ML18036B098
| ML18036B098 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| Issue date: | 12/17/1992 |
| From: | ZERINGUE O J TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9212210328 | |
| Download: ML18036B098 (9) | |
See also: IR 05000259/1992038
Text
A.CCEI ERATED DOCVMENT DISTJUBUTION
SYSTEM r>'EGULATORY
INFORMATION
DISTRIBUTION
SYSTEM (RIDS)ACCESSION NBR:9212210328
DOC.DATE: 92/12/17 NOTARIZED:
NO DOCKET~SCIL:50-059
Browns Ferry Nuclear Power Station, Unit 1, Tennessee 05000259 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH.NAME AUTHOR AFFILIATION
ZERZNGUE,O.J.
Tennessee Valley Authority RECIP.NAME
RECIPIENT AFFILIATION
Document Control Branch (Document Control Desk)SUBJECT: Responds to NRC 921123 lre re violation noted in Insp Repts 50-259/92-38,50-260/92-38
&50-296/92-38
on 921102-06.-
Corrective
actions:support
calculation
revised to incorporate
loads from latest stress analysis.DISTRIBUTION
CODE: IEOID COPIES RECEIVED:LTR
I ENCL[SIZE: TITLE: General (50 Dkt)-Znsp Rept/Notice
of Violation Response NOTES: S INTERNAL: RECIPIENT ID CODE/NAME HEBDONPF WILLIAMSiJ.
ACRS AEOD/DEZB AEOD/TTC NRR MORISSEAUPD
NRR/DLPQ/LPEB10
NRR/DREP/PEPB9H
NRR/PMAS/ILRB12
OE-DXR REG FILO 02 EXTERNAL: EGSG/BRYCEPJ
H.NSIC COPIES LTTR ENCL 1 1 1 1 2 2 2 2 1 1'1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME ROSSPT.AEOD AEOD/DSP/TPAB
DEDRO NRR/DLPQ/LHFBPT
NRR/DOEA/OEAB
NRR/PMAS/ILPB
NUDOCS-ABSTRACT
OGC/HDS3 RGN2 FILE 01 NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 D NOTE TO ALL RIDS" RECIPIENTS:
0 PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK.ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROh1 DISTRIBUTION
LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 27
I t(
TenneSSee Valley AutnOirty, POSt OttiCe BOX 2000.DeCatur.Atabama 35609.2000
O.J."Ike" Zering Ue Vice President, Browns Ferry Nuclear Plant OEC 1 7 1992 U.S.Nuclear Regulatory
Commission
ATTN: Document Control Desk Washington, D.C.20555 Gentlemen:
In the Matter of Tennessee Valley Authority Docket Nos.50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN)-NRC INSPECTION
REPORT 50-259, 50-260, 50-296/92-38
REPLY TO NOTICE OF VIOLATION (NOV)This letter provides TVA's reply to the NOV transmitted
by letter from C.A.Julian to M.0.Medford dated November 23, 1992.In this letter, NRC cited TVA with a violation involving one example of a pipe support not being qualified to the latest revision of the piping stress analysis.NRC further stated the"the violation is of concern because it indicated an inattention
to design control in the pipe support calculations
which could result in overstress
of support members." TVA agrees that the violation occurred;however, TVA believes that the violation was caused by an isolated human error.This conclusion
is based on'TVA's investigation
of this event.This investigation
consisted of reviewing a substantial
number of other pipe support calculations.
The results of this investigation
revealed that all the support calculations
reviewed were in compliance
with the applicable
design criteria.Additionally, since this incident was found to be an isolated case and modification
to the support was not required, the occurrence
has minor safety or environmental
significance.
Accordingly, TVA determined
that if the incident had been left uncorrected, a more serious condition would not have developed.
