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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17309A9961999-06-30030 June 1999 Rev 35 to HP-90, Emergency Equipment. ML17309A9941999-06-17017 June 1999 Rev 1 to COP-06.06, Guidelines for Collecting Post Accident Samples. ML17241A3541999-06-0101 June 1999 Proposed Tech Specs Section 3.5.2,allowing Up to 7 Days to Restore Inoperable LPSI Train to Operable Status ML17309A9951999-05-27027 May 1999 Rev 0 to COP-06.11, Establishing Remote Lab for Analyses of Accident Samples. ML17241A3451999-05-24024 May 1999 Proposed Tech Specs 3/4.5.1 Re Safety Injection Tanks ML17229B0711999-03-19019 March 1999 Proposed Tech Specs Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity, Per Soluble Boron Credit ML17229B0441999-03-0202 March 1999 Cycle 11 Reactor Startup Physics Testing Rept. with 990304 Ltr ML17229B0201999-02-23023 February 1999 Proposed Tech Specs 3/4.1.2.9 Re Reactivity Control sys- Boron Dilution ML17229B0361998-12-22022 December 1998 Rev 20 to Procedure C-200, Odcm. ML17229A9551998-12-16016 December 1998 Proposed Tech Specs Pages Revising Administrative Controls & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position ML17229A9161998-11-25025 November 1998 Proposed Tech Specs Pages,Replacing Insert-A,attachment to 971231 Submittal & Revises LCO 3.4.9.11 & Associated Bases ML17229A9251998-11-22022 November 1998 Proposed Tech Specs Revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1 ML17229A9131998-11-19019 November 1998 Proposed Tech Specs,Revising Administrative Contols TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position ML20155C3061998-10-29029 October 1998 Proposed Tech Specs Pages Revising Terminology Used in Notation of TS Tables 2.2-1 & 3.3-1 Re Implementation & Automatic Removal of Certain Reactor Protection Sys Trip Bypasses ML20153G0781998-08-26026 August 1998 Rev 19 to Plstqp, Guard Training & Qualification Plan ML17229A8441998-08-24024 August 1998 Proposed Tech Specs Removing Obsolete License Conditions & Incorporating Revs Which Clarify Component Operations That Must Be Verified in Response to Containment Sump Recirculation Actuation Signal ML17229A7731998-06-15015 June 1998 Proposed Tech Specs Pages 6-20,6-20a & 6-20c,correcting Info Supplied by Fuel Vendor Relative to Titles of Approved TRs That Are Referenced in Proposed TS 6.9.1.11.b ML17229A7601998-06-0303 June 1998 Proposed Marked Up TS Pages Modifying Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1 to Provide for Use of Lab Gas Partitioner to Periodically Analyze Concentration of Oxygen in Svc Waste Gas Decay Tank ML17229A7441998-05-27027 May 1998 Proposed Tech Specs Providing for More Efficient Use of on- Site Mgt Personnel in Review & Approval Process for Plant Procedures ML17229A7481998-05-27027 May 1998 Proposed Tech Specs Section 3.5.1,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions ML17229A7511998-05-27027 May 1998 Proposed Tech Specs Section 6.2.2.f,revised to Allow for Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews ML17229A6751998-03-27027 March 1998 Cycle 15 Reactor Startup Physics & Replacement SG Testing Rept. W/980402 Ltr ML17229A6501998-03-0303 March 1998 Proposed Tech Specs 3.4.7 Re RCS Chemistry/Design Features/ Administrative Controls ML17229A6381998-02-12012 February 1998 Rev 19 to C-200, Offsite Dose Calculation Manual. ML17229A6151998-01-12012 January 1998 Rev 0 to ISI-PSL-1, St Lucie Nuclear Plant Unit 1 ISI Plan. ML17229A6141998-01-12012 January 1998 Rev 0 to ISI-PSL-1, Third Interval ISI Program for St Lucie Nuclear Power Plant,Unit 1. ML17229A5691997-12-31031 December 1997 Proposed Tech Specs Pages Modifying TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity ML17309A9131997-12-29029 December 1997 Proposed Tech Specs Modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17229A5851997-12-12012 December 1997 Rev 0 to ADM-29.01, IST Program for Pumps & Valves. ML17229A5491997-12-0101 December 1997 Proposed Tech Specs Revising Units 1 & 2 EPP Section 4, Environ Conditions & Section 5, Administrative Procedures to Incorporate Proposed Terms & Conditions of Incidental Take Statement Included in Biological Opinion ML17309A9171997-11-26026 November 1997 Rev 0 to PSL-ENG-SENS-97-068, Spent Fuel Pool Dilution Analysis. ML17229A5931997-09-26026 September 1997 Rev 4 to Procedure QI-5-PSL-1, Preparation,Rev,Review/ Approval of Procedures. ML17229A5921997-09-18018 September 1997 Rev 0 to Procedure ADM-17.11, 10CFR500.59 Screening. ML20211Q5841997-09-10010 September 1997 Rev 18 to Training & Qualification Plan ML17229A4621997-08-22022 August 1997 Proposed Tech Specs Pages,Revising Specification 4.0.5 Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Control Section 6.8 ML17229A4341997-08-0101 August 1997 Proposed Tech Specs,Extending semi-annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996 & Associated SE ML17309A8951997-06-11011 June 1997 Rev 0 to PL-CNSI-97-004, Transportation & Emergency Response Plan for St Lucie Unit 1 SG Project. ML17229A3601997-05-29029 May 1997 Proposed Tech Specs Incorporating Administrative Changes That Improve Consistency Throughout TSs & Related Bases ML17229A2981997-03-0606 March 1997 Final Analysis of Radiological Consequences of Main Steam Line Break Outside Containment for St Lucie Unit 1 NPP Using NUREG-0800 Std Review Plan 15.1.5 App A. ML17229A1831996-12-20020 December 1996 Proposed Tech Specs Re Safety Limits & Limiting Safety Sys Settings ML17229A1611996-12-0909 December 1996 Proposed Tech Specs 1.9a Re Core Operating Limits Rept ML17229A1191996-10-31031 October 1996 Proposed Tech Specs 6.0 Re Administrative Controls ML17229A1111996-10-30030 October 1996 Proposed Tech Specs 3/4.9.9 Re Containment Isolation Sys & 3/4.9.10 Re Water level-reactor Vessel ML17229A1061996-10-28028 October 1996 Proposed Tech Specs 1.6 Re Channel Functional test,1.7 Re Containment Vessel integrity,1.8 Re Controlled leakage,1.9 Re Core alteration,3/4.6 Re Containment Systems & 3/4.6.1 Re Containment Vessel ML17229A1091996-10-28028 October 1996 Proposed Tech Specs Rev to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria ML17229A0951996-10-24024 October 1996 Rev 0 to 00000-OSW-16, In-Situ Pressure Test Results for St Lucie Unit 1 Spring 1996 Outage. ML17229A0861996-10-18018 October 1996 Startup Physics Testing Rept. W/961018 Ltr ML17229A2441996-09-23023 September 1996 Rev 18 to Offsite Dose Calculation Manual (Odcm). ML17228B5641996-07-15015 July 1996 Revised Tech Specs Re Core Alteration Definition ML17229A0961996-06-12012 June 1996 Rev 0 to TR-9419-CSE96-1101, Test Rept - SG Tube In-Situ Hydrostatic Pressure Test Tool Hydro Chamber Pressure Determination. 1999-06-30
