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{{#Wiki_filter:0912712012 U.S. Nuclear Regulatory Commission Operations Center Event Report Paze I Power Reactor Event# 48353 Site: FITZPATRICK Notification Date /Time: 09/27/2012 22:17 (EDT)Unit: 1 Region: 1 State: NY Event Date / Time: 09/27/2012 12:12 (EDT)Reactor Type: [1] GE-4 Last Modification:
{{#Wiki_filter:0912712012                     U.S. Nuclear Regulatory Commission OperationsCenter Event Report                       Paze I Power Reactor                                                                                     Event#       48353 Site: FITZPATRICK                               Notification Date /Time: 09/27/2012       22:17   (EDT)
09/27/2012 Containment Type: MARK I NRC Notified by: JORGE O'FARRILL Notifications:
Unit: 1             Region: 1     State: NY         Event Date / Time: 09/27/2012       12:12   (EDT)
RONALD BELLAMY R1DO HQ Ops Officer: MARK ABRAMOVITZ PART 21 GROUP Emergency Class: NON EMERGENCY 10 CFR Section: 21.21 (d)(3)(i)
Reactor Type:   [1] GE-4                                         Last Modification: 09/27/2012 Containment Type:       MARK I NRC Notified by: JORGE O'FARRILL                                   Notifications: RONALD BELLAMY               R1DO HQ Ops Officer: MARK ABRAMOVITZ                                                   PART 21 GROUP Emergency Class: NON EMERGENCY 10 CFR Section:
DEFECTS AND NONCOMPLIANCE Unit Scram Code RX Crit Init Power [Initial RX Mode Curr Power Current RX Mode 1 N Yes 92 Power Operation 100 Power Operation PART-21 REPORT -FAULTY MASTER TRIP UNITS, SLAVE UNITS, AND RESISTANCE TEMPERATURE DETECTORS"On September 27, 2012, the Site Vice President was notified that a 1OCFR21 evaluation of thirteen (13) reworked Master Trip Units, Resistance Temperature Detector Units, and Slave Units supplied by Rosemount Nuclear Instruments, Inc. (Rosemount) determined that a non-compliant condition involving a basic component existed."Rosemount informed James A. FitzPatrick Nuclear Power Plant (JAF) that 13 reworked Master Trip Units, Resistance Temperature Detector (RTD) Units and Slave Units were received at JAF which did not comply with their rebuild repair specification.
21.21 (d)(3)(i)       DEFECTS AND NONCOMPLIANCE Unit Scram Code         RX Crit Init Power [Initial RX Mode               Curr Power Current RX Mode 1           N           Yes   92           Power Operation             100           Power Operation PART-21 REPORT - FAULTY MASTER TRIP UNITS, SLAVE UNITS, AND RESISTANCE TEMPERATURE DETECTORS "On September 27, 2012, the Site Vice President was notified that a 10CFR21 evaluation of thirteen (13) reworked Master Trip Units, Resistance Temperature Detector Units, and Slave Units supplied by Rosemount Nuclear Instruments, Inc. (Rosemount) determined that a non-compliant condition involving a basic component existed.
Specifically, epoxy was not applied under certain resistors as required.
"Rosemount informed James A. FitzPatrick Nuclear Power Plant (JAF) that 13 reworked Master Trip Units, Resistance Temperature Detector (RTD) Units and Slave Units were received at JAF which did not comply with their rebuild repair specification. Specifically, epoxy was not applied under certain resistors as required. In accordance with JA FitzPatrick plant procedures, this condition was determined as a 10CFRPart 21 condition involving a defect in a basic component.
In accordance with JA FitzPatrick plant procedures, this condition was determined as a 1OCFRPart 21 condition involving a defect in a basic component."As noted by an engineering review, some of the applications for the trip units require them to energize to perform the associated safety functions.
"As noted by an engineering review, some of the applications for the trip units require them to energize to perform the associated safety functions. Therefore, a failure occurrence by an installed non-conforming unit could potentially have an adverse affect on the associated systems' safety/accident mitigation functions.
Therefore, a failure occurrence by an installed non-conforming unit could potentially have an adverse affect on the associated systems' safety/accident mitigation functions."JAF verified that none of the 13 deficient units were installed in any plant systems. Therefore, this condition had no actual safety consequences as the deficiency was identified by Rosemount prior to installation.
"JAF verified that none of the 13 deficient units were installed in any plant systems. Therefore, this condition had no actual safety consequences as the deficiency was identified by Rosemount prior to installation. The 13 units that were received at JAF without the epoxy have been returned to Rosemount for the addition of the epoxy and have subsequently been reworked and returned to JAF.
