Undetected Loss of Reactor CoolantML031130322 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, 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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill |
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Issue date: |
09/30/1987 |
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From: |
Rossi C Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-87-046, NUDOCS 8709240315 |
Download: ML031130322 (9) |
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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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill |
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Category:NRC Information Notice
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. 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 [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </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 [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </code>. |
SSINS No.: 6835
- IN 87-46 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 September 30, 1987, NRC INFORMATION NOTICE NO. 87-46: UNDETECTED LOSS OF REACTOR COOLANT
Addressees
All pressurized water reactor facilities holding an operating license or a
construction permit.
Purpose
- .*
This Information notice iss provided to alert recipients to potentially serious
operational errors that may result in the inadvertent loss of reactor coolant
system (RCS) inventory during abnormal system conditions. It is expected that
recipients will review this information for applicability to their reactor
facilities and consider actions, if appropriate, to prevent similar problems.
Suggestions contained In.this notice do not constitute NRC requirements;
therefore, no specific action or written response is required.
Description of Circumstances
On.June 21,. 1987, the North Anna Unit 1 operators discovered that approximately
17,000 gallons of reactor coolant had been lost from the RCS while the unit was
in cold shutdown. The delay in discovering.the inventory loss resulted from
1 the use of pressurizer level as an indication of reactor coolant inventory,
2 failure to use all available indications, (3) and failure to perform a mass
inventory balance.
On June 17, 1987, while making preparations to start up North Anna Unit 1 following a refueling outage, a problem developed with a reactor coolant pump
motor, requiring removal of the motor. When the problem was discovered, the
unit was at approximately 1950F, 325 psig, with a bubble in the pressurizer.
In order to establish plant conditions for removal of the motor (which may
involve leakage from the RCS), the plant would normally have been (1)cooled to
less than 1400F, (2)drained to mid-nozzle, and.(3) placed on the residual heat
removal system. In order to expedite the work, the plant was cooled to 110*F.,
and the pressurizer was cooled by filling the pressurizer while venting via the
power-operated relief valves (PORVs). The pressurizer level was lowered to 80%
with the PORVs open. The PORVs were then shut because the vapor space tempera- ture led the operators to believe a bubble still existed, and the level was
further lowered to 20%. This was done using a procedure that was not specifi- cally intended for draining the system. The operators did not realize that
lowering the level with the PORVs shut -- and subsequently cooling the pressur- izer -- caused a vacuum to form in the pressurizer, essentially holding the
pressurizer level at 20%.
IN 87-46 September 30, 1987 On June 18, 1987, the pump'motor was uncoupled and a small amount of expected
leakage (estimated 2 gallons-per minute) up the pump shaft was encountered.
This leakage was relatively clean water from the seal injection line past the
pump seals, which did not provide a tight seal when the motor was uncoupled.
Makeup to the RCS was from the volume control tank (VCT). The VCT level was
maintained with VCT pressure greater than reactor pressure. The operators
believed that maintaining the pressurizer level and VCT'level would maintain
the reactor coolant inventory by making up for any losses by flow from the VCT
to the RCS. Voids consisting of non-condensable gases and vapor formed in the
RCS and collected in the system high points (reactor vessel head and steam
generator tubes). The voids were not indicated by any decrease of the pressur- izer level.
On June 21, 1987, a decision was made to reduce the pump shaft leakage by
raising the pressurizer level, cycling the PORVs to vent the pressure,' and, then lowering the pressurizer level to draw a slight vacuum in the pressurizer.
This was a condition that already existed, but'the operators were unaware of
it. When the PORVs were cycled, the pressurizer relief tank pressure dropped, as well as the pressurizer level, indicating that a vacuum already existed in
the pressurizer. The reactor vessel level indicating system (RVLIS) indication
at this time was 79%; however, the operators were not monitoring this indica- tion because the system had been modified during the previous outage and the
operators thought it unreliable. Because of the recorder scale and the time
span visible on the RVLIS trend recorder, the change in the level indication
would-onl-yav&-been noticed (lLwtth aseparatelel -plotor
(2) by rolling
the chart back 12 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to compare it with the present indTcatf-or. Wh3en- -
the condition was discovered, the operators took action to make up to the RCS
and vent the reactor vessel head, as well as to check other available informa- tion to account for the system inventory. A total of 17,000 gallons of borated
water was required to reestablish the RCS inventory.
Discussion:
The principal error associated with this event is that the operator used only
pressurizer level as an indication of RCS inventory. The operator relied on
this single indication of inventory for an extended period with a known but
unquantified leak from the RCS, rather 'than using other available indications
to confirm reactor inventory.
