IR 05000250/1992002

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Insp Repts 50-250/92-02 & 50-251/92-02 on 920113-17.No Violations or Deviations Noted.Major Areas Inspected:Maint Procedures for New Equipment Added During Emergency Power Sys Enhancement Project
ML17348B398
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 02/06/1992
From: Hunt M, Jape F
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML17348B397 List:
References
50-250-92-02, 50-250-92-2, 50-251-92-02, 50-251-92-2, NUDOCS 9202240097
Download: ML17348B398 (8)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION II

101 MARIETTASTREET, N.W.

ATLANTA,GEORGIA 30323 Report No~.:

50-250/92-02 and 50-251/92-02 Licensee:

Florida Power and Light Company 9250 t.'Est Flaaler Street t'ai ami, FL 33102 Docket Nos.:

50-250 and 50-251 License Ncs.:

DPR-31 and DPR-41 Facility Name:

Turkey Point 3 and

.

1nspectior.

Ccrducted:

January 13-17, 1992 1nspector:

ll. U.

Hunv.

ate Sigred e

~c.

Approved by: /I L ~

Frank ape, C'e-Tos.

PIUI:rarI.S Section Enaineering Branch Division o>

ReacTor Safety SUt'1MARY Scope:

This routine, at nounced inspectior.

w. coIIducted in the areas of maintenance, procedI;Ies for new equipment addeo auriI.e t!Ie Emeraency Power System (EPS}

Er hancement project.,

rov.'ew cf a

seouercer probleIr, and clusuI c of two violations.

Results:

In the areas inspected, violations or deviations were not identified.

The following violations were closed:

50-250/251-91-35-01, Failure to maintain Current and Accurate Eq Documentation Packaaes 50-250/251/91-39-01, No PK Program for Transfer Inh',bit Relays.

9202240097 920211 PDR ADOCK 05000250 G

PDR

REPORT DETAILS Persons Contacted Licensee Emplo~ ees

  • W. A. Busch, Electrical Staff Enaineer.
  • S. N. Franzone, I8C Engineerirg Support Supervisor
  • H. R. Gavankar, Nuclear Enginec,ring Technic:al Specialist,

":J. Gianfrancesci, Support Service Supervisor

"'R. Gouldy, Juno Nuclear Licensing, Principal Engineer

  • S. T. Hale, Fvgireering Hanager J.

Hardy, I8C Engineer

". E. Knorr, Plant Licensing

"R. S, Kundalkar, Project Engineer

"L. h. Pearce, Plant General Vanager T. Plunkett,'ice President, Nuclear

':D.'. Powell, Services Yanaaer

"'J. Sharpe, Plant Electrical t1ainteriance.

  • F. Varona, Juno Plant Nuc!rar, Engineering Supervisor Other licensee employees contacted dul"ina th s

inspection included craftsmen, engineers arid operators.

NRC Residert Inspectors

  • R. C. Butcher, Senior Resident Inspector G.. A. Schnebl-i, Resident Inspector

.L. Trocine, Resident Inspector

/

(Closed) Violai.ior:

50-250/251/91-35-01, -Failure to l'iaintain Current and Accurate Eg Documentazion Pacl:ages.

The licensee submitted a

response dazed December 19, 1991 which concurred with the finding, identified tlie cause, outlined the corrective actions taken and the actions tn prevent further violations.

The eiaht documertation packages found deficient during the inspection were updated to current as-built status.

The additional EO documentation packages that were impacted by the recently complieted design changes have been updated.

The inspector reviewed the engineering evaluation for 20 documertation packages and found them, acceptable.

This item is closed.

(Closed) Violation 50-250/251/91-39-01, Ne PN Program for Transfer Inhibit Relays.

The licensee submitted a response dated December 18, 1991 which concurred with zhe violation anc listed the corrective actions whicli have been taken.

The inspector had observed a portior, o tliese actions during the inspection which identified the violation.

Procedure O-PliR-005.10, HGA 1C2/TDDO Relay Calibration which was issued and approved on October 22, 1991 requires calibration ever v 18 months and includes the acceptance cr'teria.

Tfiis item is close Programmable Loaic Controllers - EAGLE 2'iid Sequencers The Control of software for programmable processes is defined in -three procedures which are part of the design/engineering processes, the ori site/plant process and the equal',ty Assurance Manual.

These are:

JPN-OI 7.3 - Nuclear Engineering-Process Soft Mare Control (12-PTN-15 - Turkey Point Nuclear Plant - Control of Computer Software gP-2. 15 - Cuality Assurance Manual Control of Computer Software These procedure'efine the responsibilities and contrcls for the develcpment, implementation, verification, validation, testing documentation, maintenance, procurement, and security of software which is used in the proerammabl>>

process equipment that control safety related processi s

and functions.

The responsibilit.ies for development, implementatior and alterations are clearly defined.

These procedures also require review fur LO CFR 50.59 applicability vAcn changes are made to process software and require validation arid verification for the changes.

In conJurction with the above procedures

.he FhhLF.

System 18 month calibrations for the RCS (Tave and Delta) protective function are controlled h the foiiowing procedures.

3/4 - Pf!'-04!.,6, RCS Temperature Loop.A Channel Set I Calibration

'/4 - PYii-04!.7, PCS Ti.mperature Loop B Channel Set II Calibration 3/4 - PNI-041.8, RCS Temperature Loop B Channel Set III Calibration The procedures cover channel calibration for the following parameters of the RCS protectioli loops:

Average Temperature (Tave)

Tempei ature Difference (Delta)

Over temperature Setpcirt (OTSP)

Over Power Setpoint (OPSP)

The wide range T hot and T cold calibrations are covered by these procedures.

