|
|---|
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
{{#Wiki_filter:. _ _ . _ _ _ . _ _ _ _ _ _ . _ _ _ _ . _ _ _ - . . . _ _ _ . . _ _ _ _ . _ _
l . p ur 6b 498
, 't ' UNITED STATES ;
L' '
e fi NUCLEAR REEULATORY COMMISSION WASHINGTON. D.C. 30806 0001
%*****/ May 14, 1997 LICENSEE: HOUSTON LIGHTING AND POWER COMPANY (HL&P)
FACILITY: South Texas Project, Units 1 and 2 (STP)
SUBJECT:
SUMMARY
OF APRIL 24, 1997, MEETING ON INCOMPLETE CONTROL R00 INSERTION (IRI) AT STP On April 24, 1997, HL&P met with the Nuclear Regulatory Commission (NRC) to discuss HL&P's plans regarding IRI at STP. Meeting attendees are listed in Attachment 1. Attachment 2 is a handout provided by HL&P. I During a January 25, 1997, rod drop test on Unit 1, which took place during the middle of Cycle 7, 2 control rods stuck at 6 steps. During a subsequent test on April 5, 1997, 4 control rods stuck at 6 steps (the same 2 from th6 January test plus 2 others). HL&P attributes the root cause to fuel assembly thimble tube distortion caused by excessive axial compressive loads, with irradiation metallurgical effects as a contributing factor.
HL&P has been addressing this problem by limiting fuel assembly burnups in rodded fuel assemblies. In addition, HL&P is planning to augment their approach with Phase I and Phase II fuel design changes. Phase I plans include using Zirlo fuel cladding, thimble tubes and mid-grids to reduce fuel assembly growth and corrosion, and adding a debris grid at the fuel assembly bottom to reduce assembly skeleton axial loading. Phase I is scheduled for Unit 1 Cycle 8 (September 1997). Phase II plans include increasing the thimble tube outside diameter and increasing the tube wall thickness for improved buckling resistance, and using a single (versus a double) dashpot to lower the top of the dashpot and remove a transition. Phase I is scheduled for Unit 2 Cycle 7 (October 1998). HL&P noted that they have not approved Phase II at this time.
Other design changes under consideration include decreasing the top nozzle spring force and reducing the-control rod rodlet outside diameter.
Regarding the current operating cycle for Unit 1, HL&P presented a graph that compares the shutdown margin limit of 56 IRIS at 6 steps with a predicted equivalent number of IRIS at 6 steps during Cycle 7, based on Cycle 6 data and ;
Cycle 7 data observed to date. Based on this graph, which HL&P believes shows substantial safety limit margin, HL&P plans to perform only one additional rod drop test (on June 28,1997) between now and the end of Cycle 7 (September 13, 1997). From this graph, HL&P is predicting the equivalent of 8 IRIS at 6 steps during the June test and 14 IRIS at 6 steps during the end of Cycle 7 ;
test. HL&P indicated that if the June test results are substantially l different from what they are expecting, they will reevaluate their plan. 1
\ l Regarding the current operating cycle for Unit 2, HL&P indicated that Unit 2 has not experienced IRI when standard fuel is limited to burnups of 30 GWD/MTV h[I and Vantage SH fuel is limited to burnups of 25 GWD/MTU. The current Unit 2 cycle burnups are projected to slightly exceed these values, and therefore,
- HL&P may decide to do a rod drop test just prior to Unit 2 end of cycle. I l \
l 160044 NRC FILE CENTER C0Ff 9705160135 970514 PDR ADOCK 05000498 )
l P PM
The NRC expressed concerns that under HL&P's proposed plan for Unit 1, the proposed burnup deltas since the last rod drop test (i.e., 3009 MWD /MTU for the June test and 2769 MWD /MTV for the end of Cycle 7 test) will exceed the 2500 MWD /MTV minimum burnup increment between successive tests that was proposed by the Westinghouse Owners Group in response to Bulletin 96-01,
" Control Rod Insertion Problems." The NRC also expressed concern with the possibility of control rods sticking in the upper part of the core, since rod drop traces are showing evidence of slowing down in this area. The NRC indicated that they will consider HL&P's plan and provide feedback.
