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| issue date = 06/01/1992
| issue date = 06/01/1992
| title = LER 92-003-01:on 920323,identified Improper Pressure Transmitter Calibration.Caused by Inadequate Procedures. Transmitters Locations Will Be Checked & Calibration Procedures Will Be revised.W/920601 Ltr
| title = LER 92-003-01:on 920323,identified Improper Pressure Transmitter Calibration.Caused by Inadequate Procedures. Transmitters Locations Will Be Checked & Calibration Procedures Will Be revised.W/920601 Ltr
| author name = HANEK O I, PLUNKETT T F
| author name = Hanek O, Plunkett T
| author affiliation = FLORIDA POWER & LIGHT CO.
| author affiliation = FLORIDA POWER & LIGHT CO.
| addressee name =  
| addressee name =  
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:ACCELERATED DI.TRIBUTION DEMONS TION SYSTEM REGULATORY XNFORMATION DISTRIBUTION SYSTEM.(RIDS)ACCESSION NBR:9206050056 DOC.DATE: 92/06/01 NOTARIZED:
{{#Wiki_filter:ACCELERATED DI. TRIBUTION DEMONS                                       TION SYSTEM REGULATORY XNFORMATION DISTRIBUTION SYSTEM .(RIDS)
NO FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C AUTH.NAME AUTHOR AFFILIATION HANEK,O.I.
ACCESSION NBR:9206050056                 DOC.DATE:   92/06/01   NOTARIZED: NO           DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light                       C 05000250 AUTH. NAME             AUTHOR AFFILIATION HANEK,O.I.             Florida     Power & Light Co.
Florida Power&Light Co.PLUNKETT,T.F.
PLUNKETT,T.F.           Florida     Power & Light Co.
Florida Power&Light Co.RECXP.NAME RECIPIENT AFFILIATION DOCKET 05000250 R  
RECXP.NAME             RECIPIENT AFFILIATION                                                     R


