IR 05000348/1979018
| ML19246B825 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/09/1979 |
| From: | Cantre F, Cantrell F, Hardin A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19246B805 | List: |
| References | |
| 50-348-79-18, NUDOCS 7907180658 | |
| Download: ML19246B825 (5) | |
Text
.
UNITED STATES k" 'f Gug NUOLEAR REGULATORY COMMISSION t
p
,
,#,
f, yVp(e (/[,g REGION ll
' 'J/.. r 101 M ARIETT A ST REET. N.W.
.
,
ATLANTA, GEORGIA 30303
,g f
o
- es,*
.
Report No. 50-348/79-18 Licensee: Alabama Power Company 600 North 18th Street Birmingham, Alabata 35202 Facility Name: Farley Unit 1 Docket No.
50-348 License No.
NPF-2 Inspection at Farley Site ear Dothan, Alabama
[/ou
-
j f
Inspector:_
g w
D'.te Signed A. K. liardin '
,
.I!9
,3 Approved by:
n-F. S. Cantrell, Acting Section Chief, RONS Branch Date Signed
/ e SUMM.GY Inspection on April 24-27, 1979
.
Areas Inspected This routine, unannounced inspection involved 27 inspector-hours onsite in the areas of licensee event reports, IE bulletins and circulars, followup on allegations, independent inspection and plant operations.
Results Of the five areas inspected, no apparent items of noncompliance or deviations were identified in five areas.
344 203 7 0 0718 065g-i
.
.
DETAILS 1.
Persons Contacted Licensee Employees
- J. D. Woodard, Assistant Plant Manager
- D. C. Poole, Operations Superintendent
- E. W. McCracken, Technical Superintendent
- J. J. Thomas, Supervisor I and C
- R. D. Hill, Plast QA Engineer
- F. A. Wurster, Operations QA
- I. W. Kale, Operations QA Other licensee employees contacted included techn.cians, rperators, and mechanics.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on April 27, 1979, with those persons indicated in Paragraph I above. Those licensee event reports which require further input iy the licensee were designated by the inspector. The status cf IE bulletins and circulars were discussed.
The inspector stated that two conditions of the license, i.e., replacement of certa:a transmitters and installation of an overpressure mitigative system (OMS) appeared to be met provided completion of testing verifies the acceptance criteria for the OMS. The inspector also stated that an allegation that the emergency escape hatch was partially 2 ' acked appeared to be correct for Unit 2.
There were no adverse comments on the findings by the licensee.
3.
Licensee Action on Previous Inspection F1., ding; Not inspected.
4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involv. noncommplian:e or deviations.
New unresolved, items identified during this inspection are discussed in paragraph 5.
k 1544.10
_
.
-2-
.
5.
Containment Emergency Escape Hatches
-
An inspection of the emergency escape hatches for both Units 1 and 2 was conducted to dete rmine whether entrances or exits to the locks were obstructed. The inspector judged the entrance and exit to the emergency lock on Unit 1 to be adequately free from installed abstructions. The inspector judged the entrance to the emergency lock in Unit 2 to be unduly obstructed by installed structural supports and a containment heat exchanger. The exit of Unit 2 emergency lock is similar to Unit 1 and is considered adequate.
There is not a quantitative ocasure of the degree of effort required to gain entrance to the Uait 2 emergency escape hatch. However, quelite-tively an employee would t be very mobile and agile to climb through the pipe supports or squeeze past installed equipment to gain access to the entrance to the hatch.
These findings and conclusions were stated at the exit interview. The licensee made note of the conclusions. On a subsequent telephone call to the licensee, the inspector stated he was planning to list the item as unresolved pending a review by the licensee of the adequacy of access to the escape hatch (348/79-18-01).
6.
Review of Nonroutine Events Reported ly 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.
Licensee action with respect to select reports was reviewed to verify that the events were reviewed and evaluated by the licensee as required by Technical Specifications, that corrective action was taken by the licensee, and that safety limits, limiting safety system settings, and limiting conditions for operations were not exceeded.
