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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217D7031999-10-0707 October 1999 Informs That USNRC Had Dicussions with Licensee on 990908 Application for License Amend to Relocate 18-month Standby Diesel Generator Insp Sr.Forwards Preliminary Info Submitted by Licensee Re Supplement to Application ML20212L3481999-10-0101 October 1999 Forwards Document Re Replacement SG Water Level Trip Setpoint Differences to Be Placed in PDR ML20216F9021999-09-21021 September 1999 Notification of 991005-07 Meeting with STP Nuclear Operating Co in Bay City,Tx,To Review Plant Categorization & Feedback Process of Risk Ranking Components ML20211J2141999-08-27027 August 1999 Notification of 990831 Meeting with Util to Discuss Issues Associated with STPNOC Recent Request to Exclude safety- Related Low Risk Significant & non-risk Significant Components from Scope of Special Treatment Requirements ML20211G7001999-08-25025 August 1999 Forwards Examination Rept with as Given Written Exam Administered on 990706-15 for Distribution Under Rids Code IE42 ML20211G2501999-08-25025 August 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990706-15 ML20211F3801999-08-20020 August 1999 Notification of 990831 Meeting with Util in Rockville,Md to Discuss Issues Associated with STPNOC Recent Request to Exclude safety-related low-risk Significant & non-risk Significant Components, Designated Under Gqa Program ML20210P9351999-08-0909 August 1999 Notification of 990923 Meeting with Util in Arlington,Tx to Introduce New Director,Safety Quality Concerns Program & Status of Activities to Support Confirmatory Order Modifying License ML20210M6841999-08-0505 August 1999 Notification of Licensee Meeting with Util on 990914 in Arlington,Tx to Discuss New Mgt Team Introduction & Site Status ML20209D5751999-07-0909 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Licensee Proposed SG Water Level Trip Setpoint TS & Setpoint Impact on Pressurizer Water Level TS Per 10CFR50.36 ML20196L1481999-07-0707 July 1999 Forwards Info Provided by Licensee to Facilitate Conference Calls Re Licensee Desire to Propose Emergency Technical Specification Changes on Fuel Handling Building Exhaust Air Sys ML20212J2641999-06-24024 June 1999 Forwards Addl Info from Licensee Re Clarification of Sentence in Util (on Page 4 of 7) Which States That, Isolation Valves in This Sys Designed to Be Operated remote-manually from Control Room ML20195J0441999-06-14014 June 1999 Refers to Discussions with Licensee on Future Suppl to Application on Replacement Steam Generator Reactor Coolant Flow Differences ML20195J0841999-06-14014 June 1999 Forwards Info Re Suppl to Application on TS 3.6.3,action B, to Clarify Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration,To Be Placed in PDR ML20207E8961999-06-0303 June 1999 Discusses Which Submitted Relief Request RR-ENG-2-8 Which Requested Relief from ASME Code Based on Provisions of Code Case N-491-2.Requests That Encl Be Placed Into PDR ML20207D9911999-05-28028 May 1999 Informs That NRC Requested That Licensees Respond to Survey on Hydrogen Storage Facilities,To Support Preliminary Evaluation to Determine If Addl Study Warranted.South Texas Project Licensee Response Encl for Placement in PDR ML20207A6671999-05-20020 May 1999 Notification of 990602 & 03 Meeting with Util in South Texas Project Nuclear Support Ctr,Southwest of Bay City,Tx,In Order for Licensee to Present low-power Shutdown Risk Model ML20207A3381999-05-19019 May 1999 Informs of Discussions with Licensee on 980831 Application for License Amend to TS 3.4.9.3 to Reflect Revised Cold Overpressure Mitigation Curve Associated with Replacement Sgs.Request That Encl Documents Be Placed in PDR ML20206N6411999-05-13013 May 1999 Refers to Discussions with Licensee on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20206G5041999-05-0404 May 1999 Requests That Enclosures 1 & 2 Re 990412 Conference Call, Discussing Preliminary Results of SG Insp,Be Placed in PDR ML20206G2041999-05-0404 May 1999 Discusses 981201 Telcon Between NRC Staff & STP Re 10CFR50.59 Evaluation of MSLB Reanalysis & Effect on Isolation Valve Cubicle & Rcb.Requests That Encl Draft Info Be Placed in PDR ML20206A4851999-04-26026 April 1999 Informs That Staff Needs to Conduct Phone Call with Licensee on Licensee Response to GL 95-07.In Order to Conduct Phone Call,Staff Needs to Provide Licensee with Attached Info ML20205Q8251999-04-15015 