==SUBJECT:==
==SUBJECT:==
LER 92-003-01:on 920323 identified improper pressure transmitter calibration.
LER   92-003-01:on 920323 identified improper pressure transmitter calibration. Caused by inadequate                   procedures.
Caused by inadequate procedures.
Transmitters locations will be checked & calibration                                     D procedures       will be     revised.W/920601     ltr.
Transmitters locations will be checked&calibration procedures will be revised.W/920601 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR 3 ENCL/SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, et NOTES:NRR RAGHAVAN,L D 05000250 A D RECIPIENT ID CODE/NAME PD2-2 LA AULUCK,R INTERNAL: ACNW AEOD/DSP/TPAB NRR/DET/EMEB 7E NRR/DLPQ/LPEB1 0 NRR/DREP/PRPB11 NRR/DST/SICB8H3 NRR/DST/SRXB 8E RES/DSIR/EIB EXTERNAL EG&G BRYCE g J~H NRC PDR NSIC POOREgW NOTES COPIES LTTR ENCL 1~1 1 1 2 2 1 1 1 1 1 1 2 2 1 1 1'1 1 1 3 3 1 1 1 1 1.1 RECIPIENT ID CODE/NAME PD2-2 PD AEOD/DOA AEOD/ROAB/DSP NRR/DLPQ/LHFB10 NRR/DOEA/OEAB NRR/DST/SELB 8D NRR ST SPLBBD1 G, 02 RGA2 FILE 01 L ST LOBBY WARD NSIC MURPHY'A NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D D S NOTE TO ALL"RIDS" RECIPIENTS:
DISTRIBUTION CODE: IE22T             COPIES   RECEIVED:LTR 3 ENCL /         SIZE:
D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOb'I P 1-37 (EXT.20079)TO ELlivIINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31 P.O.Box 029100, Miami, FL, 33102-9100
TITLE: 50.73/50.9 Licensee Event               Report (LER), Incident Rpt, et NOTES:NRR RAGHAVAN,L                                                                     05000250 A D
.JUN 1 1992 L-92-163 10 CFR 50.73 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen:
RECIPIENT                 COPIES              RECIPIENT          COPIES ID CODE/NAME             LTTR ENCL          ID CODE/NAME        LTTR ENCL            D PD2-2 LA                       1  ~  1      PD2-2 PD                1      1 AULUCK,R                       1      1 INTERNAL: ACNW                             2      2      AEOD/DOA                1      1 AEOD/DSP/TPAB                   1      1    AEOD/ROAB/DSP            2      2 NRR/DET/EMEB 7E                 1      1      NRR/DLPQ/LHFB10        1      1 NRR/DLPQ/LPEB1 0               1      1      NRR/DOEA/OEAB          1      1 NRR/DREP/PRPB11                 2      2      NRR/DST/SELB 8D        1      1 NRR/DST/SICB8H3 NRR/DST/SRXB 8E RES/DSIR/EIB 1
Re: Turkey Point Unit 3 and 4 Docket Nos.50-250 and 50-251 Reportable Event: 92-003-01 Date of Event: March 23, 1992 Operation With Improper Pressure Transmitter Calibration The attached'upplement 1 to Licensee Event Report 250/92-003-00 is being provided, pursuant to the requirements of 10 CFR 50.73 to present the results of further review of the event.Very truly yours, d T.F.Plunkett Vice President Turkey Point Nuclear ,TFPNOIH Attachment cc: Stewart D.Ebneter, Regional Administrator, Region III USNRC R.C.Butcher, Senior Resident Inspectorr USNRCI Turkey Point Plant 9206050056 92060k PDR ADOCK 05000250 S PDR an FVL Group company FACILITY NAME)1)LICENSEE EVENT REPORT (LER)DOCKET NUMBER)2)PAGE)3)TURKEY POINT UNITS 3 AND 4 05000250 OF 4 TITLE (4)0 eration With Im ro er Pressure Transmitter Calibration EVENT DATE (5 LER NUMBER{6 RPT DATE<2)OTHER FACILITIES INV.<8 03 DAY 23 YR 92 YR 92 SEQ 9 003 01 MON" 06 DAY 01 YR 92 FACILITY NAMES Turkey Pc)nt Un1t 4 DOCKET 4 (S)05000251 OPERATING MODE{9)1/1 PONER LFVEL<10)82/100 10 CFR 50.73 a 2 i LICENSEE CONTACT FOR THIS LER (12)Olga I.Hanek, Licensing Engineer COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)TELEPHONE NUMBER 305-246-6607 CAUSE SYSTEM COMPONENT MANUFACTURER NPRDS2 CAUSE SYSTEM COMPONENT MANUFACTURER NPRDS2 SUPPLEMENTAL REPORT EXPECTED{14)NO X YES (If yee, conylete EXPECTED SUBMISSION DATE)ExpecTeD SUBMISSION DATE (15)MONTH DAY YEAR ABSTRACT (16)In response to NRC Information Notice 91-75,"Static Head Corrections Not Included in Pressure Transmitter Calibration Procedures", issued by the NRC on November 25, 1991, a review of the Turkey Point Units 3 and 4 calibration procedures revealed that the static head c'orrection was not considered in some pressure transmitter calibration procedures.
1' 1
IN 91-75 also reported that several plants did not include the static pressure span effects in the differential pressure transmitter calibration procedures.
1 1
A review of the Turkey Point Units 3 and 4 calibration procedures revealed that the static pressure span effects had been included in the calibration procedures.
1 G,
However, an error was found in the calibration procedures for steam generator level where the static pressure span effect was not applied properly.On March 23, 1992, FPL concluded that, after including the static head correction, and correcting the static pressure span effect error, Turkey Point Units 3 and 4 are operating in accordance with the current Technical Specifications.
NRR ST SPLBBD1 RGA2     FILE 01 02 1
However, without inclusion of static head corrections in some pressure transmitter calibration procedures and after correcting the static pressure span effect error found, operations were not in accordance with the old Technical Specifications in effect prior to August 26, 1991'PL performed an engineering analysis and determined that after inclusion of static.head corrections, correcting the static pressure span effect error, and assuming worst case instrument uncertainties, all the setpoints in question were within the design basis of the plant during operation prior to August 26, 1991.
1 1
LICENSEE]ANT REPORT (LER)TEXT COZINUATION FACILITY NAME TURKEY POINT UNITS 3&4 DOCKET NOHBER 05000250 LER NUMBER 92-003-01 PAGE NO.02 OF 04 KNG NT DESCRIPTION NRC Information Notice 91-75,"Static Head Corrections Not Included in Pressure Transmitter Calibration Procedures", issued by the NRC on November 25, 1991, reported that several plants did not include the static head corrections in their pressure transmitter calibration procedures.
1 1
A review of the Turkey Point Units 3 and 4 calibration procedures revealed that the static'head correction was not included in the calibration procedures.
1 EXTERNAL    EG &G BRYCE g J ~ H            3      3    L ST LOBBY    WARD      1     1 NRC PDR                        1     1     NSIC MURPHY' A          1     1 NSIC POOREgW                    1     1     NUDOCS FULL TXT          1     1 NOTES                                        1     .1 D
IN 91-75 also reported that'everal plants did not include the static pressure span effects in the differential pressure transmitter calibration procedures.
S D
A review of the Turkey Point Units 3 and 4 calibration procedures revealed that the static pressure span effects had been included in the calibration procedures.
D NOTE TO ALL "RIDS" RECIPIENTS:
However, an error was found in the calibration procedures for steam generator level where the static pressure span effect was not applied properly.The impact resulting from not incorporating the static head correction in the pressure transmitter calibration procedures and the static pressure span effect error for Safety Related applications was evaluated for the following Technical Specification setpoints:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOb'I P 1-37 (EXT. 20079) TO ELlivIINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
1.2.3.5.6.7.8.9.High pressurizer pressure reactor trip Low pressurizer pressure reactor trip Pressurizer high water level reactor trip Steam generator low-low water level reactor trip Pressurizer pressure input to overtemperature delta-T reactor trip Steam/feedwater flow mismatch coincident with steam generator low water level reactor trip Low pressurizer pressure safety injection actuation setpoint High steam line flow coincident with low steam generator pressure safety injection actuation setpoint High differential pressure between steam line header and any steam line safety injection actuation setpoint The calculated static head correction factors are as follows:.Steam header pressure-3.5 psi (minimum)Steam generator pressure (Main steam line pressure)-4.4 psi (maximum)Pressurizer pressure-14.5 psi (maximum)On March 23, 1992, FPL concluded the evaluation of the above setpoints including the static head and pressure span corrections in the existing transmitter calibration procedures.
FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR                   31   ENCL   31
For the worst'ase pressurizer pressure and steam generator pressure transmitter trip setpoints, the corrected values remain within the current Technical Specification values and therefore are in compliance with the present Technical Specifications and Safety Analysis Limits.For Technical Specification 3/4.2.5, DNB Parameters, Item b.pressurizer pressure, the potential existed for the minimum operational pressure value to be violated under system I perturbations.
However, the automatic pressure control system would restore system pressure within the allowed action time.Therefore there is no adverse effect on safety.For the original Technical Specifications prior to Amendments 137 and 132 (i.e., p..ior to August 26, 1991)for Units 3 and 4 respectively for the above setpoints, after inclusion of static head


