IR 05000364/1980022
| ML19339B019 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/05/1980 |
| From: | Kellogg P, Wagner A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19339B014 | List: |
| References | |
| 50-364-80-22, NUDOCS 8011060168 | |
| Download: ML19339B019 (4) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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o 101 MARIETTA ST., N.W., SUITE 3100
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o ATLANTA, GEORGIA 30303
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Report No. 50-364/80-22 Licensee: Alabama Power Company 600 North 18th Street Birmingham, AL 35202
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Facility Name: Farley Unit 2
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Docket No. 50-364
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Licensee No. CPPR-86 Inspection at: Farle S'te near Dothan, Alabama Inspector:
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A.G.Waga.,,o.,
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Dath Si ed
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Approved by:
Q 6d nj P. J. p110t% f$ection #YieL RONS Branch Da(e/Sigrfed
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SUMMARY Inspection on July 8-17, 1980 Areas I.spected This routine insp ction involved 72 inspector hours on site in the area of preoperational test program results review.
Results Of the one stea inspected, one apparent item of noncompliance was identified (Deficiency: Failure to follow procedure paragraph 5.b.1; and Failure to prop-erly record data paragraph 5.b.2).
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DETAILS 1.
Persons Contacted
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- D. E. Mansfield, Startup Supervisor
- J. D. Woodard, Assistant Plant Manager
- K S. Buss, Assistant Startup Supervisor
- J. E. Dorsett, Management Staff
- J. W. Kale Jr., Quality Assurance Supervisor C. Cogbill, Startup Engineer S. M. Hall, Startup Engineer l
NRC Resident Inspectors W. H. Bradford J. P. Mulkey
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- Attended exit interview.
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2.
Exit Interview l
The inspection scope and findings were summarized on July 17, 1980 with those persons indicated above. The licensee commented that a noncomplian ?
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for item discussed in paragraph 5.b.1 beiuw was too severe.
It was felt i
that the intent of the procedure was met by the individual performing the
test.
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Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncorapliance or deviations.
An unresolved item disclosed during the inspection is
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discussed in paragraph 5.b.2. (a).
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5.
Preoperational Test Results Review The following Test Procedures were reviewed for compliance with Startup Standard 6, 18, Regulatory Guide 1.68, Operational Quality Assurance Policy Manual Chapter 11 and Final Safety Analysis Report Ch. 14.
No comments were noted with the following approved procedures l
a.
(1)
100-5-010 Unit 1/ Unit 2 Shared and Unit 1 Modified Emergency Power Distribution Pre 0p, Approved 5-28-80.
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(2) 064-5-012 Pressurizer Spray Line Miniflow Preoperational Test (Initial Setting during Hot Functional testing), approved 7-3-80.
(3)
100-5-005 Hot Functional Dynamic Test Procedure, approved 7-3-80.
(4)
100-5-007 Steam Generator Feedwater Hammer Test Procedure, approved 7-3-80.
b.
Inspector findings were noted for the following approved procedures.
(1) 064-5-017 RCS Leak Rate Preoperational Test, Approved 7-3-80.
Test Step 8.1 required the completion of a system inspection and correction of leakage prior to commencing the leak test.
The step was not dated until after the start of the official leak test in step 8.2.
This is an item of noncompliance, deficiency failure to follow procedure (364/80-22-01)
(2) 064-5-015 RTD/Thermonronple Cross Calibration Preop, approved 7-3-80.
(a) Supporting data sheets for steps 8.15, 8.31, 8.35 and 8.5 do not indicate that the values for the decade box test device setting were adjusted as required in the test steps. This item is unresolved pending procedural clarification of the step requirements (364/80-22-02).
(b) Corrections to data recorded in data sheets 3, 6, 7, 8, 12, 13, 14, and 15 were not made as required by Startup Standard 6 paragraph 5.6.6.
This is an item of noncomp1'ance, deficiency, failure to properly record data (364/80-22-01).
(c) Comments on the following completed, unreviewed procedures were provided to a senior licensee representative, who stated that appropriate corrective action will be taken prior to final approval. This will be an inspector followup item (364/80-22-03).
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083-5-003 Steam Dump System
063-5-005 Steam Generator Blowdown System
040-5-021 Solid System Pressure Control
040-5-017 RCP Seal Injection and Charging
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060-5-010 Containment Ventilation (Hot) System
0'6-5-005 Turbine Driven Aux. Feedwater System
064-5-011 RTD Bypass Loop Flow l
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040-5-015 CVCS Letdown I
052-5-G11 Safety Injection (Not) System
034-5-004 Pressurizer Hot Pressure and Level
]]I 064-6-016 Hot Functional Outline
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6.
Plant Tour The inspector toured portions of Unit 2 containment building and auxiliary building. The following observations were made.
An area around a radiation detection instrument was posted as a contami-a.
nated arca and had a lunch box in the area. Health Physics personnel surveyed the area and found no contamination. It was determined that the radiation posting was inadvertantly turned over displaying the erroneous sign.
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b.
A sheet of steel approximately 10 inches x 4 inches x 1 inch fell approximately three levels in the area of the Charging Pump Hot Leg Recirculation piping. An inspection of the area was made by Quality Assurance inspectors. No damage to plant systems were noted.
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