IR 05000335/1979011
| ML17206A912 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 05/24/1979 |
| From: | Cantrell F, Webster E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17206A911 | List: |
| References | |
| 50-335-79-11, NUDOCS 7907250147 | |
| Download: ML17206A912 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGtON It 101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 Report No. 50-335/79-11 Licensee:
Florida Power and Light Company 9250 Vest Flagler Street Miami, Florida 33101 Facility Name: St. Lucie Unit 1 Docket No. 50-335 License No. DPR-67 Inspection at
. L ie Plant near Fort Pierce, Florida Inspecto
ebste Approved by:
. S. Cantrell, Ac i
,
Section Chief, RONS Date Signed ate ig d
Inspection on April 17-20, 1979 Areas Inspected This routine, unannounced inspection involved 35 inspector-hours onsite in the areas of plant procedures, refueling outage maintenance, refueling outage opera-tions, licensee event reports, IE Bulletins, Circulars and Notices, previously identified inspector items, and presentations concerning the Three Mile Island incident.
Results Of the seven areas inspected, no apparent items of noncompliance or deviations were identifie ~
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DETAILS Persons Contacted Licensee Employees
- C. M. Wethy, Plant Manager
- J. E. Bowers, Maintenance Superintendent
- C. A. Wells, Operations Supervisor
+A. W. Bailey, Quality Assurance Supervisor
- G. M. Vaux, Quality Control Supervisor
+R. R. Jennings, TechnicalStaff Supervisor T. A. Dillard, Jr., Mechanical Maintenance Supervisor
+N. D. West, Outage Coordinator Other licensee employees contacted-included operators.
+Attended exit interview.
2.
Exit Interview 3.
The inspection scope and findings were summarized on April 20, 1979 with those persons indicated in Paragraph 1 above.
Licensee Action on Previous Inspection Findings (Open)
Unresolved Item (335/79-06-07):
QA documentation missing in Plant Change Package'PC/M).
The inspector reviewed the documentation on the plate material used in PC/M 493-78 and Plant Work Order (PWO) 3931 asserting that ASTM A-36 material had been used to change the Safety Injection Tank structural support.
As noted in Quality Assurance Report (QAR) 5814, dated February 16, 1979, three other problems concerning this plate still exist in the documentation, however, the most significant being acceptability of the A-36 material, when A515 Gr.70 was specified.
This item is no longer considered unresolved, but completion of the items indicated on QAR 5814 shall be followed up by the inspector in future inspections.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Plant Status At the time of this inspection, St.
Lucie Unit 1 was shutdown, cooled down, in Mode 6 conducting core alterations for cycle 3.
'lant Procedure Review The inspector reviewed the following nine plant maintenance, health physics, and operating procedures to assure conformance with Technical Specifications
(T.S.),
and that proper controls are established in each to meet regulatory requirements.
This review completed the inspection detailed in IE Report 335/79-09 paragraph 8.
Off-Normal OP 0110030 FLCEA (Full Length Control Element Assembly) Off Normal Operations and Realignment - Revision 4 OP 0030221 Initial Criticality Following Refueling - Revision 2 OP 0210020 Changing and Letdown - Normal Operations - Revision 8 OP 0210020 Charging and Letdown - Normal Operations - Revision 8 OP 0410021 SIT (Safety Injection Tank) Operations - Revision 8 OP 0530021 Gas Release To Atmosphere - Revision 14 OP 0950020 Boric Acid Heat Trace System Operation - Revision 2 OP 0970020 Operation of 120V AC System - Revision 2 Maintenance OP 0120360 Pressurizer Safety Valve Maintenance - Revision
HP-1 Radiation Work Permits - Revision
The inspector had no further questions in this area.
7.
Licensee Event Reports Review The following LER's were reviewed to verify that reporting requirements had been met, causes had been identified, corrective actions appeared appropriate, generic applicability had been considered, and the LER forms were complete.