LICENSEE kNT REPORT (LER)TEXT (QTINVATION
P.O. Box 029100, Miami, FL, 33102-9100
~FACILITY NAME TURKEY POINT UNITS 3&4 DOCKET NUMBER 05000250 LER NUMBER 92-003-01 PAGE NO.03 oF 04 corrections, static pressure span correction, and assuming worst case instrument uncertainties, the following Technical Specifications setpoints were violated: 2.Technical Specification 2', Limiting Safety System Settings, Protective Instrumentation Setpoints:
                                                                    . JUN      1      1992 L-92-163 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn:      Document        Control Desk Washington, D. C. 20555 Gentlemen:
Pressurizer:
Re:    Turkey Point Unit 3 and 4 Docket Nos. 50-250 and 50-251 Reportable Event: 92-003-01 Date of Event: March 23, 1992 Operation With Improper Pressure Transmitter Calibration The attached'upplement            1 to Licensee Event Report 250/92-003-00 is being provided, pursuant to the requirements of 10 CFR 50.73 to present the results of further review of the event.
Low pressurizer pressure reactor trip Steam Generator:
Very    truly      yours, d
Low-low water level Overtemperature delta-T reactor trip Technical Specification 3.5, Instrumentation, Table 3.5-4, Engineered Safety Feature Setpoints:
T. F. Plunkett Vice President Turkey Point Nuclear
Item 3.Pressurizer Low Pressure Safety Injection Actuation Setpoint Item 4.High Steam Line Differential Pressure Safety Injection Actuation Setpoint Item 5.High Steam Line Flow Coixcident with Low Steam Line Pressure Safety Injection Actuation Setpoint For Technical Specification 3.1.6, Reactor Coolant System, DNB Parameters, Item b.pressurizer pressure, the potential existed for the minimum operational pressure value to be violated under system perturbations.
,TFPNOIH Attachment cc:      Stewart D. Ebneter, Regional Administrator, Region III USNRC R. C.      Butcher, Senior Resident Inspectorr USNRCI Turkey Point Plant 9206050056 92060k PDR      ADOCK 05000250 S                        PDR an FVL Group company
However, the automatic pressure control system would restore system pressure within the allowed action time.Therefore there is no adverse effect on safety.FPL performed an engineering analysis and determined that after inclusion of static head corrections, correction of the static pressure span effect error, and assuming worst case instrument uncertainties, all the setpoints in question were within the design basis of the plant during operation prior to August 26, 1991.II.EVENT CAUSE The cause of the event is attributed to inadequate procedures.
 