The inspector examined selected Plant Nuclear Safety Committee minutes, incident reports, logs, and records, and inspected equipment and interviewed selected personnel. The inspector had no further questions except as identified below, LER No. 79-7, Delay in Performing RCS Leakage Surveillance Test.
a.
b.
LER No. 79-8, Failure of Main and Emergency Air Lock Outer Doors to Meet Surveillance Test Requirements.
c.
LER No. 79-9, T average Dropped 3 F Below TS Limit Due to Steam Dumps.
g}g(3
..
.
,
.
I-3-
,
d.
LER No. 79-10, Steam Flow / Feed Flow Bistable (FB 478A) Set Point Drift.
e.
LER No. 79-11, Loss of Offsite Power BIF Sequence Step 6 Set Point Drift.
f.
LER No. 79-12, Inoperable Containment Spray Relay Test Circuitry.
g.
LER No. 79-13, Faulty Switch Mechanism in B1F Sequence Made DG-1-2A Inoperable.
h.
LER No. 79-14, Error in Cable Termination Caused DG2C to Fail to Close on the Bus.
In addition to the corrective actions described in the LER, the licensee has issued a memorandum to the Startup Manager providing for tighter control of construction work which involves Unit 1, and Unit 2 interface.
i.
LER No. 79-15, Linear Surface Indications on 2" ECCS Line to Loop 1 Cold Leg.
The licensee stated in the written LER that they would either cut out and replace the piping or they would grind out the subject indications.
A supplemental report was committed to on completion of corrective action. On the current inspection, the licensee stated they intended to cut out and replace the af fected piping.
The LER will remain open pending further IE review of the corrective action (348/79-18-02).
j.
LER No. 79-16, Loss of Off Site Power B1F Sequencer Step 6 Setpoint Drift.
k.
LER No. 79-17, Potential Single Drop Rod Safety Analyses - Non Cons e rva tive.
At the exit interview the inspector stated the licensee must establish a sctisfactory resolution of this problem prior to startup f rom the current refueling outag;. The licensee indicated they understood the need to resolve this problem.
This event remains open pending review of the licensee's solution (348/79-18-03).
7.
Overpressure Mitigating System
,
Section 2.C.(3).(b). of Operating License NPF-2 for Farley Unit I requires that a long term means of protection against reactor coolant system overpressurization be installed prior to startup from the first regularly scheduled refueling outage.
}kk
.
e
.
s
-4-
On this inspection the design changes which were written for installation of the system, the operating logic and the proposed Technical Specifica-tions were reviewed.
Questions raised by the inspector were answered satisfactorily. At the conclusion of the inspection, verification of the system in accordance with the licensee procedure FNP-1-ETP-111 had not been completed. The licensee stated at the exit interview that upon successful completion of the test, the test data would be provided to the inspector for review (348/79-18-04).
8.
Stem Mounted Limit Switches Reference IE Bulletin 78-04 and Outstanding Ite No. 348/78-17-01. IEB 78-04 required that the licensee determine if environmentally unqualified stem mounted limit switches were installed in Farley Unit 1.
Subsequently, the licensee found 46 of the stem mounted limited switches used in systems at Farley were not environmentally qualified.
Outstanding Item No. 348/78-17-01 was established to follow the replace-ment of the existing switches. On the current inspection, the inspector reviewed in containment the installation of about 75 percent of the new environmentally qualified switches.
All of the stem mounted limit switches requiring replacement have been replaced.
Outstanding Item 348/78-17-01 is closed.
9.
Modified Instrumentation Section 2.c.(3).(e) of Operating License NPF-2 for Farley Unit I requires that certain instrumentation associated with the pressurizer, steam gener-ator and reactor coolant system be replaced. On the current inspection, replacement of 17 transmitters was verified.
The calibration of the instruments were reviewed. The licensee has met the condition of license as specified.
'}kk
-