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| number = ML17026A413
| number = ML17026A413
| issue date = 01/11/2017
| issue date = 01/11/2017
| title = Fitzpatrick - Part 21 - Failure of Power Supplies to Meet Voltage Stability Specifications
| title = Part 21 - Failure of Power Supplies to Meet Voltage Stability Specifications
| author name = Hawes M
| author name = Hawes M
| author affiliation = Entergy Nuclear Operations, Inc
| author affiliation = Entergy Nuclear Operations, Inc
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:0111112017 . U.S. Nuclear Regulatory Commission Operations Center Event Report Pagel Power Reactor Event# 52480 Site: FITZPATRICK Notification Date I Time: 01/10/2017 22:45 (EST) Unit: 1 Region: 1 State: NY Event Date I Time: 11/10/2016 16:04 (EST) Reactor Type: [1] GE-4 Last Modification:
{{#Wiki_filter:0111112017 .                   U.S. Nuclear Regulatory Commission Operations Center Event Report                         Pagel Power Reactor                                                                                     Event#       52480 Site: FITZPATRICK                                 Notification Date I Time: 01/10/2017       22:45   (EST)
01/10/2017 Containment Type: MARK I NRC Notified by: MARK HAW.ES Notifications:
Unit: 1             Region: 1       State: NY         Event Date I Time: 11/10/2016       16:04   (EST)
ANTHONY DIMITRIADIS R1DO HQ Ops Officer: DONALD NORWOOD PART 21/50.55 REACTOREMAIL Emergency Class: NON EMERGENCY 10 CFR Section: 21.21(a)(2)
Reactor Type:   [1] GE-4                                           Last Modification: 01/10/2017 Containment Type:       MARK I NRC Notified by: MARK HAW.ES                                       Notifications: ANTHONY DIMITRIADIS R1DO HQ Ops Officer: DONALD NORWOOD                                                     PART 21/50.55 REACTOREMAIL Emergency Class: NON EMERGENCY 10 CFR Section:
INTERIM EVAL OF DEVIATION Unit Scram Code RX Crit lnit Power Initial RX Mode Curr Power Current RX Mode 1 N Yes 67 Power Operation 67 Power Operation PART 21 -FAILURE OF POWER SUPPLIES TO MEET VOLTAGE STABILITY SPECIFICATIONS "This notification is a 1 O CFR 21.21 (a)(2) interim report for power supply model N-2ARPS-A6.
21.21(a)(2)         INTERIM EVAL OF DEVIATION Unit Scram Code       RX Crit lnit Power   Initial RX Mode               Curr Power     Current RX Mode 1         N           Yes   67           Power Operation               67             Power Operation PART 21 - FAILURE OF POWER SUPPLIES TO MEET VOLTAGE STABILITY SPECIFICATIONS "This notification is a 10 CFR 21.21 (a)(2) interim report for power supply model N-2ARPS-A6. Two instrument power supplies for the 'B' Residual Heat Removal (RHR) system were being bench tested prior to installation when it was discovered that they failed to meet Vendor Technical Manual specifications for voltage stability for varying loads. The deviation was a voltage drop of approximately 300mV. This did not meet the specification of less than 150mV when varying current from 5 amps (full load) to 2.5 amps. A second replacement power supply exhibited a similar 300 mV drop.
Two instrument power supplies for the 'B' Residual Heat Removal (RHR) system were being bench tested prior to installation when it was discovered that they failed to meet Vendor Technical Manual specifications for voltage stability for varying loads. The deviation was a voltage drop of approximately 300mV. This did not meet the specification of less than 150mV when varying current from 5 amps (full load) to 2.5 amps. A second replacement power supply exhibited a similar 300 mV drop. "James A. FitzPatrick (JAF) reviewed the work order instructions to determine if there was a deviation from the recommendations in the Foxboro technical manual F180-0309 Spec 200 Multinest Power Supply 2ARPS Series calibration.
  "James A. FitzPatrick (JAF) reviewed the work order instructions to determine if there was a deviation from the recommendations in the Foxboro technical manual F180-0309 Spec 200 Multinest Power Supply 2ARPS Series calibration. Since as-found voltage readings were within the required tolerance of the RHR instrument loops, the power supplies appear to have been capable to perform their intended function. However, this evaluation did not troubleshoot why the power supplies failed to meet the calibration requirements.*
Since as-found voltage readings were within the required tolerance of the RHR instrument loops, the power supplies appear to have been capable to perform their intended function.
  "The power supplies were sent to a repair vendor. The input from this vendor is expected to allow JAF to complete the evaluation per 10 CFR 21.21 (a)(1) by March 21, 2017, and a notification for failure to comply or defect per 10 CFR 21.21(d)(3)(i) is expected by March 24, 2017, if necessary. This notification is being submitted as an interim report per 10 CFR 21.21 (a)(2)."
However, this evaluation did not troubleshoot why the power supplies failed to meet the calibration requirements.* "The power supplies were sent to a repair vendor. The input from this vendor is expected to allow JAF to complete the evaluation per 1 O CFR 21.21 (a)(1) by March 21, 2017, and a notification for failure to comply or defect per 10 CFR 21.21(d)(3)(i) is expected by March 24, 2017, if necessary.
The licensee notified the NRC Resident Inspector.
This notification is being submitted as an interim report per 10 CFR 21.21 (a)(2)." The licensee notified the NRC Resident Inspector.  
 