The static head corrections had not been incorporated into the calibration procedures for these pressure transmitters.
LICENSEE EVENT REPORT                                                          (LER)
The static pressure span effects were erroneously applied for the steam generator low-low water level setpoint.III'VENT SAFETY ANALYSIS On March 23, 1992, FPL concluded that, after inclusion of the static head correction, correction of the static pressure span error, and assuming worst case instrument uncertainties, Turkey Point Units 3 and 4 are operating in accordance with the'current Technical Specifications.
FACILITY NAME )1)                                                                                      DOCKET NUMBER )2)        PAGE )3)
FPL reviewed the old Technical Specificati.'ons and the calibration procedures in effect prior to the Technical Specification revision which incorporated the new setpoint methodology.
TURKEY POINT UNITS 3 AND 4                                                  05000250                      OF      4 TITLE (4)          0  eration With            Im  ro er Pressure Transmitter Calibration EVENT DATE (5            LER NUMBER{6            RPT DATE <2)            OTHER  FACILITIES INV.    <8 DAY    YR            YR      SEQ 9          MON"    DAY    YR                                                      DOCKET  4  (S)
FPL determined that, after applying the static head correction factors to the setpoints, and correcting the static pressure span effect error, there is still adequate margin to the Safety Analysis Limit which existed for the setpoints discussed in Section I.Therefore, there was no operability concern or safety concern with the operation of the Turkey Point Units 3 and 4 without the pressure transmitter static head.correction factors incorporated and the static pressure span effect error in the pre'ssurize." pressure and steam generator pressure and level procedures.
FACILITY NAMES 03        23      92            92      003      01    06      01    92        Turkey Pc)nt Un1t    4                        05000251 OPERATING MODE {9)      1/1                                              10 CFR    50.73 a          2    i PONER LFVEL <10)        82/100 LICENSEE CONTACT FOR THIS LER (12)
LICENSEE 1+NT REPORT (LER)TEXT CTINUATION FACILITY NAME DOCKET NUMBER LER NOMBER TURKEY POINT UNITS 3 6 4 05000250 92-003-01 PAGE NO 04 OF 04 CORRECTIVE ACTIONS V.Although inclusion of the static head correction factor and correction of the static pressure span effect for the pressure transmitters is not a violation of the current Turkey Point Units 3 and 4 Technical Specifications (Amendments 137 and 132), applicable plant pressure transmitters locations will be checked and the calibration procedures will be revised (as needed)to include the static head correction factor and correct the pressure span effect error.This work will be completed by the end of the next refueling outages currently scheduled for October 26, 1992 for Turkey Point Unit 3, and June 13, 1993 for Turkey Point Unit 4~ADDITIONAL INFORMATION No similar events involving pressurizer pressure transmitter static head corrections have been reported for Turkey Point This event was reported in accordance with 10 CFR 50'3 (a)(2)(i)(B).}}
Olga    I. Hanek,      Licensing Engineer                                                                        TELEPHONE NUMBER 305-246-6607 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED  IN THIS  REPORT  (13)
CAUSE    SYSTEM        COMPONENT      MANUFACTURER            NPRDS2    CAUSE        SYSTEM                      MANUFACTURER    NPRDS2 COMPONENT ExpecTeD        MONTH        DAY          YEAR SUPPLEMENTAL REPORT EXPECTED  {14)    NO  X        YES                                        SUBMISSION DATE  (15)
(If yee,  conylete  EXPECTED SUBMISSION DATE)
ABSTRACT (16)
In response to NRC Information Notice 91-75, "Static Head Corrections Not Included in Pressure Transmitter Calibration Procedures", issued by the NRC on November 25, 1991, a review of the Turkey Point Units 3 and 4 calibration procedures revealed that the static head c'orrection was not considered in some pressure transmitter calibration procedures.                                        IN 91-75 also reported that several plants did not include the static pressure span effects in the differential pressure transmitter calibration procedures. A review of the Turkey Point Units 3 and 4 calibration procedures revealed that the static pressure span effects had been included in the calibration procedures.
However, an error was found in the calibration procedures for steam generator level where the static pressure span effect was not applied properly. On March 23, 1992, FPL concluded that, after including the static head correction, and correcting the static pressure span effect error, Turkey Point Units 3 and 4 are operating in accordance with the current Technical Specifications.
However, without inclusion of static head corrections in some pressure transmitter calibration procedures and after correcting the static pressure span effect error found, operations were not in accordance with the old Technical Specifications in effect prior to August 26, 1991 an engineering analysis and determined that after inclusion of static .head
                                                                                                                  'PL      performed corrections, correcting the static pressure span effect error, and assuming worst case instrument uncertainties, all the setpoints in question were within the design basis of the plant during operation prior to August 26, 1991.
 
