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, 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, 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 [[: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>. |
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 the
notice to alert addressees to a potential problem that could result from
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 no
contained in this information notice are not NRC requirements; therefore, specific action or written response is required.
Background
Westinghouse supplied the Braidwood Station RCPs, incorporating a three-stage 1 seal series arrangement to limit coolant flow up the pump shaft. The No.
riding face
seal, the main seal of the pump, is a controlled-leakage, film
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
the
system. In this manner, the primary coolant is prevented from entering liters
radial bearing and seal section of the pump unit. The remainder (11.4
[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 2 seal
chemical and volume control system. Minor flow passes through the No.
and its leakoff line to the reactor coolant drain tank. A back flush into
injection of 0.8 liters [0.21 gallons] per hour from a head tank flows of the
the No. 3 seal between its "double dam" seal area. At this point, half line
flow passes through one side of the seal and out the No. 2 seal leakoff
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 response. If
This information notice requires no specific action or writtenplease contact
you have any questions about the information in this notice, Office of
one of the technical contacts listed below or the appropriate
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 INSTAOPIPE
DRDRAIN IIMP
TO
REGENERATIWE1
HEAT
EXCHANGER
' LAl -NIN ThERL
sAN
ARRHER HEAT EXCHANGERF
"U.t,&
go 0 Zrt
aq ct
(D j O
xD
m 00 MS
0 t
I-'.
II-h
ID
w
LEAKOFF FLOW DIAGRAM
SIMPLIFIED BRAIDWOOD SEAL WATER INJECTION AND
I>
Attachment 2 IN 93-84 October 20 1993 Nuclear Westinghouse Page 1 of I
Services Technical Bulletin
Division
irts.ation or operation of Wastghous&suppi*d Nudr
An advisory notice of a recent technical development pertining to th- aIRonl, and initite action wh-r aomopriabt.
Plant equipment. Recipients shouSd evaluate the Information and recomnM
P.O. SOX 35, Pltttxzu PA 15o
REVISED PROCEDURES FOR ROP SHUTDOWN WITH NO.
.o
Subject NSD-TB- 93-01-RO
'.FAl I FAKA(LF OUTSIDE OPERATING UMITS
REACTOR COOLANT SYSTEM Date 03r3/9 System(s)
PLant ALL WESTINGHOUSE REACTOR COOLANT PUMPS WITH lr SO(s) 125 CONTROLLED LEAKAGE SEALS (See Aftacivelt B)
References _- -- , .nA~. cten
C 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
failure of the No. 1 Years of Westinghouse RCP operating experience has demonstrated that complete
in conjunction
seal is a rare occurrence. A complete failure is defined as excessive No. 1 seal leakage
or exceeding the maximum
with pump bearing/seal inlet and/or No. 1 leakoff temperatures approaching
leakoff be isolated
limits. Current operating procedures for failed No. 1 seals direct that the No. I seal
These procedures are specified in the RCP
within 5 minutes and RCP shutdown witlin 30 minutes.
instruction books or addenda to the books.
high and low leaking
After a review of current operating procedures and actual operating experiences with
emergency and orderly
No. 1 seals, it was concluded ftht distinct procedures could specify steps for both
procedures in this
RCP shutdowns. The two iems that follow have been incorporated into the revised
mrefers to a condition that is related
technical bulletin. As used within this bulletin, the term 'emergefly
as defined in
only to RCP operation and in no way pertains to emergency conditions for plant operation
a plant hnal Safety Analysis Report (FSAR).
the
I) A damaged No. 1 seal may produce debris or leak at a high enough rate to exceed
In the
injection rate and introduce unfiltered, high temperature reactor coolant into the seals.
for the
presence of debris. the ability of the No. 2 seal to survive and function as a backup
have pump
No. 1 seal is more favorable under static conditions. Thus, it is preferred to
shutdown precede No. 1 seal leakoff isolation.