April 1999 Forwards Documentation on Licensee 980928 Proposed Changes to TS on Control Room & Fuel Handling Bldg Ventilation Sys, Per 990304 Discussion with Util ML20205Q7961999-04-15015 April 1999 Forwards Documentation from Preliminary Discussions with Licensee on Proposed Changes to Atmospheric Steam Relief Valve Tss.Licensee Subsequently Made Formal Application on 990322 (Accession Number 9903300195) ML20205Q8111999-04-15015 April 1999 Forwards Draft Undated Rev 6 to Operations QA Plan Independent Technical Review, Per Discussions with Licensee on 990407 Re Proposed Change to TSs on Independent Safety Engineering Group ML20204H7731999-03-22022 March 1999 Notification of Significant Licensee Meeting with Util on 990419 in Arlington,Tx to Present Overview of Licensee Emergency Plan ML20207G8201999-03-0404 March 1999 Notification of Significant Licensee Meeting with Util on 990325 to Discuss Plant Performance Review Results ML20207K2301999-03-0404 March 1999 Notification of 990315 Meeting with STP Nuclear Operating Co in Rockville,Md So Licensee May Present risk-informed Exemptions Util Need for Implementation of Graded Quality Assurance at South Texas Project ML20199D1891999-01-11011 January 1999 Notification of 990126 Meeting with STP Nuclear Operating Co to Discuss C/As for Incomplete Control Rod Insertion Anomaly & to Discuss Need for Future mid-cycle Control Rod Drop Testing ML20198H3281998-12-15015 December 1998 Forwards Draft Info Submitted by Util Re 980728 Application for Amend Concerning Operator Action to Mitigate Sbloca,Per 981117 Telcon & for Placement in PDR ML20196G1521998-12-0303 December 1998 Forwards Draft Outline to NRC to Facilitate Discussions Between Util & NRC Re Actions Believed Needed to Address Restraints to Implementation of Graded QA ML20196F1751998-11-27027 November 1998 Notification of Licensee Meeting with Util on 981210 in Arlington,Tx to Discuss Certain Issues of Comprehensive Cultural Assessment for South Texas Project Site ML20196A8641998-11-24024 November 1998 Notification of 981208 Meeting with Util in Rockville,Md to Discuss Status of Current & Proposed Licensing Actions & Activities for Plant ML20195B9251998-11-10010 November 1998 Forwards,For Placement in Pdr,Draft Proposals That Were Provided by Licensee at Request of Staff,In Order to Assist Staff in Developing Commission Paper on Options for Making 10CFR50 More risk-informed ML20155H7471998-11-0505 November 1998 Notification of 981117 Meeting with STP Nuclear Operating Co in Arlington,Tx Re Presentation by Rosen,Manager,Risk Mgt& Industrial Relations on Licensee Perspective on Probablistic Risk Analysis ML20155C2651998-10-29029 October 1998 Forwards SG Insp Results Conducted in Oct 1998,to Be Placed in Pdr.Licensee Provided Info to Facilitate 981015 Conference Call ML20155C2231998-10-29029 October 1998 Forwards Draft Ltr from STP Nuclear Operating Co on Action Needed for Implementation of Graded QA for Plant Units 1 & 2 for Placement in PDR ML20155C2171998-10-26026 October 1998 Notification of 981109-10 Meeting with Util to Obtain Info from Licensee for NRC Proposed risk-informed Insp & Assessment Program.Agenda Encl ML20154L4101998-10-0909 October 1998 Forwards NRC Operator Licensing Exam Repts 50-498/98-301 & 50-499/98-301,including Completed Graded Tests Administered on 980602-04 ML20154L9261998-10-0909 October 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980602-04 ML20154A0331998-09-24024 September 1998 Informs That Based on Review of Licensee 10CFR50.59 Evaluation of Environ Qualification of Mechanical Components,Staff Found That Proposed Change to UFSAR to Eliminate Meq Program Would Not Alter Any Plant Sys ML20151Y7231998-09-12012 September 1998 Notification of Licensee Meeting with Util on 981013 in Arlington,Tx Re Licensee Presentation Concerning Graded Quality Assurance Program at Plant ML20239A0941998-09-0303 September 1998 Notification of 980915 Meeting W/Util in Rockville,Md to Discuss Problems W/Implementing Graded QA,10CFR50.59,impact on risk-informed Applications & Comments on NRC Proposed Rev to 10CFR50.59 ML20239A1171998-09-0202 September 1998 Notification of 980915 Meeting W/Stp Nuclear Operating Co in Rockville,Md Re Licensee Presentation of Uses of Probabilistic Safety Assessment ML20151T6061998-09-0101 September 1998 Notification of Significant Licensee Meeting W/Util on 980918 to Discuss Licensee Insp Plans for Units 1 & 2 Replacement Steam Generators