ML14181A155
| ML14181A155 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 12/08/1993 |
| From: | Merschoff E NRC/IE, NRC/RGN-II |
| To: | Dietz C Carolina Power & Light Co |
| References | |
| NUDOCS 9312270213 | |
| Download: ML14181A155 (24) | |
Text
DEC -8 1993 Docket No.:
50-261 License No.: DPR-23 Carolina Power and Light Company ATTN:
Mr. C. R. Dietz Vice President H. B. Robinson Steam Electric Plant Unit 2 P. 0. Box 790 Hartsville, SC 29550-0790 Gentlemen:
SUBJECT:
MEETING
SUMMARY
- ROBINSON UNIT 2 This refers to the management meeting conducted in the Region II Office on December 3, 1993. The purpose of the meeting was to discuss the results of your investigation of root cause analysis of core load deficiencies at the Robinson Plant. A list of attendees and a copy of your slides are enclosed.
It is our opinion that this meeting was beneficial and it satisfied your commitment in CAL 2-93-08 to meet with the NRC prior to completing the core configuration alternatives.
In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Room.
Should you have any questions concerning this matter, please contact us.
Sincerely, Original signed by:
Ellis W. Merschoff Ellis W. Merschoff, Director Division of Reactor Projects
Enclosures:
- 1. List of Attendees
- 2. Licensee Slides cc w/encls:
(See page 2) 230045 9312270213 931208 PDR ADOCK 05000261 P
PDR 2IELJV
Carolina Power and Light Company 2
DEC 8 199 cc w/encls:
M. P. Pearson Plant Manager H. B. Robinson Steam Electric Plant P. 0. Box 790 Hartsville, SC 29550 H. W. Habermeyer, Jr.
Vice President Nuclear Services Department Carolina Power & Light Company P. 0. Box 1551 - Mail 0HS7 Raleigh, NC 27602 D. B. Waters, Manager Regulatory Compliance H. B. Robinson Steam Electric Plant P. 0. Box 790 Hartsville, SC 29550 Max Batavia, Chief Bureau of Radiological Health Dept. of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 Dayne H. Brown, Director Division of Radiation Protection N. C. Department of Environment, Commerce & Natural Resources P. 0. Box 27687 Raleigh, NC 27611-7687 McCuen Morrell, Chairman Darlington County Board of Supervisor County Courthouse Darlington, SC 29535 H. Ray Starling Vice President - Legal Department Carolina Power and Light Co.
P. 0. Box 1551 Raleigh, NC 27602 Karen E. Long Assistant Attorney General State of North Carolina P. 0. Box 629 Raleigh, NC 27602 (cc w/encls cont'd - See page 3)
- 8 1993 Carolina Power and Light Company 3
(cc w/encls cont'd)
Robert P. Gruber Executive Director Public Staff -
NCUC P. 0. Box 29520 Raleigh, NC 27626-0520 Public Service Commission State of South Carolina P. 0. Box 11649 Columbia, SC 29211 bcc w/encls:
H. Christensen, RH B. Mozafari, NRR Document Control Desk NRC Resident Inspector U. S. Nuclear Regulatory Commission Route 5, Box 413 Hartsville, SC 29550 RIIDRt RII:DRP DVerrelli JJohnson 12/ 7/93 12/ /93
ENCLOSURE 1 List of Attendees Carolina Power and Light Company:
W. S. Orser, Executive Vice President H. W. Habermeyer, Vice President, Nuclear Services C. R. Dietz, Vice President, Robinson B. Rogan, Manager, Licensing J. Martin, Manager, Fuel Performance S. Zimmerman, Manager, Nuclear Fuels B. Clark, Manager, Maintenance G. Bussell, Manager, Mechanical Maintenance A. McCauley, Manager, Electrical Systems B. Ziegler, Manager, Pressure Water Reactor Fuel Analysis Siemens Fuel Manufacturing:
J. Helm, Manager, Pressure Water Reactor, Nuclear Engineering Nuclear Requlatory Commission:
S. D. Ebneter, Regional Administrator, Region II (RH)
E. W. Merschoff, Director, Division of Reactor Projects (DRP), RH A. F. Gibson, Director, Division of Reactor Safety (DRS), RII T. A. Peebles, Chief, Operations Branch, DRS, RH S. S. Bajwa, Acting Director, Project Directorate II-1, Office of Nuclear Reactor Regulation (NRR)
D. M. Verrelli, Chief, Reactor Projects Branch 1, DRP, RH H. 0. Christensen, Chief, Projects Section lA, DRP, RH B. L. Mozafari, Project Manager, NRR M. E. Ernstes, Reactor Inspector, DRS, RH
ENCLOSURE 2 Carolina Power & Light Company H. B. Robinson Steam Electric Plant NRC Management Meeting Atlanta, Georgia December 3, 1993
Agenda Opening Remarks C. R. Dietz Fuel Issues H. W. Habermeyer, Jr.
