IR 05000269/1980013
| ML19310A136 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/23/1980 |
| From: | Jape F, Martin R, William Orders NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19310A133 | List: |
| References | |
| 50-269-80-13, 50-270-80-08, 50-270-80-8, 50-287-80-08, NUDOCS 8006060152 | |
| Download: ML19310A136 (5) | |
Text
o UNITED STATES
-
~*
NUCLEAR REGULATORY COMMISSION
,,
$
E REGION 11
,
e
~[
101 MARIETTA ST., N.W., SUITE 3100 o
S b
ATLANTA, GEORGIA 30303 g
o
.....
Report Nos. 50-269/80-13, 50-270/80-08 and 50-287/80-08 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility: Oconee Nuclear Station Docket Nos. 50-269, 50-270 and 50-287 License Nos. DPR-38, DPR-47 and DPR-55 Inspection at Ocon Nuclear Station Units 1, 2, and 3 Inspectors:
/74/4 1e
N F. Jape p
I)6te S'igned
$dA
$YYPD W. T. Or
'
Dite jrigned Approved by:
'A dd
/!2-V[0
'
R. O flartin, Section Chief, RONS Branch D/te Signed SUMMARY Inspection on March 3-31, 1980 Areas Inspected This routine inspection involved 108 resident inspector hours on site in the areas of plant operations, outage activities, followup on previous inspection findings, and review of LER's.
Results
>
Of the four areas inspected, no items of noncompliance or deviations were
.
identified.
i 0 $
g 606
__.
-
.
.
.
..
- _ _ _ _ _ _ _ _ _ _ _ -.
_ _ _ _ _ _ _ _ _ _.
,
,
DETAILS 1.
Persons Contacted Licensee Employees
- J. E. Smith, Station Manager
- J. M. Davis, Superintendent of Maintenance
- J. N. Pope, Superintendent of Operations
- T. B. Owen, Superintendent of Technical Services
- R. T. Bond, Licensing and Projects Engineer
- J. Brackett, Senior QA Engineer Other licensee employees contacted included 20 operations supervisors, 8 technicians, 25 operators and 6 mechanics.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on March 7 and 28, 19'O with those persons indicated in Paragraph I above. The inspectica 1".d2 ngs were acknowledged without significant comment.
3.
Licensee Action on Previous Inspection Findings (Closed) Open Item (269/80-04-02; and 270/287/80-03-02) Procedure for a.
Qualifying High Level Gaseous Radioactivity Releases during Accident Conditions.
Che inspector reviewed procedure HP/0/B/1006/05 which was revised to incorporate concentration units compatible between the body of the procedure and the attached graphs. There were no further questions.
b.
(Closed) Open Item (269/80-04-01; 270/287/80-03-01) Emergency Equipment Inventory. The inspector reviewed procedure HP/0/B/1009/01 which had been revised to provide an operational / inventory check of the emergency equipment in the conference room and set a limit of three days for removal of instruments for calibration or repair. The inspector had no further concerns.
4.
Unresolved Items Unresolved items were not identified during this inspection.
S.
Plant Operations
,
The inspector reviewed plant operations, throughout the report period, to
,
'
asertain conformance with regulatory requirements, technical specifications and administrative directives. The control room logs, shift supervisors'
,
_.__
.. _
_
_
~.
.
-2-i.
logs, shift turnover records, and the removal and restoration record books for all three units were reviewed.
Interviews with plant operations, maintenance, chemists, health physicists and performance personnel were held on the day and night shifts.
Activities within the control rooms were observed and monitored during day and night shifts and at shift changes. The actions and activities were conducted as prescribed in Section 3.08 of the Station Directives. The number of licensed personnel on each shift met or exceeded the minimum required by IEB 79-05C. Operators were assigned special duty as required by the February 7, 1980 Show Cause Order. Plant tours were taken during the inspection period as follows:
a.
Turbine Building b.
Auxiliary Building c.
Unit 2 and 3 Reactor Buildings d.
Unit 1, 2 and 3 Electrical Equipment Rooms Unit 1, 2 and 3 Cable Spreading Rooms e.
f.,
Station Yard Areas within the protected area g.