LICENSEE    ]ANT REPORT      (LER) TEXT COZINUATION FACILITY NAME                  DOCKET NOHBER        LER NUMBER          PAGE NO.
TURKEY POINT UNITS 3    & 4      05000250        92-003-01        02 OF 04 KNG NT DESCRIPTION NRC  Information Notice 91-75, "Static Head Corrections Not Included in Pressure Transmitter Calibration Procedures", issued by the NRC on November 25, 1991, reported that several plants did not include the static head corrections in their pressure transmitter calibration procedures. A review of the Turkey Point Units 3 and 4 calibration procedures revealed that the static 'head correction was not included in the calibration procedures.      IN 91-75 also reported that'everal plants did not include the static pressure span effects in the differential pressure transmitter calibration procedures. A review of the Turkey Point Units 3 and 4 calibration procedures revealed that the static pressure span effects had been included in the calibration procedures.      However, an error was found in the calibration procedures for steam generator level where the static pressure span effect was not applied properly. The impact resulting from not incorporating the static head correction in the pressure transmitter calibration procedures and the static pressure span effect error for Safety Related applications was evaluated for the following Technical Specification setpoints:
: 1. High pressurizer pressure reactor trip
: 2.      Low pressurizer pressure reactor trip
: 3.      Pressurizer high water level reactor trip Steam generator low-low water level reactor trip
: 5. Pressurizer pressure input to overtemperature delta-T reactor trip
: 6. Steam/feedwater flow mismatch coincident with steam generator low water level reactor trip
: 7.      Low pressurizer pressure safety injection actuation setpoint
: 8. High steam line flow coincident with low steam generator pressure safety injection actuation setpoint
: 9. High differential pressure between steam line header and any steam line safety injection actuation setpoint The calculated static head correction factors are as follows:.
Steam header pressure      3.5 psi (minimum)
Steam generator pressure (Main steam line pressure)  4.4 psi (maximum)
Pressurizer pressure  14.5 psi (maximum)
On March 23, 1992, FPL concluded the evaluation of the above setpoints including the static head and pressure span corrections in the existing transmitter calibration procedures.        For the worst'ase pressurizer pressure and steam generator pressure transmitter trip setpoints, the corrected values remain within the current Technical Specification values and therefore are in compliance with the present Technical Specifications and Safety Analysis Limits.
For Technical Specification 3/4.2.5, DNB Parameters, Item b.
pressurizer pressure, the potential existed for the minimum operational pressure value to be violated under system                    I perturbations. However, the automatic pressure control system would restore system pressure within the allowed action time. Therefore there is no adverse effect on safety.
For the original Technical Specifications prior to Amendments 137 and 132 (i.e., p..ior to August 26, 1991) for Units 3 and 4 respectively for the above setpoints, after inclusion of static head
 
LICENSEE     kNT     REPORT     (LER) TEXT (QTINVATION
~ FACILITY NAME                   DOCKET NUMBER        LER NUMBER        PAGE NO.
TURKEY POINT UNITS 3     & 4       05000250         92-003-01       03 oF 04 corrections, static pressure span correction, and assuming worst case instrument uncertainties, the following Technical Specifications setpoints were violated:
Technical Specification 2     ', Limiting Safety System Settings, Protective Instrumentation Setpoints:
Pressurizer: Low pressurizer pressure reactor trip Steam Generator: Low-low water level Overtemperature delta-T reactor trip
: 2. Technical Specification 3.5, Instrumentation, Table 3.5-4, Engineered Safety Feature Setpoints:
Item 3. Pressurizer Low Pressure Safety Injection Actuation Setpoint Item 4. High Steam Line Differential Pressure Safety Injection Actuation Setpoint Item 5. High Steam Line Flow Coixcident with Low Steam Line Pressure Safety Injection Actuation Setpoint For Technical Specification 3.1.6, Reactor Coolant System, DNB Parameters, Item b. pressurizer pressure, the potential existed for the minimum operational pressure value to be violated under system perturbations. However, the automatic pressure control system would restore system pressure within the allowed action time. Therefore there is no adverse effect on safety.
FPL performed an engineering analysis and determined that after inclusion of static head corrections, correction of the static pressure span effect error, and assuming worst case instrument uncertainties, all the setpoints in question were within the design basis of the plant during operation prior to August 26, 1991.
II. EVENT CAUSE The cause of the event     is attributed to inadequate procedures. The static head corrections     had not been incorporated into the calibration   procedures   for these pressure transmitters. The static pressure span effects were erroneously applied for the steam generator low-low water level setpoint.
III'VENT SAFETY ANALYSIS On March 23, 1992, FPL concluded that, after inclusion of the static head correction, correction of the static pressure span error, and assuming worst case instrument uncertainties, Turkey Point Units 3 and 4 are operating in accordance with the'current Technical Specifications.
FPL reviewed the old Technical Specificati.'ons and the calibration procedures in effect prior to the Technical Specification revision which incorporated the new setpoint methodology. FPL determined that, after applying the static head correction factors to the setpoints, and correcting the static pressure span effect error, there is   still   adequate margin to the Safety Analysis Limit which existed for the setpoints discussed in Section I. Therefore, there was no operability concern or safety concern with the operation of the Turkey Point Units 3 and 4 without the pressure transmitter static head. correction factors incorporated and the static pressure span effect error in the pre'ssurize." pressure and steam generator pressure and level procedures.
 
