IR 05000413/1981024
| ML20039D087 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/10/1981 |
| From: | Bryant J, Van Doorn P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20039D071 | List: |
| References | |
| 50-413-81-24, 50-414-81-24, NUDOCS 8112310303 | |
| Download: ML20039D087 (6) | |
Text
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'* d 'o UNITED STATEsi ~ ' - 8 NUCLEAF. REGULATORY COMMISSION '. o
E REGION 11 -# "o% ,/
.101 MARIETTA ST N.W,CUTTE 3100 s fj , e ,] ATLANTA, GEORotA 30301 ~ _ , z . n y w)
w $ -e - , 1/ ' - , c . - Report Nos. ' 50-413/81-24 and 50-414/81-24 ~, p , - , . ~ .m ' ' Licensee: Duke Power Company 422 South Church Street
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p , , , ^ " Charlotte, NC 28242 . g ;e - ? y e ' W ' Facility Name: Catawba . , ,.., j ~ Docket-Nos. 50-413 and 50-414 , ,s -
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.,- , License Nos. CPPR-116 and CPPR-117 . % Inspection at Catawba site near Rock Hiil,'S'outh Carolina -
.e y , d d cd,o C, M /[[N h ;J Inspector:_P. K. Van (Doorn // Date Signed, .. v e Approved by: /WMA,.,
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gd. Bryant p ection Cnief, Division of .Date Signe<j -
y Resident and Reactor Project Inspection yv s ,- , "' SUMMARY e %, Inspection on September 26 - October 25, 1981 >- , , - e.
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e ,' , .. ' Areas Inspected . - , jfef', f , This routine announced inspection involved 139:i'nspecto'r-hours on site >i.rythe; .. , areas of safety-related support and restraint ~1} stems JUnit.1); electriceF ,
' (cables and terminations) - observation of work and 1ri acdvities '(Unif 2); .,/1 - electrical (components and systems) - observation,of'wo'ri and work activ'ities.
/ ' (Unit 2); reactor coolant pressure boundary piptr.g '{ welding) 4-observation. afatork g , and work activities (Unit 1); safety-related pipivig7(welding) - observation af 7 - ' work and work activities (Utiit 1); followup of licensee 50.55(e)= items; and NRC -' identified items (Units 1 and 2).
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, - Of the seven areas inspected, no violations or= devntions were identified in six areas; one violation was found in one area (Inadequate' evaluation of lack of fusion, weld defect - paragraph 3.c).
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, ," y y / , .- ~, , , -- _ DETAILS 1.
Persons Conta;ted sy .. !.,;' 't ' flicensee Employ,ees -
. ,,a, x , ,, / r/c W. H. Owen, Senior Vice President, Engineering and Construction D, j,t. b Dail, Vice President Design Engineering y/ F - - R.- L. Dick, Vice Presideist Construction V, ML'
- J.'-C'. Rogers, Project fianager
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R. Wells, Corporate QA !!anaaer
- S. W. Dressler, Senior Construction Engineer
- W. O._ Henry, QA Manager, Technical Services m L'. R. Davison, QA flanager, Projects Division
' "R. A. Morgan, Project QA Engineer ~ ,
- J. C. Shropshire, QA Engineer Supervisor
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- H. D. flason, QA Engineer Supervisor-J. E. Cavender, Level III Inspector s
M. R. Hamphill, QA Engineer H. L. Atkins, QA Engineer ,, J. W. Glenn, QA Engineer , + D.,H. Llewellyn, Welding Engineer - - A. E. Gadd, Welding Engineer ' l .Ct 'R. Baldwin, Welding Inspector Supervisor "S.J.;Hamrick, flechnical Engineer - Other licensee employees contacted included construction craftsmen, ' technicians, inspectors and. office personnel.
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- ,,j Other Organizations r
( - , ', Hartford Steam Sciler Inspection and Insurance Company ! ' ! l ,,. , J. W. Koske, Autnorized Nuclear Inspector e C. F. Toegel, Authorized fluclear Inspector - B. Wood, Authorized fluclear Inspector ' ,, 'f
- 6ctended exit dnterview
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Esit Ihterview The inspection scope an:i findings were summarized on October 23, 1981, with , those persons in;dicated in Paragraph 1 above. The unresolved item described in paragraph 5'was discussed in detail.
The violation described in ' paragraph 3.c. was discussed in detail with site management on October 2, 1981.
