IR 05000259/1978020
| ML18024A502 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| Issue date: | 09/12/1978 |
| From: | Sullivan R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18024A501 | List: |
| References | |
| 50-259-78-20, 50-260-78-21, 50-296-78-19, NUDOCS 7811010280 | |
| Download: ML18024A502 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30303 Report Nos.:
50-259/78-20, 50-260/78-21 and 50-296/78-19 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:
August 7-10, 1978 Inspector:
R. F, Sullivan
/
Reviewed by:
(
H.
C. Dance, Chief Reactor Projects Section No.
Reactor Operations and Nuclear Support Branch P /z 7g a
e Ins ection Summa Ins ection on Au ust 7-10 1978:
(Re ort Nos. 50-259/78-20 50-2 0 78-21 and 50-29 78-19 Areas Ins ected:
Routine, unannounced inspection of plant operations, reportable occurrences, electrical modifications and plant tour.
The inspection involved 30 inspector-hours onsite by one NRC inspector.
Results:
Of the four areas inspected no apparent items of noncompliance or deviations were identifie h J
RII Rpt. Nos. 50-259/78-20 50-260/78-21 and 50-296/78-19 DETAIIS I Prepared by:
R. F. Sullivan, Reactor Inspector Reactor Projects Section No.
Reactor Operations and Nuclear Support branch
~q(i/~ b Date Dates of Inspection:
August 7-10, 1978 Reviewed by:
C H.
C. Dance, Chief Reactor Projects Section No.
Reactor Operations and Nuclear Support Branch 1.
Persons Contacted
- J.
G. Dewease, Plant Superintendent-H. L. Abercrombie, Assistant Plant Superintendent J. L. Harness, gA Supervisor
+J.
B. Studdard, Operations Supervisor R. Hunkapillar, Assistant Operations Supervisor J.
A. Teague, Assistant Maintenance Supervisor R.
G. Metke, Results Section Supervisor A. L. Burnette, Shift Engineer T. E. Mayfield, Shift Engineer W.
W. Banks, Shift Engineer T.
W. Jordan, Shift Engineer P. Crabb, Work Plan Coordinator
- Denotes those present at the Exit Interview.
2.
I,icensee Action on Previous Ins ection Findin s Not inspected.
3.
Unresolved Items No new unresolved items were identified during this inspection.
t 4.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on August 10, 1978 At this meeting the inspectors discussed the areas inspected and their findings as discussed in this report.
The licensee was informed that there were no items of noncompliance or deviations identifie ~
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RII Rpt. Nos. 50-259/78-20 50-260/78-21 and 50-296/78-19 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 compliance with Technical Specifications and other regulatory requirements.
The inspector examined selected Plant Operations Review Committee minutes, internal correspondence, work plans, operating records and discussed events with appropriate personnel.
LER No.
Date Event
- 259/788 259/7820 7/15/78 Hydrogen monitoring sensor in torus failed.
3/31/78 Analysis revealed potential undervoltage problem under certain conditions.
- 260/789 5/5/78 Total local leak rates exceeded limit.
260/7814
- 296/786 7/18/78 4/20/78 HPCI inoperative.
Connector assemblies on temperature monitoring not qualified.
296/7811 296/7814 5/8/78 7/18/78 Radiation air monitor inoperative.
Main steam isolation valve closed too fast.
296/7816 7/24/78 HPCI inoperable.
- 296/7819 7/25/78 Crack in weld on an instrument line.
+Denotes reports which were further reviewed at the site.
Corrective action taken was determined to be satisfactory.
No items of noncompliance'or deviations were identified by the inspecto RII Rpt. Nos. 50-259/78-20 50-260/78-21 and 50-296/78-19 I-3 6.
In lant Electrical S stem Modifications The inspector reviewed records on the modifications to the inplant electrical systems which had been authorized by NRC as Amendment Nos.
39, 37 and 13 to the licenses for Units 1, 2 and 3.
TVA deemed these modifications necessary as a result of an analysis based on inplant measurements which indicated a postulated undervoltage condition for a three unit shutdown situation.
This was reported to NRC in IZR BFRO-50-259/788.
The inspector examined the following Engineering Change Notice (ECN) with the associated work plans to verify that required safety evaluations, reviews, approvals and inspections were conducted in connection with the modification:
ECN No.
P0081 Change Alternate Power Supplies For 4-KV Unit Boards 3A, 3B and 3C ECN No. P0088 Add Capacitors to the 161-KV System The inspector noted that the modifications had received review and approval of both the onsite and offsite safety committees and that the work was completed prior to restart of Unit 2 from its refueling outage on June 26, 1978.
The inspector had no further questions on this activity.
7.
A review was made of plant operations for all three units with emphasis on the period July 20-31, 1978, to ascertain that operations were being conducted in accordance with the Technical Specifications and other regulatory requirements.
The review included examination of the following selected records for the dates or periods indicated:
b.
c ~
d.
e.
Shift Engineers Journal 7/20-31/78 Assistant Shift Engineers Journal, Unit 1, 2 and 3, 7/20/78 Unit Operators Journals, Units 1, 2 and 3; 7/20-30/78 Auxiliary Unit Operators Journals, Units 1, 2 and 3; 7/20-30/78 Jumper, Inhibit and Wire Removal log, Units 1, 2 and 3; a total of about 175 active items most of which were not safety-relate P RII Rpt.
Nos
~ 50-259/78-20 50-260/78-21 and 50-296/78-19 I-4 g ~
h.
Corrective Action Reports, all 3 units; 10 items during current year.
S.E. Nite Orders; current items.
Surveillance Instruction 2, Units 1, 2 and 3; 7/16-22/78 The inspector noted that among the relatively large number of JIWR items, there were many dating back to 1976 and 1977 which appeared to be enjoying a semi-permanent status.
The inspector discussed with plant staff the advisability of reviewing the older items for applicability as permanent changes to the facility and to consider separating non-safety-related items to make a more manageable list of current safety-related items.
The superintendent agreed to review the matter.
The inspector indicated that he would followup on this matter in future inspections.
The inspector toured portions of all three reactor buildings and visited the control room of each.
Control room activities were observed on two different shifts.
Observations included instrument readings and recordings, valve line-ups, snubber positions, housekeeping, tag status and annunciator alarms.
Control room activities observed were those associated with full power operation on each unit.
Informal discussions were held with operators and supervisors concerning current activities and plant status.
(}uestions developed by the inspector were satisfactorily answere ll
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