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Category:ARCHIVE RECORDS
MONTHYEARIA-97-252, Packages Consisting of 19 Pages of Accession Numbers for South Texas Project1997-10-0707 October 1997 Packages Consisting of 19 Pages of Accession Numbers for South Texas Project ML20217F7671997-10-0707 October 1997 Packages Consisting of 19 Pages of Accession Numbers for South Texas Project ML20115E7131996-02-13013 February 1996 Rev 2 to Sub-Calculation MC-6441-101, Pressure Locking/ Thermal Binding Evaluation ML20198J5581995-06-0606 June 1995 Rev 0 to MC-6458, ECCS Isolation Valve Leak Analysis. W/ One Oversize Drawing ML20198J5521995-06-0606 June 1995 Rev 1 to MC-6313, ECCS Valve Leakage to RWST Analysis ML20059H3951993-11-0101 November 1993 Cold Ecw Chiller Analysis ML20058J5591993-10-14014 October 1993 Essential Chilled Water Load ML20059H3751993-10-0505 October 1993 Essential Chilled Water Load ML20059H3611993-09-28028 September 1993 Essential Chiller Performance Test ML20046A1421993-03-19019 March 1993 Package Consisting of 1993 Emergency Response Graded Exercise Objectives ML20092C7681992-01-0909 January 1992 Package Consisting of Objectives for 1992 Graded Emergency Preparedness Exercise on 920429 ML20197B1461991-11-20020 November 1991 Rev 1 to Calculation MC-6305, RHR Relief Valves as Coms/Ltop ML20079N3791991-11-11011 November 1991 Response to NUMARC Survey in Support of NRC License Renewal Rulemaking ML20055J4631990-05-0909 May 1990 Package Consisting of Director Highlights of Unusual Event Due to Required Shutdown by Tech Spec 3.4.6.1 for Pressure Boundary Leakage.Unit Entered Cold Shutdown to Make Repairs. Estimated Restart Date Is 900522 ML20055H8791990-05-0808 May 1990 Package of Info Re 900508 Shutdown Due to Pressure Boundary Leakage ML20247R3711989-09-18018 September 1989 Package of Three FOIA Requests ML20246P8441989-05-0505 May 1989 Errata to Annotated Rev to FSAR & Tech Specs Bases ST-HL-AE-3040, Proposed Revs to FSAR1989-04-18018 April 1989 Proposed Revs to FSAR ML20148C5971988-03-18018 March 1988 Slide Prsentation Entitled, Commission Briefing on Full Power Licensing of South Texas Project,Unit 1 ML20237D7901987-12-10010 December 1987 Package of Unrelated Documentation Re Listed Plants Concerning NRC Emergency Response Data Sys HL-3708, Record of 870819 Telcon W/A Singh,P Kadambi of Nrc,A Guidry of Bechtel Re Deviations Not Documented in Plant Ser.Nrc Concurred That Deviations Described in Attachment 2 to ST-HL-AE-2252 Acceptable1987-08-19019 August 1987 Record of 870819 Telcon W/A Singh,P Kadambi of Nrc,A Guidry of Bechtel Re Deviations Not Documented in Plant Ser.Nrc Concurred That Deviations Described in Attachment 2 to ST-HL-AE-2252 Acceptable HL-7514, Record of Telcon W/Ca Ayala,Ma Friedlander,Rl Perch,R Emch & C Moon on 870708 to Clarify Intent & Proper Interpretation of Encl marked-up Final Draft Tech Spec Table 3.3-31987-07-0808 July 1987 Record of Telcon W/Ca Ayala,Ma Friedlander,Rl Perch,R Emch & C Moon on 870708 to Clarify Intent & Proper Interpretation of Encl marked-up Final Draft Tech Spec Table 3.3-3 ML20209F5901987-03-13013 March 1987 Region IV Daily Rept on 870311 Steam/Water Hammer Event at Facility & Photographs of Facility Piping ML20209B0091987-02-0202 February 1987 Package of Supplemental Info Re Reg Guide 1.75 Testing Configurations ML20212G6831987-01-16016 January 1987 Package of Comments on Facility long-term Cooling Analysis ML20207N3951987-01-12012 January 1987 Package of Three Pages Providing Addl Clarification of Instrument Tubing ML20214A1831986-10-15015 October 1986 Nonproprietary Version of Slide Presentation Entitled, Presentation & Handout Matl Re Leak-Before-Break Calculations for South Texas Project 12-Inch Diameter Accumulator Line ML20211F0041986-09-30030 September 1986 Marked-up Notice of Violation from Insp on 791110-800207, Draft Investigation Rept & Proposed Enforcement Actions IA-86-784, Package