ML18139A158
| ML18139A158 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 04/07/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Ferguson J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 8004180401 | |
| Download: ML18139A158 (5) | |
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In Reply Refer To:
RII:JPO 50-338, 50-339 50-4~ 50-405 EzC50-29 e
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 APR 7 1980 Virginia Electric and Power Company Attn:
J. H. Ferguson Executive Vice President-Power P. o. Box 26666 Richmond, Virginia Gentlemen:
23261 The enclosed Bulletin 80-08 is forwarded to you for action.
A written response is required. If you desire additional information regarding this matter, please contact this office.
Enclosures:
- 1.
- 2.
Listing of IE Bulletins Recently Issued Sincerely,
~-,-~
James P. O'Reilly Director
,*/(.-.*/
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Virginia Electric and Power Company cc w/encl:
e W.R. Cartwright,-Station Manager Post Office Box 402 Mineral, Virginia 23117 P. G. Perry Senior Res_ident Engineer Post Office Box 38
APR 7 1980 _.,.
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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 April 7, 1980 SSINS No.: 6820 Accessions No. :
7912190650 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 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 uitrasonics 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.
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e IE Bulletin No. 80-08 Action to be Taken by Licensee:
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 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.
IE Bulletin No. 80-08 April 07, 1980 Bulletin No.
80;.08 80-07 79-03A 80-06 80-05 79-0lB 80-04 80-03 80-02 80-01 79-0lB 79-28 RECENTLY ISSUED IE BULLETINS Subject Date Issued Examination of Containment 4/7/80 Liner Penetration Welds BWR Jet Pump Assembly 4/4/80 Longitudinal Weld Defects 4/4/80 In ASME SA-312 Type 304 Stainless Steel Pipe Engineered Safety Feature 3/13/80 (ESF) Reset Controls Vacuum Condition Resulting 3/10/80 In Damage To Chemical Volume Control System (CVCS) Holdup Tanks Environmental Qualification 2/29/80 of Class IE Equipment Analysis of a PWR Main
- 2/8/80 Steam Line Break With Continued Feedwater Addition Loss of Charcoal From 2/6/80 Standard Type II, 2 Inch, Tray Adsorber Cells Inadequate Quality 1/21/80 Assurance for Nuclear Operability of ADS Valve 1/11/80 Pneumatic Supply Environmental Qualification 1/14/80 of Class IE Equipment Possible Malfunction of 12/7/79 Namco Model EA 180 Limit Switches at Elevated Temperatures Enclosure Issued To All power reactors facilities with a CP or OL GE BWR facilities with a CP and GE BWR-3 and BWR-4 facilities with an OL.
All power reactor facilities with an OL or CP
. All power reactor facilities with an OL All PWR power reactor facilities holding OLs and to those with a CP All power reactor facilities with an 01 All PWR reactor facilities holding OLs and to those nearing licensing All holders of Power*.
Reactor OLs and *cPs All BWR licenses with a CP or 01 All BWR power reactor facilities with and 01 All power reactor facilities with an 01 All power r~actor facilities with an 01 or a CP