Information Notice 1986-50, Inadequate Testing to Detect Failures of Safety-Related Pneumatic Components or Systems: Difference between revisions

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{{#Wiki_filter:ORIGINAL                             SSINS No.: 6835 IN 86-50
{{#Wiki_filter:ORIGINAL
                                  UNITED STATES.


NUCLEAR REGULATORY COMMISSION
SSINS No.: 6835 IN 86-50
UNITED STATES.


===NUCLEAR REGULATORY COMMISSION===
OFFICE OF INSPECTION AND ENFORCEMENT
OFFICE OF INSPECTION AND ENFORCEMENT


WASHINGTON,,D.C. 20555 June 18, 1986 IE INFORMATION NOTICE NO. 86-50:   INADEQUATE TESTING TO-DETECT FAILURES OF
WASHINGTON,,D.C.
 
20555
 
===June 18, 1986===
IE INFORMATION NOTICE NO. 86-50:  
INADEQUATE TESTING TO-DETECT FAILURES OF


SAFETY-RELATED PNEUMATIC COMPONENTS OR
SAFETY-RELATED PNEUMATIC COMPONENTS OR
Line 39: Line 46:
problem pertaining to inadequate testing practice relating to air operated
problem pertaining to inadequate testing practice relating to air operated


valves. The NRC expects that recipients will review this notice for applica- bility to their facilities. However, suggestions contained in this notice do
valves.
 
The NRC expects that recipients will review this notice for applica- bility to their facilities.


===However, suggestions contained in this notice do===
not constitute NRC requirements; therefore, no specific action or written
not constitute NRC requirements; therefore, no specific action or written


Line 49: Line 59:


Gradual Loss of Air Pressure," July 20, 1982 IE Information Notice No. 85-35,- '.Failure of Air Check Valves to Seat,"
Gradual Loss of Air Pressure," July 20, 1982 IE Information Notice No. 85-35,- '.Failure of Air Check Valves to Seat,"
  April 30, 1985 IE Information Notice No. 85-84, "Inadequate Inservice Testing of Main
 
===April 30, 1985===
IE Information Notice No. 85-84, "Inadequate Inservice Testing of Main


Steam Isolation Valves," October 30, 1985 IE Information Notice No. 85-94, 'Potential for Loss of Minimum Flow
Steam Isolation Valves," October 30, 1985 IE Information Notice No. 85-94, 'Potential for Loss of Minimum Flow
Line 65: Line 77:
control air pressure decreased slowly rather than rapidly as would be expected
control air pressure decreased slowly rather than rapidly as would be expected


for an air line break. In the case of IN 85-35, the fault was exposed by a
for an air line break.
 
In the case of IN 85-35, the fault was exposed by a


loss of offsite power test, and in the case of IN 82-25, the fault was exposed
loss of offsite power test, and in the case of IN 82-25, the fault was exposed


by a preoperational test designed .to simulate a slow air leak. In both cases,
by a preoperational test designed .to simulate a slow air leak.
                                                    8606160044
 
In both cases,
8606160044


IN 86-50
IN 86-50
                                                                  June 18, 1986 the components in question--an accumulator isolation check valve (IN 85-35) and
June 18, 1986 the components in question--an accumulator isolation check valve (IN 85-35) and


pneumatic selector valves (IN 82-25)--were not tested adequately. Several
pneumatic selector valves (IN 82-25)--were not tested adequately.


recent events have indicated continuing problems of similar nature. These
Several
 
recent events have indicated continuing problems of similar nature.
 
These


events are discussed below.
events are discussed below.
Line 85: Line 105:
NRC a concern that the component cooling water (CCW) system might fail to meet
NRC a concern that the component cooling water (CCW) system might fail to meet


its functional requirements for a design-basis accident. One part of the
its functional requirements for a design-basis accident.


concern involved the CCW heat exchanger outlet control valve. This valve
===One part of the===
concern involved the CCW heat exchanger outlet control valve.


regulates flow of intake cooling water (ICW) to this heat exchanger. Loss of
This valve
 
regulates flow of intake cooling water (ICW) to this heat exchanger.
 
Loss of


control air, coincident with a loss of offsite power, a valid engineered
control air, coincident with a loss of offsite power, a valid engineered
Line 95: Line 120:
safeguards features (ESF) actuation signal, and a loss of an emergency diesel
safeguards features (ESF) actuation signal, and a loss of an emergency diesel


generator (EDG) would cause this valve to fail closed. If this happened, the
generator (EDG) would cause this valve to fail closed.


