IR 05000348/1979032
| ML19262A589 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/19/1979 |
| From: | Bradford W, Hardin A, Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19262A586 | List: |
| References | |
| 50-348-79-32, 50-364-79-14, NUDOCS 7912070097 | |
| Download: ML19262A589 (4) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION II
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ATLANTA, GEORGIA 303o3
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Report Nos. 50-348/79-32 and 50-364/79-14 Licensee: Alabama Power Company 600 North 18th Street Birmingham, Alabama 35202 Facility Name: Farley Units 1 and 2 License Nos. NPF-2 and CPPR-86 Inspection at: Farley ite Inspectors:E[
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Date Signed
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/ D//9/79 W. H. Ihadford Date Signed
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Accompanying Per nel:
R. D. Martin (September 27, 1979)
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Approved by:,
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J R! D. t}5rtin, Bection (nief, RONS Branch Date S'igned Dates
.f Inspection: September 25-28, 1979 Areas Inspected This routine unannounced inspection involved 60 inspector-hours onsite in the areas of Operations Review, Licensee Event Reports, open items, IE Circulars and manage-ment meeting on Unit 2.
Results Of the five areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- J. D. Woodard, Assistant Plant Manager
- J. W. Kale, Jr., QA Engineer
- R. D. Hill, Plant QA Engineer
- R. Yance, Plant Engineer
- H. O. Thrash, Manager, Nuclear Generation
- 0. D. Kingsley, Assistant Manager, Nuclear Generation
- J. A. Mooney, Project Manager Construction
- W. G. Hairston, Plant Manager
- D. E. Mansfield, Startup Superintendent
- J. R. Campbell, Manager, Operation QA Other licensee employees contaced included technicians, Operr. tors, and security force members.
- Attended exit interview
- Attended Unit 2 Management Meeting 2.
Exit Interview The inspection scope and findings were summarized on September 28, 1979 with those persons indicated in Paragraph 1 above by a single asterick.
The management meeting related to Unit 2 was attended by those designated with a double asterisk.
The inspectors discussed the items inspected. No objections to the findings were raised by the licensee.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Management MeetingUnit -2 A meeting was held with corporate level and site managers to discuss the construction status of Unit 2. and the NRC's inspection program relative to test and startup of a new facility.
The inspectors discussed the IE program for selective review of procedures, test results, and operating instructions and the overall inspection pro 8 ram as it applies to a reactor in the test and startup stage.
The Ticensee presented a summary of their program and their estimate of the percent complete on construction. The licensee concludes that for Unit 2, 1522 281
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-2-F they are 82% complete on the auxiliary building, 80% on the turbine building, and 84% on containment.
The primary loop is 94% complete.
6.
IE Circulars No. 79-13 The subject circular referred to failure of starting contactors on a diesel fire pump. The inspector verified the licensee had reviewed the circular and cad determined that the two diesel fire pump engines at Farley were not susceptable to the problem described in the circular.
This circular is closed.
7.
Open Items (Closed) Open Item (348/79-12-01) This item was opened to track the a.
licensee's proposed Technical Specification change to revise the Reactor Coolant Pump (RCP) breaker trip circuit.
On the current inspection the licensee stated they had decided not to pursue a Technical Specification change but believe they have solved the problem of reactor trip on a single inverter failure which was being caused by the RCP breaker open trip circuits on the inverters. The licensee has placed the power for the RCP breaker open trip circuit onto a Class IE Sola power source. Thus failure of an inverter will not deenergize the RCP breaker open trip circuit.
b.
(Closed) Open Item (348/79-12-02) A failure of the Unit 1 R-11 and R-12, containment gas and particulate monitoring instruments, was originally believed to have been caused by varying thickness or overly thick filter paper. On the current inspection the licensee stated their review led them to conclude the paper was not at fault and that a general wear problem appeared to to be the likely explanation for the failure. The licensee stated they were continuing to look at general improvements to insure fewer failures of R-11 or R-12 instruments.
(Closed) Open Item (348/79-12-03) During a test of emergency core c.
cooling valves, the Boron Injection Tank (BIT) became diluted because of a leaking isolation valve. The licensee committed to revise Surveillance Test Procedure (STP) 10.3 to require additional isolation of the BIT during ECCS Testing. On this current inspection the inspec-tor verified that STP 10.3 had been revised.
d.
(Closed) Open Item (348-79-23-01) This open item dealt with a followup review of the licensee's administrative procedures for verifying valve alignments. The inspector concluded, following review of AP-16, AP-52 and Operations Memorandum No. 79-16 issued September 20, September 25, and August 9 respectively that valve alignment verification procedures are now adequate.
(Closed) Open Item (348/79-23-02) In IE Report 79-23 the licensee e.
stated they were working on methods to keep lockout, hold, caution or 1522 282
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-3-similar tags from obscuring process information. On the current outage the inspector observed warning tags of a size and design which precludes the tag hiding other panel information.
8.
Review of Nonroutine Events Reported by the Licensee The following licensee event reports were reviewed in office for potential-generic problem 3, 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 selected reports was reviewed to verify that the events were reviewed and a C.iated by the licensee as required by the Technical Specification, that corrective action was taken by the licensee, and that safety limits, limiting safety settings, and limiting conditions of operation were not exceeded. The inspector examined selected Plant Nuclear Safety Committec.ninutes, incident reports, logs and records, and interviewed selected personnel.
R0-79-23 Insulation of Steam (Gen. Level Transmitter Reference Legs)
R0-79-24 Inadequate Surveillance Test Procedure R0-79-33 Inoperable Fuel Storage Area Radiation Monitor R0-79-34 Surveillance Test Not Performed During Required Time Interval-R0-79-35 Replacement of Certain 7300 Process 2&C Printed Circuit Cards 9.
Plant Operations The inspector reviewed plant operaticas to ascertain conformance with regulatory requirements, technical specifications and administrative procedures.
Station logs, such as supervisor's logs, control room operator's logs, de 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. Observations were made of monitoring instrument, radiation ccatrols, fluid leaks, piping vibration, pipe hangers, valve positions and housekeeping. Within the areas inspected no items of noncompliance or deviation were identified.
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