IR 05000387/1978021
| ML17138A492 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna |
| Issue date: | 12/22/1978 |
| From: | Durr J, Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138A491 | List: |
| References | |
| 50-387-78-21, 50-388-78-19, NUDOCS 7902060397 | |
| Download: ML17138A492 (9) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I 50-387/78-21 R
p N
50-387 Il I II CPPR-101 tf N
Pr iority Category A
Licensee:
v nia Power and Li ht Com any 2 North Ninth Street All town Penns lvania 18101 Facility Name:
Sus uehanna Units 1 and
Inspection at:
Berwick, Pennsylvania Inspection conducted:
December; 5-8, 1978 Inspectors:
.
P. Durr, eactor nspec or daM signed date signed Approved by:
e er c
n seT, ngsneering Support Section 1, RC8ES Branch date signed
)
xv d te igned Ins ection Summar
Unit.1 Ins ection on December.
5-8 1978 Re ort No. 50-387 78-21 td:Agt 'Igdt pp
d t,d inspection of piping storage, maintenance, and installation activities and documentation.
The inspection involved 24 inspector-hours onsite by one NRC regional based inspector.
Results:
No items of noncompliance were identified in the three areas inspected.
Unit 2 Ins ection on December 5-8 1978 Re ort No. 50-388 78-19
~dd:
A gf
"IP dt p
p d
I, d
1nspection of piping storage and maintenance activites.
The inspection involved ree inspector-hours onsite by one NRC inspector.
ults:
No items of noncompliance were identified in -the two areas inspected.
Region I Form 12 (Rev. April 77)
DETAILS Persons Contacted Penns lvania Power and Li ht Com an L. Ballard, Site QAE
- S. L. Denson, Assistant Project Construction Manager
- R. H. Featenby, Project Construction Manager
- J.
D. Green, Resident Nuclear QAE
- T. F. Oldenhage, Resident Engineer Bechtel Cor oration
- M. A. Drucker, Lead QAE
- H. F. Lilligh, Project QAE
- J. O'ullivan, Assistant Project Field Engineer
- B. W. Ott, Lead Welding QCE
- A. Spielhagen, Project field Engineer
- K. G. Stout, Assistant Project Field QCE
- C., Turnbow, Field Construction Manager
- denotes those present at the exit interview.
2.
Licensee Action on Previous Ins ection Findin s (Closed)
Unresolved item (387/78-12-08):
Radiography of pipe wal.l repair areas.
A review of Nonconformance Reports (NCR) disclosed that a repair had been performed on pipe spool HBC--115-1-12C which exceeded 3/8" or 105 of the wall thickness.
Repairs that exceed these limits are required to be radiographed by the ASME III Code.
The licensee determined that the repairs to pipe spool HBC-115-1-12C did, in fact, require radiography.
He issued NCR 2891 and performed the required radiography.
A review of the NCR file disclosed one more questionable repair that may have required radiography on NCR 550.
The repair was located adjacent to a circumferential butt weld and was radiographed during the routine weld joint examination.
The licensee issued a memorandum dated December 8, 1978, file No.
M204, 40.d, which directs the responsible-individuals to consider this requirement in future NCR dispositions.
This item is considered close (Closed)
Noncompliance (387/78-12-04}: Failure to calibrate oxygen analyzers.
The licensee is employing oxygen analyzers which are capable of being functionally calibrated by the operator prior to use.
The calibration is referenced against the atmosphere which is assumed to represent oxygen levels of 20.85.
A training course was held to instruct the quality control welding inspectors in the proper use of the oxygen analyzer.
The inspector interviewed four of the -licensee's quality control inspectors and verified that they had received training in the use of the analyzer and that they were aware of the procedural requirements.
The General Purging Specification -
1 was amended to incorporate the aforementioned functional check requirement.
This item is considered closed.
(Closed)
Unresolved item (387/78-16-01):
Main steam piping preheat/
postweld heat treatment practices do not meet ASME III - 1971 Code requirements.
The General Ele'ctric Company issued a letter, EAG-964, dated October 31, 1978, which states that a review was performed to assure the change in preheat practice does not affect the design or stress analysis and that other piping wall thicknesses are not involved.
This item is considered closed.
(Open) Unresolved item (387/78-12-06): Specification statements incon-sistent with NRC and ASME III Code requirements
.
The licensee amended the Gener al Purging Specification, GPS-1 to delete paragraph 2.10.
The revision of the General Melding Standards (GWS) has not been completed at this time.
This item remains open pending revision of the GWS series.
Plant Tour Unit
and
The inspector toured the Unit
and 2 containment and reactor buildings observing piping work in-progress, in-place storage practices, and area cleanliness.
He discussed the technical aspects of the work in progress with the construction craftsmen, supervisors, and quality control personnel.
No items of noncompliance were identifie.
Reactor Coolant Pressure Boundar RCPB
- Review of ualit Records Unit
The inspector selected five Piping Subassembly Fabrication, Installation, and Rework guality Control Inspection Records, P--1.10, for review relative to the requirements and guidance of the applicable guality Control Instruction.
In addition, he randomly selected attri butes from the inspection records and verified, where accessible, that the piping installations meet the requirements.
The following pipe spools were selected:
DLA-104-1-2 RD-N-A3 RS-N-A3 RS-N-A2 RD-1-Al No items of noncompliance were identified.
5'.
RCPB and Safet Related Pi e Weldin
- Observation of Work Unit
The inspector witnessed the liquid penetrant testing of the completed field weld DLA-104-1-FW1 and the lug removal areas on pipe weld GBC-101-6-FW3.
He verified that the tests were performed in accordance with procedure IPPT-300-39-03, Amendment 2, Revision D and that the test technicians were properly qualified.
He examined the preliminary fitup, alignment, rigging, handling, and tack welding of the wedge blocks for the recirculation pipe spool RS-1-lA.
The foregoing activities were performed, as observed, in accordance with the ASME III Code, the guality Assurance Manual ASME Section III, and Specification M204.
No items of noncompliance were identified.
Twenty-four small bore pipe socket welds were examined for compliance with the visual and dimensional requirements of the ASME III Code.
The following welds were examined:
SP-DCA-120-2FW18, 19, 22, 23, 24,,25, 29, 30 and
SP-DCA-119-1FW2, 3, 4, 7, 8, 9, 10,.11, 12, 13, and
SP-DCA-119-2FW10 SP-DCA-119-5FW19 and
Meld SP-HBC-138-1FW5, a socket welded flange, has internal drop-through/burn through of the pipe wall in the weld area.
This con-dition is not specifical-ly addressed by the codes or specifications for acceptability.
This item is unresolved pending further evaluation by the licensee and the NRC.
(387/78-21-01)
6.
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 5.
7; Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)
at'he conclusion of the inspection on December 8, 1978.
He summarized the purpose, scope, and findings of the inspectio g'
.
0