IR 05000566/1980005
| ML19323B818 | |
| Person / Time | |
|---|---|
| Site: | Yellow Creek  |
| Issue date: | 03/21/1980 |
| From: | Crowley B, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19323B809 | List: |
| References | |
| 50-566-80-05, 50-566-80-5, 50-567-80-05, 50-567-80-5, NUDOCS 8005140302 | |
| Download: ML19323B818 (5) | |
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UNITED STATES
,fdy 8 NUCLEAR REGULATORY COMMISSION n
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REGION 11 e[
0, 101 MARIETTA ST N.W., SUITE 3100
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,o ATLANTA, GEORGIA 30303
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MAR 211980 Report Nos. 50-566/80-05 and 50-567/80-35 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Facility Name: Yellow Creek Nuclear Plant Docket Nos. 50-566 and 50-567 License Nos. CPPR-172 and CPPR-173 Inspection at Combustion Engineering, Inc. and TVA's office of Division of Nuclear Power, Chattanooga, Tennessee Inspector:
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70
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B. R.
rowle
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~ Date Signed Approved by:
/ '16 3/3//fo A. R. Herdt, Chief, ESS No. 2, RCES Branch
'Dat'e Signed SUMMARY Inspection on March 4-5, 1980 Areas Inspected This routine announced inspection involved 16 inspector-hours at Combustion Engin-eering and TVA's office of Division of Nuclear Power in the area of preservice inspection of NSSS Components.
Results No items of noncompliance or deviations were identified.
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DETAILS
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1.
Persons Contacted Licensee Employees
- R. H. Daniel, Supervisor Baseline & Inservice Inspection Section, QA Staff D. Kirby, Nuclear Engineer, NSSS Contract Section T. D. Lee, Audit Supervisor, Quality Assurance & Audit Staff Other Organizations Combustion Engineering, Inc. - ISI Division J. J. Dore, Project Engineer R. A. Morehouse, ISI Engineer
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- Attended exit interview 2.
Exit Interview On March 5, 1980, the inspector met with the licensee representative noted in paragraph 1 above and summarized the scope and findings of the inspection of preservice inservice inspection activities of NSSS Components.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items aresolved items are matters about which more information is required to aetermine whether they are acceptable or may involve noncompliance or deviations.
New unresolved items identified during this inspection are discussed in paragraph 5.
5.
Preservice Inspection - Review of Program (Units 1 & 2)
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The inspector reviewed the licensee's preservice inspection (PSI) program
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in the areas indicated below. The PSI of NSSS Components is being performed in accordance with the 1974 Edition of Section XI of the ASME Boiler and Pressure Vessel Code including addcnda through the summer of 1975.
a.
As outlined in IE-RII report number 50-566-567/80-02 the inspector reviewed the PSI program for Unit I components.. After the inspection covered by report 80-02, Engineering Notice (EN)~TVA 1-23 was issued
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i to add Unit 2 components to the program.
In ad,dition to the areas described below, the inspector reviewed changes to the p~rogram relative to Unit 2 components.
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b.
TVA (Division of Design) has contracted Combust. ion Engineering, Inc.,
Power System Services - ISI Division (CE-ISI Div.) to perform PSI of NSSS Components as part of the NSSS contract. The TVA Division of Nuclear Power has certain responsibilities for the the PSI.
The inspector reviewed the TVA organizational structure including quali-fications, responsibilities and duties of personnel responsible for the PSI. For previous PSI work, where the PSI was performed on site
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when the plant was near operational status, these areas (organizational structure and responsibilities) were covered by the Division of Power Production Operational QA Manual. However, for Yellow Creek, Hartsville, and Phipps Bend where the NSSS components are being inspected in the vendor shops, the Operational QA Manual is not clearly applicable and the activities such as procedure approval, program surveillance, and final report review being performed by the Baseline and Inservice
Inspection Section are not clearly defined. The Division of Power Production has recently reorganized and the Operational QA Manual is in the process of being completly revised to cover the new organization.
According to responsible personnel, the responsibilities of the Baseline
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and Inservice Inspection Section relative to PSI work performed in the vendor shops is being included in the revised QA Manual which will take several months to issue. The Supervisor of the Baseline and Inservice Insjection Section agreed to issue an interim change to the existing Operational QA Manual to more clearly define the Sections activities relative to vendor shop PSI work until the revised QA manual is issued.
i This item is considered unresolved pending review of the change to the
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Operational QA Manual and is identified as item number 50-566,567/80-05-01, Responsibilities for PSI.
