Information Notice 1995-05, Undervoltage Protection Relay Settings Out of Tolerance Due to Test Equipment Harmonics: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
Line 16: Line 16:
{{#Wiki_filter:UNITED STATES
{{#Wiki_filter:UNITED STATES


NUCLEAR REGULATORY COMMISSION
===NUCLEAR REGULATORY COMMISSION===
OFFICE OF NUCLEAR REACTOR REGULATION
 
WASHINGTON, D.C.


OFFICE OF NUCLEAR REACTOR REGULATION
20555


WASHINGTON, D.C. 20555 January 20, 1995 NRC INFORMATION NOTICE 95-05:   UNDERVOLTAGE PROTECTION RELAY SETTINGS OUT OF
===January 20, 1995===
NRC INFORMATION NOTICE 95-05: UNDERVOLTAGE PROTECTION RELAY SETTINGS OUT OF


TOLERANCE DUE TO TEST EQUIPMENT HARMONICS
===TOLERANCE DUE TO TEST EQUIPMENT HARMONICS===


==Addressees==
==Addressees==
Line 51: Line 55:


===Dresden Nuclear Power Station===
===Dresden Nuclear Power Station===
On April 11, 1994, during routine calibration of the Dresden Unit 3 Asea Brown
On April 11,  
1994, during routine calibration of the Dresden Unit 3 Asea Brown


Boveri (ABB) Model ITE 27N undervoltage relays, both relays were found to be
Boveri (ABB) Model ITE 27N undervoltage relays, both relays were found to be
Line 63: Line 68:
The test source was diagnosed and verified, using an oscilloscope, as having a
The test source was diagnosed and verified, using an oscilloscope, as having a


distortion on the positive side of the single-phase 120-Vac sine wave. In
distortion on the positive side of the single-phase 120-Vac sine wave.
 
In


addition, further evaluation showed that the Unit 2 degraded voltage relays
addition, further evaluation showed that the Unit 2 degraded voltage relays
Line 85: Line 92:
pickup/dropout operating points to shift high at radiation levels above those
pickup/dropout operating points to shift high at radiation levels above those


ppR                         '/
ppR
9501120037 I(f
 
'/
9501120037 I (f
 
I
 
I
 
K


===I I                    K===
IN 95-05 January 20, 1995 affecting the time delay, but below 630 Gy (6.3E04 rad). In response to the
                                                                IN 95-05 January 20, 1995 affecting the time delay, but below 630 Gy (6.3E04 rad). In response to the


notification, the licensee modified the 27N relays in accordance with the
notification, the licensee modified the 27N relays in accordance with the
Line 102: Line 116:


Before this event, the voltage test source was classified as a 'general usage"
Before this event, the voltage test source was classified as a 'general usage"
    piece of test equipment; its electrical output characteristics, therefore, were not periodically verified. After this event, as a corrective action, the
piece of test equipment; its electrical output characteristics, therefore, were not periodically verified. After this event, as a corrective action, the


licensee added the ac voltage test source to a general surveillance program.
licensee added the ac voltage test source to a general surveillance program.
Line 114: Line 128:
certified and general usage to determine if other vulnerabilities exist.
certified and general usage to determine if other vulnerabilities exist.


Comanche Peak Steam Electric Station
===Comanche Peak Steam Electric Station===
 
On May 23, 1994, Comanche Peak Unit 2, was in Mode 5 during its mid-cycle
On May 23, 1994, Comanche Peak Unit 2, was in Mode 5 during its mid-cycle


Line 126: Line 139:
dropouts were found to be 1 to 3 V outside the expected values. These relays
dropouts were found to be 1 to 3 V outside the expected values. These relays


were adjusted to correct setting values. Following this discovery and
were adjusted to correct setting values.


===Following this discovery and===
corrective action, the licensee performed a comprehensive root cause
corrective action, the licensee performed a comprehensive root cause


Line 139: Line 153:


and Train B relay actuation settings using a clean (low harmonic distortion)
and Train B relay actuation settings using a clean (low harmonic distortion)
    ac power supply. On May 28, 1994, during the reverification process, it
ac power supply. On May 28, 1994, during the reverification process, it


appeared that five of the Train A relays, Types ITE-27N and ITE-27H, were
appeared that five of the Train A relays, Types ITE-27N and ITE-27H, were
Line 151: Line 165:
harmonic distortion for testing these types of relays.
harmonic distortion for testing these types of relays.


