ML20199E281
| ML20199E281 | |
| Person / Time | |
|---|---|
| Issue date: | 01/23/1998 |
| From: | Callan L NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| SECY-98-012, SECY-98-012-01, SECY-98-012-R, SECY-98-12, SECY-98-12-1, SECY-98-12-R, NUDOCS 9802020120 | |
| Download: ML20199E281 (27) | |
See also: IR 07100001/2012031
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POLICY ISSUE
(Information)
Januan/ 23.1998
EQB:
The Commissioners
EROM.
L. Joseph Callar.
Executive Director for Operations
SUBJECT:
QUARTERLY STATUS REPORT ON THE PROBABILISTIC RISK
ASSESSMENT IMPLEMENTATION PLAN
PURPOSE:
To report the status of the Probabilistic Risk Assessment (PRA) Implementation Plan for the
period of October 1 to December 31,1997, and to respond to a Staff Requirements
Memorandum dated May 28,1997, which relates to staff plans for using Individual Plant
Examination (IPE) results to assess regulatory effectiveness.
SUMMARY:
This paper describes accomplishments and changes to the staffs PRA Implementation Plan for
the period of October 1,1997 to December 31,1997, The principal accomplishments include
preparation of the final versions of Regulatory Guide (RG) 1.174 (formerly draft guide DG 1061)
and Standard Review Plan (SRP) Chapter 19, which provide general guidance on the use of
PRA in risk informed decisions for changes in a reactor current licensing basis, completion of the
South Texas graded quality assurance pilot program, publication (for public comment) of the
draft RG and SRP on risk-informed inservice inspection, and the development of the staffs plan
to use IPE results to assess regulatory effectiveness in resolving major safety issues. The
principal change is the delay of the application-specific regulatory guides and Standard Review
Plan sections from December 1997 to March 1998, to permit the incorporation of the policy
decisions associated with the finalization of RG 1.174.
CONTACT:
NOTE:
TO BE MADE PUBLICLY AVAILABLE
g
IN 5 WORKING DAYS FROM THE DATE OF
Ol
Ashok Thaaani, OEDO
THIS PAPER
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BACKGROUND:
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In a memorandum dated January C .1996, from the t!xecutive Director for Operations to
Chairman Jackson, the staff committed to submitting quarterly reports on the status of its
development of risk informed standards and guidance. Previous quarterly reports were
provided to the Commission on March 26, June 20, and October 11,1996, and on January 13,
April 3, July 22, and October 14,1997. This quarterly report covers the period from October 1,
1997 to December 31,1997.
DISCUSSION:
The significant accomplishments and changes to the PRA Implementation Plan in the past
quarter are summarized below.' More detailed information is provided in Attachment 1.
Significant achievements during the past quarter include:
Section 1: Reactor Regulation (NRR)
1.1 Develop Standard Review Plans for Risk Informed Regulation
NRR and RES staff met with ACRS and CRGR to discuss the final versions of the general
guidance on use of PRA in risk informed decision making in changes to the plant specific
current licensing basis; Standard Review Plan Chapter 19 (NRR lead) and Regulatory Guide 1.174 (RES lead). A Commission paper providing the final versions of these documents will be
provided to the Commission in the near future.
Draft Standard Review Flan 3.9.8 (NRR lead) and Regulatory Guide DG-1063 (RES lead) on
risk informed inservice inspection of piping were published for public comment and the subjects
of a public workshop on November 20 and 21,1997, The workshop was well attended by
industry representatives who offered a number of constructive comments, some criticisms, and
some suggestions for changing the guidance. Overall, the comments indicated strong support
for pursuing risk informed inservice inspection (RI-ISI) but in a manner which would necessitate
some modifications to the draft guidance.
1.2 Pilot Applications for Risk informed Regulatory Initiatives
The staff evaluation of the South Texas Project risk informed graded quality assurance (QA)
implementation plan was transmitted to the Commission via SECY 97-229 on October 6,1997.
I The staff has modified the format of the PRA Implementation Plan to reduce
redundancy and improve readability. This revised format consists of the body of the
Commission paper, which now provides a summary of accomplishments and changes to the
plan for the past quarter, and the Plan's table (Attachment 1), modified to explicitly show where
milestones have been added, completed, or changed. Such changes are discussed and
additional information provided in endnotes to the table.
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By SRM dated October 30,1997, the staff was informed that the Commission had no objection
to the issuance of the South Texas graded QA safety evaluation report. By letter dated
November 6,1997, the licensee was informed that the staff had approved the graded QA
change and was provided with the associated staff safety evaluation.
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The staff has received risk informed inservice inspection pilot submittals from Surry 1, ANO 2,
and Vermont Yankee which are currerstly being reviewed for completeness. The staff will
develop a review schedule if the submittals are determined to be complete and in conformance
with the DG 1061 and DG 1063 submittal guidance. The staff is also developing schedules and
priorities for the review of other RI ISI pilot submittals as well as submittals expected
subsequent to the pilot RI ISI program approvals.
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1.3 Inspections
The staff completed nine additional maintenance rule baseline inspections during this quarter,
which included inspection of licensee methods for using PRA in maintenance programs and
inspection of safety assessments performed by licensees when removing equipment from
service for maintenance in accordance with Paragraph (a)(3) of the Maintenance Rule. As of
December 31,1997, the staff has completed a total of 45 inspections.
Section 2: Reactor Safety Research (RES)
2.1 Develop Regulatory Guides
As discussed above, NRR and RES staff met with ACRS and CRGR to discuss the final
versions of Standard Review Plan Chapter 19 (NRR lead) and Regulatory Guide 1.174 (RES
lead). A Commission paper en policy issues was forwarded to the Commission as SECY-97-
287, dated December 12,1997. A Commission paper providing the final versions of these
documents will be provided in the near future.
2.4 Methods Development and Demonstration
A demonstration at the Seabrook nuclear power plant of the human reliability analysis method
ATHEANA (A Technique for Human Event Analys;s) has been completed. A medium break
LOCA scenario, including inappropriate termination of makeup (an error of commission), was
selected for analysis and simulator exercise. The ATHEANA demonstration helped plant
personnelidentify safety-related weaknesses in plant barriers and design. Specifically, the
exercise identified weaknesses in the use of well planned and tested emergency procedures as
well as identifying improvements needed in the draft ATHEANA documentation.
- The final version of NUREG-1560, *lPE Program: Perspectives on Reactor Saf9ty and Plant
Performance," has been submitted for publication. This report was initially issued in late 1996
for public comment. l Based on the comments received, the report was revised, with an
addrtional appendix written discussing the comments received and staff responses.
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The first IPEEE staff evaluation report, for the Diablo Canyon Power Plant, was completed and
issued to the licensee on December 4,1997, in addition, requests for additionalinformation on
fifteen IPEEE submittals were prepared to send to licensees.
An interim report has been developed that provides preliminary IPEEE perspectives and
summarizes the information presented in the first 24 IPEEE submittals reviewed by the staff.
This interim report will be sent to the Commission in the near future. (A summary of the
significant preliminary perspectives from the first 24 IPEEE reviews was provided to the
Commission in Attachment 7 to SECY 97 234.)
