ML20206G484
| ML20206G484 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 04/30/1999 |
| From: | Alexion T NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| TAC-MA4871, TAC-MA4872, NUDOCS 9905100030 | |
| Download: ML20206G484 (39) | |
Text
. 3 LICENSEE: STP Nuclear Op: rating Company (STPNOC) April 30,1999
/
FACILITY: South Texas Projhet, Units 1 and 2 (STP)
SUBJECT:
SUMMARY
OF MEETING TO DISCUSS STPNOC'S PROPOSED RISK-INFORMED EXEMPTIONS NEEDED FOR LOW SAFETY SIGNIFICANT COMPONENTS (TAC NOS. MA4871 AND MA4872)
On March 15,1999, the Nuclear Regulatory Commission (NRC) staff met with STPNOC to discuss STPNOC's " Submittal of Draft Request for Exemption from Special Treatment Requirements for Components that are Low Safety Significant or Non-Risk Significant," dated March 1,1999. Meeting attendees are listed in Enclosure 1. The handout provided by STPNOC is listed as Enclosure 2.
The STPNOC's presentation focused on the slides in Enclosure 2. STPNOC indicated that it has identified changes in scope since the March 1,1999, letter and STPNOC may identify additional changes before making its final submittal (i.e., an exemption from Title 10 of the Code of Federal Reaulations. Part 50, Appendix J requirements may be added to the scope, and the exemption from inservice inspection requirements may be deleted from the scope).
STPNOC indicated that these exemptions are needed to reduce unnecessary burdens of about
$2 million per year.
The NRC staff asked several questions (and identified a number of preliminary issues needing ,
resolutiori) during the meeting and indicated that it would compile a list of these questions and 1 identify additional questions after the meeting and would include the list as an enclosure to its meeting summary. That list is provided as Enclosure 3 to assist STPNOC in preparing its formal submittal package. The staff also asked STPNOC to carefully consider, in future revision (s) of the March 1,1999, draft request, to only request exemptions or reliefs in areas or subareas where the existing regulations cannot accommodate STPNOC's desires.
Both STPNOC and the NRC staff indicated that the information exchanged at the meeting was useful and that they were looking forward to further discussions on the subject.
ORIG. SIGNED BY Thomas W. Alexion, Project Manager, Section 1 1 O O G .% Project Directorate IV & Decommissioning T
5100 g 9g Division of Licensing Project Management Office of Nuclear Reactor Regulation P PDR .
Docket Nos. 50-498 and 50-499
Enclosures:
As stated (3) cc w/encls: See next page ag hhh hm d-1 DISTRIBUTION: See next page Document Name: G:\STPFINAL\MTSA4871.WPD 'See previous concurrence f OFC PDIV-11PM PDIV-1/LA SPSB/BC IOMB/BC EICB/BC EMEB/BC f NAME TA$xab LBerry b RBarrett* TOuay* JCalvo* Elmbro*
DATE /N99 9 9 04/08/99 04/19/99 04/20/99 04/20/99
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COPY NO YES/NO YES/NO YES/NO YES/NO YES/NO l u = mm -- r muru -- =-
-- = - .
OFC EMCB/BC PDIV-1/SC PDIV&D/CIE/D b d DSSA/D DLPM/DD NAME WBateman* RGrammh SRicharF astro Er Gsoiehan- SBi#
DATE 04/26/99 N/N /99 h Lh/99 d/ 99 04/13/99 f/$d99 COPY YES/NO h NO hEh/NO YES/NO YES/NO hO OFFICIAURECORD COPY j
LtCENSEE: STP Nuclzr Op: rating Comp ny (STPNOC) I FACILITY: South Texts ProJ:ct, Units 1 cnd 2 (STP)
SUBJECT:
SUMMARY
OF MEETING TO DISCUSS STPNOC'S PROPOSED RISK INFORMED EXEMPTIONS NEEDED FOR LOW SAFETY SIGNIFICANT COMPONENTS (TAC NOS. MA4871 AND MA4872)
On March 15,1999, the Nuclear Regulatory Commission (NRC) staif met with STPNOC to discuss STPNOC's " Submittal of Draft Request for Exemption from Special Treatment Requirements for Components that are Low Safety Significant or Non-Risk Significant," dated March 1,1999. Meeting attendees are listed in Enclosure 1. The handout provided by STPNOC is listed as Enclosure 2.