LICENSEE   1+NT REPORT     (LER) TEXT CTINUATION FACILITY NAME                 DOCKET NUMBER       LER NOMBER       PAGE NO TURKEY POINT UNITS 3     6 4     05000250       92-003-01     04 OF 04 CORRECTIVE ACTIONS Although inclusion of the static head correction factor and correction of the static pressure span effect for the pressure transmitters is not a violation of the current Turkey Point Units 3 and 4 Technical Specifications (Amendments 137 and 132), applicable plant pressure transmitters locations will be checked and the calibration procedures will be revised (as needed) to include the static head correction factor and correct the pressure span effect error. This work will be completed by the end of the next refueling outages currently scheduled for October 26, 1992 for Turkey Point Unit 3, and June 13, 1993 for Turkey Point Unit 4     ~
V. ADDITIONAL INFORMATION No   similar events involving pressurizer pressure transmitter static head   corrections have been reported for Turkey Point This event was reported in accordance with 10 CFR 50 '3 (a) (2) (i) (B) .}}

Latest revision as of 08:51, 22 October 2019

LER 92-003-01:on 920323,identified Improper Pressure Transmitter Calibration.Caused by Inadequate Procedures. Transmitters Locations Will Be Checked & Calibration Procedures Will Be revised.W/920601 Ltr
ML17349A245
Person / Time
Site: Turkey Point NextEra Energy icon.png
Issue date: 06/01/1992
From: Hanek O, Plunkett T
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-92-163, LER-92-003-01, LER-92-3-1, NUDOCS 9206050056
Download: ML17349A245 (7)
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Text

ACCELERATED DI. TRIBUTION DEMONS TION SYSTEM REGULATORY XNFORMATION DISTRIBUTION SYSTEM .(RIDS)

ACCESSION NBR:9206050056 DOC.DATE: 92/06/01 NOTARIZED: NO DOCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 AUTH. NAME AUTHOR AFFILIATION HANEK,O.I. Florida Power & Light Co.

PLUNKETT,T.F. Florida Power & Light Co.

RECXP.NAME RECIPIENT AFFILIATION R

SUBJECT:

LER 92-003-01:on 920323 identified improper pressure transmitter calibration. Caused by inadequate procedures.

Transmitters locations will be checked & calibration D procedures will be revised.W/920601 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR 3 ENCL / SIZE:

TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, et NOTES:NRR RAGHAVAN,L 05000250 A D

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD2-2 LA 1 ~ 1 PD2-2 PD 1 1 AULUCK,R 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB10 1 1 NRR/DLPQ/LPEB1 0 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB8H3 NRR/DST/SRXB 8E RES/DSIR/EIB 1

1' 1

1 1

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1 EXTERNAL EG &G BRYCE g J ~ H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY' A 1 1 NSIC POOREgW 1 1 NUDOCS FULL TXT 1 1 NOTES 1 .1 D

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D NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOb'I P 1-37 (EXT. 20079) TO ELlivIINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31

P.O. Box 029100, Miami, FL, 33102-9100

. JUN 1 1992 L-92-163 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:

Re: Turkey Point Unit 3 and 4 Docket Nos. 50-250 and 50-251 Reportable Event: 92-003-01 Date of Event: March 23, 1992 Operation With Improper Pressure Transmitter Calibration The attached'upplement 1 to Licensee Event Report 250/92-003-00 is being provided, pursuant to the requirements of 10 CFR 50.73 to present the results of further review of the event.

