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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20212H2231999-09-24024 September 1999 Summary of 990831-0901 Meeting with STPNOC in Rockville, Maryland Re 990713 Request for 14 risk-informed Exemptions to Exclude safety-related LSSC & non-risk Significant Components from Special Treatment Requirements ML20210Q1841999-08-11011 August 1999 Summary of 990722 Meeting with Util Re Proposed TS for SG Water Level low-top Trip Setpoint.List of Meeting Attendees & Handout Provided by Util Encl ML20206G4841999-04-30030 April 1999 Summary of 990315 Meeting with STP Nuclear Operating Co Re Util Submittal of Draft Request for Exemption from Special Treatment Requirements for Components That Are Low Safety Significant or non-risk Significant, ML20199D1931999-01-11011 January 1999 Summary of 981208 Meeting with STPNOC Re Status of Current & Future Licensing Actions & Activities.List of Meeting Attendees & Handout Provided by Licensee Encl ML20195G0641998-11-17017 November 1998 Summary of 980915 Meeting with STP Nuclear Operating Co Re Graded Quality Assurance Implementation & Challenges.List of Attendees & Handout Provided by Licensee Encl ML20155E1271998-11-0202 November 1998 Summary of 981008 Conference Call with Util to Discuss Course Action That Would Be Anticipated If Licensee Were to Submit risk-informed Inservice Insp &/Or risk-informed Inservice Testing Program ML20154J7961998-10-13013 October 1998 Summary of 980915 Meeting with Licensee Re risk-informed Operations at Stp.Copies of Slides Presented Encl ML20247L7411998-05-20020 May 1998 Summary of 980506 Meeting W/Util in Re Proposed Merger Between America Electric Power Co,Inc & Central & Southwest Corp (Csw).Meeting Attendees & Handout Provided by Csw Encl ML20217Q6491998-05-0505 May 1998 Summary of 980413 Meeting W/South Texas Project Nuclear Operating Company Re Current South Texas Project Improved TS Schedule.List of Meeting Attendees & Schedule Encl ML20217N0851998-04-0606 April 1998 Summary of 980303 Meeting W/South Texas Project Re long-term Resolution of Bulletin 88-08, Thermal Stresses in Piping Connected to Reactor Coolant System. Proprietary & non-proprietary Handouts Provided by Licensee Encl ML20199J3371998-02-0202 February 1998 Summary of 980121 Meeting W/Stp Nuclear Operating Co Re Schedule for NRC Review of STPNOC Application for Conversion to Improved Standard Ts.List of Attendees & Handout Provided by Licensee Encl ML20198K4781998-01-0606 January 1998 Summary of 971204 Meeting W/Licensee & Representatives from W Re Proposed 3 Volt Alternate Repair Criteria for Plants Unit 2 Sg.List of Attendees & Handout Encl ML20198G4601997-12-19019 December 1997 Summary of 971210 Meeting W/Licensee Re SG Replacement for Unit 1.List of Attendees & Handout Matls Provided by Licensee Encl ML20199E5771997-11-13013 November 1997 Trip Rept of 971105-06 Visit to Facility for Interviews in Preparation of SALP for Plant ML20212G5041997-10-29029 October 1997 Summary of 971002 Meeting W/Util in Rockville,Md to Discuss Staff Review Schedule for Plant Improved Std TS Conversion Amend.List of Attendees Encl ML20217E4511997-09-22022 September 1997 Summary of 970911 Meeting W/Util in Rockville,Md Re STP 3-train Design & Improved Std TSs Format ML20141C0811997-05-14014 May 1997 Summary of 970424 Meeting W/Util to Discuss Hl&P Plans Re Incomplete Control Rod Insertion at Stp,Units 1 & 2.Meeting Attendees & Handout Provided by Hl&P,Encl ML20140H7801997-05-0808 May 1997 Summary of 970421 Meeting W/Hl&P to Discuss Hl&P Proposed QA Program Change to Implement Graded QA ML20137Z3651997-04-22022 April 1997 Summary of 970403 Meeting W/Util in Rockville,Md to Discuss Staff Review of Licensee Pilot Submittal for Section 3.5 of Project Conversion Amend.List of Attendees & Staff Handouts Encl ML20137Q8641997-04-0909 April 1997 Summary of 970331 Meeting W/Util Re Util Graded QA Application.List of Attendees Encl ML20137F2351997-03-24024 March 1997 Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants ML20133N3821997-01-17017 January 1997 Summary of 970109 Meeting W/Hl&P Re Response to NRC Bulletin 96-01, Control Rod Insertion Problems. List of Attendees & Licensee Handout Encl ML20133M2671997-01-15015 