Sectinn 3: Analysis and Evaluation of Operating Experience and Training (AtiOD)
3.1 Risk Based Trends and Patterns Analysis
Letters are in the concurret.ce process to distribute the common cause failure (CCF) database
and associated technical report to all U.S. nuclear utilities for their use. The database contains
CCF events from 1980 through 1995.
3.2 Accident Sequence Precursor (ASP) Program
All 1996 precursor analyses have been finalized, with the 1996 ASP report now in publication.
Three preliminary analyses of 1997 events are being reviewed. The annual Commission paper
describing the ASP program in more detail was sent to the Commission on December 23,1997
(SECY 97 296).
3.6 Staff Training
Development activities for the PRA Technology and Regulatory Perspectives (P 111) course
were comploted during this quarter. The first course presentation will be January 26 - February
6,1998. The staff has established a goal of having one Resident inspector at each she
complete the course by the end of 1998.
Significant changes made to the implementation Plan during the last quarter include:
Section 1: Reac'or Regulation (NRR)
1.1 Develop Standard Review Plans for Risk-Informed Regulation
As discussed above, the general regulatory guide and Standard Review Plan for use of PRA in
plant-specific current licensing basis changes will be transmitted to the Commission in the near
future. To permit efficient incorporation of the resolution of policy issues contained in these
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documents into the application-specific SRP sections on inservice testing and technical
specifications, completion of these SRP sections has been delayed until March 31,1998, a
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change from their previous completion date of December 31,1997.
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1.2 Pilot Applications for Risk Informed Regulatory initiatives
The staff is currently developing a draft safety evaluation report (SER) for the Comanche Peak
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risk informed inservice testing program (Rl IST) program. The licensee (TU Electric) is
currently developing a program that is sufficiently detailed and consistent with DG 1062. TU
Electric has indicated that it intends to complete a draft revision to their program description by
the end of January 1998. Assuming that the program is finalized by mid February, the staff
anticipates having a completed Comanche Peak Rl IST SER to the Commission in March 1998,
rather than December 31,1997.
The completion date for the graded quality assurance (GQA) pilot interactions has been revised
from March 1998 to July 1998 to reflect the anticipated issuance date of the final GOA
inspection guidance.
The staff received a supplemental amendment request from the San Onofre Nuclear
Generating Station (SONGS) in early January 1998 to put the configuration risk management
program description into the SONGS technical specif cations. SONGS has recently become
the lead plant for this Combustion Engineering Owner's Group (CEOG) activity, when the
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originallead plant decided not to pursue risk-informed TS changes at this time. With receipt of
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the SONGS supplen etal request, the staff anticipates completing the SONGS review as the
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lead pilot plant and isung the license amendment by March 31,1998. This is a change from
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the previous date of December 31,1997.
1.3 Inspections
The NRR Inspection Program Branch (P'PB) proposals for revising core inspection procedures
have been transmitted to the appropriate NRR technical branches having responsibility for
specific core inspection procedures. Due to the large number of branches involved, completing
all individual branch concurrences is anticipated to take an additional two months. The revised
completion date for th!s task is February 1998, a chan9e from the previous date of October
1997.
1.6 Evaluate Use of PRA in Resolution of Generic issues
As part of the IPE follow-up program, the staff is in the process of identifying generic issues to
be audited. These issues are those which have been explicitly identified and addressed by the
licensee as part of the IPE process.
A report that identifies the above generic issues and staff views on the adequacy of the
proposed resolution k. In preparation. The report will provide the basis for the selection of
generic safety issues to be audited. The staff has moved the completion date for this milestone
to March 1998, in order to utilize the report in the audit process.
In addition to the above issues, RCP seal LOCA had been identified as a dominant contributor
to core damage in many PWR IPEs. The staff has a separate ongoing activity in RES to
address this issue under Generic issue 23, and will utilize IPti insights in the proposed
resolution.
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1.7 Regulatory Effectiveness Evaluation
in a Staff Requirements Memorandum dated May 28,1997 (Attachment 2), the Commission
requested that the staff provide the scope and schedule of activities relatad to using IPE results
to assess regulatory effectiveness in resolving major safety issues. With respect to scope, the
staff identified three major safety issues for assessment. The selection had been based on
both the potential risk significance of the issue, and the fact that probabilistic techniques were
used extensively in the resolution process. These issues include:
1, Resolution of USl A-44 Station Blackout at Nuclear Power Plants
2. Resolution of USl A-45 Decay Heat Removal Reliability
3. Resolution of USl A 09 Anticipated Transient Without Scram
To evaluate the three major issues, the staff will utilizJ both representative plants, and
information contained in NUREG 1560, to audit and draw conclusions regarding regulatory
effectiveness. Information generated under Task 1.6, as deteribed above, and Task 1.10, as
described below, will also be integrated into the assessment process. These tasks may expar!d
the staff's consideration of other cafety issues and effectiveness of the regulatory process. The
staff will inform the Commission of any additional safety issues that come under consideration.
The staff plans to complete Task 1.7 by the end of December 1998, and will recommend at that
time any additional staff action.
1.8 Advanced Reactor Reviews
Doe to personnel being assigned to higher priority activities, such as risk-informed pilot
initiatives and IPE followup activities, the staff is reassessing their position regarding the
development of an SRP, especially since there are no new advanced design certification
submittals anticipated. We will provide the results of this reassessment in a future update of
the PRA implementation Plan.
1.10 Evaluation of IPE Insights
The staff has developed an IPE followup plan (Attachment 3) which describes those actions to
be taken to ensure that plant improvements warranted by 'he IPE results are, in fact, made.
This plan consists of a number of items and its implementation involves NRR, RES, and the
Regions, as described in the plan.
Section 2: Reactor Safety Research (RES)
2,1 Develop Regulatory Guides
As discussed above, the general regulatory guide and Standard Review Plan for use of PRA in
risk informed decision making for plant specific current licensing basis charges will be
transmitted to the Commission in the near future. To permit efficient incorporation of the
resolution of policy issues contained in these documents into the application-specific regulatory
guides on inservice testing, graded quality ascurance, and technical specifications, completion
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of these guides has been delayed until March 31,1998, a change from their previous
completion date of December 31,1997.
The staff has reviewed all the 76 IPE submittals and issued staff evaluatiun reports (SERs) on
their findings to each licensee, in three of the SERs, it is indicated to the licensees that the
staff was not able to conclude that the licensee met the intent of Generic Letter 88 20 for their
plant (s). These three IPEs include Crystal River 3, Susquehanna 1&2, and Browns Ferry 3.
The licensee for Crystal River 3 has indicated their intention to submit an updated analysis
(February 1998) addressing the staff's concerns. It is anticipated that the review of this new
IPE submittal will be concluded in June 1998. Discussions are still ongoing with licensees
regarding Susquehanna 182 and Browns Ferry 3.
