IR 05000387/1980005
| ML17138B432 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/20/1980 |
| From: | Durr J, Reynolds S, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138B428 | List: |
| References | |
| 50-387-80-05, 50-387-80-5, 50-388-80-03, 50-388-80-3, NUDOCS 8008120618 | |
| Download: ML17138B432 (5) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I 50-387/80-05 Report No.
50-388/80-03
~0-387 Docket No.
50-388 License No.
CPPR-102 Priority Category Licensee:
Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Facility Name:
SUs uehanna Unit
.
Inspection at:-
Berwick, Pennsylvania Inspection conducted:
March 24-28, 1980 Inspectors:
. Durr Reactor Inspector da signed S. Reynolds, actor Inspector date signed date signed Approved by:
~.
E. Tri, Chief, Engineering Support Section No.
1.
RC8ES Branch ate signed Ins ection Summar
Unit 1 Ins ection on March 24-28, 1980 Re ort 50-387/80-05 reas Ins ecte
egsona based snspectons performe a routine, unannounced inspection of plplng an welding activities.
The inspection involved 62 inspector-hours on site by two NRC inspectors.
Results:
One item of noncompliance was identified in one of the two areas inspected
~Infraction Failure to identify a nonconforming condition, paragraph S. )
Unit 2 Ins ection on March 24-28, 1980 Re ort 50-388/80-03)
~AI d:
Ipl;
p g; g,k dkkg, d
qkp protect>on actsvities.
The inspection involved 8 inspector-hours on site by tIp)o NRC inspectors.
Results:
No items of noncompliance were identified.
Region I Form 12 (Rev. April 77)
Opsy'@/
,
Persons Contacted DETAILS Penns lvania.'Power and Li ht Ccm an T. Clymer, Site Quality Assurance Engineer
- R. W. Featenby, Assistant Project Director
- W. H. Gulliver, Resident Nuclear Quality Assurance (Acting)
R. Prego, Site Quality Assurance Engineer,
- A. R. Sabol, Manager, Nuclear Quality Assurance Bechtel Cor oration.
2.
W. Collins, Quality Control Engineer, M&QS
- G. V. Cranstori:pe'student'..Project Engineer
- B. Henke, Welding'uperintendent
- H. F. Lilligh, Project Quality Assurance.
Engineer
- M; Muir, Project Manager
- J.
E. O'ullivan, Assistant Field Project Engineer W. Ross, Lead Field Welding Engineer C. Stanley, Engineering Specialist, M&QS
- K. G. Stout, Project Field Quality Control Engineer
- C. Turnbow, Field Construction Manager In addition to the persons listed above, other supervisors, craftsmen, and technicians were 'interviewed when their activities interfaced with the inspection.
- Denotes those persons present at the exit interview.
Plant Tour (Unit No.
1 and 2)
The inspectors toured the Units No.
1 and 2 Reactor Buildings and Primary Containments observing work in progress and the status of installed equipment.
Specific areas of interest were storage, handling, and protection of equipment; cleanliness;
'and quality control activities.
Several areas of the inside containment liner plate in Unit No.
above penetration X-44 were observed.to have chipping hammer marks, ground areas, manufacturing discontinuities, and temporary attachments affixed. It was determined that the licensee has a control program for the attachment and removal of appurtenances to the containment liner.
However, it could not be established from the imnediately available documentation that the observed surface imperfections had been identified and dispositioned.
The applicable Technical Specification, 8856-C-50, paragraph 8. 1. 17, permits imperfections to be.Ol'inches in depth.
Many of the imperfections observed appear to exceed this limi This item is considered unresolved pending the NRC's review of documentation supporting the disposition of the aforementioned plate imperfections.
(50-388/80-03-01}
L'icensees Action on Previous Identified. Ins ection Findin s (Closed)
Noncompliance (387/79-19-01 }:
Improper weld surface transition.
The 20" diameter pipe weld joint DCA-"108-1-FM1 was indentified as hot meeting. the weld sufrace transition requirements of the specification.
The licensee issued guality Control Corrective Action Report (CAR),
dated May 17, 1979, describing the condition.
The resulting Nonconformance Report, No. 3879, dispostioned the problem by grinding the "notched" area such that i.t blended smoothly with the adjacent surface and nondestructively testing the area for thickness and defects.
The CAR directed that the guality Control Melding Engineers be instructed in the proper weld surface transitions and that additional similar welds be inspected to assure that this was a unique occurence.
The NRC inspector reviewed the instruction attendance list and the Field Inspection Report No. 3879 which documents the additional inspections.
He also examined..welds in Units.No.
1 and 2 to verify the adequacy of the corrective actions.
Reactor Coolant Pressure Boundar Pi in
- Review of ualit Records Unit No.
Two nulcear Class I pipe welds were selected for review to verify that portions of the ASME III Code, the guality Assurance Manual,. ASNE Section III., and regulatory requirements were satisfied.
The following weld documentation was reviewed:
Weld Identification VNB-B21-2 FM-B2 DCA-110-1 FM-5
~Sstem Main Steam RHR Diameter 26"
"
24" No items of noncompliance were identified.
Observation of Work - Pi in and Weldin (Unit 1)
The main steam line, VNB-BZ1-2, line "B", was selected for a "walkdown" inspection.
The piping was visually examined for surface defects, weld joint appearance, component location, compliance with installation drawings, and interferences.
The piping was inspected, where accessible, from the primary containment penetration to the reactor vessel nozzle.
Two welder "arc strikes" and a temporary support were identified and reported to the licensee's quality control group.
Nonconformance Report No.
5568 was issued to assure disposition of these construction irregularities.
No items of noncompliance were identifie The 20" diameter; RHR.system, weld, repair, GBB-.104-1-FW16-Rl, was selected for, observation.
The weld had been completed and rejected for radiographic. defects,. the rejected"areas excavated,.
and the joint prepared for rewelding.
The excavations. in several areas penetrated completely through, the pipe wall, necessitating a root,weld closure..
During the excavations, the root gap spacing exceeded the 5/32" permitted by the specified welding procedure Pl-AT-LH-RO.
The quality control inspector recognized this nonconforming condition but. released the weldfor'completion without initiating a Nonconformance Report.
The foregoing failure to report a nonconforming condition is contrary to-10 CFR 50, Appendix B, Criterion XV and an item'f noncompliance.
(387/80-05-01)
Unresolved Items Unresolved items are matters about which more information is necessary to determine. if they are acceptable, items of noncompliance, or deviations.
An'unresolved item identified during this inspection is discussed in
'paragraph 2.
Site,Meetin At the request of the licensee, a meeting was held on March 28; 1980, to discuss'Welding Procedures and Procedure Qualification Records.
The following persons attended:
NRC
'R. Gallo, Resident Inspector J., Durr, Reactor Inspector S. Reynolds, Reactor Inspector PP&L W. Gulliver, RNQAE (Acting )
J.
Clymer, QAE Bechtel Cor oration W. Collins, QCE, M&QS W. 'Ross, LFWE H. Lilligh, PQAE C.
S tan 1 ey, Enginee ring Speci a 1 ist, M&QS J. O'ullivan, APFE
The'essence of the meeting dealt with the NRC's concern for the apparent marginal. control of welding parameters specif ied in welding procedures and'ual.ification records.
Exi.t.Intervi ew The inspectors met. with representatives of the licensee (denoted in paragraph 1)
on March 28,, 1980, at. the conclusion of the inspection.
They summarized the purpose, scope, and findings of the inspection.
Mr. A.
R., Sabol was. telephonically in cotanunication with the proceedings.