Setpoint Testing of Pressurizer Safety Valves with Filled Loop Seals Using Hydraulic Assist DevicesML031150163 |
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: |
08/22/1988 |
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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-88-068, NUDOCS 8808160451 |
Download: ML031150163 (6) |
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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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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>. |
UNITED STATES
NUCLEAR REGULATORY CQOMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 August 22, 1988 NRC INFORMATION NOTICE NO. 88-68: SETPOINT TESTING OF PRESSURIZER SAFETY
VALVES WITH FILLED LOOP SEALS USING
HYDRAULIC ASSIST DEVICES
Addressees
permits for nuclear power
All holders of operating licenses or construction
reactors.
Purpose
to alert addressees to potentially
This information notice is being provided testing of pressurizer safety valves
generic problems that have occurred duringassist device. Use of hydraulic
with filled loop seals using a hydraulic results for safety valve setpoint
assist devices may result in inaccurateto water or two-phase flow. It is
testing when the valves are subjected information for applicability to their
expected that recipients will review the
facilities and consider actions, asthisappropriate. to avoid similar problems.
notice do not constitute NRC require- However, suggestions contained in written response is required.
ments; therefore, no specific action or
Description of Circumstances
Canyon 1 tested the three pressur- On August 30, 1986, the licensee of Diablo using a hydraulic assist device.
izer safety valves with the loop seal filled
as 2747.8, 3028.0, and 2661.0 psig for
The initial lift points were reported respectively. The required setpoint for
valves number RCS-1-8010A, B, and C, method monitored hydraulic pressure on
the valves was 2485+/-1% psig. The test stem displacement to infer lift point.
the test rig for an indication of valve lift point was not accurate on the
The licensee concluded that the inferred drained. Water moving through the
first lift because the loop seal was not because of the different
seat area produced little valve stem displacement then entered the valves at an
physical properties of steam and water. Steam displacement, resulting in the
elevated hydraulic pressure and caused a larger After the loop seal was
point.
prediction of an inaccurately high lift were
points of the valves measured again and found to be
drained, the lift
(2485+/-1%) at 2464, 2493, and 2503 within technical specification (TS) limits
psig (LER 50/275-86/018).
2 tested the setpoints of the
On April 2, 1988, the licensee of Sequoyah low setpoints could be the cause of
pressurizer safety valves to determine if A hydraulic assist device
the leakage that the valves had been experiencing.
a80451 s
IN 88-68 August 22, 1988 was used with reactor pressure between 1700 psig and normal operating pressure, and with a water seal at the valve seat maintained at an elevated temperature
by external heaters. The lifting force required to open the valve was measured
by a load cell and recorded on a strip chart to provide data necessary to
calculate the valve setpoint. Disc lift was determined by a change in slope on
the load cell trace and confirmed by test personnel who listened for audible
passage of flow through the discharge piping. With valve lift assumed known, the lift force was used to calculate an equivalent pressure. This pressure was
added to the system static pressure to infer the valve setpoint. Initial lift
results were 2634 psig for valve 2-68-563, 2678 psig for 2-68-564, and 2660
psig for 2-68-565. The required setpoint was 2485+/-1% psig for each valve.
Setpoints were readjusted and the valves were retested in situ, after re- establishing the water seal.
On April 8, 1988, with the unit in cold shutdown, the Sequoyah 2 pressurizer
safety valves were sent to Wyle Laboratories for bench testing and seat refur- bishment. The valve lifts were performed using water heated to 1200F and
pressurized by nitrogen. Valve stem lift was directly measured by a linear
voltage differential transformer (LVDT) mounted on the valve stem, and the stem
displacement was recorded on a strip chart. The lift setting was indicated by
a clear peak on the pressure strip chart and confirmed by spindle displacement
measured by the LVDT. Two of the valves had some internal parts replaced prior
to the tests. Lift points were 2435 and 2384 psig for valve 2-68-563, 2430 and
2432 psig for 2-68-564, and 2390 psig for 2-68-565.
