IR 05000259/1982018

IE Insp Repts 50-259/82-18,50-260/82-18 & 50-296/82-18 on 820626-0725.No Noncompliance Noted.Major Areas Inspected: Operational Safety,Ros,Surveillance Testing,Maint Observation,Tmi Action Items & Independent Insp Effort

ML20062J582
Person / Time
Site:	Browns Ferry
Issue date:	07/26/1982
From:	Cantrell F, Chase J, Paulk G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20062J538	List: IR 05000259/1982018 ML20062J536
References
TASK-2.B.1, TASK-TM 50-259-82-18, 50-260-82-18, 50-296-82-18, IEB-79-01B, IEB-79-1B, IEB-79-27, NUDOCS 8208160408
Download: ML20062J582 (8)

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p* Rf %g UNITED STATES ,

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o WUCLEA" REGULATORY COMMisslOM y '

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5 a-101 MARIETTA STREET, *

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i Report flos. 50-259/82-18, 50-260/82-18 and 50-296/82-18 4 i

. Licensee: Tennessee Valley Authority ,

500A Chestnut Street

Chattanooga, Til 37401

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Facility Name: Browns Ferry fluclear Plant  ;

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Docket Nos. 50-259, 50-260 and 50-296 F

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License Nos. DPR-33, DPR-52 and DPR-68 *

Inspection at Browns Ferry site near Athens, Alabama  !

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Inspectors

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J W. Chass Date Signed I O (, 7 -6 4 A G. L. Paulk

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Approved by: , 4d([

F. S. Cantrell, Sectidn/Afef, Division of 7 C Date Sig'ned 2- '

j Projects and Resident Programs l r

SUMMARY I l

Inspection on June 26 - July 25, 1982

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Areas Inspected

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! This routine inspection involved 110 resident inspector-hours in the areas of (

i operational safety, reportable occurrences, surveillance testing, maintenance observation, TMI action items, independent inspection effort, plant physical

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! protection and bulletin revie :

Results F

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j Of the eight areas inspected, no violations or deviations were identifie l

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PDR ADOCK 05000259 *

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l DETAILS .

a Persons Contacted i G. T. Jones, Power Plant Superintendent

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J. R. Bynum, Assistant Power Plant Superintendent J. R. Pittman, Assistant Power Plant Superintendent L. W. Jones, Quality Assurance Supervisor  ;

W. C. Thomison, Engineering Section Supervisor l l A. L. Clement, Chemical Unit Supervisor  !

D. C. Mims, Engineering and Test Unit Supervisor I i A. L. Burnette, Operations Supervisor

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R. Hunkapillar, Operations Section Supervisor i T. L. Chinn, Plant Compliance Supervisor M. W. Haney, Mechanical Maintenance Section Supervisor

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T. D. Cosby, Electrical Maintenance Section Supervisor 4 R. E. Burns, Instrument Maintenance Section Supervisor

J. E. Swindell, Field Services Supervisor

A. W. Sorrell, Supervisor, Radiation Control Unit R. E. Jackson, Chief Public Safety

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j R. Cole, QA Site Representative, Office of Power '

i Other licensee employees contacted included licensed reactor operators and ;

j- senior reactor operators, auxiliary operators, craftsmen, technicians, '

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public safety officers, Quality Assurance, Quality Control and engineering l personnel.

s l Management Interviews ,

Management interviews were conducted on July 2, 9, and 16, 1982, with the i Power Plant Superintendent and/or the Assistant Power Plant Superintendents ,

i and other members of his staff. There were no violations or deviations *

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Licensee Action on Previous Inspection Findings j-i

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(Closed)OpenItem(259/82-06-05) Spread of airborne contamination during 1 maintenance. A health physics memorandum now requires all sump pumps being i removed for maintenance be coated with a lightfilm of oil and wrapped in I

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plastic to minimize the spread of airborne contamination. The inspector had ( no further questions in this are ,

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(Closed) Violation (259/82-06-04) Failure to perform safety evaluation on

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I radwaste drain line. The licensee has rewritten Standard Practice (SP) 8.2, !

l Temporary Alterations, which now requires an Unreviewed Safety Question .

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Determination (USQD) to be performed prior to installing a temporary ( alteration. This SP is compatable with 10 CFR 50.59 which requires a USQD

on any modification made to a system described in the Final Safety Analysis l Report (FSAR). The inspector had no further questions in this area.