January 1997 Summary of 961212 Meeting W/Util Re Status of Staff Review of Licensee Request to Convert Plant TS to Improved Std TS Format.List of Attendees Encl ML20134L7841996-11-20020 November 1996 Summary of 961114 Meeting W/Hl&P in Rockville,Md to Discuss Status of NRC Review of Licensee Request to Convert STP TSs to Improved STS Format.List of Attendees Encl ML20206R4701996-11-0707 November 1996 Summary of 960821-22 Meetings with Hl&P in Wadsworth,Texas Re Graded Quality Assurance Program at Stp.List of Meeting Attendees for Initial Meeting,List of Meetings Held During Two Day Session & Handouts for Meetings Encl ML20128L2901996-10-0808 October 1996 Summary of 960916 Meeting W/Hl&P to Discuss Plans for SG Replacement at STP-1.List of Attendees & Handout Encl ML20059K1731994-01-27027 January 1994 Summary of 940121 Meeting W/Utils Re Results of Operational Readiness Assessment Team Insp at Plant.Various Deficiencies Noted.Media Representatives in Attendance ML20059F3491994-01-0606 January 1994 Summary of 931217 Meeting W/Hl&P Re Analysis Performed on Ecw Sys.W/Attendance List & Meeting Agenda ML20058L7311993-12-13013 December 1993 Summary of 931108-09 Meeting W/Licensee in Rockville,Md Re Resolution of NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. Agenda & List of Attendees Encl ML20059A6861993-10-0808 October 1993 Discusses 931006 Operating Reactors Events Briefing 93-38 Which Informed Senior Managers from Listed Ofcs of Selected Events That Occurred Since Last Briefing on 930929.Attendees Listed in Encl 1 ML20128P8491993-02-18018 February 1993 Summary of Operating Reactors Events Briefing 93-05 on 930210 ML20062B3771990-10-15015 October 1990 Summary of 900919 Meeting W/Util & Sandia Re Fire Protection Portion of Probability Safety Assessment ML20056A0011990-07-27027 July 1990 Summary of 900530-31 Meeting W/Sandia Natl Labs & Util Re PRA Review.Meeting Attendees Listed in Encl 1 ML20058L0521990-07-19019 July 1990 Summary of 891128 & 29 Meetings W/Util,Sandia & Sea,Inc Re Plant Probability & Safety Assessment.List of Attendees & Sandia Questions W/Licensee Answers Encl ML20246P6111989-09-0505 September 1989 Summary of 881130 Meeting W/Util at Plant Re Ability of Pressurizer Surge Line to Withstand Effects of Thermal Stratification.Discussions Concentrated in Areas of Design Documentation,Thermal Hydraulics & Stratification ML20246K2171989-08-24024 August 1989 Summary of Operating Reactors Events Meeting 89-30 on 890823 Re Reactor Trip W/Multiple Instrumentation & Equipment Failures at DC Cook Unit 2 on 890814 & Auxiliary Feedwater Flows at Hb Robinson ML20245J4261989-08-11011 August 1989 Summary of 890808 Meeting W/Util & Sandia at Sandia Re PRA Study for Plant.Attendance List & Viewgraphs Encl ML20246P1811989-05-0909 May 1989 Summary of 890506 Meeting W/Utils & Westinghouse Re Licensee Decision to Remove Remainder of Excessive Cooldown Protection Circuitry & Amend to Tech Specs.List of Meeting Attendees & Licensee Meeting Handout Encl NUREG-0781, Summary of 890130-0201 Meeting W/Westinghouse,Houston Lighting & Power,Texas Utils,Bnl & EAS in Monroeville,Pa Re Overview of Status of Work on Bmi Thimble Tube Wear.Related Info Encl1989-05-0909 May 1989 Summary of 890130-0201 Meeting W/Westinghouse,Houston Lighting & Power,Texas Utils,Bnl & EAS in Monroeville,Pa Re Overview of Status of Work on Bmi Thimble Tube Wear.Related Info Encl ML20246L2621989-05-0909 May 1989 Summary of 880517 Meeting W/Util & Westinghouse Re Results of bottom-mounted Instrumentation Thimble Tube Insp. List of Meeting Attendees.Presentation Matl Handout Withheld ML20245F5081989-04-25025 April 1989 Summary of 890127 Meeting W/Util Re Status of Licensee Pra. List of Attendees,Agenda & Util Presentation Slides Encl ML20196E2621988-12-0202 December 1988 Summary of 881129 Meeting W/Util & Newman & Holtzinger Re Readiness for Low Power License.List of Attendees & Viewgraphs Encl ML20204D5431988-10-12012 October 1988 Summary of 880908 Meeting W/Util in Arlington,Tx Re Schedule for Completion of Certain Security Tasks ML20154N4471988-09-0707 September 1988 Summary of Operating Reactors Events Meeting 88-036 on 880906 Re Events Which Occurred Since Last Meeting on 880830.List of Attendees