Consisting of Request for Addl Info Re Alternative Pipe Break Criteria Attached to NRC to Util1986-07-10010 July 1986 Package Consisting of Request for Addl Info Re Alternative Pipe Break Criteria Attached to NRC to Util ML20214K2741986-07-10010 July 1986 Package Consisting of Request for Addl Info Re Alternative Pipe Break Criteria Attached to NRC to Util ML20207E1021986-07-0202 July 1986 Telcon W/Util,Nrc & Westinghouse to Discuss Bart Code Assessment ML20207F6921986-07-0202 July 1986 Telcon W/Sl Wu & P Kadambi of NRC to Discuss Util Providing Supplemental Info on Momentary Fuel Assembly Liftoff,Per SER Confirmatory Item 9 HL-3578, Record of 860630 Telcon W/R Goel & P Kadambi of NRC Re NRC Review of Fire Hazards/Safe Shutdown.Summary of Changes Incorporated Into Amend 4 to Fire Hazards Analysis Rept Encl1986-06-30030 June 1986 Record of 860630 Telcon W/R Goel & P Kadambi of NRC Re NRC Review of Fire Hazards/Safe Shutdown.Summary of Changes Incorporated Into Amend 4 to Fire Hazards Analysis Rept Encl HL-3576, Record of Telcon W/Mr Wisenburg,Pg Trudel,T Roberson,R Goel & P Kadambi Re NRC Review of Fire Hazards Analysis Rept & Safe Shutdown1986-06-25025 June 1986 Record of Telcon W/Mr Wisenburg,Pg Trudel,T Roberson,R Goel & P Kadambi Re NRC Review of Fire Hazards Analysis Rept & Safe Shutdown ML20199G0611986-06-18018 June 1986 Record of 860618 Telcon W/Nrc,Util,Bechtel & Westinghouse Re Deletion of Sump Additive Tank from Facility Design ML20204A0251986-04-22022 April 1986 Record of 860422 Telcon W/J Brammer,S Hou,S Long, T Robertson,M Powell,W Watson & P Kadambi Re Pipe Break Screening Criteria.Jet Load Calculations Will Not Be Performed w/NUREG/CR-2913 Methodology ML20207P2701986-01-14014 January 1986 Supplemental Info Received on Safe Shutdown Issue ML20010D9081981-08-26026 August 1981 Slide Presentation Re Soil Structure Interaction ML19350E1901981-05-26026 May 1981 Slide Presentation from 810526 Meeting Re Hafnium Control Rods 1997-10-07
[Table view] Category:PACKAGE OF NONCODED MATERIAL
MONTHYEARML20217F7671997-10-0707 October 1997 Packages Consisting of 19 Pages of Accession Numbers for South Texas Project IA-97-252, Packages Consisting of 19 Pages of Accession Numbers for South Texas Project1997-10-0707 October 1997 Packages Consisting of 19 Pages of Accession Numbers for South Texas Project ML20046A1421993-03-19019 March 1993 Package Consisting of 1993 Emergency Response Graded Exercise Objectives ML20092C7681992-01-0909 January 1992 Package Consisting of Objectives for 1992 Graded Emergency Preparedness Exercise on 920429 ML20079N3791991-11-11011 November 1991 Response to NUMARC Survey in Support of NRC License Renewal Rulemaking ML20055J4631990-05-0909 May 1990 Package Consisting of Director Highlights of Unusual Event Due to Required Shutdown by Tech Spec 3.4.6.1 for Pressure Boundary Leakage.Unit Entered Cold Shutdown to Make Repairs. Estimated Restart Date Is 900522 ML20055H8791990-05-0808 May 1990 Package of Info Re 900508 Shutdown Due to Pressure Boundary Leakage ML20247R3711989-09-18018 September 1989 Package of Three FOIA Requests ML20246P8441989-05-0505 May 1989 Errata to Annotated Rev to FSAR & Tech Specs Bases ST-HL-AE-3040, Proposed Revs to FSAR1989-04-18018 April 1989 Proposed Revs to FSAR ML20237D7901987-12-10010 December 1987 Package of Unrelated Documentation Re Listed Plants Concerning NRC Emergency Response Data Sys ML20209F5901987-03-13013 March 1987 Region IV Daily Rept on 870311 Steam/Water Hammer Event at Facility & Photographs of Facility Piping ML20209B0091987-02-0202 February 1987 Package of Supplemental Info Re Reg Guide 1.75 Testing Configurations ML20212G6831987-01-16016 January 1987 Package of Comments on Facility long-term Cooling Analysis ML20207N3951987-01-12012 January 1987 Package of Three Pages Providing Addl Clarification of Instrument Tubing ML20211F0041986-09-30030 September 1986 Marked-up Notice of Violation from Insp on 791110-800207, Draft Investigation Rept & Proposed Enforcement Actions ML20214K2741986-07-10010 July 1986 Package Consisting of Request for Addl Info Re Alternative Pipe Break Criteria Attached to NRC to Util IA-86-784, Package Consisting of Request for Addl Info Re Alternative Pipe Break Criteria Attached to NRC to Util1986-07-10010 July 1986 Package Consisting of Request for Addl Info Re Alternative Pipe Break Criteria Attached to NRC to Util ML20207P2701986-01-14014 January 1986 Supplemental Info Received on Safe Shutdown Issue 1997-10-07