Section 3: Analysis and Evaluation of Operating Experience and Training (AEOD)
3.6 Staff Training
Eight PRA for Regulatory Applications courses are now planned for FY 1998 and FY 1999 to
meet the needs of the technical staff. Funding for these courses was obtained by reducing the
number of SRA series from two to one per year. Modifications to the PRA Basics for
Regulatory Applications, PRA for Technical Managers, and PRA Technology and Regulatory
Perspectives courses have been made to 'alude the final draft R.G.1.174 and SRP, Chapter
19. Seven PRA for Technical Managers courses are planned for FY 1998, which will allow two -
thirds of agency technical managers to attend.
Procurement actions for acquisition of risk monitor software are in process. The EPRI Risk and
Reliability (R&R) Workstation is the current industry standard for risk monitors Current plans
are to integrate the R&R workstation into the reactor technology and PRA technology curricula
to improve student understanding of configuration management, the importance of plant
operations to the risk profile of the plants, and use of the tool to provide insights regarding the
use of risk informed applications by the industry. The workstation will also be used to
demonstrato the capabilities and limits of this and simi!ar tools as they are being used by the
industry.
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Section 4: Nuclear Materials and Low Level Waste Safety and Safeguards Regulation (NMSS)
44
Risk Assessment of Material Una
The target schedule for the work to develop and demonstrate a risk assessment for industrial -
gauges containing cesium 137 and cobalt-60 using PRA (and other related techniques) has
been extended from July 1998 to September 1998. The extension is due to difficulties in
obtaining data from non-licensees related to actual and potential doses to the public resulting
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from gauges which enter the scrap metal cycle.
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The tar 9et schedule for the work to develop and demonstrate risk assessment methods for
application to medical and industrial licensee activities has been determined to be September
1998 based on scheduling of a planned Commission paper on the topic.
4.5 -
Framework for Use of PRA in'Reauintina Nuclear Materials
The target schedule for providing a p
for developing a framework has been extended from
October 1997 to January 1998 to permit interoffice coordination.
COORDINATION:
The Office of the General Counsel has reviewed this paper and has no legal objections to its
issuance.
M G (/ *
L. Jclseph Callan
Executive Dire
VOperations -
Attachments:
As stated
DISTRIBUTION:
Commissioners
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REGIONS
SECY
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ATTACHMENT 1
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PRA IYPLEMENTATION PLAN TASK TABLE (December 1997)
1.0 REACTOR REGULATION
Cegulatory Activity
Objectives
Methods
Target
iend
Status (tNs
Schedule
Offee(s)
queder)
1.1
DEVELOP
Standard revew plans for NRC
' Evaluate available industry
STANDAHL
staff to use in rak 6nformed
guidance.
/RES
REV!EW PLANS
regulatory decison making
FOR RISK.
- Develop a broad sco
INF ORM* D
standard rewew plan ( ,RP)
REGULAtlON
chapters and a senes of
applicaton specife standard
revew plan chapters that
correspond to industry
initiatives.
- These SRPs will be
consistent with the Regulatory
Guides developed for the
industry.
- Draft SRPs transmitted to
Commisson to issue for
puble comment
G,neral
497C'
IS T
497C
E97C
TS
497C
- Final SRP transmitted to
Commmagin for approval
General
1/98
in final renew
393
Changed (Note 1)
ISt
498
TS
398
Changed (Note 1)
la
PILOT
- Evaluate the PRA methodology
- Interface with Industry
NRR/RES
APPLICATIONS
ond deveksp staff positons on
groups
FOR RISK.
emerging, rak informed
INFORMED
Initiatives enciuding those
- Evaluaten of appropnate
REGUL ATORY
essociated with
documentaton te g .10 CFR.
INITIATIVES
SRP. Reg Guides, mspecten
1. Motor operated vatves
procedures. and industry
1. 2,96C
codes) to edentify elements
2 IST requirements
entcal to acheving the entent
2a Comanche Peak
of extsting requrements.
2a 398
Changed (Note 2)
2b Paio Verde
20.TDD
' Evaluaton of industry
3 ISirequirements
proposain.
3 TBD
4 Graded quality assurance.
- Evaluaton of industry pilot
4. 7/98
Changed (Note 3)
program implementaten.
5 Maintenance Rule
5 E95C
' As appropnate, complete
6 Techncalspecifcatons
pilot revews and tasue staff
6a Commisstun Approval
findings on regulatory
6a 597C
6b. Pilot Amendments issued
requests.
6b.198
Changed (Note 4)
7. Other appleatens to be
identifed later (apphcations
related to desel generator start
times and hydrogen control are
expected)
1 C = Tash prewousy comp 6eted
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Cegulatory ActMty
Obrectrves
Methods
Target
Status (this
Schedule
Offee(s)
quener)
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1.3
lNSl%',TIONS
- Provide guidance on the use of
- Develop IC #00 technical
697C
plant-specife and genene
guidance on the use of PRAs
enformaton from IFEs and other
in the power reactor inspecten
plant specife PRAs.
program.
- Revse IC 25t$ Appendix C
7/g7 C
on the use of PRAs in the
power reactor inspecton
program.
- Propose guklance options
t097
Completed
forint ton procedures
totot to 60 59 t,stuntons
and regular rnanntenance
observatens.
- Review core inspecten
1697
Completed
procedures and propose PRA
guidance where needed
- Complete revision to
propened core .nspecten
2/98
Changed (Note 5)
procedures
- losue dran Graded OA
Inspecten Procedure
498
Changed (Note 6)
- lasue final Graded QA
inspecton Procedure
7/98
C%nged (Note 6)
- Provide PRA training for
- Identify inspector functons
7/96C
inspen. tors
whch should utilize PRA
methods as input to
AEOD/TTO for their
development and refinement
of PRA trairung for inspectors
'
- Develop consolidated and
comprehensive 2 3 week PRA
1697
NRR/
Completed
for regulatory ap
tranng course. picatens
' Provide PRA training for Senior
Reactor Analysts (SRA)
- Conduct training for
Mantenance Rule baseline
&960
inspectons
' Conduct training courses
according to SRA training
Ongoing
programs
- Rotatonal assignments for
SRAs to gain working
Ongoing
NRR/RES
exponence
' Continue to provide expertise in
- Monitor the use of nsk in
Ongoing
NTIR
risk assessment to support
inspecten reports.
regionalinspection activites and
to communcate inspecten
- Develop new methodologes
program guidance and
and communcate appropnate
examples of its implementatort
uses of nsk insights to
regional offces
- Update inspecten
procedures as needed
- Asset regional offces as
needed
- Conduct Maintenance Rule
baseline inspectons
7/98
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Cogulatory ActNi'y
Objectwos
Methods
TarDet
Status (this
Scheoute
Offce(s)
quarter)
14
OPERATOR
Monstry insf.;s from HRAs and
- Reese the Knowiedge and
&95C
UCENSING
Atwides (K/A) Cataicos
IPEEEs) and operating
(NUREGs 1122 and 1123) to
1
e ronce to ioentify possible
encorporate operating .
e ncements for inclusaon an
exponence and nok 6nsghts
planned revisions to guidance for
operator licensing actuttes (rvtal
- Revise the Examiner
197C
and requahfcation)
Standards (NUREG-1021), as
needed to reflect PRA
Insights
19
EVENT
' Continue to conduct quantitative
' Continue to evaluate 50 72
Ongoing
ASSESSMENT
event assessments of reactor
events using ASP models
events while at. power and dunng
low power and shutdown
conddions
- Assess the desirab6ldy and
- Define the current use of risk
feasibihty of conducting
analysis methods and insights
quantitafive nok assessments on
in current event assessments
non-power reactor events
- Assess the easibility of
r
developing appropnate not;
assessment models
- Develop recommendations
an the feasitulity and
desirabihty of conducting
quantitative risk asses!,ments.