Encl ML20153D4941988-08-26026 August 1988 Summary of 880810 Meeting W/Util,Westinghouse & BNL Re Status of Studies on Bmi Thimble Tube Wear Problems. Discussions & Licensee Handout Withheld ML20151N0521988-07-26026 July 1988 Summary of Operating Reactors Events Meeting 88-30 on 880726.List of Attendees & Summary of Reactor Scrams Encl ML20196A9201988-06-17017 June 1988 Summary of Operating Reactors Events Meeting 88-24 on 880614.Two Significant Events Identified for Input to NRC Performance Indicator Program.No Events Suggested for long-term Followup.List of Attendees Encl ML20151W5141988-04-21021 April 1988 Summary of Operating Reactors Events Meeting 88-016 on 880419 in Rockville,Md.List of Attendees & Viewgraphs Encl ML20237D8231987-12-17017 December 1987 Summary of 871030 Meeting W/Util Re Assessment of Util Compliance W/License Condition on Physical Security During Low Power Operation ML20237C6061987-12-14014 December 1987 Summary of 871202 Meeting W/Util & Bechtel Re Causes & Mods Relative to Pipe Failures in Auxiliary Feedwater Sys at Plant.List of Meeting Attendees & Util Handouts Encl 1999-09-24
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20212H2231999-09-24024 September 1999 Summary of 990831-0901 Meeting with STPNOC in Rockville, Maryland Re 990713 Request for 14 risk-informed Exemptions to Exclude safety-related LSSC & non-risk Significant Components from Special Treatment Requirements ML20210Q1841999-08-11011 August 1999 Summary of 990722 Meeting with Util Re Proposed TS for SG Water Level low-top Trip Setpoint.List of Meeting Attendees & Handout Provided by Util Encl ML20206G4841999-04-30030 April 1999 Summary of 990315 Meeting with STP Nuclear Operating Co Re Util Submittal of Draft Request for Exemption from Special Treatment Requirements for Components That Are Low Safety Significant or non-risk Significant, ML20199D1931999-01-11011 January 1999 Summary of 981208 Meeting with STPNOC Re Status of Current & Future Licensing Actions & Activities.List of Meeting Attendees & Handout Provided by Licensee Encl ML20195G0641998-11-17017 November 1998 Summary of 980915 Meeting with STP Nuclear Operating Co Re Graded Quality Assurance Implementation & Challenges.List of Attendees & Handout Provided by Licensee Encl ML20155E1271998-11-0202 November 1998 Summary of 981008 Conference Call with Util to Discuss Course Action That Would Be Anticipated If Licensee Were to Submit risk-informed Inservice Insp &/Or risk-informed Inservice Testing Program ML20154J7961998-10-13013 October 1998 Summary of 980915 Meeting with Licensee Re risk-informed Operations at Stp.Copies of Slides Presented Encl ML20247L7411998-05-20020 May 1998 Summary of 980506 Meeting W/Util in Re Proposed Merger Between America Electric Power Co,Inc & Central & Southwest Corp (Csw).Meeting Attendees & Handout Provided by Csw Encl ML20217Q6491998-05-0505 May 1998 Summary of 980413 Meeting W/South Texas Project Nuclear Operating Company Re Current South Texas Project Improved TS Schedule.List of Meeting Attendees & Schedule Encl ML20217N0851998-04-0606 April 1998 Summary of 980303 Meeting W/South Texas Project Re long-term Resolution of Bulletin 88-08, Thermal Stresses in Piping Connected to Reactor Coolant System. Proprietary & non-proprietary Handouts Provided by Licensee Encl ML20199J3371998-02-0202 February 1998 Summary of 980121 Meeting W/Stp Nuclear Operating Co Re Schedule for NRC Review of STPNOC Application for Conversion to Improved Standard Ts.List of Attendees & Handout Provided by Licensee Encl ML20198K4781998-01-0606 January 1998 Summary of 971204 Meeting W/Licensee & Representatives from W Re Proposed 3 Volt Alternate Repair Criteria for Plants Unit 2 Sg.List of Attendees & Handout Encl ML20198G4601997-12-19019 December 1997 Summary of 971210 Meeting W/Licensee Re SG Replacement for Unit 1.List of Attendees & Handout Matls Provided by Licensee Encl ML20212G5041997-10-29029 October 1997 Summary of 971002 Meeting W/Util in Rockville,Md to Discuss Staff Review Schedule for Plant Improved Std TS Conversion Amend.List of Attendees Encl ML20217E4511997-09-22022 September 1997 Summary of 970911 Meeting W/Util in Rockville,Md Re STP 3-train Design & Improved Std TSs Format ML20141C0811997-05-14014 