0rawc Teb hoffl 412- 963-5634 or (W) 29-5634 AJol" W omutfi. Flequd. may be Obhuned fron @fe
Appmvi.
T. W. Dunn, Manager, Fied Service & RCP Engineerng L J.Haper
Ener Systes Saes Suport
'q7--t-. N
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corame inW"t "Pon or - wy reqpo-"kdy 1b "ik&ym
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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 to address a specfic RCP seal
If no alternative Westinghouse direction has been provided
the recommended shutdown procedures for
performance condition at a plant, the following are
gpm).
No. 1 seal leak rates outside the operating limits (08-6.0
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.
complete stop.
2) Isolate the No. 1 seal leakoff after the RCP has come to a
flow and
3) Monitor component cooling water (CCW) to ensure adequate
in the
manually override automatic isotation as required. (Local boiling
the CCW
thermal barrier of the affected pump may cause isolation of
system.)
has been
4) Do not restart the pump until the cause of the seal malfunction
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.
of
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 />
flow rate is
exceeding 6.0 gpm No. I seal flow. Ensure that seal injection
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. 1seal 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. 1sa 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. 1seal 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: 0
q4
3IF
0
Total No. 1seal flow a No. 1 leakoff plus No. 2 leakoff indications 0
oz
Pz n
wo
MD0
rt
a% ID
0 i2w~
0'-
P-a
(J.
%D
,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 10/07/93 All holders of OLs or CPs
Fuel Pool Cooling for boiling water reactors
Following A Loss of (BWRs).
Coolant Accident (LOCA)
93-82 Recent Fuel and Core 10/12/93 All holders of OLs or CPs
Performance Problems in for nuclear power reactors
Operating Reactors and all NRC-approved fuel
suppliers.
93-81 Implementation of 10/12/93 All holders of OLs or CPs
Engineering Expertise for nuclear power reactors.
on Shift
93-80 Implementation of the 10/08/93 All byproduct, source, and
Revised 10 CFR Part 20 and special nuclear material
licensees.
93-79 Core Shroud Cracking at 09/30/93 All holders of operating
Beltline Region Welds licenses or construction
in Boiling-Water Reactors permits for boiling-water
reactors (BWRs).
93-78 Inoperable Safety Systems 10/04/93 All holders of OLs or CPs
At A Non-Power Reactor for test and research
reactors.
93-77 Human Errors that Result 10/04/93 All nuclear fuel cycle
in Inadvertent Transfers licensees.
of Special Nuclear
Material at Fuel Cycle
Facilities
93-76 Inadequate Control of 09/21/93 All holders of OLs or CPs
Paint and Cleaners for for nuclear power reactors.
Safety-Related Equipment
93-75 Spurious Tripping of 09/17/93 All holders of OLs or CPs
Low-Voltage Power Circuit for nuclear power reactors.
Breakers with GE'RMS-9 Digital Trip Units
OL = Operating License
CP = Construction Permit
IN 93-84 October 14, 1993 If
This information notice requires no specific action or written response. contact
you have any questions about the information in this notice, please
of
one of the technical contacts listed below or the appropriate Office
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 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. I
Seal Leakage Outside Operating Limits"
3. List of Recently Issued NRC Information Notices
OFF *OGCB:DORS *SRXB:DSSA *SRI:DRP:RIII *TECH ED
NAME PCWen CYLiang SGDuPont MMejac
DATE 07/26/93 07/26/93 07/26/93 07/27/93
- SC/DRP:RIII *C/DRP:RIII *SC/SRXB:DSSA *C/SRXB:DSSA
MJFarber BClayton MACaruso RCJones
07/29/93 08/05-93 08/09/93
07/29/93
- D/DSSA *C/OGCB:DORS .4:;tes
ACThadani GHMarcus
09/23/93 09/28/93 10//r 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
OFF *OGCB:DORS *SRXB:DSSA *SRI:DRP:RIII *TECH ED
NAME PCWen CYLiang SGDuPont MMejac
DATE 07/26/93 07/26/93 07/26/93 07/27/93
- SC/DRP:RIII *C/DRP:RIII *SC/SRXB:DSSA *C/SRXB:DSSA
MJFarber BClayton MACaruso RCJones
07/29/93 07/29/93 08/05/93 08/09/93
- D/DSSA C/OGCB:DOi,_ D/DORS PcEY
ACThadani GHMarcu$s& !:' BKGrimesng P4it P (so-.-qI),MAM
09/23/93 DOCUMENT NAME: WRCPSEAL.We 049 /9o 0fFnfS T HE o3eevat lro
1hE NftC 41TA03rA* THS g*Sr*qWS
O0a'
- -. W""i r.MOFbV4'
_
( H&
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%,A _
dr itw LWI44n44t
U.
