ML20064C060
| ML20064C060 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/09/1982 |
| From: | Kammer D TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-SSINS-6820 IEB-82-03, IEB-82-3, NUDOCS 8301040298 | |
| Download: ML20064C060 (4) | |
Text
o TENNESSEE VALLEY AUTHQRITY.
CH ATTANC,0GA. TENT.ESSEE 3'7401 400 Chestnat Street Tower II
., 0 : f' 15 ni0 53 December 9, 1982 (y '26s U.S. Nuclear Regulatory Commission Region II (3 v]/,
ATTN: James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
OIE BULLETIN 82 STRESS CORROSION CRACKING IN THICK WALL, LARGE DIAMETER, STAINLESS STEEL, RECIRCULATION SYSTEM PIPING AT BWR PLANTS - BROWNS FERRY NUCLEAR PLANT Enclosed is our response to IE Bulletin 82-03 item Nos. 4a, 4b, and 4c for the Browns Ferry Nuclear Plant. Extension of the response beyond the bulletin submittal deadline of December 1, 1982 was discussed with your staff as documented in L. M. Mills' letter to you dated December 3, 1982. If you have any questions, please call Jim Domer at FTS 858-2725.
To be best of my knowledge, I declare the statements contained herein are complete and true.
Very truly yours, TENNESSEE VALLEY AUTHORITY D5 W D. S. Kammer Nuclear Engineer Enclosure c.301040298 921209 PDR ADOCK 05000259 O
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ENCLOSURE RESPONSE TO IE BULLETIN 82-03 ITEM NCS. 4a, 4b, AND 4c BROWNS FERRY NUCLEAR PLANT 4.a.1 The isometric drawing for the unit 2 recirculation piping system at Browns Ferry is shown in Attachment 1.
There were 27 recirculation j
system welds examined in response to IE Bulletin 82-03 Recirculation System Welds Examined Weld No.
Size SRI N1A (safe end) 28" 1.31 KR-2-17 12" 2.09 N1B (safe end) 28" 1.31 GR-2-14 12" 1.52 GR-2-27 28" 0.87,
KR-2-18 12" 2.39 KR-2-24 28" 1.04' GR-2-41 12" 1.93 GR-2-53 28" 1.11 GR-2-42 12" 1.72 GR-2-18 22" 1.07 KR-2-40 12" 2.42 KR-2-45 28" 1.44 GR-2-43 12" 1.71 KR-2-51 28" 1.08 GR-2-38 12" 2.76 GR-2-54 28" 1.17 GR-2-4 4"
N/A GR-2-51 22" 0.92 GR-2-33 4"
N/A GR-2-12 12" 2.81 KR-2-37 22" N/A GR-2-13 12" 1.60 KR-2-15 22" N/A N2C (safe end) 12" 1.71 GR-2-52 22" 0.98 N2G (safe end) 12" 1.52 4.a.2 Stress rule index was the basis for selection of N1A, N1B, N2C, and N2G safe end welds, weld KR-2-45, cnd the ten 12-inch recirculation riser welds. The selection of welds KR-2-37 and GR-2-52 was at the request of NRC inspector, Jim Coley. The selection of weld KR-2-15 was based on previous examination findings at other nuclear facilities. The remaining welds consist of those welds previously examined this outage in accordance with the ASME Section XI in-service inspection program. The 12-inch recirculation riser and four-inch bypass stub tube welds were examined because of managemenc's concern that they be examined during this outage. They are not part of the IF.Bulletin 82-03 required examination.
4.a.3 The piping materials are listed below:
Min.
Size Wall Material 28" 1.088" A358 Class 1 from plate mt'l. A-240 TP 304 22" 1.088" A358 Class 1 from plate mt'l. A-240 TP 304 12"
.569" A358 Class 1 from plate mt'l. A-240 TP 304 4"
337" A376 TP 304
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4.a.4 The occupational radiation exposure incurred by the examination team as a result of IE Bulletin 82-03 was 6 rem. The precautions taken to minimize radiation exposure were a radiation survey of the area to be worked in, radiation " hot spots" noted for the examiner's information, and/or a portable radiation monitor may be required if there are several hazardous radiation areas in the proximity.
In addition, a slave unit was used for weld examinations to enable part of the examination team to remain outside the drywell.
4.b Examinations were conducted using the following techniques and equipment:
1.
Ultrasonic Instrument - Nortec 131D 2.
Transducer - Harisonic Dual Element, 1.5 MHz, 450 shear wave 3
Calibration Blocks - flat blocks, A240 mater'al, 1 inch and 1.25 i
inch nominal thickness 4.
Reference Reflector percent nominal thickness square notches (Sawtoor")
5.
Calibration Range - 2 full VEE-paths 6.
Reference Sensitivity - first ID notch set to 80 percent of full screen height.
7.
Scanning Sensitivity - 2x (6db) 8.
Evaluation Sensitivity - essentially 2x because procedure requires recording of all nongeometric reflectors regardless of amplitude 9
Recording Criteria - all nongeometric reflectors, all geometric reflectors greater than 50 percent of the distance amplitude correction curve at reference sensitivity 4.c No previous examinations were conducted using the validated methodology.
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