CCW heat exchanger would not receive sufficient flow of ICW. This situation
===If this happened, the===
CCW heat exchanger would not receive sufficient flow of ICW.


was discovered during a design review of the ICW system. Earlier disclosure
===This situation===
was discovered during a design review of the ICW system.


===Earlier disclosure===
might have been possible if ICW operation had been considered or tested with
might have been possible if ICW operation had been considered or tested with


Line 111: Line 139:
air-operated valves in the safety injection (SI) pump minimum-flow recircula- tion line from the pump discharge to the refueling water storage tank (RWST).
air-operated valves in the safety injection (SI) pump minimum-flow recircula- tion line from the pump discharge to the refueling water storage tank (RWST).


This concern evolved from review of IN 85-94. Two such valves had been insert- ed in series in this line and had been designed to fail closed on loss of
This concern evolved from review of IN 85-94.


non-safety-related air or loss of electrical power to the valves. The purpose
Two such valves had been insert- ed in series in this line and had been designed to fail closed on loss of


of the valves is to protect the RWST (outside containment) from highly radioac- tive reactor coolant during the long-term circulation phase of accident recov- ery. In the event of SI initiation under small-break loss-of-coolant-accident
non-safety-related air or loss of electrical power to the valves.
 
The purpose
 
of the valves is to protect the RWST (outside containment) from highly radioac- tive reactor coolant during the long-term circulation phase of accident recov- ery.
 
In the event of SI initiation under small-break loss-of-coolant-accident


conditions concurrent with closure of either of these valves, the SI pumps
conditions concurrent with closure of either of these valves, the SI pumps
Line 121: Line 155:
would be operating with no flow until reactor pressure decreased below their
would be operating with no flow until reactor pressure decreased below their


shutoff head. This would damage the SI pumps after only a short time. The
shutoff head.
 
This would damage the SI pumps after only a short time.
 
The


licensee's remedy was to put mechanical blocks on the air operators so the
licensee's remedy was to put mechanical blocks on the air operators so the
Line 139: Line 177:
not have closed against system pressure. The other two PORVs had their normal
not have closed against system pressure. The other two PORVs had their normal


complement of springs. The valve with the missing spring had been found
complement of springs.


satisfactory in preoperational tests. During the preoperational loss of air
===The valve with the missing spring had been found===
satisfactory in preoperational tests.


===During the preoperational loss of air===
test, the valve closed because system pressure was not present; during the hot
test, the valve closed because system pressure was not present; during the hot


Line 152: Line 192:


IN 86-50
IN 86-50
                                                                June 18, 1986 No specific action or written response is required by this information notice.
June 18, 1986 No specific action or written response is required by this information notice.


If you have any questions about this matter, please contact the Regional
If you have any questions about this matter, please contact the Regional
Line 160: Line 200:
;d~waA tJordan, Director
;d~waA tJordan, Director


Divisi   of Emergency Preparedness
Divisi
 
of Emergency Preparedness


and E gineering Response
and E gineering Response


-   ~   Office of Inspection and Enforcement
-
~  
 
===Office of Inspection and Enforcement===


===Technical Contact:===
===Technical Contact:===


===Vern Hodge, IE===
===Vern Hodge, IE===
                    (301) 492-7275 Attachment: List of Recently Issued IE Information Notices
(301) 492-7275 Attachment:  


Attachment 1 IN 86-50
===List of Recently Issued IE Information Notices===
                                                              June 18, 1986 LIST OF RECENTLY ISSUED


IE INFORMATION NOTICES
===Attachment 1===
IN 86-50


Information                                    Date of
===June 18, 1986===
LIST OF RECENTLY ISSUED


Notice No.      Subject                        Issue    Issued to
===IE INFORMATION NOTICES===
Information


86-49          Age/Environment Induced        6/16/86  All power reactor
Date of


Electrical Cable Failues                facilities holding
Notice No.


an OL or CP
Subject
 
Issue
 
Issued to


86-48           Inadequate Testing Of Boron    6/13/86  All BWR facilities
86-49
86-48
86-47 Age/Environment Induced


Solution Concentration In The            holding an OL or CP
===Electrical Cable Failues===
Inadequate Testing Of Boron


===Solution Concentration In The===
Standby Liquid Control System
Standby Liquid Control System


86-47          Feedwater Transient With       6/9/86  All BWRs and PWRs
===Feedwater Transient With===
Partial Failure Of The
 
===Reactor Scram System===
Improper Cleaning And Decon- tamination Of Respiratory
 
===Protection Equipment===
Potential Falsification Of
 
===Test Reports On Flanges===
Manufactured By Golden Gate
 
Forge And Flange, Inc.


