ML18038B809
| ML18038B809 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/22/1997 |
| From: | Abney T TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18038B810 | List: |
| References | |
| NUDOCS 9701280304 | |
| Download: ML18038B809 (14) | |
Text
CATEGORY 1 REGULAT INFORMATION DISTRIBUTION@STEM (RZDS)
ACCESSION NBR:970128030$
DOC.DATE: 97/01/22 NOTARlZ+: NO DOCKET FACIL:.50-296 Browns Ferry Nuclear Power Sta&.on, 'Unit 3, Tennessee 05000296 AUTH.NAME AUTHOR AFFILIATION ABNEY,T.E.
Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control, Desk)
SUBJECT:
Provides initial issue of ISI 6 Sys Pressure Test programs for BFN,Unit 3,second insp interval IAW ASME Section XI, C
IWA-1400(c).Brief descriptions of requests for relief
!('equested date for NRC approval, listed.
A DISTRIBUTION CODE:
A047D COPIES RECEIVED:LTRj ENCLj SIZE:
IG T
TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code GL-89-04 NOTES:
RECIPIENT ID CODE/NAME PD2-3 WILIIAMS,J.
COPIES LTTR ENCL 1
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1 RECIPIENT ID CODE/NAME PD2-3-PD COPIES LTTR ENCL 1
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INTERNAL:
FILE CENTER 01 RES/DET/EIB EXTERNAL: LITCO ANDERSON NRC PDR 1
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1 AEOD/SPD/RAB NRR/DE/EMEB OGC/HDS3 RES/DET/EMMEB 1
1 NOAC 1
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NOTE TO ALL "RIDS" RECIPIENTSI PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 14 ENCL.
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'Tennessee Valley Authority, Post Office Box 2000, Decatur, Ahbama 35609-2000 January 22, 1997 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of Tennessee Valley Authority Docket No. 50-296 BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 3 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME ) r SECT ION XIr INSERVICE INSPECTION (ISI) AND SYSTEM PRESSURE TEST PROGRAMS FOR THE SECOND INSPECTION INTERVAL AND COST BENEFICIAL LICENSING ACTION (CBLA) 13 The letter provides the initial issue of the ISI and System Pressure Test programs for the BFN Unit 3 second inspection interval in accordance with ASME Section XI, IWA-1400(c).
The code of record for the second inspection interval is the 1989 Edition (no addenda) of the ASME Boiler and Pressure Vessel Code;Section XI.
The applicable regulation, 10 CFR 50.55a(g),
requires that ISI examinations.
and System Pressure Tests of ASME code components of a water-cooled nuclear power facility meet the ISI requirements of ASME Section XI.
In addition, 10 CFR 50.55a(g)(4)(ii) requires that the ISI and System Pressure Test programs be updated every 10 years to the latest NRC 970i280304 95ppp~q~
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U.S. Nuclear Regulatory Commission Page 2
January 22,=1997 approved Edition and Addenda of Section XI, which is in effect 12 months before the start of the next 120-month inspection interval.
The first inspection interval for BFN Unit 3 was extended to end one year after restart (November 19, 1995) by TVA letter to NRC, dated March 1, 1988.
As a result, the second interval for BFN Unit 3'egan November 19, 1996.
Enclosure 1 to this letter contains the updated BFN Unit 3 ISI program which conforms to the 1989 Edition (no addenda) of the ASME Section XI code.
There are six requests for relief submitted for staff approval in the initial issue of the ISI program.
Relief Request 3-ISI-3 was previously accepted by NRC letter, dated September 28, 1994, for the first ISI inspection interval.
A listing and brief description of the requests for relief and a requested date for NRC approval is provided below:
3-ISI-1 Requests relief from the IWB-2420(b) requirement that the "flaw indications or relevant conditions" of the Reactor Pressure Vessel shell welds identified in the third inspection period of the first ten-year interval be reexamined during the next three inspection periods.
(Approval requested by June 1997) 3-ISI-2 Requests relief from the ASME Section XI, 1989 Edition (no Addenda),
requirement for examination, testing and repair/replacement of snubbers in accordance with the first Addenda to ASME/American National Standards Institute (ANSI) Operations and Maintenance (OM) '1987, Part 4.
(Approval requested by October 1997) 3-ISI-3 Requests relief to use ASME Code Case N-524, "Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping,Section XI, Division 1,"
in lieu of the ASME Section XI, 1989 Edition requirements.
