IR 05000566/1979001
| ML19282B094 | |
| Person / Time | |
|---|---|
| Site: | Yellow Creek  |
| Issue date: | 01/26/1979 |
| From: | Gouge M, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19282B093 | List: |
| References | |
| 50-566-79-01, 50-567-79-01, NUDOCS 7903090006 | |
| Download: ML19282B094 (6) | |
Text
km Riou UNITED STATES
,,
,
NUCLEAR REGULATORY COMMISSION
o,,
[
REGION ll o
,$
101 M ARIETTA STREET, N.W.
ATLANTA, GEORGIA 30303
%,*****/
Report Nos.: 50-566/79-01, 50-567/79-01 Licensee: Tennessee Valley Authority 830 Power Building Chattanooga, Tennessee 37401 Facility Name: Yellow Creek Nuclear Plant, Units 1 and 2 Docket Nos.: 50-566, 50-567 License Nos.: CPPR-172 and CPPk-173 Inspection at Yellow Creek Site near Iuka, Mississippi
/!79
/
Inspecto M. J. Gouge Date' Signed Approved by:
/ _///9 A. R. Herdt, Chief, Projects Section, RCES Branch Dhte $igried SUMMARY Inspection on January 9-12, 1979 Areas Inspected This routine, unannounced inspection involved 27 inspector-hours onsite in the areas of construction status, QA records, QA audits, control of welding materials, civil design drawing review, licensee action on previous inspec-tion findings and observation of safety-related work activities (Unit 1).
Results No items of noncompliance or deviation were identified.
790309 0 066
.
.
.
.
-
.
'
-1-
.
DETAILS 1.
Persons Contacted Licensee Employees
- M. M. Price, Project Manager L. S. Cox, Construction Engineer
- C. G. Wages, Assistant Construction Engineer (QC)
C. Mcdonald, Assistant Construction Superintendent
,
J. Adams, Assistant Construction Superintendent
- L. G. Heber;, OEDC QA Staff
- R. G. Delay, Supervisor, Civil and Materials QC Unit
- R. D. Briggs, Supervisor, Mechanical QC Unit
- J. N. Holladay, Supervisor, Project QA Unit
- S. E. Alge, Supervisor, Document Control Unit
- J.
R. Daniel, Materials QC Unit C. M. Freeman, Civil QC Unit G. Alexander, Civil QC Unit J. B. Nelson, Lead Auditor, Project QA Unit K. K. Durrani, Project QA Unit K. Shivers, Boilermaker Foreman
- S. Watson, Document Control Unit Betty Davis, Document Control Unit H. Larson, Welding Engineer Various craftsmen and laborers
- Denotes those present at the Exit Interview.
2.
Exit Interview The inspection scope and findings were summarized on January 12, 1979, with those persons indicated by an asterisk in paragraph I above. The inspector summarized the scope of the inspection as follows: construc-tion status, QA record review, QA audit review, inspection of welding material control, civil design drawing review, review of licensee action on previous inspection findings and observation of safety-related work activities. The Region II inspector identified one unresolved item, Concrete Design Requirements, 566-567/79-01-01.
No items of noncompliance or deviations were identified.
3.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (566-567/78-09-01), Audit Report Time Requirements. The licensee issued Revision 1 to QASP 7.1 on December 22, 1978, which incorporates a 30-day requirement for the
,
.
..
. - _ _ _.
.
~
-
.
.
.
.
-2-issuance of the QA audit report after the completion of the post-audit conference as required by ANSI N45.2.12, Draft 4, Revision 2.
This item is closed.
4.
Unresolved Items Unresolved items are matters about which more information is required to ascertain whether they are acceptable items, items of noncompliance or deviations. An unresolved item identified during this inspection is discussed in paragraph 5.f.
5.
Independent Inspection Effort a.
Construction Status (Units 1 and 2)
Placement of fill concrete is progressing in the foundation area of the Unit 1 Reactor Building.
Shop fabrication of the stainless steel sumps, that are part of the Equipment and Floor Drainage System, is in progress.
Various structural concrete pours are in progress in the Units 1 and 2 Turbine Building areas. Work continues on the fabrication of Condenser Circulating Water (CCW)
System piping.
Fabrication of warehouse, office and shop buildings and grading of site roads are continuing operations. The central-mix batch concrete plant is in operation.
b.
Quality Assurance (QA) Records (Units 1 and 2)
(1) Quality Control Investigation Report (QCIR) System The master QCIR log maintained by the Document Control Unit
-
was reviewed for content and accuracy in accordance with CEP 15.01.
Completed (cleared) QCIR's up to and including QCIR 4885 were reviewed for acceptable disposition.
