ML19260A538
| ML19260A538 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/20/1979 |
| From: | Mattia J, Mcgaughy R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19260A533 | List: |
| References | |
| 50-352-79-07, 50-352-79-7, 50-353-79-07, 50-353-79-7, NUDOCS 7911210420 | |
| Download: ML19260A538 (6) | |
See also: IR 05000352/1979007
Text
.
.
U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
Region I
50-352/79-07
Report No.
50-353/79-07
50-352
Docket No.
50-353
CPPR-106
License No. CPPR-107
Priority
Category
A
--
Licensee:
Philadelphia Electric Comoany
2301 Market Street
Philadelphia, Pennsylvania
19101
Facility Name:
Limerick Gneration Station, Units 1 and 2
Inspection at:
Limerick, Pennsylvania
Inspection co ducted: July 5, 6, and 9,1979
Inspectors:
A
9 [, F
j
,.
M Mattia, Reactor Inspector
date signed
cate signed
date signed
Approved by: [/1/ M/h@#.5
0/79
R. McGau'ghy, Chie[d/ojects Section,
/ date signed
'
RC&ES Branch
Inscection Summary:
Unit 1 Inspection on July 5, 6, and 9, 1979 (Report No. 50-352/79-07)
Areas Inspected:
Routine, unannounced inspection by regional based inspector
of work activities and records associated with safety related piping.
The
inspector also performed a plant tour inspection. The Unit 1 inspection
involved 23 inspector-hours on site by one regional based inspector.
Results: Of the two areas inspected, no items of noncompliance were identified
in one area, two apparent items of noncompliance were identified in one area
(Infractions - (1) Failure to follow design requirement for welding of safety
related pipe restraint, Paragraph 4; (2) Failure to follow design specificationc
~
requirement for the welding of temporary attachments to containment liner
Paragraph 4).
Unit 2 Inspection on July 5, 6, and 9, 1979 (Report No. 50-353/79-07)
Areas Inspected:
Routine, unannounced inspection by regional based inspector.
The inspector performed a plant tour inspection.
The Unit 2 inspection involved
2 inspector-hours on site by one regional based inspector.
.
Results:
No items of noncompliance were identified.
138i
320
Region I Form 12
(Rev. April 77)
7911210
.
DETAILS
1.
Persons Contacted
Philadelphia Electric Company
- D. Clohecy, QA Engineer
- J. Corcoran, Field QA Branch Head
D. DiPaolo, yA Engineer
J. Evans, QA Engineer
- J. Fedick, Construction Engineer
- S. Genca, Assistant QA Engineer
- D. Marascio, QA Engineer
Bechtel Power Corporation
- T. Altum, Lead Field Welding Engineer
- B. Dragon, QA Engineer
- T. Fallon, Assistant Project Field QC Engineer
- H. Foster, Assistant Project Field QC Engineer
- R. French, Field Contracts Administrator
- G. Harper, Subcontracts Field Engineer
- M. Jan, Area Engineer
- G. Kelly, QA Engineer
- E. Klossin, Project QA Engineer
- R. Leingang, Assistant Project Field Engineer
M. Norman, Assistant Lead QC Weld Engineer
- L. Pons, Resident Engineer
- J. Reiney, Project Construction Manager
- R. Sevo, Lead OA Engineer
T. Waters, Lead QC Weld Engineer
- R. Zittel,. Area #1 Superintendent
- Denotes those in attendance at the Exit Interview
2.
Licensee Action on Previous Inspection Findings
(Closed) Noncompliance (352/79-02-05):
Failure to properly store safety
related stainless steel pipe spools in laydown area.
The inspector reviewed
four licensee audit reports, Nos. P-121, P-122, P-123, and P-127, which
reported the results of the audits the licensee conducted on pipe storage
in the laydown area and also in the plant buildings.
The audit results
were properly documented and timely corrective action had been taken.
The
inspector inspected the laydown area for storage of safety related stainless
steel pipe spools.
The inspector noted that nine stainless steel spools
were not stored in accordance with the requirements of the storage procedure.
138i
Q1
.
3
The licensee identified these spools (DCA-201-1-1 thru DCA-201-1-6 and DCA-
101-1-2,
-3, and -4), as the surplus spools mentioned in their audit
report P-127.
The inspector verified that these spools were surplused;
however, the Bechtel memo which was dated June 12, 1979, stated that the
above spools can be used in whole or canibalized for use in rework of other
systems if the material is compatible with that system. The inspector
informed the licensee that since these pipe spools may be used in a safety
related system, they have to be stored in accordance with the requirements
of the Bechtel Storage Procedure.
Corrective action was taken and the nine
pipe spools were stored in accordance with the Bechtel Job Rule G-8 Require-
ment.
No items of noncompliance were identified.
3.
Plant Tour (Units 1 and 2)
The inspector toured the Units 1 and 2 containment and reactor buildings
observing work in-progress, inplace storage practices, area cleanliness,
and completed work. The inspector examined work items for any obvious
defects or noncompliance with Regulatory Requirements.
The following item
was identified during this plant tour inspection:
a.
The inspector noted a partial weld buildup on a safety related pipe
located in Area 15 at elevation 181', which was adjacent to Hanger
HBB-ll 7-ill 8.
