IR 05000338/1979047
| ML19262C146 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/12/1979 |
| From: | Economos N, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19262C135 | List: |
| References | |
| 50-338-79-47, NUDOCS 8002070016 | |
| Download: ML19262C146 (6) | |
Text
.
.
/
'o UNITED STATES
g NUCLEAR REGULATORY COMMISSION o
$
E REGION 11
.
f[
101 MARIETTA ST N.W.. SUtTE 3100 o,
%
o'
ATLANTA. GEORGIA 3o303
DEC 191979 Report No. 50-338/79-47 Licensee: Virginia Electric and Power Company Post Office Box 26666 Richmond, Virginia 23261 Facility Name: North Anna Power Station Unit 1 Docket No. 50-338 License No. NPF-4 Inspection at North A na S' clinir Mineral, Virginia L
Y ___.
..
Inspector:
/
' xC-x h n,L-o j JJ- /{- ? V.
o N. Econ
^
Date Signed hy'h-
/d - /) - M
'
Approved by:
'
A. R. Herdt, Section Chici, RC&ES Branch Date Signed SUMMARY Inspection on November 13-16, 1979 Areas Inspected This routine unannounced inspection involved 33.5 inspector-hours onsite in the areas of inservice inspection activities; welding and nondestructive activities parformed by the licensee during this outage; steam generator tube eddy current examination.
Results Of the four areas inspected no items of noncompliance or deviations were identi-fied in two areas; two items of noncompliance were found in two areas (Infrac-tion - Deposited weld metal thicknr.ss - weld procedures and welder qualification, paragraph 8; Deficiency - Ultrasonic instrument - screen height and amplitude control calibration records, paragraph 7).
.
.
1925 340 n 0 00 070 016
.
.
.
DETAILS 1.
Persons Contacted
-
Licensee Employees
- W. R. Cartwright, Station Manager 11. L. Travis, Mechanical Foreman - NDT K. B. Chrisman, Welding Forem a A. Vig, Level III Examiner Other licensee employees contacted included craf tsmen, technicians, security force members and office personnel.
Other Organizations Nuclear Energy Services Inc. (CONAM)
-
R. Lofgren, Level II Eddy Current Westinghouse - Nuclear Technology Division (W)
D. A. Sagar, Research Engineer - EC NRC Resident Inspector M. Kidd
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on November 16 with those persons indicated in Paragraph 1 above by T. Webster, inspector-in-charge.
The areas inspected included welding and nondestructive activities performed by the licensee during this outage. Findings (noncompliances) identified after the exit interview were discussed with the licensee by telephone. These findings are discussed in paragraphs 7 and 8.
The licensee had no disserting comments.
3.
Licensee Action on Previous Inspection Findings
.
'
Not inspected.
,
U' resolved Items
~1925 34i 4.
n Unresolved items were not identified during this inspectio.
.
.
-2-5.
Independent Inspection Effort Eddy Current Examination of Steam C-nerator (S/G) Tubes Eddy Current (EC) examination of S/G tubes was still in progress at the time of this inspection. This area was inspected and d1< cussed in paragraph 6 of IE RII: Report 50-338/79-43. The examination was being performed in accordance with RG 1.83 and VEPCO E.C. procedure NDT-14.1 Rev. 7.3.
Discussions with the licensee's representative disclosed the following:
S/G "C" - Examined 450 tubes at 400 KHz. These and tubes in the first two rows were being examined at lower frequencies e.g.,
100 KHz, 7.5KHz and sensitivities with different type coils. This effort was being perfomed so that W could analyze the data for possible ligament (support plate) cracking and tube denting. Two tubes in row 1, columns 51 and 60 will be plugged for le is.
Denting appears to be on both hot and cold leg sides, but more pronounced on the hot leg and around the upper supports on the cold leg side of the S/G.
S/G "B" - Approximately 115 tubes were examined at 400 KHz and 7.5 KHz.
Tubes in the first row were examined at 100 KHz with absolute and differental coils, 0.610" and/or 0.540" diameter.
.
S/G "A" - Examined 450 tubes at 400 KHz and 7.5 KHz frequencies. Tubes in the first row were examined at 100 KHz with absolute and differ-ential coils, 0.610" and/or 0.540" diameter.
Steam generators "A" and "B" exhibit conditions similar to those identified in S/G "C" above.
.
Within the areas examined no items of noncompliance or deviations were identified.
6.
Inservice Inspection (ISI) Data Review and Evaluation This record review was a followup effort performed to conclude work in this area which was initiated on a previous inspection documented in IE RII: Report 50-338/79-43. The code governing ISI activities during this interval is
, ASME Section XI (74S75).
'
Nondestructive records of pressure retaining welds selected for review were as follows:
1925 342
.
.
.
.
-3-Weld No.
Size-Diameter, Inches Sketch No.
34, 35, 36
VRA-1-4501 12 and 13
VRA-1-4503 5, 6 and 7
VRA-1-4502 2 and 3
VRA-1-4500
'These records were reviewed in the areas of major deviations in unit calibra-tion during examination; documentation of examination data; evaluation of recordable indications by qualified personnel consistent with code and procedural requirements.