Several outstanding QCIR's were checked for proper posting of the Quality Control (QC) hold tags on the affected part or component. The QCIR system was found to be implemented and functioning in accordance with CEP 15.01.
(2) Field Change Request (FCR) System The licensee has established a FCR system to provide control of design changes proposed by site engineering to correct minor drawing errors, improve existing design, or to facilitate construction activities.
CEP 3.01, entitled " Field Change Request", provides procedural guidance to the construction organization in this area. The Region II inspector examined the records associated with control of the FCR syste *
-
.,.
.
.
.
_
.
.
-3-Affected drawings were examined for proper control of the following Yellow Creek Nuclear Plant FCR's: C-5, C-9, C-10, M-1, M-3 and M-5.
The drawing control interface with the FCR system was reviewed and various master drawings, superceded master drawings and field copies of drawings were inspect?d for proper control of civil and mechanical FCR's.
The FCR system at Yellow Creek Nuclear Plant was found to be implemented and functioning in accordance with applicable procedures.
No items of noncompliance or deviations were identified in the above areas inspected.
c.
Quality Assurance (QA) Audits (Units 1 and 2)
The following QA audits conducted by the site QA unit were examined by the project inspector for completeness, deficiencies found, corrective action taken, and implementation in accordance with the licensee's procedures CEP 18.01 and QASP 7.1:
Audit Number Subject YC-L-78-03 Concrete Operations
'
YC-M-78-01 Fabrication and Documentation of RB Stainless Steel Sump Liners The audits reviewed were found to be conducted and documented in a thorough, objective manner.
No items of noncompliance or deviations were identified in the above area inspected.
d.
Control of Welding Material (Units 1 and 2)
Weld Material Control Centers 1 and 2 were inspected for proper storage and control of welding material in accordance with CEP 8.03, Revision 3, entitled " Control of Welding Material". The Region II inspector examined the Welding Materials Issue Inspectors for knowledge of applicable procedures, reviewed the veld saterial control center 1 and 2 records for distribution control of welding electrodes, and inspected the storage facilities and holding Welding QC personnel were found to be knowledgeable of ovens.
applicable procedures and were maintaining accurate and complete records for control of welding materials. The storage facilities were adequate and the bolding oven thermometers were in calibration.
Holding oven temperatures were recorded and were within specified ranges.
Site control of welding material was adequate.
16 -
.
_._ -
. _. - _. _ _ _ _ _ _
-.
_
'
..
.
A
-4-No items of noncompliance or deviations were identified in the above area inspected.
e.
Observation of Safety-Related Work Activities (Unit 1)
The following safety-related work was observed by the inspector during the course of the inspection:
(1) Preparations for Category I fill concrete pour AI-DS.
(2) Curing of Category I fill concrete pour AI-DS.
(3) Fabrication of stainless steel sumps that will be part of the Equipment and Floor Drainage System.
(4) Reinforcing steel placement in the emergency sump area of Unit 1 Reactor Building foundation.
(5) Operation of the central-mix batch concrete plant.
No items of noncomplian:e or deviations were identified in the above areas inspected.
f.
Civil Design Drawing Review (Units 1 an'd 2)
Several civil design drawings were examined to ensure that the licensee's PSAR commitments had been correctly reflected in design drawings. Section 3.8 of the Yellow Creek Nuclear Plant PSAR gives requirements for design of Category I structures. The first paragraph of section 3.8.3.6.1.1 of the PSAR states, in part, " Concrete not dependent on shores, metal decking or bottom face forms for support is designed to attain its required compres-sive strength in 90 days.. 0ther concrete is designed to attain its required compressive strength in 28 days".
Stated concisely, the PSAR requires Category I structural concrete that is dependent on shores, metal decking or bottom face forms for support to attain its required compressive strength in 28 days. Yellow Creek Nuclear Plant Drawing 4RE0417-5R-3 (Walls and Slabs, EL 440 to 513 outline-Reactor Building-Auxiliary Structure, Units 1 and 2) shows structures that are dependent on shores, metal decking or bottom fare forms for support. Drawing 4RE0417-5R-1 gives general notes applicable to sll sheets of drawing series 4RE0417-5R. Note 1 on drawing 4RE0417-5R-1 specifies a concrete six designed to attain 4000 psi compressive strength in 90 days with the additional design requirement of 2500 psi at 28 days for form removal purposes. The PSAR as stated above specifies a 28-day requirement for required compressive strength. This
. _.,,,...
... _ _. - _.. -..
,
.
>
.
.
-5-apparent discrepancy in concrete mix design for structural Category I concrete dependent on shores, metal decking or bottom face forms for support is identified as unresolved item number 566-567/79-01-01, Concrete Design Requirements.
No items of noncompliance or deviations were identified in the above area inspected.
-
.