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ACRSR-1723
ACRSR-1723
    .    [one     ^                            UNITED STATES                                               p[)p
[one UNITED STATES p[)p
        /                             NUCLEAR REGULATORY COMMISSION y                         ADVISORY COMMITTEE ON REACTOR SAFEGUARDS o                                     WASHINGTON, D. C. 20684 September 19, 1997
^
/
NUCLEAR REGULATORY COMMISSION y
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS o
WASHINGTON, D. C. 20684 September 19, 1997
~
~
The Honorable Shirley Ann Jackson Chairman U.S. Nuclear Regulatory Commission Washington, DC       20555-0001
The Honorable Shirley Ann Jackson Chairman U.S. Nuclear Regulatory Commission Washington, DC 20555-0001


==Dear Chairman Jackson:==
==Dear Chairman Jackson:==
==SUBJECT:==
==SUBJECT:==
SITE-TO-SITE       VARIATION           IN   RISK-BASED               REGULATORY ACCEPTANCE CRITERIA FOR PLANT-SPECIFIC APPLICATION OF SAFETY GOALS In the Staff Requirements Memorandum dated May 27, 1997, the Commission requested that the ACRS determine the change in core
SITE-TO-SITE VARIATION IN RISK-BASED REGULATORY ACCEPTANCE CRITERIA FOR PLANT-SPECIFIC APPLICATION OF SAFETY GOALS In the Staff Requirements Memorandum dated May 27,
,              damage frequency (CDF) and large, early release frequency (LERF) from site-to-site when these lower-tier criteria are derived from the individual early fatality quantitative health objective (OHO) .
: 1997, the Commission requested that the ACRS determine the change in core damage frequency (CDF) and large, early release frequency (LERF) from site-to-site when these lower-tier criteria are derived from the individual early fatality quantitative health objective (OHO).
In response to this Commission request, during the 443rd and 444th meetings of the Advisory Committee on Reactor Safeguards, July 9-11 and September 3-5,           1997,       we   discussed the plant-specific application of NRC Safety Goals and derivation of subsidiary criteria.       These criteria would be used in determining the acceptability of proposed changes to the licensing basis. During the discussions, we had the benefit of the documents referenced.
In response to this Commission request, during the 443rd and 444th meetings of the Advisory Committee on Reactor Safeguards, July 9-11 and September 3-5,
.            This report discusses           the site variability in LERF as a risk-acceptance criterion derived from the individual early f atality QHO. The bases for the conclusions and recommendations in this report are provided in the attached studies. We addressed the CDF criterion in our April 11, 1997 report.
: 1997, we discussed the plant-specific application of NRC Safety Goals and derivation of subsidiary criteria.
Variability     in LERF Criteria           Derived     from   the         Safety       Goal Individual Early Fatality OHO 4
These criteria would be used in determining the acceptability of proposed changes to the licensing basis.
In support of preparing our response to the Commission's request, an ACRS Senior Fellow performed a study (Attachment 1) to answer the following questions:
During the discussions, we had the benefit of the documents referenced.
e     Is there sufficient site-to-site variability in the site                                         .;
This report discusses the site variability in LERF as a
characteristics     important to individual early f atality risk to f'J)I warrant site-specific determination of lower level acceptance criteria - e.g., LERF?
risk-acceptance criterion derived from the individual early f atality QHO. The bases for the conclusions and recommendations in this report are provided in the attached studies.
!            e     can this range of variability be evaluated and bounded?
We addressed the CDF criterion in our April 11, 1997 report.
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Variability in LERF Criteria Derived from the Safety Goal Individual Early Fatality OHO In support of preparing our response to the Commission's request, 4
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an ACRS Senior Fellow performed a study (Attachment 1) to answer the following questions:
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e Is there sufficient site-to-site variability in the site characteristics important to individual early f atality risk to f'J)I warrant site-specific determination of lower level acceptance criteria - e.g.,
LERF?
e can this range of variability be evaluated and bounded?
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2
2
                    .f 9      Can generic criteria or site-specific criteria be determined 4
.f Can generic criteria or site-specific criteria be determined 9
using simplified approximate methods?
using simplified approximate methods?
The   range of variability in individual early fatality risk due to the site-to-site variations- in the parameters important to individual early f atality_ risk, such as site-to-site population distribution, wind direction frequency distribution, exclusion zone
