Determination of Westinghouse Reactor Coolant Pump Seal FailureML031070307 |
Person / Time |
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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, 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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Issue date: |
10/20/1993 |
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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-93-084, NUDOCS 9310140192 |
Download: ML031070307 (16) |
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Similar Documents at 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, 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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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 [[:Mcguire]] 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 [[:Mcguire]] 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>. |
UNITED STATES NUCLEAR'REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 October 20, 1993 NRC INFORMATION
NOTICE 93-84: DETERMINATION
OF WESTINGHOUSE
REACTOR COOLANT PUMP SEAL FAILURE
Addressees
All holders of operating
licenses or construction
permits for pressurized
water reactors (PWRs).PurDose The U.S. Nuclear Regulatory
Commission (NRC) is'issuing
this information
notice to alert addressees
to a potential
problem that could result from the use of Westinghouse-designed
reactor coolant pump (RCP) shutdown procedures
for pumps whose No. 1 seals have failed. 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
Westinghouse
supplied the Braidwood
Station RCPs, incorporating
a three-stage
seal series arrangement
to limit coolant flow up the pump shaft. The No. 1 seal, the main seal of the pump, is a controlled-leakage, film riding face seal. The No. 2 and No. 3 seals are rubbing face seals. During normal operation, an injection
flow of nominally
30.3 liters [8 gallons] per minute enters the pump below the No. 1 seal (see Attachment
1). Here the flow splits. A portion (approximately
18.9 liters [5 gallons] per minute) flows down through the thermal barrier heat exchanger
and enters the reactor coolant system. In this manner, the primary coolant is prevented
from entering the radial bearing and seal section of the pump unit. The remainder
(11.4 liters[3 gallons] per minute) (controlled
leakage) passes through the pump radial bearing and enters the No. 1 seal. Above the No. 1 seal, most of the flow leaves the pump through the No. 1 seal leakoff line and returns to the chemical and volume control system. Minor flow passes through the No. 2 seal and its leakoff line to the reactor coolant drain tank. A back flush injection
of 0.8 liters [0.21 gallons] per hour from a head tank flows into the No. 3 seal between its "double dam" seal area. At this point, half of the flow passes through one side of the seal and out the No. 2 seal leakoff line while the remaining
flow passes through the other side and out the No. 3 seal leakoff line. This arrangement
ensures essentially
zero leakage of reactor coolant from the pump.9310140192 o W q 3.O3;Afe4% ;IivftC
IN 93-84 Octoer 20, 1993 During normal operation, the No. 1 seal is subject to full reactor coolant system pressure.
When the injection
flow passes through the No. 1 seal, it produces a pressure drop of approximately
15.41 MPa [2235 psi]. The No. 2 seal has the capability
to withstand
full operating
pressure, and its major function is to act as a backup in case the No. 1 seal fails. If the No. 1 seal fails, leakage through the No. 2 seal increases.
The No. 2 seal high leak flow alarm actuates at 3.8 liters [1 gallon] per minute.Description
of Circumstances
In the middle of 1992, while developing
shutdown procedures
for the RCPs at the Braidwood
Station, Commonwealth
Edison Company (the licensee)
found that its abnormal operating
procedure
contained
inadequate
instructions
for responding
to a failure of the RCP No. 1 seal. On a high RCP No. 1 seal leakoff condition, the abnormal operating
procedure
directed the operating personnel
to check the condition
of the No. 2 seal. If the No. 2 seal was acting as the primary pressure boundary on the basis of leakage of at least 3.8 liters [1 gallon] per minute from the No. 2 seal, the procedure
required that the RCP be shut down. If the condition
of the No. 2 seal was normal, the procedure
required no further action and gave no further guidance.Discussions
with Westinghouse
indicated
that the condition
of the No. 2 seal might not be a sufficient
indication
of the operability
of the No. 1 seal.Discussion
The inadequacies
in the operating
procedure
stem from the limitations
of the instrumentation
used to monitor the leakage. The relevant No. 1 seal instrumentation
limits maximum readings to 22.7 liters [6 gallons] per minute.Although the No. 2 seal high leak flow alarm was set at 3.8 liters [1 gallon]per minute, very high No. 1 seal leak rates, more than 113.6 liters (30 gallons] per minute, are needed for the No. 2 seal to reach this flow rate. Thus, the No. 1 seal could have substantial
leakage (e.g., 22.7-113.6 liters (6-30 gallons] per minute) even though the No. 2 seal high leak flow alarm was not actuated.
