NRC Generic Letter 1980-28
| ML031350348 | |
| Person / Time | |
|---|---|
| Issue date: | 04/07/1980 |
| From: | Grier B NRC Region 1 |
| To: | |
| References | |
| BL-80-008 GL-80-028, NUDOCS 8004180125 | |
| Download: ML031350348 (4) | |
4. J
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION I
631 PARK AVENUE
KING OF PRUSSIA, PENNSYLVANIA 1940
5L
O ?
An A-
Docket Nos. 50-03 April 7, 1980
50-247 Consolidated Edison Company of New York, Inc.
ATTN: Mr. W. J. Cahill, Jr.
Vice President
4 Irving Place New York, New York 10003 Gentlemen:
The enclosed IE Bulletin No. 80-08, "Examination of Containment Liner Penetra- tion Welds," is forwarded to you for action. A written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely,
6J Boyce H. Grier Director Enclosures:
1. IE Bulletin No. 80-08
2. List of Recently Issued IE Bulletins
CONTACT
- L. E. Tripp
(215-337-5282)
cc w/encls:
L. 0. Brooks, Project Manager, IP Nuclear W. Monti, Manager - Nuclear Power Generation Department M. Shatkouski, Plant Manager J. M. Makepeace, Director, Technical Engineering W. D. Hamlin, Assistant to Resident Manager J. D. Block, Esquire, Executive Vice President - Administration Joyce P. Davis, Esquire / !
8004180
I
ENCLOSURE 1 SSINS No.: 6820
UNITED STATES Accessions No.:
NUCLEAR REGULATORY COMMISSION 7912190650
OFFICE OF INSPECTION AND ENFORCEMENt WASHINGTON, D.C. 20555 IE Bulletin No. 80-08 Date: April 7, 1980 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 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 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.
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 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.
Enclosure 1 IE Bulletin No. 80-08 Date: April 7, 1980 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 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 the ASME B&PV 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 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 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 Director, Division of Reactor Construction Inspection, Washington, D. C. 20555.
Approved by GAO, B180225 (R0072); clearance expires 7-31-80. Approval was given under a blanket clearance specifically for identified generic problems.
- -
ENCLOSURE 2 IE Bulletin No. 8no_0R
Date: April 7, 1980 RECENTLY ISSUED IE BULLETINS
Bulletin Subject Date Issued Issued To No.
80-01 Operability of ADS Valve 1/14/80 All BWRs with an Pneumatic Supply Operating License (OL)
80-02 Inadequate Quality V/21/80 All BWRs with an Assurance for Nuclear OL or Construction Supplied Equipment Permit (CP)
80-03 Loss of Charcoal From 2/6/80 All Power Reactor Standard Type II, 2 Inch, Facilities with an Tray Adsorber Cells OL or CP
80-04 Analysis of a PWR Main 2/8/80 All Power Reactor Steam Line Break with Facilities with an Continued Feedwater Ad- OL or CP
dition
79-O1B Environmental Quali- 2/29/80 All Power Reactors fication of Class IE with an OL except Equipment SEP Plants
80-05 Vacuum Conditions 3/10/80 All PWR Power Reactor Resulting in Damage to Facilities with an Chemical Volume Control OL or CP
System (CVCS) Holdup Tanks
80-06 Engineered Safety 3/13/80 All Power Reactor Feature (ESF) Reset Facilities with an Controls OL (For Action)
All Power Reactor Facilities with a CP
(For Information)79-03A Longitudinal Weld 4/4/80 All Power Reactor Defects in ASME Facilities with an SA-312, Type 304 OL or CP
Stainless Steel Pipe
80-07 BWR Jet Pump Assembly 4/4/80 BWR 3 & 4's with OL
Failure (For Action)