ML20128N334
| ML20128N334 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/18/1993 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | Medford M TENNESSEE VALLEY AUTHORITY |
| References | |
| GL-88-01, GL-88-1, GL-89-10, TAC-M85070, TAC-M85071, TAC-M85072, NUDOCS 9302230209 | |
| Download: ML20128N334 (3) | |
Text
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'o UNITED STATES
~g NUCLEAR REGULATORY COMMISSION n
f WASHINGTON, D. C. 20555
\\.,,, #,e February 18, 1903 Docket Nos. 50-259, 50-260 and 50-296 Tennessee Valley Authority ATTN: Dr. Mark 0. Medford, Vice President Nuclear Assurance, Licensing and Fuels 3B Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
Dear Dr. Medford:
SUBJECT:
ALTERNATIVE INSERVICE INSPECTION METHODS FOR THE REACTOR WATER CLEANUP AND RESIDUAL HEAT REMOVAL SYSTEMS - BROWNS FERRY (TAC N05. M85070, M85071, AND M85072)
By letter dated November 25, 1992, the Tennessee Valley Authority (TVA) requested NRC concurrence to employ alternative methods for the inservice l
inspection of piping welds in the reactor water cleanup (RWCU) and residual j
i heat removal (RHP) systems required by Generic letter (GL) 88-01 "NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping."
TVA has proposed to delete all RWCU piping welds outboard of the containment isolation valves from the GL 88-01 inspection program.
This proposal is based on TVA's commitment to replace all RWCU piping outside the drywell with piping resistan+ to IGSCC. TVA will replace this piping for Units 1 and 3 before restart d for Unit 2 during the current Cycle 6 refueling outage scheduled to fini; oy June of 1993.
Furthermore, TVA is also planning to implement the recommended actions of GL 89-10, " Safety-related Motor-operated Valve Testing and Surveillance."
Once the RWCU piping is replaced with IGSCC resistant material, the staff agrees that IGSCC inspections of RWCU welds outside of the containment isolation valves (non-Code class) are not necessary assuming the actions of GL 89-10 for applicable motor-operated valves are satisfactorily complete.
Presently, each of two RHR return penetrations (assemblies X-13A and X-13B) for Units 1, 2, and 3, contain an inaccessible weld within the scope of GL 88-01.
By letter dated August 1, 1988, TVA had committed to remove these welds or apply local leak aetection.
GL 88-01 provides the following staff position regarding the inspection of inaccessible welds:
Welds that are not UT [ ultrasonic test] inspectable should be replaced, " sleeved", or local leak detection applied.
RT [ radiographic test] examination or visual inspection for leakage may also be considered.
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i Dr. Mark 0. Medford ;
TVA has now decided co revise its previous commitment by proposing to conduct only visual inspections of the aferementioned inaccessibic welds for leakage.
These welds are classified as IGSCC susceptible Category G.
They are part of the RHR system process piping located in a sleeved guard pipe.
The staff reviewed TVA's procedure for leak testing these welds.
TVA will perform a system leakage test each refueling outage in accordance with Section XI of the ASME Code; this includes notifying the Authorized Inspection Agency or Authorized Nuclear Inservice Inspector (ANII) before testing.
Insulation between the guard pipe and process pipe will be removed to aid visual inspection. The RHR process pipe will be pressurized to greater than 500 psig while conducting system walkdowns and allowing test parameters to stabilize.
Process piping pressure will then be increased to a minimum of 1005 psig (normal reactor operating pressure). Qualified quality control inspectors will visually inspect the RHR process piping, in particular the subject inaccessible welds, for evidence of leakage. Any leaking areas will be evaluated for repair or replacement.
Furthermore, the ANII will review and approve the final data package.
Based on these conditions, the NRC staff agrees that TVA's proposed visual inspections are in compliance with the staff positions promulgated by GL 88-01.
If there are any questions regarding this letter, please contact the NRC project manager, Thierry M. Ross at (301) 504-1474.
Sincerely, Original signed by Frederick J. Hebdon, Project Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc:
See next page Distribution Docket: File NRC & Local PDR BFN Rdg. File S. Varga 14-E-4 G. Lainas 14-H-I F. Hebdon J. Williams
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Mr. John B. Waters, Director Claude Earl Fox, M.D.
Tennessee Valley Authority State Health Officer ET 12A
-State Dept. of Public Health 400 West Summit Hill Drive State Office Building Knoxville, Tennessee 37902 Montgomery, Alabama 36130 Mr. J. R. Bynum, Vice President Regional Administrator Nuclear Operations U.S.N.R.C. Region II j
3B Lookout Place 101 Marietta Street, N.W.
i 1101 Market Street Suite 2900 i
Chattanooga, Tennessee 37402-2801 Atlanta, Georgia 30323 Mr. Charles Patterson Mr. R. R. Baron, Site Licensing Manager Senior Resident Inspector i
Browns Ferry Nuclear 'ilant Browns Ferry Nuclear Plant Tennessee Valley Authority U.S.N.R.C.
j P.O. Box 2000 Route-12, Box 637 j
Decatur, Alabama 35602 Athens, Alabama 35611 q
Mr. O. J. Zeringue, Vice President i
Browns Ferry Nuclear Plant Tennessee Valley Authority j
P.O. Box 2000-l Decatur, Alabama 35602 Mr. M. J. Burzynski, Manager i
Nuclear Licensing and Regulatory Affairs
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5B Lookout Place Chattanooga, Tennessee 37402-2801-l TVA Representative Tennessee Valley Authority e
11921.Rockville Pike Suite 402 Rockville, Maryland 20852 i
General Counsel 4
-Tennessee. Valley Authority ET 11H 400 West Summit Hill Drive
-Knoxville,-Tennessee 37902 s
Chairman, Limestone County Commist. ion
- i P.O. Box 188
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Athens, Alabama 35611-i I
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