The STPNOC's presentation focused on the slides in Enclosure 2. STPNOC indicated thet it has identified changes in scope since the March 1,1999, letter and STPNOC may identify additional changes before making its final submittal (i.e., an exemption from Title 10 of the Code of Federal Reaulations. Part 50, Appendix J requirements may be added to the scope, and the exemption from inservice inspection requirements may be deleted from the scope).
STPNOC indicated that these exemptions are needed to reduce unnecessary burdens of about j
$2 million per year.
l The NRC staff asksd several questions (and identified issues needing resolution) during the meeting and indicated that it would compile a list of these questions and identify additional questions after the meeting and would include the list as an enclosure to its meeting summary.
That list is provided as Enclosure 3. The staff also asked STPNOC to carefully consider, in future revision (s) of the March 1,1999, draft request, to only request exemptions or reliefs in areas or subareas where the existing regulations cannot accommodate STPNOC's desires.
Both STPNOC and the NRC staff indicated that the information exchanged at the meeting was useful and that they were looking forward to further discussions on the subject.
Thomas W. Alexion, Projec.t Manager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear R actor Regulation Docket Nos. 50-498 and 50 499 /
Enclosures:
As stated (3) cc w/encis: See next page
/
DISTRIBUTION: See next page Document Name: G:\STPFINAL\MTSA4871.WPD / bD M*MF OFC PDI PDiV-1/LA SPSRIB[ lOMB/BC EICB/BC EMEB/BC NAME TAlex kBek hBarrett TOuay JCalvo Elmbro DATE k /h /99 f/ 7/99 4/ 99 4/ f} /99 #/%0 /99 4/20j99 COPY NO h NO YES/NO YES/NO YES/NO YES/NO
/
OFC EMCBl % PDIV-1/SC PDIV&D/D DE/D DSSA/D DLPM/DD NAME bhbRGramm / SRichards JStrosnider GHolahh SBlack DATE b vl/99 / /99 / /99 / /99 4 /16/99 / /99 COPY YES/NO YES/tdO YES/NO YES/NO (YESJNO YES/NO OFFICIAL RECORD COPY
n eeroq g t UNITED STATES i* j NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. 3000H001
% April 30, 1999
- LICENSEE: STP Nuclear Operating Company (STPNOC) '
FACILITY: South Texas Project, Units 1 and 2 (STP)
SUBJECT:
SUMMARY
OF MEETING TO DISCUSS STPNOC'S PROPOSED RISK INFORMED EXEMPTIONS NEEDED FOR LOW SAFETY SIGNIFICANT COMPONENTS (TAC NOS. MA4871 AND MA4872)
On March 15,1999, the Nuclear Regulatory Commission (NRC) staff met with STPNOC to discuss STPNOC's " Submittal of Draft Request for Exemption from Special Treatment Requirements for Components that are Low Safety Significant or Non-Risk Significant," dated
{
March 1,1999. Meeting attendees are listed in Enclosure 1. The handout provided by i STPNOC is listed as Enclosure 2. '
The STPNOC's presentation focused on the slides in Enclosure 2. STPNOC indicated that it has identified changes in scope since the March 1,1999, letter and STPNOC may identify additional changes before making its final submittal (i.e., an exemption from Title 10 of the Code of Federal Reaulations, Part 50, Appendix J requirements may be added to the scope, and the exemption from inservice inspection requirements may be deleted from the scope).
STPNOC indicated that these exemptions are needed to reduce unnecessary burdens of about
$2 million per year.
