IR 05000259/1979001
| ML18024A738 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/12/1979 |
| From: | Dance H, Price D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18024A737 | List: |
| References | |
| 50-259-79-01, 50-259-79-1, 50-260-79-01, 50-260-79-1, 50-296-79-01, 50-296-79-1, NUDOCS 7903210030 | |
| Download: ML18024A738 (4) | |
Text
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t UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30303 Report Nos.:
50-259/79-1, 50-260/79-1 and 50-296/79-1 Docket Nos.:
50-259, 50-260 and 50-296 License Nos.:
DPR-33, DPR-52 and DPR-68 I,icensee:
Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, Tennessee 37401 Facility Name:
Browns Ferry, Units 1, 2 and
Inspection at:
Browns Ferry Site, Athens, Alabama Inspection conducted:
January 13-18, 1979 Inspector:
D.
S. Price Accompanying Personnel:
None Approved by:
H.
C. Dance, Chief Reactor Projects Section No.
Reactor Operations and Nuclear Support Branch 7f Date Ins ection Summar Ins ection on Januar 13-18 1979 (Re ort Nos. 50-259/79-1 50-260/79-1 and 50-29 /79-1 Areas Ins ected:
Routine, unannounced inspection of licensee actions on reportable events, spent fuel rack modifications, and licensee verification of emergency core cooling systems (ECCS)
response times.
The inspection involved 31 inspector-hours on-site by one NRC inspector.
Results:
Of the three areas inspected, no items of noncompliance or deviations were identified.
7903 21003a,
RII Rpt. Nos. 50-259/79"1, 50-260/79-1 and 50-296/79-1 DETAILS Prepared by:
S.
rice, Reactor Inspector Reactor Projects Section No.
Reactor Operations and Nuclear Support Branch 1 2+~ggp Date Dates of Inspection:
January 15-18, 1979 Reviewed by:
H.
C. Dance, Chief Reactor Projects Section No.
Reactor Operations and Nuclear Support Branch 2.-14
~ 1 /
Date 1.
Persons Contacted
- "J. Dewease, Plant Superintendent-H Abercrombie, Assistant Plant Superintendent
="J. Harness, QA Supervisor G. Jones, Outage Coordinator J. Pittman, Instrument Supervisor R. Metke, Plant Results Supervisor R. Cockrel, Reactor Engineer J.
Teague, Electrical Supervisor T. Childress, Drywell Outage Coordinator C. Rozear, QA Lead Engineer R. Perry, QA Engineer R. Burns, Instrument Engineer K. Montgomery, Instrument Engineer J. Harrell, Outage Engineer
- R. Sullivan, NRC Resident Inspector
"-Denotes those present at the exit interview.
2.
Licensee Action on Previous Ins ection Findin s
Not inspected.
3.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviations.
No new unresolved items were identified during this inspectio RII Rpt. Nos. 50-259/79-1, 50-260/79-1 and 50-296/79-1-2-4 ~
Exit Interview The inspection scope and findings were summarized on January 18, 1979 with those persons indicated by an asterisk in Paragraph 1, above.
5.
Review of Nonroutine Events Re orted b
the Licensee The following licensee event reports were reviewed in office for potential generic problems, to detect trends, to determine whether the information included in the report meets NRC reporting requirements, and to consider whether the corrective action discussed in the report appears appropriate.
Licensee action with respect to these reports was reviewed further at the site, as discussed below, to verify that the events were reviewed and evaluated by the licensee as required by Technical Specifications, that corrective action was taken by the licensee and the safety limits, limiting safety system settings and limiting conditions for operations were not exceeded.
A.
Licensee Event No. 50-259/78-28 The licensee reported by letter on October 2, 1978 that he had received a notification from a vendor that instrument power supplies located in main control room panel 9-20 were not seismically qualified.
Replacement power supplies, supplied by the vendor, have been received by the licensee and a Document Change Request is being approved for the replacement.
This licensee event report remains open pending further progress toward installation of the power supplies.
B.
Licensee Event No. 50-296/78-24 The licensee reported by letter on September 29, 1978 that a
broken wire had been found on the signal lead for a Reactor Core Isolation Cooling (RCIC) turbine high steam flow switch which provides RCIC isolation.
The inspector confirmed that the wire has been replaced and the system tested satisfactorily.
The inspector had no further questions and this licensee event report is closed.
C.
Licensee Event No. 50-296/78-29 The licensee reported by letter on November 15, 1978 that two intermediate range monitoring channels became inoperable in the same trip system.
Administrative controls were established by the licensee to prevent reoccurrence of this event.
The inspector had no further questions and this licensee event report is close RII Rpt.
Nos. 50-259/79-1, 50-260/79-1 and 50-296/79-1 6.
Hi h Densit S ent Fuel Stora e Racks The inspector reviewed documentation concerning the installation of high density spent fuel storage racks to verify that expansion of spent fuel storage capacity is being done in accordance with regulatory requirements contained in 10 CFR, Appendix B, and Amendments Nos.
42, 39 and 16 to Facility Licenses for the Browns Ferry Nuclear Plant, Unit Nos.
1, 2 and 3.
The review included examination of licensee work plans, receipt inspections, quality certifications, shipment check lists, and requests for acceptance of nonconformities.
No items of noncompliance or deviations were identified.
7.
Emer enc Core Coolin S stem Res onse Times Standard Technical Specifications for General Electric Boiling Water Reactors require licensees to verify ECCS response times.
The Browns Ferry Nuclear Plant Technical Specifications do not impose this requirement, although the Browns Ferry Nuclear Plant Final Safety Analysis Report, Sections 6.4.1 and 6.5.3 give time intervals after which the ECCS systems will be capable of performing their intended safety functions.
The licensee is not certain that he can, at present, demonstrate that these time intervals are being routinely verified.
The licensee is investigating the matter.
This matter will remain open item pending receipt of further informa-tion from the licensee (259/79-1-1, 260/79-1-1, and 296/79-1-1).