IR 05000328/1980022
| ML19345F767 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/02/1981 |
| From: | Herdt A, Zajac L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19345F760 | List: |
| References | |
| 50-328-80-22, NUDOCS 8102190249 | |
| Download: ML19345F767 (5) | |
Text
pa nacg
o UNITED STATES 8\\.,;
NUCLEAR REGULATORY COMMISSION-ms c
REGION 11
- o, h j
101 MARIETT A ST., N.W., SUtTE 3100
'%#
jf AT LANT A, GEORGI A 30303
.....
Report No. 50-328/80-22 Licensee:
Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Facility Name: Sequoyah Docket No. 50-328
'
License No. CPPR-73 Inspection at-quoya Nuclear Plant near Chattanooga, Tennessee
/
/'
Inspector:
L.
f Date Signed
/
Approved by:
KHerdt, Section Chief, RC&ES Branch
' Date Signed Inspection on November 17-20, 1980 Areas Inspected This routine, unannounced inspection involved 30 inspector-hours on site in the areas of IE Bulletin 80-08, Examination of Containment Liner Penetration Welds; Previous noncompliance 80-11-02, Failure of Ultrasonic examination procedure to provide adequate instructions and failure of personnel to comply with procedural requirements; previous unresolved item 80-11-03, apparent noncompliance of using notch for calibration of ultrasonic equipment; previous unresolved item 80-11-01, potential inadequate preservice/ inservice inspection program; review of quality records for reactor coolant pressure boundary and safety related piping; and observation of completed reactor coolant pressure boundary piping welds.
Resul ts Of the six areas inspected, no items of noncompliance or deviation were identified in five areas; one violation was found in one area (Failure of weld to blend smoothly into adjacent base metal, paragraph 7).
81021go 1 k
.._
-
-
.
.
.
-
.
.,
,
.
l DETAILS 1.
Persons Contacted Licensee Employees
- G. G. Stack, Construction Project Manager
,
- T. B. Northern Jr., Constrte. ion Engineer
- D. L. McCloud, Nuclear Power QA Supervisor
- M. Gothard, PSI /ISI Engineer
- W. J. Glasser, Nuclear Power QA Coordinator
- L. W. Jones, Construction Supervisor Mechanical & Welding Inspection
- D. W. Mack, Assistant Construction Engineer W. Andrews, QA Supervisor - Nuclear Power R. Lynskey, QA Engineer - Nuclear Power i
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on November 20, 1980 with those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings a.
(Closed) Deficiency (328/80-11-02) Failure of Ultrasonic procedure to provide adequate instructions and failure of personnel to comply with procedural requirments.
The inspector reviewed the j
revisions dated September 1980 made by the licensee to ultrasonic procedures N-UT-1 and N-UT-6 and concluded that the corrective actions taken were satisfactory.
Therefore this item is closed.
b.
(Closed) Unresolved Item (328/80-11-03) Apparent noncompliance of using notch for calibration of ultrasonic equipment. The licensee performed additional testing as requested and forwarded the l
results of this testing in a letter dated July 31,1980 to the Director of Nuclear Reactor Regulation.
This completes the corrective action requested.
Therefore this item is closed.
c.
(0 pen)
Unresolved Item (328/80-11-01)
Potential inadequate pre. service / inservice inspection program.
The licensee has prepared a draft which revises the Operational Quality Assurance Manual, Part II, Section 5.1 to include the QA functions identi-fied in NRC Report No. 50-328/80-11 as being inadequately addressed.
The inspector reviewed this draft and concludes that it adequately l
addresses the QA functions.
This item will remain open until the t
revision is formally issued.
_.
_ __
_ -
_ _ _ _.
___ _. _. _ _ _ _
_.
_.
_
-- - - _ _
'
i
'
l
,
d
i
.
4.
Unresolved Items l
Unresolved items were not identified during this inspection, 5.
Reactor Coolant Pressure Boundary Piping - Review of Quality Records j
The inspector reviewed the installation inspection records for the welded joints listed below to ascertain whether the applicable
,
requirements were met. The applicable code is the ANSI Standard B31.7, i
1969 Edition and the 1970 addenda.
Joint identification Pipe Size & Mat'l 2 RC-1 29" Stainless steel 2 RC-6 31" Stainless steel
,
'
2 RX-15 4" stainless steel 2 RX-19 4" stainless steel 2 RX-23 4" stainless steel Specific areas reviewed were:
.
a.
scope of inspection performed and recorded b.
records confirm chat specifications and installation procedures, including cleanliness requirements, were met.
i No violations or deviations were identified.
6.
Safety Related Piping - Review of Quality Records i
a.
The inspector reviewed the installation records for the pipe spools listed below to ascertain whether the applicable requirements were met.
The applicable code is identified in paragraph 5.
