IR 05000259/1980006
| ML18025A881 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/09/1980 |
| From: | Chase J, Dance H, Sullivan R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18025A880 | List: |
| References | |
| 50-259-80-06, 50-259-80-6, 50-260-80-06, 50-260-80-6, 59-296-80-06, NUDOCS 8005270173 | |
| Download: ML18025A881 (12) | |
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UNITEDSTATES NUCLEAR REGULATORYCOMMISSION REGION Il 101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 Report Nos. 50-259/80-06, 50-260/80-06, and 50-296/80-06 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 License Nos.
. ~
Inspection at Bro s Fer Site near Athens, Alabama Xespeetors:I R.
.
ullivan C
J.
W.
C ase Approved by:
C:
H.
C. Dance Section Chief, RONS Branch D
e igned Da e
igned Da e S gned SUMNARY.
Inspection on January 14 through February 1,
1980 Areas Inspected This routine inspection involved 82 resident inspector hours in the areas of plant operations, plant tours, reportable occurrences, refueling, noncompliance followup, IE Bulletin followup, plant physical protection and radiation area controls.
Results Of the eight areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 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, Outage Director J. E. Swindell, Assistant Outage Director R. T. Smith, QA Supervisor D.
C.
Cummin, Outage Health Physicist A. L. Burnett, Shift Engineer R. E. Jackson, Chief, Public Safety J.
D. Glover, Shift Engineer R. R. Smallwood, Shift Engineer R. Cole, QA Site Representative, Office of Power Other licensee employees contacted included Licensed Senior Reactor Opera-t'ors and Reactor Operators, auxiliary operators, craftsmen, technicians,
,public safety officers, QA personnel and engineering personnel.
Management Interviews Management interviews were conducted on January 18, 25, and February 1,
1980 with the Plant Superintendent and selected members of his staff.
The'nspectors summarized the scope and findings of their inspection activities.
The licensee was informed that no items of noncompliance or deviations were identified during this report period.
Licensee Action on Previous Inspection Findings (Closed)
Items of noncompliance (50-269/79-45-01,02 and 03)
(Closed) Unresolved Item (50-269/79-45-04)
The inspectors reviewed licensee actions taken on the three items of non-
'compliance and the one unresolved item identified in IE Report 50-259, 50-260, and 50-296/79-45.
The events covered in that report resulted in the NRC issuing on January 4, 1980, to TVA A Notice of Violation, Notice of Proposed Imposition of Civil Penalties and an Order Modifying License.
TVA responded to these documents by letter dated January 10, 198 ~,
'e The inspectors confirmed that the actions taken were consistent with those described in the TVA response.
This included verification of implementation of requirements imposed by the Order which amended the License.
With respect to the Order all actions were to be completed-by January 15, 1980, which the inspectors determined had been accomplishe'd.'here were some further changes in certain procedures subsequent to this date but they did not involve change in intent.
Item (1) of the Order which imposed the requirement for independent verifi-cation of the restoration of containment penetration closures following maintenance or other activities, was implemented by the issuance of new procedure MMI-95, Closure of Primary Containment Hatches and revisions of other procedures listed below:
BF 6.1 Performance of Maintenance,Rev.
1/20/80 BF 12.15 Primary Containment Integrity, Rev. 1/29/80 BF 13.1 Format for Maintenance Instructions, Rev. 1/ll/80 BF 13.13 Format for Refueling/Special Test Instruction, Rev.
1/21/80 BF 14.9 Entry and Work In Primary Containment, Rev.
1/21/80 BF 13.4 Instructions and Guidelines,Rev.
1/ll/80 BF 13.2 Format for Operating Instructions,Rev.
1/ll/80 BF 13.7 Format for Surveillance Instructions,Rev.
1/ll/80 BF 13.9 Format for Instrument System Maintenance Guideline BFA 28 Plant 'Modifications and Work Plans,Rev.
1/21/80 GOI 100-1 Integrated Plant Operations,Rev.