Point Beach Nuclear Plant
===Point Beach Nuclear Plant===
 
In February 1994, the Point Beach licensee replaced the installed Type 27D
In February 1994, the Point Beach licensee replaced the installed Type 27D


Line 201: Line 214:
indicated above, the licensees used ac voltage test sources which were
indicated above, the licensees used ac voltage test sources which were


subsequently found to have high harmonic distortion. During relay
subsequently found to have high harmonic distortion.


===During relay===
calibration, a calibrated digital voltmeter (DVM) was used to measure the
calibration, a calibrated digital voltmeter (DVM) was used to measure the


Line 213: Line 227:
caused by harmonic distortion does not result in an equivalent change in the
caused by harmonic distortion does not result in an equivalent change in the


RMS voltage as indicated by the DVM. The relay operating point is
RMS voltage as indicated by the DVM.


===The relay operating point is===
significantly influenced by its peak voltage detection circuitry. Therefore, if the voltage test source power supply is not included in a calibration
significantly influenced by its peak voltage detection circuitry. Therefore, if the voltage test source power supply is not included in a calibration


Line 223: Line 238:
Using harmonic filters in the 27N relays will attenuate both ac voltage test
Using harmonic filters in the 27N relays will attenuate both ac voltage test


source harmonics and system harmonics. However, ABB pointed out that the
source harmonics and system harmonics.


===However, ABB pointed out that the===
harmonic filter option could cause the pickup/dropout operating points to
harmonic filter option could cause the pickup/dropout operating points to


shift high at radiation levels below the testing end point of 630 Gy
shift high at radiation levels below the testing end point of 630 Gy


(6.3E04 rad). In addition, ABB documentation indicates that using the
(6.3E04 rad).
 
In addition, ABB documentation indicates that using the


harmonic distortion filter option increases the repeatability tolerance of the
harmonic distortion filter option increases the repeatability tolerance of the
Line 255: Line 273:
Nuclear Reactor Regulation (NRR) project manager.
Nuclear Reactor Regulation (NRR) project manager.


Brian K. Grimes, Director
===Brian K. Grimes, Director===
Division of Project Support
 
===Office of Nuclear Reactor Regulation===
Technical contacts:
 
===D. Nguyen, NRR===
(301) 504-3202
 
===D. Butler, RIII===
(708) 829-9720


Division of Project Support
===F. Ashe, NRR===
(301) 504-2785


Office of Nuclear Reactor Regulation
===D. Skeen, NRR===
(301) 504-1174 Attachment:


Technical contacts:  D. Nguyen, NRR            D. Butler, RIII
===List of Recently Issued===
4~47cl


(301) 504-3202            (708) 829-9720
flew
                    F. Ashe, NRR              D. Skeen, NRR


(301) 504-2785            (301) 504-1174 Attachment:
===Information Notices===
tI"
_.,4te


===List of Recently Issued Information Notices===
IN 95-05 January 20, 1995 This information notice requires no specific action or written response.
4~47cl        flew    tI"  _.,4te


IN 95-05 January 20, 1995 This information notice requires no specific action or written response. If
If


you have any questions about the information in this notice, please contact
you have any questions about the information in this notice, please contact
Line 279: Line 310:
Nuclear Reactor Regulation (NRR) project manager.
Nuclear Reactor Regulation (NRR) project manager.