ML20236X8171998-08-0303 August 1998 Notification of Licensee Meeting W/Util on 980820 in Arlington,Tx to Discuss Certain Issues Ongoing at STP Site ML20249A6781998-06-16016 June 1998 Forwards Confirmatory Order Modifying Licenses NPF-76 & NPF-80 (Effective Immediately),For Transmittal to Ofc of Fr for Publication.W/O Encl ML20216J4491998-04-16016 April 1998 Notification of 980506 Meeting W/Util in Rockville,Md to Discuss Proposed Merger Between Aep & Central Southwest ML20217K9381998-04-0303 April 1998 Notification of 980413 Meeting W/Util in Rockville,Md to Discuss Licensee Desire for Update on Schedule for NRC Review of Licensee Application for Conversion to Improved Std TSs ML20197B0551998-03-0505 March 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam submittal,2nd & 3rd Exam Submittal as Given Operating Exam Administered on 971020-1205 1999-09-21
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217D7031999-10-0707 October 1999 Informs That USNRC Had Dicussions with Licensee on 990908 Application for License Amend to Relocate 18-month Standby Diesel Generator Insp Sr.Forwards Preliminary Info Submitted by Licensee Re Supplement to Application ML20212L3481999-10-0101 October 1999 Forwards Document Re Replacement SG Water Level Trip Setpoint Differences to Be Placed in PDR ML20216F9021999-09-21021 September 1999 Notification of 991005-07 Meeting with STP Nuclear Operating Co in Bay City,Tx,To Review Plant Categorization & Feedback Process of Risk Ranking Components ML20211J2141999-08-27027 August 1999 Notification of 990831 Meeting with Util to Discuss Issues Associated with STPNOC Recent Request to Exclude safety- Related Low Risk Significant & non-risk Significant Components from Scope of Special Treatment Requirements ML20211G2501999-08-25025 August 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990706-15 ML20211G7001999-08-25025 August 1999 Forwards Examination Rept with as Given Written Exam Administered on 990706-15 for Distribution Under Rids Code IE42 ML20211F3801999-08-20020 August 1999 Notification of 990831 Meeting with Util in Rockville,Md to Discuss Issues Associated with STPNOC Recent Request to Exclude safety-related low-risk Significant & non-risk Significant Components, Designated Under Gqa Program ML20210P9351999-08-0909 August 1999 Notification of 990923 Meeting with Util in Arlington,Tx to Introduce New Director,Safety Quality Concerns Program & Status of Activities to Support Confirmatory Order Modifying License ML20210M6841999-08-0505 August 1999 Notification of Licensee Meeting with Util on 990914 in Arlington,Tx to Discuss New Mgt Team Introduction & Site Status ML20209D5751999-07-0909 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Licensee Proposed SG Water Level Trip Setpoint TS & Setpoint Impact on Pressurizer Water Level TS Per 10CFR50.36 ML20196L1481999-07-0707 July 1999 Forwards Info Provided by Licensee to Facilitate Conference Calls Re Licensee Desire to Propose Emergency Technical Specification Changes on Fuel Handling Building Exhaust Air Sys ML20212J2641999-06-24024 June 1999 Forwards Addl Info from Licensee Re Clarification of Sentence in Util (on Page 4 of 7) Which States That, Isolation Valves in This Sys Designed to Be Operated remote-manually from Control Room ML20195J0841999-06-14014 June 1999 Forwards Info Re Suppl to Application on TS 3.6.3,action B, to Clarify Use of Check Valve with Flow Through Valve Secured as Means to Isolate Affected Containment Penetration,To Be Placed in PDR ML20195J0441999-06-14014 June 1999 Refers to Discussions with Licensee on Future Suppl to Application on Replacement Steam Generator Reactor Coolant Flow Differences ML20207E8961999-06-0303 June 1999 Discusses Which Submitted Relief Request RR-ENG-2-8 Which Requested Relief from ASME Code Based on Provisions of Code Case N-491-2.Requests That Encl Be Placed Into PDR ML20207D9911999-05-28028 May 1999 Informs That NRC Requested That Licensees Respond to Survey on Hydrogen Storage Facilities,To Support Preliminary Evaluation to Determine If Addl Study Warranted.South Texas Project Licensee Response Encl for Placement in PDR ML20207A6671999-05-20020 May 1999 Notification of 990602 & 03 Meeting with Util in South Texas Project Nuclear Support Ctr,Southwest of Bay City,Tx,In Order for Licensee to Present low-power Shutdown Risk Model ML20207A3381999-05-19019 May 1999 Informs of Discussions with Licensee on 980831 Application for License