The enclosure to this letter is TVA's"Reply to the Notice of Violation" (10 CFR 2.201).92122i0328
92i2i7 PDR ADOCK 050002S9 Q PDR
s
U.S.Nuclear Regulatory
Commission
DEC i 7 1992 If you have any questions, please telephone G.D.Pierce, Interim Manager of Site Licensing, at (205)729-7566.Sincerely,.Zeringue Enclosure cc,(Enclosure):
NRC Resident-Inspector Brogans Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611 Mr.Thierry M.Ross, Project Manager U.S.Nuclear Regulatory
Commission
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr.B.A.Wilson, Project Chief U.S.Nuclear Regulatory
Commission
Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
'
Tennessee Valley Authority Browns Ferry Nuclear Plant (BFI)Reply to Kotice of Violation (ROV)Inspection
Report Eumber 2 2 2-RESTA OP VIOLATIO"During an HRC inspection
conducted on Hovember 2-6, 1992, a violation of HRC requirements
was identified.
In accordance
with the"General Statement of policy and Procedure for NRC Enforcement
Actions," 10 CFR Part 2, Appendix C, the violation is listed below: 10 CFR Part 50, Appendix B, Criteria III, Design Control requires that design changes, including field changes, shall be subject to design control measures commensurate
with those applied to the original design and be approved by the organization
that performed the original design unless the applicant designates
another responsible
organization.
TVA Nuclear Engineering
procedure HEP-3.1, Attachment
4, Page 1 of 1 states that design inputs, including information
such as loads, temperature,...shall be correctly selected current, referenced, and applied.TVA Rigorous Analysis Handbook, Section No.BFN-RAH-401, Rigorous Analysis Checklist requires that the correct support loads from the post processor output, or adjusted loads from'hand calculations, have been transmitted
to the support designer.Contrary to the above, Support Ho.2-47B46480029 (Calculation
Ho.CD-Q20?0-881980)
was not qualified per the latest stress calculation
Ho.CD-Q2070-880983, Rev.2.Instead, the support calculation
qualified the'upport
by using the stress loads from Rev.1 of the stress calculation
which were significantly
lower than the latest stress loads.This is a Severity Level IV violation (Supplement
I)."
~S VIO TIO s o eVoato The violation occurred because of an isolated human error that resulted in a pipe support (2-47B464H0029)
not being qualified to the latest revision of the piping stress analysis (Hl-270-2R).
An evaluation
vas performed on 70 pipe support calculations
to determine if this error occurred in other calculations.
The'results of this review revealed no reoccurrence
of this error.Therefore, based on the results of.this investigation, TVA has determined
that the error, vhich resulted in this violation, vas an isolated case.o rective Ste s a%en and Results Achieved During the inspection, TVA revieved 18 of the 38 safety related pipe supports associated
vith the affected pipe stress problem (Hl-270-2R).
TVA verified that all of these supports', except the support that vas found during the HRC inspection, considered
the loads from the latest stress analysis.Subsequent
to the inspection,, TVA completed its review of the remaining 20 of the 38 safety related pipe supports associated
vith the affected pipe stress analysis (Hl-270-2R)
to verify that the latest loads were considered.
It vas determined
that the support calculations
vere designed with loads either higher or equal to those in the latest stress analysis, except for the support that vas found during the HRC inspection.
TVA has revised the support calculation
to incorporate
the latest loads, determined
that no modification
to the support vas required, and determined
that system operability
was not affected.In addition, 32 additional
safety related supports from nine systems received the same reviev as part of TVA's evaluation.
This additional
review revealed that the supports were designed using loads equal to or greater than the loads generated by the appropriate
pipe stress analysis.ec ive Ste s That have een or il e aken o Prevent ec rence Existing TVA design procedures
prescribe requirements
that ensure the transmittal
and receipt of revised support loads.These procedures
also require that this information
be incorporated
into the appropriate
documentation
during the design change process.Since TVA has determined
that this is an isolated human error and does not indicate a failure of TVA's Quality Assurance Program, no additional
corrective
steps are required.ate en Fu Com liance i 1 Be chic ed TVA considers that full compliance
has been achieved.