et
-K'%$ 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
OFF *OGCB:DORS *SRXB:DSSA *SRI:DRP:RIII *TECH ED
NAME PCWen CYLiang SGDuPont MMejac
DATE 07/26/93 07/26/93 07/26/93 07/27/93
- SC/DRP:RIII *C/DRP:RIII *SC/SRXB:DSSA *C/SRXB:DSSA
MJFarber BClayton MACaruso RCJones
AF 07/29/93 08/05/93 08/09/93
07/29/
D/DSS ai' _ C/OGCB:DORS D/DORS
ACThadani GHMarcus BKGrimes
09/2_/93 09/ /93 09/ /93 DOCUMENT NAME: WRCPSEAL.WEN
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
OFF *OGCB:DORS *SRXB:DSSA *SRI:DRP:RIII *TECH ED SC/SRXB:DSSAL
NAME PCWen CYLiang SGDuPont MMejac MACaruso `y r
DATE 07/26/93 O7/26/93 07/26/93 07/27/93 r/4r/93 / r
STW :I I I
RD C/R J.:RIII ,JSRXB:DSSA
MJFarber 4 BClayton C ones
07ial/93 J 07/< /93 ?//93 we 74FCoo .7,6/93 D/DSSA C/OGCB:DORS D/DORS
ACThadani GHMarcus BKGrimes
07/ /93 07/ /93 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 OCB:DORS SRXB SA L S I RIII TECH ED SC/SRXB:DSSA
NAME PCWen CYLiang _ SGDuPont MR- MMejac*M MACaruso
DATE 07/a6/93 07/;xb/93 V~ 07/Vb/93 T1-e'A.@i 07/1.7/93 07/ /93 SC/DRP:RIII C/DRP:RIII C/SRXB:DSSA
MJFarber BClayton RCJones
07/ /93 07/ /93 07/ /93 D/DSSA C/OGCB:DORS D/DORS
ACThadani GHMarcus BKGrimes
07/ /93 07/ /93 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, Topic: Uranium Hexafluoride, Overexposure)
- Information Notice 1993-05, Locking of Radiography Exposure Devices (14 January 1993, Topic: Uranium Hexafluoride, Inattentive)
- 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, Topic: Uranium Hexafluoride)
- 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, Topic: Uranium Hexafluoride)
- 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, 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, Topic: Thermal fatigue)
- 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, Thermal fatigue)
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure (26 March 1993, Topic: Commercial Grade, Thermal fatigue)
- Information Notice 1993-23, Weschler Instruments Model 252 Switchboard Meters (31 March 1993, Topic: Commercial Grade, Thermal fatigue)
- Information Notice 1993-24, Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner Standards (31 March 1993, Topic: Job Performance Measure, Thermal fatigue)
- Information Notice 1993-25, Electrical Penetration Assembly Degradation (1 April 1993, Topic: Thermal fatigue)
- 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, Topic: Commercial Grade)
- 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, Topic: Water hammer)
- Information Notice 1993-49, Improper Integration of Software Into Operating Practices (8 July 1993)
... further results |
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