Amend to TS 3.4.9.3 to Reflect Revised Cold Overpressure Mitigation Curve Associated with Replacement Sgs.Request That Encl Documents Be Placed in PDR ML20206N6411999-05-13013 May 1999 Refers to Discussions with Licensee on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20206G2041999-05-0404 May 1999 Discusses 981201 Telcon Between NRC Staff & STP Re 10CFR50.59 Evaluation of MSLB Reanalysis & Effect on Isolation Valve Cubicle & Rcb.Requests That Encl Draft Info Be Placed in PDR ML20206G5041999-05-0404 May 1999 Requests That Enclosures 1 & 2 Re 990412 Conference Call, Discussing Preliminary Results of SG Insp,Be Placed in PDR ML20206A4851999-04-26026 April 1999 Informs That Staff Needs to Conduct Phone Call with Licensee on Licensee Response to GL 95-07.In Order to Conduct Phone Call,Staff Needs to Provide Licensee with Attached Info ML20205Q8251999-04-15015 April 1999 Forwards Documentation on Licensee 980928 Proposed Changes to TS on Control Room & Fuel Handling Bldg Ventilation Sys, Per 990304 Discussion with Util ML20205Q8111999-04-15015 April 1999 Forwards Draft Undated Rev 6 to Operations QA Plan Independent Technical Review, Per Discussions with Licensee on 990407 Re Proposed Change to TSs on Independent Safety Engineering Group ML20205Q7961999-04-15015 April 1999 Forwards Documentation from Preliminary Discussions with Licensee on Proposed Changes to Atmospheric Steam Relief Valve Tss.Licensee Subsequently Made Formal Application on 990322 (Accession Number 9903300195) ML20204H7731999-03-22022 March 1999 Notification of Significant Licensee Meeting with Util on 990419 in Arlington,Tx to Present Overview of Licensee Emergency Plan ML20207G8201999-03-0404 March 1999 Notification of Significant Licensee Meeting with Util on 990325 to Discuss Plant Performance Review Results ML20207K2301999-03-0404 March 1999 Notification of 990315 Meeting with STP Nuclear Operating Co in Rockville,Md So Licensee May Present risk-informed Exemptions Util Need for Implementation of Graded Quality Assurance at South Texas Project ML20199D1891999-01-11011 January 1999 Notification of 990126 Meeting with STP Nuclear Operating Co to Discuss C/As for Incomplete Control Rod Insertion Anomaly & to Discuss Need for Future mid-cycle Control Rod Drop Testing ML20198H3281998-12-15015 December 1998 Forwards Draft Info Submitted by Util Re 980728 Application for Amend Concerning Operator Action to Mitigate Sbloca,Per 981117 Telcon & for Placement in PDR ML20196G1521998-12-0303 December 1998 Forwards Draft Outline to NRC to Facilitate Discussions Between Util & NRC Re Actions Believed Needed to Address Restraints to Implementation of Graded QA ML20196F1751998-11-27027 November 1998 Notification of Licensee Meeting with Util on 981210 in Arlington,Tx to Discuss Certain Issues of Comprehensive Cultural Assessment for South Texas Project Site ML20196A8641998-11-24024 November 1998 Notification of 981208 Meeting with Util in Rockville,Md to Discuss Status of Current & Proposed Licensing Actions & Activities for Plant ML20195B9251998-11-10010 November 1998 Forwards,For Placement in Pdr,Draft Proposals That Were Provided by Licensee at Request of Staff,In Order to Assist Staff in Developing Commission Paper on Options for Making 10CFR50 More risk-informed ML20155H7471998-11-0505 November 1998 Notification of 981117 Meeting with STP Nuclear Operating Co in Arlington,Tx Re Presentation by Rosen,Manager,Risk Mgt& Industrial Relations on Licensee Perspective on Probablistic Risk Analysis ML20155C2231998-10-29029 October 1998 Forwards Draft Ltr from STP Nuclear Operating Co on Action Needed for Implementation of Graded QA for Plant Units 1 & 2 for Placement in PDR ML20155C2651998-10-29029 October 1998 Forwards SG Insp Results Conducted in Oct 1998,to Be Placed in Pdr.Licensee Provided Info to Facilitate 981015 Conference Call ML20155C2171998-10-26026 October 1998 Notification of 981109-10 Meeting with Util to Obtain Info from Licensee for NRC Proposed risk-informed Insp & Assessment Program.Agenda Encl ML20154L9261998-10-0909 October 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980602-04 ML20154L4101998-10-0909 October 1998 Forwards NRC Operator Licensing Exam Repts 50-498/98-301 & 50-499/98-301,including Completed Graded Tests Administered on 980602-04 ML20154A0331998-09-24024 September 1998 Informs That Based on Review of Licensee 10CFR50.59 Evaluation of Environ Qualification of Mechanical Components,Staff