IR 05000250/1979041
| ML17339A994 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 01/24/1980 |
| From: | Martin R, Vogtlowell R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17339A989 | List: |
| References | |
| 50-250-79-41, 50-251-79-41, NUDOCS 8005050229 | |
| Download: ML17339A994 (12) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 Report Nos. 50-250/79-41 and 50-251/79-41 Licensee: Florida Power 8 Light 9250 West Flagler Street Miami, Florida 33101 Facility Name: Turkey Point 3/4 Docket Nos. 50-250 and 50-251 License Nos.
DPR-31 and DPR-41 Inspection at Turkey oint Site, near Homestead, Florida Inspected by:
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R. J.
V-Lowell Approved by:
R. D. Martin, Section Chief, RONS Branch Dat Signed l ~<
J4 ate gned
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SlPPbtPy Inspection on December 1-20, 1979 Areas Inspected This routine inspection involved 118 inspector-hours onsite in the areas of receipt of,new fuel, refueling activities, plant operations, maintenance activites, debris in Unit 3 steam generators, Unit 4 reactor trips, radiation protection-operations.
Results Of the 7 areas inspected, no apparent Items of noncompliance or deviations were identified in six areas; one apparent item of noncompliance was found in one area (Infraction - failure to follow procedure - paragraph 10.b).
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DETAILS Persons Contacted H. E. Yaeger, Site Manager J.
K. Hays, Plant Manager - Nuclear J.
E. Moore, Operations Superintendent
- 'Nuclear D.
W. Haase, Technical Department Supervisor K. E. Beatty, Training Supervisor V. B. Wager, Operations Supervisor J.
Wade, Chemistry Supervisor P.
W. Hughes, Health Physics Supervisor T. A. Finn, Nuclear Plant Supervisor L. C. Huenniger, Nuclear Plant Supervisor J. L. Whitehead, Nuclear Plant Supervisor J.
E. Crockford, Nuclear Plant Supervisor P.
R. Lanning, Nuclear Watch Engineer V. A. Kaminskas, REactor Engineering Supervisor R.
G. Mende, Unit 3 Reactor Engineer C. J. Becker, Unit 4 Reactor Engineer D. C. Bradford, Refueling Coordinator W. A. Klein, Licensing Engineer J. Bates, Health Physics Operations Supervisor P. J. White, Maintenance Superintendent W. R. Williams, Assistant Superintendent Electrical Mainten J.
P. Mendieta, ISC Department Supervisor L. Thomas, Assistant Superintendent Nuclear Maintenance - P B.
C. Kilpatrick Assistant Superintendent Nuclear Maintenan G. Vaux, QC Supervisor S. Feith, Operations QA Supervisor ance rimary ce - Secondary Other licensee employees contacted included operators, craftsmen, technicians, security personnel, QA personnel, and engineering personnel.
Management Interviews Management interviews were conducted on December 7,
14 and 20, 1979 with the Site Manager or Plant, Manager-Nuclear and selected members of his staff.
The inspector summarized the scope and findings of his inspection activities.
Licensee Action on Previous Inspection Findings Not inspected.
Unresolved Items None identified during this inspection perio.
New Fuel Receipt and Inspection Shipments of new fuel for the Unit 3 refueling outage were completed during this report period.
Prior to the shipments the inspector verified that approved procedures for the receipt, inspection and storage of new fuel were in effect and current.
The inspector witnessed various areas of new fuel handling including unloading shipping containers, serial number verification, radiation checks, visual inspection and storage.
Data sheets on fuel handling were being maintained on a current basis as required by plant procedures.
The inspector examined the Westinghouse Nuclear Fuel Department's
"Quality Release Forms" for twelve fuel assemblies.
No discrepancies were noted.
Within the areas inspected, no items of noncompliance were identified.
6.
Refueling Activites - Unit 3 The inspector reviewed the reactor control zoom copy of the following completed procedures:
MP 1407 '
Reactor Vessel - Removal of Missile Shield MP 1407.2 Removal of Control Rod Drive Mechanism Cooling MP 1407.3 Reactor Vessel - Removal of Rod Drive Electrical Cables MP 1407.4 Reactor Vessel - Removal of Instrument Ports MP 1407.5 Reactor Vessel - Removal of Head Insulation MP 1407.6 Installation of Reactor Vessel Cavity Seal Ring MP 1407.9 Reactor Vessel - Removal of Upper Internals OP 16004.2 Refueling System Interlocks Verification OP 16104.1 Fuel Transfer System - Periodic Test OP 16204.1 Manipulator Crane and RCC Change Fixture - Periodic Test OP 16304.1 Spent Fuel Pit Bridge Crane - Periodic Test OP 16404.1 New Fuel Elevator - Periodic Test OP 16404.2 New Fuel Monorail Hoist - Periodic Test OP 16504.1 New Fuel Bridge Crane - Periodic Test
"3-OP 16900.1 Uncoupling Full Length Control Rods.
