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Gentlemen:
The enclosed Bulletin No. 82-01, " Alteration of Radiographs of Welds in Piping Subassemblies", is forwarded to you for information.
No written response is required.
If there are any questions related to the applicability of this bulletin please contact this office.
Sincerely, i
I c\\
- 2. - 'T qw Ro ald
. Haynes
/J Re ional Administrator
Enclosure:
IE Bulletin No. 82-01 with 2 ttachments CONTACT:
S. D. Ebneter (215) 337-5283 00$KOhhh
s LIST OF HOLDERS OF NUCLEAR POWER REACTOR OPERATING LICENSES AND CONSTRUCTION PERMITS RECEIVING IE BULLETIN NO. 82-01 (FOR INFORMATION)
Baltimore Gas and Electric Company Docket Nos. 50-317 ATTN:
Mr. A. E. Lundvall, Jr.
50-318 Vice President, Supply P. O. Box 1475 Baltimore, Maryland 21203 Boston Edison Company M/C Nuclear Docket No. 50-293 ATTN: Mr. William D. Harrington Senior Vice President, Nuclear 800 Boylston Street Boston, Massachusetts 02199 Connecticut Yankee Atomic Power Company Docket No. 50-213 ATTN: Mr. W. G. Counsil Senior Vice President - Nuclear Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Consolidated Edison Company of Docket Nos. 50-03 New York, Inc.
50-247 ATTN:
Mr. John O'Toole Vice President - Nuclear Engineering and Quality Assurance 4 Irving Place New York, New York 10003 Duquesne Light Company Docket No. 50-334 i
ATTN:
Mr. J. J. Carey Vice President l
Nuclear Division R. O. Box 4 Shippingport, Pennsylvania 15077 GPU Nuclear Corporation Docket No. 50-219 ATTN:
Mr. P. B. Fiedler Vice President and Director j
Oyster Creek Nuclear Generating Station P. O. Box 388 Forked River, NJ 08731
i 2
Maine Yankee Atomic Power Company Docket No. 50-309 l
ATTN: John H. Garrity Senior Director Nuclear Engineering and Licensing 83 Edison Drive Augusta, Maine 04336 GPU Nuclear Corporation Docket No. 50-289 ATTN:
Mr. H. D. Hukill Vice President and Director of TMI-l P. O. Box 480 Middletown, Pennsylvania 17057 GPU Nuclear Corporation Docket No. 50-320 ATTN:
Mr. J. J. Barton 4
Acting Vice President and Director of TMI-2 i
P. O. Box 480 Middletown, Pennsylvania 17057 Niagara Mohawk Power Corporation Docket No. 50-220 ATTN:
Mr. T. E. Lempges Vice President Nuclear Generation t
300 Erie Boulevard West Syracuse, New York 13202 Northeast Nuclear Energy Company Docket Nos. 50-336 ATTN:
Mr. W. G. Counsil 50-245 Senior Vice President - Nuclear 50-423 Engineering and Operations Group l
P. O. Box 270 Hartford, Connecticut 06101 i
Philadelphia Electric Company Docket Nos. 50-277
.i ATTN:
Mr. S. L. Daltroff 50-278 Vice President Electric Production i
2301 Market Street
+
Philadelphia, Pennsylvania 19101 l
Power Authority of the State of New York Docket No. 50-286 Indian Point 3 Nuclear Power Plant ATTN:
Mr. J. C. Brons Resident Manager P. O. Box 215 Buchanan, New York 10511 i
s' 3
t Power Authority of the State of New York Docket No. 50-333 James A. FitzPatrick Nuclear Power Plant ATTN: Mr. Corbin A. McNeill, Jr.