The 13 units that were received at JAF without the epoxy have been returned to Rosemount for the addition of the epoxy and have subsequently been reworked and returned to JAF."This notification is made pursuant to 10CFR21.21(d)(3)(i)." 0 61 0110--
"This notification is made pursuant to 10CFR21.21(d)(3)(i)."
NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION (12-2000)
0 0110-- 61
OPERATIONS CENTER REACTOR PLANT EVENT NOTIFICATION WORKSHEET EN # L48 3 5-3 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 #O1 1-7 -.i-r James A. FitzPatrick 1 Jorge L. O'Farrill (315) 349-6793 EVENT TIME & ZONE EVENT DATE POWERIMODE BEFORE POWER/MODE AFTER 12:12 pm EST 07/27/2012 92% Power -Mode 1 100% Power -Model 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 #       L48 3 5-3 NRC OPERATION TELEPHONE NUMBER: PRIMARY -- 301-816-5100 or 800-532-3469', BACKUPS- [1st] 301-951-0550 or 800-449-3694",
[] (v)(A) Safe SID Capability AINA O GENERAL EMERGENCY
(2nd] 301-415-0550 and [3rd] 301-415-0553                                                           'Licensees who maintain their own ETS are provided these telephone numbers.
* GEN/AAEC r31 TS Deviation AOEV E] (v)(B) RHR Capability AINB-SITE AREA EMERGENCY SITIAAEC 4-Hr. Non-Emergency 10 CFR 50.72(b)(2)
NOTIFICATION TIME         FACILITY OR ORGANIZATION                                 UNIT               NAME OF CALLER                                 CALL BACK #
D (v)(C) Control of Rad Release AINC-l ALERT ALE/AAEC El (i) TS Required S/D ASHU rl (v)(0) Accident Mitigation AiND 5 UNUSUAL EVENT UNU/AAEC 00 iv)(A) ECCS Discharge to RCS ACCS 5 (xii) Offsite Medical AMED O 50.72 NON-EMERGENCY (see next columns) 5 (ivXB) RPS Actuation (scram) ARPS Q] (xili) Loss Comm/AsmtlResp ACOM 5 PHYSICAL SECURITY (73.71) DODD 5 (xi) Offsite Notificalion APRE 60-Day Optional 10 CFR 50.73(a)(1)
O1 1-7         i-r
O MATERIALUEXPOSURE B??? 8-Hr. Non-Emergency 10 CFR 50.72(b)(3) nvalid Specified System Actuation AINV O FITNESS FOR DUTY HFIT 5 (IiXA) Degraded Condition ADEG Other Unspecified Requirement (Identify)
                    -. James A. FitzPatrick                                     1                 Jorge L. O'Farrill                                     (315) 349-6793 EVENT TIME & ZONE         EVENT DATE                           POWERIMODE BEFORE                                             POWER/MODE AFTER 12:12 pm EST                   07/27/2012                     92% Power - Mode 1                                             100% Power - Model EVENT CLASSIFICATIONS                                     1-Hr. Non-Emergency 10 CFR 50.72(b)(1)                     [] (v)(A)   Safe SID Capability                 AINA O   GENERAL EMERGENCY
C OTHER.UNSPECIFIEDREOMT. (see last column) 5 (ii)(B) Unanalyzed Condition AUNA 0 10CFR 21.21(d)(3)(i)
* GEN/AAEC         r31             TS Deviation                           AOEV   E] (v)(B)   RHR Capability                       AINB
NONR Cl INFORMATION ONLY NINF El] (iv)A) Specified System Actuation AESF NONR DESCRIPTION Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc. (Continue on back)On September 27, 2012, the Site Vice President was notified that a 10 CFR 21 evaluation of thirteen (13) reworked Master Trip Units, Resistance Temperature Detector Units, and Slave Units supplied by Rosemount Nuclear Instruments, Inc. (Rosemount) determined that a non-compliant condition involving a basic component existed.Rosemount informed James A. FitzPatrick Nuclear Power Plant (JAF) that 13 reworked Master Trip Units, Resistance Temperature Detector (RTD) Units and Slave Units were received at JAF which did not comply with their rebuild repair specification.
  -   SITE AREA EMERGENCY                       SITIAAEC             4-Hr. Non-Emergency 10 CFR 50.72(b)(2)                     D   (v)(C) Control of Rad Release               AINC
Specifically, epoxy was not applied under certain resistors as required.
  -l ALERT                                     ALE/AAEC         El   (i)       TS Required S/D                       ASHU rl (v)(0)     Accident Mitigation                 AiND 5   UNUSUAL EVENT                             UNU/AAEC               00 iv)(A)   ECCS Discharge to RCS                 ACCS   5   (xii)   Offsite Medical                     AMED O   50.72 NON-EMERGENCY               (see next columns)       5     (ivXB)     RPS Actuation (scram)                 ARPS   Q] (xili) Loss Comm/AsmtlResp                 ACOM 5   PHYSICAL SECURITY (73.71)                       DODD       5     (xi)       Offsite Notificalion                   APRE         60-Day Optional 10 CFR 50.73(a)(1)