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(Closed) Violation (259, 260, 296/82-06-01) Failure to follow procedur This violation identified six specific instances in which plant personnel failed to adhere to plant procedures. TVA responded to the overall violation stating that TVA has expanded considerable effort in improving management control system Since this violation, the number of violations involving failure to follow procedure has decreased significantly. This indicates that the improvement in the management control system has been positive. This item is considered closed; however, the inspectors will continue to monitor TVA's ptogress in this are (Closed) Deviation (259/82-12-04) Failure to update Muscle Shoals Emergency Control Center Implementing Procedure 10. The Division of Nuclear Power has combined all identified commitment dates into a single computerized Committment Control System to ensure commitment dates are met on schedul The inspector had no further questions as the procedure has been adequately revise (Closed) Open Item (259, 260, 296/82-12-05) Update MMI-6 to cover proper diesel engine filter maintenance. The licensee updated MMI-6 to include all diesel engine related filters on a preventive maintenance schedule. The inspector has no further question In the above area, no violations or deviations were identifie . Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or deviations. A new unresolved item is identified during the inspection and is discussed in paragraph . 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 ard various members of the plant operating staf The inspectors made frequent visits to the control room 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; status and alignments of emergency standby systems; purpose of temporary tags on equipment controls and switches; annunciator alarms; adherence to procedures; adherence to limiting conditions for operations; temporary alterations in effect; daily journals and data sheet entries; and control room manning. This inspection activity also included numerous informal discussions with operators and their supervisor General plant tours were conducted on at least a weekly basis. Portions of the turbine building, each reactor building and outside areas were visite Observations included valve positions and system alignment; snubber and

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hanger conditions; instrument readings; housekeeping; radiation area con-trols; tag controls on equipment; work activities in progress; vital area controls, personnel badging, personnel search and escor Informal discus-sions were held with selected plant personnel in their functional areas during these tours. In addition a complete walkdown of the plant emergency D. C. power supply batteries was conducte During the walkdown of the Unit 3 battery board room, the inspector observed cable conduit support bracket bolts missing on pipe conduit running from the Unit 3 preferred A. C. bus transformer (37.5 KVA) to the Unit 3 bus A and B alternate source power box. The inspector informed plant management and an investigation was begun to ensure support requirements are properly me The inspector reviewed various workplans to determine when the supports were installed, but no workplans were located to describe the installation to date. This item will remain unresolved and followed up on future inspections. (296/82-18-01).

During an operational safety tour of the Unit I reactor building at 12:45 on July 13, 1982, the inspector observed a posted fire watch at the High Pressure Coolant Injection Pump Room not fully alert. The inspector notified the shift engineer and the plant safety engineer of his obser-vations. The plant safety engineer toured the area at 1318 and noted the firewatch to be apparently asleep. The firewatch was relieved of firewatch duties. The inspector considers this item closed due to prompt management attentio . Independent Inspection Effort During this report period, the licensee identified two surveillance instructions (SI) as being over-due for performance, SI 3.2.8 (Testing of HPCI and RCIC Vacuum Relief Valves) and SI 4.11.D-3 (Monthly Visual Inspection of Fire Protection). The inspector reviewed the licensee's method for identifying and tracking late si If an SI is not completed on the due date, Plant Services places the test on its Weekly Status Reports of sis. This list is distributed to plant management for actio If the SI is still over-due the next week, it is identified as being a repeat item but no reason is given for why it is over-due nor is there a system to adequately alert plant management to a potential proble In the case of SI 3.2.8, it appeared on the Weekly Status Report of sis three times before action was taken to perform the required test. In addition, this SI appeared on the Status of Routine Maintenance list, (which identifies over-due maintenance), four times before action was taken to perform the required work. This item will remain open pending the inspector's review of corrective action (259, 260, 296/82-18-02).

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7. Bulletin Review Licensee action on the below listed bulletin was reviewed by a Region II inspector to determine if the evaluation and action taken was appropriate to satisfy the concerns described in the bulletin. The inspection consisted of records, drawings and procedure review and discussions with plant personne The below listed bulletin is cbnsidered closed on Units 1 and 3: IE Bulletin 79-27 " Loss of Non-Class IE Instrumentation and Control Power System Bus During Operation."