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17309A9961999-06-30030 June 1999 Rev 35 to HP-90, Emergency Equipment. ML17309A9941999-06-17017 June 1999 Rev 1 to COP-06.06, Guidelines for Collecting Post Accident Samples. ML17309A9951999-05-27027 May 1999 Rev 0 to COP-06.11, Establishing Remote Lab for Analyses of Accident Samples. ML17229B0361998-12-22022 December 1998 Rev 20 to Procedure C-200, Odcm. ML20153G0781998-08-26026 August 1998 Rev 19 to Plstqp, Guard Training & Qualification Plan ML17229A6381998-02-12012 February 1998 Rev 19 to C-200, Offsite Dose Calculation Manual. ML17229A6151998-01-12012 January 1998 Rev 0 to ISI-PSL-1, St Lucie Nuclear Plant Unit 1 ISI Plan. ML17229A6141998-01-12012 January 1998 Rev 0 to ISI-PSL-1, Third Interval ISI Program for St Lucie Nuclear Power Plant,Unit 1. ML17229A5851997-12-12012 December 1997 Rev 0 to ADM-29.01, IST Program for Pumps & Valves. ML17229A5931997-09-26026 September 1997 Rev 4 to Procedure QI-5-PSL-1, Preparation,Rev,Review/ Approval of Procedures. ML17229A5921997-09-18018 September 1997 Rev 0 to Procedure ADM-17.11, 10CFR500.59 Screening. ML20211Q5841997-09-10010 September 1997 Rev 18 to Training & Qualification Plan ML17309A8951997-06-11011 June 1997 Rev 0 to PL-CNSI-97-004, Transportation & Emergency Response Plan for St Lucie Unit 1 SG Project. ML17229A2981997-03-0606 March 1997 Final Analysis of Radiological Consequences of Main Steam Line Break Outside Containment for St Lucie Unit 1 NPP Using NUREG-0800 Std Review Plan 15.1.5 App A. ML17229A2441996-09-23023 September 1996 Rev 18 to Offsite Dose Calculation Manual (Odcm). ML17229A0971996-06-10010 June 1996 Rev 0 to TP-9419-CSE96-2104, Steam Generator Tube In-Situ Hydrostatic Pressure Test Tool Hydro Chamber Pressure Determination. ML20137P3651996-05-20020 May 1996 Rev 5 to Procedure 1-1220055, Calibration of Area Radiation Monitoring Sys (Arms) ML17228B4921996-04-22022 April 1996 FPL St Lucie Unit 1 SG Program. ML20137P3381996-03-0404 March 1996 Rev 0 to Procedure 1-1400207, Calibr of Containment Process Monitor ML20137K6111995-12-0707 December 1995 Auxiliary Feedwater Pump 1C Disassembly Insp & Reassembly Mechanical Maint Procedure for St Lucie Plant,Unit 1 ML17228B3461995-11-16016 November 1995 Rev 0 to Plant Administrative Procedure 2-0010024, Inservice Testing Program for Pumps & Valves. ML20137P3061995-08-31031 August 1995 Rev 2 to Procedure 2-1220057, Functional Testing of RM-80 Power Supply Assemblies ML17228B0491995-02-0303 February 1995 Rev 0 to Subsequent Inservice Exam Plan for Pressurizer Instrument Nozzles. ML17228B0171995-01-0606 January 1995 Rev 5 to Second 10-Yr ISI Interval IST Program for Pumps & Valves St Lucie Nuclear Power Plant Unit 1. ML17228A8811994-09-28028 September 1994 Rev 0 to PSL-200-AOA-94-1, St Lucie Nuclear Plant,Unit 2 ISI Interval Request for Authorization of Alternative Exam. W/Attachment Re Implementation of Reg Guide 1.150 ML20137M1611994-09-15015 September 1994 Rev 2 to Procedure 1-1220053, Calibr of Control Room Outside Air Intake Monitors ML20080M4881994-06-14014 June 1994 Rev 