IR 05000259/1980019
| ML19318A799 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/24/1980 |
| From: | Chase J, Dance H, Sullivan R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19318A791 | List: |
| References | |
| 50-259-80-19, 50-260-80-14, 50-296-80-15, NUDOCS 8006240174 | |
| Download: ML19318A799 (5) | |
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UNITED STATES
NUCLEAR REGULATORY COMMISSION v{
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REGION II
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101 MARIETTA sT N.W., SUITE 3100 o,
ATLANTA, GEORGIA 30303
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Report Nos. 50-259/80-19, 50-269/80-14 and 50-296/80-15
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Licensee: Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, Tennessee 37401
Facility: Browns Ferry Nuclear Plant Docket Nos. 50-259, 50-260, and 50-296
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License Nos. DPR-33, DPR-52, and DPR-68 Inspection at Browns Ferry site near Athens, Alabama Inspectors:
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Date Signed Approved by:
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H. C. Dance, Se'ction Chief, RONS Section Date Signed SUMMARY Inspection on March 7 - April 4, 1980 Areas Inspected This routine inspection involved 124 resident inspector-hours in the areas of operational safety, maintenance, reportable occurrences, followup on noncompliance
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and unresolved items, radiation control, plant physical protection and reactor trips.
j Results Of the seven areas inspected no items of noncompliance were identified in six One item of apparent noncompliance was found in one area (Infraction -
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failure to follow procedures in heat-tre. +. ment of Unit HPCI 1 steam piping, paragraph 7).
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O DETAILS 1.
Persons Contacted Licensee Employees H. L. Abercrombie, Plant Superintendent J..L. Harness, Assistant Plant Superintendent J. B. Studdard, Operations Supervisor R. Hunkapillar, Assistant Operations Supervisor J. A. Teague, Maintenance Supervisor, Electrical M. A. Haney, Maintenance Supervisor, Mechanical J. R. Pittman, Maintenance Supervisor, Instruments R. G. Metke, Results Section Supervisor G. T. Jones, Area Outage Director, BFNP and YCNP J. C. Swindell, Outage Director R. T. Smith, QA Supervisor J. Roche, Mechanical Engineer - Chat. Maintenance E. Hollis, Mechanical Engineer - Chat. Maintenance G. T. Cowles, Mechanical Engineer A. L. Burnett, Shift Engineer R. E. Jackson, Captain, Public Safety J. D. Glover, Shif t Engineer R. R. Smallwood, Shift Engineer R. Cole, QA Site Representative Office of Power Other licensee employees contacted included licensed Senior Reactor Opera-tors and Reactor Operators, auxiliary operators, craftsmen, technicians, public safety officers, QA personnel and engineering personnel.
2.
Management Interviews Management interviews were conducted on March 14 and 28, 1980 staff. The_
inspectors sammacized the scope and findings of their inspection activities.
The licensee was informed on March 13, 1980 that an apparent item of non-compliance had been identified, Corrective action was initiated.
3.
Licensee Action on Previous Inspection Findings The inspectors reviewed licensees response and confirmed correction action taken as indicated.
(Closed) Infraction (78-01-01) - PORC failed to review Technical a.
Specification noncompliance. Administrative procedure revised-to require review.
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b.
(Closed) Deficiency (78-11-01) - Inadequate maintenance documentation on Itcuble Request forms. Forms completed to included proper documen-tation.
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(Closed) Unresolved Item (78-11-02) - Maintenance activities performed without proper approval. Recent authorizations show proper approvals.
4.
Unresolved Items
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No unresolved items were identified during this inspection.
5.
Plant Organization
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Several changes in the the outage organization at Browns Ferry were announced recently. These involved the promotion of Mr. G. T. Jones to the newly created position of Area Outage Director for the Browns Ferry and Yellow Creek Nuclear Plants.
Mr. J. C. Swindell was promoted to Outage Director from Assistant Outage Director.
Mr. J. Miller was promoted to Assistant Outage Director from Outage Scheduling.
The inspectors upon review of the qualifications of the above personnel had no questions.
6.
Operational Safety
The inspectors kept informed on a daily basis of the overall plant status and any significant safety matters related to plant operations. Daily discussions were held each morning with plant management and various members of the plant operating staff.
The inspectors made frequent visits to the control rooms such that each was
visited at least daily when an inspector was on site. Observations included instrument readings, setpoints and recordings; status of operating systems,
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status and alignments of emergency standby systems; purpose of temporary
tags on equipment control switches; annunciator alarms; adherence to procedures; i
adherence to limiting canditions for operations; temporary alterations in effect; daily journals and data sheet entries; and control room manning.