-The NRC staff asked several questions (and identified a number of preliminary issues needing resolution) during the meeting and indicated that it would compile a list of these questions and 1 identify additional questions after the meeting and would include the list as an enclosure to its l meeting summary. That list is provided as Enclosure 3 to assist STPNOC in preparing its i formal submittal package. The staff also asked STPNOC to carefully consider, in future l revision (s) of the March 1,1999, draft r6 quest, to only request exemptions or reliefs in areas or j subareas where the existing regulations cannot accommodate STPNOC's desires. l Both STPNOC and the NRC staff indicated that the information exchanged at the meeting was useful and that they were looking forward to further discussions on the subject.
u .
Thomas W. Alexion, Project anager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosures:
As stated (3) cc w/encis: See next page
O DISTRIBUTION FOR MEETING
SUMMARY
DATED: April 30,1999 H&BQ COPY pasatste PUBLIC PD# 4-1 Reading
.T. Alexion
.OGC ACRS g-MAIL J. Zwolinski/S. Black S. Richards R. Gramm L. Berry R. Barrett J. Strosnider G. Holahan J. Moore M. Drouin J. Vora M. Rubin M. Cheok D. Fischer
.J. Knox R. Smith G. Bagchi S. Turk S. Wong R. Correia S. Dinsmore D. Terao P.Chen K. Manoly D. Lange (DJL)
K. Brockman
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F-STP Nuclear Operating Company South Texas, Units 1 & 2 cc:
Mr. Comelius F. O'Keefe Jack R. Newman, Esq.
' Senior Resident inspector Morgan, Lewis & Bocklus U.S. Nuclear Regulatory Commission 1800 M Street, N.W.
P. O. Box 910 Washington, DC 20036-5869 Bay City, TX 77414 Mr. T. H. Cloninger A. Ramirez/C. M. Canady Vice President, Engineering & Tech Servs Cityof Austin STP Nuclear Operating Company Electric Utility Department P. O. Box 289 721 Barton Springs Road Wadsworth,TX 77483 Austin,TX 78704 Office of the Govemor Mr. M. T. Hardt ATTN: John Howard, Director Mr. W. C. Gunst Environmental and Natural City Public Service Board Resources Policy P. O. Box 1771 P. O. Box 12428 San Antonio,TX 78296 Austin,TX 78711 Mr. G. E. Vaughn/C. A. Johnson Jon C. Wood Central Power and Light Company Matthews & Branscomb P. O. Box 289 One Alamo Center MailCode: N5012 106 S. St. Mary's Street, Suite 700 Wadsworth,TX 74483 San Antonio, TX 78205-3692 INPO Arthur C. Tate, Director Records Center Division of Compliance & Inspection 700 Galleria Parkway Bureau of Radiation Control Atlanta, GA 30339-3064 Texas Department of Health 1100 West 49th Street Regional Administrator, Region IV Austin,TX 78756 U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Jim Calloway Arlington,TX 76011 Public Utility Commission of Texas Electric Industry Analysis D. G. Tees /R. L. Balcom P. O. Box 13326 ,
Houston Lighting & Power Co. Austin, TX 78711-3326 l P. O. Box 1700 Houston,TX 77251 Mr. William T. Cottle President and Chief Executive Officer Judge, Matagorda County STP Nuclear Operating Company Matagorda County Courthouse South Texas Project Electric ;
1700 Seventh Street Generating Station i Bay City, TX 77414 P. O. Box 289 l Wadsworth, TX 77483 I
i s l l
MEETING BETWEEN STP NUCLEAR OPERATING COMPANY AND NRC PROPOSED RISK-INFORMED EXEMPTIONS NEEDED FOR
\
LOW SAFETY SIGNIFICANT COMPONENTS I
MARCH 15.1999 Name Oraanization W. Harrison STPNOC G. Schinzel STPNOC S. Rosen STPNOC R. Chackal STPNOC
, C. Grantom STPNOC K . Work STPNOC ,
S. Frantz Morgan, Lewis & Bocklus B. Bradley NEl T. Sutter Bechtel D. Stellfox McGraw-Hill T. Alexion NRC R. Barrett NRC S. Black NRC J. Strosnider NRC G. Holahan NRC J. Moore NRC i M. Drouin NRC I J. Vora NRC i M. Rubin NRC i M. Cheok NRC l D. Fischer NRC l J. Knox NRC R. Smith NRC G. Bagchi NRC S. Turk NRC S. Wong NRC R. Correia NRC R. Gramm NRC S. Dinsmore NRC D. Terao NRC P.Chen NRC K. Manoly NRC Enclosure 1 I
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PRELIMINARY LIST OF QUESTIONS AND ISSUES NEEDING RESOLUTION Probabilistic Risk Assessmert
- 1. Explain why STPNOC is proposing that both low safety significant (LSS) and non-risk significant (NRS) structures, systems and components (SSCs) be removed from scope and not, for example, only NRS. If not all LSS and NRS SCCs are to be removed from scope, explain how some will be selected and others not.
