ML17090A400

Fitzpatrick - Part 21 - Failure of Power Supplies to Meet Voltage Stability Specifications

ML17090A400
Person / Time
Site:	FitzPatrick
Issue date:	03/24/2017
From:	Mark Hawes Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
52480
Download: ML17090A400 (4)

Text

0312412017 U.S. Nuclear Regulatory Commission Operations Center Event Report Pagel ***This Event has been retracted

!!! ***This Event has been retracted!!!

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:

03/23/2017 Containment Type: MARK I NRC Notified by: MARK HAWES 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 Grit lnit Power Initial RX Mode Curr Power Current RX Mode 1 N Yes 67 Power Operation 67 I 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 Multi nest 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.

• • • RETRACTED AT 1705 EDT ON 03/23/17 FROM MARK HAWES TO S. SANDIN***

The licensee is retracting this report based on the following:

0312412017 U.S. Nuclear Regulatory Commission Operations Center Event Report Pagel "The testing vendor Argo Turboserve Corp provided input to this condition in Non Conformance Report NC161. Engineering reviewed NC161 and discussed this condition with the vendor. The power supplies showed an initial drift following a 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> burn-in but continued operation was stable. Therefore, even though the initial voltage drift did not meet the power supply's calibration requirement in F180-0309, it would not be expected to drift significantly further.

Engineering concluded that this condition will have a negligible impact on system components.

Readings were steady and within the tolerance of the RHR instrument specification.

Based on all current information, the component will function over its mission time of 100 days. "Based on these results, a notification for failure to comply or defect per 10 CFR 21.21 (d)(3)(i) is not required and the interim report per 10 CFR 21.21(a)(2) may be retracted."

The licensee informed the NRC Resident Inspector.

Notified R1 DO (Bickett) and Part 21 Group via email. ***********************************************************************************************************************************

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 provided 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 SID 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-Emergency 10 CFR 50.72(b)(2)

D (v)(C) Control of Rad Release AINC D ALERT ALE/AA EC D (i) TS Required SID ASHLI D (v)(O) 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-Emergency 10 CFR 50.72(b)(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 0 10 CFR 21.21 (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 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 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 D YES (Explain above) [{]NO NRC RESIDENT 0 D D NOT UNDERSTOOD?

STATE(s)

D 0 D DID ALL SYSTEMS [{]YES D NO (Explair,i above) LOCAL D 0 D FUNCTION AS REQUIRED?

OTHER GOV AGENCIES D 0 D MODE OF OPERATION I ESTIMATED I ADDITIONAL INFO ON BACK D 0 D UNTIL CORRECTED:

RESTART DATE: DYES 0 NO MEDIA/PRESS RELEASE (MM/DD/YYYY)

NRC FORM 361 (12-2000)

PAGE 1OF2 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 provided 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-Emergency 10 CFR 50.72(b}(2)

D (v)(C) Control of Rad Release AINC D ALERT ALE/AA EC D (i) TS Required SID 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/AsmVResp ACOM D PHYSICAL SECURITY (73.71) DDDD D (xi) Offsite Notification APRE 60-Day Optional 10 CFR 50.73(a)(1)

D MATERiALIEXPOSURE B??? 8-Hr. Non-Emergency 10 CFR 50.72(b)(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 0 10 CFR 21.21 (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 instrumEfnt 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 D YES (Explain above) [{JN01 NRC RESIDENT 0 D D NOT UNDERSTOOD?

J STATE(s)

D 0 D DID ALL SYSTEMS [{]YES D NO (Explain above) LOCAL D 0 D FUNCTION AS REQUIRED?

\ OTHER GOV AGENCIES D 0 D MODE OF OPERATION I ESTIMATED I ADDITIONAL INFO ON BACK D 0 D UNTIL CORRECTED:

RESTART DATE: DYES 0 NO MEDIA/PRESS RELEASE (MM/DD/YYYY)

NRC FORM 361 (12-2000)

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