Recent Failures of Charging/Safety Injection Pump ShaftsML031060430 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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, Three Mile Island, 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 ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
10/26/1994 |
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From: |
Grimes B Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-94-076, NUDOCS 9410200153 |
Download: ML031060430 (12) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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, Three Mile Island, 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 |
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Category:NRC Information Notice
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
4 UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 October 26, 1994 NRC INFORMATION
NOTICE 94-76: RECENT FAILURES OF CHARGING/SAFETY
INJECTION PUMP SHAFTS
Addressees
All holders of operating
licenses or construction
permits for pressurized
water rekctors.
Purpose
The U.S. Nuclear Regulatory
Commission (NRC) is issuing this information
notice (IN) to alert addressees
to recent failures of charging/safety
injection
pump shafts at facilities
designed by the Westinghouse
Electric Corporation (Westinghouse).
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.Background
4 At Westinghouse-designed
facilities, charging/safety
injection
pumps have three funct ons: (1) to deliver seal iri 4 ction flow to the reactor coolant pumps, (2) .o eliver makeup water flcv ) the reactor coolant system, and (3) to deliver high head safety injection
and recirculation
flow to the reactor coolant system during and after a loss-of-coolant
accident.
During normal operation, one of two, or in some cases, one of three pumps is always in operation
to deliver seal injection
and makeup water flow. The loss of an inservice
charging/safety
injection
pump creates a condition
that may challenge
reactor coolant pump seal integrity
and, if makeup water flow is not restored in a timely manner, can result in a loss of coolant inventory.
On February 29, 1980, the NRC issued IN 80-07, "Pump Shaft Fatigue Cracking," to alert recipients
to failures of charging/safety
injection
pump shafts that occurred during the 1970s. All of the charging/safety
injection
pump shafts addressed
in that notice were procured by Westinghouse
from the Pacific Pump Division of Dresser Industries (now Ingersoll-Dresser
Pump Co). Actions taken at that time to correct the problem included design modifications, changes in the heat treatment
of the shaft material, and the use of formed cutting tools during fabrication.
Also, abnormal operation
of the pumps such as operation with a partial or complete loss of fluid or with high vibration
present was found to be a significant
contributor
to the shaft failures.
The Westinghouse
Nuclear Service Division issued Technical
Bulletins
TB-77-", TB-78-1, and TB-79-6, to provide guidance on vibration
monitoring, operation
and maintenance
of the pumps, and allowable
vibration
amplitude
limits.9410200153 gf 4 okC 4 P4R On C AI 0+ic 4V Iae
vJ IN 94-76 October 26, 1994 Recent events indicate that failures of charging/safety
injection
pump shafts continue to be a problem.Description
of Circumstances
Sequoyah Unit 1 On February 18, 1991, plant operators
for Sequoyah Unit 1 received indications
of decreasing
flow and increasing
motor current on charging pump IB-B. When efforts to restore full flow failed, they declared the pump inoperable
and began shutting down the reactor as required by plant technical
specifications.
Charging pump lB-B had been in operation
for several months and had shown no previous signs of degradation.
The licensee disassembled
the pump, found heavy wear on the impeller shoulders
and the balance drum, and found a 280-degree
crack in the shaft near the 11th stage impeller.
Westinghouse
analyzed the shaft and determined
that the crack had been in the shaft for several months (possibly
years) and that the rotating element was of the improved type referred to in IN 80-07. The licensee replaced +he rotating element and, after testing the pump successfully, returned the pump to service. [Licensee
Event Report (LER) 50-327/91-003]
Callaway On February 2, 1992, the Union Electric Company Callaway Plant was at power and charging pump B was in service to support operations.
Plant operators received indications
of zero flow in the charging header and at the reactor coolant pump seal. The operators
placed charging pump A iA service to restore normal flow, and pump B tripped. Plant personnel
inspected
pump B and found that the shaft had sheared on the outboard end between the balance drum lock nut an, balance drum mating area. le licensee documented
the failure in Suggestion
Occurrence
Solution 92-10 and replaced the failed shaft.Shearon Harris On March 18, 1993, operators
at the Shearon Harris plant received indications
of a shaft failure on charging/safety
injection
pump B. The indications
were high motor current, low charging flow, and low pump discharge
pressure.
