IR 05000259/1978025
| ML18024A582 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/09/1978 |
| From: | Dance H, Sullivan R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18024A581 | List: |
| References | |
| 50-259-78-25, NUDOCS 7812180325 | |
| Download: ML18024A582 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30303
++*de +
Report Nos.:
50-259/78-25, 50-260/78-28 and 50-296/78-24 Docket Nos.:
50-259, 50-260 and 50-296 License Nos.:
DPR-33, DPR-52 and DPR-68 Licensee:
Tennessee Valley Authority 830 Power Building Chattanooga, Tennessee 37401 Facility Name:
Browns Ferry Units 1, 2 and
Inspection at:,
Browns Ferry Site, Athens, Alabama Inspection conducted:
September 25-27, 1978 Inspector:
R. F. Sullivan Accompanying Personnel:
B. Moon Reviewed by:
e H. C. Dance, C ief Reactor Projects Section No.'
Reactor Operations and Nuclear Support Branch ate Ins ection Summar Ins ection, on Se tember 25-27 1978 (Re ort Nos. 50-259/78-25 50-260/78-28 and 50-296/78-24 tions, LER review, IE Circulars and Bulletins, and plant tour.
The inspec-tion involved 42 inspector-hours by two NRC inspectors.
Results:
Of the four areas inspected no apparent item of noncompliance or deviations were identifie RII Report Nos. 50-259/78-25, 50-260/78-28 and 50-296/78-24 DETAILS I Prepared by:
R.
. Sullivan, Reactor Inspector Reactor Projects Section No.
Reactor Operations and Nuclear Support Branch Date Reviewed by:
Dates of Inspection:
Se tember 25-27, 1978 C
H. C. Dance, Chief Reactor Projects Section No.
Reactor Operations and Nuclear Support Branch
)8 Date 1.
Persons Contacted-J.
D. Dewease, Plant Superintendent-H. L. Abercrombie, Assistant Plant Superintendent
"'J. L. Harness, QA Supervisor J.
B. Studdard, Operations Supervisor R. Hunkapillar, Assistant Operations Supervisor J. A. Teague, Assistant Maintenance Supervisor M. A. Haney, Mechanical Maintenance Supervisor R.
G. Metke, Results Section Supervisor J.
R. Pittman, Instrument Engineer G. T. Jones, Outage Director W. C. Thomison, Chemical Engineer L. Blankner, Reactor Engineer-R. Cole, QA Site Representative, Office of Power
"Denotes those present at the exit niterview.
2.
Licensee Action on Previous Ins ection Findins Not inspected.
3.
Unresolved Items No new unresolved items were identified during this inspection.
4.
Exit Interview The inspectors met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on September 27, 1978.
The findings in the areas inspected were discussed.
The licensee was informed that there were no items of noncompliance or deviations identifie RII Report Nos. 50-259/78-25, 50-260/78-28 and 50-296/78-24 I-2 5.
Re ortable Occurrence Review The below listed licensee event reports were reviewed in the office for potential generic problems, to detect trends, to determine if the information provided meets NRC reporting requirements and to consider whether corrective action discussed appeared appropriate.
Selected reports, as denoted, were further reviewed at the site to verify adequacy of information provided, corrective action taken, and com-pliance with the Technical Specifications and other regulatory require-ments.
The inspector examined selected Plant Operations Review Committee minutes, internal correspondence, operating records and discussed events with appropriate personnel.
LER No.
259/7815 Date 6/13/78 Event Drywell hyrogen monitor inoperative 259/7818-259/7821 6/2/78 7/21/78 Torus oxygen monitor inoperative Rod sequence control system inoperative 259/7822 8/3/78 Diesel generator field breaker tripped 259/7824-259/7825-259/7826 8/7/78 8/28/78 9/15/78 Reactor water level switch setpoint drift Weld material in vessel may be other than spec Drywell leakage above limit due to valve packing leak 260/786 296/7815 5/5/78 7/27/78 HPCI check valve stuck open Defective 4-KV standby power circuit breaker 296/7817 296/7818 8/3/78 8/3/78 Control room smoke detector inoperative RCIC system inoperative
RII Report Nos. 50-259/78-25, 50-260/78-28 and 50-296/78-24 I"3 296/7820 8/17/78 Main steam high flow switch setpoint drift
""296/7821 8/30/78 Main steam relief valve failed to reset
-"296/7822 296/7823 9/1/78 9/13/78 Main steam relief valve opened below setpoint Auxiliary instrument room smoke detector inoperative
"Denotes reports which were further reviewed at the site.