(Approval requested by February 1998)
U.S. Nuclear Regulatory Commission Page 3
January 22, 1997 3-ISI-4 Requests relief from the ASME Section XI, Table IWB-2500-1, requir'ements related to 100 percent examination of the required weld and base material required for Examination Category B-K-1, integrally welded supports.
(Approval requested by October 1997) 3-ZSI-5 Requests relief to use ASME Code Case N-547, "Alternative Examination Requirements for Pressure Retaining Bolting of Control Rod Drive (CRD) Housings,Section XI, Division 1," in lieu of the ASME Section XI, 1989 Edition requirements.
(Approval requested by February 1998)
~
3-ISI-6 Requests relief to use ASME Code Case N-532, "Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000: Section XI, Division 1" in lieu of the ASME Section XI, 1989 Edition.
(Approval requested by February 1998)
TVA requests that request for relief 3-ISI-1 be given priority review since it is an issue related to the first inspection period of the interval.
Also included in Enclosure 1 are the following:
~
Attachments 1 and 2 to request for relief 3-ISI-1, which provide additional reference information for use in reviewing 3-ISI-l.
~
A printout of Class 1,
2, and 3 equivalent components as additional information to support the ISI examination schedule tables in Section 8.1 of 3-SI-4.6.G, Inservice Inspection
- Program, Unit 3.
Enclosure 2 provides the updated System Pressure Test Program which conforms to the 1989 Edition of the ASME Section XI code.
Included with the program update are five requests for
- relief, 3-SPT-1 through 3-SPT-5, submitted for approval.
il 4l
U.S. Nuclear Regulatory Commission Page 4
January 22, '1997 Relief request 3-SPT-1 was accepted by the staff in NRC letter dated, August 8,
1995, for the first ASME Section XI System Pressure Test inspection interval.
Each of the five relief requests adopts the use of a specific ASME Section XI code case.
A listing and brief description of the requests for relief and a requested date for NRC approval is provided below:
3-SPT-1 Requests relief to use ASME Code Case N-416-1, "Alternative Pressure Test Requirements for Welded Repairs or Installation of Replacement Items by Welding," in lieu of the ASME Section XI, 1989 Edition requirements.
(Approval requested by February 1997) 3-SPT-2 Requests relief to use ASME Code Case N-498-2, "Alternative Rules for 10-Year System Hydrostatic Testing for Class 1,
2, and 3 Systems,Section XI, Division 1," rather than the ASME Section XI, 1989 Edition requirements.
(Approval requested by July 1998) 3-SPT-3 Requests relief to use ASME Code Case N-546, "Alternate Requirements for Qualification of VT-2 Examination Personnel,"
rather than the requirements specified in ASME Section XI, Subsection IWA-2300.
(Approval requested by February 1997) 3-SPT-4 Requests relief to use ASME Code Case N-566, "Corrective Actions for Leakage Identified at Bolted Connections," in lieu of the requirements of ASME Section XI, Subsection IWA-5250(a)(2).
(Approval requested by February 1997) 3-SPT-5 Requests relief to use ASME Code Case N-522, "Pressure Testing of Containment Penetration
- Piping,Section XI, Division 1," in lieu of the requirements of ASME Section XI, Table IWC-2500-1, Category C-H.
(Approval requested by July 1998)
4l
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U.S. Nuclear Regulatory Commissio~
Page 5
January 22, 1997 TVA has determined that Relief Request 3-ISI-4 represents a
CBLA because continued examination of 100 percent of integral attachment welds would be unnecessarily costly without providing a commensurate level of safety.
- Further, the examination of accessible areas of integral attachments without removal of support members was approved for a future code revision by the ASME Section XI committee in March 1995.
TVA estimates that approval of this relief request could save approximately
$ 1, 600, 000 during the remaining Unit 3 inservice inspection intervals.
There are no commitments contained in this letter.
If you have any questions please call me at (205) 729-2636.
cer
/
T. E. Abney Manager of Lice sing and Industry Affairs Enclosures cc (Enclosures):
Mr. Mark S. Lesser, Branch Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900
- Atlanta, Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road
- Athens, Alabama 35611 Mr. J.
F. Williams, Project, Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pi;ke Rockville, Maryland 20852
Cl 4l
ENCLOSURE 1
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 3 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)
SECTION XI SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION (ISI)
PROGRAM (SEE ATTACHED)
0 41 I