Steam Generator

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The steam generator is the component between the high pressure primary loop and secondary loop of a PWR.

There are two, three, or four loop steam generators reactor models. Each steam generator can measure up to 70 feet (21 m) in height and weigh as much as 800 tons. Each steam generator can contain anywhere from 3,000 to 16,000 tubes, each about .75 inches (19 mm) in diameter. The coolant (treated water), which is maintained at high pressure to prevent boiling, is pumped through the nuclear reactor core. Heat transfer takes place between the reactor core and the circulating water and the coolant is then pumped through the primary tube side of the steam generator by coolant pumps before returning to the reactor core. This is referred to as the primary loop.

That water flowing through the steam generator boils water on the shell side (which is kept at a lower pressure than the primary side) to produce steam. This is referred to as the secondary loop. The secondary-side steam is delivered to the turbines to make electricity. The steam is subsequently condensed via cooled water from a tertiary loop and returned to the steam generator to be heated once again. The tertiary cooling water may be recirculated to cooling towers where it sheds waste heat before returning to condense more steam. Once-through tertiary cooling may otherwise be provided by a river, lake, or ocean. This primary, secondary, tertiary cooling scheme is the basis of the pressurized water reactor.

Reactor Scrams

Feedwater supplies the water to the secondary loop and if it stops supplying water, the water level decreases. If the steam generators can't extract heat from the reactor then pressure and temperature would increase; therefore, a manual Scram may be initiated.

 TitleSiteReactor type 
05000244/LER-2002-0010 LER 2002-001, Loss of "A" Condenser Circulating Water Pump Results inR.E. Ginna Nuclear Power Plant0 Page: 1 Of 8
05000244/LER-2005-001Failure of ADFCS Power Supplies Results in Plant TripDocket Number
05000244/LER-2007-002Closure of Main Steam Isolation Valve Results in Safety Injection Signal and Plant Trip
05000244/LER-2011-003Reactor Trip Due to Failure of Turbine Lube Oil PipingGinnaWestinghouse PWR 2-Loop
05000244/LER-2013-002Reactor Trip Due to Generator Trip During Main Generator Reactive Power TestingGinnaWestinghouse PWR 2-Loop
05000247/FIN-2013002-01Inadequate Maintenance Procedure Results in a Reactor TripIndian PointWestinghouse PWR 4-Loop
05000247/LER-2001-001
05000247/LER-2001-007Docket Number
05000247/LER-2002-003Docket Number
05000247/LER-2003-003Docket Number
05000247/LER-2003-0041 OF T 6Indian Point Unit 2
05000247/LER-2004-001Manual Reactor Trip Due to Oscillating Feedwater Flow and Steam Generator Level with Flow Perturbations Caused by a Degraded Feed Water Regulating ValveDocket Number
05000247/LER-2004-002Manual Reactor Trip Due to Decreasing 23 Steam Generator Level Caused by Feedwater Regulating Valve Closure Due to a De-energized Solenoid Operated Valve from Wiring FailureDocket Number
05000247/LER-2004-005Automatic Reactor Trip Due to Turbine Generator Trip Caused by Low Stator Cooling Water PressureIndian Point Unit 2
05000247/LER-2005-004Automatic Start of both Motor Driven Auxiliary Feedwater Pumps Due to 22 Steam Generator High-High Level Signal Caused by Overfeeding Due to Personnel ErrorDocket Number
05000247/LER-2006-003Manual Reactor Trip Due to a Mismatch Between Reactor Power and Turbine Load Caused by Cycling of Steam Dump Valves After a Power Reduction for Loss of Heater Drain Tank PumpsDocket Number
05000247/LER-2006-005Automatic Reactor Trip Due to a Turbine Trip as a Result of a Main Generator Exciter Protective Trip Caused by a Generrex Power Supply Loss of Electrical GroundDocket Number
05000247/LER-2008-001Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused by Loss of Feedwater Flow as a Result of Feedwater Pump Speed Control MalfunctionDocket Number
05000247/LER-2008-003Docket Number
05000247/LER-2009-002Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused by a Loss of Main Feedwater Pump 21 and Failure of the Main Turbine to Automatically RunbackIndian PointWestinghouse PWR 4-Loop
05000247/LER-2009-005450 Broadway, GSB
P.O. Box 249
Buchanan, N.Y. 10511-0249Entergy Tel (914) 734-6700
J. E. Pollock
Site Vice President
NL-09-159
January 4, 2010
U.S. Nuclear Regulatory Commission