This inspectica activity also included numerous informal discussions with operators and their supervisors.
General plant tours were conducted on at least a weekly basis. Portions of the turbine building, each reactor building and outside areas were visited.
Observations included valve positions and system alignment, snubber and
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hanger conditions, instrument readings, housekeeping, radiation area controls,
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tag controls on equipment, work activities in progress, vital area controls, badging, search and escort.
Informal discussions were held with selected plant personnel in their functional areas during these tours.
No items of noncompliance or deviations were identified by the inspictors in the above areas.
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Unit 1 HPCI Maintenance
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After replacement of the damaged HPCI turbine pedestals which were discovered during the recent refueling outage (IE Report 259/80-13), maintenace personnel
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encountered difficulty in establishing proper alignment of the turbine.
TVA Engineering Design personnel and Maintenance Specialists visited the site on March 9, 1980 to evaluate conditions and outline corrective action.
Distortion of the steam supply piping, which had been attributed to past instances of water hammer, tended to pull the turbine onc of alignment.
The decision was made to bend the pipe back into position by application of heat to certain sections. The inspectors determined that a Trouble Report to authorize the pipe bending was not issued prior to the work activity on March 11, 1980 nor was the TVA procedure, G-29, which established the controls on heat treatment of piping, adhered to.
The procedure specified the use of crayons or equivalent in temperature control where instead visual observation for color changes was used as the pipe was heated by torch. The procedure also specified air cooling and it was determined that wet rags were used to speed up cooldown.
In addition there was no QC coverage provided as required by the QA Manual for special processes. The inspectors identify this as an apparent item of noncompliance (259/80-19-01)
and on March 13, 1980 notified the Assistant Plant Superintendent of this
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A construction specialist inspector from the IE Regional Office was dis-patched to the site on March 13 and 14, 1980 to review the HPCI repair activities and planned NDE testing to confirm that the piping could perform its intended function (IE Report 259/80-14).
An IE inspector witnessed portions of the NDE testing on March 15 and 16, 1980 and confirmed that TVA Engineering Design performed the required evaluation and made the determination that the system remained capable of meeting design requirements. The inspector had no further questions in this area.
8.
Reportable Occurrence Review The below listed licensee event reports were reviewed to determine if the information provided met NRC reporting requirements. The determination included adequacy of event description and corrective action taken or planned, existence of potential generic problems and relative safety sig-aficance of each event.
LER No.
Date Event 259/79-1 1/31/79 7ast period from high notch worth 259/80-2 2/8/80 Wind direction channel at 33 ft elevation
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259/80-5 1/31/80 Piping restraints missing on RECCW system
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259/80-7 2/22/80 Reactor building isolation channel
"B" inoperative
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LER No.
Date Event (CONTINUED)
259/80-9 2/22/80 Reactor building radiation monitor late on surveillance test 259/80-16 2/22/80 Potential for line break in RBCCW system 259/80-18 3/14/80 Shutdown board B failed to transfer on test.
259/80-19 3/14/80 Loss of off-site 161 KV power during ice storm 260/80-6 3/3/80 2A recirculation pump tripped by error 260/80-8 3/6/80 Both recirculation pumps tripped by error 260/80-9 3/12/80
"B" steam line radiation monitor inoperative 260/80-10 3/13/80 HPCI pedestal cracked 290/79-6 R1 11/7/80 Torus hydrogen sensor inoperative 296/80-3 2/22/80 Control rod did not move with normal drive pressure 296/80-4 2/27/80 4160 V bus tie board de-energerized to trans-fer b.ek to normal power supply Corrective action indicated on the above reports was determined to be adequate. The inspectors questions were satisfactorily answered.
9.
Inspector Identified Open Items The inspectors performed followup review of the below listed Open Items and considered these items closed:
a.
78-01-02 - Technical Specification change to be submitted to eliminate outside consultant requirement for NSRB. The T. S. Change has been submitted to NRC.
b.
78-05-01 - Revise E01-39 to define number of times to cycle relief valves and reduce time to remove beat from torus. Pro ~cedure was revised.
c.
78-08-01 - Revise fire protection procedure to reflect actual CO2
.sys em operat on for spreading rooms.
Procedure was revised.
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78-09-03 - Clear hold tags on drywell' penetration. Tags have been cleared.
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