ML18039A781
| ML18039A781 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/21/1999 |
| From: | Peterson S NRC (Affiliation Not Assigned) |
| To: | Scalice J TENNESSEE VALLEY AUTHORITY |
| Shared Package | |
| ML18039A783 | List: |
| References | |
| TAC-M97805, NUDOCS 9905250304 | |
| Download: ML18039A781 (8) | |
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t UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 May 21, 1999 Mr. J. A. Scalice Chief Nuclear Officer and'Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNIT3 RELIEF FROM ASME BOILER AND PRESSURE VESSEL CODE, SECTION XI REQUIREMENTS: RELIEF REQUESTS 3-ISI-3, AND 3-ISI-6 (TAC NO. M97805)
Dear Mr. Sea[ice:
By letters dated January 22, 1997, and June 12, 1998, the Tennessee Valley Authority (TVA) submitted its second 10-year interval inservice inspection plan for the Browns Ferry Nuclear Plant, Unit 3 (BFN-3) and associated requests for relief, and additional information was submitted by letter dated October 29, 1998. TVAsubmitted a total of 11 relief requests.
Relief requests 3-ISI-3 and 3-ISI-6 are the subject of this letter and the enclosed safety evaluation.
Previously, the staff reviewed, arid approved relief requests 3-ISI-2 (May 3, 1999), 3-SPT-1 (March 10, 1997), 3-SPT-3 and 3-SPTA (September 28, 1998). Relief request 3-ISI-1 was denied (July 8, 1997), and relief requests 3-[S[-4, 3-[S[-5, 3-SPT-2, and 3-SPT-5 were withdrawn by TVAletter dated October 29, 1998.
Relief Request 3-ISI-3 requests relief,regarding the length of longitudinal piping welds required to be examined in accordance with American Society of Mechanical Engineers (ASME) Code,Section XI, Table IWB-2500 and IWC-2500.
In accordance with 10 CFR 50.55a(a)(3)(i).
TVA has proposed an alternative that would examine only the portions of longitudinal weld within the examination area of the intersecting ci'rcumferential weld in accordance with Code N-524, Alternative Examination Requirements forLongitudinal Weldsin Class 1 and 2 Piping. The U. S. Nuclear Regulatory Commission staff has reviewed the information submitted regarding TVA's proposed alternative to use Code Case N-524. The staff has concluded that the use of Code Case N-524 provides an acceptable level of quality and safety. Therefore, TVA's proposed alternativ, to use Code Case N-524, is authorized pursuant to 10 CFR 50.55a(a)(3)(i).
The use of this Code Case is authorized for the second 10-year interval at Browns Ferry, Unit 3, or until the Code Case is approved for general use by reference in Regulatory Guide 1.147. Afterthat time, TVAmust followthe conditions, ifany, specified in the regulatory guide.
Relief Request 3-ISI-6 requests relief from ASME Code,Section XI, Paragraph IWA-6220 which requires TVAto prepare reports using NtS-1, Ownefs Report for Inservice Inspections, and NIS-.2, Owner's Report forRepair or Replacements; and IWA-6230 which requires these reports to be filed with the enforcement and regulatory authorities having jurisdiction at the plant site within 90 days of the completion of the inservice inspection conducted during each refueling outage.
Pursuant to 10 CFR 50.55a(a)(3)(i), TVAproposes to implement Code Case r MV
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May 21, 1999 N-'532, Alternative Requin.ments,To Repair.and Replacement Documentation Requirements and Inservice Summary Report Pre paratron and Submission as Required by IWA-4000 and IWA-6000; Sect/on XI, Division 1, as an alternative to the applicable ASME Section XI requirements.
The staff has reviewed TVA's.proposed alternative to use Code Case N-532,
'nd h'as determined that use of the alternatives to Code requirements contained in.Code Case N-532 provide an acceptable level of quality.and safety for Browns Ferry, Unit 3. Therefore, TVA's proposed alternative, is authorized pursuant to 10 CFR 50.55a(a)(3)(i).
The use of alternatives contained in Code Case N-532 is authorized for the current interval or until the Code Case is published,in;a,future revision of Regulatory Guide 1.147. Atthat time, ifTVA intends to continue to implement the alternatives of'this Code Case, TVAis to followall provisions in Code Case N-532.with limitations issued in Regulatory Guide 1.147, ifany.
The staff's evaluation and.conclusions are contained'in Enclosure 1. Enclosure 2 is the Idaho National Engineering and Environmental Laboratory Technical Evaluation Report.
Sincerely, Original signed by:
Sheri R. Peterson, Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-296
Enclosures:
- 1. Safety Evaluation
- 2. Technical Evaluation Report cc w/enclosures:
See next page DISTRIBUTION:(Enclosures 1 and 2)
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N-5 "2, Alternative Requirements To Repair ar d Replacement Documentation Requr'rements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000;Section XI, Division 1, as an alternative to the applicable ASME Section XI requirements.
The staff.has,reviewed TVA's proposed alternative to use Code Case N-532, and has determined that use of the alternatives to Code requirements contained in Code Case N-532 provide an acceptable level of quality and safetyfor Browns Ferry, Unit 3. Therefore,
,TVA's proposed alternative is authorized pursuant to 10,CFR 50.55a(a)(3)(i).
The use of alternatives contained in Code Case N-532 is authorized for, the current interval or until the Code Case is published in a future revision of Regulatory Guide 1.147. Atthat time, ifTVA intends to continue to implement the alternatives of this Code Case, TVAis to followall provisions in Code Case N-532 with limitations issued, in Regulatory'Guide 1.147, ifany.
The staffs evaluation and conclusions are contained in Enclosure 1. Enclosure 2 is the Idaho National Engineering and Environmental Laboratory Technical Evaluation Report.
'Sincerely, P.P Sheri R. Peterson, Chief, Section 2 Project Directorate II Division of Licensing'Project Management
,Office of Nuclear Reactor Regulation Docket No. 50-296
Enclosures:
- 1. Safety Evaluation
- 2. Technical Evaluation Report cc w/enclosures:
See next page
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Mr. J. A. Scalice Tennessee Valley Authority
'BROWNS FERRY NUCLEAR'PLANT CC:
Senior Vice President Nuclear Operations Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Mark J. Burzynski, Managar Nuclear Licensing Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Jack A. Bailey, Vice President Engineering 8 Technical Services Tennessee Valley Authority 6A L'ookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Timothy E. Abney, Manager Licensing and, Industry Affairs Browns Ferry Nuclear. Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL35609 Mr. Karl'W. Singer, Site Vice President Browns Ferry Nuclear Plant Tennessee Valley.Authority P.O. Box'2000 Decatur, AL 35609 Senior Resident Inspector U.S. Nuclear Regulatory Commission Browns Feny Nuclear Plant I0833 Shaw Road Athens, AL35611 General Counsel Tennessee Valley Authority ET 10H 400 West Summit Hill Drive Knoxville, TN 37902 Mr.,N. C. Kazanas, General Manager Nuclear Assurance Tennessee Valley Authority 5M Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 State Health Officer Alabama Dept. of Public Health 434 Monroe Street Montgomery, AL36130-1701 Chairman Limestone County Commission 310 West,Washington Street Athens, AL 35611 Mr. Robert'G. Jones, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. 'Box 2000 Decatur, AL 35609
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