ORIGINAL SIGNED BY:
Thomas W. Alexion, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Hos. 50-498 and 50-499 Attachments: 1. List of Meeting Attendees
- 2. Licensee Handout cc w/atts: See next page DISTRIBUTION:
HARD COPY E-MAIL Docket File SCollins/FMiraglia (SJC1/FJM) RZimmerman (RPZ)
PUBLIC JRoe (JWR) EAdensam (EGAl)
PD4-1 r/f TAlexion (TWA) CHawes (CMH2)
OGC WBeckner (WDB) PGwynn (TPG)
ACRS GHolahan (GMH) JLyons (JEL)
MChatterton (MSC1) HConrad (HFC)
FGrubelich (FXG)
Document Name: ST042497.MTS [9I 0FC. PM/PD W k LA/PD4-1 ( A)BC/S'PSB NAME TAlexih(CHawesOdN JLyoY DATE h/97 $/5/97 I /Ih97 COPY hES)10 YES/NO YES/N0 U OFFICIAL RECORD COPY
_- .= . . .- - - . - _ _ . - . . . _ .
1 The NRC expressed concerns that under HL&P's proposed plan for Unit 1, the proposed burnup deltas since the last rod drop test (i.e., 3009 MWD /MTV for the June test and 2769 MWD /MTU for the end of Cycle 7 test) will exceed the 2500 MWD /MTU minimum burnup increment between succersive tests that was proposed by the Westinghouse Owners Group in response to Bulletin 96-01,
" Control Rod Insertion Problems." The NRC also expressed concern with the possibility of control rods sticking in the upper part of the core, since rod drop traces are showing evidence of slowing down in this area. The NP.C
, indicated that they will consider HL&P's plan and provide feedback. i r
J .
Thomas W. Alexion, Proje t Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499 _
1 Attachments: 1. List of Meeting Attendees
- 2. Licensee Handout cc w/atts: See next page l
\
l
Houston Lighting & Power Company South Texas, Units 1 & 2 l
CC*
l l Mr. David P. Loveless Jack R. Newman, Esq.
Senior Resident Inspector Morgan, Lewis & Bockius l U.S. Nuclear Regulatory Commission 1800 M Street, N.W.
l P. O. Box 910 Washington, DC 20036-5869 l 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 i 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 i Dr. Bertram Wolfe I 15453 Via Vaquero Texas Public Utility Commission Monte Sereno, CA 95030 ATTN: Mr. Glenn W. Dishong 7800 Shoal Creek Blvd. l Judge, Matagorda County Suite 400N !
Matagorda County Courthouse Austin, TX 78757-1024 i 1700 Seventh Street Bay City, TX 77414 Mr.' William T. Cottle Executive VP & General Manager Nuclear
- Houston Lighting & Power Company l South Texas Project Electric
! Generating Station l P. O. Box 289 l Wadsworth, TX 77483 i
MEETING WITH HL&P ON INCOMPLETE CONTROL R0D INSERTION April 24, 1997 Nama Draanization T. Cloninger HL&P S. Head .HL&P D. Leazar HL&P R. Dunn HL&P G. Holahan NRC J. Lyons NRC M. Chatterton NRC H.-Conrad NRC F. Grubelich NRC T. Alexion NRC i
D.
i l
4 i
ATTACHMENT 1
i SOUTH TEXAS PROJECT i MEETING WITH THE NUCLEAR REGULATORY COMMISSION TO DISCUSS INCOMPLETE ROD INSERTION STATUS APRIL 24,1997 i
i VISION: SOUTH TEXAS PROJECT - - A WORLD CLASS POWER PRODUCER !
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SOUTH TEXAS PROJECT l.
Puroose
. Communicate STP-specific information regarding:
-Incomplete rod insertion (IRI)
- Planned STP fuel assembly design changes to prevent iRI
- Proposed Unit 1 rod drop testing schedule to monitor IRI
. STP Team !
Ted H. Cloninger - Vice President, Nuclear Engineering !
