ML20031G023
| ML20031G023 | |
| Person / Time | |
|---|---|
| Issue date: | 09/16/1981 |
| From: | Barnes I, Ellershaw L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20031G014 | List: |
| References | |
| REF-QA-99900209 NUDOCS 8110200655 | |
| Download: ML20031G023 (9) | |
Text
ORGANIZATION: BERGEN-PATER 0N PIPESUPP0CT CORPORATION LACONIA, NEW HAMPSHlRE REPORT NO.: 99900209/81-0] INSPECTION DATE{Sh 7/28-31/81 INSPECTION ON-SITE HOURS: 32 CJ4RESPONDENCE ADDRESS: Bergen-Paterson Pipesupport Corporation ATTN:
Mr. H. Noreen, Jr., Director Quality Assurance and Vice President 34 Moulton Street Laconia, New Hampshire 03246 ORGANIZATION CONTACT:
Mr. H. Noreen, Jr., Director-Quality Assurance and TELEPHONE:
Vice President (603) 524-1990 PRINCIPAL PRODUCT: Component Supports NUCLEAR INDUSTRY ACTIVITY:Bergen-Paterson Pipesupport Corporation (B-P) is providing component supports to approximately 23 nuclear power generating sites.
Currently, approximately 50% of their work is devoted to the commercial nuclear industry.
ASSIGNED INSPECTOR:
8%d 9 -M -f/
g L. E. Ellershaw, Reactive Inspection Section (RIS) Date OTHER INSPECTOR (S):
l APPROVED BY:
/bm-,
9 - /6.. f i l
I. Barnes, Chief, RIS Date i
INSPECTION BASES AND SCOPE:
A.
BASES:
10 CFR Part 21 and 10 CFR Part 50, Appendix B.
B.
SCOPE: This inspection was made as a result of:
(1) a 10 CFR Part 21 written notification by B-P pertaining to insufficient design clearances between combinations of B-P pipe clamps and Pacific Scientific Company mechanical arrestors provided to the Shoreham, Waterford, Callaway, and Wolf Creek sites; (2) a 10 CFR Part 50.55(e) notification pertaining to weld symbol errors on drawings supplied to the Shearon Harris site; and (3) an LER pertaining to failure of safety related snubbers at Brunswick, Units 1 and 2.
Additional areas selected for inspection included previous inspection findings.
DE3IG D ORIGINAL ro et~ a m.,
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~ 8110200655 810921 PDR GA999 EMVDRPP l
99900209 PDR
ORGANIZATION: BERGEN-PATERSON PIPESUPPORT CORPORATION LACONIA, NEW HAMPSHIRE REPORT NO.: 99900209/81-01 INSPECTION RESULTS:
PAGE 2 of 5 A.
VIOLATIONS:
1.
Contrary to 10 CFR Part 21, posting of Section 206 of the Energy Reorganization Act of 1974, or an appropriate notice had not been accomplished.
2.
Contrary to 10 CFR Part 21, procedures had not been adopted to provide for:
(1) evaluating deviations or informing the licensee or purchaser and (2) assuring that a director or responsible officer was informed if the supplied basic component (a) failed to comply or (b) contained a defect.
B.
NONCONFORMANCES:
None C.
UNRESOLVED ITEMS:
None D.
STATUS OF PREVIOUS INSPECTION FINDINGS:
1.
(Closed) Item A, Notice of Deviation (Report No. 80-02):
This item dealt with welding material being released for use without being checked in accordance with purchase order requirements, and without being properly certified.
B-P implemented their committed corrective action in that a training session pertaining to proper documentation requirements was held with the responsible personnel on October 30, 1980.
In addition, the welding material was identified as not for use on nuclear work.
2.
(Closed) Item B, Notice of Deviation (Report No. 80-02): This item dealt with special drawing requirements pertaining to minimum yield strength not being passed on to a material supplier in purchase documentation.
Subsequently the material was received, accepted, and issued to manufacturing without meeting the drawing requirements.
B-P had issued an Engineering Change Notice (ECN) to eliminate this requirement from several drawings, but inadvertently omitted the particular drawing in question.
B-P issued a new ECN on September 15, 1980 to resolve and correct this situation.
ORGANIZATION:
BERGEN-PATERSON PZPESUPPORT CORPORATION LACONIA, NEW HAMPSHlRE REPORT NO.: 99900209/81-01 INSPECTION RESULTS:
PAGE 3 of 5 3.
(Closed) Item C, Notice of Deviation (Report No. 80-02).
This item dealt with B-P's welder qualification records showing weld 1'g cperators to be qualified to perform friction welding when, in fact, their per-formance qualifications did not meet the requirements of ASME Code Case N-55.
B-P implemented their committed corrective action by qualifying the identified welding operators in accordance with ASME Code Case N-55.
E.
OTHER FINDINGS OR COMMENTS 1.
A 10 CFR Part 21 written notification was made by B-P on March 6, 1981, pertaining to insufficient design clearances between combina-tions of B-P pipe clamps and Pacific Scientific Company (PSCo) mechanical arrestors.