The operators
secured pump B from service and placed pump A in service. Plant personnel
uncoupled
the pump from the motor and found that the pump shaft had sheared under the balancing
drum lock nut. This was the same location as in three failures that occurred in the 1970s. (LER 50-400/93-005)
D.C. Cook Unit 2 In July 1993, at D.C. Cook Unit 2, a charging pump failed a surveillance
test when it could not deliver the required 454 liters [120 gallons] per minute.The rotating element in that pump had been installed
in 1987. The licensee disassembled
the pump and found a 10 centimeter
[4 inch!, 180 degree circumferential
crack through the number 9 impeller shaft keyway. Smaller cracks were found in two other impeller keyway areas. (LER 50-316/93-006)
IN 94-76 October 26, 1994 Braidwood
Unit 1 and Sequoyah Unit 2 The NRC staff has received information
on two other recent failures of charging/safety
injection
pump shafts: (1) on September
15, 1993, at the Braidwood
Nuclear Station Unit 1 (Braidwood), a charging/safety
injection
pump shaft sheared between the 10th and 11th stage impellers, and (2) on February 7, 1994, at Sequoyah Unit 2, a charging\safety
injection
pump shaft failed, resulting
in a reactor shutdown as required by plant technical specifications.
The licensee for Braidwood
replaced the pump shaft and documented
the failure on Problem Investigation
Report 456-200-93-03600.
The licensee for Sequoyah reported that the affected pump had not exhibited
any indication
of degradation
before the shaft failure and that, similar to many of the other shaft failures, the shaft had failed near the location of the balancipng
drum lock nut. (LER 50-328/94-002)
Discussion
Charging/safety
injection
pumps are important
for normal plant operation
and for core cooling during accidents
such as a small break loss-of-coolant
accident.
Fcr most of the failure events described
above, determination
of the root cause of the failure was inconclusive.
However, the operational
histories
of many of the failed shafts showed that they had been operated with void formation, gas entrainment, or other abnormal conditions
within a few years of the failure. Operation
of the pumps under these conditions
may have caused or contributed
to the later failure of the shafts. Avoiding operation of charging pumps under abnormal conditions
and maintaining
vibration
levels within manufacturer
recommendations
may increase pump reliability.
To increase the benefit of predictive
maintenance
programs, Wbstinghouse
recommends
that pump vibrations
be monitored
at least monthly; preferably, every two weeks. This is more frequent than is required by Section XI of the ASME B iler and Pressure Vessel Code. V'stinghouse
will provide recommended
vibration
limits upon request.Industry experience
in detecting
shaft failures in pumps such as the reactor coolant pump and the recirculation
pump is relevant to monitoring
programs of charging/safety
injection
pumps because the precursors
to shaft failure are similar. For those pumps, monitoring
phase angles as well as monitoring
vibration
amplitude
is considered
to be important
in detecting
shaft degradation.
These data are routinely
trended by some licensees
for detection of impending
shaft failures.A description
of the analyses and conclusions
for some of the above events follows: Westinghouse
evaluated
seven possible root causes for the shaft failure at Callaway, including
material defects, design flaws, errors in fabrication
or processing, assembly or installation
defects, off-design
or unintended
service conditions, maintenance
deficiencies, and improper operation.
Westinghouse
concluded
that the shaft failure was most likely the result of a 1986 event in which the pump had experienced
a loss of suction water flow for approximately
seven minutes. The loss of suction flow increased
the vapor-to-liquid
ratio in the pump and caused a dynamic imbalance.
Events of this type could cause
K>~IN 94-76 October 26, 1994 immediate
pump failure or cause cyclic fatigue damage that could lead to premature
shaft failure at a later date.A gas entrainment
event that occurred on August 20, 1990, was determined
to be the probable cause of the shaft failure at Sequoyah Unit 2. Problems caused by gas entrainment
are discussed
in NRC Information
Notice 88-23, "Potential
for Gas Binding of High-Pressure
Safety Injection
Pumps During a Design Basis Accident," and its supplements.