Additionally, for those reports identified by asterisk, a more detailed review was performed to verify that the licensee had reviewed the events, corrective actions had been taken, no unreviewed safety questions were involved, and violations of regulations or Technical Specification conditions had been identified.
a.
LER 78-43/036-1,*
CEA 62 Slipped twice During Operations.
This supple-mental report was discussed in IE Report 335/79-01 paragraph 7.b.(5)
as a licensee identified omission in the original LER. The inspector verified the occurrence by reviewing the operating logs for November 20, 1978.
The procedure change to Off-Normal Procedure 0110030, part of the corrective action, was approved by the Facility Review Group (FRG), but not yet typed or distributed.
The inspector had no further questions in this area.
b.
LER 79-07/036-0,*
Low SIT Level Due to Leaking Drain Valve.
The inspector reviewed the system prints and operating procedure 0410021 (rev.8)
on SIT fillingoperations, to verified the licensee identified cause of occurrence.
Plant Work Orders (PWO) 3919 directs repair of
w3 valve V-3641, which was identified as leaking thru.
Although work on the valve was not yet complete, the inspector was satisfied that licensee action was consistent with the report and will correct the identified problem.
C.
LER 79-08/03L-O,* Low Diesel Fuel Oil Storage Tank Level Due to Stuck Gage.
The inspector was informed that the gage involved had been calibrated within a month before the failure was discovered.
The inspector was not able, due to other commitments, to review the cali-bration procedure or ascertain whether it was involved in the failure.
This review, and a check of generic application of the subject gages will be followed up in future inspections.
d.
LER 79-09/03L-O, CEA 62 Out of Alignment During Testing.
8.
IE Bulletins The following IE Bulletins were reviewed to determine whether they had been received and reviewed by appropriate management, responses, where necessary, were accurate and complete, and that action taken, if required, was complete.
a
~
IEB 78-14, Deterioration of BUNA-N Components in ASCO Solenoids.
This bulletin was not directed to St.
Lucie for response, but was distri-buted to appropriate supervisors for information as required'he inspector had no further questions in this area."
b.
C.
IEB 79-03, Weld Defects in Stainless Steel Spools.
The licensee requested 45 days more time to respond to this bulletin in a letter to NRC dated April 17, 1979.
The inspector will followup in this area at that time.
f IEB 79-06B, Review of the Three Mile Island Incident.
At the time of this inspection, the licensee had reviewed IEB 79-06B and action in response was being formulated.
In order to assure licensee understanding of the bulletin and the issues that it addresses, three NRC inspectors presented briefings to licensee management and operations personnel.
Three briefings were given covering The sequence of events at Three Mile Island from March 28 April 4, 1979.
IEB 79-06B - paragraph - by paragraph breakdown.
Effects of the incident on operator training, responsibilities, and qualification.
Questions brought up by operators at these briefings, have been submitted to NRC Headquarters for evaluation.
Subsequent to the inspection, the licensees response to IEB 79-06B, dated April 24, 1979 was reviewed by this office.
Questions concerning this
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-4-response and followup onsite of the corrective action identified will be
.the subject of future inspections prior to the completion of the refueling outage (335/79-11-01).
9.
IE Circulars The following IE Circulars were reviewed to determine whether they had been received by station management, reviewed for applicability and appropriate action had been taken or planned:
a.
IEC 79-02, Failure of 120 Volt Vital AC Power Supplies b.
IEC 79-04, Loose Locking Nut on Limitorque Valve Operators No items of noncompliance or deviations were identified.
10.
IE Notices The following IE Information Notices were reviewed to insure their receipt and review by appropriate management.
a.
IEN 79-05, Use of Improper Materials in Safety-Related Components b.
IEN 79-06, Stress Analysis of Safety-Related Piping.
Further correspon-dence and action on this issue is presented in IEB 79-07, and will be followed up in future inspections.
c.
IEN 79-07, Rupture of Radwaste Tanks d.
IEN 79-08, Interconnection of Contaminated Systems Mith Service Air Systems Vsed as the Source of Breathing Air.
e.
