IR 05000259/1979026
| ML18024B150 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/10/1979 |
| From: | Burnett P, Julian C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18024B149 | List: |
| References | |
| 50-259-79-26, 50-260-79-26, 50-296-79-26, NUDOCS 7911290131 | |
| Download: ML18024B150 (7) | |
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'o UNITEDSTATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 Report Nos. 50-259/79-26, 50-260/79-26 and 50-296/79-26 Licensee:
Tennessee Valley Authority 500A Chestnut Street Chattanooga, Tennessee 37401 Facility Name:
Browns Ferry Nuclear Plant Docket Nos. 50-259, 50-260 and 50-296 License Nos.
DPR-33, DPR-52 and DPR-68 Inspected at Browns Perry Site near Athens, Alabama Inspected by:
l an Approved by.
P.
. Burne
, Acting Section Chief, RONS Branch Date Signed Date Signed Inspected on September 17-20, 1979 Areas Inspected This routine, unannounced inspection involved 34 inspector-hours onsite in the areas of review of the results of post-refueling testing performed on Unit 1 and on Unit 2 and the closeout of various outstanding items from previous inspections.
Results
.Of the 3 areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
+H. L. Abercrombie, Plant Superintendent
+J. L. Harness, Assistant Plant Superintendent
+R.
G. Metke, Results Section Supervisor W.
C. Thomison, Assistant Results Section Supervisor
+R.
G. Cockrell, Reactor Engineer
+R. T. Smith, Quality Assurance Supervisor F. L. Kelley, Nuclear Engineer M. Wingo, Nuclear Engineer S. Hinkle, Nuclear Engineer'ther licensee employees contacted included various technicians, operators, security force members, and office personnel.
Other NRC Personnel-R. F. Sullivan, NRC Resident Inspector D. S. Price, NRC Inspector-Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on September 20, 1979, with those persons indicated in Paragraph 1 above.
The inspector stated that the only problem encountered during review of post-refueling testing records was the incomplete documentation of RTI-5 on unit 1 as described in paragraph
below.
Licensee representatives committed to correct the matter.
The inspector explained the status of the outstanding items from previous inspections detailed in paragraphs 3 and 7 below.
The licensee representa-tives acknowledged these findings.
3.
Licensee Action on Previous Inspection Findings The inspector verified that the corrective action commitments made by the licensee in response to the following previous items of noncompliance are being met.
These items are closed:
i 50-260/78-22-01 (deficiency) - Improper procedure changes 50-260/78-22-02 (deficiency) - Improper IPRM calibration 50-260/79-16-03 (infraction) - Improper shift turnover
L l
The inspector reviewed the following previously-identified unresolved items with licensee representatives.
50-260/79-16-06:
The licensee has been unable to find the Unit 2 process computer alarm typer printout for the hours 1925 through 2400 on 5/26/79.
This item is closed.
50-260/79-16-02:
The licensee is in the process of revising approved control rod withdrawal sequences to minimize reactivity worths of individual rods.
This action is in response to bulletin 79-12 dealing with short period events in BWR reactors.
As a part of this action, the licensee will make changes to the rod withdrawal sequence documents to achieve better administrative control over their use.
This item remains unresolved pending NRC review of these changes at a future inspection.
50-259/79-04-01:
Measures are being taken to reduce the reactivity worths of individual control rods as outlined above.
This item is closed.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Review of the Unit 1 Post Refueling Tests The inspector examined the procedures employed and the results of tests listed.below which were conducted following the refueling of Unit 1 for cycle 3.
BF-MRTI RTI-3 RTI-4 RTI-5 RTI-23A RTI-32A XTI"4 RTI-5 RTI-12 RTI-13 RTI-18
- "Master Refueling Test Instruction"
- "Fuel Ioading"
- Full Core Shutdown Margin" (open vessel)
- "Control Rod Drive System" (open vessel).-
- "Feedwater System, open Vessel
"Recirculation M-G Set Speed Control"
- "Full Core Shutdown Margin" (closed vessel)
- "Control Rod Drive System" (closed vessel)
- "APRM calibration"
- "Process Computer and Core Performance"
- "Core Power Distribution" The portion of RTI-5 performed in the open vessel condition requires the friction testing of each control rod.
Initial review of the records of this test showed that no test result was included for control rod 02-23.
Upon further review the licensee produced a polaroid photograph of an oscilloscope trace to document that control rod 02-23 was friction tested.
A licensee representative explained that just after completion of the friction testing it was recognized that rod 02-23 had been missed.
The rod was then tested but the complete documentation was not filed with the test record.
At the exit interview, the licensee agreed to add the results of the friction test of rod 02-23 to the RTI-5 recor The inspector stated that this item will be reviewed during a future inspec-tion (50-259/79-26-01).
No items of noncompliance or deviations were identified in this area.
6.
Review of the Unit 2 Post Refueling Tests The results of the tests performed on Unit 2 following the'- refueling in preparation for cycle 3 were examined.
Tests conducted were 'the same ones listed in paragraph 5 above.
No items of noncompliance or deviations were found during this review.
The inspector noted that procedure RTI-5 for friction testing control rods had been modified from the previous Unit 1 version.
The revision incorporates preprepared data sheets listing the rods to be tested.
This change was made by the licensee to avoid failing to friction test all rods.
7.
Review of Outstanding Items The inspector observed that the licensee has taken appropriate action in response to the following open items identified in previous inspections.
These items are closed.
50-296/78-36-01
-
Modification to procedure RTI-4 50-259/78-36-02
-
SRM electrica'l interference 50-260/79-16-01
-
Identification of approved rod withdrawal sequences 50-260/79-16-04 50-260/79-16-05 Corrective action to prevent double notching of control rods Corrective action to prevent reactor short period events The inspector discussed with the licensee representatives licensee event report 50-296/793 wherein linear heat generation rate limits were exceeded briefly.
Appropriate action appears to have been taken and this item is close h l
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