Westinghouse
considers
an operational
phenomenon, such as gas entrainment, may have led to the shaft failure at Shearon Harris, although the licensee found no evidence of gas pockets in the charging system. In May 1991 (two years before-the
shaft failure), the licensee reported to the NRC that the charging system had been in a degraded condition
during the previous operating
cycle.An NRC Special Inspection
Team reviewed the event and determined
that several water hammer events could have occurred in the system as a result of weaknesses
in the design of the alternate
minimum flow system. The NRC issued IN 92-61, "Loss of High Head Safety Injection," and its supplement
regarding that event. Another concern at Shearon Harris was the fact that the A and B charging/safety
injection
pumps are alternated
at approximately
2-week intervals.
Therefore, each pump is started about 25 to 30 times each year.Westinghouse
believes the high number of starts also could contribute
to early shaft failure. Problems associated
with excessive
pump starts include galled wear rings, increased
vibration, and decreased
pump performance.
However, Westinghouse
concluded
that the available
data were insufficient
to directly link the failure of the shaft to the high number of pump starts.Although Westinghouse
could not conclusively
determine
the root cause of the shaft failure at Shearon Harris, West 'nghouse made recommendations
which could help pre-ent or detect impendine
shaf fa;lures.
Westinghou- suggested
that the liceasee conduct a detailed review, of the possibility
that gas could become entrained
in the charging pump suction piping and the cross connczts to other systems. Westinghouse
also recommended
that, when the rotating element of the pump is replaced, consideration
be given to installing
the latest shaft design which has an improved one-piece
balance drum lock nut. Westinghouse
included recommendations
for vibration
monitoring
in Westinghouse
Technical Bulletin TB-79-6. Westinghouse
has not specified
a limitation
on the number of pump starts but recommends
that pump starts be minimized
to maintain pump reliability.
In addition to the industry actions described
above, Westinghouse
and the Westinghouse
Owners Group (WOG) are implementing
a program to address these pump shaft failures.
The program includes:
(1) a survey of WOG member utilities
for pump service operating
history data, (2) a pump design review, and (3) a shaft material enhancement
evaluation.
The program is intended to identify any weaknesses
in design, maintenance, or operation
of the pumps in order to improve shaft reliability.
I .S : ..I IN 94-76 October 26, 1994 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact 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
contact: D. Roberts, RII (919) 362-0601 Attachment:
List of Recently Issued NRC Information
Notices daret4s
Attachment
IN 94-76 October 26, 1994 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 93-60, Supp. 1 94-75 94-74 94-73 94-72 94-71 94-70 94-69 94-68 Reporting
Fuel Cycle and Materials
Events to the NRC Operations
Center Minimum Temperature
for Criticality
Facility Management
Responsibilities
for Purchased
or Contracted
Services for Radiation Therapy Programs Clarification
of Critical-ity Reporting
Criteria Increased
Control Rod Drop Time from Crud Buildup Degradation
of Scram Solenoid Pilot Valve Pressure and Exhaust Diaphragms
Issues Associated
with Use of Strontium-89 and Other Beta Emitting Radiopharma- ceuticals Potential
Inadequacies
in the Prediction
of Torque Requirements
for and Torque Output of Motor-Operated
Butterfly
Valves Safety-Related
Equip-ment Failures Caused by Faulted Indicating
Lamps 10/20/94 10/14/94 10/13/94 10/12/94 10/05/94 10/04/94 09/29/94 09/28/94 09/27/94 All 10 CFR Part 70 fuel cycle licensees.
All holders of OLs or CPs pressurized-water
reactors (PWRs).All U.S. Nuclear Regulatory
Commission
Medical Licensees.
All fuel fabrication
facilities.