W. R. Ziegler Root Cause Investigation G. T. Bussell "B" Emergency Diesel Generator Failure D/G Auto Voltage Control A. M. McCauley, Jr.
Closing Remarks W. S. Orser
Purpose:
To Describe CP&L's Verification Of The Cycle 16 Core Configuration.
Defense In Depth:
Design Manufacturing Startup Testing 1
Steps Taken To Ensure That All Fuel Assemblies Loaded For Cycle 16 Were Fabricated Correctly 2
Bundle Daign/Manufacting Quality Verification CP&L Siemens Fuel Bundle And Fuel Bundle And Core Design Core Design Calculations Calcilations Siemens
- Pr List Current-Bundle Type Current CP&L Bundle Map!
Siemens
-Bundle M ap/
erificatioNumber Verificatio Rod Position Map Referenced Entered Into Bundle Map Computer Number Bundle Proof Map Original Printed By Q
Computer Verification Rods Loaded Into Bundle Per Computer As-Built Original Customer Bundle Printout QC Packrge FVerification Package From Computer
CP&L Activities Comparison Of Assembly Maps CP&L Design Process Vs. Siemens Bundle Map Comparison Of Siemens As-Built Bundle Printout With Corresponding Bundle Map Siemens Activities Siemens Review Confirms CP&L Review Of Bundle Assembly Loading Maps Eighteen Of Twenty Video Taped Rods Have Visible Rod Serial Numbers And Are Identical To Serial Numbers Recorded On Siemens As-Built Bundle Printout Records Siemens Certifies Fuel Rod Pellet Loading Conforms To Design Confirmation Fuel Examination Select One Fuel Bundle From Each Group Of Three Mis-Fabricated Bundles.
Move Two Selected Fuel Bundles To Spent Fuel Pool Read Rod Serial Numbers From 2 Locations Where Gadolinia Rods Are Expected.
Confirm Siemens As-Built Bundle Printout.
Conclusion If Successful:
There Are No Other Mis-Fabricated Bundles In The Robinson Cycle 16 Core.
4
Missing Tool Pieces In Guide Tube Of Assembly U-24 Areas Reviewed:
Structural Support From Guide Tube:
o Adequate Support Provided In Assembly Design Potential For Fretting Inside Guide Tube:
o Flow Velocities Within Guide Tube Not Adequate To Levitate Loose Parts Material Compatibility:
0 Parts Are Stainless Steel And Are Compatible With Guide Tube And Reactor System Potential For Parts Escaping From Guide Tube:
o Insufficient Flow Within Dashpot Region To Dislodge The Parts Additional Consideration:
Independent Evaluation By CP&L Nuclear Engineering Department Confirms Results Of Previous Evaluations
==
Conclusion:==
Assembly U-24 Acceptable For Use In Un-Rodded Core Location 5
Calculational Steps Taken To Ensure That All Detectable Misloaded Core Anomalies Have Been Identified For Cycle 16
SIMPLIFIED SPC/CP&L CALCULATION FLOWCHART I
I ISIEMENS PROCESSI CP&L REVIEW PROCESS I
NCERDSN I
CMAIO I
I COARREOT I
INEEDN I
ICORE I
IDESIGN 4-------1I------------------------------1 K-LOCATION I
D-BUNDLES I
I I
RESOLVEI I
I DESIGHN UI CALCO I
I ISSUE I
IANALYSIS ANALYSIS CP&L I
I INCORE ICORE IDESIGH DESIGN IREVIEW MODEL I
NO INUCLEAR DESGN I
COMPARISON II COMPARE REPORTS I
STARTUP & OPS I---
DES. REVIEW 1I OK TRAVELLER I
?
I ISYES I
ICP&L RESULTS II ACCEPT II CORE INDEPENDANT II DESIGN EYALUATION I
I NO I
J 1
INCORE I
CP&L I
ICOMPARE LOOK FOR I
DATA DECK 1-4 RECEIPT ICREATE I
ACTIVITYOKCUE F
I IF POWER SHAPE I
as IANOMALY Y ES YES PLANT INCORE MEASURED
)MEASURED DETECTOR POWER TRACES SHAPE CONFIRM NO RESULTS TECH SPEC YSPASS N
EVALUATE COMPIANE,VERIFY POOR MAP REPRT,"""TESTS RESULTS
CP&L Activities CP&L Calculations/Independent Generation Of INCORE Decks Performed To Eliminate Any Common Root Cause Calculational Error Results:
o Tilt Confirmed To Exist o
CP&L "As-Designed" Model Performance Would Have Prompted Investigation of 30% Map Anomaly o
CP&L "As-Loaded" Model Supports Conclusion That Anomaly Has Been Explained CP&L Calculations/Independent Receipt Inspection Of SPC INCORE Decks Has Ensured That Final Accepted INCORE Code Results Are Accurate Results:
o Revised SPC Decks delivered. CP&L Processing Confirmed Decks Are Error Free.