The RYLIS level was available but was not used, as discussed previously. This
system was not reQuired to be operable while the reactor was shut down.
Recorded RVLIS readings in the recorder viewing window did not show a downward
trend in vessel level until the paper was removed from the recorder and evalu- ated for an extended period, because the level decrease was very gradual.
Also, several work request stickers on the RVLIS display had not been removed
following the modifications made during'the outage. In addition, an inventory
balance was not maintained to show how much water was being collected from the
leak compared with the amount of water being added to the system.
IN 87-46 September 30, 1987 The plant procedures were;not adequate for monitoring'the reactor coolant
inventory. The procedure used to establish plant conditions for removing the
motor did not contain appropriate instructions for monitoring and maintaining
RCS inventory..
The licensee is changing the procedure to require (1) a review of reactor
coolant system inventory and (2)routine surveillance of all available level
indication, including RYLIS.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the Regional
Administrator of the appropriate regional office or this office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: R. Croteau, RII
(404) 242-4668 Sam MacKay, NRR
(301) 492-8394 Attachment: List of Recently Issued NRC Information NIotices -.- . ; - . -,
Attachment
1K 87-46 Septembr 30, 1987 LIST OF RECEIILY ISSUEO
INFOPHATION NOTICES1987 Infrmteton Date of
NoticeNo. Subiect Issuance Issued to
57-45 RecentSefetytRelatiId 9/n5/57 All RRClicensees, Violations ef PC - autorized to poses
Requiremnts by Ift 1strial and use sealed sources
Radiograpy Licernsa is for industrlal radio.
graphy.
87.44 Thimble Tube Thimini qg In 3/16/57 All PWRfacilities
Wetinghou Reactop ts emplaying a M nuclear
$teem supplyfsystoi
holding in OLor CP.
87-43 CpS ton Neutron-AbSCereing M87 'All npcleai per
Material IN mgh.bof r41ty reactor fac1ities
Spent Fuel Storage bchS holding an OL or CP.
87.42 Ofesl Generetor Fus a 9/4/67 All nuclea ruer
Contacts reactor fac1 ities
holding an OL or CP.
87.41 el luree f Certaiw Seal 8131/87 All nuclear poWer
evenr Electric Cirevit reactor facilities
Breakers holdingas OL or CP.
87-40 Bachkseeting Volv& Iboutlnely B/31/87 - All n"ulea posr '
to Prevnt Pecking LLekage reactor facilities
holding so OL or CP.
87-31 Control of Not Perti cle 3/21/87 All nuclear poar
Contamination at Ng leer reactor facilities
PaverPlants and spent fuel
storage facilities
holdingan we
licenseor CP.
57-38 Inadequate or Inadve rtept 8/17/P All ,nucler1 cwer
8l1cking of Valvo Mevest reactor factitie
hol1ingao tL or CP.
OL* Opetig1conse
a Constrtin Permit
- -- ..4.A- . ___ - -
UNITED STATES FIRST CLASS MAIL
NUCLEAR REGULATORY COMMISSION POSTAGE 6 FENS PAID
USNRC
WASHINGTON, D.C. 2055 PERMIT No. O-II
OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE. $300
IN 87-46 September 30, 1987 The plant procedures were not adequate for monitoring the reactor coolant
inventory. The procedure used to establish plant conditions for removing the
motor did not contain appropriate instructions for monitoring and maintaining
RCS inventory.
The licensee is changing the procedure to require (1) a review of reactor
coolant system inventory and (2) routine surveillance of all available level
indication, including RYLIS.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the Regional
Administrator of the appropriate regional office or this office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: R. Croteau, RII
(404) 242-4668 Sam MacKay, NRR
(301) 492-8394 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
- C/OGCB:DOEA:NRR *PPMB:ARM *OGCB:DOEA:NRR *RI I
CHBerlinger TechEd SDMacKay MErnst
09/21/87 08/28/87 08/27/87 07/28/87
RCroteau FCantrell TPeebles VBrownlee LReyes
07/22/87 07/24/87 07/24/87 07/24/87 07/24/87
IN 87-XX
September xx, 1987 The plant procedures were not adequate for monitoring the reactor coolant
inventory. The procedure used to establish plant conditions for removing the
motor did not contain appropriate instructions for monitoring and maintaining
RCS inventory.
The licensee is changing the procedure to require (1) a review of reactor
coolant system inventory and (2) routine surveillance of all available level
indication, including RVLIS.
