IR 05000566/1980015
| ML19345B250 | |
| Person / Time | |
|---|---|
| Site: | Yellow Creek  |
| Issue date: | 10/08/1980 |
| From: | Cantrell F, Matt Thomas NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19345B248 | List: |
| References | |
| 50-566-80-15, 50-567-80-15, NUDOCS 8011260421 | |
| Download: ML19345B250 (5) | |
Text
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NUCLEAR REGULATORY COMMISSION
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I REGION 11
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I 101 MARIETTA sT., N.W., SUITE 3100 ATLANT A, G EORGI A 30303 s
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Report Nos. 50-566/80-15 and 50-567/80-15 Licensee: Tennessee Valley Authority 500A Chestnut Street
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Chattanooga, TN 37401 Docket Nos. 50-566 and 50-567 Facility Name: Yellow Creek Nuclear Plant License Nos.- CPPR-172 and CPPR-173 Inspection at Yellow Creek site near Iuka, Mississippi fL//fttf -
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7D Inspector:
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M. Thomas
'Dat6 Signed Approved by:
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F. "$. 'Cantrell, Secti6n b(rf,RCESBranch eate/ Signed SUMMARY Inspection on September 8-11, 1980 Areas Inspected This routine, unannounced inspection involved 32 intpector-hours on site in the areas of receiving inspection, storage, preventive maintenance; concrete activi-ties; construction status; QA audits; and IE Bulletins and Circulars.
Results Of the five areas inspected, no items of noncompliance or deviations were iden-tified.
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DETAILS
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1.
Persons Contacted
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Licensee Employees
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M. M. Price, Project Manager
- L. S. Cox, Construction Engineer
- C. G. Wages,-Assistant Construction Engineer - QC
- C. E. Hale, Assistant Construction Engineer - Engineering Services
- J. D. Shanlever, Supervisor, Materials Services Unit - QC
- R. G. Delay, Supervisor, Materials & Civil - QC
- J. N. Holladay, Project QA Supervisor
- S. P. Watson, Document Control Unit
- S. Blount, Supervisor, Technical Services L. B. Parker, QA Engineer Other licensee employees contacted included construction craftsmen, technicians, operators, and office personnel.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on September 11, 1980, with those persons indicated in paragraph I above. Inspector followup item 566-567/80-15-01, Resolution of site QA audit YC-G-80-07 deficiencies (paragraph 5.d.), was discussed in detail.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Independent Inspection Effort The inspector conducted an inspection of Unit I reactor building, fuel handling building, vaste management building, receiving inspection, storage, and preventive maintenance, concrete laboratory, and quality assurance (QA)
records.
Areas inspected included:
concrete laboratory and batch plant operation a.
b.
calibration of laboratory and test equipment
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I Receiving Inspection and Storage (Units 1 & 2)
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The inspector conducted an inspection of levels B and C storage in-warehouses A & B, rebar and stainless steel pipe storage yard areas,
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nuclear steam supply' system (NSSS) storage yard for major components, and reviewed of receiving -inspection and preventive maintenance records.
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The following documents were reviewed for acceptance criteria:
-(1) Receiving Inspection ' Storage. & Preventive Maintenance (RIS&PM)
Procedures M-121, M-122, M-123, M-655 (2) Construction Engineering Procedures (CEP) 7.02, 13.03, 14.01,
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15.01, 18.01 (3) Standard Operating Procedure (S0P)-24 (4) Quality Assurance Staff Procedure (QASP) 7.1, Quality Assurance Procedure (QAP) 18.1 Areas inspected included proper assignment of storage levels, identi-
fication of stored material, and control of nonconforming items.
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addition to the information necessary for proper identification, tags designating storage levels were also placed on items to ensure proper
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storage levels.
Nonconforming items were placed in the QC hold cage.
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q Items not placed in the hold cage because of size were clearly marked and identified as being nonconforming and placed in the appropriate storage level area.
