Inadequate Net Positive Suction Head in Low Pressure Safety SystemsML031180034 |
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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
12/09/1987 |
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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-87-063, NUDOCS 8712030052 |
Download: ML031180034 (7) |
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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 |
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Category:NRC Information Notice
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[: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]] </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]] </code>. |
IN P7-63 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 December 9, 1987 NRC INFORMATION NOTICE NO. 87-63: INADEQUATE NET POSITIVE SUCTION HEAD
IN LOW PRESSURE SAFETY SYSTEMS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
This information notice is being provided to alert addressees to problems which
could result in inadequate net positive suction head (NPSH) at the inlet to the
low pressure pumps following a loss-of-coolant accident (LOCA). It is expected
that recipients will review the information for applicability to their facili- ties and consider actions, as appropriate, to avoid similar problems. However, suggestions contained in this information notice do not constitute NRC reauire- ments; therefore, no specific action or written response is required.
Description of Circumstances
A Nuclear Regulatory Commission review has identified several similar reported
problems related to excessive flow rates in low pressure safety systems that
could occur following a LOCA. Higher than expected flow rates in the pump
discharge lines can lead to lower than calculated suction line pressures and
consequently to inadequate pump NPSH.
On.May 19, 1987, Turkey Point, Unit 3, personnel reported that during a reexam- ination of the containment spray (CS) system the hydraulic resistance of the CS
system was found to be less than that assumed in the design calculations.
Furthermore, they reported that adequate NPSH for the CS pumps could not be
assured during the injection phase following a LOCA when the CS system was
drawing water from the refueling water storage tank. This deficiency was
caused by missing flow orifices in the pump discharge lines that were assumed
in the system design but never installed. The licensee corrected the problem
by installing the missing flow orifices and reported the event in Licensee
Event Report 250-87-014.
On December 12, 1986, while designing modifications for the facility residual
heat removal (RIR) system, the Haddam Neck licensee discovered that pump
cavitation could occur in the low pressure pumps during the recirculation phase
ERA05
--,IN 87-63 December 9, 1987 following a LOCA (in a narrow range of break sizes). A combination of break
flow, a system arrangement where the high pressure pumps are downstream of the
low pressure pumps, and a certain volume of water in the containment sump at
the time of switchover from the injection to the recirculation phase all
contributed to the scenario in which inadeauate NPSH would exist at the low
pressure pump inlet. The licensee corrected the problem by throttling the RHR
system control valves to balance the flowpaths and effectively increase the
system hydraulic resistance on the low pressure pump discharge line while
maintaining minimum flow requirements.
On March 31, 1986, the Trojan licensee discovered that there would be inade- quate NPSH at the inlet to the low pressure pumps of the emergency core cooling
system (ECCS) at Trojan under certain accident conditions. During the recircu- lation phase following a LOCA, two low pressure pumps feed the charging pumps, the safety injection pumps, and the cold leg injection paths. If only one low
pressure pump is operating (accounting for a single failure) and the cross-tie
between ECCS trains is open, the low pressure pump NPSH would be deficient by
about 10 feet. The licensee corrected the problem by modifving procedures to
(1) isolate the cross-tie between trains prior to entering the recirculation
phase and (2) secure ell other pumps in the same-train as the inoperable low
pressure pump.
In July 1977, the Farley, Unit 1, licensee reported that the residual heat
removal (RHR) pump flow rate at that facility would be significantly above the
expected flow rate during the cold leg recirculation mode of operation follow- ing a LOCA. Investigations by the licensee revealed that the high flow rates
were due to lower than expected hydraulic resistances in the RHR pump discharge
piping. The actual roughness of the installed piping was less than the stan- dard commercial steel roughness assumed in the calculations, and the hydraulic
resistance of installed check valves was less than estimated. Consequently, the licensee installed orifices in the pump discharge piping to reduce the flow
to a rate that would provide adequate NPSH at the low pressure pumps under all
post-LOCA conditions.
Discussion:
Inadequate FPSH can cause pump cavitation and lead to pump unavailability.
Identification of deficiencies in system design, installation, or operation
that could result in inadequate WPSH can occur in any type of pump system
arrangement and may require more than a review of the original design calcula- tions, as noted by the above mentioned events. In general, pump availability
may also be affected by sudden suction pressure oscillations durina pump starts
that may cause unexpected pump trips. This is discussed in NRC Information
Notice 87-53, "Auxiliary Feedwater Pump Trips Resulting From Low Suction
Pressure".
IN 87-63 December 9, 1987 No specific action or written response is required
If you have any questions about this matter, please by this information notice.
contact listed below or the Regional Administrator contact the technical
of the appropriate regional
office.
arles E.R oss Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Sanford Israel, AEOD
(301) 492-4437 Attachment: List of Recently Issued NRC Information Notices
Attachlent 1 IN 17.63 December to ItS?
LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES 1I7 snTcnnasan
Notice No.
Dte oa
SU..... Mssuance Issued to
£7-62 Pechsnical Failure of 17/S/87 All holders of OLe
Indicating-Type fuses or CPs for nuclear
power reactors
£7.61 Failure of Westinghouse 12/7/67 All holders of OLs
1.Type Circuit Breaker or CPs for nuclear
Cell Stches. power reactors.
67-60 Depressurlzation of Reactor 12/4/87 All holders of OLs
Coolant Systems in or CPSfor MWRs.
Pressuriaed-Wattr Peactors
C6-108 Deoradation of Reactor 11/19J/7 All holders of OLs
SupP. Coolant System Pressure or CPe for nuclear
- oundary 14sulting from power reactors.
Boric Acid Corrosion
87-59 Potential RHR Pump Loss 11/17/87 All holden of OLe
or CPS for nuclear
power reactors.
S7-58 continuous Ctiniou~cationa 11/16/87 All nuclear PMwer
Pei lowing Emergency reactor facilities
Notifications holding an OL and
the following fuel
facilities that have
Emergency Notification
Systes: Nuclear
Fuel Services. Erwin.
TN; general Atomics, San Diego, CAI UNC,
Nontvillle CTI and
Navy, Lynchburg. VA.
87-57 Less of EWrgency Boration 11/6/87 All holders of OLs
Capability Due to Nitrogen or CPs for nuclear
Gas Intrusion power reactors.
87.56 improper IPydraulic Control 11/4/87 All holders of OLs
Unit Installation at *WR or CPS for boiling
Plants. water reactors (BWRs).
OL
CP
FIRSTCLASSMAF1 UNITED STATES IP0STA8t & Fasa PAID
UCLEAR REGULATORY COMMISSION
WASHINGTON, D.C. 20555 USNRCJ
OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE, $300
imW
IN 87-63 December 9, 1987 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate regional
office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Sanford Israel, AEOD
(301) 492-4437 Attachment: List of Recently Issued NRC Information Notices
CA E S)
(TRANSMITTED BY MEMORANDUM TO C.E.ROSSI FROM T.M.NOVAK DATED OCTOBER 7, 1987)
- SEE PREVIOUS CONCURRENCES
- OGCB:DOEA:NRR *ROAB:DSP:AEOD *PPMB:ARM
JGuillen
11/06/87 SIsrael
11/06/87 TechEd
11/06/87
CHBerlinger
11/17/87
4'12
12/B5/81
4
IN 87-XX
November xx, 1987 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate regional
office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Sanford Israel, AEOD
(301) 492-4437 Attachment: List of Recently Issued NRC Information Notices
OA ache
- SEE PREVIOUS CONCURRENCES
- OGCB:DOEA:NRR *ROAB:DSP:AEOD *PPMB:ARM C/OGCB2E:NRR D/DOEA:NRR
JGuillen SIsrael TechEd CHBerlinger CERossi
11/06/87 11/06/87 11/06/87 11/7/187 11/ /87
IN 87-XX
November xx, 1987 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate regional
office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Sanford Israel, AEOD
(301) 492-4437 Attachment: List of Recently Issued NRC Information Notices
OGC :
A~RR Abk SP:AEOD PPMB:ARM4/ C/OGCB:DOEA:NRR D/DOEA:NRR
JGu i~ SIsrael TechEdaU CHBerlinger CERossi
II/L I7 II/V/87 11/(1/87 11/ /87 11/ /87
|
---|
|
list | - Information Notice 1987-02, Inadequate Seismic Qualification of Diaphragm Valves by Mathematical Modeling and Analysis (13 January 1987, Topic: Boric Acid)
- Information Notice 1987-03, Segregation of Hazardous and Low-Level Radioactive Wastes (15 January 1987, Topic: Boric Acid)
- 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)
- Information Notice 1987-11, Enclosure of Vital Equipment within Designated Vital Areas (13 February 1987, Topic: Contraband)
- Information Notice 1987-11, Enclosure of Vital Equipment Within Designated Vital Areas (13 February 1987, Topic: Contraband)
- Information Notice 1987-12, Potential Problems with Metal Clad Circuit Breakers, General Electric Type AKF-2-25 (13 February 1987)
- Information Notice 1987-13, Potential for High Radiation Fields Following Loss of Water from Fuel Pool (24 February 1987)
- 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)
- Information Notice 1987-17, Response Time of Scram Instrument Volume Level Detectors (7 April 1987, Topic: Scram Discharge Volume)
- Information Notice 1987-18, Unauthorized Service on Teletherapy Units by Nonlicensed Maintenance Personnel (8 April 1987)
- 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)
- 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)
- 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)
- 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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