- 2. Explain why the SSC categorization process approved by the staff solely to determine which SSCs could be subjected to a reduction in some Quality Assurance (QA) controls, is also applicable to support the much more encompassing change arising from placing SSCs outside the scope of regulations.
' 3. During the Graded QA (GOA) application review, the staff determined that the LSS SSCs would be subject to QA controls appropriate to their low safety significance. Given that for GOA, LSS and NRS are treated identically, the {
staff did not review the differentiation between LSS and NRS beyond confirming that NRS was at least LSS. Explain how SSCs placed in the NRS are so much less significant than SSCs placed in LSS.
- 4. A claim that there will be no decrease in equipment availability following a reduction in OA controls, environmental qualification, seismic qualification and q
- iarious other special treatment requirements, will almost certainly not be demonstratable. Assuming that some impact on margins or availability is possible, explain how the potential aggregate risk impact of removing NRS (and possibly LSS) SSCs from the scope of regulations will be determined.
- 5. Explain why, if current Inservice Testing (IST) policy is only to allow increased inspection intervals for LSS, your proposal to remove them from regulatory scope (e.g., allowing no testing) is acceptable.
O. As a pilot, does STPNOC plan to identify regulatory changes that would allow the changes you propose without requiring exemption requests?
Quality Assurance
- 1. Explain why STPNOC does not propose using the existing Regulatory Guides for developing a risk-informed QA Program.
- 2. STPNOC should maintain the GQA program commitment for the feedback loop to make adjustments, when necessary, in the application of the QA controls for LSS/NRS equipment ba' sed on plant / industry performance, and plant modifications.
Enclosure 3 i
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- 3. Page 6 of the March 1,1999, letter describes other programs (such as motor operated valves (MOVs), air operated valves (AOVs), molded case circuit breakers) that are not listed in Attachment 1, where LSS and NRS equipment will be treated differently.
STPNOC should explicitly identify all technical areas where LSS and NRS equipment will no longer be within scope of the current program controls.
- 4. STPNOC should provide amplifying information on how commercial vendors (not necessarily the original equipment manufacturer (OEM)) will provide a suitable engineering analysis to demonstrate the LSS/NRS equipment conforms to the STPNOC procurement specifications which include typical nuclear requirements (i.e., seismic loading, harsh environment profiles).
- 5. STPNOC should re-consider waiving the entire scope of the QA program for LSS/NRS equipment. For example, why are the nonconformance/ corrective action, monitoring programs, and design controls eliminated in their entirety? Why is the Basic QA program no longer acceptable for LSS/NRS equipment?
- 6. STPNOC should provide amplifying Justification on ti e usefulness of normal plant operational feedback mechanisms to demonstrate tha functionality of LSS/NRS equipment with respect to special treatment provisions like equipment qualification and seismic qualification provisions.
- 7. Page 20 and 21 of the March 1,1999, letter discuss a commitment for enhanced treatment of non safety related high safety significant (HSS) and medium safety significant (MSS) equipment with respect to the technical areas. How will this commitment be integrated into a licensing basis document, and what specific technical enhancements will be considered? STPNOC should confirm that the GQA provisions for treatment of non-safety related HSS and MSS equipment remains intact.
