IR 05000348/1980019
| ML19344E752 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/28/1980 |
| From: | Bradford W, Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19344E727 | List: |
| References | |
| 50-348-80-19, 50-364-80-23, NUDOCS 8009110202 | |
| Download: ML19344E752 (7) | |
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UNITED STATES e
NUCLEAR REGULATORY COMMISSION n
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REGION 11
e, 101 MARIETTA ST N.W., SUITE 3100 g
o ATLANTA, G EORGIA 30303
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Report Nos.
50-348 and 50-364/80-23
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Licensee: Alabama Power Company 600 North 18th Street Birmingham, AL 35202 Facility Name: Farley License Nos. NPF-2 and CPPR-86 Inspection at Farle site near Dothan, Alabama 7!2 Inspector:
po W. H.'Bradfor Date' Sign 6d Approved by.
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R. D. Martin Dat6 Sigtfed SUMMARY Inspection on June 2 - June 30, 1980 Areas Inspected This routine in'spection involved 96 inspector-hours on site in the areas of Unit No. 2 Integrated Leak Rate Test, TMI Lessons Learned catagory "A" Open Items, IE Bulletins, Unit No. 1 Plant Operations, Unit No. 2 Plant Status.
Results Of the areas inspected, no items of noncompliance or deviations were found.
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DETAILS 1.
Persons Contacted Licensee Employees
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W. G. Hairston, Plant Manager J. D. Woodard, Assistant Plant Manager W. D. Shipman, Maintenance Superin-tendent D. Mcrey, Operations Superintendent R. S. Hill, Operations Supervisor ~
R. W. McCracken, Technical Superintendent D. E. Mansfield, Startup Superintendent, Unit No 2 R. M. Coleman, Supervising Engineer H. M. McClelland, Plant Engineer
H. Garland, Maintenance Supervisor Charles Nesbitt, C & HP Supervisor Other licensee employees contacted included Shift Supervisors, Shift Formen, technicians, plant operators, security force members, and office personnel.
Other Organizations
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S. M. Hall, Westinghouse Startup Services Manager and certain Westinghouse startup engineers.
2.
Exit Interview The inspection scope and findings were summarized during managemen interviews on June 17 and 27, 1980, with the plant manager and selected members of his staff. The' licensee acknowledged the inspection findings.
3.
Licensee Action on Previous Inspection Findings.
Not inspected.
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4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Witness of Unit No. 2 Contairment Integrated Leak Rate Testing The inspector witnessed pcction of the Unit No. 2 containment integrated leak rate testing as controlled by test procedure No. 059-5-003, "Contain-ment Integrated Leak Rate Test." The inspector verified the following:
a.
That instrumentation used for the test had been calibrated and the calibration dates were current
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b.
That test prerequisites and initial condition for the test had been met.
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-2-a That the appropriate approved test procedure was used throughout the c.
test.
d.
That personnel conducting the test were knowledgeable of the test and were qualified to conduct the test and were able to interpret the test data.
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e.
That the test data was collected and documented.
Within the areas inspected no items of noncompliance or deviations were identified.
6.
T. M. I. Lessons Learned Catagory "A" Items The inspector reviewed the licensee's response to certain items of the above subject. These items are as follows.
a.
Integrity of systems outside containment: The inspector verified that a leak reduction program implemented by FNP-1-ETP-168. "Farley Nuclear Plant Leak Reduction Program" and been implemented. The procedure and a portion of the completed data was reviewed by the inspector and
discussed with a licensee representative. The inspector had no adverse comments.
b.
Design Review of Plant Shielding and Environment Qualifications. The inspector verified that a review of radiation environmental qualifica-tion of equipment had been completed and had been submitted to the NRC.
Improved Post-Accident Sampling Capability.
c.
The inspector reviewed the post accident sampling system and verified that modificaticas to the system and been accomplished. FNP-0-RCP-25
" Chemistry and Health Physics Activities during a Radiological Accident (Short Term) was reviewed and discussed with the licesnee's representa-tive. The inspector had no adverse comments on this procedure.
d.
Increased Range of Radiation Monitors The inspector verified that the equipment for monitoring a high-level release had been installed on the vent stack and was available for use at the other release points. This area is covered in FNP-0-RCP-25
" Chemistry and Health Physics Activities During a Radiological Accident (Short Term). The inspector had no further questions.
e.
Improved In-Plant Iodine Instrumentation The inspector verified that portable air monitoring systems withf single channel analyzers and silver ziolite cartridges were available.
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The inspector verified that the specific dutiesof the STA were delineated in the appropriate administrative procedure.
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Control Room Access
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The inspector verified that the shift supervisor authority to limit access to the control room and that the line of authority under emergency conditions has been established under emergency conditions.
7.
Open Items Open Item (79-26-01)
(Closed) This open item concerned the seismic qualification for the skid mounted diesel generators. The licensee has received documentation from the Colt Industries Operating Corporation Fairbanks Morse Engine Division, dated September 10, 1979 which certifies that the skid mounted diesel generators are seismically qualified.
The inspector and reviewed this documentation and has no further questions.
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Open Item-(364/79-11-04)
(Closed) This open item addressed the inclusion of pump head calculations into the component cooling water Preoperational Test Procedure The inspector verified that pump head
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calculations were included in the test procedure. The inspector has no further questions.
