ML20050E206
| ML20050E206 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 04/07/1982 |
| From: | Brenner L Atomic Safety and Licensing Board Panel |
| To: | |
| References | |
| IEB-82-01, IEB-82-1, ISSUANCES-OL, NUDOCS 8204130103 | |
| Download: ML20050E206 (3) | |
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'87_ f?' -8 P 1 '59 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION pD ATOMIC SAFETY AND LICENSING BOARD Before Administrative Judges:
- e Lawrence Brenner, Chairman g
Dr. James H. Carpenter p
.M Dr. Peter A. Morris
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v In the Matter of
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U LONG ISLAND LIGHTING COMPANY
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Docket No.
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(Shoreham Nuclear Power Station
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April 7, 1982 Unit 1
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ORDER REGARDING IE BULLETIN NOTIFICATION OF POTENTIAL ALTERATION OF RADIOGRAPHS OF WELDS BY CONTRACTOR Through routine distribution of all "IE Bulletins" issued by the NRC Staff's Office of Inspection and Enforcement,. the Board has become aware of the attached IE dulletin No. 82-01, dated March 31, 1982, entitled:
" Alteration of Radiographs of Welds in Piping Subassemblies." As set forth in the attached Bulletin, an employee of a piping contractor over a period of many years altered rac;ographs used to verify the quality of welds in piping
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B204130103 820407 PDR ADOCK 05000322 g
_,e subassemblies supplied for nuclear power plants.
Nuclear power plants which were supplied by this contractor, Associated Piping and Engineering Corporation (AP&E), therefore potentially have piping with improper welds.
Tne Shoreham facility is included in the Bulletin's list of potentially affected plants.3/
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Tne Bulletin requests affected utilities, Jncluding LILCO, to undertake a review of all radiographs for AP&E welds, and if necessary to take further steps.
The schedule in the Bulletin requests a report to the NRC Staff of the results of the follow-up inquiry by utilities by about the end of July, 1982.
In view of our recent requirement that all technical correspondence between LILC0 and the Staff regarding Shoreham be served in the proceeding, we expect that LILC0's report on this matter will be so furnisned. We address the matter now to assure that the parties have been promptly informed, and to alert LILCO and the NRC Staff that the Board expects to be kept informed of the results of the follow-up inquiry in order to determine 1/The Board assumes that as part of routine notification procedures, this IE Bulletin will be the subject of Board Notifications from the NRC Staff in appropriate proceedings, and that such a notification would have been filed in this proceeding.
If not, then there is a serious lack of coordination between the Staff office issuing IE Bulletins and the Staff office responsible for Board Notifications.
We trust that if any such gap exists in Board notification procedures, it will be remedied. We have issued this order without waiting for a possible Board Notification due to the immediacy of the the commencement of the evidentiary hearing, and
,because we were able to determine now that it was important for the Board and the parties to be informed of the results of the inquiry for Shoreham required by the attached Bulletin.
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3-whether any further action will be required in this proceeding.
For this reason, and bearing in mind the general relevance of the subject of the Bulletin to construction QA/QC issues in the proceeding, it would be prudent j
for LILC0 to 6xpedite its response to the Bulletin.
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'IOR THE ATOMIC SAFETY AND LICENSING BOARD
_, Chairman Lawrence Brenner ADMINISTRATIVE JUDGE Bethesda, Maryland April 7, 1982 i
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SSINS No.:
6820 Accession No.:
82020 @l10 OMB No.:
3150-0084~
Expiration Date:
3/31/83 IES 82-01 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 March 31, 1982 s.
IE BULLETIN NO. 82-01:
ALTERATION OF RADIOGRAPHS OF WELDS IN PIPING SUBASSEMBLIES y
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 1 stainless steel piping of less than -inch wall thickness.
All affected 29 welds in the thin-wall piping were reexamined radiographically in accordance with the ASME Code.
No evidence of unacceptable weld quality was identified.
i 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.
Af t'er 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 customer review and approval.
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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.
1 3.
Where conformance with Items 1 and 2 cannot be satisfied, appropriate steps'shall be taken to ensure the acceptability of the affected welds 4
in accordance with the applicable ASME Section III Code requirements in I
effect for plant construction.
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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.
20555u Actions To Be Taken by Apolicants for Construction Permits or Utilities Whose Construction Permits Are Suspended or Delayed (Group 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 9
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e 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 182 Phipps Bend 1&2 Shoreham Allens Creek Unit 1 Limerick Units 1&2 WPPSS-2 Nine Mile Point 2 Hope Creek Units 1&2 a
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