IR 05000413/1980006
| ML19323H510 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/23/1980 |
| From: | Herdt A, Kleinsorge W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19323H495 | List: |
| References | |
| 50-413-80-06, 50-413-80-6, 50-414-80-06, 50-414-80-6, NUDOCS 8006130065 | |
| Download: ML19323H510 (8) | |
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UNITED STATES l'
e't NUCLEAR REGULATORY COMMISSION
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101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, G EORGIA 30303
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Report Nos. 50-413/80-06 and 50-414/80-06
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Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242
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Facility Nane: Catawba Nuclear Station Docket Nos. 50-413 and 50-414 License Nos. CPPR-116 and CPPR-117 Inspection a L l'e South Carolina
_,M M /A[ /ffd Inspector: /'.
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W. P.
e ns rg Date Signed e
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d3 Approved by:
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A. R.' Herdt, S6ction Chief, RCES Branch Bate' Signed SUMMARY Inspection on April 1-4, 1980 Areas Inspected This routine, unannounced inspection involved 29 inspector-hours on site in the areas of Reactor Coolant Pressure Boundary Piping (Unit 1), Safety Related Piping (Units 1 and 2), Containment (structural steel welding) - observation of work and work activities (Units 1 and 2), and safety related structures (welding I) -
observations of work and work activities (Units 1 and 2).
Results Of the four areas inspected, no items of noncompliance or deviations were identified in three areas; one item of noncompliance was found in one area (Deficiency - Fail-ure to Provide Identifiable Heat Number on WeJd Record - Paragraph 6b(2)).
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DETAILS 1.
Persons Contacted
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Licensee Employees
- J. R. Wells, Corp., QA Manager
- D. 'G. Beam, Project Manager
- D. L. Freeze, Project Engineer
- R. A. Morgan, Senior QA Engineer R. G. Rouse, QA Technician J. C. Shropshire, QA Engineer (QAE) Mechanical, Welding
- S. W. Dressler, Senior Construction Engineer
- L. R. Davison, Senior QC Engineer
- W. O. Henry, QA Manager, Construction Other licensee employees contacted included eight construction craftsmen, three technicians, and three engineers.
Other Organizations Hartford Steam Boiler Inspection and Insurance Company
- C. F.Toegel, Authorized Nuclear Inspector (ANI)
NRC Resident Inspector
- G. F. Maxwell Richmond Engineering Company (RECO)
J. R. Palmore, QC Inspector
- Attended exit interview
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2.
Exit Interview The inspection scope and findings were summarized on April 4,1980 with those persons indicated in Paragraph 1 above. The inspector identified the areas inspected and discussed in detail the item of noncompliance. No dissenting comments were received from the licensee.
3.
Licensee Action on Previous Inspection Findings
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(0 pen) Infraction 50-413/79-23-01:
Failure to Establish Adequate.
Measures for handling and storage of Equipment and Materials. The licensee's letter of February 11, 1980, responding to this item of noncompliance, requested re-classification and additional examination of this item based on erroneous information given to the inspector by
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the licensee at the time of the inspection. The inspector re-examined the item and stated that a supplemental response to the licensee's February 11, 1980 letter would be required. The licensee committed to supplement his response by April 25, 1980.
b.
(Open) Unresolved Item 50-413/79-23-02, 50-414/79-23-01: High Temper-ature Oven Calibration. The inspector discussed this item with the licensee, who stated that the site was revising Duke Construction
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Procedure CP-39 Revision 2 " Reconditioning of Low Hydrogen Coated Electrodes" to address this matter. This item remains open.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Independent Inspection Effort (Units 1 and 2) The inspector conducted a general inspection of the Unit I and 2 containments, Auxiliary building, fuel building, pipe fabrication shop and electrode issue station to observe construction progress and construction activities such as welding, material handling and control, housekeeping and storage.
In the areas examined no items of noncompliance or deviations were identified.
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Reactor Coolant Pressure Boundary Piping (Unit 1)
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a.
Observation of Work and Work Activities (1) The inspector observed non-welding work activities for reactor coolant pressure boundary (RCPB) piping. The applicable code for installation of RCPB piping is the ASME B and PV code, 1974 edition plus addenda through summer 1974.