Also included in these procedures

'.: verification of status lights, power supply outputs, alarms and manual and automatic surveillance testing of the so~+>>are program.

The 18 month Pressurizer Level Protection Loop calibration is performed in accordance with Procedures 3/4 -

PNI-041. 104, 105, 106, PRZR Level Protection channel I, I 1, Ill Loop Calibration.

These procedures cover the instrument loop calibration for the levcli tr"n",r:;.tter,,level indicator, (control room), level indicator peri I, (2, 3) (control room)

and remote indications at the charging pump and AFlt'ur:p-s'"t.ions.

Loop diagrams and logic =low charts are contained in these procedure',

,

'e The above listed 18 month procedures are yet to be used the first time.

However the following quarterly procedures have been performed and are similar to the 18 month procedures:

3/4-SMI-041.16.

Tave and Delta -

T Protection channel T-3/4-412, T-3/4-422, and T-3/4 - 432 Test.

3/4-SMI-041: ll Pressurizer Level Protection Loop quarterly Tests These latter procedures are performed at power and certain functions are not tested at that time but are tested during the 18 month tests.

Of the procedures reviewed for the EAGLE 21 System all were found adequate.

The sequencer emergency bus loading is tested every '8 months by procedure 0-PMI-024. 1.

Emergency Bus Load Sequencer

Month Maintenance.

This procedure directs 'he testing of sequencer trouble alarms during replacement of Processor Backup Battery.

Further, power supply outputs are verified for 12VDC, 125VDC power supplies and power transformers.

Procedures O-PMI-024.2, Emergency Bus Load Sequencers Software Verification controls verification of the software programs and program loading.

This procedure details the activities and the requirements/

controls that are needed in place when the sequencer program is tested or changed.

These procedures appear adequate to maintain the sequencers.

4.

Fuse Control Program The Fuse control program is controlled by Procedure O-ADM-030, Control of Fuses.

Control of fuse replacement is under the guidance of this procedure.

The procedure clearly defines the levels of responsibilities among supervihory personnel and departments.

The various types of fuses are described as well as various electrical terms.

The documents identifying the fuses are tiered to insure resolution of conflicts and defines when non-conforming reports are required.

The inspector examined various panels to verify fuse identification markings.

The fuses in the 4. 16 KV switch gear, the 480 VAC distribution Load Centers, and battery changers were identified. It is to be noted that only certain panels were examined at each of the above listed equipment because the units were both in full load operation.

The licensee is committed to the continuing up grade of drawings and documents relating to the fuse identification and replacement program.

5.

125 VDC Battery Charger Maintenance Battery Chargers were tested and credit taken as the result of pre-op and startup testing per Procedures 0-PME-003. 18 125VDC Station Battery Charger Maintenanc The procedu. ~ cori'.rr,'.s the inspection, testing, and adjustments for the battery chargers.

i'here voltage values or current values are recorded as the resulit o

test'.ri cr adjustments, the acceptable criteria is also

.

listed. 'his procedure appears adequate.

Sequencer Probiems On December 10; 1991, the 4A sequencer was found not functioriing in the auto test mo'de even though the auto test switch was in the auto test position.

The licensee issued LER 91-007-00 on january 7, 1992 in accordance with the requirements of Teel niical Specification Table 3.~-2

"Engineered Safety Features Actuation System Instrumentation,"

which defines the minimum operable channels required for operation.

The unit was shut downi ori December 10, 1991.

The seouencer testing revealed an invalid indication of an undervoltaoe on

'C Load Center.

Testing and trouble shooting ioentified a faulty Auto Test output card in the 4A sequencer programable logic controller (PLC).

The detailed

~inspection of output card revealed a sticking contact on an output relay which appeared to the sequencer logic to be ar, urder voltage siaral or.

4C load center.

This signal blocked the auto and manual test function while the sequencer waited for a safety injection signal which would have been necessary for the sequencer to actuate the bus stripping and sequencial loadinig on tc the emergency diesel generators.

The failed relay contact was ori the relay which is used to test the sequcrcer logic.

The contact is paralleled t,o =the under voltage relay contact for 4C load center.

Tlie test sional energizes the test rel<~,

clos',ng tl e c'cntact for approximately 0.8 seconds.

Bus stripping would not occur unless the contact closure existed for longer thar 10 sec arid a SI

'.nr.~

1, was received.

I The licensee conducted tests with an identical sequercer used for training purposes and verified that the scquencer would have functioned 'normally if the load center low voltage signal were pre ent and an SI signal was received.

A safety evaluation JPN-PTti-SEtiS 9'-099 was performed to determine tllat the sequencer could be operated with the Auto-Test feature'urned Off.

The manual test will be performed everv 30 days.

Every

hours a

surveillance of the local reflash annunciators, power switches and var'ious inidicating lights is performed.

Evcrv 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> power to the processor and input/output cards is verified.

Operation in this mode will continue until such time as an outage of sufficient duration to permit further testing occurs.

In the mear tire the

',',cersee has worked with the supplier of the equipment to find possible causes for the sticking relay contact.

The root cause of the PLC output card failure is ongoing.

The licensee has committed to further reporting if require.

Exit Interview The inspection scope and results were summarized on January,17, 1992, with those persons indicated in paragraph 1.

The inspector described the areas inspected and discussed in detail the inspection results.

proprietary information is not contained in this report.

Dissenting comments were not received from the licensee.