In the mean time, the RCP seal system might be severely damaged if loss of injection
were to occur or the No. 1 seal leak rates were more than 30.3 liters [8 gallons] per minute. Therefore, monitoring
for high No. 2 seal leakage is not a reliable method of determining
whether the No. 1 seal has failed.After finding that the condition
of the No. 2 seal might not indicate the operability
of the No. 1 seal, Westinghouse
provided guidance for the Braidwood
Station that significantly
enhances operator ability to determine
if immediate
shutdown of an RCP is required or if a more orderly shutdown can be conducted.
Westinghouse
completed
a safety evaluation
and issued Technical Bulletin, NSD-TB-93-01-RO, "Revised Procedures
for RCP Shutdown with No. 1 Seal Leakage Outside Operating
Limits," dated March 30, 1993, to other PWRs that might be affected.
An excerpt from this document is attached to this information
notice (see Attachment
2).
IN 93-84 October 14, 1993 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:
Steve DuPont, RIII (815) 458-2852 Martin Farber, RIII (708) 790-5774 Chu-Yu Liang, NRR (301) 504-2878 Attachments:
1. Simplified
Braidwood
Seal Water Injection and Leakoff Flow Diagram 2. Excerpt from Westinghouse
Technical Bulletin, NSD-TB-93-01-RO, "Revised Procedures
for RCP Shutdown with No. 1 Seal Leakage Outside Operating
Limits" 3. List of Recently Issued NRC Information
Notices
2=."I 'I'TO SEAL WATER HAT EXCHANGER CO IrRo.D my LEVEL IN STAOPIPE TO REGENERATIWE1 HEAT EXCHANGER DR DRAIN IIMP go 0 Zrt aq ct (D j xD O m 00 MS 0 t I-'.II-h' LAl -NIN sAN ThERL ARRHER HEAT EXCHANGERF"U.t,&ID w SIMPLIFIED
BRAIDWOOD
SEAL WATER INJECTION
AND LEAKOFF FLOW DIAGRAM
I>Attachment
2 IN 93-84 October 20 1993 Page 1 of I Nuclear Services Division Westinghouse
Technical
Bulletin An advisory notice of a recent technical
development
pertining
to th- irts.ation
or operation
of Wastghous&suppi*d
Nudr Plant equipment.
Recipients
shouSd evaluate the Information
and recomnM aIRonl, and initite action wh-r aomopriabt.
P.O. SOX 35, Pltttxzu PA 15o Subject REVISED PROCEDURES
FOR ROP SHUTDOWN WITH NO.'.FAl I FAKA(LF OUTSIDE OPERATING
UMITS.o NSD-TB- 93-01-RO System(s)
REACTOR COOLANT SYSTEM Date 03r3/9 PLant ALL WESTINGHOUSE
REACTOR COOLANT PUMPS WITH lr SO(s) 125 CONTROLLED
LEAKAGE SEALS (See Aftacivelt
B)References
_- -- C , .nA~. cten Is Safety Related Yes 0 Page 1 Of 8 h M L) rilv Vl..I Vr-ij' 1 Q %- W I E2o m e t adgq No O1
BACKGROUND
Years of Westinghouse
RCP operating
experience
has demonstrated
that complete failure of the No. 1 seal is a rare occurrence.
A complete failure is defined as excessive
No. 1 seal leakage in conjunction
with pump bearing/seal
inlet and/or No. 1 leakoff temperatures
approaching
or exceeding
the maximum limits. Current operating
procedures
for failed No. 1 seals direct that the No. I seal leakoff be isolated within 5 minutes and RCP shutdown witlin 30 minutes. These procedures
are specified
in the RCP instruction
books or addenda to the books.After a review of current operating
procedures
and actual operating
experiences
with high and low leaking No. 1 seals, it was concluded
ftht distinct procedures
could specify steps for both emergency
and orderly RCP shutdowns.
The two iems that follow have been incorporated
into the revised procedures
in this technical
bulletin.