Spool Identification Pipe Size
l PC 2CC-25C 8"
PC RHR-13 12" PC 2CS-33 8"
PC 2RHR-52 3"
PC 2SI-85 4"
PC 2RHR-19A 8"
PC 2CVC-41 3"
Specific areas reviewed were:
(1)
installation checklists, isometrics, etc. which document that piping was installed in conformance with applicable requirements
- _ _ _. -._ - - _ - _.._,.. _,_, _. _ _ _ _. _
_
- - -
.
.
..
-. -..
-.
- -
-
-.
.
.
(2) nondestructive examinations (3)
hydrostatic testing (4)
cleanliness (5) qualifications of examination personnel
,
b.
During a review of the records, if was noted that the visual inspection record lists 12 weld conditions or defects that the visual examiner is to checkoff as acceptable or rejectable.
However, at least four weld defects, cracks, root concavity, root oxidation (sugaring) and crater pits, are not listed on the record for evaluation.
In discussion with the QC supervisor, the inspector was advised that the visual examiner also signs the record indicating
he has examined for all defects and weld conditions. The inspector stated that all weld conditions and defects should be listed in
.
order to provide added assurance that the visual examiner did not overlook or forget to evaluate some defects or weld conditions.
The QC supervisor agreed to evaluate the possibility of including l
'
all weld defects and conditions to be visually evaluated, on the
.
visual inspection record.
This will be Inspector Followup Item l
Number 328/80-22-02, " Inadequate Visual Inspection Record Card".
No violations or deviations were identified.
7.
Reactor Coolant Pressure Boundary Piping - Observation of Completed Welds The inspector selected the completed welds for the joints listed l
a.
below to ascertain whether the applicable requirements were met j
with regard to finished surface condition. The applicable code is identified in paragraph 5.
Joint Identification Pipe Size & fiat'l System 2VH 00048 8" stainless steel Upper head Injection 2RX 00064 3" stainless steel Reactor Coolant 2RX 00065 3" stainless steel Reactor Coolant 2RX 00057 3" stainless steel Reactor Coolant 2RX 00058 3" stainless steel Reactor Coolant 2RH 00123 6" stainless steel Residual Heat Removal 2RH 00324 6" stainless steel Residual Heat Removal f
2RC 00015 31" stainless steel Reactor Coolant l
l b.
Four joints (2RX 00064, 00065, 00057, and 00008) which had been visually accepted by the licensee did not have an acceptable l
surface condition in that the weld did not blend smoothly into the adjacent valve.
Figure 1-727.3.1 and paragraph 1-727.4.2(c) of
l Chapter 1-V of ANSI B31.7 specifies a 3-1 slope across the weld
,
joining a heavy walled valve to a thin walled pipe.
The subject joints do not have a 3-1 transition, but rather have a notch formal between the weld and adjacent valve.
These joints are in violation with 10 CFR 50.55a Codes and Standards for Class I Piping as implemented by FSAR, Table 3.2-4.
This item is
._ _
. -
..-
-_
_ _ -
_
.
.
---
.
.
.
.
Violation Number 328/80-22-01, " Failure of Weld to Blend Smoothly
into adjacent Base Metal".
Within the areas examined, no items of noncompliance or deviations were
.
noted except for the violation identified above.
8.
IE Bulletin 80-08 - Examination of Containment Liner Penetration Welds IE Bulletin 80-08 was forwarded on April 7, 1980 and requested licensee's
to determine if their facility contained the flued head design for penetration connections, or other designs with containment boundary butt welds between the penetration sleeve and process piping as illustrated in Figure NE 1120-1, Winter 1975 addenda to the 1974 and later editions of the ASME Boiler and Dressure Vessel Code.
If the
,
licensee's facility does contain this design then the licensee was requested to determine if welds were made with a backing ring and whether or not volumetric examination was conducted by radiography.
The Bulletin indicates that weld joints with a backing ring that have not been radiographed, are of particular interest as they are potentially defective.
In response to the Gulletin TVA forwarded a letter dated July 8,1980 l
stating that for the Sequoyah Nuclear Plant, penetrations contain the flued head design, butt welds without backing rings were used, and that
'
these welds were radiographically examined.
During the visit to Sequayah, the inspector requested the radiographs and records for several of the penetration welds, listed below, in order to review the
!
radiographs for compliance to code requirements.
Penetration No.
Pipe Size & Mat'l X-13B 52" carbon steel X-13C 52" carbon steel X-128 30" carbon steel X-44 20" carbon steel X-48B 16" carbon steel X-81 16" carbon steel During review of the radiographs and records, it was determined that the welds radiographed were not the ones addressed in the Bulletin.
In discussion with the licensee it appears the welds described in the Bulletin were fabricated by a vendor, Tube Turns in Louisville, KY.,
thus the radiographs and records are not available at the Sequoyah site.
Discussions will be held separately with TVA as to what action should be taken to review the vendor's radiographs and records.
r J