15 to Chemistry Procedure C-200, Odcm ML20080M4791994-01-14014 January 1994 Rev 14 to Chemistry Procedure C-200, Odcm ML17228A4621994-01-14014 January 1994 Rev 4 to Second Ten-Yr ISI Interval IST Program. ML17228A2471993-07-24024 July 1993 Rev 0 of PSL-201, St Lucie Nuclear Power Plant,Unit 2 Second ISI Interval ISI Selected Component Schedule. ML17228A2461993-07-24024 July 1993 Rev 0 of PSL-200, St Lucie Nuclear Power Plant,Unit 2 Second ISI Interval Program Plan & Schedule from 930808- 200808 ML20137P3551993-03-0808 March 1993 Rev 1 to Procedure 1-1220055, Calibration of Area Radiation Monitoring Sys (Arms) ML17227A6011992-08-11011 August 1992 Rev 2 to JNS-PSL-204, First Ten-Year Inservice Inspection Interval Inservice Testing Program for Pumps & Valves, St Lucie Nuclear Power Plant,Unit 2. ML20141M4901992-07-30030 July 1992 Rev 14 to Training & Qualification Plan ML20137P3431992-04-10010 April 1992 Rev 1 to Procedure 1-1220053, Calibration of Control Room Putside Air Intake Monitors ML17223B2931991-10-10010 October 1991 Rev 3 to JNS-PSL-203, Second 10-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves,St Lucie Nuclear Power Plant,Unit 1. ML20137P2971991-07-0303 July 1991 Rev 1 to Procedure 2-1120070, Containment High Range Radiation Monitor Calibration ML20070T9761991-03-12012 March 1991 Rev 10 to Training & Qualification Plan ML17223A5771990-03-0707 March 1990 Rev 10 to Emergency Procedure 1-0030143, Total Loss of Ac Power. ML17223A4501989-12-15015 December 1989 Rev 2 to JNS-PSL-203, Second 10-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves. ML17308A1901988-08-24024 August 1988 Vols 1 & 2 to Rev 0 to JNS-PSL-100, St Lucie Plant Unit 1 Second 10-Yr Insp Plan. ML17221A7041988-04-0404 April 1988 Rev 0 to Pump & Valve Inservice Test Program. ML17342B0641987-12-30030 December 1987 Rev 1 to Independent Mgt Appraisal Program Plan for Florida Power & Light Co. ML17308A1831987-09-0202 September 1987 Rev 0 to Inservice Insp Second 10-yr Summary Program. ML17221A3781987-08-11011 August 1987 Inservice Testing Program,Section I,Valve Test Program & Section Ii,Pump Test Program. ML17221A3961987-01-28028 January 1987 Rev 1 to St Lucie Unit 1,Extraction Steam Piping Insp Program Guidelines. ML17347A2241986-12-22022 December 1986 Emergency Plan Implementing Procedures,Including Procedure 1101, Duties of Emergency Control Officer,Offsite Emergency Organization & Procedure 1102, Duties of Recovery Officer,Offsite Emergency.... W/861222 Ltr ML17216A6651986-06-17017 June 1986 Rev 4 to Maint Procedure 2-0910053, 12-Month Test of Automatic Load Sequence Relays. ML17216A6661986-03-26026 March 1986 Rev 5 to Maint Procedure 2-2200063, 2B Emergency Diesel Electrical Insp. ML17216A6671986-03-26026 March 1986 Rev 4 to Maint Procedure 2-2200062, 2A Emergency Diesel Electrical Insp. 1999-06-30
[Table view] |
Text
ENCLOSURE 1 FLORIDA POWER & LIGHT ST. LUCIE UNIT 1 STEAM GENERATOR PROGRAM PRESENTED TO THE NUCLEAR REGULATORY COMMISSION APRIL 22, 1996
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FPL PRESENTATION TO NRC - APRIL 22, 1996 ST. LUCIE UNIT 1 STEAM GENERATOR PROGRAM OPENING 8c INTRODUCTIONS I. PURPOSE OF MEETING II. STATUS OF S/G CONDITION II I. ECT TECHNIQUE QUALIFICATION IV. 5/96 REFUELING OUTAGE PLANS V.