This information notice requires no specific action or written response. If
you have any questions about this matter, please contact the Regional Adminis- trator of the appropriate regional office or this office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: R. Croteau, RIT
(404) 242-4668 Sam MacKay, NRR
(301) 492-8394 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
D/DOEA:NRR C/OGCB:DOEt;jRR_ *PPMB:ARM *OGCB:DOEA:NRR *RI I
CERossi CHBerl ing:e( TechEd t' SDMacKay MErnst
09/ /87 09/X//87 oWN/T qjiI 08/27/87 07/28/87
RCroteau FCantrell TPeebles VBrownlee LReyes
07/22/87 807/24/87 07/24/87 07/24/87 07/24/87 e"-j
PN'y"c
IN 87-XX
September xx, 1987 situation degraded, RHR suction may have been lost. Had water level decreased
below the nozzles, the water In the pressurizer may have burped out to the
vessel, providing water for the RHR suction and indicating to the operators
that a problem existed.
The RVLIS level was available but was not used, as discussed previously. This
system was not required to be operable in modes 4, 5, and 6 by the Technical
Specifications. Recorded RVLIS readings in the recorder viewing window did not
show a downward trend in vessel level until the paper was removed from the
recorder and evaluated for an extended period since the level decrease was very
gradual. Also, several work requbtt stickers on the RVLIS display had not been
removed following the modifications made during the outage.
In addition, an inventory balance was not maintained that showed how much water
was being collected from the leak compared to the amount of water being added to
the system.
The procedure used to establish plant conditions for removing the motor was not
adequate and did not contain appropriate instructions for monitoring and
maintaining RCS inventory. The procedure was not written to establish the
conditions for which it was used in this case. Pressurizer level was the sole
means being used by the operators for RCS inventory indication.
The licensee is changing the procedure to require (1) a review of reactor
coolant system inventory and (2) routine surveillance of all available level
indication, including RVLIS. As stated in IN-87-23, the NRC is currently
considering generic action on the issue of loss of decay heat removal during
reduced water level operations.
This information notice requires no specific action or written response. If
you have any questions about this matter, please contact the Regional Adminis- trator of the appropriate regional office or this office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: R. Croteau, RIU
(404) 242-4668 Sam MacKay, NRR
(301) 492-8394 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
D/DOEA:NRR C/OGCB:DOEA:NRR *PPMB:ARM *OGCB:DOEA:NRR RII
gay PA'oAuel CERossi CHBerlinger TechEd SDMacKay JNGrace
08/ /87 08/ /87 08/28/87 08/27/87 08/ /87
- RIiS{ *RII *RII *RII *RII *RII
RCroteau FCantrell TPeebles VBrownlee LReyes MErnst
7/22/87 7/24/87 7/24/87 7/24/87 7/24/87 7/28/87
IN 87-XX
August xx, 1987 lost. Had water level decreased below the nozzles, the water in the pressur- izer may have burped out to the vessel providing water for RHR suction and
indication to the operators that a problem existed.
RVLIS level was available but not used as discussed previously. This system
was not required to be operable in modes 4, 5, and 6 by the Technical Specifi- cations. Recorded RVLIS readings in the recorder viewing window did not show a
downward trend in vessel level until the paper was removed from the recorder
and evaluated for an extended period since the level decrease was very gradual.
Also, several work request stickers on the RVLIS display had not been removed
following the modifications made during the outage.
In addition, an inventory balance was not maintained showing how much water was
being collected from the leak compared to the amount of water being added to
the system.
The procedure used to establish plant conditions for removing the motor was not
adequate and did not contain appropriate instructions for monitoring and
maintaining reactor coolant system inventory. The procedure utilized was not
written to establish the conditions for which it was used in this case.
Pressurizer level was the sole means being used by the operators for reactor
coolant system inventory indication.
The licensee is changing the procedure to require (1) a review of reactor
coolant system inventory and (2) routine surveillance of all available level
indication including RVLIS. As stated in IN-87-23, the NRC is currently
considering generic action on the issue of loss of decay heat removal during
reduced water level operations.
This information notice requires no specific action or written response. If
you have any questions about this matter, please contact the Regional Adminis- trator of the appropriate regional office or this office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: R. Croteau, RII
(404) 242-4668 Sam MacKay, NRR
(301) 492-8394 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
D/DOEA:NRR C/OGCB:DOEA:NRR PPMB:AjM OGCB:DOEA:NRR RII
CERossi CHBerlinger Techw SDftacKay5' JNGrace
08/ /87 08/ /87 08/$A87 08/z7/87 08/ /87
- RII *RII *RII *RII *RII *RII
RCroteau FCantrell TPeebles VBrownlee LReyes MErnst
7/22/87 7/24/87 7/24/87 7/24/87 7/24/87 7/28/87
N
v 3 RMLIS level was available but not used as discussed previously. This system
was not required to be operable in modes 4, 5, and 6 by the Technical
Specifications. Recorded RVLIS readings in the recorder viewing window did not
show a downward trend in vessel level until the paper was removed from the
recorder and evaluated for an extended period since the level decrease was very
gradual. Also, several work request stickers on the RVLIS display had not been
removed following the modifications made during the outage.