Original signed by Brian K. GVimes
===Original signed by Brian K. GVimes===
Brian K. Grimes, Director


Brian K. Grimes, Director
===Division of Project Support===
Office of Nuclear Reactor Regulation


Division of Project Support
Technical contacts:


Office of Nuclear Reactor Regulation
===D. Nguyen, NRR===
(301) 504-3202


Technical contacts:    D. Nguyen, NRR                  D. Butler, RIII
===D. Butler, RIII===
(708) 829-9720


(301) 504-3202                  (708) 829-9720
===F. Ashe, NRR===
                        F. Ashe, NRR                    D. Skeen, NRR
(301) 504-2785


(301) 504-2785                  (301) 504-1174 Attachment:
===D. Skeen, NRR===
(301) 504-1174 Attachment:


===List of Recently Issued Information Notices===
===List of Recently Issued Information Notices===
DOCUMENT NAME:   95-05.IN
DOCUMENT NAME:
95-05.IN


* PREVIOUS CONCURRENCE
* PREVIOUS CONCURRENCE


OFC     OECB:DOPS       SC/OECB:DOPS     PUB:ADM             EELB:DE
OFC
 
OECB:DOPS
 
SC/OECB:DOPS
 
PUB:ADM
 
EELB:DE
 
NAME
 
DSkeen*
RDennig/EFG*
MMejac*
DNguyen*
DATE
 
12/19/94
,12/21/94
12/13/94
12/19/94 OFC
 
EELB:DE
 
R-III:DRS
 
C/EELB:DE
 
OECB:DOPS
 
NAME
 
FAshe*
DButler*EMAIL


NAME    DSkeen*         RDennig/EFG*    MMejac*              DNguyen*
CBerlinger*  
  DATE   12/19/94      ,12/21/94          12/13/94            12/19/94 OFC    EELB:DE          R-III:DRS        C/EELB:DE          OECB:DOPS
RKiessel*
DATE


NAME    FAshe*          DButler*EMAIL    CBerlinger*        RKiessel*
12/20/94  
  DATE    12/20/94         112/20/94         12/21/94 _         12/22/94 OFC     C/OECB:DOPS      D        /
112/20/94  
  NAME    AChaffee*        16ifme
12/21/94 _  
12/22/94 OFC


DATE 112/27/94         j1/1-d95
C/OECB:DOPS
  [OFFICIAL RECORD COPY]
 
D
 
/
NAME
 
AChaffee*
16ifme
 
DATE 112/27/94 j1/1-d95
[OFFICIAL RECORD COPY]


K)
K)
-                                                                       IN 94-XX
-
IN 94-XX


December XX, 1994 This information notice requires no specific action or written response. If
===December XX, 1994===
This information notice requires no specific action or written response. If


you have any questions about the information in this notice, please contact
you have any questions about the information in this notice, please contact
Line 322: Line 407:
Nuclear Reactor Regulation (NRR) project manager.
Nuclear Reactor Regulation (NRR) project manager.


Brian K. Grimes, Director
===Brian K. Grimes, Director===
Division of Project Support
 
===Office of Nuclear Reactor Regulation===
Technical contacts:
 
===D. Nguyen, NRR===
(301) 504-3202
 
===D. Butler, RIII===
(708) 829-9720


Division of Project Support
===F. Ashe, NRR===
(301) 504-2785


Office of Nuclear Reactor Regulation
===D. Skeen, NRR===
(301) 504-1174 Attachment: List of Recently Issued Information Notices


Technical contacts:           D. Nguyen, NRR              D. Butler, RIII
DOCUMENT NAME:
S:\\DOPS_SEC\\IN94-XX.DST


(301) 504-3202              (708) 829-9720
*
                                F. Ashe, NRR                D. Skeen, NRR


(301) 504-2785              (301) 504-1174 Attachment:        List of Recently Issued Information Notices
===DDrUTMlIC rfnmriioDPrwr===
OFC


DOCUMENT NAME:       S:\DOPS_SEC\IN94-XX.DST
OECB:DOPS


*  DDrUTMlIC  rfnmriioDPrwr
SC/OECB:DOPS


OFC      OECB:DOPS            SC/OECB:DOPS    PUB:ADM         EELB:DE
PUB:ADM


NAME    DSkeen*              RDennig/EFG*    MMejac*          DNguyen*
EELB:DE
      DATE      12/19/94            12/21/94        12/13/94        12/19/94 IOFC


NAME
NAME
DSkeen*
RDennig/EFG*
MMejac*
DNguyen*
DATE
12/19/94
12/21/94
12/13/94
12/19/94 IOFC


