IR 05000387/1979014
| ML17138A679 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/19/1979 |
| From: | Durr J, Finkel A, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138A675 | List: |
| References | |
| 50-387-79-14, 50-388-79-08, 50-388-79-8, NUDOCS 7907190029 | |
| Download: ML17138A679 (8) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I 50-387/79-14 Report No. 50-388/79-08 Docket No. 50-388 CPPR-101 Ld Licensee:
Priority Category 2 North Ninth Street Allentown Penns lvania 18101 Facility Name:
Sus uehanna Units
and
Inspection at:
Berwick, Pennsylvania Inspection conducted:
March 19-23, 1979 s
Inspectors:
g.
P. Durr, Re Inspector r
e
@>~
date sngned A
.
E. Finkel.,
er Inspector date igned Approved by:
//)'.
E. Tripp, f, Engineering Support Section No. 1, RC&ES Branch date signed
/F)
date igned Ins ection Summar
Unit 1 Ins ection on March 19-23, 1979 Re ort No. 50-387/79-14
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d nounced inspection of piping storage, maintenance,,Installation, and documentation activities; installation of safety related cable and terminations; and the rework of the PGCC system instrumentation cables.
The inspection involved 54 inspector-hours on site by two NRC inspectors.
Resu1ts:
No items of noncompliance were identified in two of the areas inspected and two items of noncompliance were identified in two of the areas (Infraction - Failure to specify the supplementary essential variables in the welding procedure specifications-para. '5; and failure to sure piping cleanliness-~ef'ore.closure-para. 4).
t 2 Ins ection on March 19-23 1979 Re ort No. 50-388 79-08 as Ins ected:
A regional based inspector performed a rout)ne, unannounced inspection of piping storage and maintenance activities.
The inspection involved 2 inspector-hours on site by one NRC inspector.
Redsults:
No items of noncompliance were identified in %e orle area inspected.
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DETAILS Persons Contacted Penns lvania Power
& Liaht Com an L. Ballard, Site gA Engineer
- R. Beckley, Site gA Engineer
- S.
R'.
Denson, Assistant Project Construction Manager
- E.
W. Elyard, Site gA Engineer
- M. Gorski, Resident Engineer
- J.
D. Green, Resident Nuclear gA Engineer
- R. Prego, Electrical Project gA Engineer Bechtel Cor oration M.
K. Boone, Lead Field Welding Engineer D. Donat, Lead Electrical Field Project gC Engineer
~M. A. Drucker, Lead gA Engineer
~G. Gelinas, Lead guality Control, Piping-Mechanical
- W. Mouver, Project Superintendent J.
E. O'ullivan, Assistant Project Field Engineer
- B. W. Ott, Lead Welding guality Control Engineer
- H. Plagge, El.ectrical Engineer
"A. L. Spielhagen, Project Field Engineer
- K. G. Stout, Assistant Project Field FACE
- C. Turnbow, Field Construction Manager General Electric Com an
- C. R. Clark, Project Manager, I8SE
- E. A. Gustai:son, Resident Site Engineer, NED
- T. M. LeVasseur, guality Control Representative, NED
- A. Lileack, Control and Instrumentation Engineer
- F. Smith, Project Engineer, NED
"T. Young, Control and Instrumentation Engineer Factor Mutual Insurance Com an G. Pitman, Authorized Nuclear Inspector
- denotes those persons attending the exit intervie.
Licensee Action on Previous Ins ection Findin s (Closed)
Unresolved Item (387/78-12-06):
Specification statements inconsistent with NkC and ASME III Code requirements (Reference:
78-21).
A review of the General Welding Standards GWS-NF, GWS-SN, and GWS-'FM, verified that revisions have been included which require welding variables to be in accordance with the Welding Procedure Specifications.
This item is considered closed.
3.
" Plant Tour Units 1 and
The inspector toured the Units 1 and 2 reactor buildings and the primary containments.
He observed pipe storage, maintenance, and installation activities.
He discussed the technical aspects of the work in progress with the craftsmen, supervisors, and quality control inspectors'.
No items of noncompliance were identified.
4.