The different lift points of the Sequoyah 2 valves were attributed to differ- ences in determining the time at which the disc began to lift. The LVDT used
at Wyle was accurate to 0.001 inch. The licensee's in situ method used a
change in the slope of a trace of lift force on a strip chart, backed up by
technicians' confirmation of audible flow.
The licensee found that the setpoint adjustments made as a result of the
Sequoyah 2 in situ tests brought the setpoint of the valves outside the limits
of the TS. This situation could have resulted in the premature liftina of the
safety valves (LER 50/328-88/016).
The licensee for Diablo Canyon has decided to drain the pressurizer safety
valve loop seal before testing. The licensee for Sequoyah is planning to send
pressurizer safety valves to Wyle Laboratories for future testing.
Hydraulic assist devices have been shown to be accurate in testing spring- actuated safety valve setpoints with saturated steam as the lift medium. They
have not been shown to be accurate for safety valve setpoint testing using
water or two-phase flow. The results of the Diablo Canyon 1 and Sequoyah 2 tests appear to show that these devices produce inaccurate results when testing
pressurizer safety valves with filled loop seals. If the inaccurate results
are believed and the valves are reset, a situation can occur in which the
setpoints of the valves are low, resulting in valve leakage, and/or premature
lift.
iN 88-68 August 22, 1988 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact one of the techni- cal contacts listed below or the Regional Administrator of the appropriate NRC
regional office.
rles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Mary S. Wegner, AEOD
(301) 492-7818 Charles G. Hammer, NRR
(301) 492-0919 Attachment: List of Recently Issued NRC Information Notices
Attachment
IN 88-68 August Z2. 19E8 Page I of I
.ILIST OF RECENTLY ISSUED
NRC INFCRI'ATION NOTICES
InTorratiOn
I'l forr atixon Date of
INotice No. Subject Issuance Issued to
I88-67 PWR Auxiliary Feedwater Pump 8/22/Ea All nolders of Os
Turbine Overspeed Trip or CFs for nuclear
Failure power reactors.
88-66 Industrial Padicgracty 8/22/6E All NRCinoustrial
Inspection and Enfcrcement radiOcraphy licensees.
88-65 Iracyertent Drainaces of 8/18/e8 All holders of OLs
Spent Fuel Peols or CPs for nuclear
power reactors aro
fuel storace facilities.
88-64 Recorting Fires in Nuclear 8/1e/88 All holders of ^Ls
Process Systems at; Nuclear or CPs for nuc eer
Power Plants power reactors.
88-E3 huigh Raaiat1on Hazarcs 8/15/cS All holde-s of :Ls
frcm Irradiated :nccre or CPs for nuclear
Detectors ane Cables power reactors.
research reactors
and test reactcrs.
88-62 Recent Finoings Conce~ring 8/12/8E All holders of NRC
Iroierentation of '"ality quality assurarce
Assurance Progrars ty prcgran ac;rcvai
Suo:liers of -ranspcrt for radicactsve
Paoacras material packaces.
88-61 Ccntrol Rocm viabitaotlity - All holcers of Dls
Recent Reviews of C;eratinq or CPs 'or nuclear
Exrerience power reactors.
88-60 Irndeeuate Cesign ano s/1./8 All hcIders of Ls
Installation of Watertight or C'Psfor nuclear
Peretration Seals power reactors.
88O - InaedUaOTe-ulification
Suppierent I and -ocumeniation of Fire or CPs for ruc'ear
Barrier Penetratior Seals power reactors.
88-59 MairnSteam :solatlcn Valve 8/9!E8 All holders of -Ls
Guiee Rail Failure at or CFs for nuclear
Waterford Unit 3 power reactors.
OL
CP
FIRST CLASS MAIL
UNITED STATES POSTAGE t1 FEES PAIO
USNRC
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D.C. 20555 PERMIT No. G-67 OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE, *300
IN 88-68 August 22, 1988 information notice.