May 1997 Summary of 970424 Meeting W/Util to Discuss Hl&P Plans Re Incomplete Control Rod Insertion at Stp,Units 1 & 2.Meeting Attendees & Handout Provided by Hl&P,Encl ML20140H7801997-05-0808 May 1997 Summary of 970421 Meeting W/Hl&P to Discuss Hl&P Proposed QA Program Change to Implement Graded QA ML20137Z3651997-04-22022 April 1997 Summary of 970403 Meeting W/Util in Rockville,Md to Discuss Staff Review of Licensee Pilot Submittal for Section 3.5 of Project Conversion Amend.List of Attendees & Staff Handouts Encl ML20137Q8641997-04-0909 April 1997 Summary of 970331 Meeting W/Util Re Util Graded QA Application.List of Attendees Encl ML20137F2351997-03-24024 March 1997 Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants ML20133N3821997-01-17017 January 1997 Summary of 970109 Meeting W/Hl&P Re Response to NRC Bulletin 96-01, Control Rod Insertion Problems. List of Attendees & Licensee Handout Encl ML20133M2671997-01-15015 January 1997 Summary of 961212 Meeting W/Util Re Status of Staff Review of Licensee Request to Convert Plant TS to Improved Std TS Format.List of Attendees Encl ML20134L7841996-11-20020 November 1996 Summary of 961114 Meeting W/Hl&P in Rockville,Md to Discuss Status of NRC Review of Licensee Request to Convert STP TSs to Improved STS Format.List of Attendees Encl ML20206R4701996-11-0707 November 1996 Summary of 960821-22 Meetings with Hl&P in Wadsworth,Texas Re Graded Quality Assurance Program at Stp.List of Meeting Attendees for Initial Meeting,List of Meetings Held During Two Day Session & Handouts for Meetings Encl ML20128L2901996-10-0808 October 1996 Summary of 960916 Meeting W/Hl&P to Discuss Plans for SG Replacement at STP-1.List of Attendees & Handout Encl ML20059K1731994-01-27027 January 1994 Summary of 940121 Meeting W/Utils Re Results of Operational Readiness Assessment Team Insp at Plant.Various Deficiencies Noted.Media Representatives in Attendance ML20059F3491994-01-0606 January 1994 Summary of 931217 Meeting W/Hl&P Re Analysis Performed on Ecw Sys.W/Attendance List & Meeting Agenda ML20058L7311993-12-13013 December 1993 Summary of 931108-09 Meeting W/Licensee in Rockville,Md Re Resolution of NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. Agenda & List of Attendees Encl ML20059A6861993-10-0808 October 1993 Discusses 931006 Operating Reactors Events Briefing 93-38 Which Informed Senior Managers from Listed Ofcs of Selected Events That Occurred Since Last Briefing on 930929.Attendees Listed in Encl 1 ML20128P8491993-02-18018 February 1993 Summary of Operating Reactors Events Briefing 93-05 on 930210 ML20062B3771990-10-15015 October 1990 Summary of 900919 Meeting W/Util & Sandia Re Fire Protection Portion of Probability Safety Assessment ML20056A0011990-07-27027 July 1990 Summary of 900530-31 Meeting W/Sandia Natl Labs & Util Re PRA Review.Meeting Attendees Listed in Encl 1 ML20058L0521990-07-19019 July 1990 Summary of 891128 & 29 Meetings W/Util,Sandia & Sea,Inc Re Plant Probability & Safety Assessment.List of Attendees & Sandia Questions W/Licensee Answers Encl ML20246P6111989-09-0505 September 1989 Summary of 881130 Meeting W/Util at Plant Re Ability of Pressurizer Surge Line to Withstand Effects of Thermal Stratification.Discussions Concentrated in Areas of Design Documentation,Thermal Hydraulics & Stratification ML20246K2171989-08-24024 August 1989 Summary of Operating Reactors Events Meeting 89-30 on 890823 Re Reactor Trip W/Multiple Instrumentation & Equipment Failures at DC Cook Unit 2 on 890814 & Auxiliary Feedwater Flows at Hb Robinson ML20245J4261989-08-11011 August 1989 Summary of 890808 Meeting W/Util & Sandia at Sandia Re PRA Study for Plant.Attendance List & Viewgraphs Encl ML20246L2621989-05-0909 May 1989 Summary of 880517 Meeting W/Util & Westinghouse Re Results of bottom-mounted Instrumentation Thimble Tube Insp. List of Meeting Attendees.Presentation Matl Handout Withheld ML20246P1811989-05-0909 May 1989 Summary of 890506 Meeting W/Utils & Westinghouse Re Licensee Decision to Remove Remainder of Excessive Cooldown Protection Circuitry & Amend to Tech Specs.List of Meeting Attendees & Licensee Meeting Handout Encl NUREG-0781, Summary of 890130-0201 Meeting W/Westinghouse,Houston Lighting & Power,Texas