ML17309A897
| ML17309A897 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/23/1997 |
| From: | Landis K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Plunkett T FLORIDA POWER & LIGHT CO. |
| References | |
| NUDOCS 9707070049 | |
| Download: ML17309A897 (78) | |
Text
June 23, 1997 Florida Power and Light Company ATTN:
Mr. T.
F. Plunkett President
- Nuclear Division P. 0.
Box 14000 Juno Beach, FL 33408-0420
SUBJECT:
MEETING
SUMMARY
- BI-MONTHLY PLANT PERFORMANCE STATUS ST.
LUCIE 1 AND 2 -
DOCKET NOS. 50-335 AND 50-389
Dear Mr. Plunkett:
This refer s to the meeting held on June 17, 1997, at NRC Region II office in Atlanta, Georgia.
The purpose of the meeting was to discuss the progress in the St. Lucie Performance Improvement Program.
It is our opinion that this meeting was informative and beneficial.
Enclosed is a list of attendees and a
copy of the Florida Power and Light Company handouts.
The discussions included the following topics:
Presentation of Selected Plant Indicators, Presentation on St. Lucie Unit 2 Outage Perf'ormance, and Steam Generator Replacement Briefing.
In accordance with Section 2.790 of NRC's "Rules of Practice, "Part 2, Title 10 Code of Federal Regulations, a copy ot this letter and its enclosures will be placed in the NRC Public Document Room.
Should you have any questions concerning this letter, please contact me at (404) 562-4530.
Sincerely, Orig signed by Kerry D: Landis Kerry D. Landis, Chief Reactor Projects Branch 3
Division of Reactor Projects Docket Nos. 50-335.
50-389 License Nos.
Enclosures:
1.
List of Attendees 2.
St. Lucie Handout cc w/encls:
J.
A. Stall Site Vice President St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen
- Beach, FL 34957 cc w/encl:
Continued see page 2
~gnng3
"'7707070049 970623" PDR ADQCK 05000335 P
PDR OFFICIAL COPY ll!!ll!lllllllllllll!lllllllllllllllfl
FPSL cc w/encls:
Continued H.
N. Paduano, Manager Licensing and Special Programs Florida Power and Light Company P. 0.
Box 14000 Juno Beach.
FL 33408-0420 J. Scarola Plant General Manager St. Lucie Nuclear Plant 6351 South Ocean Di.ive Jensen
- Beach, FL 34957 E. J.
Weinkam Licensing Hanager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen
- Beach, FL 34957 H. S.
- Ross, Attorney Florida Power 8 Light P. 0.
Box 14000 Juno Beach, FL 33408-0420 John T-. Butler, Esq.
- Steel, Hector and Davis 4000 Southeast Financial Center
- Hiami, FL 33131-2398 Bill Passetti Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Boulevard Tallahassee.
FL 32399-0700 Joe Hyers. Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, FL 32399-2100 Douglas Anderson County Administrator St. Lucie County 2300 Virginia Avenue Ft. Pierce.
FL 34982
FP8L Distr ibution w/encls:
L. Wiens, NRR B. Crowley. RII G. Hopper, RII PUBLIC NRC Resident Inspector U.S. Nuclear Regulatory Comm.
7585 South Highway A1A Jensen Beach.
FL 34957-2010 SIGNATURE NANE Rud sall OATE 06 I) / 97 coen 06 /
/ 97 06 /
/ 97 06 /
/ 97 YES NO YES NO YES HO 06 /
/ 97 06 /
/ 97 YES HO YES NO
NUCLEAR REGULATORY COMMISSION LIST OF ATTENDEES L. Reyes.
Regional Administrator, Region II (RII)
B. Mallett, Acting Deputy Regional Administrator, RII J. Johnson, Director, Division of Reactor Projects (DRP). RII J.
- Jaudon, Director. Division of Reactor Safety (DRS), RII K. Landis. Chief, Branch 3, DRP, RII H. Christensen, Chief. Engineering
- Branch, DRS. RII W. Holland, Acting Chief, Maintenance
- Branch, DRS, RII M. Miller, Senior Resident Inspector, St. Lucie,,DRP. RII S. Rudisai 1, Project Engineer, DRP, RII L. Wiens, Project Manager, Project Directorate II-3, NRR R. Hannah, Public Affairs Officer FLORIDA POWER AND LIGHT T. Plunkett, President, Nuclear Division A. Stall, Site Vice President, St.
Lucie R. Kundalkar, Vice President Engineering E.
Weinkam, Licensing Manager C.