Found That Proposed Change to UFSAR to Eliminate Meq Program Would Not Alter Any Plant Sys ML20151Y7231998-09-12012 September 1998 Notification of Licensee Meeting with Util on 981013 in Arlington,Tx Re Licensee Presentation Concerning Graded Quality Assurance Program at Plant ML20239A0941998-09-0303 September 1998 Notification of 980915 Meeting W/Util in Rockville,Md to Discuss Problems W/Implementing Graded QA,10CFR50.59,impact on risk-informed Applications & Comments on NRC Proposed Rev to 10CFR50.59 ML20239A1171998-09-0202 September 1998 Notification of 980915 Meeting W/Stp Nuclear Operating Co in Rockville,Md Re Licensee Presentation of Uses of Probabilistic Safety Assessment ML20151T6061998-09-0101 September 1998 Notification of Significant Licensee Meeting W/Util on 980918 to Discuss Licensee Insp Plans for Units 1 & 2 Replacement Steam Generators ML20236X8171998-08-0303 August 1998 Notification of Licensee Meeting W/Util on 980820 in Arlington,Tx to Discuss Certain Issues Ongoing at STP Site ML20249A6781998-06-16016 June 1998 Forwards Confirmatory Order Modifying Licenses NPF-76 & NPF-80 (Effective Immediately),For Transmittal to Ofc of Fr for Publication.W/O Encl ML20216J4491998-04-16016 April 1998 Notification of 980506 Meeting W/Util in Rockville,Md to Discuss Proposed Merger Between Aep & Central Southwest ML20217K9381998-04-0303 April 1998 Notification of 980413 Meeting W/Util in Rockville,Md to Discuss Licensee Desire for Update on Schedule for NRC Review of Licensee Application for Conversion to Improved Std TSs ML20197B0551998-03-0505 March 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam submittal,2nd & 3rd Exam Submittal as Given Operating Exam Administered on 971020-1205 1999-09-21
[Table view] |
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November 10,.1998
. MEMORANDUM TO: PD IV-1. File i
L James R'. hall, Project Manager ORIGINAL SIGNED.BY:
FROM:
Project Diredorate IV-1 Division of Reactor Projects Ill/IV
' Office of Nuclear Reactor Regulation L
SUBJECT:
~ PROPOSED RISK-lNFORMED REGULATORY CHANGE, SOUTH j TEXAS PROJECT, UNITS 1&2 The NRC staff held conference calls with the licensee on October 29 and November 6, )
199E, to discuss the licensee's proposed risk-informed regulatory changes to enable full l 1
implementation of the graded quality assurance program at STP. These discussions related to l l
l the licensee's letter of October 14,1998, and two subsequent draft proposals, transmitted by electronic mail on November 4 and 6,1998 (Attachments 1 and 2, respectively). The draft ,
i j proposals were provided by the licensee at the request of the staff, in order to assist the staff in i
developing a Commission paper on options for making 10 CFR Part 50 more risk-informed.
The purpose of this memorandum is to place the attachments in the Public Document Room.
l' 1
Docket Nos. 50-498 and 50-499
! ' Attachments:- As stated l
DISTRIBUTION. !
m e e D ois e s A M ?
- PUBLIC TAlexion DOCUMENT NAME: G:\STPFINAL\ST111298.MEM {
' To receive a copy of this document, indicate in the box C= Copy w/o attact ment / enclosure E= Copy with i attachment! enclosure N = No copy / '
I'-
OFFICE PM/PD4-1 E LA/PD4-1 E' D/PD4-1v b h c i
! NAME- JRHall h CHawes' W JHannon M'{O i
{ DATE- 11//o/98 ff 11/l0jgg ggf/hg
[- OFFICIAL RECORD COPY i 9811160319 981110 * -
f _
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p urug j t UNITED STATES j
g NUCLEAR REGULATORY COMMISSION
- / November 10, 1998 MEMORANDUM TO: PD IV-1 File
}
FROM: James R. Hall, Project Manager (4/\' ( ;
Project Directorate IV-1 Division of Reactor Projects 111/
l Office of Nuclear Reactor Regulation l
SUBJECT:
PROPOSED RISK-INFORMED REGULATORY CHANGE, SOUTH TEXAS PROJECT, UNITS 1&2 l
The NRC staff held conference calls with the licensee on October 29 and November 6, 1998, to discuss the licensee's proposed risk-informed regulatory changes to enable full ,
implementation of the graded quality assurance program at STP. These discussions related to I the licensee's letter of October 14,1998, and two subsequent draft proposals, transmitted by 1
electronic mail on November 4 and 6,1998 (Attachrnents 1 and 2, respectively). The draft proposals were provided by the licensee at the request of the staff, in order to assist the staff in l developing a Commission paper ca options for making 10 CFR Part 50 more risk-informed.
The purpose of this memorandum is to place the attachments in the Public Document Room.