Partial Failure Of The                  facilities holding
6/16/86
6/13/86
6/9/86
6/12/86
6/10/86
86-46
86-45
86-44


Reactor Scram System                    an OL or CP
===All power reactor===
facilities holding


86-46            Improper Cleaning And Decon-  6/12/86  All power reactor
an OL or CP


tamination Of Respiratory                facilities holding
===All BWR facilities===
holding an OL or CP


Protection Equipment                    an OL or CP and
===All BWRs and PWRs===
facilities holding
 
an OL or CP
 
===All power reactor===
facilities holding
 
an OL or CP and


fuel fabrication
fuel fabrication
Line 208: Line 292:
facilities
facilities


86-45            Potential Falsification Of      6/10/86 All power reactor
===All power reactor===
facilities holding


Test Reports On Flanges                  facilities holding
an OL or CP and


Manufactured By Golden Gate              an OL or CP and
research and test
 
Forge And Flange, Inc.                  research and test


facilities
facilities


86-44          Failure To Follow Procedures 6/10/86    All power reactor
===All power reactor===
facilities holding


When Working In High Radiation          facilities holding
an OL or CP and
 
Areas                                    an OL or CP and


research and test
research and test
Line 228: Line 310:
reactors
reactors


86-43          Problems With Silver Zeolite    6/10/86  All power reactor
===All power reactor===
facilities holding
 
an OL or CP
 
===All power rector===
facilities holding
 
an OL or CP
 
===All byproduct===
material licensees


Sampling Of Airborne Radio-              facilities holding
Failure To Follow Procedures 6/10/86


iodine                                  an OL or CP
===When Working In High Radiation===
Areas


86-42            Improper Maintenance Of        6/9/86  All power rector
86-43


Radiation Monitoring Systems            facilities holding
===Problems With Silver Zeolite===
Sampling Of Airborne Radio- iodine


an OL or CP
86-42
 
===Improper Maintenance===
Radiation Monitoring
 
Of


86-41            Evaluation Of Questionable    6/9/86  All byproduct
Systems


Exposure Readings Of Licensee          material licensees
6/10/86
6/9/86
6/9/86
86-41


Personnel Dosimeters
===Evaluation Of Questionable===
Exposure Readings Of Licensee


===Personnel Dosimeters===
OL = Operating License
OL = Operating License


Latest revision as of 10:08, 16 January 2025

Inadequate Testing to Detect Failures of Safety-Related Pneumatic Components or Systems
ML031220684
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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill, Crane
Issue date: 06/18/1986
From: Jordan E
NRC/IE
To:
References
IN-86-050, NUDOCS 8606160044
Download: ML031220684 (4)
v • d • e


ORIGINAL

SSINS No.: 6835 IN 86-50

UNITED STATES.

NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

WASHINGTON,,D.C.

20555

June 18, 1986

IE INFORMATION NOTICE NO. 86-50:

INADEQUATE TESTING TO-DETECT FAILURES OF

SAFETY-RELATED PNEUMATIC COMPONENTS OR

SYSTEMS

Addressees

All nuclear power reactor facilities holding an operating license (OL) or a

construction permit (CP).

Purpose

This notice is being provided to alert recipients to a potentially significant

problem pertaining to inadequate testing practice relating to air operated

valves.

The NRC expects that recipients will review this notice for applica- bility to their facilities.

However, suggestions contained in this notice do

not constitute NRC requirements; therefore, no specific action or written

response is required.

Past Related Correspondence:

IE Information Notice No. 82-25, "Failures of Hiller Actuators Upon

Gradual Loss of Air Pressure," July 20, 1982 IE Information Notice No. 85-35,- '.Failure of Air Check Valves to Seat,"

April 30, 1985

IE Information Notice No. 85-84, "Inadequate Inservice Testing of Main

Steam Isolation Valves," October 30, 1985 IE Information Notice No. 85-94, 'Potential for Loss of Minimum Flow

Paths Leading to ECCS Pump Damage During a LOCA," December 13, 1985

Description of Circumstances

The NRC has reported previously on instances where safety-related equipment

failed to operate as intended when non-safety-related pneumatic systems were

unavailable (IE INs 82-25 and 85-35). In these situations, main steam isola- tion valves and containment isolation valves failed to operate properly when

control air pressure decreased slowly rather than rapidly as would be expected

for an air line break.

In the case of IN 85-35, the fault was exposed by a

loss of offsite power test, and in the case of IN 82-25, the fault was exposed

by a preoperational test designed .to simulate a slow air leak.