Unit land 2 Spent Fuel areas Observations were made during the tours of housekeeping and cleanliness, ongoing activities, security, equipment status and radiation control practices.
In general, housekeeping and cleanliness were found to be satisfactory.
Security and radiation control practices were adhered to during the periods of observation.
Fluid leaks were observed in the turbine building on secondary, non-safety-related equipment.
Lock out tags on equipment required to be tagged were found as specified by Station Directive 3.1.1.
Within the areas inspected, no items of noncompliance or deviations were identified.
6.
Outage Activities During the report period outage activities at Units 2 and 3 were observed for compliance with regulatory requirements and administrative directives.
The activities observed are listed below and within the areas inspected no items of noncompliance or deviations were identified.
The activities were revised to verify that appropriate limiting conditions for operation were met, maintenance activities were accomplished using approved procedures and approvals were obtained prior to initiating the work.
The following acceptance criteria were utilized in determining if the activity was acceptable.
Final Safety Analysis Report a.
b.
Technical Specifications
,
c.
Station Directives 3.1, 3.3, and 3.7
.
._.
.. _ _
_. _ _
..
.
-..
.-
-
.
.
-3-The activities observed and reviewed were as follows:
(1) NSM 1391, "PORV and Code Safety Valve Position Indication". This modification provides a direct indication of the power-operated relief valve and safety valves position within the control room.
Installation of the conduit within Units 2 and 3 reactor buildings was observed.
Installation of the readout panel in the control rooms was also observed.
(2) NSM 1392, " Diverse Containment Isolation Signals".
Containment isolation was previously initiated on reactor building pressure of 4 psig. Automatic isolation has been modified to actuate on
,
either reactor building pressure or engineered safeguards initiation.
The rewiring of the cable spreading rooms and control rooms was observed.
(3) RC-66 Position Indicator, Troubleshooting.
Work Request 46816 was issued to correct a faulty position indication on RC-66, the valve was verified to be closed, yet the position indicator showed the valve partially open. The repair was controlled by IP/0/A/100/01 and was observed by the inspector.
(4) Hydraulic Suppressors. As a result of a problem, identified in LER 269/79-20, a locking device to prevent rotation of hydraulic suppressors is being installed. The locking device consists of two set screws to lock the suppressor in place. This activity was observed in Unit 2 reactor building. The suppressors on the main steam headers were repaired. The work was controlled by MP/0/A/3018/01 and by work requests.
(5) Refueling. Fuel handling operations were observed in the reactor building, spent fuel pool and control room. The refueling activ-ities are controlled by OP/0/A/1502/07, and were found to be in compliance with technical specifications. The licensee is main-taining access control for personnel and equipment brought into the transfer area while the reactor head is off. A log of all equipment is maintained. Their records were reviewed and the control was observed on five different occasions by the inspector.
(6) Reactor Internal Vent Valve Examination. The eight reactor internal vent valves are examined as part of the inservice inspec-tion program. The examination includes looking for misaligned valves, damaged components and status of locking devices. The work is done with underwater TV camera. The inspector witnessed the video taping examination of six of the eight valves. All were found satisfactory.
-
7.
Review of Licensee Event Reports The inspector performed an in-office review of nonroutine event reports to verify that the report details met license requirements, identified the i
.
._.
..
.
,
.
-4-
,,
cause of the event, described corrective cetions appropriate for the identi-fied cause, and adequately addressed the event and any generic implications.
In addition, for those reports marked with an asterisk, the inspector examined selected operating and maintenance logs and records and internal incident investigation reports. Personnel were interviewed to verify that the report accurately reflected the circumstances of the event, that the corrective action had been taken or responsibility assigne to assure com-pletion and that the event was reviewed by the licensee as stipulated in the Technical Specifications. The following event reports were reviewed:
- R0-269/79-35, SFP Radiation Monitor Inoperable
- RO-269/79-36, HPSW Pump Inoperable
- R0-270/79-08, RB Penetration Inoperable
- RO-270/79-09, HPI Suction Valves Rendered Inoperable
- RO-287/79-12, LPSW Pump Out of Service
<
4
,
,
-