As used within this bulletin, the term 'emergefly
m refers to a condition
that is related only to RCP operation
and in no way pertains to emergency
conditions
for plant operation
as defined in a plant hnal Safety Analysis Report (FSAR).I) A damaged No. 1 seal may produce debris or leak at a high enough rate to exceed the injection
rate and introduce
unfiltered, high temperature
reactor coolant into the seals. In the presence of debris. the ability of the No. 2 seal to survive and function as a backup for the No. 1 seal is more favorable
under static conditions.
Thus, it is preferred
to have pump shutdown precede No. 1 seal leakoff isolation.
AJol" W omutfi. Flequd. may be Obhuned fron @fe 0rawc Teb hoffl 412- 963-5634 or (W) 29-5634 Appmvi.T. W. Dunn, Manager, Fied Service & RCP Engineerng
L J. Haper Ener Systes Saes Suport'q7- -t-. N R. F pleiter. mwnA~e CR 4 -& Seal Engineain at tr* gwonmul)Of
corame in W"t "Pon or -an wy reqpo-"kdy
1b "ik&ym dafiQ$ ~iC flf umastamtom
am of mooh irdofflol.
Attachment
2 IN 93-84 October 20, 1993 NSD-TB-93-01-RO 2) High No. 1 seal leakage (> 6.0 9pm) or low No. 1 seal leakage (< 0.8 gpen) can occur while no other RCP parameter
limits are approached
or violated.
In these cases. pump shutdowns
within several hours are within the capabilities
of the RCPs and are more conducive
to orderly plant shutdowns.
The following
new procedures
are provided to address each of four conditions
that irncate No. 1 seal flow outside of the operating
limits (0.8-6.0 gpm). The first three conditiors
address high No. I seal leakage and the fourth condition
addresses
low leakage. Each condition
with its respective
procedure
is specified
below and is summarized
in Attachment
A.PROCEDURES
The following
procedures
supersede
those in the RCP instruction
books or addenda to the books relative to: 1) RCP emergency
operation
and shutdown procedures
for high or low No. 1 seal leakage. Apply the Conditions
1 through 4 procedures
that follow.2) RCP emergency
operation
and shutdown procedure
for No. 2 and No. 3 seals. Apply the procedure
for shutdown specified
under Condition
1 below. The No. 2 and No. 3 seal parameters
tat indicate emergency
operation
remain the same as specified
in the RCP instruction
books.Definitions:
No. 1 seal leakoff indication:
Flowmeter
readout of No. 1 seal leak rate No. 2 seal leakoff indication:
Flowmeter
readout or estimate of No. 2 seal leak rate Total No. 1 Seal Flow: Sum of No. 1 and No. 2 seal leakoff indications
Immediate
Shutdown:
RCP shutdown and isolation
of No. 1 seal leakoff within 5 minutes Orderly Shutdown:
RCP shutdown within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of higtow No. 1 seal leakoff flow indication
NOTE; A manual plant trip must precede an "Emergency
or 'Ordery RCP shutdown.
This will prevent an automatic
plant tip on a low flows signal which represents
an unnecessary
challenge
to installed
safety systems.
Attachment
2 IN 93-84 October 20, 1993 NSD-TB-93-011-RO If no alternative
Westinghouse
direction
has been provided to address a specfic RCP seal performance
condition
at a plant, the following
are the recommended
shutdown procedures
for No. 1 seal leak rates outside the operating
limits (08-6.0 gpm).Condition
1: a) No. 1 sea leakoff indication
> 6.0 gpcn.b) Increasing
pump beanngfseal
inlet temnperature.
and/or increasing
No. I seal leakoff temperature.
Procedure:
1)Shut down the RCP immediately.
2) Isolate the No. 1 seal leakoff after the RCP has come to a complete stop.3) Monitor component
cooling water (CCW) to ensure adequate flow and manually override automatic
isotation
as required. (Local boiling in the thermal barrier of the affected pump may cause isolation
of the CCW system.)4) Do not restart the pump until the cause of the seal malfunction
has been determined
and corrected.
Condition
2;a)No. I seal leakoff indication
> 6.0 gpm.andfor Total No. 1 seal flow > 6.0 gpm and < 8.0 gpm.b) Ppump bearing/seal
inlet temperature
is not increasing.
c) No. 1 seal leakoff temPerature (if equipped)
is not increasing.
Procedure:
1)Prepare for an orderly pump shutdown to take effect within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of exceeding
6.0 gpm No. I seal flow. Ensure that seal injection
flow rate is 9 gpm or greater to the affected RCR
Attachment
2 IN 93-84 October 20, 1993 NSD-TB-93-o -RO 2) Continue to monitor the No. 1 seal for further degradation
durng the orderly shutdown.