Docket Nos. 50-498 and 50-499 l Attachments: As stated 4
PROPOSED RISK INFORMED REGULATORY CHANGE PURPOSE OF STPNOC PILOT This pilot is a continuation of the GQA pilot which will define the regulatory changes necessary to fully implement risk-informed changes to 10CFR50 and supporting regulations.
Existing Situation:
For components categorized as safety related in the UFSAR, NRC regulations require that these components be qualified to meet the requirements of 10CFR50.49 (Equipment Qualification) and/or 10CFR100 (seismic). Through the Graded Quality Assurance (GQA) risk significance evaluation process (which has been reviewed / approved by the NRC in a Safety Evaluation Report (SER) dated 11/6/97), a number of these safety related components have been determined to be non-risk significant (NRS). If a 10CFR50.59 evaluation is performed to reclassify these NRS components from safety related to non-safety related, an unreviewed safety question (USQ) exists. The USQ results from the deterministic application of 10CFR50.59 where the probability of a malfunction of equipment important to safety may be increased and/or the margin of safety for a Technical Specification will be reduced. The determination that a USQ results is made regardless of the component's relationship to risk and regardless of the size ofincrease.
Although there may be some possibility of other interpretations of 10CFR50.59, the regulations should be applicable in a clear and consistent manner. In addition, the regulations provide no exception for NRS components, and an exemption to the regulations would be required to reclassify components. Also, classifications of systems in the UFSAR could be construed as part of the Quality Assurance program description and 10CFR50.54(a) would require NRC approval of the reclassifications. Finally, there are no provisions in the existing 10CFR50.59 criteria l which would allow reclassification of safety related LOW risk significant components that do not exceed a ' minimal' threshold (i.e., change of 1E-5 is not acceptable) for increases in risk.
STPNOC proposes tht following risk informed regulatory changes as an extension to the existing Graded Quality Assurance pilot process:
Request exemption to the definition of safety related in 10CFR50.2 to allow a definition of risk-important as an alternative to safety related.
The following definition of risk-important is proposed as an alternate to the definition of safety related:
Risk-important Structures, f>ystems and Components (SSCs) may be identified based on approved risk informed processes. The risk-important definition may be used in place of the safety-related definition.
Attachment 1
Allow the application of the risk-informed 10CFR50.59 process, via an exemption, to allow the use of risk information (as used in the NRC approved Graded Quality Assurance process for establishing the risk significance of equipment) to permit minimal increases in risk. The approved STPNOC GQA process for determination of non-risk-significant and low-risk-significant would define acceptable " minimal" changes to the facility.
o I
j Establish that the exemption to the definitions extends to their use throughout the regulations. l i
l Request exemption to 10CFR50.54(a) to remove any ambiguity regarding the application of the already approved GQA process to the reclassification of SSCs.
l . Exempt non-risk-significant components from the requirements of 10CFR50.49,10CFR50.65, l and 10CFR100.
l l
Provide relief as needed from 10CFR50.55a for reduction in ISI/IST scope.
How the above change would be used: l Through the NRC approved Graded Quality Assurance process for ranking component risk significance, groups of risk-important components within a system which have been risk '
ranked as non-risk significant, would be declassified (i.e., classification changed from safety-related or Important-to-Safety to not risk-important).
I The risk informed 10CFR50.59 process described above would be exercised for risk-important l- components within a system which have been risk ranked as LOW risk significant and are l determined to not exceed a ' minimal' threshold for increases in risk would be declassified l (i.e., classification changed from Important-to-Safety or safety-related to not risk-important).
j In addition, the risk informed 10CFR50.59 process would be used to determine if proposed l changes to tN South Texas Project represents a change that is greater than minimal, thus resulting in ,ut unresolved safety question.
Components reclassified as not risk-important would be removed from the scope of the aforementioned regulations (i.e.,10CFR50.49,10CFR50.65,10CFR100, and 10CFR50.55a (as applicable)) pMaining to risk-important equipment. Requests for removal from the scope of other regulations would 'oe submitted at a later time.
The scope of the expanded pilot effort would apply to the systems risk-ranked by the Graded Quality Assurance process. It is expected that the following systems will go through the risk-ranking process by mid-1999, with other systems to follow.
Chemical and Volume Control (CV)* SafetyInjectica (SI)
Radiation Monitoring (RA)* Auxiliary F:edwater (AF)
Essential Cooling Water (EW)* Mechanical Auxiliary Building HVAC (HM)
- Emergency Diesel Generators (DG)* Residual Heat Removal (RH) i Reactor Coolant (RC)* Steam Generator Blowdown (SB) l Electrical Auxiliary Building HVAC (HE)* Main Steam (MS)
- Component Cooling Water (CC)* Main Feedwater (FW) l 4
, - ,- - , . . ,-m,-- --~,,_--.s -m---,- - -. - - - , - -_ e , ,-_.--
L Essential Chilled Water (CH)* Reactor Containment Building HVAC (HC)
Fuel Handling Building HVAC (HF)
- Systems which have already been risk-ranked by the GQA program.
