IR 05000387/1979003
| ML17138A602 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/16/1979 |
| From: | Fasano A, Mcbrearty R, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138A598 | List: |
| References | |
| 50-387-79-03, 50-387-79-3, NUDOCS 7905040156 | |
| Download: ML17138A602 (12) | |
Text
R I II U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I
I II.JRIRRR License No.
Licensee:
Prior ity Category 2 North Ninth Street Allentown Penns lvania 18101 Facility Name:
Sus uehanna Unit
Inspection at:
Berwick, Pennsylvania Inspection conducted; January 30 - February 2, 1979 Inspectors:
R. A.
cBrearty, Reactor Inspector te igned A..N.
asano, Reactor Inspector date signed A. C. Cerne, Reactor Inspector Approved by:
. E. +
L. Tripp, hief, Engineering Support Section Nci..l, RC
ES Branch date signed date signed Ins ection Summar
nit
.
Ins ection on Januar
Februar 2,
1979 Re ort No. 50-387/79-03 RI I
I p
I d
I, d
~nspection on the reactor vessel internals including:
protection, welding, nondestructive examination and the QA/QC recordsQA/QC for pipe supports, and structural welds.
The inspection involved 64 inspector-hours on site by three NRC regional based inspectors.
Results:
One item of noncompliance was identified in the area of structural
"nWpe Ws Infraction - failure to control structural steel arc strikes in accordance with code requirements Paragraph 4).
Region I Form
(Rev. April 77)
F905040<56
S
1.
Persons Contacted DETAILS Penns lvania Power 8 Li ht Com an R. Beckley, Site QAE G. Burvis, Site QAE T. Clymer, Senior NQA Analyst
- E.
W. Elyard, QAE
- J.
D. Green, Resident QAE
- D. E. Witmer, QAE Bechtel Cor oration Y. Ananda, Civil QAE J.
Danner, QAE
- M. A. Drucker-, Electrical QAE G. Gelinas, Lead QCE, Piping/Mechanical J.
Khandhar, QAE R.
Lamb, Assistant Lead WeTding QCE
- H. F. Lilliqh, Project QAE
~D.
E. Montrevil, Civil QCE B. Ott, Lead QCE, Welding
- J. E. O'ullivan, Assistant Project Field Engineer
~A. Spielhagen, Project Field Engineer
- K. G. Stout, Assistant'roject Field QCE
- C. Turnbow, Field Construction Manager
- J. Van Omen, Subcontractor Adminstrator Cives Cor oration B. Kennicutt, QC Inspector General Electric Com an D. Hess, Site QA Supervisor P. Langille, Welding Supervisor E. Reczek, NDE Level II R. Wagner, I8SE QA Supervisor
- denotes those present at the exit intervie.
Plant Tour The inspectors observed work activi-ties in-progress, completed work and, plant status in several areas of the, plant. during general inspection of the plant.
The inspectors examined work for any obvious defects or noncompliance with regulatory requirements or License Conditions.
.The inspectors interviewed craft personnel, supervision, and quality inspector personnel as such personnel were available in the work areas.
No items of noncompliance were identified.
3.
Safet Related Pi e
Su ort. and Restraint S stems - Records The inspectors examined the document records of ten fixed pipe support systems and two dynamic pipe supports, The criteria for the inspection were based on Specification M-209, Pipe Hangers, Supports and Restraints; Specification M-213, Installation,'nspection',
arid Documentation of Pipe Supports, Hangers and Restraints; and Specification M-204, Field Fabrication and Instal-lation of Nuclear Service Piping.
The records were examined for support-classification and type; gA/gC verification of support location; designation of weld location; welding material identi-ficatton welder qualification; traceability for safety related pipe component welded attachments; nondestructive test reports; and NDE personnel qualifications.
The applicable records for the following pipe support and restraints were examined:
a.
EBB-102-H21, Revi sion 1/Fl b.
GBB-109-H27, Revision 0/F2 c.
HBB-120-H17, Revision 2/Fl d..
HBB-120-H15, Revision 2/Fl e.
SP-HCB-138-H1, Revision F2 f.
SP-DCA-106-H5, Revision 1/Fl
g ~
h.
SP-DCA-106-H4, Revision 2/F4 SP-DCA-103-H1, Revision 3/F5 SP-DCA-135-Hl, Revision 3/Fl SP-DCA-139-H1, Revision 1/Fl SP-DCA-106-H7, Revision F2 SP-DCA-106-H5, Revision F3 The following records were examined to validate the existence of attributes stated above:
guality Control Inspection Reports, gCIR, 26.0-M-213-A1-271-(F),
Supports a thorough. d, gCIR A1-254-(F)-and,Form P-129, September 21, 1978 Drawing SP-HCB-138-1, Revision
Drawing SP-DCA-106-2, Revision
Drawing SP-DCA-103-3, Revision
Drawing SP-DCA-135-1, Revision
Drawing SP-DCA-139-1, Revision
Heat numbers for pipe attachments to supports b, d, y, and =j'-.
HT 680142, 781504, 2P5435, 781504, 2P1535 Weld gualification - Form WR-1, Revision
NDE Training Certification Records for PT and MT May, 1976, September, 1977, and August, 1978.
gCIR's 26.0-M-..213-.Al:
236 Supports 6, ll; Support h 255 Supports i, j, 259 Supports i', J~ 263 Supports c, d Field Weld Check L'ist (FWCL), August 23, 1978, Support j,'=,
FWCL, September 15, 1978, Support i; FWCL May 5, 1978, Sup-port
== The examination of the" document'ecords.:resulted.'in,:the-:following.
', findings:
Documentation remains incomplete for pipe supports a,-thorough. d fop location:verificati:on.