If the total No. 1 seal flow exceeds 8.0 gpm or temperatures
begn to increase, proceed with immediate
shutdown in accordance
with the Condition
3 procedure.
Otherwise, proceed with the orderly shutdown.3) Secure the pump within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of exceeding
a No. 1 seal eamkof indication
or total No. 1 seal flow of 6.0 gpn.4) Moritor component
cooing waler (CCOW to ensure adequate flow and manually override as required. (Local boiling in the thermal banier of the affected pump may cause isolaton of the CCW system.)5) No. I seal leakoff may be isolated at the discretion
of operations
to mitigate inventory
loss and to assure that seal injection
flow exceeds total No. 1 seal flow on the affected pump.6) Do not restart the pump until the cause of the seal malfunction
has been determined
and corrected.
Condition
3: a) Total No. 1 seal flow x 8.0 gpm.Procedure:
1) Shut down the RCP immediately.
2) Isolate the No. 1 seal leakoff after the RCP has come to a complete stop.3) Monitor component
cooling water (CCW) to ensure adequate flow and rnanaly override automatic
Isolation
as required. (Local boiling in the thermal banier of the affected pump may cause isolation
of the CCW system.)4) .Do not restart the pump until the cause of the seal malfunction
has been determined
and corected.Condition
4: a) No. I seal leakoff indication
c 0.8 gpm.b) Zero (or negligible)
No. 2 seal leak rate such that total No. 1 seal flow < 0.8 gprn.c) Pump bearingfseal
inlet temperature
and No. 1 seal leakoff temperature (if equipped)
are stable (i.e.. not coninuously
increasing)
and within limits.
Attachient
2 IN 93-84 October 20, 1993 NSD-TB-93"01-RO Procedure:
1) Prepare for an orderly pump shutdown to take effect within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of violating
the rninimum 0.8 No. 1 seal leak rate Knit 2) Continue to monitor the No. 1 seal for further degradation
duing the orderly shutdown.
If the bw No. 1 sa lealkge reverses to high leakage (> 6.0 gpim) or temperatures
start to increase, proceed with immeciate shutdown in accordance
with the Condcion 1 procedure.
Otherwise, proceed with the orderly shutdown.3) Secure the pump within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of violasts the rnirnmum 0.8 No. 1 seal leak rate limit.4) Do not restart the pump until the cause of the seal malfunction
has been determined
and corrected.
ATTACHMENT
A No. 1 Leakotf No. 2 Leakoft Total Pump Bearing/Seal
Condition
Indication
Indication
No. 1 Seal Flow Inlet and/or RCP Shutdown No. 1 Leakoff Temp.1 > 6.0 gpm > 6.0 gpm Increasing
Immediate (wilhin 5 minutes)2 > 6.0 gpm > 6.0 and < 8.0 gpm Stable Orderly (within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />)3 > 8.0 gpm Stable or Immediate increasing (within 5 minutes)4 < 0.8 gpm zero < 0.8 gpm Stable Orderly (or negligible) (within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />)Note: Total No. 1 seal flow a No. 1 leakoff plus No. 2 leakoff indications
(0 0 q4 0 oz 3 IF wo I'd Pz n MD 0 a% ID 0 0'-P-a (J.%D rt*r1-U) 0 i2w~,r
Attachment
3 IN 93-84 October 20, 1993 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 93-83 Potential
Loss of Spent Fuel Pool Cooling Following
A Loss of Coolant Accident (LOCA)10/07/93 All holders for boiling (BWRs).of OLs or CPs water reactors 93-82 93-81 93-80 93-79 93-78 93-77 93-76 93-75 Recent Fuel and Core Performance
Problems in Operating
Reactors Implementation
of Engineering
Expertise on Shift Implementation
of the Revised 10 CFR Part 20 Core Shroud Cracking at Beltline Region Welds in Boiling-Water
Reactors Inoperable
Safety Systems At A Non-Power
Reactor Human Errors that Result in Inadvertent
Transfers of Special Nuclear Material at Fuel Cycle Facilities
Inadequate
Control of Paint and Cleaners for Safety-Related
Equipment Spurious Tripping of Low-Voltage
Power Circuit Breakers with GE'RMS-9 Digital Trip Units 10/12/93 10/12/93 10/08/93 09/30/93 10/04/93 10/04/93 09/21/93 09/17/93 All holders of OLs or CPs for nuclear power reactors and all NRC-approved
fuel suppliers.