Open Item (364/79-11-02)
(Closed) This open item addressed the inclusion of pump head calculations for the boron injection pumps into the " Boron Injection System Preoperational Test Procedure." The inspector verified that pump head calculations were included in the test procedure. The inspector had no further questions.
Open Item (364/79-11-03)
(C1soed) This open item concerned verification of flow data' by startup personnel in the " Containment Cooling Preoperational Test." The inspector verified that flow data is noted and verified by startup personnel in the test procedure. The inspector had no further questions.
Open Item (364/79-11-04)
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(Closed) This item concerns the rating of the refueling water surface *
supply fan not being in accordance with the rating listed in the FSAR Table 6.2-16.
The licensee has established that the rating listed in the FSAR is erronous. The license has submitted a change to the FSAR to correct this inconsistanc The inspector has no further questions.
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-4-s Open Item (364/79-11-05)
(Closed) This item concerns verification of flow data by startup personnel in the " Containment Dome Recirculation" preoperational test procedure. The inspector verified that flow data is noted and verified by startup personnel in the test procedure.
The inspector had no further questions.
Open Item (364/79-11-06)
-(Closed) This item concerned the inclusion of pump head calculations for the Auxiliary Feed Water pump (motor driven) into the " Auxiliary Feed Water preoperational Test procedure.
The inspector verified that pump head calculations were included in the test procedure.
Open 7 tem (364/79-11-07)
(Closed) This item addressed the operational check of the service water emergency supply valve to the suction of the r.uriliary feed water pumps.
The inspector verified that these valves are fum 'ionally checked cut in another procedure. The inspector had no further quez. ions.
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Open Item (364/79-11-08)
(Closed) This item concerned the inclusion of pump head calculations for the Turbine Driven Auxiliary Feedwater Pump into the preoperational test procedure for the subject pump.
The inspector verified that pump head calculations were included in the preoperational test procedure.
The inspector ah had no further questions.
8.
IE Bulletins IE Bulletin 79-13 " Cracking in Feedwater System Piping" The subject a.
Bulletin is closed based on the review of the licensee responses to the NRC dated July 16, 1979, July 26, 1979 and August 27, 1979 as well as inspections performed by Region II documented in Report Nos. 50-348/
79-24 and 50-348/79-27.
b.
IE Bulletin 79-15, " Deep Draft Pump Deficiences."
The subject bulletin is closed based on the inspectors review of the licensee's supplemental response to the NRC dated February 26, 1980 i
which delincates the action taken and/or planned to improve performance and reliability of the river water and service water pumps.
The inspector had no further questions.
IE Bulletin 79-17 " Pipe Cracks on Stagnant Borated Water Systems"
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c.
The subject Bulletin is closed based on the review of the licensee response dated February 27, 1980 as well as inspections performed by Region II documented in Report Nos. 50-348/79-46 and 50-348/80-01.
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IE Bulletin 80-05, " Vacuum Condition Resulting In Damage to Chemical Volume Control System Holdup Tanks."
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The inspector reviewed the licensee response dated June 4,1980 concerning-the Volume Control Tank, Recycle Holdup Tanks, Liquid Waste Processing Tanks, Refueling Water Storage Tank and the Concentrated Waste Storage
Tank.
Based on the inspectors review of the tanks in question, this Bulletin is considered to be closed.
IE Bulletin 80-09,."Hydramotor Actuator Deficiencies."
e.
The inspector reviewed the licensee response dated June 16, 1980. The licensee has determined that no ITT General Controls models AH-90 or NH-90 Hydramotor Actuators have been or will be used.
9.
Unit No.1 Plant Operation The inspector reviewed Unit 1 operation to ascertain whether it was in conformance with refulatory requirements, technical specifications and Administrative Procedure No. 16, " Conduct of Operations Group".
Station
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logs such as the shift supervisor, shift foreman, control room operator,
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plant operator, shift turnover, the out of service equipment, night orders, and the limited condition of operation logs were reviewed. The inspector conducted tours of selected areas of the Unit 1 portion of the plant which included portions of the auxiliary building, diesel generator building and the turbine building. Observations were made of plant operation, monitoring instrumentation, radiation controls, fluid leaks, piping vibration, pipe hangers, the position of certain valves, housekeeping, fire hazards and equipment, tagged out of service for maintenance. Discussions were held with operators throughout the plant concerning their response to certain alarms and their function during plant operations. The inspector witnessed portions of selected surveillance tests performed through out the reporting period.
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The unit was removed from service on June 14, 1980 to plug a leaking tube in the "B" steam generator. A total of 48 tubes in the first row and 3 in the second row were successfully eddy current tested. In addition to the known leaking steam generator tube, the testing identified two other tubes which showed abnormal indications were also plugged.
Within the areas inspected no items of noncompliance or deviation were identified.
10.
Unit No. 2 Plant Status i
The status of the licensee's Phase II Preoperational Testing program was reviewed. As of June 30, 1980 construction was estimated to be 94% completed ',
with 363 out of 444 systems or subsystems turned over to Startup for Testing.
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The preoperational testing' program is summarized as follows:
l Testing completed 33%
Testing in Progress 16%,
Testing not Started
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39% '
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Test Data Approved by the licensee 12%
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