SUMMARY
FPL PRESENTATION TO NRC - APRIL 22, 1996 ST. LUCIE UNIT 1 STEAM GENERATOR PROGRAM II; STATUS OF S/6 CONDITION S/G DESIGN FEATURES DRY STEAM~ DOERS HOT SIDE QEPARATO~ COLD SIDE RECIRCULATING RECIRCULATING FLUID FLOW FLUID FLOW DOWNCOMER FEED WATER Rl ER INLEI'100%)
UNIFORM DISTRIBUTION DOWNCOMER DOWNCOMER FLOW FLOW
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FPL PRESENTATlON TO NRC - APRlL 22, 1996 ST. LUCIE UNlT 1 STEAM GENERATOR PROGRAM II. STATUS OF S/6 CONDITION S/G DESIGN FEATURES
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FPL PRESENTATION TO NRC - APRIL 22, 1996 ST. LUCIE UNIT 1 STEAM GENERATOR PROGRAM II. STATUS OF S/G CONDITION INSPECTION & TUBE PLUGGING HISTORY
,::>,EXANfR ~B0BBIN~ ~j,;".,TUBES=.y",, .~ +RESuLTPSi"-COMMENT~
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I',DATE= ; PL'UGGED.".
MFG 100% 23 Preservice Shop Plugs 1977 10%
1978 10%
1979 10% 21 Drilled Support Rim Cut 1981 A- 28% 103 U-Bend Cracking Rows 8-11 B -38%
1984 100% 507 Preventive Plugging Rows 8-11 Random Indic. - Sludge Pile 8 Supports 1985 100% (8X1) 66 Random Indic. - Sludge Pile & Supports Pulled 3 Tubes 1986 (Midcycle) 23 Post Outage ECT Review 8 Pltjgging 1987 100% <50 Bobbin Indications 76 Random Indic. - Sludge Pile & Supports 1988 100% <50 Bobbin Indications 239 Random Indic. - Sludge Pile 8 Supports 1990 100% 97 Bobbin Indications 180 Random Indic. - Sludge Pile & Supports 1991 100% 100% HL Expan.Trans. 449 3% CL Expan. Trans. 98 Circ. Indications - HL Expan. Trans.
650 Bobbin Indications 1993 100% 100% HL Expan.Trans. 130 Random Indic. - Sludge Pile & Supports 3% CL Expan.Trans.
250 Bobbin Indications 12 Circ. Indications - HL Expan. Trans.
1994 100% 100% HL Expan. Trans. 94 Random Indic. - Sludge Pile & Supports 3% CL Expan. Trans. 14 Circ. Indications - HL Expan. Trans.
100 Bobbin Indications TOTAL TUBES - Each = 8519 PLUG MARGIN - 2129 Tubes (25%) each S/G TOTAL PLUGS - S/G A = 1138 (13.3%) +/- 7% Asymmetry S/G B = 774 ( 9.1%)
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FPL PRESENTATION TO NRC - APRIL 22, 1996 ST. LUCIE UNIT 1 STEAM GENERATOR PROGRAM II. STATUS OF S/6 CONDITION 1985 TUBE PULL RESULTS Correlation of ECT and Metallography Results ST. LUCIE UNIT 1 -'S/G "A" PULLED TUBE CORRELATION BOBBIN COIL EDDY CURRENT vs METALLOGRAPHY LINE ROW ELEV. ECT % MET. ECT % DEFECT 1985 DEPTH 1996 APPEARANCE 120 12 Sludge Pile 41'1 30% 26% IG/TG SCC parallel axial cracks.
0.4" longest over 1" axial length across 360'f tube circumference.
Most over 90'.
120 12 ¹3 EC-Hot 82% 72% 70% IGNTG SCC parallel axial cracks in land area 0.6'ongest over across 0.1'f tube 2'xial circumference.
79 91 Sludge Pile UDS 16% NDD IGA Patch .5'xial x.5'irc.