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i Level-D storage areas for safety-related piping, rebar, an'd NSSS. major
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components were inspected. All piping inspected had end caps, proper i
identification, and was stored on cribbing off the ground. Rebar was
properly marked and stored on platforms off the ground. Unit 1 steam
generators, reactor vessel and head, and the pressurizer are stored in the NSSS storage yard.
The components are adequately supported to
prevent unnecessary movement which may cause damage.
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The inspector reviewed receiving inspection and preventive maintenance records for the following components:
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Emergency ~ component cooling system (CCS) pumps & motors l
Pump Serial No.
Motor Serial No.
j-809501 809502 8-5115-90332-2-2
. 809801 8-5115-90332-2-3 i
~ 809802 8-5115-90332-2-4
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' Normal CCS Pumps Serial No.
809401 809402-
809701 809702 The inspector verified that activities were being perforns! in accord-ance with applicable procedures.
d.
Quality Assurance (QA) Records (Units I and 2)
The inspector reviewed closed Quality Control Investigation Reports (QCIR) through QCIR 23400 for acceptable disposition, evaluation of
significance and adherence to ' appropriate construction engineering
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procedures (CEP).
The QCIR system appears to be implemented ana
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functioning in accordance with CEP 15.01.
The following audits conducted by the site' QA unit were examined by the inspector for completeness, deficiencies four.J, corrective action taken, and implementation in accordance with the licensee's procedures QASP 7.1, QAP 18.1 and CEP 18.01:
Audit No.
Subject-YC-C-80-06 Grouting of Foundation Anchors YC-C-80-07 Earthfill-for ERCW Spray Pond YC-C-S0-09 Blasting Inspection YC-G-80-05 Surveillance of Site Contractors YC-G-80-06 Handling of Nuclear Components YC-G-80-07 Work Releases The above audits were found to be conducted and documented in accord-ance with procedures. QA audit YC-G-80-07 identified several deficien-
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cies in the implementation of the QA pregram for verification and
control of work releases. The inspector will review the resolution of
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these audit deficiencies. This item will be identified as inspector followup item 566-567/80-15-01, Resolution of Site QA Audit YC-G-80-07
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Deficiencies.
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6.
Containment (Structural Concrete II) - Observation of Work and Work Activities, i
Unit 1 i
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The inspector. observed partial placement; of concrete pours numbers F1-K13
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'and W-FD34, FD35, FD36, FD37. Acceptance criteria examined by the inspector i
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- appeared in the following documents:
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Section 3.8 of th'e PSAR b.
1TA Specification G-2, Plain and Reinforced Concrete
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. Quality Control Instructions.(QCI) C-201, - C-202, C-204, C-208, and C-209 d.
Construction Engineering Procedure (CEP) 15.01
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Forms were tight and clean and rebar was properly cleaned. Preplace -
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ment; inspections were indicated by the signed pour _ cards. Placement activities pertaining to free fall, flow distance, and consclidation conformed to specifications. Activities were monitored by civil QC personnel. Test for slump, air content, temperature, unit weight, and samples for concrete cylinders met frequency and acceptance criteria.
The inspector observed batch plant activities and verified that equip-ment met requirements for calibration, accuracy, readability, and proper mixes specified were.being delivered to the location designated.
7.
IE Bulletins and Circulars (Units 1 and 2)
a.
The licensee has - received and reviewed IE Bulletins (IEB) through 80-20.
Responsible site management ~ review all IEB's for site applica-bility and coordinate a response, if needed, with engineering design and licensing personnel.
The following IEB's 'are not applicable to the site or require no action (issued for information only) and, therefore, are closed:
IEB 80-04 IEB 80-13 IEB 80-06 IEB 80-14 IEB 80-07 IEB 80-15 IEB 80-10 IEB 80-17 IEB 80-11 IEB 80-18 IEB 80-12 The inspector reviewed the file of IE circulars (IEC).
IE circulgrs through IEC 80-18 have been received on site and reviewed by responsible project management for applicability to' the site. 'If a potential prob-lem exists a determination is made by site and/or engineering design of the extent of the problem and corrective action is initiated.
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