In accordance with JA FitzPatrick plant procedures, this condition was determined as a 10 CFR Part 21 condition involving a defect in a basic component.
O   MATERIALUEXPOSURE                                 B???         8-Hr. Non-Emergency 10 CFR 50.72(b)(3)                                 nvalid Specified System Actuation   AINV O   FITNESS FOR DUTY                                   HFIT     5     (IiXA)     Degraded Condition                     ADEG     Other Unspecified Requirement (Identify)
As noted by an engineering review, some of the applications for the trip units require them to energize to perform the associated safety functions.
C   OTHER.UNSPECIFIEDREOMT.             (see last column)       5     (ii)(B)   Unanalyzed Condition                   AUNA   0   10CFR 21.21(d)(3)(i)                       NONR Cl INFORMATION ONLY                                 NINF     El] (iv)A)       Specified System Actuation             AESF                                                   NONR DESCRIPTION Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc. (Continue on back)
Therefore, a failure occurrence by an installed non-conforming unit could potentially have an adverse affect on the associated systems' safety/accident mitigation functions.
On September 27, 2012, the Site Vice President was notified that a 10 CFR 21 evaluation of thirteen (13) reworked Master Trip Units, Resistance Temperature Detector Units, and Slave Units supplied by Rosemount Nuclear Instruments, Inc. (Rosemount) determined that a non-compliant condition involving a basic component existed.
JAF verified that none of the 13 deficient units were installed in any plant systems. Therefore, this condition had no actual safety consequences as the deficiency was identified by Rosemount prior to installation.
Rosemount informed James A. FitzPatrick Nuclear Power Plant (JAF) that 13 reworked Master Trip Units, Resistance Temperature Detector (RTD) Units and Slave Units were received at JAF which did not comply with their rebuild repair specification. Specifically, epoxy was not applied under certain resistors as required. In accordance with JA FitzPatrick plant procedures, this condition was determined as a 10 CFR Part 21 condition involving a defect in a basic component.
The 13 units that were received at JAF without the epoxy have been returned to Rosemount for the addition of the epoxy and have subsequently been reworked and returned to JAF This notification is made pursuant to 10 CFR 21.21(d)(3)(i).
As noted by an engineering review, some of the applications for the trip units require them to energize to perform the associated safety functions. Therefore, a failure occurrence by an installed non-conforming unit could potentially have an adverse affect on the associated systems' safety/accident mitigation functions.
NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR NRC RESIDENT ] .NOT UNDERSTOOD?
JAF verified that none of the 13 deficient units were installed in any plant systems. Therefore, this condition had no actual safety consequences as the deficiency was identified by Rosemount prior to installation. The 13 units that were received at JAF without the epoxy have been returned to Rosemount for the addition of the epoxy and have subsequently been reworked and returned to JAF This notification is made pursuant to 10 CFR 21.21(d)(3)(i).
O YES (Explain above) NO STATE(s) ...... .. ...... .DID ALL SYSTEMS YES LOCAL __ _ FUNCTION AS REQUIRED?
NOTIFICATIONS                       YES       NO         WILL BE           ANYTHING UNUSUAL OR NRC RESIDENT                                                 .    ]           NOT UNDERSTOOD?             O           YES (Explain above)             NO STATE(s)       ......                             ..   ......   .           DID ALL SYSTEMS                         YES
NO (Explain above)OTHER GOV AGENCIES El ._I MODE OF OPERATION ESTIMATED ADDITIONAL INFO ON BACK MEDIA/PRESS RELEASE ..... --- --- Ul UNTIL CORRECTED:
__               _                             FUNCTION AS REQUIRED?                                                   NO (Explain above)
MRESTART DATE: El YES [ NO IX i1-UI-YYiy C] YES-2XNO~NRC FORM 361 (12-2000)I PAGE 1 OF 2}}
LOCAL OTHER GOV AGENCIES                     El               .         _I       MODE OF OPERATION                   ESTIMATED                       ADDITIONAL INFO ON BACK MEDIA/PRESS RELEASE             ..... ---             -
                                                      --                     UNTIL Ul   CORRECTED:                            DATE:
MRESTART                   El     YES             [   NO i1-UI-YYiy IX                              C]   YES-2XNO~
NRC FORM 361 (12-2000)I PAGE 1 OF 2}}