In the above area, no violations or deviations were identifie . Surveillance Testing Observation The inspectors observed the performance of the below listed surveillance procedures. The inspection consisted of a review of the procedure for technical adequacy, conformance to technical specifications, verification of test instrument calibration, observation on the conduct of the test, removal from service and return to service of the system and a review of test dat S.I. 4.2.D.1, Off-Gas Post Treatment Radiation Monitor S.I. 4.1.B.2, Reactor Water Level, Unit 3 S.I. 4.2.A.8, Group I isolation; Main Steam Line High Temperature, extensive review was performed for emergency technical specification changes evaluation, to allow operation with a failed switch in the untripped channel condition. The inspector verified that the instru-ment channel was in the tripped condition until emergency technical specification changes can be receive In the above area, no violations or deviations were identified.

l 9. Maintenance Observation

! During the report oeriod, the inspectors observed the below listed main-tenance activities for procedure adequacy, adherence to procedure, proper tagouts, adherence to Technical Specifications, radiological controls, and t

adherence to Quality Control hold points: Torus modifications Unit 2 i Electrical Maintenance Instruction 72, Checking the VS Relays on Speed l Sensing Panels on the 3B Diesel Generator

Electrical Maintenance Instruction 3, Unit 3 Diesel Generator Redundant

! Start Test.

In the above areas, no violations or deviations were identified.

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10. Reportable Occurrence The below listed licensee event reports (LERs) 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 the relative safety significance of each event. Additional inplant reviews and discussions with plant personnel as appropriate were conducted for those reports indicated by an asterisk:

LER N Date Event 259/80-31R1 6/01/82 Electrical fault on 480V Shutdown Board 1 *260/82-09 3/02/81 2B Recirculation Motor MG set trip

• 296/81-28 6/13/81 3A Recirculation Motor MG set trip

• 296/81-31 6/24/81 3A Recirculation Motor MG set trip

• 260/81-54R1 10/10/81 Hydrogen analyzer "B" sample return pump inoperable

• 260/81-62 11/17/81 Main steam line radiation monitors erratic 296/81-62R1 10/09/81 DG3C inoperable to calibrate relay

• 260/82-01-R1 01/15/82 Input error to process computer 296/82-11 04/14/82 RPS water level switch setpoint drift 296/82-12 04/22/82 Drywell high pressure setpoint drift

• 260/82-14 04/20/82 Failure to perform SI when HPCI was inoperable

• 260/82-16 05/19/82 Loss of oil in HPCI oil reservoir 259/82-18R1 06/01/82 Missing turbine exhaust outer rupture disc on RCIC. (Will be inspected on Followup to Violation 259/82-12-06)

296/82-21 05/25/82 Core standby cooling system switch setpoint drift 259/82-22 03/24/82 CAM flow control valve inoperable

• 259/82-23 03/27/82 "A" Recirculation pump trip

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• 296/82-24 05/23/82 Failure to control rods to meet 5%  ;

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259/82-26 04/22/82 Failure of windspeed indicator

) 259/82-29 05/21/82 Ventilation monitoring recorders found [

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j 259/82-32 06/10/82 "A" RHR and CS pump inoperable while ,

4 HPCI was inoperable. (Will be

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inspected on Follow-up to Violation  !

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259/82-15-01).

• 259/82-33 05/26/82 Degraded voltage relay drift i 259/82-34 05/13/82 Radiation Monitor setpoint drift

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j *259/82-35 06/22/82 Exceeded four hour downtime allowed by

technical specification for post-treat- I j ment monitor, ,

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in the above area, no violations or deviations were identifie :

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! 11. Plant Physical Protection

l During the course of routine inspection activities, the inspectors made i observations of certain plant physcial protection activities. These  ;

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j included personnel badging, personnel search and escort, vehicle search and escort, communications and vital area access control.

One violation was noted in this area by the resident inspector on July 8, [

{ 1982. This violation will be discussed and included in inspection report  !

259,260,296/82-2 r 12. TMI Action Items  ;

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11.B. Reactor Coolant System Vents - This action item required the

' licensee to install vent lines off the reactor coolant system and the r i reactor vessel head high point. Browns Ferry is constructed with a vent  !

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line which the licensee believes meets the intent of II.B.1.2. This vent l line comes off between the reactor vessel and the "C" inboard Main Steam l

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Isolation Valve (MSIV) and also from the reactor vessel head. There are two i remote operated isolation valves in the line which are actuated from the  ;

! control room. The line vents to clean radwaste. This item will remain open ,

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l II.B. Plant Shielding - Equipment Qualification - This item requires  !

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the licensee to have qualified safety-related equiment which will not be j

! unduly degraded by radiation during post accident operation. This includes  ;

! equipment inside and outside the containment. TVA's response to this item ,

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is documented in response to IE Bulletin 79-01B. The licensee's response is currently under review by the NR III. Emergency Preparedness - Action Items III.A. (Install Facility Hardware and Software), III.A. (Full Capability for Facilities) and III.A.2.6. (Licensee Review of DCM) will be inspected during the next inspection by the NRC Emergency Preparedness Team. This item will remain open pending satisfactory completion of that inspectio In the above area, no violations or deviations were identifie ;

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