All of the above procedures were completed prior to commencement of the fuel shuffle.
The inspector observed fuel handling activities both from the main control room and from the refueling deck inside the containment.
The activities were reviewed to assure that:
a.
proper core monitoring was being maintained b.
fuel accountability methods were being implemented c.
proper make-up and license requirements for the crews on the refueling deck and in the control room were established d.
coordination between the refueling crew in the containment and the crew in the control room existed.
e.
Technical Specification boron concentration requirements were being observed
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f.
containment integrity requirements during the refueling operations were being observed g.
fuel assembly handling was being properly performed h.
general good hou'sekeeping was being observed on the refueling bridge and refueling deck.
Within the areas inspected, no items of noncompliance or deviations were identified.
7.
Plant Operations The inspector reviewed plant operations to ascertain conformance with regulatory requirements, technical specifications and administrative directives.
The control room logs, shift supervisors logs, and equipment clearance logs for both units were reviewed.
Interviews with a number of plant operations personnel were held on the day and night shifts.
Supervisor and control room operator actions were observed during shifts and at various shift changes.
The number of licensed personnel on each shift met or exceeded the requirements of the Technical Specifications.
Operators were responsive to annunicator alarms and appeared to be cognizant of plant. statu The following areas were toured by the inspector at various times during the inspection report period:
a.
Control Room b.
Cable Spreading Area c.
Motor generator set and battery rooms d.
Rod control equipment rooms e.
Switchgear Rooms f.
Auxiliary Building g.
Radwaste building h.
Turbine area During the tours, observations were made of housekeeping and cleanliness, ongoing activities, security equipment status and radiation control practices.
Within the areas inspected, no items of noncompliance or deviations were
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identified..
8.
Maintenance Activities The inspector witnessed the bench testing related to the "pop" and leak test on the "A" Pressurizer Safety Valve for Unit 3 to insure that:
a.
Administrative approvals were obtained and controls were established for performing the work b.
Maintenance was accomplished using an approved and technically adequate procedure c.
Testing was performed at the completion of the maintenance d.
equality control records were available for the maintenance being performed e.
Maintanance was accomplished by technically qualified personnel.
Within the areas inspected no items of noncompliance or deviations were identified.
9.
Debris in Unit 3 Steam Generators Shortly after the December 2, 1979 shutdown marking the commencement of the Unit 3 refueling outage, the licensee reported the finding of some unidenti-fiable material in the 3B and 3C steap generator hog )egs.
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was of sheet metal appearance and exhibited ferromagnetic characteristics.
Subsequent analysis by the licensee indicate the material to be carbon steel.
At this writing, the licensee is unaware of the origin or identity of the material.
The licensee plans to perform an in-vessel inspection of the lower plenum that would reveal any additional foreign material that may be present.
10.
Unit 4 Reactor Trips a o December 13, 1979:
A manual reactor trip (after a controlled power reduction from 100$ power operation)
was effected at 6:58 a.m.
after experiencing an apparent high steam flow indication on the 4B steam generator.
A containment entry by the licensee disclosed a steam leak in the feeder line to the steam flow transmitter.
The leak was located at a failure of the weld connection of the sensing line to the main steam line.
The cause of the failure is attributed to vibration of the sensing line resulting from a U-bolt support which had worked itself loose.
The licensee repaired the line and inspected the analogous lines on the unaffected steam generators prior to restarting the unit.
b.
December 19, 1979:
Unit 4 experienced a reactor trip and attendant turbine trip from 100/ power at 1:37 a.m.
due to the initial trip of the 4A Reactor Coolant Pump (RCP).
There were no unusual system response characteristics observed subsequent to the trip.
The cause of the RCP trip is attributed to an electrical short between phases in the RCP motor resulting in the opening of the circuit breaker in the power supply to the motor.
This in turn gave rise to the automatic reactor trip signal.
Repairs to the motor are underway as of this writing.
During subsequent inspector followup of this event it was noted that the recording instrument charts associated with steam generators A, B and C had been cut and sent to Document Control as required by procedure but had not been identified and dated, as is also required by Administrative Procedure 103;2, "Duties and responsi-bilities of operators on shift and maintenance of operating logs and records".
This is contrary to Technical Specification 6.8.1 and is an item of noncompliance.
(50-251/79-41-01)
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Radiation Protection - Operations The inspector randomly examined various radiation protection instruments in use and verified operability and currency of calibration.
Various ongoing operations were examined by the inspector to assure that work activities were being conducted in accordance with the applicable Radiation Work Permit requirements.
The inspector verified by selective examination that high radiation area posting and control and
CFR
posting requirements were being met.
Within the areas inspected, no items of noncompliance or deviations were identifie ~
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