EELB:DE
EELB:DE


FAshe*
R-III:DRS
                                    R-III:DRS
 
C/EELB:DE
 
OECB:DOPS
 
NAME


FAshe*
DButler*EMAIL
DButler*EMAIL


C/EELB:DE
CBerlinger*
RKiessel*
DATE
 
12/20/94
12/20/94
1
12/21/94
12/22/94 OFC
 
C/OECB:DOPS
 
D/DOPS


CBerlinger*
NAME
                                                                    OECB:DOPS


RKiessel*
AChaffee*  
      DATE      12/20/94            12/20/94      112/21/94        12/22/94 OFC      C/OECB:DOPS        D/DOPS
BGrimes


NAME    AChaffee*            BGrimes
DATE 1
12/27/94
/
/94
'OFFICIAL RECORD COPY]


DATE    1 12/27/94              /  /94
K.
    'OFFICIAL RECORD COPY]


K.          IN 94-XX
IN 94-XX


Month XX, 1994 This information notice requires no specific action or written response. If
Month XX, 1994 This information notice requires no specific action or written response. If
Line 376: Line 504:
Nuclear Reactor Regulation (NRR) project manager.
Nuclear Reactor Regulation (NRR) project manager.


Brian K. Grimes, Director
===Brian K. Grimes, Director===
 
Division of Operating Reactor Support
Division of Operating Reactor Support


Office of Nuclear Reactor Regulation
===Office of Nuclear Reactor Regulation===
 
Technical contacts:
Technical contacts:   D. Nguyen, NRR


(301) 504-3202 F. Ashe, NRR
===D. Nguyen, NRR===
(301) 504-3202


(301) 504-2785 D. Butler, RIII
===F. Ashe, NRR===
(301) 504-2785


===D. Butler, RIII===
(708) 829-9720
(708) 829-9720
                      D. Skeen, NRR


(301) 504-1174 Attachment:   List of Recently Issued NRC Information Notices
===D. Skeen, NRR===
(301) 504-1174 Attachment:


===List of Recently Issued NRC Information Notices===
* PREVIOUS CONCURRENCE
* PREVIOUS CONCURRENCE


OFC     OECB:DOPS       l+   EC 0OPS       PUB:ADM     l EELB:DE
OFC
 
OECB:DOPS
 
l +  
EC 0OPS
 
PUB:ADM
 
l EELB:DE
 
NAME


NAME    DSkeen                         I MMejac*        DNguyen 7k
DSkeen


DATE  lt//¶/94          [2 /al/94          12/13/94 I
I MMejac*
DNguyen 7k


DATE lt//¶/94
[2 /al/94
12/13/94
__4__________
__4__________
  OFC    EELB:DE          R-11I:D S Agm      C/EEIaD al    OECB:DOP
I


NAME    FAshe  S10-      DButler 'f        CBerlinger    RKiessel
OFC


DATE  ___    _o/94_  _  A/J94      *  - /611'/94 OFC    C/OECB:DOPS      D/DORS        l
EELB:DE
 
R-11I:D S Agm C/EEIa
 
D l


NAME    AChaffep)V'      BGrimes        l
OECB:DOP


DATE   APL/.27/94         / /94
a
 
NAME
 
FAshe S10-
DButler 'f
 
CBerlinger
 
RKiessel
 
DATE
 
__ _
_o/94_
_ A/J94
-
*
/611 '/94 OFC
 
C/OECB:DOPS
 
D/DORS
 
l
 
NAME
 
AChaffep) V '
BGrimes
 
l
 
DATE
 
APL/.27/94  
/  
/94
[OFFICIAL RECORD COPY]
[OFFICIAL RECORD COPY]
DOCUMENT NAME: G:\DLS\IN94-XX.DST
DOCUMENT NAME:  
G:\\DLS\\IN94-XX.DST


11_.     V , _
11_.
                                                              Attachment


IN 95-05 January 20, 1995 LIST OF RECENTLY ISSUED
V , _
Attachment


IN 95-05
===January 20, 1995 LIST OF RECENTLY ISSUED===
NRC INFORMATION NOTICES
NRC INFORMATION NOTICES


Information                                 Date of
Information


Notice No.            Subject                Issuance  Issued to
Date of


95-04          Excessive Cooldown and        01/19/95  All holders of OLs or CPs
Notice No.