Reports 296/7821 and 296/7822 did not provide sufficient information in the description for the inspector to make a meaningful evaluation; however, reference to operating records and recording and discussion with plant personnel provided the needed information.
The licensee agreed to submit revised reports of these two events which would include a
more complete description of the events.
The inspector identified this as an open item (296/78-24-01).
Corrective action taken or implemented on the other reports was determined to be satis-factory.
No items of noncompliance or deviations were identified by the inspector.
6.
IE Circular and Bulletin Followu The inspectors reviewed licensee action on the following circulars and bulletins:
IEC 78-07, Damaged Components of a
Bergen-Paterson Series 25000 Hydraulic Test Stand IEC 78-08, Environmental 'qualifications of Safety-Related Electrical Equipment IEC 78-11, Recirculation M-G Set Overspeed Stops IEB 78-09, BMR Drywell Leakage Paths Associated with Inadequate Drywell Closures IEB 78-10, Bergen-Patterson Hydraulic Shock Suppressor Accumulator Spring Coils Discussions were held with licensee personnel and internal files were examined.
Licensee action had been completed or initiated on IEC's
RII Report Nos. 50-259/78-25, 50-260/78-28 and 50-296/78-24 I-4 78-07, 78-08 and 78-11 and the inspector considered these closed.
On IEB's 78-09 and 78-10 the inspector informed the licensee that further followup would be made.
The inspectors review of IEC 78-08 revealed that plant personnel did address all the items in the Circular and had requested the assistance of the Division of Design Engineering to initiate a program to identify all safety-related electrical components which required the post-acci-dent qualification and to furnish qualification documentation to the plant.
Design Engineering was in the process of scoping of the request and had not yet set a schedule for completing the assignment.
The inspector indicated that he would identify this as an open item to review the progress of the, program on subsequent inspection (259/78-25-01).
No items of noncompliance or deviations were identified by the inspector.
Startu Procedures Followin Refuelin The inspector reviewed the licensees plans for startup of Unit 3 following completion of the current refueling outage.
Plant procedures require a prestartup review which include provisions to assure that core reassembly and systems disturbed or modified and returned to operating status prior to resumption of operations.
The required Master Refueling Test Instruction (MRTI) was being developed for the pending startup of Unit 3.
Review by the Plant Operations Review Committee and approval by the Plant Superintendent are procedural requirements.
Procedures applicable to the startup which the inspector reviewed included:
a.
Standard Practice 3.4, Unit Prestartup Review b.
Standard Practice 101, Refueling Test Program The inspector had no further questions in this area.
Tour The inspectors toured portions of each Units reactor building, the refueling floor and each Units'ontrol room.
Observations included work activities in progress, instrument readings and recordings, house-keeping and systems status.
Unit
was being operated at 55~ power with one recirculation loop idle which had been authorized by a recent Technical Specification change.
The inspectors verified that conditions of the Technical Specifications were being met.
The operating loop, "A", was at 50$
RII Report Nos. 50-259/78-25, 50-260/78-28 and 50-296/78-24 I-5 pump speed.
The pump speed had been operated up to 80$ but was returned to 50$
because the jet pump differential pressure gauges indicated oscillations greater than experienced during normal two loop operations.
The oscillations followed an erratic pattern with pressure fluctuations at the 80/ level about twice the
!2 psi normally observed.
G.E.
had been contacted and plans were made to obtain special recordings of pump speed, LPRM responses and core flow for further evaluation of single loop operation.
The inspectors made a
special escorted tour of the main condenser off-gas system which included accessible components, controls and monitoring instrumentation in the turbine building, the service building, the off-gas treatment building and the stack house.
Emphasis was placed on the location of loop seals and the monitoring of their integrity and the adequacy of ventilation in these locations.
The inspectors'uestions were satisfactorily answered.
No items of noncompliance or deviations were identified by the inspec-tion