NGR3343'as been issued requesting clarification on. location verification and dimensional toler-ances.,
The final documentation o'f gCIR Al-271-(F) remains open pending action on NCR3343.
This is an unresolved item'pending completion of gCIR Al-271-(F) (387/79-03-01).
The in: progress gCIR for pipe support '(SP-HCB-138-Hl)
was not available for review.
Also, notation of weld procedures P8-Pl-T appears to be missing on the applicable in-progress gCIR's.
This is an unresolved item pending the location of the unavailable gCIR and a documentation check to verify notation of the requi.red weld'procedures, where required for each hanger (387/79-03-02).
Support GBB-109-H27 has been changed to reflect its present seismic class 2 categorization.
However, Drawing GBB-109-1, Revision 5, and Specification M-199 indicate that this support is seismic cl.ass 1.
This appears to be in. conflict with the instal.lation drawing.
Clarification as to the appropriate seismic category is required.
This is an unre-solved item pending proper category. cl.assification and appro-priate design consideration clarification, if required (387/79-03-03).
No items of noncompliance were identified.
4.
Structural Welds The inspector examined the in-place condition of several members of structural steel of the Reactor Building Superstructure above elevation 818'.
He randomly checked bolted joints for fit-up damage and nut engagement and generally viewed structural pieces for.obvious defects or apparent nonconforming conditions.
The inspector verified the existence of engineering approval and.':.
documentation (Cives Steel Company Supplier Deviation Disposition Request No.
F7) for one repair work item requiring the substitution of a welded connection for a bolted join In examining the overall quality of the erected structural steel, the inspector noted several arc,strikes on various members.
The "Structural Welding Code,"
AWS Dl.l'; Revision 1-76, to which commitment is made in Bechtel Specification 8856-C-66 (Revision 2)
governing the erection of structural steel for the Reactor Building Superstructure, requires the removal of any cracks or blemishes caused by arc strikes and a subsequent-check of material soundness.
Interviews with licensee personnel indicated, however, that program-matic controls for the identification, evaluat1on, and disposition of arc strikes on the Reactor Building Superstructure steel appear to be lacking.
No evidence was available to provide assurance that. the licensee's QA program, as presently constituted to con-trol structural steel welding, would properly address such arc strikes.
This failure to provide control over arc, strikes cons1stent with the referenced AWS Code requirement is considered to be an item of noncompliance (387/79-03-04).
5.
Reactor Vessel Internals Installat1on The inspector observed activit1es associated with the installation of CRD Housings in the Unit 1 reactor pressure vessel in order to ascertain that those activ1ties were done in compliance with the requirements of the applicable codes, specificati.ons and work procedures.
a ~
~Me 1 di n The inspector observed welding in progress, reviewed appli-.
cable procedures and records, and observed, that required nondestruct1ve examinations were performed.
The inspector witnessed CRD Housing in Stub Tube 46-43 and 50-39 root pass eel'di,og, The inspector found. that the welding was done in accordance w1th Detail Weld Procedure ISE-DWP-4002, Rev1sion 2, which was properly qualified as evidenced by Procedure Qualifi-cat1on Record ISE-PQ-401.
The qual1f1cat1on of welders performing the. work was confirmed by Welder Qualif1cation Record ISE-WQ-52.
Prior to welding, the weld prep areas were found to be dry, clean and free from grease and other deleterious foreign material.
The inspector found that the specified filler materials were being used and no other kinds of weld materials were present.
- Facilities in the reactor vessel access area were provided for storage and issue of weld materials.
Covered electrode material'as found stored in a locked baking oven operating within the specified temperature range and the bare filler material was stored in two locked wooden containers in the same area.
The key to the locked containers, including the baking oven, was kept by the General Electric Company welding supervisor who was responsible for issuing the materials.
Issue records were found on individual Joint Process Control Sheets which identified the welder and the type of fi'lier material used.
Each entry was dated and initialed by the welding supervisor.
- Weld material control and storage was found to meet the requirements in General Welding Procedure 160A71203.
The inspector selected the following welds to ascertain accuracy and retrievability of the associated records:
Weld 46-43 Weld 50-39 Weld 42-39 Weld 10-23 Weld 14-23 Meld 18-23 Meld 14-27
....
" 'In,'addition,'he location of weld 46-43 and 50-39 was verified by the inspector.
No items of noncompliance were identified in the areas inspecte b.
Nondestructive Examination The inspector witnessed the ultrasonic examination of CRD Housing'o Stud Tube weld 38-35, and the liquid penetrant examination of root. pass weld 50-39 and 46-43 to ascertain that ASHE. Code and procedural.,requirements were met.
The ultrasonic examination was done using the immersion technique with the test system calibrated on a full size mock-up of'the weld joint.
Examination personnel were certified to NDE Level II in the ultrasonic method.
The root pass liquid penetrant examinations were done using solvent removable, visible dye in accordance with procedure 18 XA7400, Revision 1, by an individual certified to NDE Level II in the liquid penetrant method.
The equipment used for the ultrasonic and penetrant examina-tions was found to be properly certified.
The inspector found that the examinations were conducted in compliance with the applicable code and procedural require-ments.
No items of noncompliance were identified.
6.
Unresolved Items Unresolved items. are matters about which more information is required in order to ascertain whether they are acceptable items or items of noncompliance.
Unresolved items are disclosed during the inspection are discussed in Paragraph 3.
7.
Exit Interview At the conclusion of the inspection on February 2, 1979, a meeting was held. at the Susquehanna site with representatives or the licensee and contractor organizations.
Attendees at this meeting included personnel whose;.names are indicated by notation (*) in Paragraph l.
The inspectors summarized the results of the inspection as described in this repor I