The inspector reviewed TVA's requirements for audit of PSI activities.
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The Quality Assurance and Audit Staff of the Office of Power is respon-sible for audits. The inspector rr eiewed the following documents which detail the requirements:
(1) TVA Topical TVA-TR75-1, paragraph 17.2.18, " Audits" (2) Office of Power Quality Assurance Procedure, OP-QAP-18.1, Rev. 2,
" Audits"
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A (3) Quality Assurance and Audit Staff Procedure, QAAS-QAP-3.1, Rev.
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4, " Quality Audit Program"
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In addition, the inspector reviewed audit number OPQAA-SP-80-V-1 dated
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January 17-18, 1980 which covered evaluation of baseline NDE being
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d.
Generation and custody of NDE records up to completion of inspection of the components is governe,d by combustion Engineering, Inc., and Wuclear Energy Systems QA procedures, which were. reviewed as reported
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in IE-RII report number 50-566-567/80-02. 'the einspector reviewed requirements for control of records aftier dompletion of inspection, which are covered in the following TVA procedures from the OEDC QA Manual:
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V (1) QAP 17.01, Rev. 2, " Quality Assurance Records" (2) QAP 5.5, Rev. 1, " Quality Compliance Records and Records Control For NSSS Vendor Procurred Material" Within the areas inspected, no items of noncompliance or deviation were identified.
6.
Preservice Inspection - Review of Procedures (Units 1 & 2)
As noted in paragraph 5.a.
above, the program has been revised to cover Unit 2 component.
The inspector reviewed the procedures listed under procedure review of IE-RII report number 50-566-567/80-02 for any changes made since that review. Revision 02 to procedure 534115-ESS-093, " Liquid Penetrant Examinstion Procedure for Preservice and Inservice Inspection (Solvent-Removable Type)" has been issued to change paragraph 5.1.1 to more clearly define requirements for wire brushing prior to testing.
This closes inspector followup item 566/80-02-02.
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Within the areas inspected no items of noncompliance or deviation were identified.
7.
Preservice Inspection - Observation of Work and Work Activities (Units 1 &
2)
The inspector observed the PSI activities described below to determine whether these activities were being performed in accordance with regulatory requirements and licensee procedures. See paragraph 5 above for the applic-able code.
a.
Personnel qualification records for two level I and two level II examinera vere reciewed.
b.
The licensee's PSI plans and schedules were reviewed to determine whether the number of items being inspected, the methods of examination, and the extent of examinations were consistent with the SAR and the licensee's PSI program. This was accomplished by comparing a sample
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of iteus from the program plan with the requirements of IWB-2500 and IWC-2520 of the code. The sample consisted of:
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(1) Secondary side of steam generators #1 and #2 (2) Loop #1 Reactor Coolant Piping Hot Leg (3) Reactor Vessel
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c.
In-process ultrasonic inspection, including calibration checks on
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applicable calibration blocks was observed for the following welds:
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Unit 1 Steam Generator # 2 Secondary side Girth weld 01-021-003
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(0 degrees, 45 degrees, 60 degreed)
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Reactor C1olant Pipe Elbow 711-202-3 LonkSeams02-012-Unit 2
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002 and 02-012-033 (0 degrees, 45 degrees)
The inspections were compared with applicable procedures in the following areas:
(1) Availability of and compliance with approved NDE procedures (2) Use of knowledgeable NDE personnel (3) Use of NDE personnel qualified to the proper level (4) Recording of inspection results (5) Type of apparatus used (6) Extent of coverage of weldment (7) Calibration requirements (8) Search Units (9) Beam Angles (10) DAC Curves (11) Reference level for monitoring discontinuities (12) Method for demonstration of penetration (13) Limits for evaluating and recording indications (14) Recording significant indications (15) Acceptance limits d.
In process liquid penetrant examination was observed on Unit 1 Steam Generator #2 Key Bracket weld 01-021-040. The inspection was compared with the applicable procedure in the following areas:
(1) Availability of and compliance with approved NDE procedures (2) Use ofknowledgeable NDE personnel (3) Use of NDE personnel qualified to the proper lead (4) Recording of inspection results
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(5) Method consistent with procedure (6) Penetrant materials identified and consistent with code (7) Surface preparation (8) Drying time following surface cleaning (9) Penetrant application and penetration time (10) Surface temperature (11) Removal of penetrant
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(12) Developer application including drying time prior to application
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(13) Examination technique and time between developer application and evaluation
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(14) Reporting of examination results Within the areas inspected, no items of noncompliance or deviation were identified.
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