IR 05000348/1978024
| ML19294A456 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/23/1978 |
| From: | Kellogg P, Ouzts J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19294A452 | List: |
| References | |
| 50-348-78-24, NUDOCS 7811130229 | |
| Download: ML19294A456 (5) | |
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Report No.:
50-348/78-24
Docket No.:
50-348 License No.: NPF-2 Licensee: Alabama Power Company P. O. Box 2641 Birmingham, Alabama 35291 Facility Name:
Farley Unit No. 1 Inspection at:
Ashford, Alabama Inspection conducted:
September 19-22, 1978 Inspectors:
J. E. Ouzts M. C. Ashenden B. R. Messitt Accompanying Personnel:
P. J. Kellogg g/
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/[ 28 Approved by:
'Date P.l M ogg, Vnief Fsclepr Support Section No. 2 Pr>ctor Operations and Nuclear Support Branch Inspection Summary Inspection on 9/19-22/78:
(Report No. 50-348/78-24)
Areas Inspected:
Routine, unannounced inspection of Surveillance Test Program for unit no. 1.
The inspection involved 63 inspector-hours onsite by three NRC inspectors.
Results:
Within the area inspected no items of noncompliance or deviations were identified.
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RII Rpt. No. 50-348/78-24 I-l DETAILS I Prepared by: (.,
cM, b.f.
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f Ouzts, Rgjrttor Inspector
'Dats Nuclear Support Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspection:
eptember 19-22, 1978
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Reviewed by:
MMT8 s
[8 25 P. J. F/) W g, Cbffl Bate'
Nucleat Support Section No. 2 Reactor Operations and Nuclear Support Branch 1.
Persons Contacted
- W.
G. Hairston, Plant Manager
- D. L. Cox, Operational Quality Assurance-QA Engineer L. W. Enfinger, Document Control Supervisor
- K. W. McCracken, Technical Superintendent
- D. C. Poole, Operations Superintendent J. J. Thomas, I&C Supervisor
- J. D. Woodard, Assistant Plant Manager
- F. Wurster, Operational Quality Assurance-QA Engineer One plant operator and four instrument technicians were also contacted.
- Denotes those attending exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved (78-14-01):
A number of QC inspectors were not recertified within the period as required by Administrative Procedure FNP-0-Ap-31.
Through discussions with licensee management and a review of an updated listing of inspector certifications, the inspector was able to verify that corrective action had been accomplished.
There were no further questions on this item.
3.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance or deivations.
Two unresolved items disclosed during
the inspection are discussed in paragraph.
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RII Rpt. No. 50-348/78-24 I-2
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4.
Exit Inte rview The inspectors met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on September 22, 1978. The inspectors summarized the scope and findings of the inspection as discussed in paragragph 5.
The licensee acknowledged the inspection findings and agreed to take steps to improve data calculations, evaluation and reviews, pending possible additional corrective action in response to an APCo Quality Assurance Audit Report and Consultation with the NSSS Vendor.
5.
Surveillance (Periodic) Test Procedure and Results Verification The inspectors conducted a review of test procedures and results as follows:
Full Length Control Rod Operability Test FNP-1-STP-5.0
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FNP-1-STP-7.0 -
Quadrant Power Tilt Ratio Calculation RCS Leakage Test FNP-1-STP-9.0
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RCP Seal Leakage Test FNP-1-STP-8.0
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FNP-1-STP-12.0 -
Boron Injection Tank Operability Test FNP-1-STP-11.1 -
RHR Pump 1A Inservice Test FNP-1-STP-11.2 -
RHR Pump 1B Inservice Test FNP-1-STP-11.3 -
RER Pump 1A Annual Inservice Test FNP-1-STP-11.4 -
RHR Pump IB Annual Inservice Test FNP-1-STP-11.5 -
RHR Suction Valve Automatic Isolation Test FNP-1-STP-11.6 -
RHR Valves Inservice Test FNP-1-STP-16.1 -
Containment Spray Pump 1A Inservice Test FNP-1-STP-16.2 -
Containment Spray Pump IB Inservice Test FNP-1-STP-16.3 -
Containment Spray Pump 1A Annual Inservice Test
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RII Rpt. No. 50-348/78-24 I-3 FNP-1-STP-16.4 -
Containment Spray Pump 1B Annual Inservice Test FNP-1-STP-28.1 -
Diesel Generator IC Operability Modes 14 FNP-1-STP-29.1 -
Shutdown Margin Calculation TAVG J547 F Ih'P-1-STP-29.2 -
Shutdown Margin Calcul& tion TAVG F547 F FNP-1-STP-37.0 -
Power Distribution Surveillance (Plant Computer Inoperable)
Power Range Neutron Flux Channel Calibration FNP-1-STP-109
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(Heat Balance Only)
The inspectors used one or more of the following acceptance criteria for the above items:
(1) FSAR Section 17.2.10, 17.2.11 (2) ANSI N18.7 (1972) (5.12) (5.1.7)
(3) ANSI N45.2 (1971) (12)
(4) Technical Specifications Tables 4.3.1, 4.3.4 & 4.3.2 (5) ANSI N18.1 (4.3.2)
(6) Quality Assurance Program (7)
Inspector Judgement The Test Procedures & Test Reusults were reviewed to verify:
That test prerequisites and plant conditions were specified
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and reviewed, and approvals had been performed.
That contents of the procedures were correct, and the tests were
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performed on schedule.
That test instruments were listed in the procedures and the
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instruments used were identified in the results.
That test results were recorded and compared with acceptance
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criteria and the return of the equipment to service and the removal of test equipment was verified upon completion of the test.
Within the areas inspected no items of noncompliance or deviations were identified.
However, an overall finding of incomplete technical and supervisory review of surveillance test procedures, as evidenced by numerous errors in data recording and calculation, was communicated to the licensee.
The licensee has acknowledged this finding and has agreed to upgrade his Administrative Review Procedure '
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RII Rpt. No. 50-348/78-24 I-4 This item will remain unresolved pending future reviews of test results by NRC and a site review and response to a forthcoming APCo QA Audit report covering the area of surveillance testing (348/78-24-01).
In another area the inspectors noted that the licensee was not taking prompt action to reduce thermal power when his daily calorimetric (FNP-1-STP-109) showed him to be in excess of his licensed power level.
This item will remain unresolved pending licensee's consulation with the NSSS Vendor and further discussions with NRC (348/78-24-02).
The inspectors witnessed the below listed test procedures.
FNP-1-STP-256.7 - Steam Line Pressure Response Time Test.
FNP-1-STP-4.1.1 - Source Ranege Functional Check, Channel 32.
FNP-1-STP-256-11 - Reactor Trip and ESFS Logic Response Time.
The inspectors used one or more of the following acceptance criteria for the above items:
(1) FSAR Section 17.2.10 - 17.2.11 (2) ANSI N 18.7 (1972 (5.1.2) (5.1.7)
(3) ANSI N 45.2 (1971) (12)
(4) Technical Specification - Tables 4.3.1, 4.3.4 *
J.2 (5) ANSI N 18.1 (4.3.2)
(6) Quality Assurance Program (7)
Inspector Judgement The test procedures Witnessed Verified:
That test prerequisites and plant conditions were specified and reviewed.
That contents of the procedures were correct, and the tests were performed on schedule.
That the test instruments were listed in the procedures and the instruments used were identified in the results.
That test results were recorded and compared with acceptance criteria and the return of the equipment to service and removal of test equipment was verified upon completion of the test.
Within the areas where tests were witnessed no items of noncompliance or deviations were identified.
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