RIS 2002-14, Proposed Changes to the Safety System Unavailability Performance Indicators

Proposed Changes to the Safety System Unavailability Performance Indicators

ML022740012
Person / Time
Issue date:	09/30/2002
From:	Beckner W NRC/NRR/DRIP/RORP
To:
Sanders S, NRR/DIPM, 415-2956
Shared Package
ML022740008	List: RIS 2002-14, Proposed Changes to the Safety System Unavailability Performance Indicators
References
RIS-02-014, Suppl 1
Preceding documents:	ML022410004 (28 August 2002)
Download: ML022740012 (5)

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001 September 30, 2002 NRC REGULATORY ISSUE SUMMARY 2002-14, SUPPLEMENT 1 PROPOSED CHANGES TO THE SAFETY SYSTEM UNAVAILABILITY

PERFORMANCE INDICATORS

ADDRESSEES

All holders of operating licenses for nuclear power reactors, except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel.

INTENT

The U. S. Nuclear Regulatory Commission (NRC) is issuing this supplement to Regulatory Issue Summary (RIS) 2002-14 to provide to the addressees revised versions of the three attachments to the RIS.

BACKGROUND

Regulatory Issue Summary 2002-14 informed addressees that the NRC was starting a 6-month pilot program on September 1, 2002, to evaluate changes to the safety system unavailability (SSU) performance indicators (PIs), and that the pilot program would be assessed midway through the test period to determine if more than six months were needed to obtain meaningful results. The RIS and its three attachments provided guidance to participating addressees for submitting PI data to the NRC and on the program success criteria.

Addressee participation in the pilot program is voluntary and participants were asked to conform to the guidance in the RIS for the voluntary submission of PI data.

Addressees

were also informed that updated guidance would be provided in the form of revisions to the attachments to the RIS, namely, Attachment 1, an excerpt from Draft NEI 99-02, Rev. 0, Regulatory Assessment Performance Indicator Guideline, Section 2.2, Mitigating System Performance Index, and Attachment 2, Draft NEI 99-02, Rev. 0, Appendix F, Methodologies For Computing the Unavailability Index, the Unreliability Index and Determining Performance Index Validity.

SUMMARY OF ISSUE

Since the issuance of RIS 2002-14 on August 28, 2002, Attachments 1 and 2 have been updated and Attachment 3 has been revised. The revised attachments are attached to this RIS

supplement.

ML022740008

RIS 2002-14, Sup. 1

BACKFIT DISCUSSION

This RIS supplement requires no action or written response. Therefore, the staff did not perform a backfit analysis.

FEDERAL REGISTER NOTIFICATION

A notice of opportunity for public comment was not published in the Federal Register because this RIS supplement is informational.

PAPERWORK REDUCTION ACT STATEMENT

This RIS supplement does not request any information collections.

If there are any questions about this matter, please contact one of the persons listed below.

/Original signed by: TReis/

William D. Beckner, Program Director Operating Reactor Improvements program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Technical contact: Serita Sanders, NRR

301-415-2956 E-mail: sxs5@nrc.gov Attachments:

1. Draft NEI 99-02, Rev. 0, Regulatory Assessment Performance Indicator Guideline, Section 2.2, Mitigating System Performance Index

2. Draft NEI 99-02, Rev. 0, Regulatory Assessment Performance Indicator Guideline, Appendix F, Methodologies For Computing the Unavailability Index, the Unreliability Index, and Determining Performance Index Validity

3. Mitigating System Performance Index Pilot Program Success Criteria

4. List of Recently Issued NRC Regulatory Issue Summaries

Package ML022740008, ML022740012, ML022740072

• See previous concurrence OFFICE OE:RORP:DRIP IIPB:DIPM SC:IIPB:DIPM BC:IIPM:DIPM