Resident Manager P. O. Box 41 Lycoming, New York 13093 Public Service Electric and Gas Company Docket Nos. 50-272 ATTN: Mr. Richard A. Uderitz 50-311 Vice President - Nuclear Mail Code T15A P. O. Box 570 l
Newark, New Jersey 07101 2
Rochester Gas and Electric Corporation Docket No. 50-244 ATTN:
Mr. John E. Maier Vice President Electric and Steam Production 89 East Avenue Rochester, New York 14649 Vermont Yankee Nuclear Power Corporation Docket No. 50-271 ATTN: Mr. Robert L. Smith Licensing Engineer 1671 Worcester Road Framingham, Massachusetts 01701 Yankee Atomic Electric Company Docket No. 50-29 ATTN:
Mr. James A. Kay Senior Engineer-Licensing 1671 Worcester Road Framingham, Massachusetts 01701 Duquesne Light Company Docket No. 50-412 ATTN:
Mr. E. J. Woolever Vice President Nuclear Construction Robinson Plaza Building No. 2 i
Suite #210, PA Route 60 Pittsburgh, Pennsylvania 15205 Jersey Central Power & Light Company Docket No. 50-363 ATTN: Mr. J. T. Carroll Acting Director Oyster Creek Nuclear Generating Station P. O. Box 388 Forked River, New Jersey 08731 4
l
4 Pennsylvania Power & Light Company Docket Nos. 50-387 ATTN:
Mr. Norman W. Curtis 50-388 Vice President Engineering and Construction - Nuclear 2 North Ninth Street Allentown, Pennsylvania 18101 Public Service Company of New Hampshire Docket Nos. 50-443 ATTN:
Mr. W. C. Tallman 50-444 Chairman and Chief Executive Officer 1000 Elm Street Manchester, New Hampshire 03105
LIST OF HOLDERS OF NUCLEAR POWER REACTOR CONSTRUCTION PERMITS RECEIVING IE BULLETIN NO. 82-01 (FOR ACTION)
Long Island Lighting Ccmpany Docket No. 50-322 ATTN:
Mr. M. S. Pollock Vice President - Nuclear 175 East Old Country Road Hicksville, New York 11801 Niagara Mohawk Power Corporation Docket No. 50-410 ATTN:
Mr. G. K. Rhode Vice President System Project Management c/o Miss Catherine R. Seibert 300 Erie Boulevard, West Syracuse, NY 13202 Philadelphia Electric Company Docket Nos. 50-352 ATTN:
Mr. John S. Kemper 50-353 Vice President Engineering and Research 2301 Market Street j
Philadelphia, Pennsylvania 19101 Public Service Electric & Gas Company Docket Nos. 50-354 ATTN:
Mr. T. J. Martin 50-355 Vice President Engineering and Construction l
80 Park Plaza - 17C l
Newark, New Jersey 07101 i
DE3IGNATED ORIGINAI,
,'9 /k Cortifica By N
g D
SSINS No.:
6820 Accession No.:
RECEIVED 9
8202040 10 p-OMB No.:
3150-0084 APR 141982>
Expiration Date:
3/31/83 nugegrf
~g IEB 82-01 TIDC
//
UNITED STATES e%
NUCLEAR REGULATORY COMMISSION N
OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 March 31, 1982 IE BULLETIN NO. 82-01: ALTERATION OF RADIOGRAPHS OF WELOS IN PIPING SUBASSEMBLIES Description of Circumstances:
On October 19, 1981, the U.S. Nuclear Regulatory Commission (NRC) was notified by Washington Public Power Supply System (WPPSS) that alterations were found in certain radiographs of 21 shop welds in piping subassemblies supplied to their WPPSS-3 by Associated Piping and Engineering Corporation (AP&E) of Compton, California.
Further examination of essentially all AP&E radio-graphs previously sent to the site revealed alterations on 14 additional radiographs associated with eight welds in quality Class I stainless steel piping of less than 1-inch wall thickness.
All affected 29 welds in the thin-5 wall piping were reexamined radiographically in accordance with the ASME Code.
No evidence of unacceptable weld quality was identified.
The alterations consisted of artificial enhancement of the ASME Code specified penetrameter 4T-Hole image.
This was apparently accomplished in one of three ways:
(1) touchup with a soft lead pencil, (2) scribed or scratched with a sharp object, or (3) indention with a sharp object.
These forms of enhancement are very difficult to detect by normal film interpretation techniques (i.e., subdued background lighting).
However, utilizing direct overhead lighting, the alterations may be detected by close inspection of the film surface reflections as the film is being manipulated by the observer at various oblique angles.
After this finding, an investigation was made at AP&E by the NRC Region IV staff on December 7-11, 1981.
The results of the investigation were reviewed at the Region IV headquarters and determined to be potentially generic.
On January 29, 1982, the specific plants potentially affected were identified by the regional office.
The investigation and review established the following:
1.
Radiographs were altered on occasion by one Level II interpretor over a period of approximately eight years prior to the date of this investi-gation.
2.
The alterations were limited to the set of radiographs of welds submitted for custcmer review and approval.
hIk
IEB 82-01 March 31, 1982 Page 2 of 3 3.
The alterations involved welds associated with pipe wall thickness of less than h-inch that used isotope radiography techniques and a number 10 or 12 penetrameter.
4.
Radiograph sets retained in AP&E file for WPPSS Unit 2 contained unaltered radiographs that did not exhibit the Code-required 2-4T penetrameter sensitivity.
5.
A number of nuclear plant sites receiving fabricated piping assemblies from AP&E may have similar discrepancies.
The affected sites are listed in Table 1.
ASME Section III Code Rules, Articles NB-5000 and NC-5000, requires that weld quality acceptance of Class 1 and 2 piping be evaluated on the basis of radio-graphy.
In radiography examination, meaningful interpretation of weld quality is dependent on the use of a radiographic technique of sufficient sensitivity as shown by the penetrameter image indicators on the film.
The adequacy of technique sensitivity is confirmed by the ability to visibly discern the appropriate T-hole images of the penetrameter when evaluating the radiographs for weld quality in accordance with the governing Code rules.