4 The range of variability in individual early fatality risk due to the site-to-site variations-in the parameters important to individual early f atality_ risk, such as site-to-site population distribution, wind direction frequency distribution, exclusion zone size, and meteorology record, was evaluated for all U.S.
!                      size, and meteorology record, was evaluated for all U.S. plant
plant sites and was found to be relatively small (a variation of a factor of 4).
'                      sites and was found to be relatively small (a variation of a factor of 4).
This study has been independently reviewed, and although the reviewers had different opinions on some of the details of the
This study has been independently reviewed, and although the reviewers had different opinions on some of the details of the
;                      analysis,   all           of the reviewers             concurred   with     the overall conclusion on the magnitude of the variability.                                   Since this variability is much less than the magnitude of uncertainties associated with the probabilistic risk assessment (PRA) calculation of the LERF, this study cor.cluded that the site-to-site variability in individual early fatality risk is insufficient to warrant a
: analysis, all of the reviewers concurred with the overall conclusion on the magnitude of the variability.
development of site-specific LERF criteria.                         Hence, a single LERF criterion can be determined on a generic basis. This is consistent with the approach used by the staff in the draft Regulatory Guide DG-1061, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Current
Since this variability is much less than the magnitude of uncertainties associated with the probabilistic risk assessment (PRA) calculation of the LERF, this study cor.cluded that the site-to-site variability in individual early fatality risk is insufficient to warrant development of site-specific LERF criteria.
Hence, a single LERF a
criterion can be determined on a generic basis. This is consistent with the approach used by the staff in the draft Regulatory Guide DG-1061, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Current
]
]
Licensing Basis."
Licensing Basis."
We believe that the information provided in the study can be used to bound the variability of site-specific LERFs.
We believe that the information provided in the study can be used to bound the variability of site-specific LERFs.
Adecuacy of Individual Risk Metric 5                       In addition to the               individual risk metric,               DG-1061 contains deterministic considerations that include other risk parameters -
Adecuacy of Individual Risk Metric 5
one of which is " siting factors."                           A second study, which was performed by an ACRS Senior Fellow (Attachment 2), noted that one such siting factor, site population density, is a robust indicator of total (societal) early fatality risk.                               Consequently, we
In addition to the individual risk metric, DG-1061 contains deterministic considerations that include other risk parameters -
:                      recommend that the consideration of siting factors, mentioned in DG-1061 only in passing, be given much greater visibility and prominence as part of the decision making process.
one of which is " siting factors."
Conclusions and Recommendations
A second study, which was performed by an ACRS Senior Fellow (Attachment 2), noted that one such siting factor, site population density, is a robust indicator of total (societal) early fatality risk.
!                      We have determined that there is insufficient site-to-site variability in the f actors that influence individual early f atality risk to warrant site-specific differences in the LERF subsidiary 4
Consequently, we recommend that the consideration of siting factors, mentioned in DG-1061 only in passing, be given much greater visibility and prominence as part of the decision making process.
criterion, i
Conclusions and Recommendations We have determined that there is insufficient site-to-site variability in the f actors that influence individual early f atality risk to warrant site-specific differences in the LERF subsidiary criterion, 4
Large site-to-site. variations.in the population density result in large variations in total early fatality risk. We recommend that f
i Large site-to-site. variations.in the population density result in large variations in total early fatality risk.
We recommend that f
this robust indicator of societal risk be made more explicit and 4
this robust indicator of societal risk be made more explicit and 4
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prominent in the criteria to be used in assessing plant-specific changes to the current licensing basis.
".          prominent in the criteria to be used in assessing plant-specific changes to the current licensing basis.
Sincerely, n
Sincerely, n
                                                      .+y         -
.+y R. L. Seale Chairman
R. L. Seale Chairman i


==References:==
==References:==
: 1. Memorandum dated May 27, 199'i, from John C. Hoyle, Secretary, NRC, to John T. Larkins, Executive           Director, ACRS,  
i 1.
Memorandum dated May 27, 199'i, from John C. Hoyle, Secretary, NRC, to John T. Larkins, Executive Director, ACRS,  