Depressurization of the                  for nuclear power reactors.
Subject


Reactor Coolant System
Issuance


Following a Loss of
Issued to
 
95-04
95-03
95-02
95-01
94-90
94-89
94-88


Offsite Power
===Excessive Cooldown and===
Depressurization of the


95-03          Loss of Reactor Coolant       01/18/95  All holders of Ols or CPs
===Reactor Coolant System===
Following a Loss of


Inventory and Potential                  for nuclear power reactors.
===Offsite Power===
Loss of Reactor Coolant


===Inventory and Potential===
Loss of Emergency Mitiga- tion Functions While in
Loss of Emergency Mitiga- tion Functions While in


a Shutdown Condition
a Shutdown Condition


95-02          Problems with General         01/17/95    All holders of OLs or CPs
===Problems with General===
 
Electric CR2940 Contact
Electric CR2940 Contact                   for nuclear power reactors.


Blocks in Medium-Voltage
Blocks in Medium-Voltage


Circuit Breakers
===Circuit Breakers===
 
DOT Safety Advisory:
95-01          DOT Safety Advisory:         01/04/95    All U.S. Nuclear Regulatory
 
High Pressure Aluminum                    Commission licensees.


===High Pressure Aluminum===
Seamless and Aluminum
Seamless and Aluminum


Line 461: Line 660:
Cylinders
Cylinders


94-90          Transient Resulting in a       12/30/94  All holders of OLs or CPs
===Transient Resulting in a===
Reactor Trip and Multiple
 
===Safety Injection System===
Actuations at Salem
 
===Equipment Failures at===
Irradiator Facilities


Reactor Trip and Multiple                for nuclear power reactors.
===Inservice Inspection===
Deficiencies Result in


Safety Injection System
===Severely Degraded Steam===
Generator Tubes


Actuations at Salem
01/19/95
01/18/95
01/17/95
01/04/95
12/30/94
12/28/94
12/23/94
 
===All holders of OLs or CPs===
for nuclear power reactors.


94-89          Equipment Failures at          12/28/94  All U.S. Nuclear Regulatory
===All holders of Ols or CPs===
for nuclear power reactors.


Irradiator Facilities                    Commission irradiator
===All holders of OLs or CPs===
for nuclear power reactors.


licensees.
===All U.S. Nuclear Regulatory===
Commission licensees.


94-88          Inservice Inspection          12/23/94  All holders of OLs or CPs
===All holders of OLs or CPs===
for nuclear power reactors.


Deficiencies Result in                    for pressurized water
===All U.S. Nuclear Regulatory===
Commission irradiator


Severely Degraded Steam                  reactors.
licensees.


Generator Tubes
===All holders of OLs or CPs===
for pressurized water
 
reactors.


OL - Operating License
OL - Operating License


CP - Construction Permit}}
CP -
Construction Permit}}


{{Information notice-Nav}}
{{Information notice-Nav}}

Latest revision as of 10:49, 16 January 2025

Undervoltage Protection Relay Settings Out of Tolerance Due to Test Equipment Harmonics
ML031060397
Person / Time
Site: Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane  Entergy icon.png
Issue date: 01/20/1985
From: Grimes B
Office of Nuclear Reactor Regulation
To:
References
IN-95-005, NUDOCS 9501120037
Download: ML031060397 (8)


UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C.

20555

January 20, 1995

NRC INFORMATION NOTICE 95-05: UNDERVOLTAGE PROTECTION RELAY SETTINGS OUT OF

TOLERANCE DUE TO TEST EQUIPMENT HARMONICS

Addressees

All holders of operating licenses or construction permits for nuclear power

reactors.

PurDose

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information

notice to alert addressees that undervoltage relay settings could be out of

tolerance because of test equipment harmonics. It is expected that recipients

will review the information for applicability to their facilities and consider

actions, as appropriate, to avoid similar problems. However, suggestions

contained in this information notice are not NRC requirements; therefore, no

specific action or written response is required.