Utils,Bnl & EAS in Monroeville,Pa Re Overview of Status of Work on Bmi Thimble Tube Wear.Related Info Encl1989-05-0909 May 1989 Summary of 890130-0201 Meeting W/Westinghouse,Houston Lighting & Power,Texas Utils,Bnl & EAS in Monroeville,Pa Re Overview of Status of Work on Bmi Thimble Tube Wear.Related Info Encl ML20245F5081989-04-25025 April 1989 Summary of 890127 Meeting W/Util Re Status of Licensee Pra. List of Attendees,Agenda & Util Presentation Slides Encl ML20196E2621988-12-0202 December 1988 Summary of 881129 Meeting W/Util & Newman & Holtzinger Re Readiness for Low Power License.List of Attendees & Viewgraphs Encl ML20204D5431988-10-12012 October 1988 Summary of 880908 Meeting W/Util in Arlington,Tx Re Schedule for Completion of Certain Security Tasks ML20154N4471988-09-0707 September 1988 Summary of Operating Reactors Events Meeting 88-036 on 880906 Re Events Which Occurred Since Last Meeting on 880830.List of Attendees Encl ML20153D4941988-08-26026 August 1988 Summary of 880810 Meeting W/Util,Westinghouse & BNL Re Status of Studies on Bmi Thimble Tube Wear Problems. Discussions & Licensee Handout Withheld ML20151N0521988-07-26026 July 1988 Summary of Operating Reactors Events Meeting 88-30 on 880726.List of Attendees & Summary of Reactor Scrams Encl ML20196A9201988-06-17017 June 1988 Summary of Operating Reactors Events Meeting 88-24 on 880614.Two Significant Events Identified for Input to NRC Performance Indicator Program.No Events Suggested for long-term Followup.List of Attendees Encl ML20151W5141988-04-21021 April 1988 Summary of Operating Reactors Events Meeting 88-016 on 880419 in Rockville,Md.List of Attendees & Viewgraphs Encl ML20237D8231987-12-17017 December 1987 Summary of 871030 Meeting W/Util Re Assessment of Util Compliance W/License Condition on Physical Security During Low Power Operation ML20237C6061987-12-14014 December 1987 Summary of 871202 Meeting W/Util & Bechtel Re Causes & Mods Relative to Pipe Failures in Auxiliary Feedwater Sys at Plant.List of Meeting Attendees & Util Handouts Encl ML20236P2841987-11-0505 November 1987 Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl 1999-09-24
[Table view] |
Text
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f %,4 UNITED STATES g y NUCLEAR REGULATORY COMMISSION p # WASHINGTON. D.C. 20666-4001
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- April 22, 1997 LICENSEE: HOUSTON LIGHTING & POWER COMPANY FACILITY: South Texas Project
SUBJECT:
SUMMARY
OF APRIL 3, 1997, MEETING ON THE SOUTH TEXAS PROJECT REQUEST TO CONVERT TO THE IMPROVED STANDARD TECHNICAL SPECIFICATIONS A meeting was held on Thursday, April 3,1997, for the Nuclear Regulatory Commission (NRC) staff and the licensee to discuss the staff's review of the licensee's pilot submittal for Section 3.5 of the South Texas Project (STP) conversion amendment. The meeting was held at the request of the staff at NRC headquarters in Rockville, Maryland. A notice of this meeting was issued on March 18, 1997. Attachment.1 is the list of attendees. Attachment 2 is the staff's handout used daring the meeting.
In a letter to the licensee dated November 27, 1996, te staff identified numerous deficiencies in the licensee's amendment request to convert the STP Technical Specifications (TS) to the improved Standard Technical Specification format. A meeting was held on December 12, 1996, to discuss how best to supplement the original application. During that meeting, the licensee stated that a pilot supplemental submittal for one section of the TS would be submitted for staff review prior to a full supplement for the entire conversion amendment. On February 11, 1997, the licensee submitted revised Section 3.5 of the TS for staff review.
During the April 3, 1997, meeting, the staff noted that the licensee's pilot submittal did attempt to address previous comments made by the NRC regarding the adequacy of the technical justification supporting the amendment.
However, the staff noted that there are still some areas for improvement.
Specifically, the key areas that need additional work are: (1) the philosophy behind which STP is converting TS for a standard 2-train plant to TS for the STP 3-train design; and (2) the issue of staggered test basis.