(a) The following piping " runs" were inspected for compliance with installation specifications of plans.
From (Weld No.)
To (Weld No.)
Plan
11 CN-INC-33
11 CN-INI-148
11 CN-INI-149
14 CN-INV-483
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CN-INV-484
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(2) The inspector observed field welding of reactor coolant pressure
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boundary piping.
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(a) The inspector examined weld joint fitup prior to welding, to determine whether weld identificati u/ location, joint prepara-tion and alignment, evidence of QC verification meet applicable procedures. The following weld joint was examine._ - _ _ -
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Joint Number Isomeiric System Pipe Size NV-474-9 INV-474 Chemical 2"
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Control (b) Observations of weld material control included; identifica-tion, segregation, oven temperatures, issue slips and control
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of unused material at issue stations and work areas.
(c) During observation of welding activities there oid appear to be an sufficient number of qualified inspection personnel at
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the work site l
b.
Review of Quality Records (1) Records of the following items were selected for review to ascertain
whether they (records) were in conformance with applicable require-
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ments relative to the following areas: Material test reports /certi-fications; vendor supplied NDE reports; site receipt inspection; storage; installation; vendor nanconformance reports.
Item System 1" 6000# Special Welding Reactor Coolant Flow orifice boss 10" Sch 140 pipe Reactor Coolant 6" Sch 160 pipe Safety injection 10" x 10" x 6" Sch 140 x 140 Safety Injection x 160 reducing tee 10" Sch 140 90 degree Safety Injection Elbow
2" 6000# 90 degree Elbow Chemical and Volume control 2" Sch 160 pipe Chemical and Volume Control
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(2) On April 4,1980 during the review of records for a 1" 6000#
special welding flow orifice boss installed with weld no.1-NC-33-7 into the reactor coolant system, the inspector noted that the heat number for the above boss was not identifiable on the
" weld process Control Sheet" for the above joint. This is in
.., noncompliance with 10 CFR 50 Appendix "B" criterion XVII... Based on additional review this appears to be an isolated case of noncompliance and is therefore a deficiency in lieu of an -
infraction.
This is item 413/80-06-01 " Failure to Provide Identifiable Heat Number on Weld Record". '
Within the area examined, no items of noncompliance or deviations except as described in paragraph 6.b(2) were identifi,ed.
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7.
Safety-Related Piping (Units I and 2)
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Observation of Work and Work Activities (Units I and 2)
(1)
(Unit 1) The inspector observed non-welding work activities for safety-related piping outside of the reactor coolant boundary.
For the applicable code see paragraph 6.
The following piping
" runs" were inspected for compliance with installation specifica-
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tions of plans.
( From Weld No. )
To (Weld No.)
Plan
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CN-1BB-79
16 CN-1BB-52 (2)
(Unit 1 and 2) The inspector observed field welding of safety-related piping outside the reactor coolant pressure boundary at various states of weld completion.
(a) The inspector examined weld joint fitup, prior to welding, to determine whether weld identification / location, joint preparation and alignment, evidence of QC verification meet applicable procedures.
The following weld joints were examined.
Joint No.
Unit Isometric System KC-41-19
2-KC-41-19 Component Cooling W-17-7
2-FW-17-7 Refueling Water (b) The inspector examined weld joints where the root pass (only)
has been completed to determine; weld / welder identification, qualified welder / weld procedure, physical appearance of weld and evidence of QC verification. The following weld joints were examined.
Joint No.
Unit Isometric System NV-31-7
2-NV-31-7 Chemical and 7olume Control FW-17-7
2-FW-17-7 Refueling Water FW-17-6
2-W-17-6 Refueling. Water (c) The inspector examined weld joints of pipe to pipe / fitting I
l (PPF) and pipe to components (PC) where welding was beyond
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the root pass to determine; weld / welder idet. *ication, l
qualified welder / weld procedure, periodic cher':0 f welding i
variables, use of specified weld materia), proper interpass
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l temperature and where applicable. pre-heat ad post-weld heat
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treatment and physical appearance of weld (e.g. starts,
-tops, undercut and surface imperfections). The following joints were examined.
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Joint No.
