0
0 0
0 0
0 0
1 1
2 M
0 0
0 0
0 0
0 0
0 0
0 0
0 1
1 39 6
19 1
0 5
17 11 2
1 7
2 1
62 1
l
(
H = HRA Posting i-L = Locked HRA V = Very HRA 3
i D = Unintended Dose Page 1
].
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