As identified in Attachment 2, the staff noted that the licensee's discussions in the February 11, 1997, submittal regarding the 3-train philosophy and staggered test basis were somewhat confusing and needed to be reworked. The licensee agreed to modify the table in the pilot submittal that contains proposed changes in allowed outage times (A0Ts) to make it more clear with respect to conformance with the standard TS A0Ts. Currently, the A0Ts for a number of systems with 2 trains inoperable are not consistent with the standard TS A0Ts for systems with I train inoperable. The staff indicated that the licensee needed to focus on consistency between the STP A0Ts and
- those in the standard TS.
t
- The staff also noted that the licensee's discussion of staggered testing i requirements in the February 11, 1997, submittal was confusing. The licensee agreed to rewrite that discussion in more simple terms to identify the need for STP to have a longer interval in which to accomplish the staggered testing 9704240119 970422 PDR ADOCK 05000498
=
EC E E M S M W O C ('I i P PDR
l I
l l
> l requirements. The need for a larger interval stems f:om the fact that STP has 3 trains to test rather than the standard 2 trains at most other nuclear plants. Therefore, the time between tests will be langer.
The staff then proceeded to go through each of the ct.nversion packaging I examples identified in Attachment 2. The staff pointed cut that the wording in a number of the discussion of changes was confusing and could be more clear as to what was being changed, why it was being changed, and why that change .
was acceptable. The staff agreed to send the licensee a comprehensive listing l of the issues identified by the NRC's contractor who reviewed the licensee's j original conversion application. The staff noted that the contractor's report '
had not been reviewed by the staff for accuracy. I 1
At the end of the meeting, the licensee noted that they would be reworking the l discussions on 3-train conversion and staggered test basis and resubmitting them to the staff in the near future. In addition, the licensee is still on track to provido the remaining revised TS sections for staff review sometime in June 1997.
CRIGIfML SIGED BY:
Janet L. Kennedy, Project Manager Project Directorate IV-1 i Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499 Attachments: 1. List of fleeting Attendees
- 2. NRC Handout cc w/atts: See next page DISTRIBUTION:
HARD COPY E-MAIL Docket File SCollins/FMiraglia (SJC1/FJM) RZimmerman (RPZ)
PUBLIC JRoe (JWR) EAdensam (EGA1)
PD4-1 r/f TAlexion (TWA) CHawes (CMH2)
OGC WBeckner (WDB) PGwynn (TPG)
ACRS CSchulten (CSSI) JKennedy (JLK2)
CGrimes (CIG) ETomlinson (EBT)
Document Name: ST040397.MTS %db 0FC PM/PD4-1 ._ LA/PD4-1 TSB S
//_ D/PD4-1(M H NAME JKennedy/vw CHawesAGU CGrimedMk WBecknh[6 DATE il // 7/97 Y//8/97 &/M/97 9 /22/97 COPY DES /N0 YES/N0 dS'fN0 YES/(To>
0FFICIAL RECORD COPY gg3gCMTEBCDPV
t 4
requirements. The need for a larger interval stems from the fact that STP has 3 trains to test rather than the standard 2 trains at most other nuclear
. plants. Therefore, the time between tests will be longer.
The staff then proceeded to go through each of the conversion packaging examples idontified in Attachment 2. The staff pointed out that the wording in a number of the discussion of changes was confusing and could be more clear as to what was being changed, why it was being changed, and why that change was acceptable. The staff agreed to send the licensee a comprehensive listing of the issues identified by the NRC's contractor who reviewed the licensee's original conversion application. The staff noted that the contractor's report had not been reviewed by the staff for accuracy.
At the end of the meeting, the licensee noted that they would be reworking the discussions on 3-train conversion and staggered test basis and resubmitting them to the staff in the near future. In addition, the licensee is still on
, track to provide the remaining revised TS sections for staff review sometime i
in June 1997.
- s ie L /anwkp .,
Janet L. Kennedy, Project Manager Project Directorate IV-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
! Attachments: 1. List of Meeting Attendees
- 2. NRC Handout 4
cc w/atts: See next page l
d 1
. Houston Lighting & Power Company South Texas, Units 1 & 2 cc:
Mr. David P. Loveless Jack R. Newman, Esq.
Senior Resident Inspector Morgan, Lewis & Bockius U.S. Nuclear Regulatory Commisrion 1800 M Street, N.W.
P. O. Box 910 Washington, DC 20036-5869 Bay City, TX 77414 Mr. Lawrence E. Martin Mr. J. C. Lanier/M. B. Lee General Manager, Nuclear Assurance Licensing City of Austin Houston Lighting and Power Company Electric Utility Department P. O. Box 289 721 Barton Springs Road Wadsworth, TX 77483 Austin, TX 78704 Rufus S. Scott Mr. M. T. Hardt Associate General Counsel Mr. W. C. Gunst Houston Lighting and Power Company City Public Service Board P. O. Box 61867 P. O. Box 1771 Houston, TX 77208 San Antonio, TX 78296 Joseph R. Egan, Esq.
