Pressurizer Safety Valve Reliability| ML031250138 |
| 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, 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, Crane |
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| Issue date: |
11/04/1986 |
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| Revision: |
0 |
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| From: |
Jordan E L NRC/IE |
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| To: |
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| References |
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| IN-86-092, NUDOCS 8610300067 |
| Download: ML031250138 (4) |
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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, 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, Crane |
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Category:NRC Information Notice
[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 [[: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]] OR [[:Crane]] </code>. |
SSINS No.: 6835IN 86-92-UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF INSPECTION AND ENFORCEMENTWASHINGTON, D.C. 20555November 4, 1986IE INFORMATION NOTICE NO. 86-92: PRESSURIZER SAFETY VALVE RELIABILITY
Addressees
- All pressurized-water reactor (PWR) facilities holding an operating license ora construction permit.
Purpose
- This notice is provided to inform recipients of potentially significant problemspertaining to the reliability, of pressurizer safety valves. It is expected thatrecipients will review the information for applicability to their facilities andconsider actions, if appropriate, to preclude a similar problem from occurringat their facilities. However, suggestions contained in this information noticedo not constitute NRC requirements; therefore, no specific action or writtenresponse is required.
Description of Circumstances
- St. Lucie 2:On April 17, 1986 while shut down for refueling, St. Lucie 2 personnel benchtested three pressurizer safety valves that have a technical specification (TS)set point of 2515 +/- 1x psig. Valve V-1200 lifted at 2554 psig (14 psi above themaximum TS set point, valve V-1201 lifted at 2893 psig (353 psi above themaximum TS set point), and valve V-1202 was leaking too much to test. Theproblem with V-1201 was attributed to a hole in the bellows which allowed boricacid to contaminate and corrode the valve internals causing them to bind. Theseat of V-1202 was badly steam cut. The minor set point drift of V-1200 wasconsidered normal for 18 months operation. All valves were repaired beforereplacing them in service.McGuire 1:On September 2, 1986, McGuire 1 reported that a pressurizer safety valve hadlifted at 2375 psig, 85 psi below the 2485 +/- 1% TS required set point. Theprimary system depressurized to 1800 psig before the valve fully closed. Thisevent occurred during pressurization for an inservice leak test. Duringsubsequent bench testing of that valve, the as-found set point was determinedto be 2320 psig. Analysis showed that the three lifts used to determine thevalve set point at the last test were trending downward. Cocking of the spring,probably because of debris under the spring or a burr, was considered to be thecause of the set point "drift." When the spring was properly seated, the setpoint stabilized.8610300067 IN 86-92November 4, 1986 The low pressure at which the valve reclosed is attributed by the licensee tothe setting of the blowdown adjusting ring, which deviated from the vendor'srecommended setting by 137 notches. The remaining pressurizer safety valves onunit 1 were inspected and one other had misadjusted ring settings. Themisadjustment was attributed to on-site readjustment by maintenance personnel.The correctly set rings on the third valve were set by the vendor's representa-tive. Unit 1 valves will be repaired and reset.Unit 2 had two pressurizer safety valves set by the vendor's representative andone set by plant maintenance personnel. The plant technician had recorded thering settings, which were the same as the vendor's recommendation. Therefore,Unit 2 valves were determined to be operable.Arkansas Nuclear One, Unit 2:On September 15, 1986 while at 29% power, ANO 2 experienced a spurious openingand rapid reseating of two pressurizer safety valves, which resulted in anincrease in level and pressure in the quench tank and a 4 psig drop in reactorcoolant pressure. On September 25, 1986 following a reactor trip, quench tankparameters and tail pipe temperatures indicated that one or both pressurizersafety valves had lifted. Licensee tests showed that the setpoints of the valveswere lower than the TS required 2485 psig +/- 1%. One valve lifted at 2365 psigand the other between 2430 and 2455 psig. It was determined that the wrong testequipment had been used to set the lift pressure of the valves at the outageprior to these events. The valve manufacturer