- Wood, Work Control Manager R. Daly, Director, Steam Generator Replacement Project R. Gross, Project Engineer OTHER L. Colson,
- Engineer, Florida Public Service Commission Enclosure 1
..9707070049
o Introduction and Openi'ng Comments o
Presentation of Selected Plant Indicators e
Presentation on St. Lucie Unit 2 Outage Performance o Steam Generator Replacement Briefing e
Closing Remarks
e ecte ant n icators
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ucle Illt2 Outa e Per ormance Summar 22
Outage Shutdown Risk Overview e
Risk Assessment Team and Outage Schedule Safety Review Included As an Aspect of Outage Preparations
~ ORAM-Type Software Used to Analyze Potential Schedule Impacts on Nuclear Safety e
Output From Schedule Safety Analysis Reviewed by Risk Assessment Team
~
Risk Assessment Team Review Resulted in Schedule Changes and Improved Margin of Safety and Defense in Depth 23
Outage Shutdown Ibsl< Overview (cont.
EP~~~%22KCB Risk Assessment Team Monitored Schedule and Shutdown Safety-Periodically During the Outage and After Major Schedule Changes e The STA Analyzed Plant Configuration on a Shift-By-Shift Basis During the Outage Using the Shutdown Safety Assessment
~
Plant Configuration Analysis Results and Protected Equipment Requirements 0/ere Communicated to Each Outage Shift
Reduced Inventory Restrictions
~
No Switchyard Work Without the Operations Supervisor's Permission o -Limited Work Only. On Vital 4.16KV and 480V Buses
~
No Work on Circuits, Transmitters, Power Supplies or Controllers Which Support Shutdown Cooling Components
~
Independent Vessel Level Monitoring Methods Are in Use
~
When the Reactor Head Is Installed, 2 Core Exit Thermocouple Readouts Are Available in the Control Room and the Pressurizer Manway Is Removed 25
Reduced Inventory Restrictions cont.
~
Containment Closure As Defined in GL 88-17 or the Abilityto Achieve Closure Within 30 Minutes; Unannounced Closure Drills Conducted Periodically
~
One EDG Operable and One EDG Available to Carry All Loads Necessary to Maintain Cold Shutdown
~
Two Containment Coolers Are Available on the Same Train As the Operable EDG With Cooling Water Supplied
~
One HPSI Pump Administratively Controlled So That It Is Capable of Taking Suction on the RWT and Injecting Water Into the RCS and Can Transfer Suction to the Containment Sump, If Required, and One Additional Makeup Pump (HPSI or Charging) Available 26
Reduced Inventory Restrictions cont.
If the Plant Is Placed in Mid-Loop Conditions, the Following Additional Measures Are Imposed:
o An Operator Is Dedicated to Monitoring Reactor Vessel Level (ERDADS)
~
No Work Is Allowed Inside the RTGBs Which Involves Wire Removal or Installation e
No Work ls Permitted on Vital 4.t6KV or 480V Buses e
An Additional Management SRO Is on Duty 27
St. I,ucie Plant Otrtage Performance
~~~a~~AOiKKR4$NR55~
Outage Performance Indicator Nuclear Safety Problems Personnel Safety - Lost Time Accidents Doctor Case injuries Personnel Exposure (Man-REM)
Personnel Contaminations Outage Related Significant Condiiton Reports Cubic Feet of Waste Generated Meet or Beat the Outage Schedule
- Duration Meet or Beat the Outage Budget Contaminated Floor Space within 30 Days Post-Outage Goal 0
0 6
181 10 6,500 42 532.5M 0
Unit 2 1997 0
167 4 440 41 f27.5M 0
Unit1 Unit 2 1996 1995 0
0 0
0 366 311 11,935 84 88
$31.0M
$22.2M
0
Significant Outage Activities
~
Conducted Full Core Offload to Support Freeze Seals and Other
'rimary System Valve Work
~
Steam Generator Eddy Current Testing 100'.k Both Steam Generators ECT Use of "Plus Point" Probe 92 Tubes Plugged (-4% Cumulative Tube Plugging) e Ft. Calhoun Flow Accelerated Corrosion Event of April 1 997 Reviewed Against St. Lucie inspection Plan
Significant Outage Activities cont.