1C
EVALUATE USE
- Audit the adequacy of hcensee
- Identrry genere safety issues
198
NRR/RES
Changed (Note 7)
OF PRA IN
analyses in IPEs and IPEEEs to
to be audited
RECOLUTION OF
identify plant-specifc apphcability
GENERIC ISSUES
of genene issues closed out
- Select plants to be sudded
398
Changed (Note 7)
i
for each issue.
programs.
- Desende and discuss
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licensees * onetyses supporting
i
issue resolution.
- Evaluate results to determine
regulatory response; i e., no
action, additional acids, or
regulatory accon.
1.7
REGULATORY
- Assess the effectiveness of
- Develop process / guidance
ongoing
NRRIRES
EFFECTNENESS
maior safety resue resolution
for assessing regulatory
EVALUATION
afforts for reducing nsk to pubic
effectiveness.
health and safety.
- Apply method to essess
ongoing
reduction in nsk.
Note Work in this actuity will be
Integrated with broader agency
- Evaluate resulting
12,98
Changed (Note B)
efforts in response to DSI 23
effectmeness of station
blackout and ATWS rules and
Unresolved Safety issue A-45.
- Propose modifications to
Changed (Note 8)
resolution approaches, as
needed (SBO rule
imp' ament.h vi and RCP seal
assue).
- Identify othe Swes for
ongoing
Changed (Note 8)
assessment 9 4;y:gnate.
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Regulatory Activity
Objectrves
Methods
Target
Status (this
Schedule
Offee(s)
quader)
1.8
ADVANCED
' Contnue staff reviews of PRAs
- Continue to apph current
ongoing
REACTOR
for design certifcation
staff review process
REVIEWS
appicatens
-
- Devehp SRP to support revww
- Develop draft SRP to tech
Changed (Note g)
of PRAs for design certifcatic.a
staff for rev ew and
reviews of evolutonary reactors
corcurrence
(ABWR and System 80+)
- rrialize SRP.
- Develop indeper. dent technical
' Reevaluate nsk-based
12/96C
NRR/ RES
analyses and critena for
aspects of the techncal bases
evaluating tndustry initiatives and
petitons regarding sirnphfcaten
Inssghts from NUREG-1150
the new source term
(EP) regulations.
Informat.m from NUREG-
1465. and available plant
design and PRA informaton
for the passive and
evolutonary reactor designs.
1.g
ACCIDENT
- Develop generic and plant
- Deveioo plant-specife A!M
NRR/RES
MANAGEMENT
specife nsk ins s to support
insghtsinformaton for
staff auditsof
accident
selected plants to serve as a
management
programs at
basis for assessing
selected plants
cor p6eteness of utihty A/M
program elements (e g ,
severe accident training)
1,10
EVALUATING IPE
- Use insights from the staff
' Reyww the report *1PE
E97C
NRR/RES
INSIGHTS TO
review of IPEs to idert.N
Program Perspectives on
DETERMINF
potental safety,
Reactor Safet
technical ssues, policy, and
Performance *y and Plant
NECESSARf
to determine en
and identify the
FOLLOW UP
appropnate course of action to
initiallist of required staff and
ACTIVnIES
resolve tnese potentialissues,
industry actions (if an )
and to identify possible safety
including insghts on
_
enhancements.
- Revww IPE results and
6/99
NRR/RES
Changed (see
interact with heensees.
Attachment 3)
- Determine appropnate
- Complete backfit analysis
12<99
Changed (see
approach for tracks tne
and actions.
regulatory uses of 1
PEEE
Attachment 3)
results
- Followup on accident
NRR/
Changed (see
i
management programs and
regions
Attachment 3)
Iconsee-stated actions.
- If sopropriate develop
1298
NRR/ RES
a
h for hnking
i
PEEE data bases.
4
.
.
.
..
.
. - -
- - - - - _
,
. _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _
.
.
20 REACTOR SAFE *Y RESEARCH
Cogulatory Adivty
Objectives
Methnos
Target
Status (this
Schedule
Offee(s)
quarter)
,
11
DEVELOP
Regulatory Guides for industry to
- Draft PRA Regulatory
RES/NRR
<
I
REGULATORY
use in rak informed regulaton
3uides transnuttedto
,
l
GUIDES
- ommesson for aproval to
j
issue for pubic comment.
l
General
C
l
C
t
C
GOA
C
TS
C
- Forwl PRA Regulatory
3uides transmitted to
l
Commission for approval.,
[
Genersi
1/98
in final revww
398
Changed (Note 1)
isi
498
GOA
396
Changed (Note 1)
TS
398
Changed (Note 1)
33
TECHNICAL
- Provide techn. cal support to
- Continue to provide ad hoc
Continuing
SUPPORT
agency users of risk
technical support to agency
assesernent in the form of
PRA users
support for nak based
}
regulaten activitwo, techncal
- Expand the database of PRA
Continuing
reviews, essue nok
nodels available for staff use,
assessments, statist. cal
expand the scope of avadabie
analyses, and aevelop
'nodels to include external event
guidance for agency uses of nok
and low power and shutdown
assessment
accidents, and refine the tools
weded to use these models, and
- ontinue maintenance and user
w
for SAPHIRE and
CS computer codes
- Support agency efforts in
'eactor safety improvements in
Continuing
'ormer Soviet Union countnes.
3.3
SUPPORT FOR
' Modify 10 CFR 52 and develop
- Develop draft guidance and
5/98
NRf1 STANDARD
. Mance on the use of updated
'une.
REACTOR PRA
". tAs beyond denen cenirmation
REVIEWS
(as desenbod in SECY 93487).
- Solett pubic comment.
11/98
- Finales staff guidance and
12,99
'ulo =
,
24
METHODS
- Devoiop, demonstrate, maintain.
- Develoo and demonstrate
9/98
DEVELOPMENT
and ensure the quality of
Tiethods for including aging
AND
methods for performina,
effects in PRAs.
DEMONSTRATION
revww1ng, and ussng F4tAs
and related techniques for
- Develop and demonstrate
9<98
,
existing reactor designs.
Tethods for including human
errors of commissen in PRAs.
- Develop and comonstrate
netfods to incorporate
gnaational performance into
- Develop and demonstrate
9/96
methods for flru nsk analysis.
- Develop and demonstrate
6/99
nothods for assessing
'ehability/nsk of digital
systems
5
,.
.
. .. .
.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
.
.
.
