ML20217H571
| ML20217H571 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/15/1999 |
| From: | Wiens L NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9910220160 | |
| Download: ML20217H571 (31) | |
Text
.
L g- % UNITED STATES s y NUCLEAR REGULATORY COMMISSION
? WASHINGTON, D.C. 20066-0001 k**,*[t October 15, 1999 LICENSEE: Florida Power Corporation 1
FACILITY: Crystal River, Unit 3 I i
SUBJECT:
SUMMARY
OF MEETING ON SEPTEMBER 27,1999, CONCERNING CRYSTAL RIVER UNIT 3 LARGE BCRE PIPING PROJECT On September 27,1999, a meeting was held between staff of the U.S. Nuclear Regulatory l Commission (NRC) and representatives of Florida Power Corporation (FPC). The purpose of j the meeting was to discuss a modified program to re-verify the design code and licensing basis of large bore sa%ty rslated piping at Crystal River Unit 3. Enclosure 1 is an attendance list for the meeting. knclosure 2 includes copies of the meeting handouts. l 1
FPC first provided a brief description of the originallarge bore piping program (LBPP), which had been developed to resolve concems with the adequacy of existing documentation to support the LBP licensing basis. The original program consisted of complete system walkdowns, analyses, and drawing reconstitutions. After the completion of this effort on two systems, FPC determined that this approach was resource intensive and inefficient, in that it would include piping systems or segments that may not have been adversely affected by previously identified code and design basis issues. No new issues were identified as a result of these walkdowns, and there was a significant impact on plant resources and as low as ,
reasonably achievable goals.
The modified program that FPC developed is intended to focus on specific issues and limit the program to piping segments that are rfrected by the issues that represent design basis concems. FPC indicated that this approach would identify nonconforming conditions more l quickly, while still establishing reasonable assurance that the CR-3 LBP was code qualified l and consistent with the licensing basis. A brief overview of the focused approach was provided,' with the main aspects being the establishment of a list of issues, evaluation of the j issues with reference to a specific system, development of corrective actions, and the updating of design and licensing documentation. A list of the 50 identified issues was provided and is included with the enclosed handouts.
The NRC staff indicated that the information presented by FPC at the meeting, as described in the handouts, was very useful in understanding the modified LBPP. The NRC representatives questioned whether the program should include risk insights in determining whether a piping segment may be adversely affected by one of the issues. The NRC staff also discussed details of the implementation of the program, and requested that a written description of the j )
modified program be provided to the NRC. The FPC representatives agreed to provide such a j h
FPC also discussed their plans to perform fatigue evaluations for reactor coolant system attached piping, CR-3 currently has fatigue evaluations for all RCS attachment nozzles. In /-
November 1997, FPC committed to upgrade their analysis for specified attached piping out to "f D the second isolation valve. However, the licensee concluded it would be more efficient to wait until the resolution of the Environmental Assisted Fatigue issue and completion of Electric h' !
Power Research Institute Thermal Fatigue ITG work, since these issues may require re-analysis of the fatigue evaluation. FPC justified this change based on the qualification of 9910220160 991015 PDR ADOCK 05000302 P PDR
e the reactor coolant system nozzles, and the performance of non-destructive evaluations of the lines performed with no ind# cations found. FPC, therefore, intended to change the commitment to perform the fatigue evaluatum as part of their license renewal application process, planned for in the 2002 - 2003 timeframe. The NRC staff requested that FPC include details on which welds were inspected on these lines, dates inspected, and the results of the inspections with the letter changing their commitment. The licensee agreed to include this information..
Original signed by:
L. A. Wens, Senior Project Manager, Section 2 Project Directorate il Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosures:
1, Attendance List
- 2. Handouts cc w/ enclosures: See next page HARD COPY Docket FileJ" PUBLIC ' +
CR-3 Reading LWens OGC ACRS E-MAIL .
JZwolinski/SBlack HBerkow SPeterson BClayton Alee ;
. YLi RWessman KManoly Elmbro JYorokun LWert, Ril' DOCUMENT NAME: G:\PDll-2\CRYSTALWITGSUMLBP.WPD -
~ To seasive a een r of ilde decomment, had este in 1is ben: "C" = Copy without uttachment/ enclosure *E" = Cc ey with attachmentlenclosure 'N" = No cosy OFFICE PDil-2\PM , 6: PDil-2\LA PDil-2\SCa NAME LWiens /fAv BClayton r-Au SPeterso'nT l DATE' 104't99 ~ 10/DB9 10/fV99 10/ /99 10/ /99 OFFICIAL RECORD COPY i n
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the reactor coolant system nozzles, and the performance of non-destructive evaluations of the. l lines performed with no indications found. FPC, therefore, intended to change the j commitment to perform the fatigue evaluation as part of theirlicense renewal application !
process, planned for in the 2002 - 2003 timeframe. The NRC staff requested that FPC
{
include details on which welds were inspected on these lines, dates inspected, and the results j of the inspections with the letter changing their commitment. The licensee agreed to include '
this information.