All'holders
of OLs or CPs for pressurized
water reactors All holders of OLs or CPs for boiling water reactors (BWRs).All U.S. Nuclear Regulatory
Commission
Medical Licensees.
All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs For nuclear power reactors.OL = Operating
License CP = Construction
Permit
- ..I IN 94-76 October 26, 1994 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Original signed by Brian K. Grimes Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation
Technical
contact: D. Roberts, RII (919) 362-0601 Attachment:
List of Recently Issued NRC Information
Notices**See previous concurrence
Mamn dated Mav 27 1994 OFFICE REGION II REGION II REGION II NAME DRoberts*
JRJohnson**
BBoger*DATE 08/18/94 05/27/94 08/19/94 OFFICE EMEB:DE C/EMEB:DE
D/DE:NRR NAME JRajan* RWessman*
BWSheron*nATF fl/19194 1 08/26/94 08/30/94 Wu.-t .I -I L*, *- _ , -., -X OFFICE TECHED:RPB
OGCB:DORS:NRR
C/OGCB:DORS:NRR
D NAME JMain* JBirmingham*
ELDoolittle*
DATE 07/20/94 08/17/94 09/08/94 10t{/94 OFFICIAL DOCUMENT1 NAME: V4-/0. IN
IN 94-xx October 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 technical
contact 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
contact: D. Roberts, R11 (919) 362-0601 Attachment:
List of Recently Issued NRC Information
Notices* See previous concurrence
- Memo dated May 27 1994 OFFICE REGION II REGION II REGION II NAME DRoberts*
JRJohnson**
BBoger*DATE , 08/18/94 [05/27/94 j 08/19/94 OFFICE [ EMEB:DE C/EMEB:DE
I D/DE:NRR NAME JRajan* RWessman*
I BWSheron*DATE 08/22/94 08/26/94 08/30/94 OFFICE TECHED:RPB
OGCB:DORS:NRR
C/OGCB:DORS:NRR
D/DORS:NRR
NAME JMain* JBirmingham*
ELDoolittle*
BKGrimes DATE , 07/20/94 1 08/17/94 , 09/08/94 1 10/ /94 vo .-.-. -^llrg *e- A o n Tl1 UV ILIAL UULUMtNl NAMt: U:\UMF 14N.JLU 4t14L
IN 94-xx October 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 technical
contact 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
contact: D. Roberts, RII (919) 362-0601 Attachment:
List of Recently Issued NRC Information
Notices* See previous concurrence
- Memo dated May 27 1994 OFFICE REGION II l REGION II REGION II NAME DRoberts*
JRJohnson**
BBoger*DATE 08/18/94 05/27/94 08/19/94 OFFICE EMEB:DE C/EMEB:DE
D/DE:NRR NAME JRajan* RWessman*
BWSheron*DATE 08/22/94 08/26/94 08/30/94-,
- _, , , ,-,, OFFICE TECHED:RPB
OGCB:DORS:NRR
C/OGCB:DORS:NRR
D/DORS:NRR
NAME JMain* JBirmingham*
ELDoolittle*
BKGrimes DATE ,07/20/94
[08/17/94
1 09/08/94 110/ /94 U-ILIAL DULUMLNI NAM: U:\FUMF 1N.JLU
IN 94-xx September
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 technical
contact 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
contact: D. Roberts, RII (919) 362-0601 Attachment:
List of Recently Issued NRC Information
Notices* See previous concurrence
- MPm= dated May 27. 1994 OFFICE REGION II REGION II REGION II NAME DRoberts*
JRJohnson**
BBoger*DATE 108/18/94
,05/27/94
08/25/94 OFFICE EMEB:DE C/EMEB:DE
D/DE:NRR NAME JRajan* RWessman*
BWSheron&nATC 08/22/Q9 nR/26/94 08/2 v/94 ulIL. I --I --. _ .OFFICE TECHED:RPB
OGCB:DORS:NRR
C B:DORS:NRR
D/DORS:NRR
NAME JMain* JBirmingham*l
Ek6V2 ittle BKGrimes DATE 1 07/20/94 -1 08/17/94 j P'Z' 94 08/ /94----- .---'OF-FICIAL
DOCUMEN NAME: b:\FUMr IN.VLb
.r IN 94-xx September
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 technical
contact 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
contact: D. Roberts, R11 (919) 362-0601 Attachment:
List of Recently Issued NRC Information
Notices* See previous concurrence
- Memo dated May 27 1994 OFFICE REGION II REGION I1 REGION II NAME I DRoberts*
JRJohnson**
BBoger*DATE l 08/18/94 [05/27/94 J 08/19/94 OFFICE EMEB:DE C/EMEB:DE
ID I iD IIRR NAME JRajan* RWessman*
I B S on W DATE 08/22/94 08/26/94 08/S6/94 OFFICE TECHED:RPB