Unit Isometric Type System BB-81-9
1-BB-81-9 PPF Steam Generator Blow-down
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Recycle KC-41-21
2-KC-41-21 PPF Component Cooling
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(d) The inspector observed activities at the weld material station see paragraph 6a(2)(b).
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c.
Review of Quality Records (Unit 1)
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The inspector reviewed the quality records for safety-related piping components and installation outside the reactor coolant pressure boun-dary. The records review included, where applicable, the following; material test reports / certification records, vendor manufacuring certifications, NSSS manufacturers quality release forms. Receiving inspection reports (including records of disposition of nonconforming materials) installation records (checklists, isometrics, NDE and inspection, hydrostatic testing, cleanliness, qualification of inspec-tion personnel).
Piping Component Size System 45 degree Elbow 2" 3000#
SGBR*
Pipe 2" sch 80 SGBR Socket weld Coupling 2"sch 80 SGBR Tee 4" sch 80 SGBR Pipe 4" sch 80 SGBR 1/2 Coupling 3/4" 3000#
SGBR
- SGBR - Steam Generator Blowdevn D'<ycle Within the areas examined, there were no items of noncompliance or deviations identified.
8.
Containment (Structural Steel Welding) - Observation of Work and Work Activities (Units 1 and 2)
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The inspector observed field welding activities associated with steel, containment structures and steel supports. for major equipment within the containment at various stages of weld completion.
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The inspector observed welding activities where joint fitup and align-a.
ment were complete (but welding had not been started) to determine conformance with applicable specifications and procedures in the areas i
of: weld identification, joint fitup and alignment -and evidence of QC verification.
Structure / Support Weld No.
Unit Applicable Code
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Crossover 1-3-2-3-1-4
ASME III, W77 (Class NF)
Leg restraint Steam 1-L-2D-20
AWS D1.1 1975
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Generator Inclosure Platform Det D on
AWS D1.1 1975 Support CN-1080-33 Structure b.
The inspector observed welding activities where welding was in progress to determine conformance with specifications and procedures in the areas of; weld identification, specified weld procedures, qualified welders, specified weld material, specified purge (if applicable); repair proce-dures, specified NDE being performed and periodic checks of welding variables.
Structure / Support Weld No.
Unit Applicable Code Containment 215-H
ASME III S72 (Class Butt NE)
Containment 216-H I
ASME III S72 (Class NE)
Butt Steam 2-L2GB
ASME III S76 (Class NF)
Generator Lower Laternal Support The inspector observed activities at the DPC Weld Material issue station c.
see paragraph 6a(2)(b).
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During observation of welding activities there did appear to be a -
suf fjcient number of qualified inspection personnel at the work site.
Within the areas examined, there were no items of noncompliance or deviations identified.
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Safety-Related Structures (Welding I) - Observation of Work and Work Activi-
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ties (Units 1 and 2)
The inspector observed field welding activities assocaited with safety-related structures and supports outside containment during various stages of weld completion. Observations were made in order to determine whether the requirements of applicable specifications, standards, work and/or inspection procedures are being met for the activities involved and in the following stages of weld completion:
The inspector examined weld joint fitup, prior to welding, to determine a.
, whether weld identification / location, joint preparation alignment and QC verification are in ccnformance with existing requirements.
Structure Isometric Unit Applicable Code Vent Stack CN-1210-12
AWS DI.1-1975 Plenum Cable Tray CN-1212-04, 05
AWS DI.1-1975 Supports b.
The inspector examined weld joints where welding is in progress to determine whether ucld identifiecation, weld procedures, welder quali-fication, weld material, defect removal (if applicable,) specified NDE and periodic checks of welding variables are in conformance with existing requirements.
Structure Isometric Unit Applicable Code Vent Stack CN-1210-12
AWS DI.1 - 1975 Plenum Cable Tray CN-1212-04, 05
AWS D1.1 - 1975 Supports P.efueling Weld 5 Water Storage D-76-412
ASME III, Wicter 1975 Tank Class 2 c.
The inspector observed activities at the DPC W' eld Material issue station - see paragraph 6a(2)(b).
d.
During observation of welding activities there did appean to be a sufficient number of qualified inspection personnel at the work site.
Within the areas examined, there were no items of noncompliance or deviations identified.
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