Attn: Document Control Desk
Mail Stop 0-P1-17
Washington, D.C. 20555-0001
SUBJECT:MLicensee Event Report # 2009-005-00, "Automatic Reactor Trip Due to a
Turbine-Generator Exciter Protective Trip Caused by a Loss of the
Generrex Power Supply Monitored Voltage Due to a High Resistance
Ground Connection"
Indian Point Unit No. 2
Docket No. 50-247
DPR-26
Dear Sir or Madam:
Pursuant to 10 CFR 50.73(a)(1), Entergy Nuclear Operations Inc. (ENO) hereby provides
Licensee Event Report (LER) 2009-005-00. The attached LER identifies an event where
the reactor was automatically tripped, which is reportable under 10 CFR
50.73(a)(2)(iv)(A) . As a result of the reactor trip, the Auxiliary Feedwater System was
actuated and the Main Steam Isolation Valves (MSIVs) were closed which is also
reportable under 10 CFR 50.73(a)(2)(iv)(A). This condition was recorded in the Entergy
Corrective Action Program as Condition Report CR-IP2-2009-04530.
There are no new commitments identified in this letter. Should you have any questions
regarding this submittal, please contact Mr. Robert Walpole, Manager, Licensing at
(914) 734-6710.
Sincerely,
-qrsuer-Pc,a
JEP/cbr
cc:MMr. Samuel J Collins, Regional Administrator, NRC Region I
NRC Resident Inspector's Office, Indian Point 2
Mr. Paul Eddy, New York State Public Service Commission
LEREvents@inpo.org


NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES: 8/31/2010
(9-2007)D•
Estimated burden per response to comply with this mandatory collection
request: 50 hours.DReported lessons learned are incorporated into the
licensing process and fed back to industry. Send comments regarding burden
estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internetLICENSEE EVENT REPORT (LER) e-mail to infocollects@ nrc.gov, and to the Desk Officer, Office of Information
and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and
Budget, Washington, DC 20503. If a means used to impose an information
collection does not display a currently valid OMB control number, the NRC may
not conduct or sponsor, and a person is not required to respond to, the
information collection.
1. FACILITY NAME: INDIAN POINT 2 2. DOCKET NUMBER 1 3. PAGE
05000-247 1TOF 5
4. TITLE: Automatic Reactor Trip Due to a Turbine-Generator Exciter Protective Trip Caused by a
Loss of the Generrex Power Supply Monitored Voltage Due to a High Resistance Ground
Connection
Indian PointWestinghouse PWR 4-Loop
05000247/LER-2010-007Automatic Reactor Trip Due to a Turbine Trip as a Result of a High Steam Generator Level Trip After Transition to Single Feedwater Purilp OperationIndian PointWestinghouse PWR 4-Loop
05000247/LER-2010-009Automatic Reactor Trip Due to a Turbine-Generator Trip Caused by a Fault of the 21 Main Transformer Phase B High Voltage BushingIndian PointWestinghouse PWR 4-Loop
05000247/LER-2013-001Manual Reactor Trip as a Result of Decreasing Steam Generator Water Levels Caused by the Trip of Both Heater Drain Tank Pumps During AOV Diagnostic TestingIndian PointWestinghouse PWR 4-Loop
05000247/LER-2013-003Manual Reactor Trip Due to Decreasing Steam Generator Water Levels Due to Loss of Main Feedwater (FW) Flow Caused by a Loss of Instrument Air to the FW Regulating ValvesIndian PointWestinghouse PWR 4-Loop
05000247/LER-2016-009Automatic Reactor Trip Due to Actuation of the Trip Logic of the Reactor Protection System During Preparation for TestingIndian PointWestinghouse PWR 4-Loop
05000247/LER-2017-001Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused By Main Boiler Feedwater Pump Turbine Low Pressure Governor Valves Failed Closed
LER 17-001-00 for Indian Point, Unit 2 Regarding Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused By Main Boiler Feedwater Pump Turbine Low Pressure Governor Valves Failed Closed
Indian PointWestinghouse PWR 4-Loop
05000247/LER-2017-002Auxiliary Feedwater Flow Indication Inoperable for Longer Than the Allowed Technical Specification Completion Time Due to Failure of Complete Restoration Following Calibration
LER 17-002-00 for Indian Point, Unit 2 Regarding Auxiliary Feedwater Flow Indication Inoperable for Longer Than the Allowed Technical Specification Completion Time Due to Failure of Complete Restoration Following Calibration
Indian PointWestinghouse PWR 4-Loop
05000250/LER-2001-003Docket Number
05000250/LER-2003-006Technical Specification Required Shutdown Due to Inoperable Containment Isolation Valve CV 3-200BTurkey PointWestinghouse PWR 3-Loop
05000250/LER-2004-006Manual Reactor Trip Due to Fire in the High Pressure Turbine Area
05000250/LER-2004-007Manual Reactor Trip Due to Main Generator Exciter Turbine Cooling Water Leak
05000250/LER-2005-005Manual Reactor Trip Due To Decrease in the 3C Steam Generator Level
05000250/LER-2005-006Incorrect Installation of the Inboard Journal Bearing in Auxiliary Feedwater Pump BDocket Number
05000250/LER-2010-006Turkey Point Unit 3Turkey PointWestinghouse PWR 3-Loop
05000250/LER-2011-0011 of 3Turkey PointWestinghouse PWR 3-Loop
05000250/LER-2013-002Automatic Reactor Trip due to Low Condenser VacuumTurkey PointWestinghouse PWR 3-Loop
05000250/LER-2013-006Reactor Protection and Auxiliary Feed Water System Actuations Due to Trip of Operating Feedwater PumpTurkey PointWestinghouse PWR 3-Loop
05000250/LER-2014-005Manual Reactor Trip Due to Loss of Instrument AirTurkey PointWestinghouse PWR 3-Loop
05000251/FIN-2015002-01Inadequate General Operating Procedure to Prevent Inadvertent AFAS While Performing a Reactor Plant Planned ShutdownTurkey PointWestinghouse PWR 3-Loop
05000251/FIN-2017004-03Inadequate Installation of Outdoor Use Electrical Enclosures Results in Manual Reactor TripTurkey PointWestinghouse PWR 3-Loop
05000251/LER-2004-002AAADocket Number
05000251/LER-2004-004Turkey Point Unit 4 05000251 1 OF 4Docket Number
05000251/LER-2005-001Steam Generator Feedwater Pump Trip Leading to Manual Reactor Trip and Auxiliary Feedwater Actuation
05000251/LER-2005-002Revised Automatic Reactor Trip due to Turkey Point Unit 4 Main Transformer Failure
05000251/LER-2008-001Manual Reactor Trip due to High Level in the 4A Steam GeneratorDocket Number
05000251/LER-2010-002Reactor Trip Resulting from Steam Generator Feedwater Pump TripTurkey PointWestinghouse PWR 3-Loop
05000251/LER-2010-004Reactor trip during Replacement of Degraded Relay in the Reactor Protection System
05000251/LER-2010-006Turkey Point Unit 4Turkey PointWestinghouse PWR 3-Loop
05000251/LER-2015-001Automatic Auxiliary Feedwater System Actuation during a Planned Reactor TripTurkey PointWestinghouse PWR 3-Loop
... further results

See also