All holders of OLs or CPs for nuclear power reactors.All byproduct, source, and and special nuclear material licensees.
All holders of operating licenses or construction
permits for boiling-water
reactors (BWRs).All holders of OLs or CPs for test and research reactors.All nuclear fuel cycle 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
IN 93-84 October 14, 1993 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. Grimef Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: Steve (815)DuPont, RIII 458-2852 Martin Farber, RIII (708) 790-5774 Chu-Yu Liang, NRR (301) 504-2878 Attachments:
1. Simplified
Braidwood
Seal Water Injection and Leakoff Flow Diagram 2. Excerpt from Westinghouse
Technical Bulletin, NSD-TB-93-01-RO, "Revised Procedures
for RCP Shutdown with No. I Seal Leakage Outside Operating
Limits" 3. List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
OFF NAME DATE*OGCB:DORS
PCWen 07/26/93*SRXB:DSSA
CYLiang 07/26/93*SRI:DRP:RIII
SGDuPont 07/26/93*TECH ED MMejac 07/27/93*SC/DRP:RIII
MJFarber 07/29/93*D/DSSA ACThadani 09/23/93*C/DRP:RIII
BClayton 07/29/93*C/OGCB:DORS
GHMarcus 09/28/93*SC/SRXB:DSSA
MACaruso 08/05-93.4:;tes 10// r 93*C/SRXB:DSSA
RCJones 08/09/93 DOCUMENT NAME: 93-84.IN
IN 93-xx October xx, 1993 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: Steve DuPont, RIII (815) 458-2852 Martin Farber, RIII (708) 790-5774 Chu-Yu Liang, NRR (301) 504-2878 Attachments:
1. Simplified
Braidwood
Seal Water Injection
and Leakoff Flow Diagram 2. Excerpt from Westinghouse
Technical
Bulletin, NSD-TB-93-01-RO, "Revised Procedures
for RCP Shutdown with No. 1 Seal Leakage Outside Operating Limits" 3. List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
OFF NAME DATE*OGCB:DORS
PCWen 07/26/93*SRXB:DSSA
CYLiang 07/26/93*SRI:DRP:RIII
SGDuPont 07/26/93*TECH ED MMejac 07/27/93*SC/DRP:RIII
MJFarber 07/29/93*C/DRP:RIII
BClayton 07/29/93*SC/SRXB:DSSA
MACaruso 08/05/93*C/SRXB:DSSA
RCJones 08/09/93*D/DSSA ACThadani 09/23/93 DOCUMENT NAME: C/OGCB:DOi,_
D/DORS PcEY GHMarcu$s&
!:' BKGrimesng
P4it P (so-.-qI),MAM
WRCPSEAL.We
0fFnfS T HE 049 /9o o3eevat lro 1hE NftC 41TA03rA*
THS g*Sr*qWS C _ %,A _ } U. .O ' 0a* W S~--.W""i r. MOFbV4' ( H& S5ef ) vvia %;nfgnri&
dr i tw LWI44n44t
et-K'%$ U -te pnvi.d %e ,W Tec6-,.p^
MoTtwcdL.