79 91 Sludge Pile 57% 42% 44 IGA Patch .8'xial x.5'irc.
59 95 ¹2 EC-Hot 29% 13% 3% IGA Patch .4'xial x.3'irc.
59 95 ¹1 EC-Hot DSS 52% 46% IGA Patch .7'xial x .3'irc.
EC Eggcrate UDS Undefined signal DSS Distorted Signal NDD No Detectable Defect nrc4 ~6 *c i
FPL PRESENTATION TO NRC - APRlL 22, 1996 ST. LUCIE UNIT 1 STEAM GENERATOR PROGRAM II. STATUS OF S/6 CONDITION LOCATION OF DEGRADATION REPORTABLE INDICATIONS IN SERVICE S/G REGION S/G A S/G S'.
Vl V2 V3 U-BEND 190 166 EIW2 18H 18C DRILLED SUPPORTS
¹9 &10 294 101 89C 88C 87H 87C 86H EGGCRATE SUPPORTS
¹1TOS 1948 1242 33H 83C 82H 82C SLUDGE O'C PILE 1131 642
~ SC TOTALS INLET OLITLET 3563 2151 nrc4 96.wpa
FPL PRESENTATION TO NRC - APRIL 22, 1996 ST. LUCIE UNIT 1 STEAM GENERATOR PROGRAM II. STATUS OF S/6 CONDITION LEAKAGE HISTORY April 1981 Leak Rate - 0.01- 0.05 Gallons/Day (gpd)
Leak Location - Steam Blanketed U-Bend Cause IGA/IGSCC January 1990 Leak Rate - 2 - 5 Gallons/Day (gpd)
Leak Location - - 13" Above Tubesheet Cause Slag Nugget Between Periphery.
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. FPL PRESENTATION TO NRC - APRIL 22, 1996 ST. LUCIE UNIT 1 STEAM GENERATOR PROGRAM II. STATUS OF S/G CONDITION LEAKAGE HISTORY TECHNICAL SPECIFICATION REQUIREMENTS 3 Samples / 7 Days - 5 ml Gross Activity Monthly Sample - 4000 ml Dose Equivalent Iodine ADDITIONALMONITORING On-Line Blowdown Monitors Air Ejector Monitors Grab Samples 400 Liter Sample on Resin Monthly if < LLD Weekly if > LLD Secondary Side Tritium Current RCS Leakage 3-5 Gallons/Day (gpd)
EPRI Leak Rate Guidelines Night Order in Control Room Incorporate into Operations Procedures Prior to Startup from 4/96 Outage nrc4 96.woa
FPL PRESENTATION TO NRC - APRIL 22, 1996 ST. LUCIE UNIT 1 STEAM GENERATOR PROGRAM III. ECT TECHNIQUE QUALIFICATION- IGA/SCC FPL BOBBIN COIL TECHNIQUE EXCEEDS EPRI S/G EXAM. GUIDELINE, "APPENDIX H" REQUIREMENTS
~Ri t tt di H R FPL Techni ue DETECTION 80% POD 90% CL 80% POD 90% CL For Flaws > 60% 'or Flaws > 35%
DEPTH SIZING RMSE < 25% RMSE = 17.9%
- EPRI PEER REVIEW APPROVED MARCH 27, 1996 ***
QUALIFICATIONSAMPLE SET FLAWS AT EGGCRATE SUPPORTS FLAWS AT SLUDGE PILE REGION ALL AVAILABLECE S/G PULLED TUBE DATA 11 FLAWS FROM CE S/Gs (6 from PSL-1) 7 IGA/SCC LAB SAMPLES FROM EPRI nrc4 96 *cc
FPL PRESENTATION TO NRC - APRIL 22, 1996 ST. LUCIE UNIT 1 STEAM GENERATOR PROGRAM 1ll. ECT TECHNIQUE QUAL1FlCATION - IGA/SCC FPL BOBBIN COll QUALIFICATIONSAMPLE SET ECT vs METALLOGRAPHY RESULTS DETECTION 80 to POD 90% CL For Flaws >35%
DEPTH SIZING RMSE = 17.9%
BOBBIN COIL APL H ODSCC
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i
"", Mean = -5.551 Std Oev 17.54,'""'",
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g'"'"'-"'""""""-'"
TW DETECTED
POD e 9014 CL 70 <<M% 3OF5 <<.00 IS OF 13 .EO H
00 3
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4.