sent a representative to the sitewith the correct equipment. The valves have been correctly reset.A search of licensee event reports from January 1, 1983 to the present showsthat 20 other evepts involving 32 valves occurred. The problems were: 18 valveswith set point drift, 12 valves with seat leakage, 1 valve with set pressurehigh and 1 valve designated as inoperable. Attachment 1 contains the detailsof this compilation. Other information on the subject of safety valveperformance and reliability may be found in information notices 86-05;86-05, Supplement 1; and 86-56, the subject of which are main steam safetyvalves.No specific action or written response is required by this information notice.If you have any questions about this matter, please contact the RegionalAdministrator of the appropriate regional office or this office.4,)!& 5 ectorOivisiji of Emergency Preparednessand Ehgineering ResponseOfficdof Inspection and Enforcement
Technical Contact:
Mary S. Wegner, IE(301) 492-4511
Attachments:
1. Other Pressurizer Safety Valve Problems2. List of Recently Issued IE Information Notices Attachment 1IN 86-92 OTHER PRESSURIZER SAFETY VALVE PROBLEMS FROM 01/01/83 TO PRESENTPLANT NO. VALVESINOPERABLESEQUOYAH 1 1LEAKINGSALEM 2 3SALEM 1 3MILLSTONE 2 1SEQUOYAH 2 1SEQUOYAH 2 1BEAVER VALLEY 1 1SUMMER 1SEQUOYAH 2 1SET POINT DRIFTCALVERT CLIFFS 2 1BEAVER VALLEY 1 1SET POINT DRIFT HIGHFT CALHOUN 1SALEM 2 3SALEM 1 3MILLSTONE 2 1PALISADES 1SUMMER 1YANKEE-ROWE 1SET POINT DRIFT LOWANO 1 1SEQUOYAH 1 1SEQUOYAH 2 3SET PRESSURE HIGHYANKEE-ROWE 1 Attactment 2IN 96-92November 4. 1986UI UUb , INootice No.68-91LIST OF RECENTLY ISSUEDIE INFObMATION NOTICESDate of'55 IV3/86nnsSubijectLimiting AccAutherizat1oIssued toAll power reactorfacilities holdingin OL or CP; fuelfabrication andprocessing facilitiesK6-90t6-e9t6-05Sup. 1e6-25Sup. 186-t8"-tJt6-U686-85Requests To Dispose Of Very 11/3/66Low-Level Radioactive WastePursuant to 10 CFR 20 302Uncontrolled Rod Vlthdrawel 10/16/t6Because Of A Single FailureRain Ste Safety Valve Test 10/16/86Failures And Ring SettingAdjustmentsTraceability And Material 10/15/U6Control of Material AndEquipment, ParticularlyFastenersCompensatory measures For 10/15/U6Prolonged Periods Of SecuritySystem FailuresLoss Ot Offsite Power Upon An 10/10/86Automatic tus TransferClarification Of Requirements 10/10/t6For Fabrication And Export OfCertain Previously ApprovedType t PackagesEnforcement Actions Against 10/3/86Medical Licensees ForWillfull Failure To Reporti satdmisistrationsAll power reactorfacilities holdingan OL or CPAll WR facilitiesholding an OL or CPAll power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CPAll power reactorfacilities holdingan OL or CP; fuelfabrication andprocessing facilitiesAll power reactorfpcilities holdingan OL or CPAll registered usersof NRC certif iedpackagesAll NRC medicalIIcenseesOL a Operating LicenseCP a Construction PermitUNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, D.C. 20555OFFICIAL BUSINESSPENALTY FOR PRIVATE USE. *300FIRST CLASS MAILPOSTAGE 6 FEES PASOUSNRCWASH O.C.PERMIT No G47r : -*I '- r,"O I Y I C.". 1 ],A IT I; -- -:I -% :' -.'.7- ' L '.1' '-
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| list | - Information Notice 1986-01, Failure of Main Feedwater Check Valves Causes Loss of Feedwater System Integrity and Water-Hammer Damage (6 January 1986, Topic: Feedwater Heater)
- Information Notice 1986-02, Failure of Valve Operator Motor During Environmental Qualification Testing (6 January 1986)
- Information Notice 1986-03, Potential Deficiencies in Enviromental Qualification of Limitorque Motor Valve Operator Wiring (14 January 1986)
- Information Notice 1986-04, Transient Due to Loss of Power to Intergrated Control System at a Pressurized Water Reactor Designed by Babcock & Wilcox (31 January 1986)
- Information Notice 1986-05, Main Steam Safety Valve Test Failures and Ring Setting Adjustments (31 January 1986)
- Information Notice 1986-06, Failure of Lifting Rig Attachment, While Lifting Upper Guide Structure at St. Lucie Unit 1 (3 February 1986, Topic: Control of Heavy Loads)
- Information Notice 1986-06, Failure of Lifting Rig Attachment, while Lifting Upper Guide Structure at St. Lucie Unit 1 (3 February 1986)
- Information Notice 1986-07, Lack of Detailed Instruction & Inadequate Observance of Precautions During Maintenance & Testing of Diesel Generator Woodward Governors (3 February 1986, Topic: Overspeed trip, Overspeed)
- Information Notice 1986-08, Licensee Event Report (LER) Format Modification (3 February 1986, Topic: GOTHIC)
- Information Notice 1986-09, Failure of Check & Stop Check Valves Subjected to Low Flow Conditions (3 February 1986)
- Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion. (5 January 1995, Topic: Boric Acid, Stress corrosion cracking)
- Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion (5 January 1995, Topic: Boric Acid, Stress corrosion cracking)