OGCB:DORS:NRR
C/OGCB:DORS:NRR
D/DORS:NRR
NAME JMain* JBirmingham*
ELDoolittle
BKGrimes DATE 07/20/94 08/17/94 08/ /94 08/ /94 sors~a rvral~I.-
Plte ^. nstl ti. of ^UMtILIAL UUUUMtNI NAML: b: \FUMr 1N.ULV
IN 94-xx August 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 technical
contact 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
contact: D. Roberts, RII (919) 362-0601 Attachment:
List of Recently Issued NRC Information
Notices* See previous concurrence
- Memo dated May 27 1994 __41 OFFICE REGION II REGION II lEMED( C/EME l D/DE:NRR NAME DRoberts JRJohnson**
JRajw" RWes ke rBWSheron DATE 08/ /94 05/27/94 0 8 /,/94 089f4/94 9 08/ /94 OFFICE 1 TECHED:RPB
J OGCB:DORS:NRR
C/OGCB:DORS:NRR
D/DORS:NRR
NAME l JMain* JBimnghim*
It ELDoolittle
BKGrimes DATE l 07/20/94 l 08/17/94 08/ /94 08/ /94 OFFICIAL DOCUMENT NAME: G:\PUMPIN.JLB
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list | - Information Notice 1994-01, Turbine Blade Failures Caused by Torsional Excitation from Electrical System Disturbance (7 January 1994)
- Information Notice 1994-02, Inoperability of General Electric Magne-Blast Breaker Because of Misalignment of Close-Latch Spring (7 January 1994)
- Information Notice 1994-03, Deficiencies Identified During Service Water System Operational Performance Inspections (11 January 1994, Topic: Biofouling)
- Information Notice 1994-04, Digital Integrated Circuit Sockets with Intermittent Contact (14 January 1994)
- Information Notice 1994-05, Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves (19 January 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-06, Potential Failure of Long-Term Emergency Nitrogen Supply for the Automatic Depressurization System Valves (28 January 1994)
- Information Notice 1994-07, Solubility Criteria for Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20 (28 January 1994)
- Information Notice 1994-08, Potential for Surveillance Testing to Fail to Detect an Inoperable Main Steam Isolation Valve (1 February 1994)
- Information Notice 1994-09, Release of Patients with Residual Radioactivity from Medical Treatment & Control of Areas Due to Presence of Patients Containing Radioactivity Following Implementation of Revised 10 CFR Part 20 (3 February 1994, Topic: Brachytherapy)
- Information Notice 1994-10, Failure of Motor-Operated Valve Electric Power Train Due to Sheared or Dislodged Motor Pinion Gear Key (4 February 1994)
- Information Notice 1994-11, Turbine Overspeed and Reactor Cooldown During Shutdown Evolution (8 February 1994)
- Information Notice 1994-12, Insights Gained from Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment (9 February 1994, Topic: Overspeed trip)
- Information Notice 1994-13, Unanticipated and Unintended Movement of Fuel Assemblies and Other Components Due to Improper Operation of Refueling Equipment (28 June 1994)
- Information Notice 1994-14, Failure to Implement Requirements for Biennial Medical Examinations and Notification to the NRC of Changes in Licensed Operator Medical Conditions (24 February 1994)
- Information Notice 1994-15, Radiation Exposures During an Event Involving a Fixed Nuclear Gauge (2 March 1994)
- Information Notice 1994-16, Recent Incidents Resulting in Offsite Contamination (3 March 1994)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (QMP), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (Qmp), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-18, Accuracy of Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to Generic Letter 89-10) (16 March 1994)
- Information Notice 1994-19, Emergency Diesel Gemerator Vulnerability to Failure from Cold Fuel Oil (16 March 1994)
