IR 05000395/1981001
| ML20003D114 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 02/10/1981 |
| From: | Quick D, Whitener H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20003D113 | List: |
| References | |
| 50-395-81-01, 50-395-81-1, NUDOCS 8103190317 | |
| Download: ML20003D114 (4) | |
Text
.
'r UNITED STATES
'
- ^f*
' ',,
NUCLEAR REGULATORY COMMISSION (/
f g
REGION il
- r g
101 MARIETTA ST ad.W., SulTE 3:00 e
ATLANTA. GEORGIA 30303
%
o
.....
Report No. 50-395/81-01 Licensee: South Carolina Electric and Gas Co.
Columbia, SC 29218 Docket No. 50-395 License No. CPPR-94 Facility Name: Summer Inspection at Summer site near Winnsboro, SC c2 //b/F'/
Inspector: Y [ // ) ~ ~ ~
Ddte S'igned ms H.' L'. Whi ten'eV 2!/0 8/
Approved by:
0. R. Quick, S'ection Chief, RONS Branch Da'te Signed SUMMARY Inspection on January 10-13, 1981 Areas Inspected This routine, announced inspection involved 29 inspector-hours on site in the area of witnessing the integrated leak rate test.
Results Of the area inspected, no items of noncompliance or deviations were identified.
-8103190SlT
.
DETAILS 1.
Persons Contacted Licensee Employees
- 0. S. Bradham, Plant Manager
- S. J. Smith, Maintenance Supervisor Other Organizations
.GAI
- G. Boward, BOP Lead Systems Supervisor H. Thickman, ILRT Supervisor Ebasco W. D. Roman, Lead Engineer, Data Analysis NRC Resident Inspector
- J. Skolds, Senior Resident Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on January 13, 1981 with those persons indicated in Paragraph One above. Licensee Management stated that the containment was baing depressurized in order to enter and make leakage repairs.
Access control will be maintained to preserve valve alignments and any work to effect leakage repair will be controlled by the ILRT supervisor.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Primary Containment Integrated Leak Rate Test The inspector reviewed test activity to determine that the primary contain-ment integrated leak rate test (ILRT) was performed in accordance with appropriate sections of the " Reactor Building preoperational Integrated Leak L_
,
.
-_
o
.
Rate Test Procedura", LR-3; Appendix J to 10 CFR 50; and ANSI N45.4.
The inspection was a coordinated effort involving the Resident Inspector and a Region II specialist. Selected sampling of the licensee's activities which were inspected included (1) review of LR-3 to verify that the procedure was approved and conformed to NRC requirements; (2) observation of test perform-ance to determine that test prerequisites were completed, special equipment
'
installed, appropriate data were recorded and analyzed; and (3) preliminary evaluation of leakage rate test results to verify that leak rate limits were met.
Pertinent aspects of the test are discussad in the following para-graphs.
6.
General Observations The inspectors witnessed and/or reviewed portions of the test preparation, containment pressurization, temperature stabilization and data processing in the period of January 8-13, 1981. The following items were inspected-a.
The test was conducted in accordance with an approved procedure main-tained at the test control center.
Changes to the procedure were documented.
b.
Selected test prerequisites were verified.
c.
Plant systems required to maintain test control were in operation.
d.
Venting and draining of systems were verified.
e.
Data required for performance of the containment leak rate calculations were recorded at 15 minute intervals.
f.
Problems encountered during the test were described in the test svent j
log.
'
I g.
Valve alignments for a random selectica of penetrations were verified.
No items of noncompliance or deviations were identified.
7.
Test Sequence After the initial pressurization of containment, the licensee identified and isolated a number of leakage paths which reduced the leak rate from about 20 times the allowable leakage to 0.12% per day. This leakage is within the
.
test acceptance leakage of 0.15% per day but does not take into consider-ation instrument error, statistical error and add-on leakage. On January 12, the licensee made the. decision to depressurize containment and repair leakage paths.
,
The Resident Inspector witnessed the subsequent containment pressurization and leakage measurement.
Preliminary evaluation of the leakage rate indicated 0.05% per day which is well belcw the test acceptance criteri.
.,
.
The inspectors had no further questions on this test.
Data anc the test report will be reviewed at a future time.
,
I
$