Description of Circumstances

The following occurrences indicate that test equipment harmonics could result

in undervoltage relay actuation settings that are out of tolerance.

Dresden Nuclear Power Station

On April 11,

1994, during routine calibration of the Dresden Unit 3 Asea Brown

Boveri (ABB) Model ITE 27N undervoltage relays, both relays were found to be

out of tolerance. Additional testing of the 27N relay showed that the relay

operating point was influenced by the polarity of the lead wires from the

voltage test source (power supply) producing the sinusoidal voltage signal.

The test source was diagnosed and verified, using an oscilloscope, as having a

distortion on the positive side of the single-phase 120-Vac sine wave.

In

addition, further evaluation showed that the Unit 2 degraded voltage relays

had also been calibrated using the same power supply in October 1992 and

April 1993.

The Dresden 27N relays were originally equipped with a harmonic filter and

time delay circuit. However, in 1992, ABB notified the NRC, pursuant to

Part 21 of Title 10 of the Code of Federal Regulations, that the relay time

delay circuit could fail to initiate the appropriate time delay when exposed

to radiation levels between 22.5 and 45 Gray (Gy) (2.25E03 and 4.5E03 rad). In

addition, ABB indicated that the harmonic filter option could cause the

pickup/dropout operating points to shift high at radiation levels above those

ppR

'/

9501120037 I (f

I

I

K

IN 95-05 January 20, 1995 affecting the time delay, but below 630 Gy (6.3E04 rad). In response to the

notification, the licensee modified the 27N relays in accordance with the

instructions of the manufacturer to remove the harmonic filter and time delay

components. The licensee is now replacing the 27N relays with 27N-R relays

for second-level undervoltage protection. The 27N-R relay is equipped with

radiation-resistant harmonic filter and time delay circuitry.

Before this event, the voltage test source was classified as a 'general usage"

piece of test equipment; its electrical output characteristics, therefore, were not periodically verified. After this event, as a corrective action, the

licensee added the ac voltage test source to a general surveillance program.

The test source output characteristics are now verified annually to meet

manufacturer specifications. In addition the licensee is performing a review

of electrical and electronic measuring and testing equipment for both

certified and general usage to determine if other vulnerabilities exist.

Comanche Peak Steam Electric Station

On May 23, 1994, Comanche Peak Unit 2, was in Mode 5 during its mid-cycle

outage. During the performance of the Train A undervoltage relay calibration

and response time surveillance testing, 14 of 16 relays were found to be

outside their respective allowable technical specification values. The relay

dropouts were found to be 1 to 3 V outside the expected values. These relays

were adjusted to correct setting values.

Following this discovery and

corrective action, the licensee performed a comprehensive root cause

evaluation. This evaluation showed that the testing device used to calibrate

the undervoltage relays did not provide accurate as-found data, because of

harmonic distortion that affected peak values of the ac testing voltage

waveform. From May 26 to May 28, 1994, the licensee reverified both Train A

and Train B relay actuation settings using a clean (low harmonic distortion)

ac power supply. On May 28, 1994, during the reverification process, it

appeared that five of the Train A relays, Types ITE-27N and ITE-27H, were

outside the technical specification values using the most conservative data.

To preclude recurrence, the corrective action taken by the licensee was to

implement a procedural change to require the use of a power source with low

harmonic distortion for testing these types of relays.

Point Beach Nuclear Plant

In February 1994, the Point Beach licensee replaced the installed Type 27D

degraded voltage relays with Type 27N. The 27N relays were more accurate and

had an adjustable reset. These relays were recently recalibrated, and all 12 were found to have "drifted' approximately 0.5 V high (120-V base). Although

the drift did not exceed calibration tolerances, the licensee had not

previously experienced similar calibration shifts for the 27D relays. A

further investigation by the licensee showed that the calibration shift was

attributed to harmonics present in the ac test voltage power source. The

licensee noted that the relays were not sensitive to harmonic frequencies,

IN 95-05 January 20, 1995 but were sensitive to harmonic amplitudes. The licensee measured the harmonic

distortion attendant to the ac voltage test source and the safeguards buses, and concluded that the relay operating point was affected by the harmonic

distortion of both the ac voltage test source and the safeguards buses when

supplied by the offsite power system. Because the system harmonics may vary, the licensee is installing the harmonic filters in all of the 27N degraded

voltage relays. The harmonic filters will attenuate harmonics attendant to

the ac voltage test source and the offsite power system.