No specific action or written response is required by this one of the techni- If you have any questions about this matter, please contactof the appropriate NRC
cal contacts listed below or the Regional Administrator
regional office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Mary S. Wegner, AEOD
(301) 492-7818 Charles G. Hammer, NRR
(301) 492-0919 Attachment: List of Recently Issued NRC Information Notices
idea
- SEE PREVIOUS (CONCURRENCES /'- *ROAB:DSP:AEOD
D RtR *C/OGCB:DOEA:NRR*RPB:ARM
CHBerlinger TechEd MSWegner
08// 7/88 08/10/88 07/11/88 06/27/88
- C/EMEB:DEST:NRR*EAD/DEST:NRR *D/DEST:NRR
- OGCB:DOEA:NRR *EMEt:DEST:NRR LCShao
BMann CGHammer LMarsh JRichardson
06/28/88 07/06/88 07/06/88 07/08/88
06/27/88
IN 88-XX
July xx, 1988 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact one of the techni- cal contacts listed below or the Regional Administrator of the appropriate NRC
regional office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Mary S. Wegner, AEOD
(301) 492-7818 Charles G. Hammer, NRR
(301) 492-0919 Attachment: List of Recently Issued NRC Information Notices
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list | - Information Notice 1988-01, Safety Injection Pipe Failure (27 January 1988, Topic: Unidentified leak, Water hammer)
- Information Notice 1988-03, Cracks in Shroud Support Access Hole Cover Welds (2 February 1988, Topic: Stolen)
- Information Notice 1988-04, Inadequate Qualification and Documentation of Fire Barrier Penetration Seals (5 February 1988, Topic: Fire Barrier, Fire Watch, Stolen)
- Information Notice 1988-05, Fire in Annunciator Control Cabinets (12 February 1988, Topic: Stolen)
- Information Notice 1988-06, Foreign Objects in Steam Generators (29 February 1988, Topic: Stolen)
- Information Notice 1988-07, Inadvertent Transfer of Licensed Material to Uncontrolled Locations (7 March 1988, Topic: Stolen)
- Information Notice 1988-08, Chemical Reactions with Radioactive Waste Solification Agents (14 March 1988, Topic: Process Control Program, Stolen)
- Information Notice 1988-09, Reduced Reliability of Steam-Driven Auxiliary Feedwater Pumps Caused by Instability of Woodward PG-PL Type Governors (18 March 1988)
- Information Notice 1988-10, Memo of Understanding Between NRC and OSHA Relating to NRC-Licensed Facilities (53 FR 43950, October 31, 1988) (23 December 1988)
- Information Notice 1988-10, Memo of Understanding Between NRC and OSHA Relating to NRC-Licensed Facilities (53 Fr 43950, October 31, 1988) (23 December 1988, Topic: Fatality, Overexposure)
- Information Notice 1988-10, Memorandum of Understanding Between NRC and Osha Relating to NRC-Licensed Facilities (53 Fr 43950, October 31, 1988. (23 December 1988, Topic: Fatality, Overexposure)
- Information Notice 1988-11, Potential Loss of Motor Control Center And/Or Switchboard Function Due to Faulty Tie Bolts (7 April 1988)
- Information Notice 1988-12, Overgreasing of Electric Motor Bearings (12 April 1988)
- Information Notice 1988-13, Water Hammer & Possible Piping Damage Caused by Misapplication of Kerotest Packless Metal Diaphragm Globe Valves (18 April 1988)
- Information Notice 1988-14, Potential Problems with Electrical Relays (18 April 1988)
- Information Notice 1988-15, Availability of Us Food & Drug Administration (FDA) Approved Potassium Iodide for Use in Emergencies Involving Radioactive Iodine (18 April 1988)
- Information Notice 1988-15, Availability of Us Food & Drug Administration (Fda) Approved Potassium Iodide for Use in Emergencies Involving Radioactive Iodine (18 April 1988)
- Information Notice 1988-16, Identify Waste Generators in Shipments of Low-Level Waste to Land Disposal Facilities (22 April 1988, Topic: Water hammer)