In both cases,

8606160044

IN 86-50

June 18, 1986 the components in question--an accumulator isolation check valve (IN 85-35) and

pneumatic selector valves (IN 82-25)--were not tested adequately.

Several

recent events have indicated continuing problems of similar nature.

These

events are discussed below.

On February 13, 1986, the licensee at Turkey Point Unit 3 first reported to tht

NRC a concern that the component cooling water (CCW) system might fail to meet

its functional requirements for a design-basis accident.

One part of the

concern involved the CCW heat exchanger outlet control valve.

This valve

regulates flow of intake cooling water (ICW) to this heat exchanger.

Loss of

control air, coincident with a loss of offsite power, a valid engineered

safeguards features (ESF) actuation signal, and a loss of an emergency diesel

generator (EDG) would cause this valve to fail closed.

If this happened, the

CCW heat exchanger would not receive sufficient flow of ICW.

This situation

was discovered during a design review of the ICW system.

Earlier disclosure

might have been possible if ICW operation had been considered or tested with

non-safety-related control air secured, coincident with loss of electrical

power.

On January 7, 1986, the licensee at Robinson Unit 2 reported a concern with the

air-operated valves in the safety injection (SI) pump minimum-flow recircula- tion line from the pump discharge to the refueling water storage tank (RWST).

This concern evolved from review of IN 85-94.

Two such valves had been insert- ed in series in this line and had been designed to fail closed on loss of

non-safety-related air or loss of electrical power to the valves.

The purpose

of the valves is to protect the RWST (outside containment) from highly radioac- tive reactor coolant during the long-term circulation phase of accident recov- ery.

In the event of SI initiation under small-break loss-of-coolant-accident

conditions concurrent with closure of either of these valves, the SI pumps

would be operating with no flow until reactor pressure decreased below their

shutoff head.

This would damage the SI pumps after only a short time.

The

licensee's remedy was to put mechanical blocks on the air operators so the

valves would fail as-is (open). Again, if SI operation had been considered or

tested with non-safety-related control air secured, the fault might have been

disclosed earlier.

On December 9, 1985, the licensee at Catawba Unit 2 reported finding that one

of the two valve closure springs was missing on one of the pressurizer

power-operated relief valves (PORVs). Thus, with loss of air the valve would

not have closed against system pressure. The other two PORVs had their normal

complement of springs.

The valve with the missing spring had been found

satisfactory in preoperational tests.

During the preoperational loss of air

test, the valve closed because system pressure was not present; during the hot

functional test, the valve closed because actuator air pressure was present.

This is clearly a case in which a fail safe valve was tested without all

actuator power secured (IN 85-84).

IN 86-50

June 18, 1986 No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact the Regional

Administrator of the appropriate regional office or this office.

d~waA tJordan, Director

Divisi

of Emergency Preparedness

and E gineering Response

-

~

Office of Inspection and Enforcement

Technical Contact:

Vern Hodge, IE

(301) 492-7275 Attachment:

List of Recently Issued IE Information Notices

Attachment 1

IN 86-50

June 18, 1986

LIST OF RECENTLY ISSUED

IE INFORMATION NOTICES

Information

Date of

Notice No.

Subject

Issue

Issued to

86-49

86-48

86-47 Age/Environment Induced

Electrical Cable Failues

Inadequate Testing Of Boron

Solution Concentration In The

Standby Liquid Control System

Feedwater Transient With

Partial Failure Of The

Reactor Scram System

Improper Cleaning And Decon- tamination Of Respiratory

Protection Equipment

Potential Falsification Of

Test Reports On Flanges

Manufactured By Golden Gate

Forge And Flange, Inc.

6/16/86

6/13/86

6/9/86

6/12/86

6/10/86

86-46

86-45

86-44

All power reactor

facilities holding

an OL or CP

All BWR facilities

holding an OL or CP

All BWRs and PWRs

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP and

fuel fabrication

facilities

All power reactor

facilities holding

an OL or CP and

research and test

facilities

All power reactor

facilities holding

an OL or CP and

research and test

reactors

All power reactor

facilities holding

an OL or CP

All power rector

facilities holding

an OL or CP

All byproduct

material licensees

Failure To Follow Procedures 6/10/86

When Working In High Radiation

Areas

86-43

Problems With Silver Zeolite

Sampling Of Airborne Radio- iodine

86-42

Improper Maintenance

Radiation Monitoring

Of

Systems

6/10/86

6/9/86

6/9/86

86-41

Evaluation Of Questionable

Exposure Readings Of Licensee

Personnel Dosimeters

OL = Operating License

CP = Construction Permit


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