ML17090A400: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(2 intermediate revisions by the same user not shown)
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:0312412017 U.S. Nuclear Regulatory Commission Operations Center Event Report Pagel ***This Event has been retracted  
{{#Wiki_filter:0312412017                     U.S. Nuclear Regulatory Commission Operations Center Event Report                   Pagel
!!! ***This Event has been retracted!!!
      ***This Event has been retracted !!!                       ***This Event has been retracted!!!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:
Power Reactor                                                                               Event#         52480 Site: FITZPATRICK                               Notification Date I Time: 01/10/2017   22:45 (EST)
03/23/2017 Containment Type: MARK I NRC Notified by: MARK HAWES 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) 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.
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 ,
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.
Emergency Class: NON EMERGENCY 10 CFR Section:
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.
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.
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.
  "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.
This notification is being submitted as an interim report per 10 CFR 21.21(a)(2)." The licensee notified the NRC Resident Inspector.  
  "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)."
***RETRACTED AT 1705 EDT ON 03/23/17 FROM MARK HAWES TO S. SANDIN***
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:
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 hour 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.
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.
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.
Engineering reviewed NC161 and discussed this condition with the vendor. The power supplies showed an initial drift following a 100 hour 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.
Notified R1 DO (Bickett) and Part 21 Group via email. ***********************************************************************************************************************************
"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."
NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION (12-2000)
The licensee informed the NRC Resident Inspector. Notified R1 DO (Bickett) and Part 21 Group via email.
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)
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*,
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)
[2nd] 301-415-0550 and [3rd] 301-415-0553                                                    *Licensees who maintain their own ETS are provided these telephone numbers.
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)
NOTIFICATION TIME          FACILITY OR ORGANIZATION                          UNIT              NAME OF CALLER                                        CALL BACK#
D MATERIAL/EXPOSURE B??? 8-Hr. Non-Emergency 10 CFR 50.72(b)(3)
2245 EST            James A. FitzPatrick                              1                Mark Hawes                                                    (315) 349-6664 EVENT TIME & ZONE          EVENT DATE                      POWER/MODE BEFORE                                                POWER/MODE AFTER
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.
*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)
Two instrument
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)
: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.
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.
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.
A second replacement power supply exhibited a similar 300 mV drop.
However, this evaluation did not troubleshoot why the power supplies failed to meet the calibration requirements.
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 instrume~t 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.
The power supplies were sent to a repair                .
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?
vendor. The input from this vendor is expected to allow JAF to complete                          . \
STATE(s) D 0 D DID ALL SYSTEMS [{]YES D NO (Explair,i above) LOCAL D 0 D FUNCTION AS REQUIRED?
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.
OTHER GOV AGENCIES D 0 D MODE OF OPERATION I ESTIMATED I ADDITIONAL INFO ON BACK D 0 D UNTIL CORRECTED:
expected by March ~4. 2017, if necessary. This notification is being submitted as an interim report per 10 CFR 21.21 (a)(2).
RESTART DATE: DYES 0 NO MEDIA/PRESS RELEASE (MM/DD/YYYY)
NOTIFICATIONS                      YES      NO          WILL BE      ANYTHING UNUSUAL OR NOT UNDERSTOOD?
NRC FORM 361 (12-2000)
D    YES (Explain above)            [{]NO NRC RESIDENT                        0        D            D STATE(s)                             D        0            D          DID ALL SYSTEMS
PAGE 1OF2 NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION (12-2000)
[{]YES                              D  NO (Explair,i above)
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
FUNCTION AS REQUIRED?
*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)
LOCAL OTHER GOV AGENCIES D
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 0
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)
0 D
D MATERiALIEXPOSURE B??? 8-Hr. Non-Emergency 10 CFR 50.72(b)(3)
D        MODE OF OPERATION                    IESTIMATED RESTART DATE:
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.
IADDITIONAL INFO ON BACK MEDIA/PRESS RELEASE                  D        0            D UNTIL CORRECTED:
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.
(MM/DD/YYYY)                         DYES                0  NO NRC FORM 361 (12-2000)
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.
PAGE 1OF2
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.
NRC FORM 361                                                                                                                        U.S. NUCLEAR REGULATORY COMMISSION (12-2000)                                                                                                                                         OPERATIONS CENTER
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) [{JN0 1 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?
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*,
\ OTHER GOV AGENCIES D 0 D MODE OF OPERATION I ESTIMATED I ADDITIONAL INFO ON BACK D 0 D UNTIL CORRECTED:
[2nd] 301-415-0550 and [3rd] 301-415-0553                                                    *Licensees who maintain their own ETS are provided these telephone numbers.
RESTART DATE: DYES 0 NO MEDIA/PRESS RELEASE (MM/DD/YYYY)
*NOTIFICATION TIME          FACILITY OR ORGANIZATION                          UNIT              NAME OF CALLER                                        CALL BACK#
NRC FORM 361 (12-2000)
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 NRC RESIDENT                        0        D ANYTHING UNUSUAL OR NOT UNDERSTOOD?
D YES      (Explain above)
J
[{JN0    1 D
STATE(s)                             D        0             D         DID ALL SYSTEMS
[{]YES                              D NO      (Explain above)   \
0                        FUNCTION AS REQUIRED?
LOCAL OTHER GOV AGENCIES D
D        0 D
D         MODE OF OPERATION                    IESTIMATED RESTART DATE:
I ADDITIONAL INFO ON BACK MEDIA/PRESS RELEASE                D       0             D UNTIL CORRECTED:
(MM/DD/YYYY)                       DYES                 0   NO NRC FORM 361 (12-2000)
PAGE 1OF2}}
PAGE 1OF2}}

Latest revision as of 18:15, 4 February 2020

Part 21 - Failure of Power Supplies to Meet Voltage Stability Specifications
ML17090A400
Person / Time
Site: FitzPatrick Constellation icon.png
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)
v • d • e


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 instrume~t 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 ~4. 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 (Explair,i above)

FUNCTION AS REQUIRED?

LOCAL OTHER GOV AGENCIES D

D 0

0 D

D MODE OF OPERATION IESTIMATED RESTART DATE:

IADDITIONAL INFO ON BACK MEDIA/PRESS RELEASE D 0 D UNTIL CORRECTED:

(MM/DD/YYYY) DYES 0 NO 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 NRC RESIDENT 0 D ANYTHING UNUSUAL OR NOT UNDERSTOOD?

D YES (Explain above)

J

[{JN0 1 D

STATE(s) D 0 D DID ALL SYSTEMS

[{]YES D NO (Explain above) \

0 FUNCTION AS REQUIRED?

LOCAL OTHER GOV AGENCIES D

D 0 D

D MODE OF OPERATION IESTIMATED RESTART DATE:

I ADDITIONAL INFO ON BACK MEDIA/PRESS RELEASE D 0 D UNTIL CORRECTED:

(MM/DD/YYYY) DYES 0 NO NRC FORM 361 (12-2000)

PAGE 1OF2

Retrieved from "https://kanterella.com/w/index.php?title=ML17090A400&oldid=2439774"