********************************************************************************************************************************
NRC FORM 361                                                                                                                        U.S. NUCLEAR REGULATORY COMMISSION (12-2000)                                                                                                                                        OPERATIONS CENTER REACTOR PLANT EVENT NOTIFICATION WORKSHEET EN# 52480 NRC OPERATION TELEPHONE NUMBER: PRIMARY -- 301-816-5100 or 800-532-3469*, BACKUPS -- [1st] 301-951-0550 or 800-449-3694*,
NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION (12-2000)
[2nd] 301-415-0550 and [3rd] 301-415-0553                                                        *Licensees who maintain their own ETS are orovided these telephone numbers.
OPERATIONS CENTER REACTOR PLANT EVENT NOTIFICATION WORKSHEET EN# 52480 NRC OPERATION TELEPHONE NUMBER: PRIMARY --301-816-5100 or 800-532-3469*, BACKUPS --[1st] 301-951-0550 or 800-449-3694*, [2nd] 301-415-0550 and [3rd] 301-415-0553
NOTIFICATION TIME          FACILITY OR ORGANIZATION                            UNIT              NAME OF CALLER                                  CALL BACK#
*Licensees who maintain their own ETS are orovided these telephone numbers. NOTIFICATION TIME FACILITY OR ORGANIZATION UNIT NAME OF CALLER CALL BACK# 2245 EST James A. FitzPatrick 1 Mark Hawes (315) 349-6664 EVENT TIME & ZONE EVENT DATE POWER/MODE BEFORE POWER/MODE AFTER 16:04 ET 11/10/2016 67% I Mode 1 67% I Mode 1 EVENT CLASSIFICATIONS 1-Hr. Non-Emergency 10 CFR 50.72(b)(1)
2245 EST            James A. FitzPatrick                                1                  Mark Hawes                                                (315) 349-6664 EVENT TIME & ZONE          EVENT DATE                      POWER/MODE BEFORE                                                POWER/MODE AFTER 16:04 ET                        11/10/2016                  67% I Mode 1                                                    67% I Mode 1 EVENT CLASSIFICATIONS                                1-Hr. Non-Emergency 10 CFR 50.72(b)(1)                        D    (v)(A)  Safe S/D Capability                  AINA D    GENERAL EMERGENCY                      GEN/AAEC        D                TS Deviation                            ADEV    D    (v)(B)  RHR Capability                      AINB D    SITE AREA EMERGENCY                    SIT/AAEC          4-Hr. Non-Emeraencv 10 CFR 50.72CblC2l                        D    (v)(C)  Control of Rad Release              AINC D    ALERT                                  ALE/AAEC        D    (i)        TS Required S/D                        ASHU    D    (v)(D)  Accident Mitigation                  AIND D    UNUSUAL EVENT                          UNU/AAEC        D    (iv)(A)      ECCS Discharge to RCS                ACCS    D    (xii)    Offsite Medical                    AMED D    50.72 NON-EMERGENCY            (see next columns)      D    (iv)(B)     RPS.Actuation (scram)                  ARPS    D    (xiii)  Loss Comm/Asmt/Resp                ACOM D    PHYSICAL SECURITY (73.71)                    DDDD      D    (xi)        Offsite Notification                  APRE          60-Day Optional 10 CFR 50.73(a)(1)
D (v)(A) Safe S/D Capability AINA D GENERAL EMERGENCY GEN/AAEC D TS Deviation ADEV D (v)(B) RHR Capability AINB D SITE AREA EMERGENCY SIT/AAEC 4-Hr. Non-Emeraencv 10 CFR 50.72CblC2l D (v)(C) Control of Rad Release AINC D ALERT ALE/AAEC D (i) TS Required S/D ASHU D (v)(D) Accident Mitigation AIND D UNUSUAL EVENT UNU/AAEC D (iv)(A) ECCS Discharge to RCS ACCS D (xii) Offsite Medical AMED D 50.72 NON-EMERGENCY (see next columns) D (iv)(B) RPS.Actuation (scram) ARPS D (xiii) Loss Comm/Asmt/Resp ACOM D PHYSICAL SECURITY (73.71) DDDD D (xi) Offsite Notification APRE 60-Day Optional 10 CFR 50.73(a)(1)
D   MATERIAL/EXPOSURE                              B???      8-Hr. Non-Emeraencv 10 CFR 50.72Cb)(3)                       D            Invalid Specified System Actuation  AINV D   FITNESS FOR DUTY                                HFIT  D   (ii)(A)      Degraded Condition                    ADEG      Other Unspecified Requirement (Identify) 0    OTHER UNSPECIFIED REQMT. (see last column)            D   (ii)(B)      Unanalyzed Condition                  AUNA    1ZJ  10CFR21.21(a)(2)                            NONR D    INFORMATION ONLY                              NINF    D   (iv)(A)     Specified System Actuation            AESF    D                                                 NONR DESCRIPTION Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc. (Continue on back)