Very truly yours, d

T. F. Plunkett Vice President Turkey Point Nuclear

,TFPNOIH Attachment cc: Stewart D. Ebneter, Regional Administrator, Region III USNRC R. C. Butcher, Senior Resident Inspectorr USNRCI Turkey Point Plant 9206050056 92060k PDR ADOCK 05000250 S PDR an FVL Group company

LICENSEE EVENT REPORT (LER)

FACILITY NAME )1) DOCKET NUMBER )2) PAGE )3)

TURKEY POINT UNITS 3 AND 4 05000250 OF 4 TITLE (4) 0 eration With Im ro er Pressure Transmitter Calibration EVENT DATE (5 LER NUMBER{6 RPT DATE <2) OTHER FACILITIES INV. <8 DAY YR YR SEQ 9 MON" DAY YR DOCKET 4 (S)

FACILITY NAMES 03 23 92 92 003 01 06 01 92 Turkey Pc)nt Un1t 4 05000251 OPERATING MODE {9) 1/1 10 CFR 50.73 a 2 i PONER LFVEL <10) 82/100 LICENSEE CONTACT FOR THIS LER (12)

Olga I. Hanek, Licensing Engineer TELEPHONE NUMBER 305-246-6607 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFACTURER NPRDS2 CAUSE SYSTEM MANUFACTURER NPRDS2 COMPONENT ExpecTeD MONTH DAY YEAR SUPPLEMENTAL REPORT EXPECTED {14) NO X YES SUBMISSION DATE (15)

(If yee, conylete EXPECTED SUBMISSION DATE)

ABSTRACT (16)

In response to NRC Information Notice 91-75, "Static Head Corrections Not Included in Pressure Transmitter Calibration Procedures", issued by the NRC on November 25, 1991, a review of the Turkey Point Units 3 and 4 calibration procedures revealed that the static head c'orrection was not considered in some pressure transmitter calibration procedures. IN 91-75 also reported that several plants did not include the static pressure span effects in the differential pressure transmitter calibration procedures. A review of the Turkey Point Units 3 and 4 calibration procedures revealed that the static pressure span effects had been included in the calibration procedures.

However, an error was found in the calibration procedures for steam generator level where the static pressure span effect was not applied properly. On March 23, 1992, FPL concluded that, after including the static head correction, and correcting the static pressure span effect error, Turkey Point Units 3 and 4 are operating in accordance with the current Technical Specifications.

However, without inclusion of static head corrections in some pressure transmitter calibration procedures and after correcting the static pressure span effect error found, operations were not in accordance with the old Technical Specifications in effect prior to August 26, 1991 an engineering analysis and determined that after inclusion of static .head

'PL performed corrections, correcting the static pressure span effect error, and assuming worst case instrument uncertainties, all the setpoints in question were within the design basis of the plant during operation prior to August 26, 1991.

LICENSEE ]ANT REPORT (LER) TEXT COZINUATION FACILITY NAME DOCKET NOHBER LER NUMBER PAGE NO.

TURKEY POINT UNITS 3 & 4 05000250 92-003-01 02 OF 04 KNG NT DESCRIPTION NRC Information Notice 91-75, "Static Head Corrections Not Included in Pressure Transmitter Calibration Procedures", issued by the NRC on November 25, 1991, reported that several plants did not include the static head corrections in their pressure transmitter calibration procedures. A review of the Turkey Point Units 3 and 4 calibration procedures revealed that the static 'head correction was not included in the calibration procedures. IN 91-75 also reported that'everal plants did not include the static pressure span effects in the differential pressure transmitter calibration procedures. A review of the Turkey Point Units 3 and 4 calibration procedures revealed that the static pressure span effects had been included in the calibration procedures. However, an error was found in the calibration procedures for steam generator level where the static pressure span effect was not applied properly. The impact resulting from not incorporating the static head correction in the pressure transmitter calibration procedures and the static pressure span effect error for Safety Related applications was evaluated for the following Technical Specification setpoints:

1. High pressurizer pressure reactor trip
2. Low pressurizer pressure reactor trip
3. Pressurizer high water level reactor trip Steam generator low-low water level reactor trip
5. Pressurizer pressure input to overtemperature delta-T reactor trip
6. Steam/feedwater flow mismatch coincident with steam generator low water level reactor trip
7. Low pressurizer pressure safety injection actuation setpoint
8. High steam line flow coincident with low steam generator pressure safety injection actuation setpoint
9. High differential pressure between steam line header and any steam line safety injection actuation setpoint The calculated static head correction factors are as follows:.