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INITIALS:
PD' d DIRECTOR HIGHLIGHTS PROJECT DIRECTORATE'- IV-l May 9, 1990 i 1
- South Texas Project. Unit 2 (STP-2)
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STP-2 declared an Unusual Event due to a required shutdown by. Technical Specifi- ,
cation 3.4.6.1 for Pressure Boundary Leakage (PBL). It has been determined <
that there is about a 10 al/ min. PBL on the 20 steam generator primary side ,
drain (channel head drain valve RC-0097). The leak is at a weld connecting a' ,
3/8" tube to the drain valve. The first indication of this. leak was a slight increase in contcinment gaseous activity over a week ago. A robot was sent into containment to ottemp_t to localize the leak. When it was determined that-the leak might be from a pressure boundary, a power. reduction was connenced.
At 0030 CST May 8, 1990, personnel confirmed that-it was PBL and the Unusual Event was declared. The unit has entered cold shutdown to make repairs.
Estimated restart date is May 22, 1990.
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CONTACT:
D. Pickett, NRR/PD-IV' 492-1344
/ I 90080go296900731 iV,'
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,, _ MMRAT_ IONS CfmITER,_
DIIEV4.t:ATED INFORIAAHUN PRO I' deb hhN FACILITY RES PUWIT NAIE PHONE W DOWN RESTART REASON OR COISENT *a_
T AltKABISAS 1 2271 000 RATED POE R 4 AltKAsISAS 2 2271 100 2272 000 05/09 05/10 IIODE 3 - HDT *#
4 COIWWICHE PEAlt 1 STAIIDSV RM TRIP DUE 10 LOSS OF FEED PUIIP COIITROL. SEE EVENT 19424.
ItICItEASIDIG POWER.
- 4 COOPER 2273 090 4 FORT CALHOUll 1 2274 000 02/17 05/21 nIODE 5 - COLD
'SHUTDoull REFUEttt8G OUTAGE 4 RIVER DEte 1 2276 100 4 l 4 SOUTH TEMAS 1 2277 000 03/29 05/28 IIODE 5 - COLD SeeUTDouN ..
4 SOUTH TEXAS 2 2277 000 .05/07 05/22 ts0DE 5 - COLD SHSTDOWIB PUTTIIIS '
- FREE 2E SEAL ABOUIS *
' ' AREA 0F PIIESSIIRE
' BOUISARY LEAIWiE.
4 WATERFa m 3 2278 '100 4 150Lf CIIEEE 1 2279 000 03/09 05/12 IIODE 3 - HDT STAIIDSV ROD DROP l .
TESTIBIE. _
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.PD 1 DIRECTOR HIGHLIGHTS ,
PROJECT DIRECTORATE - IV May 16, 1990 South Texas Project. Unit 2 The Director Highlight of May 9,1990 described a primary system leak on a 3/8"-
steam generator drain line. The leak was initially sensed by a containment radiation alarm on April 22 with Unit 2 operating at 1001 power. A robot sent behind tie biological shield wall. identified the steam leak and later, rith the power reduced to 141, personnel pinpointed the leak as being a cracked weld on the upstream side of the valve.
Root cause ' analyses by Bech'el concluded the broken weld to be vibration induced. Unit 2 has subsequently been reduced to Mode 5 for repairs.
Examinations by the licensee identified a similar crack on a second steam. >
generator drain line at Unit 2 and cracks in two of the four steam generator drain lines at Unit 1.
As a temporary fix, the licensee is installing l freeze- seals, removing the drain valves on all-steam generators at both units, capping the drain lines, and seal weldir g the caps. Permanent modifications are being investigated. Both units are currently in Mode 5 with Unit 1 continuing a refueling outage and Units 2 preparing to return to power this week.
CONTACT:
D. Pickett, NRR/PD-IV 492-1344
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