Written notification to B-P was made by Bechtel Power Corporation (BPC) on December 2,1980, 4s a result of two Nonconformance Reports (NCR) initiated by Daniel Construction Corporation on October 14, 1980 and November 14, 1980, at the Callaway Plant, Unit 1 site.
The two NCRs dealt with inadequate clearance between the B-P clamps and PSCo snubbers.
B-P advised PSCo by telephone on December 10, 1980, that PSCO part numbers 1596-03 and 1598-03 (when made from forgings) contain a shoulder which reduces available clearance from the base to the pin hole and which may cause interference with the B-P clamp.
Discrepant Mater 0 ~.
Report No. L-221 was sent to PSCc in regard to this subject on the same date as the telephone contact, advising that the machined bracket take-out dimension was not to drawing and interference prevents unit function.
PSCo responded on January 14, 1981, by stating tLat the machined brackets met the dimensional requirements of PSCo drawings and that the cause of the interference was unknown.
After being informed by B-P TWX on February 23, 1981, that the problem had been reported by BPC as a potential 10 CFR 50.55(e) report and EPC required the position of B-P and PSCo in regard to reportability under 10 CFR Part 21, PSCo responded that they did not intend to report.
Their position was identified to be that the part met PSCo ocawing requirements and that the problem was considered an installation problem involving other hardware not under their control.
ORGANIZATION: BERGEN-PATERSON PIPESUPPORT CORPORATION LACONIA, NEW HAMPSHIRE REPORT NO.: 99900209/81-01 INSPECTION RESULTS:
PAGE 4 of 5 B-P filed a 10 CTR Part 21 report on March 6, 1981.
B-P performed an evaluation and determined that a modification to their clamps (sizes 6 and 15 only) by trimming, would accomodate the shoulder in the PSCo forward brackets.
B-P's drawings were revised on February 25, 1981.
B-P initiated a 100% dimensional inspection and a verification of adequate clearance between the mating parts.
Notification was made to all of B-P's affected customers.
The NRC inspector was able to determine that PSCo started supplying the forged brackets to B-P approximately January,1977.
A review of the affected PSCo catalogue drawings provided to B-P showed '. hat these drawings were not revised to show the shoulder until January, 1981.
The PSCo design and manufacturing drawings were not available for review at B-P.
2.
A 10 CFR 50.55(e) Construction Deficiency Report (CDR) notification was made by Carolina Power & Light Company on September 8, 1980, pertaining to weld symbol errors or. drawings, and misapplication of weld on B-P pipe hangers.
l B-P is providing approximately 96,000 hangers to the Shearon Harris 1
Nuclear Power Plant, Units 1-4.
They are also responsible for providing design drawings (approximately 1600), which delineate field welding to be performed at the site by others.
It was determined that B-P failed to comply with their Engineering Manual Section I, paragraph 11.1.2 which states, in part, "Use welding symbols to provide the shop and the field with the necessary infor-mation for fabrication and erection of hanger assemblies..." and Section II, paragraph 6.1.1 which states, in part, " Field welded joints shall be identified by a weld symbol, size, and length...."
It was clearly established that B-P's Engineering Department provided drawings for field welding which contained incorrect and unclear weld symbuls, or weld symbols were missing.
As a result, field personnel failed to weld the pipe hangers in accordance with the design drawings or made welds when weld symbols were either missing or incorrect.
B-P has assigned two individuals to the site, in order to review all drawings.
The NRC inspector reviewed Main Steam Line drawings provided to TVA's Phipps Bend Nuclear Plant, and did not identify any incorrect, unclear, or missing weld symbols.
ORGANIZATION: w uuEN-PATERSON PIPESUPPORT CORPORATION LACONIA, NEW HAMPSHIRE REPORT NO.: 99900209/81-01 INSPECTION RESULTS:
PAGE 5 of 5 l
3.
A Licensee Event Report was issued by Carolina Power & Light Company on March 18, 1981, pertaining to a 20% failure rate of snubbers during functional testing at the Brunswick Steam Electric Plant, Unit No. 2.
As a result, Unit 2 was shut down and all snubbers were inspected.
B-P was contacted and requested to provide personnel to assist in determining and correcting the causes.
It was determined that the primary cause was due to line vibrations which, (1) prevented the poppet from seating which would prevent the snubber from locking up, and (2) allowing the poppet to seat too securely which would prevent the snubber-from meeting its bleed rate specifications.
Other identified problems were: misalignment, lack of fluid, and foreign material in the fluid.
All snubbers on Unit 2 were repaired at the site during March-April, 1981.
An evaluation of the snubbers on Unit No. I was performed and it was decided to continue to operate until planned shutdown at the end of March,1981.
At that time, all snubbers were inspected.
The results showed there was no problem similar to Unit 2 pertaining to line vibration.
However, there was evidence of lack of fluid.
A decision was made to remove all snubbers and return to B-P for complete examination and performance of any necessary repairs.
This was done during May-June, 1981.
The snubbers were returned to site and installed.
This was not considered to be a vendor related problem.
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