3.
Licensee Action on Previous Inspection Findings a.
(Closed) Unresolved Item (413, 414/81-01-02): Control of cutting and forming for NF supports and restraints. Licensee actions concerning .
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x. ' this ite.n included issuance of a control procedure (CP-497) and evaluation for significant material degradation.
It was detemined that no.significant degradation.has occurred. The _ inspector verified - these actions and considers them to be satisfactory.
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(0 pen) Violation (413/81-02-02, 414/81-02-04): Apparent generic items or trends not recognized nor forwarded to management. This item x concerns inadequate documentation and evaluation of problems identified - in nonconfoming item reports (NCI's).
Details of the inspector's review are discussed in paragraph 5.
c.
(Closed) Unresolved Item (413/81-22-04): Evaluation of lack _of fusion defect identified on NCI No.12682. This item concerns evaluation of lack of fusion on the inner diameter of Class B weld 1NV177-8.
Site QA l procedure Q1, Rev.15 - Control of Nonconforming Items requires proper technical evaluations to be performed by assigned personnel, for non-conforming conditions. On September 18, 1981, site costruction - technical support personnel accepted a rejectable lack of _ fusion _ defect identified by site inspection personnel.- The NRC inspector interviewed five inspection personnel. who observed the defect. ' All inspection personnel agreed that the rejectable defect existed. Overruling of this finding is not within the authority of construction personnel.
This is in noncompliance with 10 CRF 50, Appendix B, Criterion V'which requires that activities affecting quality be perfomed in accordance with established procedures. This is. Violation 413/81-24-02: Inadequate evaluation of -lack of fusion weld defect.
No violation or deviations, except as identified in paragraph 3.c, were identified.
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Unresolved Items Unresolved items are matters about which more infomation is required to detemine whether they are acceptable or may involve noncompliance or-deviations. One new unresolved item identified during this inspection is discussed in paragraph 5.
5.
Nonconforming Item Reports Review The inspector reviewed numerous NCI's to determine if adequate documentation and evaluation had been accomplished. During this review it was determined that four NCI's require further evaluation / documentation by the licensee.
These are as follows: NCI 10360.(evaluated 5/19/81) - apparent lack of fusion in base material.
Evaluation states that the defect is " acceptable to the base material specification". Since no radiography (RT) acceptance criteria are provided by the Code it is unclear as to which criteria have been used for evaluation.
In addition, there is some indication that-welding may have been performed in the area (lower radiographic l _ _ _ _ _ _
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density) and the defect would be rejectable if welding has been perfomed.
NCI 10425 (evaluated 8/19/81) - unacceptable laminations in Unit 1 steam generator enclosure steel.
It is not apparent from documentation provided that evaluation for generic implications has been performed.
NCI 12594 (evaluated 9/15/81) - failure to remove plywood purge dams.
Evaluation states " Design has insufficient data to evaluate signifi-cance".
It appears from the documentation that a possible significant < condition adverse to quality was not evaluated by management.
NCI 13187 (written 10/16/81 - not yet evaluated) - RT indication in forged valve (1FW56) body. The NCI was written.to address the difference of opinion between the Level III inspector and the Authodzed Nuclear Inspector. Justification provided on the RT reader sheet for acceptance is the fact that the required valve body inspection is ultrasonically tested (UT) and vendor records indicate that the valve was acceptable.
It is generally recognized that RT often will identify indications that UT might not identify.
In addition, the defect was identified as piping porosity.
Piping porosity is not comonly found in forgings.
This item, violation 413/81-02-02,414/81-02-04, rer.ains open until further evaluation is perfomed concerning the above NCI's and additional review of NCI's can be perfomed.
Evaluation of the above NCI's is assigned to Unresolved Item 413, 414/81-24-01: Verification of appropriate corrective action for nonconfoming items.
6.
Independent Inspection Effort (Units 1 and 2) The inspector conducted general inspections of site work and work activities and observed equipment protection / storage and housekeeping in the auxiliary building, containment buildings, pipe fabrication shop and storage areas.
7.
Licensee Identified Items 50.55(e) (Units 1 and 2) a.
(Closed) (413, 414/81-12-03) - Environmental qualification of equipment. This item concerned qualification of main steam power operated relief valves. The licensee submitted a final response on August 20, 1981. Licensee actions included modification and requal-ification of the affected valves.
