ML19305E015
| ML19305E015 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 04/09/1980 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Gerstner W ILLINOIS POWER CO. |
| References | |
| NUDOCS 8004220144 | |
| Download: ML19305E015 (1) | |
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UNITED STATES TIC NUCLEAR REGULATORY COMMISSION e$
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799 ROOSEVELT ROAD U
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Docket No. 50-462 Illinois Power Company ATTN:
Mr. W. C. Gerstner Executive Vice President 500 South 27th Street Decatur, IL 62525 t
Gentlemen:
The enclosed Bulletin 80-08 is forwarded to you for action. A l
written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely, N*
James G. Keppler i
V Director i
Enclosure:
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Central Files i
Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Mr. Dean Hansell, Ofiice of Assistant Attorney General o
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"I SSINS No.: 6820 t
UNITED STATES Accessions No.:
NUCLEAR REGULATORY COMMISSION 7912190650 0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 April 7, 1980 IE Bulletin No. 80-08 EXAMINATION OF CONTAINMENT LINER PENETRATION WELDS Description of Circumstances:
On March 20-23, l'-79, an NRC inspection at Nine Mile Point Unit 2, identified that certain nondestructive examinations performed on containment penetration welds did not satisfy the applicable ASME Boiler and Pressure Vessel (B&PV)
Code requirements.
The welds in question were the primary piping containment penetration flued head (integral fitting) to outer sleeve welds w.lch form a part of the containment pressure boundary. The examinations perfox'ed included ultrasonic and surface inspections of the outer surface.
Suosequent to the identification of this code problem at Nine Mile Point t,. A 2, three welds previously found to be acceptable using ultrasonics were radio-graphed and two revealed indications in excess of the code allowable.
The indications revealed by radiography were slag and lack-of-fusion.
Preliminary NRC review indicates that the probable reason the indications were not detected by ultrasonics.was due to masking from signals received from the backing bar.
As a result of these findings, a complete re-examination program at Nine Mile Point Unit 2 was initiated wherein 10 of 17 welds previously examined and found to be acceptable using ultrasonics, were re-examined by radiography before rework and found to have indications exceeding ASME Code allowables.
Additional information concerning Beaver Valley Unit 2 and North Anna 3 and 4 has also shown cases of flued head piping penetration weld defects exceeding ASME B&PV Code acceptance criteria when radiographed.
Original approved vendor procedures at Beaver Valley Unit 2 did not require volumetric examina-tion.
Radiography for information purposes disclosed the unacceptable indica-tions at North Anna 3 and 4. Specification deficiencies have also been discovered at Millstone 3 and River Bend where radiography of these welds was not required.
The ASME B&PV Code requires radiography of the sutjec', welds with specified exceptions. The licensees and their architect engineer (Stone and Webster) had specified ultrasonics as the volumetric en minatfon me+ hod because, in their judgement, radiography was impractical for the penetration geometry.
Radiography was successfully perfo med at North Anna 3 and 4 prior to the identification cf this problem and ai. Beaver.Vrlley 2 and Nine Mile Point 2 subseq::ca.t ts NRC inspections.
This enerience indicates that :-adiography was meaningful and more practical than UT ex aination of these penetration welds when backing bars are present.
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IE Bulletin No. 80-08 April 7, 1980 Page 2 of 2
.i Action to be Taken by Licensee:
For all power reactor facilities with an operating license or a construction permit:
1.;
Determine if your facility contains the flued head design for penetration
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connections, or other designs with containment boundary butt weld (s) between the penetration sleeve and process piping as illustrated in Figure NE 1120-1, Winter 1975 Addenda to the 1974 and later editions of l
the ASME B&r/ Code.
2.
If an affirmative answer is reached for Item 1, determine t.he following:
a.
Applicability of the ASME Code including year and addenda and/or Regulatory Guide 1.19, b.
Type of nondestructive examinations performed during construction, c.
Type of weld joint (including pipe material and size) and whether or not backing bars were used, d.
Results of construction nondestructive examinations, i.e., if repairs were required, this should be identified including extent of repairs and description of defects encountered dur hg repair, if known.
3.
For those facilities committed during construction to perform volumetric examination of such penetrations through SAR commitments which have not performed radiography, justify not performing radiography or submit plans and schedules for performing radiographic examinations.
Within 90 days of the date of this Bulletin, facilities with an operating license or a construction permit shall submit the information requested in Items 1, 2, and 3 of this Bulletin.
Reports shall be submitted to the Regional Director with a copy to the Director, Division of Reactor Construction Inspection, Washington, D. C.
20555.
Approved by GA1, B180225 (R0072); clearance expires 7-31-80.
Approval was given under a blanket clearance specifically for identified generic problems.
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h IE Bulletin No. 80-08 Enclosure April 7, 1980
,g RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To f,
No.
i 80-07 BWR Jet Pump Assembly 4/4/80 All GE BWR-3 and Failure BWR-4 facilities with an OL 80-06 Engineered Safety Feature 3/13/80 All power reactor (ESF) Reset Controls facilities with an OL 80-05 Vacuum Condition Resulting 3/10/80 All PWR power reactor In Damage To Chemical Volume facilities holding Control System (CVCS) Holdup OLs and to those with Tanks a CP 79-01B Environmental Qualification 2/29/80 All power reactor of Class IE Equipment facilities with an OL 80-04 Analysis of a PWR Main 2/8/80 All PWR reactor facilities Steam Line Break With holding OLs and to those Continued Feedwater nearing licensing Addition 80-03 Loss of Charcoal From 2/6/80 All holders of Power Standard Type II, 2 Inch, Reactor OLs and cps Tray Adsorber Cells 80-02 Inadequate Quality 1/21/80 All BWR licenses with Assurance for Nuclear a CP or OL 80-01 Operability of ADS Valve 1/11/80 All eWR power reactor Pneumatic Supply facilities with and OL 79-01B Environmental Qualification 1/14/80 All power reactor of Class IE Equipment facilities with an OL 79-28 Possible Malfunction of 12/7/79 All power reactor Namco Model EA 180 Limit facilities with an Switches at Elevated OL or a CP Temperatures
.