EFFECTS:
i i
UFSAR Section 3.2, Classification of Structures, Components and Systems, will be rewritten.
l l The current design and/or procurement specifications will not be amended in such a way that equipment design or performance capabilities will be impaired. Removal or abandonment of equipment supporting non risk significant functions will be performed using the risk
( infu...;d 10CFR50.59 process, t
Non-risk significant equipment will be removed from Technical Specifications where practical (separate license amendments will be submitted) i Non-risk Significant SSCs will be removed the from scope of testing programs in separate submittals such as the following:
Motor Operated Valve Program (routine preventive maintenance still performed) y Air Operated Valve Program (routine preventive maintenance still performed)
ISI/IST Program (50.55a relief requested for those removed from scope)
Snubbers l
Molded case circuit breakers l SAFETY EFFECTS:
i Safety effects have been reviewed and approved by the NRC in the STPNOC Graded '
Quality Assurance applications.
PROPOSED IMPLEMENTATION OF GQA AND RISK INFORMED 50.59 l l- How proposed GQA and Risk Infonned 10CFR Regulation Subject 50.59 and 50.54(a) would be used l 50.49- Equipment Qualification Components reclassified to non-risk-important would be exempted from scope l of50.49.
50.65 Maintenance Rule Components reclassified to non-risk- ,
' important would be exempted from scope -
of50.65. '
4 I
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j:
l L .-50.55a Inservice Testing Components reclassified to non-risk-l important would be removed from scope l
l of 50.55a.
1 I
10CFR100 Seismic Criteria Component reclassified to non risk- 1 important would be exempted from I Part 100 seismic requirements. l 1
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a l
PROPOSED RISK INFORMED REGULATORY CHANGE PURPOSE OF STPNOC PILOT This pilot is a continuation of the Graded Quality Assurance (GQA) pilot that will define the !
regulatory changes necessary to fully implement risk-informed changes to 10CFR50 and I supporting tegulations.
EXISTING SITUATION:
e NRC's regulations require that components categorized as safety related be qualified to meet the requirements of 10CFR50.49 (Equipment Qualification),10CFR100 (seismic),
and other substantive regulations. Through the GQA risk significance evaluation process (which has been reviewed / approved by the NRC in a Safety Evaluation Report (SER) dated 11/6/97), a number of these safety related components have been determined to be non-risk significant (NRS).
- NRC's substantive regulations provide no exception for safety related components that are NRS, and an exemption from the regulations would be required to reclassify safety-related components to non-safety related. Similarly, there are no provisions in the regulations which would allow reclassification of safety related LOW risk significant components that do not exceed a ' minimal' threshold (i.e., change of IE-5 is not
)
I acceptable) for increases in risk. This is largely attributable to the deterministic definition of" safety related" in 10CFR50.2 and to other references to "important to safety", which I encompasses safety related. The frequent use of these terms throughout the regulations is l probably the largest single obstacle to the application of risk-informed processes.
Therefore, in order to be able to reclassify components, a change in the 10CFR50.2 definition or the substantive regulations, or an exemption will be needed.
- An exemption or change in the application and use of 10CFR50.59 is also needed. Even if the 10CFR50.2 definition is revisci i 10CFR50.59 evaluation performed to reclassify these NRS components from safety related to non-safety related will likely find that an unreviewed safety question (USQ) exists. The USQ results from the deterministic application of 10CFR50.59 where the probability of a malfunction of equipment important to safety may be increased and/or the margin of safety for a Technical Specification will be reduced. A USQ results regardless of the component's relationship to risk and regardless of the size ofincrease. Therefore,in order to be able to reclassify components without going through the license amendment process, either a change to 10CFR50.59 or an exemption is necessary.
e Finally, classifications of systems in the UFSAR could be construed to be part of the Quality Assurance program description and 10CFR50.54(a) would require NRC approval of the reclassifications. Therefore, a change to 10CFR50.54(a) or an exemption also would be needed to reclassify components.
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j PROPOSED RISK INFORMED REGULATORY CHANGE EROPOSED RISK INFORMED APPROACH:
STPNOC proposes the following risk informed regulatory changes as an extension to the existing Graded Quality Assurance pilot process: l e Request exemption to the definition of safety related in t0CF R50.2 to allow a definition
! of risk-important as an alternative to safety related.
l The following definition of risk-important is proposed as an alternate to the definition of safety related:
l Risk-important Structures, Systems and Components (SSCs) may be l I '
identified based on approved risk informed processes. The risk-important definition may be used in place of the safety-related definition and in place of the term "important to safety" and any similar terms.