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IYI 10 0 10 20 30 40 70 80 MAX MET DEPTH nrc4 96 *m
FPL PRESENTATION TO NRC - APRIL 22, 'f996 ST. LUCIE UNIT 1 STEAM GENERATOR PROGRAM III. ECT TECHNIQUE QUALIFICATION DRILLED SUPPORT ECT-SIGNAL LARGER 5 INTERFERES MORE WITH FLAW DETECTION Bc SIZING 0.41 vlS N>>l 1 mI IS I 0 0 0 0
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~ .SS Mll~ SS 4'SS
&>>II DRILLED SUPPORT DESIGN ECT SIGNAL ll >>N IIII 0,41 vte lorn 1 rol III I':-
rP QQ V%I IN I.SS mll~ II tel Ill EGGCRATE SUPPORT DESIGN ECT SIGNAL
C FPL PRESENTATION TO NRC - APRIL 22, 1996 ST. LUCIE UNIT 1 STEAM GENERATOR PROGRAM III. ECT TECHNIQUE QUALIFICATION FLAW AT DRILLED SUPPORT PLATE (FLAW IDENTIFIED BY VECTOR POINTS) ls +00 Ol'rr O.ovo 5 ~ alo Sl loo 1.5vo Olfr S 22 Ilk'ill O.dvO 5 5 Ofrf r an 100 dOSl.
J.ovo 5 Sl an VOO Q V Oa leO VOO % W ann la Vdd ~ W aa lOO VOO + Va ta l00 2.2%v ~ ld 005 2.$ 0 20d 50% 2.00'ld 005 !0.0te ll1d O. 52 FLAW AT EGGCRATE SUPPORT (FLAW IDENTIFIED BY VECTOR POINTS) tr 400 Olla' loc olrf dlrl 5 Dlrr Ovo 5 ~ alt I.JVO 5 ll dl& l.ovo 5 ~ aro 2.~ 5 25 a52 vdd g v ~ aa leo vdd a vai e loo vod g v I e larva g ~o w le 2.5lv lloyd 30l 3.%%< lCdd 2.%le %kl tA 2.~ 203e 01H 0. 70 nrc4 96.wpa
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FPL PRESENTATION TO NRC - APRIL 22, 1996 ST. LUCIE UNIT 1 STEAM GENERATOR PROGRAM III. ECT TECHNIQUE QUALIFICATION- IGA/SCC EPRI BOBBIN COIL QUALIFICATION FOR IGA/SCC ALL DRILLED SUPPORT PLATE PULLED TUBE FLAWS e t e 'xHR EP I Tec DETECTION 80% POD For Flaws I ~
90% CL 60%
80% POD 90% CL For Flaws 40 DEPTH SIZING RMSE s 25% RMSE = 29~o EPRI EFFORT NOT REPRESENTATIVE FOR CE S/Gs ST. LUCIE UNIT 1 HAS 2 PARTIAL DIAMETER DRILLED SUPPORTS nrc4 96.wpa
4 I
FPL PRESENTATION TO NRC - APRIL 22, 'I996 ST. LUCIE UNIT 1 STEAM GENERATOR PROGRAM IV. 1996 S/6 INSPECT(ON PLANS DRILLED SUPPORT PLATES f