Cegulatory Actrvity
Objectives
Methods
Target
Status (this
'
Schedule
Office (s)
quarter)
15
IPE ANDIPEEE
- To evaluate IPE/IEEE
- Complete revews of IPE
Changed (Note 10)
REV?EWS
submittats to obtain reasonable
6ubmittals.
assurance that the hcensee has
adequately anatyzed the
- Complete reviews of IPEEE
699
piant desgn and operations to
bubmrttais
discovervulnersbees andto
document the sgnificant safety
- Continue regionat IPE
C
insghts resulting from
yesentations
IPEstPEEEs
'lasue IPE insghts report for
10/96C
xiblic comment.
- FinalIPE 6nsghts report
9S7
Completed
- losue prehminary IPEEE
1/98
in final review
insghts report
=,
- Initiate revew of eight
6/98
New milestone
additionalIPEEE submittals
- Comp 6ete contractor
6,98
New milestone
avsluations on twelve IPEEE
wbmittals
- lasue draft IPEEE insghts
699
New milestone
report for comment
- lasue final IPEEE insghts
1299
oport
2.6
GENERIC ISSUES
' To conduct genene safety issue
- Continue to pnortize and
Continuing
PROGRAM
ma
ment activites,
eserve genenc issues
inct ing pnorit&tation, resolution,
and documentation, for issues
relating to currently
rating
reactors. for
need
reactors as appropnate, and for
development or revtsion of
associated r ulat and
standards 6n me a
17
NEl INITIATIVE TO
- Review NElinstetive to conduct
- Agree on ground rules for
198
RES/NRR
CONDUCT
three pilot "whole
plant"
study.
"WHOLE PLANT *
nsk intormed studes of
RISK STUDY
requirements vs nsk and cost
- Complete study
2.8
PRA STANDARDS
- work with industry to develop
- Initiate actrvity.
9S7C
DEVELOPMENT
national consensus standard for
PRA scope and quality
- Finalize standard.
19
LOW POWER AND
- Collect studes of LP&S nsk as
- Collect and review existing
9S8
SHUTDOWN
a benchmark for assessi the
.P&S nsk information (domestic
BENCHMARK
need for further staff
es
and foregn).
RISK STUDY
- Instete additional work.
10S8
l
l
110
SAFETY OOAL
'Assesa need to revtse
- Initete disct=sion with ACRS
2/98
l
REVISION
Commissiorfs Safety Goalto
i
make core damage frequency a
- Recommendation to
198
l
fundame ital goal and make other Dmmission
changer,,
l
6
,
_ _ _ _ _ - _ _ - _ _ - _ _ _ _ - _ _ - _ - _ - - _ - _ _ _ - - - _
.-.
.
.. .
. . .
.
.
'
,
.
3 0 ANALYSIS AND EVALUATION OF OPERATING EXPERIENCE, AND TRAINING
Regulatory
Otyctives
Methods
Target
Status (t*us
Activity
Schedule
Offee
quarter)
3.9
RISK BASED
- Use reactor opeisting
- Trend performance of nsk.
1198
TRENDS AND
exponence data to assess the
important components
PATTERNS
trends and pottems in ooiapment,
ANALYSIS
systems, inrtistire " .. hurrun
- Trend performance of nsk.
1Z98
performance, s.
ant
important systems.
.
accxlent sequence.
l
- Trend fr
of nsk.
3,98
!
6mportant
events
- Trend human performance
for rehatuity charactenstes
- Evaluate the effectiveness of
- Trend reactor operating
As Needed
teensee actons taken to
exponence associated with
resolve nok signifcant safety
specife safety issues and
losues
assess nsk impications as a
measure of safety
performance
- Develop trending methods and
- Develop standard trending
C
special databases for use in
and statistical anatysis
AEOD trending activttes and for
procedures for 6dentified areas
PRA ap
offees. pications in other NRC
for rehatulity and statistcal
apphcations.
- Develop special software
CCF.C
and databases (e g common
Penode
cause failure)for use in
updates
trending analys,s and PRA
studies
32
ACCIDENT
- Ide, tify and rank nsk
- Screen and analyze LERs,
Ongoing
SEQUENCE
sgnifcance of operatonal
AITs, llTs. and events
PRECURSOR
events
identifed from etner sources
(ASP) PROGRAM
to obtain ASP events.
- Perform independent revew
Annual
of each ASP analyses,
report,
Licensees and NRC staff peer
Ongoing
review of each analysis.
- Complete quauty assurance
of Rev. 2 simphred piant
3,97C
specife models
- Complete feasitxl tudy for
low
and shut
11/96C
- Complete initial containment
performance and
C
consequence models.
- Compte development of the
Level 43 models
7/99
- Comge the Rev. 3
s
plant specirc
11K)1
- Complete extemal event
models for fire and earthquake
- Complete low
power / shutdown models
- Provide supplemental
- Share ASP analyses and
Annual rpt
information on plant specife
insights with other NRC
performance.
offces and Regions.
,
7
e
x
.
.
Regulatory
Objectives
Aethods
Target
Status (this
ActMtf
Schedule
Offee
guarter)
33
tNDUSTRY 8t!SK
- Provide a rnessure of industry
- Develop program plan whch
C
TRENDS
nsk that es as complete as
possible to oetermine whether
AEOD actMties whch use
not is increasing. decreasing, or
desgn and operating
remaining constant over time
exponence to assess the
emphed level of rtsk and how ll
es changing
- Update plan for nsk based
Changed
ana!yss of reactor operating
(Note 11)
exponence
- Imp 6ement program plan
6/99
elements whch willinclude
piard. specifc models and
insghts from IPEs,
component and system
relaatulity data, and other nsa.
important :;esgn and
operational data in an
integrated frame work to
scally evaluate industry
30
RISK BASED
' Estabish a comprehenstve set
- Identify new or improved
C
PERFORMANCE
of performance indicators and
nsk-based Pls whch use
INDICATORS
supplementary cerformance
component aN system
rneasures whch are more
rehabdity models & human and
clow*e related to nsk ar.d provide
organizational performance
bolo e. sty indcation and
evaluation methods
con 9mation of plant performance
problems.
- Develop and test candidate
Pis/ performance measurts.
900
- Implement nak-based Pts
with Commission approval
101
35
COMPILE
- Compile operating exponence
- Manage and maintain SCSS
Ongoing
OPERATING
lnformation In database systems
and the PI data base, provice
EXPERIENCE
suitable for uantitative rehatxlity
oversjght and access to
DATA
and rak ana is appications.
Information
Id be scrutable
SSPl, compile IPE failure
to the source at the event level to
data, collect plant-specife
the exter.t practical and be
rehability and availatxiety data.
i
!
suffcient for estimatino reinatxlity
and avestatxhty parameters for
- Develop, manage, and
Ongoing
NRC appleations
maintain agency ostabases for
rahatxutyravailatulity data
(equipment performance
initiating events, CCF, AhP,
and human performance
data).
- Determine need to revise
698
LER rule to eliminate
unnecessary and less safety.
sgnifcant reporting
- Determine need to revise
6/98
reporting rules and to better
human performance events.
- Pubhsh revised LER rule.
10/9C
8
s
2
-,
-
_
____ ____ ___ _ _ _ __ _ _ _
.'