- e Establish that the exemption to the definitions extends to their use throughout the regulations.
e Allow the application of a risk-infonned 10CFR50.59 process, via an exemption, to allow the use of risk information (as used in the NRC approved Graded Quality Assurance process for establishing the risk significance of equipment) to permit minimal increases in risk. The approved STPNOC GQA process for determination of non-risk-significant and low-risk-l significant would define acceptable " minimal" changes to the facility.
e Request exemption to 10CFR50.54(a) to remove any ambiguity regarding the application of l the already approved GQA process to the reclassification of SSCs.
!
- Exempt non-risk-significant components from the requirements of 10CFR50.49, l 10CFR50.65,10CFR100 and other regulations that apply to safety related or important to safety SSCs.
- Provide relief as needed from 10CFR50.55a for reduction in ISI/IST scope.
I How the above change would be used:
e Through the NRC approved Graded Quality Assurance process for ranking component risk significance, groups of safety related components within a system which have been risk ranked as non-risk important, would be reclassified (i.e., classification changed from safety-related or Important-to-Safety to not risk-important).
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l l PROPOSED RISK INFORMED REGULATORY CHANGE I I -
l t
1 e The risk informed 10CFR50.59 process described above would be exercised for components within a system which have been risk rt.nked as LOW risk significant and are determined to l not exceed a ' minimal' threshold for increases in risk would be reclassified (i.e.,
classification changed from Important-to-Safety or safety-related to not risk-important). In i addition, the risk informed 10CFR50.59 process would be used to determine if proposed changes to the South Texas Project represent a change that is greater than minimal, thus resulting in an unresolved safety question.
e Components reclassified as not risk-important would be removed from the scope of the l
aforementioned regulations (e.g.,10CFR50.49,10CFR50.65,10CFR100, and 10CFR50.55a
- (as applicable)) pertaining to safety related or important to safety equipment.
e The scope of the expanded pilot effort would apply to the systems risk-ranked by the Graded Quality Assurance process. It is expected that the following systems will go through the risk-ranking process by mid-1999, with other systems to follow.
Chemical and Volume Control (CV)* Safety Injection (SI)
Radiation Monitoring (RA)* Auxiliary Feedwater (AF)
Essential Cooling Water (EW)* Mechanical Auxiliary Building HVAC (HM)
Emergency Diesel Generators (DG)* Residual Heat Removal (RH)
, Reactor Coolant (RC)* Steam Generator Blowdown (SB) i Electrical Auxiliary Building HVAC (HE)* Main Steam (MS)
Component Cooling Water (CC)* Main Feedwater(FW)
Essential Chilled Water (CH)* Reactor Containment Building HVAC (HC) j Fuel Handling Building HVAC (HF)
- Systems which have already been risk-ranked by the GQA program.
l EFFECTS:
i e UFSAR Section 3.2, Classification of Structures, Components and Systems, will be I rewritten. Conforming changes will be made in other sections of the UFSAR as necessary.
l
- The design and/or procurement specifications will continue to maintain required equipment l
l design and performance pm ameters. Removal or abandonment of e(jpment supporting non-
! nsk significant functions will be performed using the risk informed 10CFR50.59 process.
1 o Non-risk significant equipment will be removed from Technical Specifications where practical (separate license amendments will be submitted)
- Non-risk Significant SSCs will be removed from the scope of testing programs such as the following:
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PROPOSED RISK INFORMED REGULATORY CHANGE
=
Motor Operated Valve Program (routine preventive maintenance still performed),
Air Operated Valve Program (routine preventive maintenance still performed),
' ISI/IST Program (50.55a relief requested for those removed from scope),
SAFETY EFFECTSi The risk ranking process, which has been reviewed and approved by the NRC in the STPNOC Graded Quality Assurance application, has determined that there will be no adverse safety affects.
PROPOSED IMPLEMENTATION OF GQA AND RISK INFORMED 50.59 Ilow proposed GQA and Risk Informed 10CFR Regulation . Subject 50.59 and 50.54(a) would be used 50.49 Equipment Qualification Components reclassified to non-risk-important would be exempted from scope of 50.49.
50.65 Maintenance Rule Components reclassified to non-risk-important would be exempted from scope l of 50.65. ~
50.55a Inservice Testing Components reclassified to non-risk-l important would be removed from secpe i of 50.55a.
j 10CFR100 Seismic Criteria Component reclassified to non-risk-l important would be exempted from l Part 100 seismic requirements.
Other substantive Misc. Components reclassified to non-risk regulations important tvould be exempted from these substantive requirements.
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