ML19305D993
| ML19305D993 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/09/1980 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Hines E DETROIT EDISON CO. |
| References | |
| NUDOCS 8004220100 | |
| Download: ML19305D993 (1) | |
Text
- pa ucoq'o 4
UNITED STATES 8" "qf('o NUCLEAR REGULATORY COMMISSION E
REGION 111 3
o,
[
799 ROOSEVELT ROAD b
GLEN ELLYN,ILLINOls 60137 o
&9 Docket No. 50-341 The Detroit Edison Company ATTN:
Mr. Edward Hines, Assistant Vice President and Manager i
Quality Assurance 2000 Second Avenue Detroit, MI 48226 Gentlemen:
The enclosed Bulletin 80-08 is Corwarded to you for action. A written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely, k oRw/
ames G. Keppler Director
Enclosure:
IE Bulletin No. 80-08 cc: w/ enc 1:
i Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Ronald Callen, Michigan Public Service Commission Eugene B. Thomas, Jr.,
Attorney 6
l l
l I
8004220/00
i i
t SSINS No.: 6820 UNITED STATES Accessions No.:
NUCLEAR REGULATORY COMMISSION 7912190650 OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 April 7, 1980 I
IE Bulletin No. 80-08 EXAMINATION OF CONTAINMENT LINER PENETRATION WELDS Description of Circumstances:
On March 20-23, 1979, an NRC inspection at Nine Mile Point Unit 2, identified that certain nondestructive examinations performed on containmeht 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 which form a part of the containment pressure boundary. The examinations performed included ultrasonic and surface inspections of the outer surface.
Subsequent to the identification of this code problem at Nine Mile Point Unit 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.
5 ACditional 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.
Radicgraphy 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.
i The ASME B&PV Code requires radiography of the subject welds with specified exceptions. The licensees and their architect engineer (Stone and Webster) had specified ultrasonics as the volumetric examination method because, in their judgement, radiography was impractical for the penetration geometry.
Radiography was successfully performed at North Anna 3 and 4 prior to the identification of this problem and at Beaver. Valley 2 and Nine Mile Point 2 subsequent to NRC inspections.
This experience indicates that radiography was meaningful and more practical than UT examination of these penetration welds when backing bars are present.
~
- -. l _..-.J-..
IE Bulletin No. 80-08 April 7, 1980 g
Page 2 of 2 Action to be Taken by Licensee:
For all power reactor facilities with an operating license or a co'nstruction permit:
1.
Determine if your facility contains the flued head design for penetration l
connections, or other designs with containment boundary butt weld (s) between the penetration sleeve and process piping as illustrated in 1
Figure NE 1120-1, Winter 1975 Addenda to the 1974 and later editions of the ASME B&r7 Code.
2.
If an affirmative answer is reached for Item 1, determine the following:
a.
Applicability of the ASME Code including year and addenda and/or i
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 during 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 j
Director, Division of Reactor Construction Inspection, Washington, D. C.
20555.
i Approved by GAO, B180225 (R0072); clearance expires 7-31-80.
Approval was given under a ble.nket clearance specifically for identified generic problems.
]
i i
-~ -.. :...
}
f IE Bulletin No. 8r-08 Enclosure April 7, 1980
.g RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
80-07 BWR Jet Pump Assembly 4/4/80 All GE BWR-3 and Failure BWR-4 facilities with an t 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 BWR 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 e
,