ENHANCED APPROACH FOR EOC 13 INSPECTION EPRI S/G Examination Guidelines, Supplement I - "Guidelines for Disposition of Bobbin Coil Indications Attributed to ODSCC at Non-Dented and Drilled Tube Support Plates" SUPPLEMENT I APPROACH BOBBIN SIZING IF INDICATION IS CONCLUSIVE MRPC IF INDICATION IS INCONCLUSIVE REPAIR FOR CRACK LIKE INDICATION MONITOR IF NOT CRACK LIKE FPL APPROACH - MRPC ALL BOBBIN INDICATIONS PLUG CRACK-LIKE INDICATIONS TRACK IF NOT DETECTED BY MRPC EVALUATE IF NOT CRACK-LIKE BY MRPC ASSESS DEPTH BY BOBBIN E. MRPC REVIEW HISTORY FOR GROWTH PLUG IF 4P%) OR EVIDENCE OF GROWTH nrc4 96 woa
FPL PRESENTATION TO NRC - APRIL 22, 1996 ST. LUCIE UNIT 1 STEAM GENERATOR PROGRAM IV. 1996 S/G INSPECTION PLANS BOBBIN COIL INSP ECTIONS
<00% OF ACTIVE TUBES FULL LENGTH MRPC COIL INSPECTIONS 100% OF ACTIVE HL EXPANSION TRANSITIONS 20% OF ACTIVE CL'EXPANSION TRANSITIONS 20% OF HL DENTED SUPPORT INTERSECTIONS SELECTED BOBBIN INDICATIONS (DIAGNOSTIC)
I
~ ~
FPL PRESENTATION TO NRC - APRIL 22, 1996 ST. LUCIE UNIT 1 STEAM GENERATOR PROGRAM IV. 1996 S/6 INSPECTION PLANS IN-SITU PRESSURE TEST SEVERAL SIGNIFICANT FLAWS AXIAL5 CIRCUMFERENTIAL INSTALLED PLUG INSPECTIONS LOCATION E. CONDITION WESTINGHOUSE ALLOY 600 PLUGS FRAMATOME "PAP" ALL HOT LEG PLUGS nrc4 96.wpa
FPL PRESENTATION TO NRC - APRIL 22, 1996 ST. LUCIE UNIT I STEAM GENERATOR PROGRAM V.
SUMMARY
CONSERVATIVE PROGRAM HISTORY PROACTIVE RESPONSE TO LEAKAGE PREVENTIVE PLUGGING PROACTIVE INSPECTIONS NO MID-CYCLE OUTAGES SINCE 1986 BOBBIN TECHNIQUE EXCEEDS APPENDIX H CONSERVATIVE APPROACH ON DRiL'D PLATES REPLACEMENT SCHEDULED FOR SPRING 1998 nrc4 96.wpa
FPL PRESENTATION TO NRC - APRIL 22, 1996 ST. LUCIE UNIT 1 STEAM GENERATOR PROGRAM V.
SUMMARY
REPLACEMENT S/G FEATURES SAME FORM, FIT & FUNCTION 50.59 SAFETY EVALUATION ALLOY 690 TUBING ALL LATTICE BAR SUPPORTS - 410 SS FLAT BAR VERTICAL SUPPORTS BLOWDOWN HEADER INTEGRAL WITH TUBESHEET I
nrc4 96.wpd
ENCLOSURE 2 MEETING BETWEEN NRC STAFF AND FLORIDA POWER 5. LIGHT COMPANY ST. LUCIE, UNIT 1 APRIL 22, 1996 Name Office W. Bohlke FPL G. Boyers FPL K. Craig FPL E. Weinkam FPL M. Schoppman FPL L. Wiens NRC R. Croteau NRR/PDII-2 P. Rush NRR/EMCB J. Norris NRR/PDI I-I B. Sheron NRR/DE F. Hebdon NRR/PD I I-3 J. Strosnider NRR/DE/EMCB E. Sullivan NRR/DE/EMCB G. Hornseth NRR/DE/EMCB K. Karwoski NRR/DE/EMCB J. Tsao NRR/DE/EMCB
lg I