D MATERIAL/EXPOSURE B??? 8-Hr. Non-Emeraencv 10 CFR 50.72Cb)(3)
This notification is a 10 CFR 21.21 (a)(2) interim report for power supply model N-2ARPS-A6. Two instrument power supplies for the "B" Residual Heat Removal (RHR) system were being bench tested prior to installation when it was discovered that they failed to meet Vendor Technical Manual specifications for voltage stability for varying loads. The deviation was a voltage drop of approximately 300mV. This did not meet the specification of <150mV when varying current from 5 amps (full load) to 2.5 amps.
D Invalid Specified System Actuation AINV D FITNESS FOR DUTY HFIT D (ii)(A) Degraded Condition ADEG Other Unspecified Requirement (Identify) 0 OTHER UNSPECIFIED REQMT. (see last column) D (ii)(B) Unanalyzed Condition AUNA 1ZJ 10CFR21.21(a)(2)
A second replacement power supply exhibited a similar 300 mV drop.
NONR D INFORMATION ONLY NINF D (iv)(A) Specified System Actuation AESF D NONR DESCRIPTION Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc. (Continue on back) --This notification is a 1 O CFR 21.21 (a)(2) interim report for power supply model N-2ARPS-A6.
James A. FitzPatrick (JAF) reviewed the work order instructions to determine if there was a deviation from the recommendations in the Foxboro technical manual F180-0309 Spec 200 Multinest Power Supply 2ARPS Series calibration. Since as-found voltage readings were within the required tolerance of the RHR instrument loops, the power supplies appear to have been capable to perform their intended function. However, this evaluation did not troubleshoot why the power supplies failed to meet the calibration requirements.
Two instrument power supplies for the "B" Residual Heat Removal (RHR) system were being bench tested prior to installation when it was discovered that they failed to meet Vendor Technical Manual specifications for voltage stability for varying loads. The deviation was a voltage drop of approximately 300mV. This did not meet the specification of <150mV when varying current from 5 amps (full load) to 2.5 amps. A second replacement power supply exhibited a similar 300 mV drop. James A. FitzPatrick (JAF) reviewed the work order instructions to determine if there was a deviation from the recommendations in the Foxboro technical manual F180-0309 Spec 200 Multinest Power Supply 2ARPS Series calibration.
The power supplies were sent to a repair vendor. The input from this vendor is expected to allow JAF to complete the evaluation per 10 CFR 21.21 (a)(1) by March 21, 2017, and a notification for failure to comply or defect per 10 CFR 21.21 (d)(3)(i) is expected by March 24, 2017, if necessary. This notification is being submitted as an interim report per 10 CFR 21.21 (a)(2).
Since as-found voltage readings were within the required tolerance of the RHR instrument loops, the power supplies appear to have been capable to perform their intended function.
NOTIFICATIONS                      YES      NO        WILL BE        ANYTHING UNUSUAL OR NOT UNDERSTOOD?
However, this evaluation did not troubleshoot why the power supplies failed to meet the calibration requirements.
D YES      (Explain above)        [{]NO NRC RESIDENT                        0        D            D STATE(s)                            D        0            D          DID ALL SYSTEMS
The power supplies were sent to a repair vendor. The input from this vendor is expected to allow JAF to complete the evaluation per 10 CFR 21.21 (a)(1) by March 21, 2017, and a notification for failure to comply or defect per 10 CFR 21.21 (d)(3)(i) is expected by March 24, 2017, if necessary.
[{]YES                            D NO      (Explain above)
This notification is being submitted as an interim report per 10 CFR 21.21 (a)(2). NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR D YES (Explain above) [{]NO NRC RESIDENT 0 D D NOT UNDERSTOOD?
LOCAL OTHER GOV AGENCIES D
STATE(s) D 0 D DID ALL SYSTEMS [{]YES D NO (Explain above) LOCAL D 0 D FUNCTION AS REQUIRED?
D 0
OTHER GOV AGENCIES D 0 D MODE OF OPERATION I ESTIMATED I ADDITIONAL INFO ON BACK RESTART DATE: MEDIA/PRESS RELEASE D 0 D UNTIL CORRECTED: (MM/DD/YYYY)
0 D
DYES 0 NO NRG FORM 361 (12-2000)
D FUNCTION AS REQUIRED?
PAGE 1 OF 2}}
MODE OF OPERATION UNTIL CORRECTED:
IESTIMATED RESTART DATE:
I  ADDITIONAL INFO ON BACK 0
MEDIA/PRESS RELEASE                 D         0             D                                               (MM/DD/YYYY)                       DYES                     NO NRG FORM 361 (12-2000)                                                                                                                                                 PAGE 1 OF 2}}