1/11/80
.With respect to item (2) of the Order dealing with procedures and controls to assure that limiting conditions for operation are not defeated by main-tenance or other activities, the inspectors verified that such a review was conducted and that certain procedures were revised as a result of the review.
Procedures in this category included most of those listed above as well as the following additional procedures.
BF 12.5 Operation of Plant-Operation Responsibility,Rev.
1/29/80 BF 12.14 Operation of Plant - Policy for Adherence to Plant Technical Specifications Limiting Conditions for Operation and Reporting of Significant Events to the NRC, Rev. 1/18/80 With respect to item (3) of the Order dealing with the requirement to implement procedures for removal and replacement of containment penetration closures, the inspectors verified that this requirement was satisfied by certain of the procedures listed above.
Item (4) of the Order concerning reporting requirements were revised and expanded.
Prompt reporting of significant events was further clarified in BF 12.14 which was already mentioned abov ~
~
The inspectors were satisfied that the conditions of the Order were imple" mented as described in the TVA response.
A review was made of the correc-tive action taken relative to the three items of noncompliance identified in the IE Inspection Report.
The inspectors verified that. procedural and administrative controls were implemented as described in the'VA response.
Procedures that. were affected have been previously identjf'ied above.
The inspectors determined that corrective action on the three items of noncompliance was adequate.
Followup was also made on the one unresolved item in the IE Inspection Report.
The issue dealt with adequacy of procedures to detect excessive drywell leakage.
The licensee implemented a new procedure, RI-50, Nitrogen Make-up Flow Review, which provided a formal shiftwise determination of nitrogen usage as indicative of containment integrity.
The inspectors considered this item closed.
4.
Unresolved Items No unresolved items were identified during this inspection
5.
Plant Operations The inspectors and any.'signific kept informed on a daily basis of the overall plant status ant safety matters related to plant operations.
Daily dzscussxons were held with plant management and various members of the plant operations staff.
Frequent visits were made to the shift engineers'office and control rooms to review current reactor operating status and activities.
Special visits were made to other locations in the plant to observe activities and to verify system or component status.
Selected portions of the daily journals and other operating records were reviewed on at least a weekly basis during the report period.
The inspectors made general plant tours on January 15, 26, and 31, 1980.
Portions of the turbine building, each reactor building and outside areas were visited.
Observations included witnessing work activities in progress, status and configuration of operating
'and standby safety systems, valve positions, snubber and hanger conditions, instrument readings and recordings, annunciator alarms, housekeeping, radiation area controls and vital area controls.
Informal discussions were held with operators and other personnel about work activities and plant conditions.
Some of the specific activities observed were:
a.
b.
Shift turnover at the Unit 1 outage station on January 14, 1980.
I Unit 3 approach to critical, attaining critical and low power opera-tions on January 17, 198 No items of noncompliance or deviations were identified by the inspectors in the above area.
6.
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 the relative safety significance of each event.
LER No.
296/7921 296/7922 Date 12/21/79 01/04/80 Event East drywell equipment hatch was leaking Drywell to suppression chamber differen-tial pressure could not be maintained.
296/7924 01/07/80 Iocal leak rate exceeded at equipment hatch.
Corrective action on the above items was determined to be adequate.
IE Bulletin Follows r
l A followup review of the licensee response to IE Bulletin 80-01, Operability of ADS Pneumatic Supply, was made.
The review included examination of
.records, procedures and system drawings as well as discussions with main-
'tenance and stores personnel.
The review disclosed a valve identification error in procedure MMI-42, ADS Relief Valve Air Supply System Testing and Maintenance.
The error was of no safety significance and timely correction to the procedure was made.
The inspectors had no further questions on licensee action to the Bulletin.
IEB 80-01 is closed.
8.
Unit 1 Refueling Several visits were made to the refueling flow to observe fuel handling or other related refueling activities.
I No items of noncompliance or deviations were noted.
9.
Plant Physical Protection During the course of routine inspection activities, the inspectors made observations of certain plant physical protection activities.
These inclu-ded personnel badging, personnel search and escort, vehicle search and escort, communications and vital area access contro No items of noncompliance or deviations were identified within the areas inspected.