ML18082A194
| ML18082A194 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/07/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Schneider F Public Service Enterprise Group |
| References | |
| NUDOCS 8004180280 | |
| Download: ML18082A194 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406 Docket No. ~0-272 Public Service Electric and Gas Company ATTN:
Mr. F. W. Schneider Vice President - Production 80 Park Place Newark, New Jersey 07101 Gentlemen:
April 7, 1980 The enc*1 osed IE Bulletin No. 80-08, 11 Examination of Containment Li rier Penetra-tion Welds, 11 is forwarded to you for action.
A written response is required.
.If you desire additional i_nformation regarding this matter, please contact this office.*
- Sincerely,
~~/k-k Boyce H. Grier
{!-. Di rector*
Enclosures:
- 1.
- 2.
List of Recently Issued IE Bulletins*
CONTACT:
L. E. Tripp (215-337-5282) cc w/encls:
F.. P. Librizzi, General.Manager - Electric Production E. N. Schwalje, Manager - Quality Assurance R. L. Mittl, General Manager - Licensing and Environment H. J. Midura, Manager ** Sa 1 em Generating Sta ti on
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ENCLOSUR.E 1
'UN !TED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENt WASHI.NGTON, D. C.
20555 SSINS No.: 6820 Accessions No.:
7912190650 EXAMINATION OF CONTAINMENT LINER PENETRATION WELDS Description of Circumstances:
IE Bulletin No. 80-08 Date:
April 7, 1980 Page 1 of *2 On March 20*23, 1979, an NRC inspection at Nine Mile Point Unit 2, identified that certain nondestructive exami.nations 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 (fotegral fitting) to outer sleeve welds which form a*.
part of the co.ntai nment 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 info)'.'mation concerning Beaver Val.ley 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 i-nformation purposes disclosed the unacceptable indica-
. tions at North Anna 3 and 4. Specification defici~ncies 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 l.
_.Action to be Taken by Licensee:
IE Bulletin No. 80-08 Date:
April 7, 1980 Page 2 of 2 For all power reactor facilities with an operating license or a construction permit:
- 1. _. Determine if your facility contains the fl ued head design for penetration connections, or,other designs with containment boundary butt weld(s) between the penetration sleeve and process piping as illustrated in
- 2.
If an affirmative answer is reached for Item 1, determine the foll.owing:
- 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 volumetri,c 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 llcense 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, 8180225 (R0072); clearance expires 7-31-80.
Approval was given under a blanket clearance specifically for identified generic problems.
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Bulletin No.
. 80-01 80-02.
80-03.
80-04 79-018 80-05 80-06 79-03A 80-07
.ENCLOSURE 2 RECENTLY ISSUED IE BULLETINS Subject Oate Issued.
Operability of ADS Valve 1/14/80 Pneumatic Supply Inadequate Quality Assurance.for Nuclear
.*Supplied Equipment 1/21/80 Loss of Charcoal From 2/6/80 Standard Type *u, *2 Inch, Tray Adsorber Cells Analysis of a PWR Main 2/8/80 Steam Line Break with Continued Feedwater Ad-
.dition Environmental Qual i'-
2/29/80 fication of Class IE Equipment Vacuum.. tondi ti ons 3/10/80 Resulting in Damage to Chemical Volume Control System (CVCS).Holdup Tanks Engineered Safety 3/13/80 Feature (ESF) Reset Controls Longitudinal Weld 4/4/80 Defects in ASME SA-312, Type 304 Stainless Steel Pipe BWR.Jet Pump Assembly*
4/4/80 Failure IE Bulletin No. 80:.:.(fr~,..
Date: April 7, 1980 Page 1 of 1.
Issued To All BWRs with an Operating License (OL)
All BWRs with an OL or Const.ructio.n Permit (CP)
All Power Reactor Facilities with an OL or CP All Power Reactor Facilities with an OL or CP All Power Reactors with an OL except SEP Plants All PWR Power Reactor Faci 1 iti es with an OL or CP All Power Reactor Facilities with an OL (For Action)
All Power Reactor Facilities with a CP (For Information)
All Power Reactor Facilities with an OL or CP BWR 3 & 4 1 s with OL (For Action)