In addition, an inventory balance was not maintained showing how much water was
being collected from the leak compared to the amount of water being added to
the system.
The procedure used to establish plant conditions for removing the motor was not
adequate and did not contain appropriate instructions for monitoring and
maintaining reactor coolant system inventory. The procedure utilized was not
written to establish the conditions for which it was used in this case.
Pressurizer level was the sole means being used by the operators for reactor
coolant system inventory indication.
Following this event, the licensee is changing the procedure used to require (1)
a review of reactor coolant system makeup and loss inventory and (2) routine
surveillance of all available level indication including RVLIS. As stated in
IN-87-23, the NRC is currently considering generic action on the issue of loss
of decay heat removal during reduced level evolutions.
This Information Notice requires no specific action or written response. If
you have any questions about this matter, please contact the Regional
Administrator of the appropriate Regional Office or this office.
Charles E. Rossi, Director
Division of Operational Events
Assessment
Office of Nuclear Reactor Regulation
Technical Contacts:
Attachment:
List of Recently Issued NRC X
Information Notices
I RII RII RII RI RII RII
roteau:jt Reantrell Tzeebles lJwniee yes JN e
V87 e7/j%/87 7/xy/87 7 /87
/7
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list | - Information Notice 1987-02, Inadequate Seismic Qualification of Diaphragm Valves by Mathematical Modeling and Analysis (13 January 1987, Topic: Boric Acid, Overspeed trip)
- Information Notice 1987-03, Segregation of Hazardous and Low-Level Radioactive Wastes (15 January 1987, Topic: Boric Acid, Overspeed trip)
- Information Notice 1987-04, Diesel Generator Fails Test Because of Degraded Fuel (16 January 1987, Topic: Boric Acid, Coatings)
- Information Notice 1987-05, Miswiring in a Westinghouse Rod Control System (2 February 1987, Topic: Unanalyzed Condition, Boric Acid)
- Information Notice 1987-06, Loss of Suction to Low-Pressure Service Water System Pumps Resulting from Loss of Siphon (30 January 1987, Topic: Boric Acid)
- Information Notice 1987-07, Quality Control of Onsite Dewatering/Solidification Operations by Outside Contractors (3 February 1987, Topic: Boric Acid, Process Control Program)
- Information Notice 1987-08, Degraded Motor Leads in Limitorque DC Motor Operators (4 February 1987, Topic: Boric Acid, Anchor Darling)
- Information Notice 1987-09, Emergency Diesel Generator Room Cooling Design Deficiency (5 February 1987, Topic: Probabilistic Risk Assessment)
- Information Notice 1987-10, Potential for Water Hammer During Restart of Residual Heat Removal Pumps (11 February 1987, Topic: Water hammer)
- Information Notice 1987-11, Enclosure of Vital Equipment within Designated Vital Areas (13 February 1987, Topic: Contraband, Water hammer)
- Information Notice 1987-11, Enclosure of Vital Equipment Within Designated Vital Areas (13 February 1987, Topic: Contraband, Water hammer)
- Information Notice 1987-12, Potential Problems with Metal Clad Circuit Breakers, General Electric Type AKF-2-25 (13 February 1987, Topic: Water hammer)
- Information Notice 1987-13, Potential for High Radiation Fields Following Loss of Water from Fuel Pool (24 February 1987, Topic: Water hammer)
- Information Notice 1987-14, Actuation of Fire Suppression System Causing Inoperability of Safety-Related Ventilation Equipment (23 March 1987, Topic: Water hammer)
- Information Notice 1987-15, Compliance with the Posting Requirements of Subsection 223b of the Atomic Energy Act of 1954, as Amended (25 March 1987)
- Information Notice 1987-15, Compliance with the Posting Requirements of Subsection 223B of the Atomic Energy Act of 1954, As Amended (25 March 1987)
- Information Notice 1987-16, Degradation of Static O Ring Pressure Switches (2 April 1987, Topic: Commercial Grade)
- Information Notice 1987-17, Response Time of Scram Instrument Volume Level Detectors (7 April 1987, Topic: Scram Discharge Volume, Water hammer)
