ML17348A414

Responds to Violations Noted in Insp Repts 50-250/90-14 & 50-251/90-14.Corrective Actions:Breakers Closed,Returning Monitoring Sys to Operable Level & Briefings Held to Explain Rvlms Sys Theory to Operations Control Room Personnel

ML17348A414
Person / Time
Site:	Turkey Point
Issue date:	07/20/1990
From:	Goldberg J FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9007240046
Download: ML17348A414 (7)

See also: IR 05000250/1990014

Text

ACCELERATED

DISTRIBUTION

DEMONSTRATION

SYSTEM REGULATORY

INFORMATION

DISTRIBUTION

SYSTEM (RIDS)A SSION NBR:9007240046

DOC.DATE: 90/07/20 NOTARIZED:

NO DOCKET FACIL:50-250

Turkey Point Plant, Unit 3, Florida Power and Light C, 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH.NAME AUTHOR AFFILIATION

GOLDBERG,J.H.

Florida Power&Light Co.RECIP.NAME

RECIPIENT AFFILIATION

Document Control Branch (Document Control Desk)SUBJECT: Responds to violations

noted in Insp Repts 50-250/90-14

&50-251/90-14.

DISTRIBUTION

CODE: IEOID COPIES RECEIVED:LTR

ENCL SIZE: 5 TITLE: General (50 Dkt)-Insp Rept/Notice

of Vio ation esponse NOTES: RECIPIENT ID CODE/NAME PD2-2 PD INTERNAL: AEOD AEOD/TPAD NRR MORISSEAUiD

NRR/DLPQ/LPEB10

NRR/DREP/PEPB9

D NRR/DST/DIR

8E2 NUDOCS-ABSTRACT

OGC/HDS2 RGN2 FILE 01 EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1,1 1 1 1, 1 1 1 1 1 1~1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME EDISON,G AEOD/DEIIB

DEDRO NRR SHANKMAN,S

NRR/DOEA DIR 11 NRR/DRIS/DIR

NRR/PMAS/ILRB12

R RE FI 02 NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE iVASTE!CONTACT THE DOCUMENT CONTROL DESK ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION

LI'S'I S FOR DOCUMENTS YOU DON'T NEED!AL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 22

'e P.O.Box 14000, Juno Beach.FL 33408.0420

ggy 2 0 890 L-90-269 10 CFR 2.201 U.S.Nuclear Regulatory

Commission

Attn: Document Control Desk Washington, D.C.20555 Gentlemen:

Re: Turkey Point Units 3 and 4 Docket Nos.50-250 and 50-251 Reply to Notice of Violation NRC Ins ection Re ort 90-14 Florida Power&Light Company has reviewed the subject inspection

report and pursuant to 10 CFR 2.201 the response is attached.Very truly yours, J.H.Goldberg)/Presiden't

'.1 Nuclear Division JHG/GRM/sh

Attachment, cc: Stewart D.Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant

0 ATTACHMENT

REPLY TO NOTICES OF VIOLATION RE: Turkey Point Units 3 and 4 Docket Numbers 50-250 and 50-251 NRC Inspection

Report 90-014 FINDING A TS Table 3.5-5, Item 15, and Action Statement 9, require at least one of two channels of RVLMS be operable or entry into the Limiting Condition for Operation (LCO)is required.Action'Statement

9 requires that at least one channel of RVLMS be restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.If this cannot be done without shutting down the reactor, an alternate method for monitoring

reactor.vessel inventory must be provided.In addition, TS 3.0.4 prevents entry into an operational

mode or other specified condition unless the conditions

for the LCO are met without reliance on provisions

contained in the action statement.

Contrary to the above, on May 21, 1990, the licensee identified

that the LCO associated

with TS Table 3.5-5, Action Statement 9, was exceeded on May 19, at 5:51 p.m., as both channels of RVLMS on Unit 3 were out of service on an equipment clearance order and~~~~~~~~~~~~~~~provisions

were not made for alternate reactor vessel inventory monitoring.

This condition had existed since May 17, 1990, at 5:51 p.m.In addition, the unit changed modes and entered Mode 3 on May 18, 1990, at 7:15 p.m., with the clearance still in effect.r RESPONSE TO FINDING A 2~FPL concurs with the finding.The cause for both channels of RVLMS being inoperable

while Unit 3 entered Mode 3 was personnel error.A licensed operator failed to perform a comprehensive

review of the clearance order book to determine if any equipment required for entry into Mode 3 was out of service.The clearance order book index was reviewed but had not been updated to include clearance order 3-90-05-110-R.

The following factors contributed

to this event: Operating Surveillance

Procedure O-OSP-200.2,"Plant Startup Surveillances," requires procedure 3-OSP-204,"Accident Monitoring

Instrumentation

Channel Checks,".to be performed prior to entering Mode 4.Procedure 3-OSP-204 did not contain acceptance

criteria for a normal expected temperature

difference

between heated and unheated junction thermocouples.

Operations

personnel.1

0 did not question both sets of thermocouples

indicating

approximately

the same temperature.

The system passed the channel check with no power to the heated junction thermocouples.