.
__
Regulatory
Obrectrves
Methods
Target
Status Ohis
Actrvey
Schedule
Offce
quarter)
t
,
i
36
STAFF TRAINING
' Present PRA cumculum as
- Continue current cWacts to
Ongoing
presently scheduled for FY
present courses es
1998
scheduled.
- Maintain current reactor
technology courses that
include PMA ensghts and
apphcations
courses wa
- Rowew cunent PRA course
matenal to ensure consistency
wth Appendix C
- Develop and present Appendix
- Prepare course materal
C
RES/AEOD
C training courses
based on Appendix C.
- Present courses on
C
Appendir C
- Determine staff requirements
- Review JTAs performed to
C
for traini} retuding
date.
ty t
a
- Perform re seentatrve JTAs
C
for staff
ens (JTA Pilot
Program .
- Evaluate staff trainino
C
requirements as identiTod in
the PRA im mentation Plan
and the Tec
I Training
Needs Survey (Phase 2) and
incorporate them into the
training requerernents analysis.
- Analyze the results of the
JTA Pilot Program and
C
determine requirements for
additional JTAs.
- Complete JTAs for other
staff posatons as needed.
C
- Sohcit a review of the
proposed training
C
requirements
- FAalize the requirements.
C
- Reese current PRA cumculum
- Prepare new courses to
Ongoing
and develop new training
meet identified needs.
program to fulfill 6dentifed staff
neeos.
- Rewse current PRA courses
Ongoing
i
to meet identifed needs.
f
- Rewse current and New
PRA course to include Reg -
9/97C
Guide and SRP information
- Revise current reactor
technology courses as
Ongoing ,
necessary to include
additional PRA Insigtds and
applications
- Present revised PRA training
- Estabirah contracts for
Ongoing
curnculum.
presentata:.of new PRA
curnculum.
- Present revised reactor
Ongoing
technoicgy courses.
rove courses based on
Ongoing
9
- - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - - - _ _ -
.
.
4 0 NUCLEAR MATERIALS AND LOW. LEVEL WASTE SAFETY AND SAFEGUARDS REGULATION
Regulatory ActMty
Objectives
Methods
Target
Status (this
Schecale
Offee(s)
quarter)
4.1
VAllDATE RISK
- Validate nsk anatysis
- Hold a workshop consisting
BS4
ANALYSIS
metxx3 ology developed to assess
C
METHODOLOGY
the relative profile or most hkoty
examine existing work and to
DEVELOPEDTO
contnbutors to misedministration
provide recommendations for
)
I
ASSESS MOST
for the gamma stereotecte dence
further methodologea!
I
LIKELY FAILURE
(gemma knife)
development.
MODES AND
HUMAN
- Examine the use of Monte
9/95
PERFORMANCE
Carlo simulaten and its
C
IN THE USE OF
apphcation to relative nsk
INDUSTRIAL AND
profding
MEDICAL
RADIATION
- Examins the use of expert
DEVICES
judgement in developing error
C
rates and consequence
measures
- Continue the development of
- Develop functionalty based
RES/
the relative nsk methodology, with
genene event trees
the additen of event tree
modehng of the trachvtherapy
remote after loader '
- Extend the appicaten of the
' Develop genere nsk
RES/
metnodology and as further
approaches.
development into additional
devees. including teletherspy
and the pulsed high dose rate
after loader
!
48
CONTINUE USE
- Develop decisen enterna to
- Conduct enhanced
BS4 PR
RES/NMSS
OF RISK
support reculatory decision
partcipatory rulemaking to
C
ASSESSMENT OF
making tha't incorporates both
establish radmiogeal entena
Final Rule
ALLOWABLE
determaste end nsbbesed
for decon.missoning nuclear
Pubhshed
RADIATION
engineenng judgement.
sites; techncal e"prart for
7/97 C
RELEASES AND
rulemaking includtri
DOSES
comprehenstve nskbood
ASSOCIATED
assessment of resittual
WITH LOW LEVEL
contamination.
RADIOACTIVE
WASTE AND
- Develop uidance for
2/98
REstDUAL
I
ng the radologeal
ACTMTY.
er ena for iconse terminston..
the extent practcable to
Ongoing
develop common approaches,
assumptons, and models for
evaluating nsks and attemative
remediaton methodologies
(nsk harmontraton)
4.3
DEVELOP
- Develop a Branch Techncal
- Solicit pubhc comments
5/97 C.
NMSS/RES
GUIDANCE FOR
Positen on conducting a
THE REVIEW OF
Performance Assessment of a
RISK
LLW disposal facdity
- Pubhsh final Branch
TBD,
ASSOCIATED
Techncal Positen
Dependent
WITH WASTE
REPOSITORIES
on
Resources
10
.
.
.
.
.
.
. . .
_.
. _ _ _ _ _
. _ _ _ _ _ _ _ _ _ _ - _ _ _ .
.
.
..
.
.
RegulWory ActMty
Obrectrves
Methods
Target
Status (tfus
Schedule
Offee(s)
cuarter)
44
RISK
- Develop and demonstrate a nsk
- Develop and demonstrate
B98
Changed (Note 12)
ASSESSMENT OF
assessment for Industnal gauges
methods for determining the
MATERIAL USES
containing cessum-137 and
nok associated with industnli
gauges containing cessum..J7
related techrwques
and cobalt 60
- The assessment should allow
- Fnal report as NUREG 12s96
Changed (Note 12)
for mcdfcaton based on
changes m regulatory
- Wcrkin0 Group with
&96
Changed (Note 13)
requrements
contractor assetance to
identify and document a
- Use empircal data as much as
t.achnical basis for a risk.
practcatde
informed approach to the
regulaton of nuclear
- Develop and demonstrate nsk
byproduct matenal, and to
assessment rnethods for
develop plans for a graded
appicaten to medcal and
approach to nuclear byproduct
industnel heensee actmtes
matenal regulation based on
nsk mformaton
45
FRAMEWORK
- develop a framework for
- Provxkt plan for developing
1/98
Changed (Note 14)
FOR USE OF PRA
applying PRA to nuclear matenal
framework
IN REGULATING
uses, similar to the one
NUCLEAR
deve g'ed for reactor regulation
- Complete framework
MATERIALS
(SECY-95-280), where
appropnate.
!
'
1
11
.
_ _ _ - _ _ _ _ _ - - _ _ - - - _ - _ - - _ -
- - - -
.
.
5.0 HIGH LEVEL NUCLEAR WASTE REGULATION
,
Cogulatory ActNRy
ObjectNes
Methods
Target
Status (this
Schedule
Offee(s)
cuarter)
51
REGULATION OF
- Develop guidance for the NRC
- Assist the staff in pre-
Ongoing
{
HIGH-LEVEL WASTE
and CNWRA staffs in the use of
hcensing actNtes and in
PA to evaluate the safety of HLW
Icense appicaten revews
programs
- Develop a techncal
assessment capattityin totab
system and subsystem PA for
use in hcensing and pre-
j
licensing revews.
-
- Combine specialized
techncal drsciplines (earth
scences and engineer )
with those of s,ystem__
i
,
_
rs
to improve ...u my.