==Subject:==
==Subject:==
 
Staff Requirements Meeting with the ACRS, May 2,
Staff Requirements     -
: 1997, Commissioners' Conference Room.
Meeting with         the ACRS, May 2, 1997, Commissioners' Conference Room.
l 2.
l
Report dated November 18, 1996, from T.
: 2. Report dated November 18, 1996, from T. S. Kress, Chairman, ACRS,   to Shirley   Ann   Jackson,         Chairman,             NRC,  
S.
Kress, Chairman,
: ACRS, to Shirley Ann
: Jackson, Chairman,
: NRC,


==Subject:==
==Subject:==
Plant-Specific Application of Safety Goals.
Plant-Specific Application of Safety Goals.
1-        3. Report dated April 11, 1997, from R. L. Seale, Chairman, ACRb, to Shirley Ann Jackson, Chairman, NRC,  
3.
Report dated April 11, 1997, from R. L. Seale, Chairman, ACRb, 1-to Shirley Ann Jackson, Chairman, NRC,  


==Subject:==
==Subject:==
Risk-Based Regulatory Acceptance Criteria for Plant Specific Application
Risk-Based Regulatory Acceptance Criteria for Plant Specific Application of Safety Goals.
,                of Safety Goals.
j 4.
j           4. U. S. Nuclear Regulatory Commission, NUREG/CR-2239, " Technical Guidance for Siting Criteria Development," Prepared by Sandia National Laboratories, December 1982.
U. S. Nuclear Regulatory Commission, NUREG/CR-2239, " Technical Guidance for Siting Criteria Development," Prepared by Sandia National Laboratories, December 1982.
Attachments:
Attachments:
l           1. Memorandum dated June 27, 1997, from R. Sherry, Senior ACRS
l 1.
,              Fellow to ACRS Members,  
Memorandum dated June 27, 1997, from R.
Sherry, Senior ACRS Fellow to ACRS Members,  


==Subject:==
==Subject:==
Considerations for Plant-
Considerations for Plant-
;                Specific, Site-Specific Application of Safety Goals and Definition of Subsidiary criteria.
: Specific, Site-Specific Application of Safety Goals and Definition of Subsidiary criteria.
: 2. Memorandum dated June 11, 1997, from R. Sherry, Senior ACRS 4
2.
Fellow to ACRS Members,  
Memorandum dated June 11, 1997, from R. Sherry, Senior ACRS Fellow to ACRS Members,  


==Subject:==
==Subject:==
Consideration of Societal Risk in Plant-Specific, Site-Specific Application of Safety Goals and Definition of Subsidiary Criteria.
Consideration of Societal 4
Risk in Plant-Specific, Site-Specific Application of Safety Goals and Definition of Subsidiary Criteria.
4 e
4 e
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Latest revision as of 00:35, 6 December 2024

Discusses Site Variability in Large,Early Release Frequency as Risk Acceptance Criterion Derived from Individual Early Fatality Quantitative Health Objective
ML20211A623
Person / Time
Issue date: 09/19/1997
From: Seale R
Advisory Committee on Reactor Safeguards
To: Shirley Ann Jackson, The Chairman
NRC COMMISSION (OCM)
Shared Package
ML20211A627 List:
References
ACRS-R-1723, FACA, NUDOCS 9709240316
Download: ML20211A623 (3)


Text

-

ACRSR-1723

[one UNITED STATES p[)p

^

/

NUCLEAR REGULATORY COMMISSION y

ADVISORY COMMITTEE ON REACTOR SAFEGUARDS o

WASHINGTON, D. C. 20684 September 19, 1997

~

The Honorable Shirley Ann Jackson Chairman U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Dear Chairman Jackson:

SUBJECT:

SITE-TO-SITE VARIATION IN RISK-BASED REGULATORY ACCEPTANCE CRITERIA FOR PLANT-SPECIFIC APPLICATION OF SAFETY GOALS In the Staff Requirements Memorandum dated May 27,

1997, the Commission requested that the ACRS determine the change in core damage frequency (CDF) and large, early release frequency (LERF) from site-to-site when these lower-tier criteria are derived from the individual early fatality quantitative health objective (OHO).

In response to this Commission request, during the 443rd and 444th meetings of the Advisory Committee on Reactor Safeguards, July 9-11 and September 3-5,

1997, we discussed the plant-specific application of NRC Safety Goals and derivation of subsidiary criteria.

These criteria would be used in determining the acceptability of proposed changes to the licensing basis.

During the discussions, we had the benefit of the documents referenced.