Latest revision as of 20:07, 11 November 2019

Part-21 Report - Faulty Master Trip Units, Slave Units, and Resistance Temperature Detectors
ML12319A011
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 09/27/2012
From: O'Farrill J
FitzPatrick, Lentz & Bubba, PC
To:
Office of Nuclear Reactor Regulation
References
48353
Download: ML12319A011 (2)
v • d • e


Text

0912712012 U.S. Nuclear Regulatory Commission OperationsCenter Event Report Paze I Power Reactor Event# 48353 Site: FITZPATRICK Notification Date /Time: 09/27/2012 22:17 (EDT)

Unit: 1 Region: 1 State: NY Event Date / Time: 09/27/2012 12:12 (EDT)

Reactor Type: [1] GE-4 Last Modification: 09/27/2012 Containment Type: MARK I NRC Notified by: JORGE O'FARRILL Notifications: RONALD BELLAMY R1DO HQ Ops Officer: MARK ABRAMOVITZ PART 21 GROUP Emergency Class: NON EMERGENCY 10 CFR Section:

21.21 (d)(3)(i) DEFECTS AND NONCOMPLIANCE Unit Scram Code RX Crit Init Power [Initial RX Mode Curr Power Current RX Mode 1 N Yes 92 Power Operation 100 Power Operation PART-21 REPORT - FAULTY MASTER TRIP UNITS, SLAVE UNITS, AND RESISTANCE TEMPERATURE DETECTORS "On September 27, 2012, the Site Vice President was notified that a 10CFR21 evaluation of thirteen (13) reworked Master Trip Units, Resistance Temperature Detector Units, and Slave Units supplied by Rosemount Nuclear Instruments, Inc. (Rosemount) determined that a non-compliant condition involving a basic component existed.

"Rosemount informed James A. FitzPatrick Nuclear Power Plant (JAF) that 13 reworked Master Trip Units, Resistance Temperature Detector (RTD) Units and Slave Units were received at JAF which did not comply with their rebuild repair specification. Specifically, epoxy was not applied under certain resistors as required. In accordance with JA FitzPatrick plant procedures, this condition was determined as a 10CFRPart 21 condition involving a defect in a basic component.

"As noted by an engineering review, some of the applications for the trip units require them to energize to perform the associated safety functions. Therefore, a failure occurrence by an installed non-conforming unit could potentially have an adverse affect on the associated systems' safety/accident mitigation functions.

"JAF verified that none of the 13 deficient units were installed in any plant systems. Therefore, this condition had no actual safety consequences as the deficiency was identified by Rosemount prior to installation. The 13 units that were received at JAF without the epoxy have been returned to Rosemount for the addition of the epoxy and have subsequently been reworked and returned to JAF.

"This notification is made pursuant to 10CFR21.21(d)(3)(i)."