?et hk~
IN 93-xx September
xx, 1993 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: Steve DuPont, RIII (815) 458-2852 Martin Farber, RIII (708) 790-5774 Chu-Yu Liang, NRR (301) 504-2878 Attachments:
1. Simplified
Braidwood
Seal Water Injection
and Leakoff Flow Diagram 2. Excerpt from Westinghouse
Technical
Bulletin, NSD-TB-93-01-RO, 'Revised Procedures
for RCP Shutdown with No. 1 Seal Leakage Outside Operating Limits'3. List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
OFF NAME DATE*OGCB:DORS
PCWen 07/26/93*SRXB:DSSA
CYLiang 07/26/93*SRI:DRP:RIII
SGDuPont 07/26/93*TECH ED MMejac 07/27/93*SC/DRP:RIII
MJFarber 07/29/ AF D/DSS ai' _ACThadani 09/2_/93 DOCUMENT NAME:*C/DRP:RIII
BClayton 07/29/93 C/OGCB:DORS
GHMarcus 09/ /93 WRCPSEAL.WEN
MACaruso 08/05/93*C/SRXB:DSSA
RCJones 08/09/93 D/DORS BKGrimes 09/ /93 Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: Steve DuPont, RIII (815) 458-2852 Martin Farber, RIII (708) 790-5774 Chu-Yu Liang, NRR (301) 504-2878 Attachments:
1. Simplified
Braidwood
Seal Water Injection
and Leakoff Flow Diagram 2. Excerpt from Westinghouse
Technical
Bulletin, NSD-TB-93-01-RO, 'Revised Procedures
for RCP Shutdown with No. 1 Seal Leakage Outside Operating Limits" 3. List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
OFF *OGCB:DORS
NAME PCWen CYLiang DATE 07/26/93 O7/26/93 STW RD I :I I C/R J.:RIII MJFarber 4 BClayton 07ial/93 J 07/< /93 we 74FCoo .7,6/93 D/DSSA C/OGCB:DORS
ACThadani
GHMarcus 07/ /93 07/ /93*SRI:DRP:RIII
SGDuPont 07/26/93 ,JSRXB:DSSA
C ones?/ /93*TECH ED MMejac 07/27/93 SC/SRXB:DSSAL
MACaruso `y r r/4r/93 / r D/DORS BKGrimes 07/ /93
\s-/Martin Farber, RIII (708) 790-5774 Chu-Yu Liang, NRR (301) 504-2878 Attachments:
1. Braidwood
Seal Water Injection
and Leakoff Flow Diagram..r-
2. Excerpt from Westinghouse
Technical
Bulletin, NSD-TB-93-01-RO, "Revised Procedures
for RCP Shutdown with No. 1 Seal Leakage Outside Operating Limits" 3. -List-ef Recently IssueFd4RC-4nf-4fmation.-Not-ies-.-
OFF NAME DATE OCB:DORS PCWen 07/a6/93 SRXB L SA S I RIII CYLiang _ SGDuPont MR-07/;xb/93 V~ 07/Vb/93 T1-e'A.@TECH ED MMejac *M i 07/1.7/93 SC/SRXB:DSSA
MACaruso 07/ /93 SC/DRP:RIII
MJFarber 07/ /93 C/DRP:RIII
BClayton 07/ /93 C/SRXB:DSSA
RCJones 07/ /93 D/DSSA ACThadani 07/ /93 C/OGCB:DORS
GHMarcus 07/ /93 D/DORS BKGrimes 07/ /93! .
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list | - Information Notice 1993-01, Accuracy of Motor-Operated Valve Diagnostic Equipment Manufactured by Liberty Technologies (4 January 1993)
- Information Notice 1993-02, Malfunction of a Pressurizer Code Safety Valve (4 January 1993, Topic: Loop seal)
- Information Notice 1993-04, Investigation and Reporting of Misadministrations by the Radiation Safety Officer (7 January 1993)
- Information Notice 1993-05, Locking of Radiography Exposure Devices (14 January 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-06, Potential Bypass Leakage Paths Around Filters Installed in Ventilation Systems (22 January 1993)
- Information Notice 1993-07, Classification of Transportation Emergencies (1 February 1993)
- Information Notice 1993-08, Failure of Residual Heat Removal Pump Bearings Due to High Thrust Loading (1 February 1993, Topic: Probabilistic Risk Assessment)
- Information Notice 1993-09, Failure of Undervoltage Trip Attachment on Westinghouse Model DB-50 Reactor Trip Breaker (2 February 1993)
- Information Notice 1993-10, Dose Calibrator Quality Control (2 February 1993)
- Information Notice 1993-11, Single Failure Vulnerability of Engineered Safety Features Actuation Systems (4 February 1993)
- Information Notice 1993-12, Off-Gassing in Auxiliary Feedwater System Raw Water Sources (11 February 1993)
- Information Notice 1993-13, Undetected Modification of Flow Characteristics in High Pressure Safety Injection System (16 February 1993)
- Information Notice 1993-14, Clarification of 10 CFR 40.22, Small Quantities of Source Material (18 February 1993)
- Information Notice 1993-15, Failure to Verify the Continuity of Shunt Trip Attachment Contacts in Manual Safety Injection and Reactor Trip Switches (18 February 1993)
- Information Notice 1993-16, Failures of Not-Locking Devices in Check Valves (19 February 1993, Topic: Anchor Darling, Flow Induced Vibration)
- Information Notice 1993-17, Safety Systems Response to Loss of Coolant and Loss of Offsite Power (25 March 1994, Topic: Fire Barrier, Backfit)
