IR 05000348/1979029
| ML19250A316 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/06/1979 |
| From: | Bradford W, Hardin A, Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19250A313 | List: |
| References | |
| 50-348-79-29, NUDOCS 7910230042 | |
| Download: ML19250A316 (4) | |
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'c, UNITED STATES
NUCLEAR REGULATORY COMMISSION
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SEP 7 1979 Report No. 50-348/79-29 Licensee: Alabama Power Company 600 North 18th Street Birmingham, Alabama 35292 Facility Name Farley Unit 1 Docket No. 50-348 License No. NPF-2 Inspection at Farley Site near Dothan, Alabama Inspectors:
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A. K. Hirdin
'Date Signed
il Y.$u c LLid 9l6l70 W. H. Bradford
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Dato Signed Approved by:
4(4 i//, /? 9 R. D. Martin, Section Chief, RONS Branch Date Signed
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SUMMARY Inspection on August 20-23, 1979 Areas Inspected This routine, unannouuced inspection involved 50 inspector-hours onsite in the areas of operations review, open and unr2 solved items, licensee event reports, and IE circulars.
Results Of the four areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- W. G. Hairston, Plant Manager
- D. C. Poole, Operations Superintendent
- K. W. McCracken, Technical Superintendent
- R. D. Hill, Plant QA Engineer
- J. W. Kale, Jr., QA Engineer Other licensee employees contacted included technicians, operators and office personnel.
- Attended exit interview.
2.
Exit Interview
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The inspection scope and findings were summarized on August 23, 1979 with those persons indicated in Paragraph 1 above.
The inspector discussed the items inspected which were considered closed and those items for which questions remained to be resolved. The licensee raised no objections to the findings.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Open Items (Closed) Open Item (348/78-11-02): This open item concerned the a.
forcing of reactor average coolant temperature above limits due to a turbine load rejection. The event occurred during a change from single to sequential valve control when the controls malfunctioned to cause a 170 MWe load rejection. The corrective actions taken by the licensee were reported in a supplemental report to LER No. 78-24. The inspector reviewed the corrective actions and at the exit interview stated there were no further questions at this time.
b.
(Closed) Open Item (348/78-29-03): This item was opened to track the repair of cylinder head temperature measuring devices on the emergency diesels. On the current inspection the inspector verified that cylin-der head temperatures were being read on emergency diesels.1B,1-2A, 1C and 2C.
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(Closed) Open Item (348/79-02-02): Several river water pump failures c.
had occurred apparently due to inadequate cooling water to the bear-ings. The licensee has completed installation of stainless steel lube water cooling piping.
In addition the licensee has installed a
"Sullectron" an electronic water treater designed to prevent buildup of scale on lube water supply piping. The licensee believes these actions will provide adequate lube water supply to the pump bearings.
The inspector stated there were no further question::.
d.
(Closed) Open Item (348/79-02-01): Several failures of containment atmosphere monitors R-11 and R-12 have occurred over the past year.
This open item dealt with the shock mounting of relays associated with R-11 and R-12 to prevent vibration induced failures. On the current inspection the licensee stated Plant Change Notice 79-326 had been issued and would be implemented during the week of August 27, 1979.
At the exit interview the inspector stated there were no further questions.
(Closed) Open Item (348/79-08-01):
This item dealt with review of e.
test data following revision to Diesel Generator 2C and 1-2A control circuits. The review was completed and reported in IE Reports 50-348/79-15 and 79-28.
f.
(Closed) Open Item (348/79-PC-01): This open item was related to slow pickup values for certain types of GE Induction Disc Relays caused by petroleum jelly lubricant used in the relays.
The inspector reviewed at the site actions taken and planned to correct the slow pickup problem. Tne actions consist of removing, cleaning, recalibrating and reinstalling potentially slow relays. A maintenance procedure which calls for periodic inspection of all affected GE induction disc type protective relays was committed too.
6.
IE Circular 79-09 The subject circular dealt with the occurrences of split or punctured diaphagms in certain selfcontained breathing appart.tus. The licensee stated they had reviewed their breathing apparatus and neither the Scot Air Paks II/ IIA nor Presur-Pak II/ IIA, the apparatus in question, are used at Farley.
7.
Plant Operations The inspector reviewed plant operations to ascertain conformance with regulatory requirements, technical specification and administrative proce-dures.
Station logs, such as the supervisor's logs, control room operat-or's logs, the shift turnover logs, and the out of service equipment log were reviewed.
In addition, a tour was conducted of selected areas of the plant including portions of the auxiliary building, service building, river water intake structure and service water intake structure. Obseivations were made of monitoring instrumentation, radiation controls, fluid leaks, piping vibrations, pipe hangers, valve positions and housekeeping.
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Within the areas inspected no items of noncompliance or deviations were identified.
8.
Review of Nonroutine Events Reported by 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.
Licenste action with respect to selected reports was reviewed to verify that the events were reviewed and evaluated by the licensee as required by the Technical Specification that corrective action was taken by the licensee, and that safety limits, limiting safety system settings, and limiting conditions for operation were not exceeded.
The inspector examined selected Plant Nuclear Safety Committee minutes, incident reports, logs and records, and interviewed selected personnel.
R0-79-20, Diesel Generator 1-C Inoperable R0-79-22, Shutdown Margin Calculation
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R0-79-25, Source Range Channels Deenergized R0-79-27, Fuel Storage Pool Area Radiation Monitor R-25A Inoperable R0-79-28, Fuel Storage Pool Radiation Monitor R-3 Inoperable R0-79-29, Failure of Penetration Room Fans R0-79-31, Loss of Source Range N-31 and N-32 Due to Blown Fuses i197'/0
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