This report discusses the site variability in LERF as a

risk-acceptance criterion derived from the individual early f atality QHO. The bases for the conclusions and recommendations in this report are provided in the attached studies.

We addressed the CDF criterion in our April 11, 1997 report.

Variability in LERF Criteria Derived from the Safety Goal Individual Early Fatality OHO In support of preparing our response to the Commission's request, 4

an ACRS Senior Fellow performed a study (Attachment 1) to answer the following questions:

e Is there sufficient site-to-site variability in the site characteristics important to individual early f atality risk to f'J)I warrant site-specific determination of lower level acceptance criteria - e.g.,

LERF?

e can this range of variability be evaluated and bounded?

l O

< (h ui

\\

[l[ll[ll'll'lhllll}hl}l}$h

[dCO

,V () 7 D

9709240316 970919 PDR ACRS R-1723 PDR

2

.f Can generic criteria or site-specific criteria be determined 9

using simplified approximate methods?

4 The range of variability in individual early fatality risk due to the site-to-site variations-in the parameters important to individual early f atality_ risk, such as site-to-site population distribution, wind direction frequency distribution, exclusion zone size, and meteorology record, was evaluated for all U.S.

plant sites and was found to be relatively small (a variation of a factor of 4).

This study has been independently reviewed, and although the reviewers had different opinions on some of the details of the

analysis, all of the reviewers concurred with the overall conclusion on the magnitude of the variability.

Since this variability is much less than the magnitude of uncertainties associated with the probabilistic risk assessment (PRA) calculation of the LERF, this study cor.cluded that the site-to-site variability in individual early fatality risk is insufficient to warrant development of site-specific LERF criteria.

Hence, a single LERF a

criterion can be determined on a generic basis. This is consistent with the approach used by the staff in the draft Regulatory Guide DG-1061, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Current

]

Licensing Basis."

We believe that the information provided in the study can be used to bound the variability of site-specific LERFs.

Adecuacy of Individual Risk Metric 5

In addition to the individual risk metric, DG-1061 contains deterministic considerations that include other risk parameters -

one of which is " siting factors."

A second study, which was performed by an ACRS Senior Fellow (Attachment 2), noted that one such siting factor, site population density, is a robust indicator of total (societal) early fatality risk.

Consequently, we recommend that the consideration of siting factors, mentioned in DG-1061 only in passing, be given much greater visibility and prominence as part of the decision making process.

Conclusions and Recommendations We have determined that there is insufficient site-to-site variability in the f actors that influence individual early f atality risk to warrant site-specific differences in the LERF subsidiary criterion, 4

i Large site-to-site. variations.in the population density result in large variations in total early fatality risk.

We recommend that f

this robust indicator of societal risk be made more explicit and 4

i t'

1

,9 3

prominent in the criteria to be used in assessing plant-specific changes to the current licensing basis.

Sincerely, n

.+y R. L. Seale Chairman

References:

i 1.

Memorandum dated May 27, 199'i, from John C. Hoyle, Secretary, NRC, to John T. Larkins, Executive Director, ACRS,

Subject:

Staff Requirements Meeting with the ACRS, May 2,

1997, Commissioners' Conference Room.

l 2.

Report dated November 18, 1996, from T.

S.

Kress, Chairman,

ACRS, to Shirley Ann
Jackson, Chairman,
NRC,

Subject:

Plant-Specific Application of Safety Goals.

3.

Report dated April 11, 1997, from R. L. Seale, Chairman, ACRb, 1-to Shirley Ann Jackson, Chairman, NRC,

Subject:

Risk-Based Regulatory Acceptance Criteria for Plant Specific Application of Safety Goals.

j 4.

U. S. Nuclear Regulatory Commission, NUREG/CR-2239, " Technical Guidance for Siting Criteria Development," Prepared by Sandia National Laboratories, December 1982.

Attachments:

l 1.

Memorandum dated June 27, 1997, from R.

Sherry, Senior ACRS Fellow to ACRS Members,

Subject:

Considerations for Plant-

Specific, Site-Specific Application of Safety Goals and Definition of Subsidiary criteria.

2.

Memorandum dated June 11, 1997, from R. Sherry, Senior ACRS Fellow to ACRS Members,

Subject:

Consideration of Societal 4

Risk in Plant-Specific, Site-Specific Application of Safety Goals and Definition of Subsidiary Criteria.

4 e

d O

i i

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