Within these areas the inspector noted that in certain instances, where full examination of welds was precluded by geometry and/or welded attachments, the record did not define the inaccessible area. This matter was previously identified as unresolved item 338/79-43.
Within the areas examined, no items of noncompliance or deviation were identified.
7.
Nondestructive Examination Actitivies - VEPCO Records of NDE personnel qualified to Level I, II and III were reviewed in order to ascertain whether they reflected accomplishments consistent with SNT-TC-1A Recommended Practice.
In addition the inspector reviewed the following VEPCO, NDE procedures in order to ascertain whether they were consistent with code, ASME Sections V and XI, requirements as applicable.
NDT-4.1 10/7/75
"NDT Written Practice" NDT-3.1 2/17/76
" Preparation Issue and Control of NDT Procedures" NDT-9.1 2/17/76
" General Requirements for Nondestructive Testing" NDT 13.1 2/3/76
" Liquid Penetrant Examination" NDT-10.1 2/18/76
" Radiographic Inspection of Pipe and Plate Welds" NDT-11.1 2/17/76
" Ultrasonic Inspection of Longitudinal and Circumfer-
,
,
ential Butt Welds"
'
NDT-12.4 10.11.76
" Magnetic Particle Inspection Using Yoke Magnitization,
"
Wet and Dry Method" In addition the inspcetor reviewed the following records of recently performed NDT examinations ca safety-related system welds:
1925 343
,
.
-4-
.
a.
3/4" steam flow transmitter valve and pipe welds 1 thru 7.
Maintenance rept. NI-79-0116-1300, Line 32" SHP-1-601-Q2.
3/4" steam flow transmitter valve 1-FW-138, S/G
"C" welds 2 and 3 Maintenance Rept. #NI-79-1016-1040 b.
Mag. Particle Shop Weld #38 and base metal feedwater line
-
Inspection WFPD-22-601-Q2 c.
Radiography Welds No. 19 and 20 16" x.843 feedwater line
-
16-24-602-Q2 These NDE records were reviewed with specific interest in the areas of use of appropriate procedure, personnel qualification, extent of examination, evaluation of findings, completeness and accuracy of documentation.
Within these areas the inspector noted that Ultrasonic inspection procedure NDT-11.1 did not provide for screen height and amplitude control linearity calibration / standardization as specified in Article I-2100 of ASME Section XI.
This matter was discussed in detail with the licensee's representative during the inspection and later by telephone on November 21, 1979. The licensee representative stated that UT instruments are calibrated periodically by VEPC0 to manufacturers specifications but could not produce objective evidence to verify that screen hight and amplitude control linearities were within the range limits specified by the code. The licensee representative agreed to make the appropriate procedural revisions and generate the required records.
Failure to maintain records relating to activities affecting quality is in noncompliance in the deficiency category with Criterion XVII of Appendix B to 10 CFR 50. This finding was identified as item 338/79-47-02, Ultri ionic Instrument -screen height and amplitude control calibration records.
8.
Welding Activities - Repairs / Modifications Welding activities performed by VEPC0 personnel are controlled by ASME Code Section IX (74W76) - inspections and quality requirements are per USAS B.31.1 1967 and B31.7 1969 as applicable.
VEPCO's procedure " General Welding Procedure," W-1.10 Rev. 1 2/18/77 describes the welding prog am while procedure W-2.0 Rev. 1 7/22/77 " Control of Velding Materials", describes the welding consumables program.
Following are weld procedure specifications and related procedure qualifi-
. cation records that were reviewed in order to ascertain whether they were
-
consistent with applicable code requirements.
,
.
.... __-- -
,
-
.
'
-5-
.
Welding Procedure Qualification Specifications Process Range P8-10 GTA/SMAW 1/16"
.266" P8-11 GTA 1/16"
.296" PI-5 SMAW 1/16"
.730" P5-13 GTA/SMAW 3/16" - max.
P5-14 GTA/SMAW 1/16"
.436" Recently completed welds in the steam flow transmitter valves of S/Gs
"B"
"C" and on the hand hole cover blocking plates of S/Gs "B"
"C" were selected for review of quality records and visual inspection in the areas of surface finish, bead appearance, thickness of weld reinforcement, arc strikes, spatter, slag and other surface defects. In addition, performance qualification records of selected welders including those who fabricated the above welds were reviewed for compliance with code requirements.
Within these areas the inspector noted that qualification records of welders and weld procedures involving a combination of weld processes e.g., GTA/SMAW did not indicate the weld metal thickness deposited by each process as required by Section IX QW-201.3 and QW-351. The inspector discussed this matter with the licensee representative during the inspection and by tele-phone on November 21, 1979. The licensee agreed to take appropriate steps to correct this probleo.
Failure to accomplish activities in accordance with code and/or procedural requirements is in noncompliance in the infraction category with Criterion V of Appendix B to 10 CFR 50.
This finding was identified as item 338/79-47-01, Deposited welding metal thickness - weld proc.-dures and welder qualifications.
-
.
eS
.
1925 345