IEN 79-09, Spill of Radioactively Contaminated Resin.
No items of noncompliance or deviations were identified.
ll. Refueling Maintenance The inspector selected the following three major maintenance projects being performed during the present refueling to determine that the maintenance was properly authorized and reviewed, administrative controls for hold points, tests, and special processes were present, material certification, where necessary, is reviewed, proper cleanliness standards are met, and system retest is provided.
a.
Plant Change/Modification (PC/M) 553-79, Modification of the Emergency Diesel Shaft Coupling to the Fan.
This work was just starting on the lA diesel by technicians from Stewart-Stevenson Co., the vendor.
The inspector discussed the work to be done with the technicians, but did not observe any work.
The inspector verified testing had been completed to demonstrate operability of the other (1B) diesel, and that the
ly,
-5-licensee's clearance of the 1A diesel was complete prior to commencement of work.
The technicians did not have a procedure for the work involved and appeared to need guidance from the licensee on coordination of their work.
The inspector notified licensee management of this problem and will followup to insure proper controls and Quality Controls were established.
Retest of each diesel was scheduled to assure operability after the modificaiton and will also'be reviewed in the future.
b.
Plant Change/Modification 485/78, Rim Cut of the Steam Generator Tube Supports.
The inspector reviewed the Combustion Engineering (CE)
letters and procedures included in the PC/M package which describe all facets of the work to be done and present the certifications of three CE welders who will be involved.
The inspector will review the work package in future inspections to assure that the modification was conducted in accordance with the procedures and that the Eddy Current Testing, and the system retest were satisfactory.
c ~
PC/M 550-79, CEA Guide Tube Sleeving.
This modification is identical to PC/M 397-78 conducted during the last refueling outage to alleviate guide tube wear problems in CE fuel assemblies.
The inspector reviewed the procedures, and observed work in progress on spent fuel assemblies.
The technicians appeared to be coordinated and effective in the opera-tion, using calibrated equipment, controlled procedures, and taking all necessary data.
One retest was observed and appeared to be satis-factory.
Final data packages willbe reviewed in future inspections.
12.
Refueling Outage Operations The inspector toured the plant and observed control functions for the core alteration, tagging for selected maintenance work, jumper log useage and control, and major work planning.
The inspector reviewed actions taken by the licensee in response to an equipment malfunction which stalled the refueling operation.
Corrective action required Facility Review Group approval, Quality Control coverage, equipment fabrication and implementation of a
temporary procedure.
The inspector observed the progress of this corrective action and had no further questions.
The area of refueling operations will be further inspected in the future.
13.
Previously Identified Inspector Concerns a.
(Open)
Open Item (335/78-26-05)
Diesel air start manual isolation valve controls.
Internal NRC correspondence resolved the question of extra controls for the manual isolation valves to the diesel air start system as unnecessary, as long as other licensee controls assure proper valve positioning after maintenance or testing.
The inspector verified licensee controls requiring diesel testing in Quality Instruc-tion QI-11-PR/PSL-2 after any applicable maintenance.
The diesel test procedure, however, OP 2200050 does not specify items to be checked to insure the diesel is lined up for operation following the operational check of the diesel.
Licensee management committed to amplify steps 8.1.16 and 8.2.16 of procedure OP 2200050.
This item remains open pending inspector review of the revised procedur /p
-6-(Closed)
Open Item (79-01-05) Fire extinguishers monthly inspections not properly documented.
The inspector reviewed inspection tags on 22 portable fire extinguishers and found all indicated completion of the March, 1979 inspections.
On April 18, the inspector observed one operator performing the April inspections and saw the tags being properly filled out.
After discussion with the mechanical maintenance engineer responsible, the inspector had no further questions in this area.
(Closed)
Open Item (335/79-06-06)
PC/M Completion prior to approval by FRG.
The inspector reviewed 7 additional completed change packages to assure, from a larger sampling of PC/M's that licensee had approved the modifications prior to implementing them.
The inspector had no further questions in this area.