EBKRHPK@~
e Emergency Diesel Generator Reliability Improvements Replaced Critical Relays With Improved Design With Better Contact Sealing Replaced Governor Actuators to Address Pin Shearing tssue Replaced Generator Slip Ring Bolts to Prevent Future Failure Performed Complete Mechanical Inspection of All Engines Performed Maintenance on Starting Air Systems 30
Significant Outage Activities cont.
o Engineered Safety Features (ESF) Testing Completely Rewritten Procedure Worked Well During First Time Use Procedure Thoroughly Tested on Simulator During Development Tested One Train at a Time So That Shutdown Cooling Flow Was Maintained Only One Significant Failure: 2A LPSl Pump Originally Scheduled to Be Performed at the Beginning of the Outage; 2A LPSI Pump Failure Required Moving Test to the End of the Outage No Failures During Testing at the End of the Outage
Slgl11flCB.lit OUtB.ge ACtlVltleS COllt.
e Containment Sump Screens Outside of Design Basis Condition Discovered by Senior Resident Inspector Late in Outage During Sump Inspection for Containment Close-Out Openings Found in Screens Around A and B Sumps Larger Than Described in UFSAR Screen Patches Applied Over Some Openings, Others Covered With Plate Containment Sump Restored to Design Conditions 32
Significant Outage Activities cont.
o Broken lncore Instruments Detectors Broke During Removal and Not Immediately Identified As Being Broken Containment Evacuation Alarm/Containment Isolation Occurred N/hen Upper Guide Structure Raised for Removal From Vessel Three InCore Instrument Pieces Remained in Upper Guide Structure Overall, Five Broken Detectors Discovered 33
Significant Outage Activities cont.
~
Clearance Problems Several Clearance Errors (DC Bus Bkr, CWP, EDG Oil Pump)
Resulted in Outage Stand Down to Implement Corrective Actions Major System Clearances (e.g.,
RCS, Main Steam, Condensate)
Tagged Some Components Unnecessarily Resulting in the Need for Boundary Modifications Some Components to Be Worked Had Clearance Tags Installed and Required Modification Root Cause Analysis of These and Other Clearance Errors Underway
Outage Balance Of Plant Issues
~
Synchroscope During Turbine Startup, Operators Discovered Loss of "Incoming Voltage" Indication; Synchroscope Was Inoperable FPL Determined That an Electrical I ead From a Current Transformer Was Landed Incorrectly After Lead Re-Landed, Phase Rotation Checked to Verify Proper Operation of Synchroscope 35
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INTRODUCTION
~
10 CFR 50.59 Changeout
~
One Piece Like for Like Replacement
~
No Tech Spec Changes
PROJECT HISTORY - Started in 1992
~
Tube Inspection Program Predicts Need for Replacement
~
Manufacturer - Babcock 8 VVilcox, Canada and Mt. Vernon, IN o
Duration - 5 Years to Build
~
Transportation - Barge via River and Ocean to St. Lucie o
Temporary Storage In St. Lucie Protected Area BEST BB W REPLACEMENT STEAM GENERATORS
~
No Tubes Plugged in Either Replacement Steam Generator
~
No Tubes Over Expanded
ENGINEERING AND UALITYINVOLVEMENT
~
FPL QA Representative at Shop 3.5 Years
~
Conducted Eight Design Reviews Tubing, Performance, Stress, etc.
~
QA Audits
~
Management Oversight Meetings
~
Conducted Third Party Reviews
KEY ENHANCEMENTS OF REPLACEMENT STEAM GENERATORS o
Inconel 690 Tubing, Thermally Treated
.~
Low Cobalt Cladding (<0.02%)
~
Electro Polished Channel Head
~
Forged Shell Sections
~
High Performance Steam Separators
((0.10% Moisture Carryover)
~
Stainless Steel Lateral Supports
~
Larger Primary Manways (181nch)
~
Increased Number Hand Holes and Inspection Ports
~
integral Tubesheet Blowdown with Two Nozzles
~
Integral Steam Nozzle Flow Restrictor
FIGURE -1. I GENERA ARRANGEMENT TEAH OUTLET NOZZLE'IGH EFFICIENCY HO ISTURE SEPARATORS ECQNOARY HEAO ECQNOARY OECK ECQNOARY HANWAY PR IMARY OECK FEEOWATE HEAOER EEDWATE'R INLET ONE SECT ION LATTICE-BAR TUBE SUPPORT GR IOS QWNCCHER ANNULUS I
HRQUO TUBE BUNOLE ISER TUBE SHEET STAY CYLINOE LOWOQWN HEAOER RIHARY HE'AO PR IHARY INLET R J HARY OUTLET
MAJOR CONTRACTORS
~
Steam Generator Team - Prime, Replacement Contract Experienced at Point Beach 1 8 2, D.C. Cook
~
Power Cutting, Inc.
Welding and Cutting Sub-Contractor to Steam Generator Team Many Steam Generator Replacements in US Salem, Point Beach, Millstone, etc.