- 8. Page 24 and 25 of the March 1,1999, letter provide a high level discussion as to why the composite set of changes will ensure adequate protection of public health and safety. The basis for this conclusion should be augmented to justify how the whole set of LSS and NRS could be found so unimportant.
- 9. STPNOC should first take advantage of current mechanisms to resolve the problems on burdensome special treatment controls, such as using the design control program to re-classify equipment as non-safety related.
Maintenance Rule
- 1. With respect to the Maintenance Rule, monitoring LSS and NRS SSCs at the system / train level is acceptable (STPNOC is requesting an exemption from monitoring at the component level). There are no requirements to monitor at the component level even for HSS SSCs. Also, the Regulatory Guide /NUMARC guidance calls for plant level monitoring (scrams, transients) for most LSS/NRS SSCs.
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- 1. With the utilization of commercial grade electrical components (i.e., components determined to be LSS or NRS that previously met all Class 1E requirements), explain how independence is preserved between redundant safety system (i.e., how will the availability of the minimum required equipment be assured during any design basis event?).
a) Present the criteria and their basis (i.e., current UFSAR commitments and/or new commitments) that establish the minimum requirements for preserving the independence between redundant safety systems).
b) If an isolation device is utilized to isolate (Class 1E HSS or MSS from i.SS or NRS), will this isolation device be required to be HSS or MSS? If not, provide l justification, c) Provide a description of the extent to which the recommendations of Regulatory Guide 1.75 are followed.
Environmental Qualification
- 1. Since 50.49 only requires components to be qualified to 50.49 requirements if they are exposed to the design basis accident (DBA) environment and must function in order to mitigate the consequences of the DBA, it is not clear which components need exemption. Provide clarification.
Inservice Testing
- 1. Explain why STPNOC did not use the existing Regulatory Guide 1.175 for risk-informed IST?
- 2. Discuss why, without monitoring at the component level, common cause failures of LSS con ponents are not important to safety.
- 3. Discuss how you can assure that LSS and NRS components in safety-related systems purchased without QA documentation (e.g., material certifications) will meet design and procurement specification requirements (e.g., strength, ductility, and corrosion-resistance).
- 4. Explain why it is acceptable for failures of LSS and NRS components in a safety-related system to occur when those components are not modeled in your probabilistic risk assessment (PRA). Could failures of LSS and NRS components impact the ability of a safety related system to pedorm its intended functions?
- 5. Describe any feedback that will occur when LSS and NRS components are found in a degraded or nonconforming condition. Will the feedback explicitly address each special treatment area being affected by the exemption request (e.g., to re-establish QA or IST requirements as may be appropriate)?
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- 6. . Quantitatively assess, to the extent practical, the aggregate effect on core damage frequency (CDF) and large early release frequency (LERF) of deleting the various special treatment requirements. What would be the effect on CDF and LERF if all LSS and NRS components were assumed to be unavailable?
- 7. Discuss the basis for deleting IST requirements for LSS components (components with a Fussell-Vessely (FV) less than 0.005 and a risk achievement worth (RAW) less than 2.0) in light of the fact that the ASME component-specific and risk-informed Code cases, currently under development, define IST requirements for these components.
- 8. Describe the deterministic factors considered by the expert panel in categorizing components. How does the licensee's overall categorization process ensure that appropriate level of QA, testing, maintenance, etc., is conducted on components categorized as LSS and NRS?
Inservice Inspection
- 1. Explain why STPNOC does not propose using the existing Regulatory Guides for developing a risk-informed Inservice inspection (ISI) Program (for piping).
- 2. How does the change in risk category impact ASME classification for the purpose of 1 ISl?
Seismic Qualification i
- 1. A se!smic event is a common cause failure initiator. Real earthquake experience data had indicated that some equipment are vulnerable to earthquake motions. Reliance on design and purchase specifications may not be sufficient to demonstrate the functions of some mechanical and electrical equipment. Discuss what criteria and procedures you plan to use to assure that LSS and NRS components will function during and after an ,
earthquake without pedorming equipment seismic qualification in accordance with the ;
current provisions in the UFSAR.
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