Reactor Coolant Pressure Boundar Pi e Weldin
- Observation of Work Unit
The following listed activities were observed and verified that they were being performed in accordance with selected portions of the ASME III and IX Codes, the guality Assurance Manual ASME Section III, and regulatory requirements:
The completed root pass on the nuclear Class 1, 24" diameter, RHR pipe weld DCA-110-2-FW-10.
Verified the weld location, weld procedure used, weld appearance, welder qualification, arid quality control checks.
The intermediate weld passes on the nuclear Class 1, 20" diameter, RHR pipe weld DCA-108-1-FW-4.
Verified the weld identification, weld procedure used, welder qualification, interpass temperature, weld materials, weld appearance, and quality control check Examination of the Inspection Record for Piping Subassembly Fabrication, Installation,.and Rework 8856/P-1.10, gCIR No.
49-M204, pipe spool DCA-108-1, Item:
DCA-108-1-2, FW4, disclosed that the cleanliness check was performed on or about February 1, 1979.
The welding, described above, was performed on March 21, 1979.
The inspector observed that the pipe spool was open and that fitting and aligning activities, such as filing, were being performed on March 19, 1979.
Paragraph 2.4 of the guality Control Instruction P-1.10 requires that the internal cleanliness inspection of piping components be performed "just prior to the connection closure."
The failure to inspect the pipe spool for cleanliness just prior to closure by welding is contrary to the guality Control Instruction and
CFR 50, Appendix B, Criterion V..This item is considered to be a noncompliance (387/79-14-01).
A review of the welding procedure specification (WPS) Pl-AT-LH (CVN) used to weld the main steam piping to the reactor pressure vessel disclosed that the supplementary essential variable gW-403.5 does not appear to be satisfied.
Th'e pressure vessel nozzel material is A-508, Class 1, which is classified as P-1 Group 2 by the ASME Section IX Code.
The pipe, which is welded to the nozzle, is A-333 Group 1 or 6
, which is classified as P-l, Group 1 material.
The ASME Section IX Code specifies, in part, in Paragraph 403.5, that:
"When joints are to be made between base metals of two different groups, a procedure qualification shall be made for the applicable combination of base metals..."
The procedure qualifica-tion records used to support the WPS Pl-.AT-.LH (CVN)= P(R's No.,
8, ll, 19, and 20, are P-1 Group 1 material to itself and P-1 Group 2 material to itself.
It appears that a
P-1 Group 1 to P-1 Group 2 P(R is required.
The licensee stated that additional information concerning this discrepancy is available from the engineering staff.
This item is considered unresolved pending review by the NRC of the additional information (387/79-14-02).
Reactor Coolant Pressure Boundar and Safet Related Pi in Observation of Work Unit
The inspector reviewed portions of the Field Disposition Instruction 32/68754, Revision 1, Feedwater Nozzle Safe End Modification and the associated work instructions and observed the in-progress work.
He observed the rigging, handling, and alignment of feedwater nozzles N4D and N4E.
He witnessed liquid penetrant testing for these nozzles and verified that the test was performed in accordance with Liquid Penetrant Examination Procedure No.
18XA7400, Revision The review of the welding procedure specification prepared for the welding of the safe end build up and the welding of the new safe end disclosed that not all of the supplementary essential variables for impact tested materials were addressed.
Specifically, specifi-cation No. ISE-DWP-SgI-1.4.1, Revision 0, does not invoke the supple-mentary essential variable gW-410.24 of the ASME Section IX Code.
This variable deals with the volume of weld metal deposited per unit length of weld.
This procedure was used to build";up the
.
internal diameter of safe ends N4A through N4F.
Also', weldipg procedure specification DWP-SgI-1.4, Revision 1, does not invoke the supplementary essential variable gW-410.16 of the ASME Section IX Code.
This variable controls the direction of welding progres-sion.
The procedure was designated for use in the welding of the new safe end to the old safe end.
The failure to address the supplementary essential variables in the weld procedure specifications is contrary to 10 CFR 50.55a and the ASME Section IX Code.
This is an item of noncompliance (387/79-14-03).
The completed accessible portions of the Hiqh Pressure Coolant Injection System from the pump to the tie-in with the main feed-water piping was selected for a walkdown visual inspection.
