IR 05000445/1979008
| ML19261D651 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 04/17/1979 |
| From: | Randy Hall, Tapia J, Renee Taylor NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19261D638 | List: |
| References | |
| 50-445-79-08, 50-445-79-8, 50-446-79-08, 50-446-79-8, NUDOCS 7906200524 | |
| Download: ML19261D651 (5) | |
Text
-
.
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Report No. 50-445/79-08; 50-446/79-08 Docket No. 50-445; 50-446 Category A2 Licensee: Texas Utilities Generating Company 2001 Bryan Tower Dallas, Texas 75201 Facility Name:
Comanche Peak, Units 1 & 2 Inspection at:
Comanche Peak Site, Glen Rose, Texas Inspection conducted: March 26-29, 1979 Inspector:
O/-
-
4 ll Tl J. I.' Japia, Reactor Inspector, Engineering Support Date 4/
Section 9!'/7/79 Reviewed:
-
R. G. Taylor, Reactor Resident Inspector, Projects Date Section
'
^
/ 7f Approved:
v-
-
W. A. Crossman, Chief, Projects Section Date s -
Y-/7-?f R. E. Hall, Chief. Engineering Support Section Date 2286
.,19 7 9 0 6 20 0 5 z'l
.
.
Inspection Sumary:
Inspection on March 26-29,1979 (Report No. 50-445/79-08;50-446/79-08)
Areas inspected:
Routine, unannounced inspection of construction activities including observation of work and review of quality assurance documentation related to concrete placement in the Unit 2 Containment Building, Safety Injection System Check Valves (Unit 1), and Pressurizer Safety Valves (Unit 1). The inspection involved thirty-two inspector-hours on site by one NRC inspector.
Resul ts: No items of noncompliance were identified in the three areas inspected.
2286 a20-2-
.
.
DETAILS 1.
Pe. sons Contacted Principal Licensee Personnel
- R. G. Tolson, TUGCO, Site QA Supervisor
- J. George, TUSI, Project General Manager R. V. Fleck, TUGC0/G&H, Civil QC Supervisor
- J. V. Hawkins, TUGC0/G&H, Product Assurance Supervisor
- 0. E. Deviney, TUSI, QA Technician Other Personnel P. Thomas, Field Representative, Westinghouse M. Wuestefeld, Field Representative, Westinghouse
- denotes those present at the exit interview.
2.
Site Tour The IE inspector toured the various areas of the site to observe construction activities in progress, including housekeeping.
No items of noncompliance or deviations were identified.
3.
Concrete Placement A review of quality related records relative to the containment building structural concrete was conducted to ascertain whether these records reflect work accomplishment consistent with NRC requirements and Safety Analysis Report conmitments.
The follow-ing records for the twenty-second six feet high lift of concrete in the Unit 2 containment wall were specifically reviewed:
a.
Concrete Pour Card b.
Inspection Report
]}
b.
Concrete Placement Plan
c.
Concrete Placement Summary
d.
Daily Curing Verification Record
e.
Report on Compressive Tests of Concrete
f.
Batch Tickets
-3-
-
.
The records reviewed indicated confonnance with the Gibbs & Hill
specification for concrete.
A review of the concrete mix design used in the placement (No.133)
was also conducted in order to verify compliance with G&H Specifica-
tion.No. 2323-SS-9, Revision 4, " Concrete." This review was previously
identified as an unresolved item in the NRC Report No. 79-04.
The
graph showing the relationship between water-cement ratio and com-
pressive strength was reviewed and found to be in conformance with
paragraph 3.8.2.1 of ACI 301-72
Documentation of the data used to
construct the graph, as well as approvel of the mix by the design
engineer, was also reviewed.
Based on the review conducted during
this inspection, this unresolved item is considered closed.
No items of noncompliance or deviations were identified.
4.
Safety Related Valves
A review of chemical composition test reports for the materials used
to construct the following valves was performed during this inspection:
a.
Three 6 inch diameter Pressurizer Safety Valves
b.
Two 6 inch diameter Safety Injection System Check Valves
The test results were compared to the American Society for Testing and
Materials (ASTM) standards specified in the Westinghouse equipment
specifications.
Westinghouse Equipment Specification G-678838, Revision 0, "fressurizer
Safety Valves Class 1, ASME Boiler & Pressure Vessel Code Section III,"
paragraph 5.1.10 states, "The spring shall be Inconel 718 or a material
approved by Westinghouse Nuclear Energy Systems." The review of the
chemical composition test reports revealed that for the three pressurizer
safety valves, the spring was constructed from ASTM A304, " Standard
Specification for Alloy Steel Bars Subject to End-Quench Hardenability
Requirements," Grade 51B60H material.
The approval for the use of
this material from Westinghouse could not be identified during this
inspection.
This matter is considered unresolved and will be reviewed
during a subsequent inspection.
No items of noncompliance or deviations were identified.
5.
Unresolved Items
Unresolved items are matters about which more information is required
in order to ascertain whether they are acceptable items of noncompliance
or dev'ations.
An unresolved item disclosed during the inspection is
discussed in paragraph 4.
2286
_4
,
.
6.
Exit Interview
The IE inspector met with licensee representatives (denoted in para-
graph 1) and with Mr. R. G. Taylor, the NRC Resident Inspector, at
the conclusion of the inspection on March 29, 1979, in order to
discuss the purpose, scope and findings of the inspection.
2286
323
.
-5-