IR 05000269/1977015
| ML19322B701 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/08/1977 |
| From: | Martin R, Verdery E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19322B698 | List: |
| References | |
| 50-269-77-15, 50-270-77-15, 50-287-77-15, NUDOCS 7912050705 | |
| Download: ML19322B701 (4) | |
Text
.
.,34%g
,9 UNITED STATES
NUCLEAR REGULATORY COMMISSION o
",g N, w ( [ g
,
'
g REGCN il
' ' " /
- t 230 PE ACHTREE STR EET, N.W. SUITE 1217 ATLANTA. GEORGI A 30303 o,
.
...../
g.m t
Report Nos.:
50-269/77-15, 50-270/77-15 and 50-287/77-15 Docket Nos.:
50-269, 50-270 and 50-287 License Nos.: DPR-38, DPR-47 and DPR-55 Licensee:
Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242 Facility Name: Oconee Units Nos. 1, 2 and 3 Inspection at: Oconee Inspection conducted: July 27, 28 and 30 and August 1, 1977 Inspector:
E. H. Verd I[/A c.4
~/
Reviewed by:
/
R. D. M5rtin,' C'hief'
'Date Nuclear Support Section Reactor Operations and Nuclear Support Branch Inspection Summary Inspection on July 27, 28 and 30 and August 1, 1977 (Report Nos.
50-269/77-15, 50-270/77-15 and 50-287/77-15)
Areas Inspected:
Routine announced inspection of the periodic contain-ment integrated leakage rate test (II.RT) on Unit N,.
2.
Specific areas examined included calibration of test instrumentation, completion of test prerequisites, crew manning, test procedure revisions, data collec-tion and evaluation, performance and verification test results, and containment inspection findings.
A tour of the facility was conducted to observe preparations for the ILRT and general safety conditions on all units.
The inspection involved 25 inspector-hours on site by one NRC inspector.
Results:
Of the areas inspected, no items of noncompliance or deviations j
were identified.
(
,
-
7912050
.
.
. _ _ _ _ _ _.. _.
_ _ _ _
_
_.
. _... _ _ _. _ _
.
,
.
RII Rpt. Nos. 50-259/77-15, 50-270/77-15 and 50-287/77-15
- -
DETAILS Prepared by:
IM
[ f/77
~
8.'H.Verdery,ReporInspector
/ ate D
Nuclear Support Section Reactor Operations and Nuclear Support Branch Dates of Inspectio - July 27, 28 and 30 and August 1, 1977 Reviewed by:
Ib'
hf
e R. D. Martin, Chief
'D4te Nuclear Support Section Reactor Operations and Nuclear Support Branch 1.
Persons Contacted R
C. Adams, Instrumentation and Control Engineer
- T. S. Barr, Performance Engineer
- R. T. Bond, Technical Services Engineer O. S. Bradham, Superintendent of Maintenance
- T. E. Cribbe, Assistant Performance Engineer
- R.
M. Koehler, Superintendent of Technical Services
- N.
Pope, Superintendent of Operations
- J.
E. Smith, Station Manager Various plant operations, maintenance and technical services personnel.
- Denotes those present at the Exit Interview.
l 2.
Licensee Action on Previous Inspection Findings Not applicable during this inspection.
3.
Unresolved Items Not identified during this inspection.
4.
Exit Interview The inspection scope and findings were discussed with the licensee's representatives listed in paragraph 1 on August 1, 1977.
The inspector recommended several changes to the licensee's test pro-cedure and advised him of proposed changes to the ANSI Standard i
_
__
_- -____
_ _ _ _ _ _ _ _ - _ _ _ _
-
,
.
RII Rpt. Nos. 50-259/77-15, 50-270/77-15 and 50-287/77-15-2-relating to containment leakage rate testing.
(ANS N274, Work Group 56.8, Containment System Leakage Testing Requirements, Draf t No. 1)
5.
Containment Integrated Leakage Rate Test The inspector observed approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> of the Unit No. 2 integrated Leakage Rate Test (ILRT).
During the conduct of the test, the inspector ensured that the containment pressurization source was isolated and vented; verified the latest up-to-date procedure was used; verified that the test prerequisites had been completed; inspected a representative sampling of valves in the control room and penetration room for correct positions in accordance with the test procedure; evaluated the performance of the test personnel; observed that test data was taken, recorded and evaluated; and reviewed the Test Coordinators log book.
Prior to the test, the inspector reviewed the calibration data sheets for all containment resistance temperature detectors, dew cells, pressure instruments, and other related instrumentation, and verified that the test prerequisites associated with that instrumen-tation had been completed.
Additionally, the inspector reviewed the Instrument Error Analysis for the ILRT measuring system.
Upon completion of the ILRT and the supplemental leakage rate verification test on Unit No. 2, the inspector reviewed the prelimi-nary test results for compliance with the Technical Specifications, Appendix J to 10 CFR 50, and ANSI 45.4-1972.
In addition, the inspector reviewed the results of the Reactor Building Inspection Test (PT /0/A/150/16) for Units 1, 2 and 3.
Pending review of the final test results, no items of noncompliance or deviations were identified.
6.
Plant Tour The inspector walked through various areas of the plant to observe
'
operations and activities associated with the ILRT; to check the lineup of systems which were required for the test; and to observe the general safety and housekeeping conditions of all three units.
No items of noncompliance or deviations were identified.
(_:
During the tour of the Unit 2 West Penetration Roem the inspector noted an excessive amount of oil and water on the floor as well as several sets of anti-contamination coveralls, cotton gloves, tools, absorbent material and other miscellaneous deEris.
The inspector
. _. -
.
. _ -. -.
-
-
.-
-
.
_ _ -
-.
,
.
-
.
.
,
v~
' ' (
j
.
RII Rpt. Nos. 50-259/77-15 50-270/77-15 and 50-287/77-15-3-
informed the licensee's representatives immediately following this tour, and again at the exit interview, that the conditions in the West Penetration Room presented a personnel safety hazard and l
should be corrected.
t i
These conditions will be reexamined during a subsequent inspection.
Fuel Handling Procedures The inspector also reviewed the licensee's fuel handling procedures
to determine the extent to which they limit the handling of heavy
'
loads over the spent fuel pool e.nd the reactor.
The inspector had no further questions in this area.
l t
d
9
l l
/
.*
.
l l
,
l
. _
_
. _.
.
I
_
_
-
S,
_
._
-., ~.