- Idenhfy agnifcant events,
- Perform sensitNtty studes
Ongoing
processes, and parameters
of key techncallasues ussng
effecting total system
iterative performance
performance
assessment (IPA)
- Assist the staff to maintain
Ongoing
results and insignts to evaluate
and to refine the regulatory
proposed change s to regulatons
structure in HLW disposal
gove
the ootential repository
regulaticas that pertain to PA.
at Yucca
ntain.
- Apply IPA analyses to advise
i
l
EPA in its development of a
Yucca Mountain regulaten
1
[
- ~
- Apply IPA enalyses to
develop a site-specife
regulation for a Yucca
Mountain site
- Continue PA activites dunng
- Provide guidance to the
Ongr ng
interactions with DOE dunng the
DOE on site charactenzation
pre-heensing phase of repository
requirements ongoing oesign
development, site
work, and hcensing issues
charactenzaton, and repository
important to the DOE's
design.
development of a complete
t
and high-quality license
,
appleation.
- Compare results of NRC's
Iterstrve performance
identify major
differences /rssues.
3.3
APPLY PRA TO
- Demonstrate methods for PRA
- P opere user needs letter to
497C
RUS/NMSS
SPENT FUEL
of spent fuel storage facihtes.
RES.
STORAGE
FACILITIES
- Conduct PRA of dry cask
9<99
storage.
3.3
CONTINUE USE OF
Use PRA methods, results, and
- t,pdate the database on
End cf FY
RISK ASSESSMENT
insights to evaluate regulations
transportation of raccactive
99
IN SUPPORT OF
governing the transportation of
matenals for future
RADICACTIVE
radcactive matenal.
MATERIAL
appications
TRANSPC9TATION
- Revalidate the results of
&99
NUREG-0170 for spent fuel
shipment nsk estimates.
12
v
'
A
_ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _
_
'
.
4
Notes
,
1.
The general regulatory guide and btandard Review Plan for use of PRA in plant-specific
current licensing basis changes will be transmitted to the Commission in the near future,
To permit efficient incorporation of the resolution of policy issues contained in these
documents into the application-specific regulatory guides and SRP sections, completion of
these guides and sections has been delayed until March 31,1998, a change from their
previous completion date of December 31,1997.
2.
The staffs RI IST team is currently working on a draft SE for the Comanche Peak RI-IST
program. The staff and TU Electric have been actively interacting through meetings and
discussions as the licensee develops a RI IST program description that is sufficiently
detailed and consistent with the draft Rl IST guidance provided in DG 1062. TU Electric
has indicated that it would be able to complete a daft revision to their RI IST Program
Description by the end of January 1998. The staff will continue to develop a draft SE
based on the licensee's responses to the staffs RAls and discussions with the licensee.
Assuming TU Electric finalizes its RI IST Program Description by mid February 1998, the
staff anticipates having a completed SE to the Commission on the proposed RI IST
program for Comanche Peak in March 1998.
3.
The completion date for the Graded Quality Assurance pilot application has been revised to
July 1998 to reflect the anticipated issuance date of the final GOA inspection guidance.
4.
With respect to the risk-informed TS pilot program, the staf' received a supplemental
amendment request from SONGS in early January 1998 tc put the configuration risk
management program (CRMP) description into the SONGS TS. The staff will review the
CRMP and, if acceptable, issue the risk-informed TS amendments for SONGS. Once
similar supplemental amendment requests are received frora the remaining pilot licensees,
the staff willissue those pilot plant amendments. Based on information from the CEOG,
the staff expects to receive the majority of the supplemental pilot amendment requests in
the first quarter of 1998. With receipt of the SONGS supplemental request, the staff
anticipates completing the SONGS review as the lead pilot plar:t and issue the amendment
by March 31,1998. This is a change from the previous date of December 31,1997, for
issuance of the lead pilot plant amendment, because of the decision by the originallead
plant not to oursue risk-informed TS changes at this time.
5.
The NRR Intipection Program Branch proposals for revising core inspection procedures
have been transmitted to the appropriate NRR technical branches having responsibility for
l
specific core inspection procedures. Due to the large number of branches involved,
completing all indivi :ual branch concunences is anticipated to take an additional two
months. The revised completion date for this task is February 1998.
6
A deci ion has been reached to generate the risk-informed regulatory documents in a
sequential manner, with the application specific guidance following the general regulatory
guide and standard review plan. Under this schedule, the regulatory guide for graded QA
will be finalized by the end of March 1998. Since the graded QA inspection procedure will
be dependent upon the technical content of the companion regulatory guide, the draft
graded QA Inspection Procedure will be prepared by April 1998 and finalized in July 1998
after having received appropriate NRC reviews.
13
,
a
- _ _ - _ _ _ _ _ _ _ _ .
-.
.
7.
As part of the IPE follow-up program, the staff is in the process of identifying generic issues
'
to be audited. These issues will be those which have been explic.itly identified and
addressed by the licensee as part of the IPE process.
A report that identifies the above generic issues and staff views on the adequar.,y of the
proposed resolution is under preparation. The report will provide the basis for the selection
of generic safety issues to be audited and selected plants. The staff has moved the
completion date for this milestone to March 1998, in order to utilize the report in the audit
process.
In addition to the .uove issues, RCP seal LOCA had been identified as a dominant
contributor to core damage frequency in many PWR IPEs. The staff has a separate
ongoing activity in RES to address this issue under Generic Safety issue 23, and will utilize
IPE insights in the proposed resolution.
8.
In at SRM (9700207) datsd May 28,1997, the Commission requested that the staff
proviie the scooe and Nhedule of activities related to using IPE results to assess
regulatory effectianc.s in resolving major safety issues. . lith respect to scope, the staff
identified three major safety issues for assessment. The selection had been based on both
the potential nsk significance of the issue, and the fact that probabilistic techniques were
!
used extensively in the resolution process. These issues include:
1. Resolution of USI A-44 Station Blackout at Nuclear Power Plants
2. Resolution of USI A-45 Decay Heat Removal Reliability
3. Resolution of USI A-09 Anticipated Transient Without Scram
To evaluate the three major issues, the staff will utilize both representative plants, and
information contained in NUREG-1560, to audit and draw conclusions regarding regulatory
effectiveness. Information generated under Task 1.6 and Task 1.10 will also be integrated
into the assessment process. In particular, the RCP seal LOCA and station blackout
issues are closely related; the station bisckout analysis in this activity willincorporate the
results of the RES seal LOCA analysis discussed in Note 7.
These tasks may expand the staff's consideration cf other safety issues and effectiveness
of the regulatory process. The staff willinform the Commission of any additional safety
issues that come under consideration. The staff plans to complete it analysin of the three
issues by the end of December 1998, and will recommend ai that time any additional staff
action.
9.
Due to personnel being assigned to higher priority activities, such as risk-informed pilot
initiatives and IPE followup activities, the staff is reassessing their position regarding the
development of an SRP, especially since there are no new advanced design certification
submittals anticipated.
10.