Although the heated junction thermocouples

were logged in the Equipment Out Of Service (EOOS)Book, clearance order 3-90-05-110-R

was not entered under the comment section for the entry when transcribed

from hand-written

to computerized

format by the Reactor Control Operator (RCO).This led to confusion about the entry.This event was reported to the.NRC in Licensee Event ,Report 50-250/90-10.

3.Corrective

steps which have been taken and the results achieved include: a~Upon discovery that the heated junction thermocouple

power supply breakers were open, the breakers were closed.This returned the Reactor Vessel Level Monitoring

System (RVLMS)to an operable status.b.Briefings were held to explain the RVLMS system theory to operations

control room personnel.

4.Corrective

steps which will be taken to avoid further~~~~~violations

include: a~b.General Operating Procedures

3/4-GOP-301,"Hot Standby to Power Operation,"and 3/4-GOP-503,"Cold Shutdown to Hot Standby," have been revised requiring the Plant Supervisor-Nuclear (PSN)to verify that the clearance order book has been reviewed prior to making a mode change.On-The-Spot-Changes (OTSCs)have been generated against procedure 3/4-OSP-204

to add a minimum acceptable

temperature

difference

between the heated and unheated junction thermocouples.

c~An entry has been made in the Operations

Night Order Book requiring the Assistant Plant Supervisors-Nuclear (APSNs)/PSNs

to review and initial the computerized

EOOS log entries to ensure that pertinent information

contained on the hand-written

log entries has been correctly transcribed.

E 5.The a~b.c~d.e.data when full compliance

was achieved: Item 3.a was completed on May 21, 1990.Item 3.b was completed on May 29,,1990.Item 4.a was completed on June 15, 1990.Item 4.b was completed on.June 27, 1990.Item 4.c was completed on June 18, 1990.FINDING B TS 6.8.1 requires that written procedures

and administrative

policies shall be established, implemented

and maintained

that meet or exceed the requirements

and recommendations

of Appendix A of USNRC Regulatory

Guide 1.33 and Section 5.1 of ANSI N18.7-1972.

Section 5.1.2 of ANSI N18.7-1972

requires that procedures

be followed.O-ADM-021, Technical Specification

Implementation

Procedure, revision dated April 12, 1990, specifies that the requirements

of this procedure (interim TS)are to be compiled with unless the procedure (interim TS)requirements

are: waived i.'n accordance

with~~~~~~~~~the procedure or are less restrictive

than the current TS.O-ADM-021, Section 3/4.5.2 requires that one operable flow path from the Refueling Water Storage Tank to the RCS via the SI pumps be operable with RCS temperature

greater then 380 F.Contrary to the above, on May 18, 1990, 0-ADM-021 was not followed in that the operators heated the Unit 3 RCS above 380'(410')with SI flowpath isolation valves (3-867A and B)locked closed.This rendered the SI flowpath inoperable.

The requirement

to have an operable SI flowpath above 380'was more restrictive

than current TS;however, the licensee did not obtain a waiver.RESPONSE TO FINDING B 2~FPL concurs with the finding.The cause of allowing SI flowpath isolation valves 3-867A and 3-867B to remain locked closed while Unit 3 exceeded 380'was personnel error.The following factors contributed

to this condition:

Administrative

Procedure (AP)0103.4,"In-Plant Equipment Clearance Orders," requires components

within the clearance boundary to be aligned or verified to be aligned for the required mode of system operation in accordance

with the applicable

plant procedure.

This

0 alignment is to be completed during the release of the clearance to return a system or component to service.The normal position for valves 3-867A and 3-867B is locked open, as specified in Operating Procedure 3-OP-062,"Safety Injection." The individual

preparing the clearance release for valves 3-867A and 3-867B did not consult 3-0P-062, as required by AP 0103.4.As specified in procedure AP 0103.4, the Nuclear Watch Engineer (NWE), Assistant Plant Supervisor-Nuclear (APSN)or Plant Supervisor-Nuclear (PSN)is responsible

for ensuring the clearance order, partial release and release forms are properly filled out by the Foreman/Supervisor

holding the clearance.

For clearance 3-90-04-162-R, the individual

initiating

the clearance release was the same individual

authorizing

the clearance release.A mistake made in specifying

a release position of locked closed for valves 3-867A and 3-867B was not subjected to an independent

review, as required by AP 0103.4.3.Corrective

steps which have been taken and the results achieved include:Upon discovery that valves 3-867A and 3-867B were in the locked closed position, they were immediately

placed in the locked open position.Corrective

steps which will be taken to avoid further violations

include: a~This event has been presented to operations

personnel in the weekly shift meetings with management

personnel.

Adherence to the requirements

and intent of AP 0103.4 were emphasized.

b.Procedure AP 0103.4 is currently being revised as a procedure upgrade effort and will be re-issued as Administrative

Procedure O-ADM-212,"In-Plant Equipment Clearance Orders." Changes will be incorporated

to clarify the requirement

to independently

verify positions specified for system components

on a clearance release.5.The date when full compliance

was achieved: a~b.c~.Item 3 was completed on May 18, 1990.Item 4.a was completed on July 3, 1990.Item 4.b will be completed by October 31, 1990.