L. A. Wiens, Senior Project Manager, Section 2 Project Directorate 11 Division of Licensing Project Management i Office of Nuclear Reactor Regulation i Docket No. 50-302
Enclosures:
- 1. Attendance List
- 2. Handouts cc w/ enclosures: See next page 1
l 1
l i
r: ,
s.
w.
o
.Mr. John Paul Cowan. CRYSTAL RIVER UNIT NO. 3 Florida Power Corporation -
. cc:
l Mr. R. Alexander Glenn Chairman
- l. Corporate Counsel (MAC-BT15A) Board of County Commissioners l' Florida Power Corporation Citrus County
. P.O. Box 14042 110 North Apopka Avenue l
. .St. Petersburg, Florida 33733-4042 Invemess, Florida 34450-4245 l - Mr. Charles G. Pardee, Director Ms. Sherry L. Bemhoft, Director l Nuclear Plant Operations (PA4A) Nuclear Regulatory Affairs _(NA2H)
! Florida Power Corporation Florida Power Corporation Crystal River Energy Complex. Crystal River Energy Complex 15760 W. Power Line Street 15760 W. Power Line Street Crystal River, Florida 34428-6708 Crystal River, Florida 34428-6708 I Mr. Michael A. Schoppman Senior Resident inspector l Framatome Technologies Inc. Crystal River Unit 3
- 1700.Rockville Pike, Suite 525 U.S. Nuclear Regulatory Commission j .Rockville, Maryland 20852 6745 N. Tallahassee Road l Crystal River, Florida 34428 Mr. William A. Passetti, Chief l Department of Health Mr. Gregory H. Halnon L
Bureau of Radiation Control . Director, Quality Programs (SA2C) 2020 Capital Circle, SE, Bin #C21 Florida Power Corporation
! Tallahassee, Florida 32399-1741 Crystal River Energy Complex l 15760 W. Power Line Street Attomey General Crystal River, Florida 34428-6708 Department of Legal Affairs -
- The Capitol .
. Tallahassee, Florida 32304
. Mr. Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive
. Tallahassee, Florida 32399-2100 i i
t
I k
MEETING ATTENDEES CRYSTAL RIVER LARGE BORE PIPING RE-ANALYSIS PROGRAM MEETING September 27, 1999 NAME ORGANIZATION l _
Sid Powell FPC - Licensing Robert Layton FPC - Design Engineering Charles Pardee FPC - CR3 Plant Manager Daniel Roderick FPC - CR3 Engineering Director l Harry B. Oates FPC - CR3 Engineering Manager !
Dan Jopling FPC - CR3 Structural Engineering. l 1
John W. Martin FPC - CR3 Structural Engineering Arnold J. Lee NRC - NRR/DE/EMEB i Yueh-Li-(Renee) Li NRC - NRR/DE/EMEB Dick Wessman NRC - NRR/DE Kamal Manoly NRC - NRR/DE/EMEB Gene Imbro NRC - NRR/DE/EMEB Len Wiens NRC - NRR/DLPM PD II ;
Sheri Peterson NRC - NRR/DLPM/PD II i
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e." FOCUSED APPROACH ISSUES Issue Remarks j No. Issue Description I
1 Equipment Rigidity 2 Inadeouate Truncation of Seismic Class 1/111 Boundanes 5- 3 Unanalyzed Large Bore Safety-Related Piping 4 Modeling of Valve Eccentricities 5 Response Spectra Damping 6 Uplift on Rod Hangers 7 Evaluation of Welded Attachments 8 Temperature Cut-Off for Rigorous Thermal Analysis 9- Uncinched U-bolts Acting as Two-Way Restraints 10 Strut / Snubber Angularity 11 Non-Standard Supports and Qualification of Clamps for Side Loading j
12 Drawing Matching the As-Built configurations 13 Overlap Criteria :
14 Decoupled Branch Stresses due to Header SAMs and TAMS !
15 New P/T Calculations Data increases j 16 RCS Attached Piping impact. RC Pump Snubber Rernovals' 17 Valve Weight Changes l-18 Nozzle Qualification
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19 Decoupling Criteria 20 Class i Analysis 21 Clearances -
22 Thermal Operating Modes ;
23 Missing Mass Effects (High Frecuency Mass Participation) 24 Support Mass Effects (Hardware Weight) l 25 Dual Snubber Supports 26 Consideration of Friction Forces 27 Response Spectra Definition 28 Closely Spaced Modes
[ 29 Post-LOCA Temperature Exclusion 30 - Anchor SRSS Dynamic Load Combination
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31 Relax Anchor Bolt inteaction Commitment 32 Support Self-Weight Excitation 33 Evaluation of Footonnt Loads (to Steel) 34 Codeof Record 35 Preloaded Rod Hangers 36 Sonng Hangers Active in Seismic Analysis 37 Computer Program Verification (Documentation) 38 Consiste.ncy between Design Packages 39 Accessibility of Pertinent Documents 40 Uncontrolled Documents 41 Hard Copies of Pipe Stress Calculations 42 Missing 79-14 Documentation 43 Excessive Snubbers 44 Support Staffness 45 Excessive Support Deflection 46 Building Seismic Anchor Motions (SAM) 47 Missing Support Calculations 48 Stress intensification Factor (StF) Selection 49 Non-Standard Anchor Desgns (Non-Rigid) 50 Multiple Stress Codes Used Page1