Discussion

All three occurrences were attributed to test equipment harmonics. When the

harmonic filters were removed from the 27N relays at Dresden, harmonic

distortion in an ac voltage source waveform had a noticeable effect on relay

operating point. The 27N relay uses a peak detector circuit. This peak

detector circuit samples half of the voltage source waveform and measures its

peak value. Although the peak detector circuit is very accurate, it is

sensitive to harmonic distortion. The relay manufacturer (ABB) recommends an

ac voltage test source with less than 0.3 percent harmonic distortion. As

indicated above, the licensees used ac voltage test sources which were

subsequently found to have high harmonic distortion.

During relay

calibration, a calibrated digital voltmeter (DVM) was used to measure the

relay input voltage to determine its trip setpoint. The DVM measures the root

mean square (RMS) value of the ac voltage test source sinusoidal waveform.

A change in the peak voltage of the ac voltage test source sinusoidal waveform

caused by harmonic distortion does not result in an equivalent change in the

RMS voltage as indicated by the DVM.

The relay operating point is

significantly influenced by its peak voltage detection circuitry. Therefore, if the voltage test source power supply is not included in a calibration

program, the DVM may not accurately reflect the setpoint of the solid-state

relay.

Using harmonic filters in the 27N relays will attenuate both ac voltage test

source harmonics and system harmonics.

However, ABB pointed out that the

harmonic filter option could cause the pickup/dropout operating points to

shift high at radiation levels below the testing end point of 630 Gy

(6.3E04 rad).

In addition, ABB documentation indicates that using the

harmonic distortion filter option increases the repeatability tolerance of the

relays as a function of temperature variations. As documented in ABB

Instructions IB 7.4.1.7-7 Issue D for Type 27N relays, temperature variations, such as -20 to +700C (-4 to 158'F), increase the relay repeatability tolerance

from +/-0.7 to +/-1.5 percent of relay pickup and dropout settings. Therefore, adding the harmonic filter option may necessitate revising the undervoltage

relay setpoint calculations. If harmonic filters are not used, system

harmonics can be determined and the test source harmonic distortion matched to

the system harmonic distortion within the tolerance band to ensure that relays

pick up and drop out at required system setpoints.

IN 95-05 January 20, 1995 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Project Support

Office of Nuclear Reactor Regulation

Technical contacts:

D. Nguyen, NRR

(301) 504-3202

D. Butler, RIII

(708) 829-9720

F. Ashe, NRR

(301) 504-2785

D. Skeen, NRR

(301) 504-1174 Attachment:

List of Recently Issued

4~47cl

flew

Information Notices

tI"

_.,4te

IN 95-05 January 20, 1995 This information notice requires no specific action or written response.

If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Original signed by Brian K. GVimes

Brian K. Grimes, Director

Division of Project Support

Office of Nuclear Reactor Regulation

Technical contacts:

D. Nguyen, NRR

(301) 504-3202

D. Butler, RIII

(708) 829-9720

F. Ashe, NRR

(301) 504-2785

D. Skeen, NRR

(301) 504-1174 Attachment:

List of Recently Issued Information Notices

DOCUMENT NAME:

95-05.IN

  • PREVIOUS CONCURRENCE

OFC

OECB:DOPS

SC/OECB:DOPS

PUB:ADM

EELB:DE

NAME

DSkeen*

RDennig/EFG*

MMejac*

DNguyen*

DATE

12/19/94

,12/21/94

12/13/94

12/19/94 OFC

EELB:DE

R-III:DRS

C/EELB:DE

OECB:DOPS

NAME

FAshe*

DButler*EMAIL

CBerlinger*

RKiessel*

DATE

12/20/94

112/20/94

12/21/94 _

12/22/94 OFC

C/OECB:DOPS

D

/

NAME

AChaffee*

16ifme

DATE 112/27/94 j1/1-d95

[OFFICIAL RECORD COPY]