The inspector verified these actions and considers them to be satisfactory.
b.
(Closed - Unit 1) (413, 413/80-21-04) - Cracked control rod guide tube support pins. The licensee submitted a final response on April 23, 1980. Licensee action has been to replace the pins with pins aanu-factured from improved material. The inspector verified that this has been accomplished for Unit 1.
This item will remain open for Unit 2 until work is satisfactorily accomplished for Unit 2.
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c.
(Closed) (413/81-17-01) - Misapplication of 3000-pound fittings. The licensee submitted a final response on June 5,1981.
Licensee actions have included replacement of installed fittings, re-marking of affected - stock fittings and correction of applicable drawings. 'The inspector-verified these actions and considers them to be satisfactory.
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(Closed) (413, 414/81-17-03) - Failure of PORV's and block valves .during prototype testing.
The licensee submitted a final' response on August 20, 1981.
Licensee actions have included replacement with valves from a different manufacturer and qualification of the replacement valve design.
The inspector verified these actions and considers them to be satisfactory.
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(Closed) (CDR 413/81-15) - Linear indications in valve body - Walworth Valve Company. The licensee submitted a final response on August 3, 1981. Licensee action concerning this item has been to-scrap the affected valve and replace it with a new valve. The inspector verified this action and considers it satisfactory.
No violations or deviations were identified.
8.
Safety-Related Pipe Support and Restraints Systems (Unit 1) The applicable code for safety-related pipe support and restraint systems installation is the ASliE Boiler and Pressure Vessel Code, Section III, Subsection NF,1974 Edition plus addenda through sumer 1975.
The inspector observed installation in progress of hanger 1-R-KC-0639 for conformance to code and procedure requirements in the areas of use of specified materials, location, documentation, conformance to drawings, and anchor bolt instal-lation.
No violations or deviations were identified.
9.
Electrical (Cables and Teminations) - Observation of Work and Work Activities (Unit 2) The inspector observed installation in progress of cables 2EPE552 and 2EPE553 for conformance to procedure and specification requirements in the areas of identification, bending radius, protection from damage, routing, supports and in process inspection.- The inspector also observed temination in progress for cable 2EPE503 (4160 volt power cable) for conformance to specifications in the areas of cable identification, cable. entry to cabinet, condition of wires, cable support and preparation for appropriate stress cones.
In addition, the inspector observed installation in progress of cable tray support in the Unit 2 annulus at elevation 559' 3" thru 561 '9" and azimuth 69 thru 88 for conformance to requirements of drawing CN-2918-04, Rev. 6.
No violations or deviations were identifie.. .. .. .
10.
Electrical (Components and Systems) - Observation of Work and Work Activities (Unit 2) The inspector observed internal wiring modifications in progress for 4160 volt switchgear 2 ETA, Cubical 19 for confomance to drawing CfN 2312.02- -0023.
No violations or deviations were identified.
11.
Safety-Related Piping (Welding) - Observation of Work and Work Activities (Unit 1) The applicable code for installation of safety-related piping is the ASME Boiler and Pressure Vessel Code, Section III,1974 Edition plus addenda through surser 1975. The inspector observed in process welds at various stages of completion and reviewed records for confomance to code and procedure requirements in the areas of documentation of pertinent infomation and QC signoffs via a weld traveler, availability of pertinent instructions, use of appropriate qualified welding procedure, provisions for weld repair provided, certification of filler material, control of welding parameters, verification of welder qualification, use of specified shielding - and purge gas, condition of welding equipment, provisions for voltage and amperage checks, verification of proper fitup, control of preheat and interpass temperature, condition of weld and base metal surfaces, and verification that appropriate inspections were being perfomed.
The following welds were observed: Weld No.
Size (In. Dia.)
Stage of Welding Observed 188104-24
Fitup 1NW14-1
Final .NW14-2
Fitup in progress 1NW14-8
Fitup 1NW14-10 1/2 Fitup 1NW14-11 1/2 F1 tup 1NW14-12
F1 tup No violations or deviations were identified.
12.
Reactor Coolant Pressure Boundary Piping (Welding) - Observation of Work and Work Activities (Unit 1) The applicable code is delineated in paragraph 11. The inspector observed root welding.in progress for 6-inch weld 1NC190-29 for confomance to code and procedure requirements in the areas delineated in paragraph 11.
No violations or deviations were identified. }}