Radiographs that have had penetrameter image quality indicators artificially enhanced by the discussed methods violate the intent of ASME Code requirements.
Accordingly, the following actions are necessary to independently reverify that the examined welds of the subassemblies fabricated by AP&E are acceptable for plant service.
Action To Be Taken by Applicants for an Operating License and Holders of Active Construction Permits (Group 1, Table 1):
1.
Determine on the basis of a 100 percent review of radiograph sets representing the shop fabricated quality Class 1&2 subassemblies provided by AP&E, whether the applicable ASME Code penetrameter sensitivity (2-2T or 2-4T as required) is unaltered, and clearly discernible, and that acceptable weld quality is demonstrated.
2.
In those cases where the specified penetrameter sensitivity is not discernible or is apparently enhanced in any manner, as by the methods discussed, weld quality interpretation may be based on the equivalent or higher penetrameter sensitivity discernible on the film sets.
For example, for those radiograph sets for which the required 2-4T penetra-meter sensitivity is not discernible, or found artificially enhanced on visual inspection, film interpretation of weld quality may be based on the presence of discernible 2-2T or 2-1T sensitivity exhibited by the radiographs.
3.
Where conformance with Items 1 and 2 cannot be satisfied, appropriate steps shall be taken to ensure the acceptability of the affected welds in accordance with the applicable ASME Section III Code requirements in effect for plant construction.
IEB 82-01 March 31, 1982 Page 3 of 3 4.
The above actions are to be completed prior to issuance of an OL or within 90 days of receipt of this bulletin, whichever occurs first. All quality assurance records reflecting the review findings and disposition of discrepancies identified shall be maintained and available for NRC review.
5.
A written report describing the findings and corrective actions taken, signed under oath or affirmation under provisions of Section 182a, Atomic Energy Act of 1954, shall be submitted within 30 days after completion of Items 1 through 4 to the Regional Administrator of the appropriate NRC Regional Office. A copy of the report is to be forwarded to the Director, Office of Inspection and Enforcement, NRC, Washington, D.C.
20555.
Actions To Be Taken by Applicants for Construction Permits or Utilities Whose Construction Permits Are Suspended or Delayed (3roup 2; Table 1):
No action required except as noted in Item 2, below.
1.
For information only.
2.
In the event reactivation of construction or transfer, sale, or other consignment of the subject piping subassemblies to another nuclear plant site is contemplated, both the NRC and recipient permit holder, or licensee, are to be notified of the disposition of said subassemblies under provisions of 10 CFR Part 21 regulations.
This request for information was approved by OMB under clearance number:
3150-0084.
Comments on burden and duplication should be directed to the Office of Management and Budget, Reports Management, Room 3208, New Executive Office Building, Washington, D.C.
20503.
Attachments:
1.
Table 1 2.
Previously Issued IE Bulletins
i IEB 82-01 March 31, 1982 TABLE 1 SITES WITH PIPING ASSEMBLIES FROM AP&E Group 1 Group 2 Grand Gulf Units 1&2 Bailly Unit 1 LaSalle Units 1&2 Black Fox Units 1&2 River Bend Units 1&2 Hartsville A1, B1, A2 & B2 Clinton Units 1&2 Phipps Bend 1&2 Shoreham Allens Creek Unit 1 Limerick Units 1&2 WPPSS-2 Nine Mile Point 2 Hope Creek Units 1&2
IEB 82-01, March 31, 1982 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
81-02 Failure of Gate Type Valves 08/18/81 All holders of a Supplement to Close against Differential power reactor 1
Pressure OL or CP 81-03 Flow Blockage of Cooling 4/10/81 All holders of a Water to Safety System power reactor Components by Carbicula 01 or CP Sp. (Asiatic Clam) and Mytilus Sp. (Mussel) 81-02 Failure of a Gate Type 3/9/81 All holders of a Valves to Close Against power reactor Differential Pressure OL or CP Revision 1 Surveillance of Mechanical 3/5/81 All holders of a 81-01 Snubbers power reactor OL or CP Supplement 5 Failure of Control Rods 2/13/81 All holders 80-17 to Insert During a Scram of a BWR power at BWR reactor OL or CP 81-01 Surveillance of Mechanical 1/27/81 All holders of a Snubbers power reactor OL or CP 80-25 Operating Problems 12/19/80 All holders of a with Target Rock Safety-BWR power reactor Relief Valves at BWRs OL or CP Supplement 4 Failure of Control Rods 12/18/80 All holders of a to 80-17 to Insert During a BWR power reactor Scram at a BWR OL or CP 80-24 Prevention of Damage Due 11/21/80 All holders of a to Water Leakage Inside power reactor OL Containment (October 17, or CP 1980 Indian Point 2 Event) 80-23 Failures of Solenoid 11/14/80 All holders of a Valves Manufactured by power reactor OL Valcor Engineering or CP Corporation