The licensee stated that a nonconformance report, No.
3615, was issued for this weld.
It appears that this weld repair was
made without Bechtel Quality Control being notified.
The surface
condition prior to the repair and the depth of the repair are unknown.
The licensee has issued a Quality Action Request (QAR #F-128) to
Bechtel stating that this is a recurrence of unauthorized welding and
that if corrective action is not effective, a Bechtel Management
Corrective Action may be warranted.
The inspector informed the licensee
that this item is considered unresolved pending review of Bechtel's
corrective action regarding this matter (352/79-07-01).
4.
Reactor Coolant Pressure Boundary - Observation of Work (Unit 1)
The following listed activities were observed to determine that the require-
ments of selected portions of the ASME III and IX Codes, the Bechtel 0A
Manual (ASME Section III) and the Bechtel Specifications P-319 (Revision
7), P-301 (Revision 6), and P-322 (Revision 1) had been adhered to:
1381
- 22
.
.
4
Primary Steam and Feedwater Piping Restraints
a.
The inspector inspected pipe restraint weld joints in various stages
of completion.
The restraints inspected were identified as PR-9, PR-
42, PR-47, PR-12, PR-43, PR-il, and PR-44.
The following items were
found during this inspection:
-
(1) A backing bar is used when welding the two circumferential pieces
of a restraint together. The inspector notes that the backing
bar is attached to the restraint ,by various amounts of weld,
since there are no requirements for the amount of weld to be used.
There are instances where the backing bar is either tack welded
on both edges, or one edge is welded to the restraint.
The
inspector also could not find in various documents any acceptance
criteria for what is the allowable gap between the backing bar
and restraint. The inspector questioned the QC engineer what
te used i v an acceptance criteria.
He stated that his criteria
was " tight against the restraint." The inspector informed the
licensee this is considered unresolved pending review of their
evaluation of this situation (352/79-07-02).
(2)
The inspector also noted during his inspection of the pipe restraints
that the restraints supplied by Chicago Bridge and Iron had a
cope or access hole where the horizontal and vertical weld joints
coincide.
This was apparently done to assure that a full penetra-
tion weld is obtained. The Mississippi Valley Company supplied
restraints do not have an access hole at the weld joint junction,
therefore, it is questionable that the required full penetration
weld can be obtained. The licensee stated that this item will be
evaluated.
The inspector informed the licensee this item is
considered unresolved pending review of their evaluation (352/79-
07-03).
(3)
During the inspection of completed restraint, identified as PR-9,
the inspector noted that the backing bar was welded on one edge
only and was warped. The completed weld joint (horizontal) was
approximately 1/4 of an inch misaligned.
The weld joint was
accepted by QC engineer on April 9, 1979.
A review of Drawing C-
292, Revision 8, indicated that a Field Change Request No. C-
5542F was issued on April 9,1979 to provide for fitup tolerances
for restraints.
This request was approved as Field Design Change
No. 5 and it requires that when there is a misalignment (1/2"
maximum) the backing bar is te be removed after one side of weld
joint has been welded and a sr. to one taper shall be provided at
the weld joint where the backing bar was. This was not done.
This is contrary to the Limerick Procedure PSP-G-6.1, Revision 2,
1381 m
.
.
5
which requires a new inspection for additional work to be accom-
plished to completed work due to an engineering change. The
licensee was informed that this was an item of noncompliance
(352/79-07-04).
(4) De ing the above inspection of restraints, the inspector also
noted that temporary brackets (used for construction aids) were
welded to the containment to temporarily support or align piping.
The inspector asked to see documentation for these temporary
welds to determine if they were being controlled. The inspector
found that these welds were treated as nonsafety related, therefore,
Quality Control was not involved and weld history information was
not documented.
Several of the welds were made on liner penetra-
tions (penetrations X9A and X98), which were 1-1/2 inches thick,
therefore, requiring a minimum preheat of 2000F.
The licensee was
informed that this was contrary to the requirements of Bechtel
Specification C-2, which require that weldina of temporary attach-
ments be controlled (use of qualified welders and proce_ures,
d
.
preheat, and nondestructive examination of liner after removal
of temporary attachment.), and that this is an item of noncompliance
(352/79-07-05).
5.
Reactor Coolant Pressure Boundary - Review of Records (Unit 1)
A review of two pipe spool Quality Assurance Document packages was performed
to verify compliance with Specification P-312, the ASME III Ccde, and
Regulatory Requirements.
The following pipe spool document packages were
reviewed:
Pipe Spool
Size
Nuclear Class
Material
DCA-105-1-3
20"
1
304 Stainless Steel
DCA-105-1-4
20"
1
304 Stainless Steel
The documents reviewed consisted of the material test reports, shop fabrica-
tion and inspection records.
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, items of noncompliance,
or deviations. Three unresolved items disclosed during this inspection are
discussed in Paragraphs 3 and 4.
1381
324
.
.
6
7.
Exit Interview
The inspector met with licensee representatives (denoted in Paragraph 1) at
the conclusion of the inspectio. cn July 9, 1979.
The inspector summarized
the purpose and scope of the inspection and the findings.
1381
325