Latest revision as of 20:45, 4 February 2020

Part 21 - Failure of Power Supplies to Meet Voltage Stability Specifications
ML17026A413
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 01/11/2017
From: Mark Hawes
Entergy Nuclear Operations
To:
Office of Nuclear Reactor Regulation
References
52480
Download: ML17026A413 (2)
v • d • e


Text

0111112017 . U.S. Nuclear Regulatory Commission Operations Center Event Report Pagel Power Reactor Event# 52480 Site: FITZPATRICK Notification Date I Time: 01/10/2017 22:45 (EST)

Unit: 1 Region: 1 State: NY Event Date I Time: 11/10/2016 16:04 (EST)

Reactor Type: [1] GE-4 Last Modification: 01/10/2017 Containment Type: MARK I NRC Notified by: MARK HAW.ES Notifications: ANTHONY DIMITRIADIS R1DO HQ Ops Officer: DONALD NORWOOD PART 21/50.55 REACTOREMAIL Emergency Class: NON EMERGENCY 10 CFR Section:

21.21(a)(2) INTERIM EVAL OF DEVIATION Unit Scram Code RX Crit lnit Power Initial RX Mode Curr Power Current RX Mode 1 N Yes 67 Power Operation 67 Power Operation PART 21 - FAILURE OF POWER SUPPLIES TO MEET VOLTAGE STABILITY SPECIFICATIONS "This notification is a 10 CFR 21.21 (a)(2) interim report for power supply model N-2ARPS-A6. Two instrument power supplies for the 'B' Residual Heat Removal (RHR) system were being bench tested prior to installation when it was discovered that they failed to meet Vendor Technical Manual specifications for voltage stability for varying loads. The deviation was a voltage drop of approximately 300mV. This did not meet the specification of less than 150mV when varying current from 5 amps (full load) to 2.5 amps. A second replacement power supply exhibited a similar 300 mV drop.

"James A. FitzPatrick (JAF) reviewed the work order instructions to determine if there was a deviation from the recommendations in the Foxboro technical manual F180-0309 Spec 200 Multinest Power Supply 2ARPS Series calibration. Since as-found voltage readings were within the required tolerance of the RHR instrument loops, the power supplies appear to have been capable to perform their intended function. However, this evaluation did not troubleshoot why the power supplies failed to meet the calibration requirements.*

"The power supplies were sent to a repair vendor. The input from this vendor is expected to allow JAF to complete the evaluation per 10 CFR 21.21 (a)(1) by March 21, 2017, and a notification for failure to comply or defect per 10 CFR 21.21(d)(3)(i) is expected by March 24, 2017, if necessary. This notification is being submitted as an interim report per 10 CFR 21.21 (a)(2)."

The licensee notified the NRC Resident Inspector.

NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION (12-2000) OPERATIONS CENTER REACTOR PLANT EVENT NOTIFICATION WORKSHEET EN 52480 NRC OPERATION TELEPHONE NUMBER: PRIMARY -- 301-816-5100 or 800-532-3469*, BACKUPS -- [1st] 301-951-0550 or 800-449-3694*,

[2nd] 301-415-0550 and [3rd] 301-415-0553 *Licensees who maintain their own ETS are orovided these telephone numbers.

NOTIFICATION TIME FACILITY OR ORGANIZATION UNIT NAME OF CALLER CALL BACK#

2245 EST James A. FitzPatrick 1 Mark Hawes (315) 349-6664 EVENT TIME & ZONE EVENT DATE POWER/MODE BEFORE POWER/MODE AFTER 16:04 ET 11/10/2016 67% I Mode 1 67% I Mode 1 EVENT CLASSIFICATIONS 1-Hr. Non-Emergency 10 CFR 50.72(b)(1) D (v)(A) Safe S/D Capability AINA D GENERAL EMERGENCY GEN/AAEC D TS Deviation ADEV D (v)(B) RHR Capability AINB D SITE AREA EMERGENCY SIT/AAEC 4-Hr. Non-Emeraencv 10 CFR 50.72CblC2l D (v)(C) Control of Rad Release AINC D ALERT ALE/AAEC D (i) TS Required S/D ASHU D (v)(D) Accident Mitigation AIND D UNUSUAL EVENT UNU/AAEC D (iv)(A) ECCS Discharge to RCS ACCS D (xii) Offsite Medical AMED D 50.72 NON-EMERGENCY (see next columns) D (iv)(B) RPS.Actuation (scram) ARPS D (xiii) Loss Comm/Asmt/Resp ACOM D PHYSICAL SECURITY (73.71) DDDD D (xi) Offsite Notification APRE 60-Day Optional 10 CFR 50.73(a)(1)

D MATERIAL/EXPOSURE B??? 8-Hr. Non-Emeraencv 10 CFR 50.72Cb)(3) D Invalid Specified System Actuation AINV D FITNESS FOR DUTY HFIT D (ii)(A) Degraded Condition ADEG Other Unspecified Requirement (Identify) 0 OTHER UNSPECIFIED REQMT. (see last column) D (ii)(B) Unanalyzed Condition AUNA 1ZJ 10CFR21.21(a)(2) NONR D INFORMATION ONLY NINF D (iv)(A) Specified System Actuation AESF D NONR DESCRIPTION Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc. (Continue on back)

This notification is a 10 CFR 21.21 (a)(2) interim report for power supply model N-2ARPS-A6. Two instrument power supplies for the "B" Residual Heat Removal (RHR) system were being bench tested prior to installation when it was discovered that they failed to meet Vendor Technical Manual specifications for voltage stability for varying loads. The deviation was a voltage drop of approximately 300mV. This did not meet the specification of <150mV when varying current from 5 amps (full load) to 2.5 amps.

A second replacement power supply exhibited a similar 300 mV drop.

James A. FitzPatrick (JAF) reviewed the work order instructions to determine if there was a deviation from the recommendations in the Foxboro technical manual F180-0309 Spec 200 Multinest Power Supply 2ARPS Series calibration. Since as-found voltage readings were within the required tolerance of the RHR instrument loops, the power supplies appear to have been capable to perform their intended function. However, this evaluation did not troubleshoot why the power supplies failed to meet the calibration requirements.

The power supplies were sent to a repair vendor. The input from this vendor is expected to allow JAF to complete the evaluation per 10 CFR 21.21 (a)(1) by March 21, 2017, and a notification for failure to comply or defect per 10 CFR 21.21 (d)(3)(i) is expected by March 24, 2017, if necessary. This notification is being submitted as an interim report per 10 CFR 21.21 (a)(2).

NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR NOT UNDERSTOOD?

D YES (Explain above) [{]NO NRC RESIDENT 0 D D STATE(s) D 0 D DID ALL SYSTEMS

[{]YES D NO (Explain above)

LOCAL OTHER GOV AGENCIES D

D 0

0 D

D FUNCTION AS REQUIRED?

MODE OF OPERATION UNTIL CORRECTED:

IESTIMATED RESTART DATE:

I ADDITIONAL INFO ON BACK 0

MEDIA/PRESS RELEASE D 0 D (MM/DD/YYYY) DYES NO NRG FORM 361 (12-2000) PAGE 1 OF 2

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