The inspection verified that the installed portions were in accordance with the following listed drawings:
DBB-120-1, DBB-120-2, EBB-102-1, and M-155.
The visual examination included weld locations and appearance, hanger locations, piping interferences, valve locations, and pipe surface defects.
Several shallow gouges were noted on pipe spool DBB-120-2-2A and an arc strike on pipe spool DBB-1'.20-2-3.
These were documented on Nonconformance Report No. 3609.
An over-ground condition was observed on the toe of weld DBB-120-1-FW3.
The inspector verified that the licensee has a program to iddntify this kind of condition and that this part of the system has not been inspected.
No items of noncompliance were identified.
PGCC/ACR Control Cables - Unit
The inspector witnessed the'inspection of the following cables associated with the field rework of the PGCC/ACR electri'cal cables.
The inspection and identification of the cables were being performed by Bechtel in accordance with work authorization 59 field procedures (FP-G-18),
Revision 0, dated February 21, 1979.
H12-P88F 11-CA-008
The inspector verified that the electrical craft personnel were performing the inspection of PGCC/ACR cables in accordance with the requirements of the General Electric Procedure WJGO, Revision 1, dated January 30, 1979.
The method for rework/repair of cables that have, gouges, nicks, abra'sions, and,cuts on conductors (as defined in Table II of WJGO)
has not been determined as of this inspection period.
The electrical craft personnel are identfying the above conditions on a gCIR to be dispositioned by the licensee at a latter date.
This matter is considered to be unresolved and will be examined during a subsequent inspection (387/79-14-04).
7.
Electrical and Instrumentation Cable Installation Unit
The inspector witnessed the installation of the following electrical and instrumentation cables.
Cable Nos.
FP1P0504B FPlP0504B RP1Y0006A FKIEC5208
~Te Location Power Instrumentation PGCC/ACR Control Trays 1KN05, 1KN06, and 1KN07 from 698 foot level to 729 foot level Conduit FlP144-MCC 1B246 Power Conduit FlP145-MCC 1B246 The -qual.ity control inspector verified that systems were clean before the cable pull in accordance with the requirements of proce-dure E-49 entitled "Conduit and Cable Tray Notes and Details."
The Bechtel gA Inspector inspected the cable installation in accordance with the requirements of,guality Control Instruction (gCI) E-l.0, E-l.l, and E-2.0 entitled
"Installation Inspection of Class IE Raceway."
The inspector witnessed prior to and during the cable installation, that the above procedure requirements were complied with by the Bechtel Inspector and that the cable pull was performed in accordance with the installation procedures.
No items of noncompliance were identifie Cable Installations in Embedded Racewa Unit
Reviewing the nonconforming reports (NCR's)
on cable installations in embedded raceway, the inspector noted that the cable pull tension requirement was being exceeded on the maximum end of the range allowable by engineering specifications.
Random review of installation records by the inspector indicated that quality control inspection was performed on the installations and that the QC inspection was performed in accordance with the requirements of Quality Control Instruction (QIC) E-1.0, E-l.l, and E-2.0 entitled "Installation Inspection of Class IE Raceway,"
Revision 7, dated May 23, 1978.
This problem has been identified by the licensee ahd is documented in their Deficiency Report Log as item 0092, Bechtel has identified this problem in Quality Assurance Finding 83 of Audit 19-2-2, concerning cable FF050401A and listed in QAL 632.
This item is considered to be unresolved and will be examined during a subsequent inspection (387/79-14-05).
Unresolved Items Unresolved items are matters about which more 'information is required in order to ascertain whether they are acceptable items,~ items of non-compliance, or deviations.
Unresolved items disclosed during this inspection are discussed in Paragraphs 4, 6, and 8.
Exit Interview The inspectors met with licensee representatives (denotes in Para-graph 1) at the conclusion of. the inspection on March 22 'and 23, 1979.
The inspectors summarized the scope and findings of the inspection.
Additional aspects of the unresolved item described'in Paragraph 4 were discussed in a subsequent telephone conversation between Mr. J.
Green and Mr. J. Durr on March 27, 1979.