- Information Notice 1986-10, Feedwater Line Break (10 November 1988, Topic: Coatings, Anchor Darling)
- Information Notice 1986-11, Anomalous Behavior of Recirculation Loop Flow in Jet Pump BWR Plants (31 December 1986)
- Information Notice 1986-13, Standby Liquid Control Squib Valves Failure to Fire (5 August 1986, Topic: Squib)
- Information Notice 1986-13, Standby Liquid Control System Squib Valves Failure to Fire (21 February 1986, Topic: Squib)
- Information Notice 1986-14, Overspeed Trips of Afw, HPCI & RCIC Turbines (26 August 1991, Topic: Overspeed trip, Overspeed)
- Information Notice 1986-14, Overspeed Trips of AFW, HPCI & RCIC Turbines (26 August 1991, Topic: Overspeed trip, Overspeed)
- Information Notice 1986-15, Loss of Offsite Power Caused by Problems in Fiber Optics Systems (10 March 1986, Topic: Squib, Loss of Offsite Power)
- Information Notice 1986-16, Failures to Identify Containment Leakage Due to Inadequate Local Testing of BWR Vacuum Relief System Valves (11 March 1986, Topic: Squib, Local Leak Rate Testing, Integrated leak rate test)
- Information Notice 1986-17, Update of Failure of Automatic Sprinkler System Valves to Operate (24 March 1986, Topic: Squib)
- Information Notice 1986-18, NRC On-Scene Response During a Major Emergency (26 March 1986, Topic: Squib, Backfit)
- Information Notice 1986-19, Reactor Coolant Pump Shaft Failure at Crystal River (21 March 1986, Topic: Squib)
- Information Notice 1986-20, Low-Level Radioactive Waste Scaling Factors, 10 CFR Part 61 (28 March 1986, Topic: Squib)
- Information Notice 1986-21, Recognition of American Society of Mechanical Engineers Accreditation Program for N Stamp Holders (31 March 1986, Topic: Squib)
- Information Notice 1986-22, Underresponse of Radiation Survey Instrument to High Radiation Fields (31 March 1986, Topic: High Radiation Area, Squib)
- Information Notice 1986-23, Excessive Skin Exposures Due to Contamination with Hot Particles (9 April 1986, Topic: Loss of Offsite Power)
- Information Notice 1986-23, Excessive Skin Exposures due to Contamination with Hot Particles (9 April 1986, Topic: Loss of Offsite Power)
- Information Notice 1986-24, Respirator Users Notice: Increased Inspection Frequency for Certain Self-Contained Breathing Apparatus Air Cylinders (11 April 1986, Topic: Hydrostatic)
- Information Notice 1986-25, Traceability and Material Control of Material and Equipment, Particularly Fasteners (11 April 1986)
- Information Notice 1986-26, Potential Problems in Generators Manufactured by Electrical Products Incorporated (17 April 1986)
- Information Notice 1986-27, Access Control at Nuclear Facilities (21 April 1986, Topic: Contraband)
- Information Notice 1986-28, Telephone Numbers to the NRC Operations Center and Regional Offices (24 April 1986)
- Information Notice 1986-29, Effects of Changing Valve Moter-Operator Switch Settings (25 April 1986)
- Information Notice 1986-30, Design Limitations of Gaseous Effluent Monitoring Systems (29 April 1986)
- Information Notice 1986-31, Unauthorized Transfer and Loss of Control of Industrial Nuclear Gauges (14 July 1986)
- Information Notice 1986-32, Request for Collection of Licensee Radioactivity Measurements Attributed to Chernobyl Nuclear Plant Accident (2 May 1986, Topic: Chernobyl, Potassium iodide)
- Information Notice 1986-33, Information for Licensee Regarding the Chernobyl Nuclear Plant Accident (6 May 1986, Topic: Chernobyl, Potassium iodide)
- Information Notice 1986-34, Improper Assembly, Material Selection, & Test of Valves & their Actuators (13 May 1986)
- Information Notice 1986-34, Improper Assembly, Material Selection, & Test of Valves & Their Actuators (13 May 1986)
- Information Notice 1986-35, Fire in Compressible Material at Dresden Unit 3 (15 May 1986, Topic: Chernobyl)
- Information Notice 1986-36, Change in NRC Practice Regarding Issuance of Confirming Letters to Principal Contractors (16 May 1986, Topic: Chernobyl)
- Information Notice 1986-37, Degradation of Station Batteries (16 May 1986, Topic: Chernobyl)
- Information Notice 1986-38, Deficient Operator Actions Following Dual Function Valve Failures (20 May 1986, Topic: Chernobyl)
- Information Notice 1986-39, Failures of RHR Pump Motors and Pump Internals (20 May 1986, Topic: Chernobyl)
- Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in Bwrs (5 June 1986, Topic: Chernobyl)
- Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in BWRs (5 June 1986, Topic: Chernobyl)
- Information Notice 1986-41, Evaluation of Questionable Exposure Readings of Licensee Personnel Dosimeters (9 June 1986, Topic: Chernobyl)
- Information Notice 1986-42, Improper Maintenance of Radiation Monitoring Systems (9 June 1986, Topic: Temporary Modification, Chernobyl)
- Information Notice 1986-43, Problems with Silver Zeolite Sampling of Airborne Radioiodine (10 June 1986, Topic: Chernobyl)
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