IR 05000387/1979004
| ML17138A617 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/01/1979 |
| From: | Durr J, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138A613 | List: |
| References | |
| 50-387-79-04, 50-387-79-4, 50-388-79-03, 50-388-79-3, NUDOCS 7906070213 | |
| Download: ML17138A617 (8) | |
Text
4 ort No.
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE-OF INSPECTION AND ENFORCEMENT Region I 50-387/79-04 50-388 79-03 Docket No.
License No.
50-387 50-388 CPPR-.101 CPPR-102 Prior ity Category A
Licensee:
Penns lvania Power-and Li ht Com any 2 North Ninth Street
.Allentown, Penns lvania, 18101 Facility Name:
Sus'ehanna'.Units
and
Inspection at:
Berwick, Pennsylvania Inspection con cted:
February 12-15, 1979 Inspectors:
p
.
P. Durr, Reactor Inspector I
ate signed date signed Approved by:.. S.J
. Tripp, C ief, Engineering Support Section No. 1, RC8ES Branch date signed date signed Ins ection Summar
Unit 1 Ins ection on Februar 12-15 1979 Re ort No. 50-387 79-04
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d inspection of piping storage, maintenance, installation, and documentation activities.
The inspection involved 25 inspector-hours onsite by one NRC inspector.
Results:
No items of noncompliance wer e identified in thr ee of the areas in-spected and one item of noncompliance was identified in one area (Infraction-failure to meet ASME III Code requirements for pipe weld joint.alignment).
Unit 2 Ins ection on Februar 12-15, 1979 Re ort No. 50-388 79-03 d:
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'nspection of piping storage, maintenance, and installation activities.
The inspection involved three inspector-hours onsite by one NRC inspector.
ults:
No items of noncompliance were identified in the three areas inspected.
egion I 'Form 12 (Rev. April 77)
V9060V03l3,
DETAILS Persons Contacted Penns lvania Power and Li ht'om an L. Ballard, Nuclear gA Engineer
%.
L.-Demson, Assistant Project Construction Manager
- R.;H. Featenby, Project Construction Manager
"J.
D. Green, Resident Nuclear gA Engineer Bechtel'or oration
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K. Boone, Lead Field Welding Engineer
"M. A. Drucker, Lead gA Engineer
- J.
E. O'ullivan, Assistant Project Field Engineer B., Ott, Lead Welding guality Control Engineer
"A. L. Spielhagen, Project Field Engineer
- K. G. Stout, Assistant Project Field gC Engineer
"C. Turnbow, Field Construction Manager General:Electric Com an
+T; M.'eVasseur, Site gC Representative NISCO M. Sopko, Site Engineer
- denotes those present at the exit interview.
Licensee Action on Previous Ins ection Findin s t
(Closed)
Noncompliance (387/78-12-01):
Surface checks in RHR 90 Piping, Elbow.
(References:
Inspection Report Nos. 50-387/78-05 and 78-11.)
The. licensee effected repairs of the. surface checks on the pipe elbow DCA-110-2-1 as previously stated in Inspection Report 50-387/78-12.
The licensee performed an audit of the supplying vendor and ascertained that the quality assurance program was functioning in this specific area (Licensee Audit No; 71).
He examined similar materials in his warehouse and verified that no other components contain these kinds of defects.
In addition, a training session was held for the receiving, welding, and piping quality control inspectors to emphasize their responsibility in identifying these conditions.
This item is considered resolve (Closed)
Unresolved item (387/78-12-07): gualification of small bore (2 1/2" and under) socket pipe welders.
The licensee received correspondence from the Assistant Secretary, ASME, dated February 6, 1979, which states that the diameter limitations of paragraph gW-403.16,Section IX do not apply to welders who have been qualified on large diameter groove welds.
This item is considered resolved.
(Closed)
Unresolved item (387/78-21-01):
socket welded flange, has internal drop through/burn through of the pipe wall in the weld area..
The licensee issued Nonconformance Report No., 3248 which directs the removal and replacement of the affected weld.
The licensee stated that future dispositioning of similar metallurgical conditions, such as this one, will be directed to the metallurgical staff to determine if this is an acceptable condition.
This item is considered resolved.
3 ~.
Plant Tour Units
and
The inspector toured the Units 1 and 2 reactor buildings, containments, and emergency diesel areas.
'He noted the pipe rigging, handling and in-place storage practices.
He observed the work in-progress and discussed the technical aspects of the work with the craftsmen, super-visors, and quality control technicians.
No items of noncompliance were identified.
