IR 05000302/1990013
| ML20034C200 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/19/1990 |
| From: | Conlon T, Fillion P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20034C198 | List: |
| References | |
| 50-302-90-13, NUDOCS 9005020161 | |
| Download: ML20034C200 (6) | |
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pk##1{ug UNITED STATES
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f NUCLEAR REGULATORY COMMISSION
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REGION It
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101 MARIETTA STREET. N.W.
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AT LANT A, GEORGI A 30323
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I Report No.:
50-302/90-13
Licensee:
Florida Power Corporation
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3201 34th Street, South i
St. Petersburg, FL 33733 Docket No.:
50-302 License No.:
DPR-72 j
Facility Name:
Crystal River 3
Inspection Co icted:
ril 2-6, 1990
Inspector: X7 h
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P. J. Iilli.
Date Signed Approved by C Y M
, Chief
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T. E. Conlon Date Signed j
Plant Systems.Section Engineering Branch Division of Reactor Safety l
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SUMMARY I
Scope:
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This routine, unannounced inspection was conducted in the area of ' electrical systems modifications.
The inspection was conducted during a planned refueling / maintenance / modification outage (refuel No. 7 scheduled March 12 through June 18).
Modifications addressed during the inspection and being implemented during the outage were:
(a) Batteries replacement I
(b) Changes to the diesel generators load sequencing and load shedding scheme.
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(c) High Pressure Injection System flow indication instrumentation upgrade.
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(d) Installation of equipment to provide a new source of offsite power.
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The inspector reviewed modification packages, outage activity schedules, i
witnessed field acceptance testing, reviewed copies of certified factory test reports, and engineering equipment source inspection reports.
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9005020t61 900420 PDR ADOCK 05000302 Q
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j Results:
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In the areas inspected, violations or deviations were not identified.
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Specific strengths or weaknesses were not apparent.
The engineering i
organization was effectual in defining necessary plant modifications. l0ther i
groups such as planning, procurement and project management successfully.
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REPORT DETAILS
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Persons Contacted Licensee Employees J. S. Andrews, Nuclear Engineer
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S. K. Balliet Nuclear Project Engineer
- D. H. Beach, Supervisor, Site Nuclear Engineering Services t
- G. A. Becker, Manager, Site Nuclear Engineering Services
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- J.' G. Brandely, Manager, Nuclear Integrated Planning
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G. W. Castleberry, Project Manager New Source of Offsite Power Project M. J. Fitzgerald, Supervisor Site Nuclear Engineering Services
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F. V. Fusick, Manager Site Nuclear Design Modification-
- P. F. McKee, Director, Nuclear Plant Operations
- F. X. Sullivan, Manager, Nuclear Plant Systems Engineering
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- M. S. Williams, Nuclear Regulatory Specialist Other licensee employees contacted during this inspection included
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craftsmen, engineers, and technicians.
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l Other Organizations Impell Corporation R. Atkinson, Principal Engineer
- Attended exit interview 2.
InspectionDetails(92701)
l This was an inspection of electrical systems plant modifications in the implementation phase.
The modifications inspected are related to i
l commitments made to the NRC.
Previous inspection activity-and background l
information on the topics covered in this report are described in NRC l
Inspection Reports 50-302/89-25, 89-28 and 89-31.
a.
Batteries replacement Modification package MAR. 89-08-03-01 implements the replacement of the safety-related batteries (one 250/125 V battery per redundant train).
At the time of this inspection the new train A battery was.
installed, and was examined by the NRC inspector.
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Battery service tests on 125 V banks 3A-1 and 3A-2 were conducted under Work Request No. NV 0261557 and Surveillance Procedure SP-523.
Both banks successfully carried the load profile in valid tests. The NRC inspector witnessed the service test on bank 3A-2.
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Related to the batteries replacement project, the NRC inspector
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reviewed a Quality Surveillance Report by Bechtel Corporation of Gaithersburg, Maryland. This Bechtel report sumarizes an inspection made at the C&D Power System Co. factory in Attica. Indiana where the batteries were manufactured (P.O. #F740214D).
The Bechtel inspection, conducted January 19 through 22, 1990, covered battery capacity tests, dimensional checks and documentation for the batteries shipped to CR3.
Copies of certified test reports for factory capacity tests were reviewed by the NRC inspector.
The NRC inspector did not identify any safety concerns related to the i
batteries replacement project.