Mr. G. E. Vaughn/C. A. Johnson Egan & Associates, P.C.
Central Power and Light Company 2300 N Street, N.W.
P. O. Box 289 Washington, DC 20037 Mail Code: N5012 Wadsworth, TX 74483 Office of the Governor ATTN: Andy Barrett, Director INP0 Environmental Policy Records Center P. O. Box 12428 700 Galleria Parkway Austin, TX 78711 Atlanta, GA 30339-3064 Arthur C. Tate, Director Regional Administrator, Region IV Division of Compliance & Inspection U.S. Nuclear Regulatory Commission Bureau of Radiation Control 611 Ryan Plaza Drive, Suite 400 Texas Department of Health Arlington, TX 76011 1100 West 49th Street Austin, TX 78756 Dr. Bertram Wolfe 15453 Via Vaquero Texas Public Utility Commission Monte Sereno, CA 95030 ATTN: Mr. Glenn k'. Dishong 7800 Shoal Creek Blvd.
Judge, Matagorda County Suite 400N Matagorda County Courthouse Austin, TX 78757-1024 1700 Seventh Street Bay City, TX 77414 Mr. William T. Cottle Executive VP & General Manager Nuclear Houston Lighting & Power Company South Texas Project Electric Generating Station P. O. Box 289 Wadsworth, TX 77483
1 ,
ATTENDEES AT MEETING OF APRIL 3. 1997 ON THE SOUTH TEXAS PROJECT CONVERSION PILOT SUBMITTAL 4
JME AFFILIATION
- J. Kennedy NRR/DRPW/PD4-1 i C. Schulten NRR/TSB T. Alexion NRR/DRPW/PD4-1 W. Beckner NRR/DRPW/PD4-1 M. McBurnett HL&P/ Licensing W. Harrison HL&P/ Licensing j M. Felix HL&P/ Licensing J. Self HL&P/ Excel J. Pinzon HL&P/ Licensing
- C. Grimes NRR/TSB
- E. Tomlinson NRR/TSB 1
)
ATTACHMENT 1 l
. j I
i South Texas Conversion LCO 3.5 Pilot Comments !
, Philosophy for incorporating Three-Train Design into improved Technical Specifications
-The objective of the conversion philosophy was intended to simply demonstrate comparability of the ITS for South Texas with the restrictions applicable to a two-train plant, to simply justify Completion. Times for one inoperable train or component. The philosophy described in the " pilot" package does not achieve this ;
objective, and appears to introduce unnecessary complexity to justify being I different from both the CTS and the STS. A typical justification for the three-train conditions consists of: The new ITS Actions are designed to include consideration of the unique STP three train design Independent RHR subsystems which are utilized for normalshutdown cooling in this condition, and LTOP considerations. In addition, Tables 1 and 2 are not very clarifying, and the notes to Table 2 raise additional questions regarding the finality of the Completion Time values in the conversion application.
The "three-train" philosophy can be more efficiently accompIlshed for the conversion (separate from the "four train" instrumentation philosophy) by developing a simply deterministic comparison to "two-train" allowances for system or component functional capabilities.
STP Staggered Test Basis STS Definition: A STAGGEREO TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or othcr designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.
STP proposes an adjustment in the intervals for staggered testing to accommodate the survelliance testing of three Engineered Safety Feature (ESF) trains instead of the standard two ESF trains. STP states that to manage the three safety train design, they use a twelve week maintenance and test (M&T) program to facilitate safe and effective plant operations. STP has the three safety trains and defines a j
" fourth train" comprised of safety related components such as RPS and ESF l l actuation logics. I
{ l l STP states that the current TS definition provides enough flexibility to adapt to the ;
l three safety feature train design, while the definition in the ISTS does not provide '
- the flexibility. The staff notes that for testing 3 trains at a 31 day frequency, CTS l
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l C l staggered test basis would require one train tested once every 10 and one third i days (31 days divided bv 3 trains). For testing 3 trains at a 31 day frequency, l
! STS staggered test basis would require one train tested once every 31 days (31 l
- days ilmaa 3 trains). STP states that the definition coupled with the surveillance ;
intervals found in ISTS is the basis for requesting staggered test intervals that I differ from the ISTS. Using " staggered intervals" in a 12 week M&T program )
appears to be unrelated to the defined term STAGGEREI) TEST BASIS used in STS 1 for establishing frequency requirements for specified TS surveillances. l l l Conversion Packaging Examples i
- 1. The proposed LCO 3.5.3 includes four Notes. Note 1 states that more than ADa HHSl pump breaker may be racked ja until one or more cold leg l temperatures (s) is/are less than 325'F.