NAME JWShapaker* SSanders* MSatorious* CCarpenter*

DATE 09/ /2002 09/19/2002 09/26/2002 09/29/2002 OFFICE OGC SC:RORP:DRIP PD:RORP:DRIP

NAME HJMcGurren* TReis* WDBeckner*

DATE 09/30/2002 09/30/2002 09/30/2002

Attachment 3 RIS 2002-14, Sup. 1 Mitigating System Performance Index Pilot Program Success Criteria The Mitigating System Performance Index (MSPI) success criteria listed below will be met if there is general agreement among internal and external stakeholders that the criteria have been met.

a. The occurrence of a single failure of an MSPI monitored component by itself, absent any other failures or unavailabilities, should rarely exceed the green/white MSPI threshold as measured from the baseline value. The term rare is defined as minimizing the inconsistencies across plants, within plants, and within systems such that there is no undue burden on resources, and the objective of having consistent publicly displayed results can be achieved.

b. False positive and false negative rates can be established for the chosen statistical method, and instances where the MSPI cannot meet the criteria are rare.

c. Instances where the results from the MSPI calculational methodology are not consistent with the SPAR-3 models are rare and the differences are explainable.

d. The MSPI pilot plant participants can identify and compile the risk significant functions for the monitored systems in a readily inspectable format and can compile a set of predetermined success criteria for those risk significant functions.

e. The active components in the monitored systems are appropriate for inclusion in the MSPI and are a manageable number of components under the MSPI.

f. By the end of the pilot, MSPI data can be accurately reported and quality checked.

g. By the end of the pilot program, inspection procedures and MSPI pilot guidelines are sufficiently detailed to minimize MSPI Questions and NRC feedback forms.

h. MSPI Questions and NRC feedback do not reveal any unresolvable issues.

i. Data collection inconsistencies between the maintenance rule and the MSPI can be reconciled in order to eliminate or significantly reduce separate reporting.

j. Differences between the linear approximation models generated by licensee probabilistic risk assessments and those generated by the NRC SPAR-3 models can be reconciled.

k. The MSPI produces no new unintended consequences that cannot be resolved.

Upon the successful meeting of the success criteria, with a determination that the MSPI pilot is a valid and appropriate means of measuring risk for the monitored systems, the MSPI will suffice as the measure of assessment and not the significance determination process for single failures of the active components within the scope of the MSPI. Any significant problems will be resolved before full MSPI implementation.

Attachment 4 RIS 2002-14, Sup. 1 LIST OF RECENTLY ISSUED

NRC REGULATORY ISSUE SUMMARIES

_____________________________________________________________________________________

Regulatory Issue Date of Summary No. Subject Issuance Issued to

_____________________________________________________________________________________

2002-17 Guidance on Performing Military 09/19/2002 All holders of operating licenses Service Verification for nuclear power reactors.

2002-16 Current Incident Response Issues 09/13/2002 All holders of operating licenses for nuclear power plants.

2002-15 NRC Approval of Commercial Data 08/28/2002 All authorized recipients and Encryption Systems for the holders of sensitive unclassified Electronic Transmission of safeguards information (SGI).

Safeguards Information

2002-14 Proposed Changes to the Safety 08/28/2002 All holders of operating licenses System Unavailability Performance for nuclear power reactors, except Indicators those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel.

2002-13 Confirmation of Employment 08/27/2002 All holders of operating licenses Eligibility for nuclear power reactors.

2002-12 NRC Threat Advisory and Various Various Protective Measures System

2002-11 Requalification Program Test 08/09/2002 All holders operating licenses for Results for Okonite Okolon Single- nuclear power reactors, except Conductor Bonded-Jacket Cable those who have permanently (Followup to Regulatory Issue ceased operations and have Summary 2000-25) certified that fuel has been permanently removed from the reactor vessel.

2002-10 Revision of the Skin Dose Limit in 07/09/2002 All U.S. Nuclear Regulatory

10 CFR Part 20 Commission material licensees.

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______________________________________________________________________________________

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