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b.
Changes to the diesel generators load sequencing and load shedding scheme.
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Modification package MAR 88-05-24-01 implements changes to the diesel generator sequencing scheme aimed at reducing the load seen by(the diesel generators.
One part of the MAR provides a decay heat DH)
j pump / emergency feedwater (EF) pump interlock to automatically prevent concurrent operation of the DH and EF pumps during LOOP events by j
starting DH at 500 psig RC pressure and tripping EF. Another part of the MAR re-arranges the loads in each load block and increases the
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number of load blocks. The purpose of rearranging the load blocks is to improve the voltage profile during accident load sequencing onto i
the D/G.
Modification package MAR 88-08-01-01 assures, by the use of selector
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switches, that only one reactor building fan will be automatically sequenced onto the diesel generator.
Modification packages MAR 87-10-03-01 and MAR 88-05-04-01 are concerned with tripping the heat tracing load when both LOOP and
"engineeted safeguards" signals are present.
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Modification package MAR 87-10-05-01 is an existing temporary plant j
modification to load shed the train A battery chargers when LOOP and
" engineered safeguards" signals are both present. During this outage (refuel No. 7) the train A battery chargers will be reinstated as an automatically sequenced load.
A corresponding temporary MAR was not
made on train B, and therefore work on the train B batter" charger i
circuit will not be necessary.
The NRC inspector reviewed the scope and concept of the changes to the diesel generators load sequencing and load shedding schemes described above, and he did not identify any safety concerns.
Each of these MARS will be implemented during the current outage-(refuel
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No. 7)
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High Pressure Injection System flow indication instrumentation i
upgrade.
FPC had committed to upgrade the High Pressure ' Injection System flow l
indication instrumentation to meet the requirements of a Type A l
Category 1 variable as defined in RG 1.97.
These commitments are stated in a letter from FPC to the NRC, " Confirmation of Conditions for High Pressure Injection (HPI) Flow Balancing" (3F0190-06), dated January 10, 1990.
A graded approach to full com)liance will be used where a first set of upgrades will be implementec during refuel No. 7
outage. and a second set at refuel No. 8 outage will bring the variable into full compliance.
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Upgrades to take place in refuel No. 7 outage are controlled by l
modification packages MAR 80-11-17-03 and MAR 82-05-03-20.
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former replaces 0-500 gpm differential pressure transmitters DPT-1, t-2,
-3, and -4 which are older style transmitters with a more modern
atyle.
This will increase the reliability of these loops although-they will remain non-Class lE until refuel No. 8 outage. The latter l
MAR will upgrade instrument loops designated as MU-23-DPT-5, -6, -7 and -8 to Class IE by replacing the wiring between the remote shutdown auxiliary cabinet and the main control board;'and installing new flow
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indicators at the main control board.
At the time of this inspection, the new indicators were not yet installed.
Modification package MAR 82-05-03-20 was reviewed in a.
general way and no safety-concerns were identified. Three (3) Field Change Notices (FCNs) to this MAR were also reviewed, and the NRC
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inspector concluded that the FCNs in no way affected the intent of the MAR, nor did the -FCNs indicate that the MAR had not been properly prepared.
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Installation of equipment to provide a new source of offsite power.
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Ninety-five percent of the construction work is coinplete for a major
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plant enhancement aimed at providing a new independent source of offsite power.
The only work remaining is to pull-in and terminate some control cable; and to make some 5 KV cable splices.
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tional functional testing is scheduled to _ begin in early May 1990.
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The transformer has already been energized.
Equipment areas, manholes, and relay and control panels were walked down by the NRC inspector together with the Project Manager.
i Modification packages related to this work are; MAR No.
Title-89-08-11-01 New Offsite Power Source for CR3 Cable
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Duct Bank
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MAR No.
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89-08-11-02-New Offsite Power Source for CR3 Cable Tray and Conduit Design and Layout 89-08-11-03 New Offsite -Power Souret for CR3 Control Room Modificatio",
89-08-11-04 Conduit Supports for-MAR 89-08-11-02
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Inspection effort related to this plant enhancement did not identify any
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safety concerns, f
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Exit Interview
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The inspection scope and results were summarized on April 6,1990, with
those persons indicated in paragraph 1.
The inspector described the areas
inspected and discussed in detail the inspection results.
Proprietary -
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information is not contained in this report.
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