Excellent Record
~
Davenport Mammoet Heavy Liftand Equipment Very Experienced US/Dutch. Company Excellent Equipment and Experienced People Sub-Contractor to Steam Generator Team and Sub-Contractors to Chem-Nuclear for Disposal of Original Steam Generators
OUTAGE
~
Level I Schedule (Attachment)
Outage Start October 20, 1997 75 Days, Breaker to Breaker Integrated Plant Schedule
~
SGRP Organization Organization Chart (Attachment)
Experienced People Florida Power 8 Light and Contractors
~
Goals Man/Rem-Nuclear Safety, Industrial Safety Schedule Cost
O4au Description
" MILESTONES & KEY PLANT ACTIVITIES" OUTAGE WINDOW BREAKER OPEN COOLT0200F ENTERMODE5 CORE OFFLOAD RE INSTALLUGS & SET HEAD DRAIN CAVITYTO Ax FLANGE AFTER CORE OFF OP RAISE ACS LEVELTO 64 FT FOR UGS REMO CORE RELOAD FILLI VENT RCS & DRAW BUBBLEIN PRESS.
RCS HEAT UP TO 200F M.4 RCS HEAT UP & PRESS. TO NOT/NOP ST.
E UNIT 1 SGRO 5 PRESS. HEATER SOMMARY 1991 OCTOBER OVE
.2.I.4 I
.I I
.I 14 l 17.l 20 123.J.Z
.).29
" MILESTONES & KEY PLANT ACTIVITIES" 20 20
~ 21 I Q I
29..01
~l I 01 08 0202 N
MBER.............
O.l 6
8 11 8
I.32.J.35 l.38 J 4 l,).443.41 l 6S 1213 Ai 13
.11 24.......2 DECEMBER 60.1 53 J 56.I 59 !.62.f.65 02 0 05:00 0 12:00 3 14:00 28 29 31 2 05:00 98 Span 1i 174.t
" STEAM GENERATOR REPLACEMENT" SGT STM. GEN. REPLACEMENT WINDOW REMOVE INTERFER. & SEC. PIPE OPEN CONSTR. HATCH & ERECT TLO AEMOVE OSG 1A INSTALLRSG 1B WELD OUT ACS REINSTALLSEC. PIPE & INTERF.
" PRESS. HEATER SLEEVES "
SET UP & PREPARE FOR HEATER WORK SET UP Nl PLATING &PWIIT EQUIPMENT HTR. SLEEVE Ni PLATING RESTORE PIPING AEINSTALLINSULATION& DEMOB
" PRESS HEATEA CABLES" REMOVE & REPLACE HEATER CABLES "STEAM GENERATOA REPLACEMENT" 06 L
" PAESS. HEATER SLEEVES I
22 I
01 I
26l
.31 L~
"PRESS HEATER CABLES" 17 11 18 1J I
I 2626 LI 28.
29[
12 13 04 0506 06......
12 5
..2 36 04:00 17 I I 12:00 18 22 30 1 12:00
l 0
STEAMGENERATOR REPLACEMENTPRO ECT ST. LUCIE PLA(XT YICI PRrslol:i T J.A.STAI.I, SG Rl' DIR I'.CTO R
~ R.J. DAI. Y kIA(IAGER ~ J. (il.TEPI.EY SPECIAl. PRO) I'.CTS I<I TECIlh(ICIAh(S Iil SGT PROJECT DIR I CTOR ill.IIl(XG IIA(il Eh(GIIIEER lhG IilAh(AGER ni GROSS IIEAI.11I Pll YSICS LrAD K. PA Y(X E PRO)I CTCOhlROI.
COST
'lV. CO IY OR E Y L'i'0RK CO(I1ROI COORDIih ATO R II. GROSS 0 PS(le 1)IR I:ACE Aho TEST L. (AICI.AUGIII.I((
Co DISTR uCTIOII I.EAO F. GIGEI.E QA~QC I.EAO R. 'LVEIS 10
OUTAGE continued m
o Lessons Learned NRC Industry
~
Self Assessments JANUS Review Internal Readiness Review Planned in July
~
Pre-Outage Preparation Training Mockups Nlelding Qualifications Replacement Steam Generator Nozzle Preps Equipment Check Out/Load Testing
OUTAGE continued
~
Heavy Liftand Upending Equipment
~
Disposal of OSG Chem-Nuclear Awarded Contract DOT Exemption Letter for IP-2 Packaging Requirements Submittal Temporary Storage on Site Transportation - Barge Inter Coastal Waterway-December/January Burial in Barnwell, South Carolina
PRESSURIZER HEATER SLEEVES ENHANCEMENT
~
Remove All 120 Heater and Associated Cables
~
Nickel Plate Each Heater Sleeve with 10 Mils
~
Replace Heaters and Cable
~
Replace Bottom Insulation
~
Plating Process
~
Minimum Schedule Impact