Reactor Coolant Pressure Boundar RCPB and Safet Related Pi in Observation of Work Unit
The inspector observed the rigging, handling, and alignment of the following pipe spools:
HBB-118-2-1, RS-1-A, and DCA-110-2-5.
He verified that these activities were in accordance with specification
.
M-204, Field Procedures FP-M-1 and 2, and the ASME III, Code.
Pipe spool GBB-118-2-3 was being modified and had the end cap removed.
Visual examination of shop weld "B" disclosed an offset misalignment of the internal weld surfaces which appeared to be excessive.
Measure-ments, performed by the licensee's quality control personnel, con-firmed that the offset misalignment exceeded 3/16".
The ASME III Code, paragraph NB-4233, states, in part, that: "...the maximum misalignment 'at any one point around the joint shall not exceed 3/32 inch...."
This is an item of noncompliance.
(387/79-04-01)
'.
Reactor Coolant Pressure Boundar and Safet Related Pi e Weldin Observation of Work The following listed activities were observed and verified that they were being performed.in accordance with the ASME III and IX Codes, the guality Assurance Manual ASME Section III, and regulatory require-ments:
Unit
Fitup,:alignment, and welding of portions of the root pass on the 3" diameter, nuclear class 2, weld joint GBC-6-1-FW9.
Verified the alignment, weld identification, and quality control checks.
Fitup, alignment, and root pass welding on the 26" diameter, nuclear. class I, main steam weld joint VNB-21-1-FW-C2; Verified the weld identification, weld procedure,.alignment, welder qualification, quality control checks, preheat temperature, and weld appearance.
Welding of the root and cover pass of the 3/4" diameter, nuclear class 2, control rod drive system pipe weld No. 2061-FW2.
Verified the fitup requirements.
Unit 2 Fitup, alignment and quality control checks for the 6" diameter, nuclear, class 2, weld joint HBB-221-FWl.
The inspector reviewed the following listed post weld heat treatment charts:
DBB-104-1-FW11 DBB-103-1-FW11 DBB-102-1-FW11 DBB-101-1-FW10 He verified that the heatup/cooldown rates, holding times, and tempera-tures conformed to the requirements of the ASME III Code, the procedure specification for Post Weld Heat Treatment PHT-501, and the procedure for Post Weld Heat Treatment FP-W-The inspector examined the two weld rod issue stations for neatness, storage of materials, records, and oven temperature.
He verified that welding materials are controlled and disposed of in accordance with the ASME III and IX Codes and WFMC-1.
No items of noncomp1 iance were identi fied.
6..
Safet Related Pi in
- Review of ualit Records Unit
A review of 12" diameter, nuclear class 2, RHR pipe spool GBB-.118-2-3 quality records was performed.
The review included the following records: guality Control Inspection Plan P-1-1106, Receiving Pipe Spool; Statement of Conformance; Traveler P.C.
No. GBB-118-2-3; Form NPP-1; Radiographic, Report; and the material certifications.
The review confirmed that the documentation satisfies the ASME III Code and the Technical= Specification for Shop Fabricated Piping for Nucl ear Servi ce'856-M-201.
Pipe weld DBB-102-1-FW11 was selected for review of the quality docu-mentation.
The documents consisted of the Weld Card WR-5, filler metal withdrawal slips, Certified Reports of NDE, and the post weld heat treatment charts.
The review confirmed that the required tests, inspections, and procedures were employed as required by the ASME Code Sections III and IX and the guality Assurance Manual ASME Section III.
No items of noncompliance were identified.
7.
Containment Liner Plate Weldin Unit
The inspector observed that repair welding was being performed on the containment liner plate in an area where a clip attachment had been removed.
Further examination of the procedural control system disclosed that the clip removal was documented thr ough the Field Inspection Report, No. C-50-4326.
The FIR required only a liquid penetrant test after the clips were removed.
The cl.ip removal area observed by the inspector was ground below the normal plate surface into the base material.
This necessitated a repair weld to the plate to restore the thickness.
These kinds, of repairs'are-addressed:in the 1'incr plate specification C-50.
The FIR does not appear to be an adequate control system to assure welding and repair s are performed in accordance with the liner plate specificatio The licensee issued a Nonconformance Report No.
3451 to further document and control the liner plate repair observed by the inspector.
He further stated that adequate control requirements would be added to the Field Procedure FP-W-l, Procedure for Control of Welding.
This item is considered unresolved pending changes to the Field Procedure FP-W-1 and review by the NRC.
(387/79-04-02)
8.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations.
An unresolved item disclosed during the inspection is discussed in paragraph 7.
9.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on February 15,. 1979.
The inspector summarized the scope and findings of the inspectio ~
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