The staff has reviewed all the 76 IPE submittals and issued staff evaluation reports (SERs)
on their findings to each licensee. In three of the SERs, it is indicated to the licensees that
the staff was not able to conclude that the licensee met the intent of Generic Letter 88-20
for their plant (s). These three IPEs include Crystal River 3, Susquehanna 1&2, and
Browns Ferry 3. The licensee for Crystal River 3 nas indicated their intention to submit an
updated analysis (February ;998) addressing the staffs concerns, it is anticipated that the
14
___ - _ __- ____ _ ___ _____
.
t
review of this new IPE submittal will be concluded in June 1998. Discussions are still
ongoing wit! licensees regarding Susquehanna 1&2 and Browns Ferry 3.
.
11.
This 'ask has been subsumed into the office operating plan, which is periodically updated.
12.
The target schedule for the work to develop and demonstrate a risk assessment for
industrial gauges containing ces;um 137 and cobalt-60 using PRA (and other related
techniques) has been extended from July 1998 to September 1998. The extension is due
to difficulties in obtaining data from non-licensees related to actual and potential doses to
the public resulting from gauges which enter the scrap metal cycle.
13.
The target schedule for the work to develop and demonstrate risk assessment methods for
app!ication to medical and industrial licensee activities has been determined to be
September 1998 based on scheduling of a planned Commission paper on the topic.
14.
The target schedule for providing a plan for developing a framework has been extended
from October 1997 to December 1997 to permit interoffice coordination.
l
I
15
.
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,
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.
.
4
Attachment 2
Sta# Requirements Memorandum
dated May 28,1997
i
i
P
/.ES/ DST
TEL 301-415-5062
Jur. 03'97
11:15 No.007 P.03
Acticn (Morrison, Nu/
.
Collins. NRR
.
- t
UNffED 5MES
Cygg ,Cg]]gn
g
NUCLEAR Rt0UL.AT0ftY C04mm8840N
Jon]en
-
y
- ApesGTon.or same
Thotpson
%
AN RESvuNse, FLk:AbE
(
May 28, 1997
REFER TO g g 70507
Blahe
-
Ross, AE0D
!
MEMORANDUM 70:
L. Joseph Callan
.
Director for Operationa
Exec # iv' k(%
FROM:
Johr v. Hoyle, Secretary
~
SUBJECT:
STAFF REQUIREMENTS - ERIEFING ON IPE INSIGHT
REPORT, 2:00 P.M
WEDNESn&V, M&V 7,
1997.
COMMISSIOhT.RS' CCNFERENCE ROOM, ONE WHITE
FLINT NORTH, ROCXV:LLE, MARYLAND (OPEN To
PUBLIC ATTENDANCE)
-
.-
The countiwmivu was briefed by the NRC stef f en the Individual
Flant Examination (IPE) insight report.
The Comission asked the
st a:l'
to expedite activhium in .Le !vilu lug areas:
(U using
IPE results to prioritize inspection activities: (2) improving
regional capabilities for the use of PRA and risk insights; and
(3) providin
ted inspecttr training,
fEDO)
MES)j
iSECT suspense:
wu'p3o
9700206
The Commission asked the stait to provice tne scopte anc scr.edule
of activities relar.ed to using IPE results to assess regulatory
effectiveness in resolving r.ager safety issues.
The comissien
stacifically reqv.2ted that the staff provide an estimate cf the
average cost to respond to the Staticn Blackout. rule per persen-
rem averted 1.n achieving an average reduction in core damage
frequency of 2E-5/RY.
These activities should be coordinated
with the regulatory effettiveness organization,
fEBO-)
(NRR)
(SECY suspense:
6/27/97)
9700207
After the IPE database has been placed on the Internet, the staff
should consider allowing licensees to update their IDES
voluntarily to reflect changer i.a plant configuration.
(RES)
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,
.
.
.
.
, , .
-
_ _ _ _ _
_ - _ _ _ _ _ _ _ _ _ _
..
.
-d
Attachment 3
lPE Follo36222matarn
The IPE program was initiated to have licensees evaluato the;r plants for vulnerabilities to
severe accidents and to take actions to correct these vulnerabilities, where appropriate. In this
process it was recognized that licensees would gain an appreciation of their plant's overall
susceptibility to severe accidents which would help in developing accident management
tirategies and programs. In this regard the IPE pregam was principally for the benefit o'
licensees. Now, however, as a result of completion of the IPE reviews (except for the three
plants where comn!stion is still under discussion) and insights report (NUREG-1560), the staff is
now in a position to utilize these results to follow up and see if:
any additional plant specific improvements are warranted,
-
licensees have followed through on the actions they indicated they were taking as a
-
result of their IPE, and
any additional generic regulatory activities should be undertaken.
-
To accomplish this the staff has developed an IPE followup program which willinvolve the
efforts of RES, NRR and the Regions. The followup program will consist of the following
sctivities:
1
1)
reviewing the iPE results for risk significant items that may warrant further attention.
Examples of the screening criteria for selection of plants and items for additional
followup are as follows:
any contributor with a aCDF' >10-5 RY or
/
-
any contributor with a 6LERF2 >104/RY
-
2)
reviewing the IPE results for similar plants and whether or not actions taken by some
l'
plants are applicable to other plants of similar design,
{
3)
reviewing licensee responses to specific containment performance improvement items
identified in the IPE generic letter supplements to see if additional actions are
warranted,
4)
reviewing the basis for very low risk contributors that appear to be out of line with other
plants (i.e., was the analysis overly optimistic and should further action be taken?),
5)
assessing licensee stated actions (e.g., safety enhancements) resulting from their IPE to
see if, in fact, they have been completed,
' Core Damage Frequency
8 Large Early Release Frequency
1
. _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ .
,
9
'
2
6)
assessing licensee accident management programs to see if, in fact, they reflect the
results, assumptions and actions from the IPE. This action will be carried out through
the staff assessment of the licensee's Severe Accident Management Guidelines
(SAMG).
7)
assessing the results for their implications for the resolution of generic safety issues or
other major safety issues.
These activities are in addition to actions already underway to incorporate '.ne IPE insights into
the NRC inspection program.
Implementation of this program will consist of RES providing to NRR information related tc
activities 1 through 4 above with NRR then discussing with licensees the appropriateness of
additional actions. This will provide licensees an opportunity to provide updated information
related to these activities and ultimatcly for NRR to take regulatory action, if such action is
warranted and can be justified by the backfit rule. Activities 5 and 6 will be performed by NRR,
,
with Regional followup as necessary. Activity 7 is addressed by items 1.6 and 1.7 of the PRA
Implementation Plan.
High priority issues identified in the screening process will be pursued as they are identified.
Dates for accomplishing these activities relative to IPE followup are:
RES supply information to NRR on items 1-4
12/98
.
NRR interact with licensees on appropriateness
6/99
.
of additional actions for items 1-4
Backfit analysis and actions complete
12/99
.
Item 5, identify items for Regional followup
9/98
.
Item 6, identification of IPE insights for Se'. sre Accident
9/98
.
Management Guidelines
The specific IPEEE followup schedule will be developed following the completion of the IPEEE
4
reviews.
.
-