l DOC L.9 (the justification for the proposed changes) includes a statement l that all but one HHSI pump breaker is required to be racked gut after I entering Mode 4 from Mode 3 orior to one or more cold leg temperature (s) j decreasing below 325'F.
o Note 1 in ITS LCO 3.5.3 does not agree with DOC L.9, and it appears l
that the Note may be wrong. The LCO requires 2 OPERABLE HHSI i pumps with one (1) pump breaker racked in while Note 1 would allow all HHSI breakers to be racked in until all four cold leg temperatures are less than 325'F.
- 2. Note 3 to the proposed LCO 3.5.3 states that all HHS! breakers may be racked nut prior to entering Mode 4 from Mode 5 until one or more RCS cold ,
leg temperature (s) is/are greater than 225'F. (Note that the term "may be racked out" implies that the breakers may also be racked in.)
DOC L.9, which was added as part of the pilot package, includes a statement that all but one HHS1 pump breakers is required to be racked nul after entering Mode 4 from Mode 5 prior to one or more cold leg temperatures exceeding 225'F.
e Proposed Note 3 and DOC L.9 do not agree. As written, Note 3 would allow all HHSI breakers to be racked JD with the Unit in Mode 4 (with RCS cold legs less than 225'). This appears to contradict the LCO which reouires 2' OPERABLE HHSI pumps and nne pump breaker racked in.
Comment: DOC L.9 is more representative of CTS requirements than l- proposed Note 3. The proposed Note is different than the STS and it may l
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be easier to include SRs to verify appropriate HHSI pump breaker positions as a function of plant status.
! 3. DOC L.9 provides justification for changing LCO 3.5.3 to delete the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
, requirement for restricting only one of the two operable HHSl pumps to have j lts breaker racked .1 for LTOP considerations and only allow abnormal
- alignments basec purely on the temperature of the RCS cold legs. Part of DOC L.9 states, "The four hour limit did little to contribute to minimization of risk, rather it imposed an additional unnecessary restriction on plant operators requiring diversion of their attention from proceeding with the required operations to track a time limit of little significance."
The above statement is part of the justification for replacing CTS 3.5.3.1 l
, Actions a and b with proposed insert 5. The justification lacks substance. I in addition, there is no explanation regarding a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> time limit in CTS '
Cond. a or b.
l 4. In the NUREG markup, parts of Cond. B and Action B.1 for LCO 3.5.3, l ECCS - Shutdown, are annotated with a reference to JFD 1 which, in turn,
- says that brackets are removed and plant specific nomenclature is provided.
The change to the NUREG consists of replacing the ECCS high head
- subsystem with one ECCS train, in this case, the annotated material is l deleted without explanation.
- 5. The licensee has proposed to delete the permissive in the Note to the STS SR 3.5.3.1. JFD 10 states that the STP design does not require any manual ,
alignment to change from RHR mode of operation to ECCS mode of I operation. It is not clear what is meant by manual alignment at STP, but i considering it is unlikely that there is LOCA signal when the plant is shutdown, alignment to the ECCS mode must at least require pushing a button, and probably much more. As a minimum, this STS deletion and the
- associated JFD need to be expanded. It is not clear that the licenses understands the difference between remote manual operation and the manual capab3ity addressed the STS Note.
- 6. In SR 3.5.3.1, the STS SRs 3.5.2.4 and 3.5.2.8 are deleted from the list of applicable SRs. JFD 1 does not provide a justification for this deletion. l
- 7. STP added a new change to revise the pressure requirement above which power from the accumulator isolation valves must be removed, based on operational flexibility and alternate means of protection. The CTS requirement is 1000 psig. The proposed ITS requirement is 2000 psig. The change was not made consistently, for example, the change was made in the applicable SR (SR 3.5.1), but a Bases Background insert states, "Above
.- . .- . - . - . _ . . - - . . . . . . . - - . . = - . - . . . . . . . - .- - _ - . -
6 1000 psig in the pressurizer, the accumulator's discharge valve is open with electricalpower removed from the MOV. . . ". In addition, NUREG LCO 3.5.1 was not changed to reflect the new value of 2000 psig. -
- 8. The way in which the licensee has chosen to delineate the Justification for Deviations adds to the confusion of the package. Because the JFDs have been divided up into JFDs for the TS and JFDs for the Bases Section, it is hard to tell which JFD is being discussed. The problem is that the JFDs for the Bases and the JFDs for the TS each are numbered 1 through n. The
! JFDs should be numbered sequentially (i.e., the JFDs for the Bases should l start at JFD 11).
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