- Information Notice 1994-20, Common-Cause Failures Due to Inadequate Design Control and Dedication (17 March 1994)
- Information Notice 1994-21, Regulatory Requirements When No Operations Are Being Performed (18 March 1994)
- Information Notice 1994-22, Fire Endurance & Ampacity Derating Test Results for 3-Hour Fire-Rated Thermo-Lag 330-1 Fire Barriers (16 March 1994, Topic: Fire Barrier)
- Information Notice 1994-23, Guidance to Hazardous, Radioactive and Mixed Waste Generators on the Elements of a Waste Minimization Program (25 March 1994, Topic: Fire Barrier)
- Information Notice 1994-24, Inadequate Maintenance of Uninterruptible Power Supplies & Inverters (24 March 1994, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1994-25, Failure of Containment Spray Header Valve to Open Due to Excessive Pressure from Inertial Effects of Water (15 March 1994, Topic: Fire Barrier)
- Information Notice 1994-26, Personnel Hazards and Other Problems from Smoldering Fire-Retardant Material in the Drywell of a Boiling-Water Reactor (28 March 1994, Topic: Fire Barrier)
- Information Notice 1994-27, Facility Operating Concerns Resulting from Local Area Flooding (31 March 1994, Topic: Fire Barrier)
- Information Notice 1994-28, Potential Problems with Fire-Barrier Penetration Seals (5 April 1994, Topic: Fire Barrier)
- Information Notice 1994-29, Charging Pump Trip During a Loss-of-Coolant Event Caused by Low Suction Pressure (11 April 1994, Topic: Boric Acid)
- Information Notice 1994-30, Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station (19 August 1994, Topic: Fire Barrier)
- Information Notice 1994-31, Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles (14 April 1994, Topic: Hydrostatic)
- Information Notice 1994-32, Revised Seismic Estimates (29 April 1994, Topic: Earthquake)
- Information Notice 1994-33, Capacitor Failures in Westinghouse Eagle 21 Plant Protection Systems (9 May 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-34, Thermo-LAG 330-660 Flexi-Blanket Ampacity Derating Concerns (13 May 1994, Topic: Fire Barrier)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(Mmr) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(MMR) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System (24 May 1994, Topic: Reactor Vessel Water Level, Stress corrosion cracking, Integrated leak rate test)
- Information Notice 1994-37, Misadministration Caused by a Bent Interstitial Needle During Brachytherapy Procedure (27 May 1994, Topic: Brachytherapy)
- Information Notice 1994-38, Results of Special NRC Inspection at Dresden Nuclear Power Station, Unit 1 Following Rupture of Service Water Inside Containment (27 May 1994)
- Information Notice 1994-39, Identified Problems in Gamma Stereotactic Radiosurgery (31 May 1994)
- Information Notice 1994-40, Failure of a Rod Control Cluster Assembly to Fully Insert Following a Reactor Trip at Braidwood, Unit 2 (26 May 1994)
- Information Notice 1994-41, Problems with General Electric Type Cr124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-41, Problems with General Electric Type CR124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-42, Cracking in the Lower Region of the Core Shroud in Boiling-Water Reactors (7 June 1994)
- Information Notice 1994-43, Determination of Primary-to-Secondary Steam Generator Leak Rate (10 June 1994, Topic: Grab sample)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand Because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-45, Potential Common-Mode Failure Mechanism for Large Vertical Pumps (17 June 1994, Topic: Biofouling)
- Information Notice 1994-46, Nonconservative Reactor Coolant System Leakage Calculation (20 June 1994)
... further results |
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