Steam header pressure 3.5 psi (minimum)

Steam generator pressure (Main steam line pressure) 4.4 psi (maximum)

Pressurizer pressure 14.5 psi (maximum)

On March 23, 1992, FPL concluded the evaluation of the above setpoints including the static head and pressure span corrections in the existing transmitter calibration procedures. For the worst'ase pressurizer pressure and steam generator pressure transmitter trip setpoints, the corrected values remain within the current Technical Specification values and therefore are in compliance with the present Technical Specifications and Safety Analysis Limits.

For Technical Specification 3/4.2.5, DNB Parameters, Item b.

pressurizer pressure, the potential existed for the minimum operational pressure value to be violated under system I perturbations. However, the automatic pressure control system would restore system pressure within the allowed action time. Therefore there is no adverse effect on safety.

For the original Technical Specifications prior to Amendments 137 and 132 (i.e., p..ior to August 26, 1991) for Units 3 and 4 respectively for the above setpoints, after inclusion of static head

LICENSEE kNT REPORT (LER) TEXT (QTINVATION

~ FACILITY NAME DOCKET NUMBER LER NUMBER PAGE NO.

TURKEY POINT UNITS 3 & 4 05000250 92-003-01 03 oF 04 corrections, static pressure span correction, and assuming worst case instrument uncertainties, the following Technical Specifications setpoints were violated:

Technical Specification 2 ', Limiting Safety System Settings, Protective Instrumentation Setpoints:

Pressurizer: Low pressurizer pressure reactor trip Steam Generator: Low-low water level Overtemperature delta-T reactor trip

2. Technical Specification 3.5, Instrumentation, Table 3.5-4, Engineered Safety Feature Setpoints:

Item 3. Pressurizer Low Pressure Safety Injection Actuation Setpoint Item 4. High Steam Line Differential Pressure Safety Injection Actuation Setpoint Item 5. High Steam Line Flow Coixcident with Low Steam Line Pressure Safety Injection Actuation Setpoint For Technical Specification 3.1.6, Reactor Coolant System, DNB Parameters, Item b. pressurizer pressure, the potential existed for the minimum operational pressure value to be violated under system perturbations. However, the automatic pressure control system would restore system pressure within the allowed action time. Therefore there is no adverse effect on safety.

FPL performed an engineering analysis and determined that after inclusion of static head corrections, correction of the static pressure span effect error, and assuming worst case instrument uncertainties, all the setpoints in question were within the design basis of the plant during operation prior to August 26, 1991.

II. EVENT CAUSE The cause of the event is attributed to inadequate procedures. The static head corrections had not been incorporated into the calibration procedures for these pressure transmitters. The static pressure span effects were erroneously applied for the steam generator low-low water level setpoint.

III'VENT SAFETY ANALYSIS On March 23, 1992, FPL concluded that, after inclusion of the static head correction, correction of the static pressure span error, and assuming worst case instrument uncertainties, Turkey Point Units 3 and 4 are operating in accordance with the'current Technical Specifications.

FPL reviewed the old Technical Specificati.'ons and the calibration procedures in effect prior to the Technical Specification revision which incorporated the new setpoint methodology. FPL determined that, after applying the static head correction factors to the setpoints, and correcting the static pressure span effect error, there is still adequate margin to the Safety Analysis Limit which existed for the setpoints discussed in Section I. Therefore, there was no operability concern or safety concern with the operation of the Turkey Point Units 3 and 4 without the pressure transmitter static head. correction factors incorporated and the static pressure span effect error in the pre'ssurize." pressure and steam generator pressure and level procedures.

LICENSEE 1+NT REPORT (LER) TEXT CTINUATION FACILITY NAME DOCKET NUMBER LER NOMBER PAGE NO TURKEY POINT UNITS 3 6 4 05000250 92-003-01 04 OF 04 CORRECTIVE ACTIONS Although inclusion of the static head correction factor and correction of the static pressure span effect for the pressure transmitters is not a violation of the current Turkey Point Units 3 and 4 Technical Specifications (Amendments 137 and 132), applicable plant pressure transmitters locations will be checked and the calibration procedures will be revised (as needed) to include the static head correction factor and correct the pressure span effect error. This work will be completed by the end of the next refueling outages currently scheduled for October 26, 1992 for Turkey Point Unit 3, and June 13, 1993 for Turkey Point Unit 4 ~

V. ADDITIONAL INFORMATION No similar events involving pressurizer pressure transmitter static head corrections have been reported for Turkey Point This event was reported in accordance with 10 CFR 50 '3 (a) (2) (i) (B) .

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