0 0110-- 61

NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION (12-2000) OPERATIONS CENTER REACTOR PLANT EVENT NOTIFICATION WORKSHEET EN # L48 3 5-3 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 #

O1 1-7 i-r

-. James A. FitzPatrick 1 Jorge L. O'Farrill (315) 349-6793 EVENT TIME & ZONE EVENT DATE POWERIMODE BEFORE POWER/MODE AFTER 12:12 pm EST 07/27/2012 92% Power - Mode 1 100% Power - Model EVENT CLASSIFICATIONS 1-Hr. Non-Emergency 10 CFR 50.72(b)(1) [] (v)(A) Safe SID Capability AINA O GENERAL EMERGENCY

  • GEN/AAEC r31 TS Deviation AOEV E] (v)(B) RHR Capability AINB

- SITE AREA EMERGENCY SITIAAEC 4-Hr. Non-Emergency 10 CFR 50.72(b)(2) D (v)(C) Control of Rad Release AINC

-l ALERT ALE/AAEC El (i) TS Required S/D ASHU rl (v)(0) Accident Mitigation AiND 5 UNUSUAL EVENT UNU/AAEC 00 iv)(A) ECCS Discharge to RCS ACCS 5 (xii) Offsite Medical AMED O 50.72 NON-EMERGENCY (see next columns) 5 (ivXB) RPS Actuation (scram) ARPS Q] (xili) Loss Comm/AsmtlResp ACOM 5 PHYSICAL SECURITY (73.71) DODD 5 (xi) Offsite Notificalion APRE 60-Day Optional 10 CFR 50.73(a)(1)

O MATERIALUEXPOSURE B??? 8-Hr. Non-Emergency 10 CFR 50.72(b)(3) nvalid Specified System Actuation AINV O FITNESS FOR DUTY HFIT 5 (IiXA) Degraded Condition ADEG Other Unspecified Requirement (Identify)

C OTHER.UNSPECIFIEDREOMT. (see last column) 5 (ii)(B) Unanalyzed Condition AUNA 0 10CFR 21.21(d)(3)(i) NONR Cl INFORMATION ONLY NINF El] (iv)A) Specified System Actuation AESF NONR DESCRIPTION Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc. (Continue on back)

On September 27, 2012, the Site Vice President was notified that a 10 CFR 21 evaluation of thirteen (13) reworked Master Trip Units, Resistance Temperature Detector Units, and Slave Units supplied by Rosemount Nuclear Instruments, Inc. (Rosemount) determined that a non-compliant condition involving a basic component existed.

Rosemount informed James A. FitzPatrick Nuclear Power Plant (JAF) that 13 reworked Master Trip Units, Resistance Temperature Detector (RTD) Units and Slave Units were received at JAF which did not comply with their rebuild repair specification. Specifically, epoxy was not applied under certain resistors as required. In accordance with JA FitzPatrick plant procedures, this condition was determined as a 10 CFR Part 21 condition involving a defect in a basic component.

As noted by an engineering review, some of the applications for the trip units require them to energize to perform the associated safety functions. Therefore, a failure occurrence by an installed non-conforming unit could potentially have an adverse affect on the associated systems' safety/accident mitigation functions.

JAF verified that none of the 13 deficient units were installed in any plant systems. Therefore, this condition had no actual safety consequences as the deficiency was identified by Rosemount prior to installation. The 13 units that were received at JAF without the epoxy have been returned to Rosemount for the addition of the epoxy and have subsequently been reworked and returned to JAF This notification is made pursuant to 10 CFR 21.21(d)(3)(i).

NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR NRC RESIDENT . ] NOT UNDERSTOOD? O YES (Explain above) NO STATE(s) ...... .. ...... . DID ALL SYSTEMS YES

__ _ FUNCTION AS REQUIRED? NO (Explain above)

LOCAL OTHER GOV AGENCIES El . _I MODE OF OPERATION ESTIMATED ADDITIONAL INFO ON BACK MEDIA/PRESS RELEASE ..... --- -

-- UNTIL Ul CORRECTED: DATE:

MRESTART El YES [ NO i1-UI-YYiy IX C] YES-2XNO~

NRC FORM 361 (12-2000)I PAGE 1 OF 2

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