Dovld A. Leazar - Manager, Nuclear Fuel & Analysis Roland F. Dunn - Supervisor, Reactor Engineering Scott M. Head - Supervisor, Nuclear Ucensing l
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STP Unit 1 Cycle 7 incomotete Rod Insertion (IRD Backaround l
l Steps above rod bottom /
(All V5H) Fuel burnup(gwd/mtu) i l H05 C-9 0 / 17 ;
l H47 K-8 0/18 H10 l C-7 0/17 0 / 26 H46 l F-8 0 /18 l 0 / 27 l
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SOUTH TEXAS PROJECT l 1 .
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STP Fuel Assembly Deslan Chanaes to Prevent IRI i<
. The root cause of incomplete rod insertion has been identified as fuel assembly thimble tube distortion caused by excessive axial compressive loads, and a contributing factor includes irradiation metallurgical effects e Therefore, in addition to fuel assembly burnup management under control rods, the following Phase I and ll fuel !
design changes are planned to address the above cause, and provide our long term correction to the IRI l condition !
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STP Fuel Assembly Desian Chanaes to Prevent IRI i
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l Phase I-Implementation planned for Unit 1 Cycle 8 (September 1997) t I
e ZlRLO fuel cladding, thimble tubes, and mid-grids !
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- reduced creep rate ;
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- reduced oxial assembly growth ;
- reduced corrosion
- requires Tech Spec change
. Debris grid added at bottom (Performance +) >
- reduced assembly skeleton oxial loading from fuel rods ;
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! STP Fuel Assembly Desian Chances to Prevent IRI Phase II- Implementation planned for Unit 2 Cycle 7 (October 1998) l l
The following proposed changes are being evaluated by the STP-W design team:
l e Tnimble tube OD from top to bottom is some diameter i
- OD above dashpot is .008" larger than V5H XL fuel, some as standard XL
- OD in dashpot is .052" larger than V5H or standard XL fuel
-improved buckling resistance in dashpot area compared to V5H and standard XL fuel i
- improved buckling resistance above dashpot compared to V5H XL fuel !
e Thicker thimble tube wall !
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- thimble tube wall thickness above dashpot increases by .004~
- thimble tube wall thickness in dashpot increases by .026" ;
-improved buckling resistance compared to V5H and standard XL fuel e Dashpot is single vs. double
- removes a transition and lowers the top of the dashpot by about 4~ (equivalent to six steps) i Page 6 of II '
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SOUTH TEXAS PROJECT .
STP Fuel Assembly Desion Chonoes to Prevent IRI Additionallong Term Actions STP has requested the following to be evoluoted by the W design team:
. Decrease top nozzle spring force
- Condition 11, loss of load /RCP overspeed event with fuel assembly liftoff may be limiting e Reduce RCCA rodlet OD
- STP is planning to replace RCCAs with chrome-plated cladding at 10 year ISI outage Page 7 of II
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SOUTH TEXAS PROJECT STP Unit 1 Cycle 7 Shutdown Morain Cooability All cases assume the highest worth stuck rod is fully withdrawn BOC and EOC shutdown margin and trip reactivity met for the following cases:
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# Stuck rods
- Position" Case 1 12 18 Case 2 20 12 Case 3 56 6
*no core location or fuel burnup restrictions, e.g., any 12 or any 20 rods
** based on digital rod position indication (DRPI)- includes 4 step uncertainty '
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l Planned Test Schedule o Rod drop test on 6/28/97, burnup delta of 3009 mwd /mtu since last test e Rod drop test at End-of-Cycle on 9/13/97, burnup delta of 2769 mwd /mtu since 6/28 These dates are acceptable for the following reasons:
e IRI condition progresses slowly with core burnup e Significant safety limit margin exists e Unit 1 operation remains bounded by previous fuel cycle IRI experience e STP will continue to use Restart Evaluation Criteria for the next Unit 1 rod drop test
- monitors rod drop time, changes in rod drop time, and shutdown margin
- evaluates reduction of burnup interval prior to next rod drop test, if required Page 10 or 11
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t Meetina Summarv i e Described STP's long term corrective actions to prevent incomplete rod insertions j
= Presented STP safety limit margin for incomplete rod insertions
. Described planned Unit 1 Cycle 7 rod drop test schedule i
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