ML19327B112
| ML19327B112 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/16/1989 |
| From: | Hairston W GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| HL-774, NUDOCS 8910250218 | |
| Download: ML19327B112 (4) | |
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.' W. G. Hairston, lH
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Nuciear Operabons
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U.S. Nuclear Regulatory Commission W
ATTN:. Document Control Desk Washington, D.C.
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PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-32.1, 50-366 OPERATING LICENSES DPR-57, NPF-5 INSERVICE INSPECTION STATUS RELATIVE TO RHCU WELD EXAMS AND. CALIBRATION BLOCKS j
Gentlemen:
'By letter dated July 24, 1989, the NRC documented the results of i
discussions 'with Georgia Power Company (GPC) on the reactor water clean-up (RHCU)' weld intergranular stress corrosion cracking' (IGSCC) h
' examinations, and' the calibration ' blocks to be used for ultrasonic
' inspection; (UT) : activities.
The status of.both these issues is discussed below.'
RHCU Held Examt - The July 24, 1989 letter documented our agreement to examine seven. welds in the RHCU piping outside primary containment and
' discuss'the findings with the NRC staff to determine if sample expansion L
. was necessary.
Georgia Power Company had also agreed to examine the l'
welds during the early part of our' current Unit 2 outage in case additional inspections were required.
On October 2,1989, a conference l
call was held with GPC, Nuclear ~ Reactor Regulation (NRR) and i<egion II personnel participating to discuss the results of these exams.
One Region II representative had been on site during the ir.spections and participated in the exams conducted by GPC.
Georgia Power Company reported finding no reportable IGSCC indications in the seven welds examined.
Geometric indications and one weld flaw, not attributed to IGSCC, were detected and briefly discussed during the phone call.
It was L
agreed by all parties that no additional RHCU weld exams were required this outage, and no NRC approval of the exam results was required prior to Unit 2 startup.
Georgia Power Company agreed to reinspect one weld L
(weld no.11) during the next Unit 2 outage and examine 7 more welds in l-the Spring 1990 Unit 1 outage.
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Calibration Blorks - The Jely 24, 1989 NRC letter stated that GPC would modify or replace the existing calibration blocks so that blocks meeting the 1980 Section XI Cot:e, with Addenda through Hinter 1981, would be available during the Spring 1990 Unit 1 outage.
Georgia Power Company intends to comply with this request.
He are intending to apply Code Cases N-98 and N-461 (ASME Section V and ASME Section XI Appendix III) for the ' purpose of upgrading our pipe calibration blocks.
These Code Cases )rovide allowable tolerances for calibration block thickness.
Our justiflcation for use of Code Case N-98 is that it has been formally approved by the NRC and appears in Regulatory Guide 1.147.
He understand y
that Code Case N-461 has been reviewed by the NRC internally with I.
favorable results and is expected to be included in the 1990 update of i
However, it has not yet been formally approved and we are requesting your permission to apply this Code Case.
He would I
only use the Code Case "when selecting calibration blocks in accordance 1
with Section XI, Division 1. III-3410." Code Case N-461 is enclosed for L
information.
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Existing calibration blocks are being modifieJ or replaced because of r
changes made.in the 1980/ Hinter 1981 Addenda of the Section XI Code regarding block thickness, material, curvature, and reflector geometry.
Use of Code Case N-461 will allow compliance with the latest ASME position regarding permissible calibration block thickness and will permit more efficient use of existing blocks at Plant Hatch.
y He would like the NRC to formally approve use of Code Case N-461 by I
GPC.
If the staff believes there will be any problem with eventual i
- approval, please contact this office, as we are proceeding with procurement and fabrication of the calibration blocks assuming use of Code Case N-461 is acceptable.
Sincerely, i
y).b. hTW H. G. Hairston, III GKMieb
Enclosure:
ASME Boiler and Pressure Vessel Code Case N-461 c:
(See next page.)
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- y U.S.' Nuclear Regulatory Comission.
October 16, 1989 L.
Page Three c:: Georgia Power _. Company p
Mr. H. C. Nix, General Manager - Nuclear Plant Mr. J. D. Heidt, Manager Engineering and Licensing - Hatch GO-NORMS e.
U.S. Nuclear Reaulatory Comission. Washinoton. D.C.
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Mr. L. P. Crocker, Licensing Project Manager - Hatch U.S. Nuclear Regulatory Comission. Reaion II Mr. S. D. Ebneter, Regional Administrator Mr. J. E. Henning, Senior Resident Inspector - Hatch I
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CASES OF ASME BOILER AND PRESSURE VESSEL CODE il o
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Case N 461 Alternatlee Rules for Piping Calibration Block Thickness Sectica XI, Division 1 t
Inguiry: When selecting calibration blocks in accordance with Section XI, Division 1, III 3410, what alternative wall thicknesses or pipe schedules may be used?.
Reply It is the opinion of the Committee that any calibration block thickness may be used that is within 2 25% of the pipe wall thickness to be examined.
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