- Information Notice 1987-18, Unauthorized Service on Teletherapy Units by Nonlicensed Maintenance Personnel (8 April 1987, Topic: Water hammer)
- Information Notice 1987-19, Perforation and Cracking of Rod Cluster Control Assemblies (9 April 1987)
- Information Notice 1987-20, Hydrogen Leak in Auxiliary Building (20 April 1987, Topic: Excess Flow Check Valve)
- Information Notice 1987-21, Shutdown Order Issued Because Licensed Operators Asleep While on Duty (11 May 1987, Topic: Inattentive)
- Information Notice 1987-22, Operator Licensing Requalification Examinations at Nonpower Reactors (22 May 1987, Topic: License Renewal)
- Information Notice 1987-23, Loss of Decay Heat Removal During Low Reactor Coolant Level Operation (27 May 1987, Topic: Boric Acid)
- Information Notice 1987-24, Operational Experience Involving Losses of Electrical Inverters (4 June 1987)
- Information Notice 1987-25, Potentially Significant Problems Resulting from Human Error Involving Wrong Unit, Wrong Train, or Wrong Component Events (11 June 1987, Topic: Boric Acid, Fire Watch, Overspeed trip)
- Information Notice 1987-25, Potentially Significant Problems Resulting From Human Error Involving Wrong Unit, Wrong Train, or Wrong Component Events (11 June 1987, Topic: Boric Acid, Fire Watch, Overspeed)
- Information Notice 1987-26, Cracks in Stiffening Rings on 48-Inch-Diameter UF6 Cylinders (11 June 1987, Topic: Boric Acid)
- Information Notice 1987-26, Cracks in Stiffening Rings on 48-Inch-Diameter Uf6 Cylinders (11 June 1987)
- Information Notice 1987-27, Iranian Official Implies Vague Threat to U.S. Resources (10 June 1987, Topic: Boric Acid)
- Information Notice 1987-28, Air Systems Problems at U.S. Light Water Reactors (28 December 1987, Topic: Boric Acid)
- Information Notice 1987-29, Recent Safety-Related Incidents at Large Irradiators (26 June 1987, Topic: Coatings, Temporary Modification, Biofouling, Uranium Hexafluoride)
- Information Notice 1987-30, Cracking of Surge Ring Brackets in Large General Electric Company Electric Motors (2 July 1987)
- Information Notice 1987-31, Blocking Bracing, and Securing of Radioactive Materials Packages in Transportation (10 July 1987, Topic: Uranium Hexafluoride)
- Information Notice 1987-32, Deficiencies in the Testing of Nuclear-Grade Activated Charcoal (10 July 1987)
- Information Notice 1987-33, Applicability of 10 CFR Part 21 to Nonlicensees (24 July 1987, Topic: Commercial Grade)
- Information Notice 1987-34, Single Failures in Auxiliary Feedwater Systems (24 July 1987)
- Information Notice 1987-35, Reactor Trip Breaker, Westinghouse Model DS-416, Failed to Open on Manual Initiation from the Control Room (30 July 1987)
- Information Notice 1987-36, Significant Unexpected Erosion of Feedwater Lines (4 August 1987)
- Information Notice 1987-37, Compliance with the General License Provisions of 10 CFR Part 31 (10 August 1987)
- Information Notice 1987-39, Control of Particle Contamination at Nuclear Power Plants (21 August 1987, Topic: Fuel cladding, Overexposure)
- Information Notice 1987-40, Backseating Valves Routinely to Prevent Packing Leakage (31 August 1987, Topic: Packing leak)
- Information Notice 1987-41, Failures of Certain Brown Boveri Electric Circuit Breakers (31 August 1987)
- Information Notice 1987-42, Diesel Generator Fuse Contacts (4 September 1987)
- Information Notice 1987-43, Gaps in Neutron-Absorbing Material in High-Density Spent Fuel Storage Racks (8 September 1987)
- Information Notice 1987-44, Thimble Tube Thinning in Westinghouse Reactors (16 September 1987)
- Information Notice 1987-45, Recent Safety-Related Violations of NRC Requirements by Industrial Radiography Licensees (25 September 1987, Topic: High Radiation Area, Overexposure)
- Information Notice 1987-46, Undetected Loss of Reactor Coolant (30 September 1987)
- Information Notice 1987-48, Information Concerning the Use of Anaerobic Adhesive/Sealants (9 October 1987, Topic: Loctite)
- Information Notice 1987-49, Deficiencies in Outside Containment Flooding Protection (9 October 1987, Topic: Safe Shutdown)
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