K)

-

IN 94-XX

December XX, 1994

This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Project Support

Office of Nuclear Reactor Regulation

Technical contacts:

D. Nguyen, NRR

(301) 504-3202

D. Butler, RIII

(708) 829-9720

F. Ashe, NRR

(301) 504-2785

D. Skeen, NRR

(301) 504-1174 Attachment: List of Recently Issued Information Notices

DOCUMENT NAME:

S:\\DOPS_SEC\\IN94-XX.DST

DDrUTMlIC rfnmriioDPrwr

OFC

OECB:DOPS

SC/OECB:DOPS

PUB:ADM

EELB:DE

NAME

DSkeen*

RDennig/EFG*

MMejac*

DNguyen*

DATE

12/19/94

12/21/94

12/13/94

12/19/94 IOFC

EELB:DE

R-III:DRS

C/EELB:DE

OECB:DOPS

NAME

FAshe*

DButler*EMAIL

CBerlinger*

RKiessel*

DATE

12/20/94

12/20/94

1

12/21/94

12/22/94 OFC

C/OECB:DOPS

D/DOPS

NAME

AChaffee*

BGrimes

DATE 1

12/27/94

/

/94

'OFFICIAL RECORD COPY]

K.

IN 94-XX

Month XX, 1994 This information notice requires no specific action or written response. If

you have any questions about the information in this notice, please contact

one of the technical contacts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Brian K. Grimes, Director

Division of Operating Reactor Support

Office of Nuclear Reactor Regulation

Technical contacts:

D. Nguyen, NRR

(301) 504-3202

F. Ashe, NRR

(301) 504-2785

D. Butler, RIII

(708) 829-9720

D. Skeen, NRR

(301) 504-1174 Attachment:

List of Recently Issued NRC Information Notices

  • PREVIOUS CONCURRENCE

OFC

OECB:DOPS

l +

EC 0OPS

PUB:ADM

l EELB:DE

NAME

DSkeen

I MMejac*

DNguyen 7k

DATE lt//¶/94

[2 /al/94

12/13/94

__4__________

I

OFC

EELB:DE

R-11I:D S Agm C/EEIa

D l

OECB:DOP

a

NAME

FAshe S10-

DButler 'f

CBerlinger

RKiessel

DATE

__ _

_o/94_

_ A/J94

-

/611 '/94 OFC

C/OECB:DOPS

D/DORS

l

NAME

AChaffep) V '

BGrimes

l

DATE

APL/.27/94

/

/94

[OFFICIAL RECORD COPY]

DOCUMENT NAME:

G:\\DLS\\IN94-XX.DST

11_.

V , _

Attachment

IN 95-05

January 20, 1995 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information

Date of

Notice No.

Subject

Issuance

Issued to

95-04

95-03

95-02

95-01

94-90

94-89

94-88

Excessive Cooldown and

Depressurization of the

Reactor Coolant System

Following a Loss of

Offsite Power

Loss of Reactor Coolant

Inventory and Potential

Loss of Emergency Mitiga- tion Functions While in

a Shutdown Condition

Problems with General

Electric CR2940 Contact

Blocks in Medium-Voltage

Circuit Breakers

DOT Safety Advisory:

High Pressure Aluminum

Seamless and Aluminum

Composite Hoop-Wrapped

Cylinders

Transient Resulting in a

Reactor Trip and Multiple

Safety Injection System

Actuations at Salem

Equipment Failures at

Irradiator Facilities

Inservice Inspection

Deficiencies Result in

Severely Degraded Steam

Generator Tubes

01/19/95

01/18/95

01/17/95

01/04/95

12/30/94

12/28/94

12/23/94

All holders of OLs or CPs

for nuclear power reactors.

All holders of Ols or CPs

for nuclear power reactors.

All holders of OLs or CPs

for nuclear power reactors.

All U.S. Nuclear Regulatory

Commission licensees.

All holders of OLs or CPs

for nuclear power reactors.

All U.S. Nuclear Regulatory

Commission irradiator

licensees.

All holders of OLs or CPs

for pressurized water

reactors.

OL - Operating License

CP -

Construction Permit