- Information Notice 1993-18, Portable Moisture-Density Gauge User Responsibilities During Field Operations (10 March 1993, Topic: Moisture Density Gauge, Moisture-Density Gauge, Stolen)
- Information Notice 1993-19, Slab Hopper Bulging (17 March 1993, Topic: Hydrostatic)
- Information Notice 1993-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators (24 March 1993)
- Information Notice 1993-21, Summary of NRC Staff Observations Compiled During Engineering Audits or Inspections of Licensee Erosion/Corrosion Programs (25 March 1993, Topic: Weld Overlay)
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure (26 March 1993)
- Information Notice 1993-23, Weschler Instruments Model 252 Switchboard Meters (31 March 1993)
- Information Notice 1993-24, Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner Standards (31 March 1993, Topic: Job Performance Measure)
- Information Notice 1993-25, Electrical Penetration Assembly Degradation (1 April 1993)
- Information Notice 1993-26, Grease Soldification Causes Molded-Case Circuit Breaker Failure to Close (31 January 1994)
- Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization (8 April 1993, Topic: Reactor Vessel Water Level)
- Information Notice 1993-28, Failure to Consider Loss of DC Bus in the Emergency Core Cooling System Evaluation May Lead to Nonconservative Analysis (9 April 1993, Topic: Fuel cladding)
- Information Notice 1993-29, Problems with the Use of Unshielded Test Leads in Reactor Protection System Circuitry (12 April 1993)
- Information Notice 1993-30, NRC Requirements for Evaluation of Wipe Test Results; Calibration of Count Rate Survey Instruments (12 April 1993)
- Information Notice 1993-31, Training of Nurses Responsible for the Care of Patients with Brachytherapy Implants (13 April 1993, Topic: Brachytherapy)
- Information Notice 1993-32, Nonconservative Inputs for Boron Dilution Events Analysis (21 April 1993, Topic: Shutdown Margin)
- Information Notice 1993-33, Potential Deficiency of Certain Class Ie Instrumental and Control Cables (28 April 1993)
- Information Notice 1993-33, Potential Deficiency of Certain Class IE Instrumental and Control Cables (28 April 1993, Topic: Brachytherapy)
- Information Notice 1993-34, Potential for Loss of Emergency Cooling Function Due to a Combination of Operational and Post-LOCA Debris in Containment (6 May 1993, Topic: Brachytherapy)
- Information Notice 1993-35, Insights from Common-Cause Failure Events (12 May 1993, Topic: Brachytherapy)
- Information Notice 1993-36, Notifications, Reports, and Records of Misadministrations (7 May 1993, Topic: Brachytherapy)
- Information Notice 1993-37, Eyebolts with Indeterminate Properties Installed in Limitorque Valve Operator Housing Covers (19 May 1993, Topic: Brachytherapy)
- Information Notice 1993-38, Inadequate Testing of Engineered Safety Features Actuation Systems (24 May 1993)
- Information Notice 1993-39, Radiation Beams From Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-39, Radiation Beams from Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-40, Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material (26 May 1993, Topic: Safe Shutdown, Fire Barrier, Fire Protection Program)
- Information Notice 1993-41, One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems (28 May 1993, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1993-42, Failure of Anti-Rotation Keys in Motor-Operated Valves Manufactured by Yelan (9 June 1993)
- Information Notice 1993-43, Use of Inappropriate Lubrication Oils in Satety-Related Applications (10 June 1993)
- Information Notice 1993-44, Operational Challenges During a Dual-Unit Transient (15 June 1993)
- Information Notice 1993-45, Degradation of Shutdown Cooling System Performance (16 June 1993)
- Information Notice 1993-46, Potential Problem with Westinghouse Rod Control System and Inadvertent Withdrawal of Single Rod Control Cluster Assembly (10 June 1993)
- Information Notice 1993-47, Unrecognized Loss of Control Room Annunciators (18 June 1993)
- Information Notice 1993-48, Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated Oil (6 July 1993)
- Information Notice 1993-49, Improper Integration of Software Into Operating Practices (8 July 1993)
... further results |
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