- Information Notice 1988-17, Summary of Responses to NRC Bulletin 87-01, Thinning of Pipe Walls in Nuclear Power Plants. (22 April 1988, Topic: Safe Shutdown, Weld Overlay, Feedwater Heater, Through-Wall Leak, Water hammer)
- Information Notice 1988-18, Malfunction of Lockbox on Radiography Device (25 April 1988, Topic: Overexposure)
- Information Notice 1988-19, Questionable Certification of Class Ie Components (26 April 1988, Topic: Water hammer)
- Information Notice 1988-19, Questionable Certification of Class IE Components (26 April 1988)
- Information Notice 1988-20, Unauthorized Individuals Manipulating Controls and Performing Control Room Activities (5 May 1988)
- Information Notice 1988-21, Inadvertent Criticality Events at Oskarshamn and at U.S. Nuclear Power Plants (9 May 1988, Topic: Shutdown Margin)
- Information Notice 1988-22, Disposal of Sludge from Onsite Sewage Treatment Facilities at Nuclear Power Stations (12 May 1988)
- Information Notice 1988-23, Potential for Gas Binding of High-Pressure Safety Injection Pumps During a Loss-Of-Coolant Accident (12 May 1988)
- Information Notice 1988-24, Failures of Air-Operated Valves Affecting Safety-Related Systems (13 May 1988)
- Information Notice 1988-25, Minimum Edge Distance for Expansion Anchor Bolts (16 May 1988, Topic: Earthquake)
- Information Notice 1988-26, Falsified Pre-Employment Screening Records (16 May 1988)
- Information Notice 1988-27, Deficient Electrical Terminations Identified in Safety-Related Components (18 May 1988)
- Information Notice 1988-28, Potential for Loss of Post-Loca Recirculation Capability Due to Insulation Debris Blockage (19 May 1988, Topic: Coatings)
- Information Notice 1988-29, Deficiencies in Primary Containment Low-Voltage Electrical Penetration Assemblies (24 May 1988)
- Information Notice 1988-30, Target Rock Two-State SRV Setpoint Drift Update (25 May 1988)
- Information Notice 1988-31, Steam Generator Tube Rupture Analysis Deficiency (25 May 1988)
- Information Notice 1988-32, Prompt Reporting to NRC of Significant Incidents Involving Radioactive Material (25 May 1988)
- Information Notice 1988-33, Recent Problems Involving the Model Spec 2-T Radiographic Exposure Device (27 May 1988)
- Information Notice 1988-34, Nuclear Material Control & Accountability of Non-Fuel Special Nuclear Material at Power Reactors (31 May 1988)
- Information Notice 1988-36, Possible Sudden Loss of RCS Inventory During Low Coolant Level Operation (8 June 1988)
- Information Notice 1988-37, Flow Blockage of Cooling Water to Safety System Components (14 June 1988, Topic: Ultimate heat sink)
- Information Notice 1988-38, Failure of Undervoltage Trip Attachment of General Electric Circuit Breakers (15 June 1988)
- Information Notice 1988-39, Loss of Recirculation Pumps with Power Oscillation Event (15 June 1988)
- Information Notice 1988-40, Examiners' Handbook for Developing Operator Licensing Examinations (22 June 1988)
- Information Notice 1988-41, Physical Protection Weaknesses Identified Through Regulatory Effectiveness Reviews (RERs) (22 June 1988)
- Information Notice 1988-41, Physical Protection Weaknesses Identified Through Regulatory Effectiveness Reviews (Rers) (22 June 1988)
- Information Notice 1988-42, Circuit Breaker Failures Due to Loose Charging Spring Motor Mounting Bolts (23 June 1988, Topic: Loctite)
- Information Notice 1988-43, Solenoid Valve Problems (23 June 1988, Topic: Stroke time)
- Information Notice 1988-44, Mechanical Binding of Spring Release Device in Westinghouse Type DS-416 Circuit Breakers (24 June 1988)
- Information Notice 1988-45, Problems in Protective Relay & Circuit Breaker Coordination (7 July 1988, Topic: Safe Shutdown)
- Information Notice 1988-46, Licensee Report of Defective Refurbished Circuit Breakers (8 July 1988)
- Information Notice 1988-47, Slower-than-Expected Rod-drop Times (14 July 1988)
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