3
Siemens Activities Following Discovery Of Misloading, SPC Produced Microburn/INPAX Core Monitoring Model Of As-Loaded Configuration Results:
o M-B/INPAX "As-Loaded" Indicates A Small Actual F-Delta-H Violation o
M-B/INPAX Results Show Very Good "Predicted Vs. Measured" Comparison o
M-B/INPAX Submitted To NRC, But Not Yet Reviewed And Approved Following Discovery Of Errors In The Cycle 16 INCORE Decks Used For "As Designed" And "As-Loaded" INCORE Models, SPC Revised INCORE Decks For Both Conditions Results:
o INCORE Map Results Show Improved "Predicted Vs. Measured" Statistics (Maximum Difference 5% Vs. Previous 10%)
o F-Delta-H Violation At 30% Confirmed.
0.36% Over Tech Spec Limit (Map 698)
Map 699 Shows No Violation o
Both Maps Indicate No Core Anomaly 4
Low Power Physics/Initial Power Ascension Results F-Delta-H Values (All Include 4% Measurement Uncertainty)
Safety Significance Of 30% Power In As-Loaded Reactor Conditions:
None - Bounded By Analysis Safety Significance of Postulated Full Power Operation If Misloading NOT DETECTED Siemens Licensing Basis (XTG) Calculations:
100% Power, ARO F-Delta-H
=
1.797 Limit
=
1.70 Bounding Bundle Misloading Analysis Full Power Limits "Undetectable" Limiting Result @ 100% = 1.81 (XN-NF-84-74)
Cycle 16 "Undetected" Limiting Result
=
1.82 Bounding Analysis (RCCA Misalignment)
Limit 1.94 5
Root Cause Investigation "B" Emergency Diesel Generator Failure 1w
Sequence of Events "B"1 EMEFIIENEY D IESEL GENEFRTOB SEQUENCE OF EVENTS ROBINSON NUCLEAR PLANT 19 Start End Sep Oct MooJ Task Name Date nate 20 12?
14 1 tr U 125 1~
fc1 122 Overhal "B" Diesel 25-Sep-9m 24klt-93 Ron 'E Diesel 2-(kt-93i 24klt-93 A
Dupeuhaai 'W Diesel 34klt-4J3 04kt-93
~
~
Ir Diesel Fails 25-Ikt-93 25-ftt-Th
'W Diesel Troubleshootin 2S4-Oc3J 2fiOct-93 "W Diesel Starts for DP-11D4 26i-&t-93 2fr4kt-9h
- A "B" Diesel Starts for DST-1163 26-Oct-93 2fi-fct-93
- A
....................... ~..
"W Diesel Team Assembled 26-Oct-93 2fi-1Jct-93 A
Broken Springs Found A6Ot9 frfc-f D i se S t rt r
I l 9
c-g A
Vr Diesel Starts for DST-4mi 27-Uct-93 27-flct-93 A
V1 Diesel Starts for DST-1I1t 27-Oct-93 27-flct-9fl A
"B" Diesel Starts for US1-401 0-NauP-93 0-Nou-5J A
Diesel Panels Painted I I-Hou-93 11-Nov-93 A
Ir Diesel Fails to Start 22-Hnu-J3 22-Nou-'J AL liendr (InSite24-tlau-91 24-Nou-93 VRlmirs Enmplete, Diesel Start 25-Notp-93 2!ij-Htu,- J3
Air Start System Fl-ow Diagram AR IIA-W [M-M
-M' M~R AAR START
&E&B VALVE (MM fm M-1 JOR TA.CM U!!!RUI!II3IfYP
Air Distributor 4
1
Air Start Pilot Valve
Root Cause Analysis All Components Outside Air Start Distributor Eliminated As Cause Cam Resting Near #2 And #6 Pilot Valves
- 2 And #6 Pilot Valves Did Not Decend During Air Test
- 2, #4, And #6 Pilot Valves Had Broken Springs Rust Noted In Pilot Valve Caps During Disassembly Proper Operation Of The Pilot Valves Verified After Maintenance Both Diesels Subject To Increased Testing Corrective Actions Develop Preventative Maintenance Process Replacement Air Start Distributor Evaluate Air Start To Other Six Cylinders Revise Maintenance Procedure To Reflect Timing Setting Improve/Update Vendor Technical Manual 6.
D/G Auto Voltage Control
D/G Auto Voltage Control "A" & "B" D/Gs Tested Satisfactory 11/08/93 "A" & "B" D/G Control Panels Painted "A" D/G Attains 440 Volts 11/22/93 "B" D/G Autostart Failure 11/22/93 "B" D/G Attains 450 Volts 11/25/93 Cause:
Automatic Voltage Control Mispositioned Corrective Action:
Position Indication + Read Each 12 Hours Work Control Safety Significance:
Under Study 2