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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20141K7711997-03-10010 March 1997 Preliminary Part 21 Rept Re Parsons Peebles/Electric Products Generators W/Modified Bearing Insulation.Util Implemented Mod to Add Insulation to Outer Spacer Ring ML20086T1761995-07-19019 July 1995 Part 21 Rept Re Potential Problem W/Type 51's & 87T Relays. Potential Problem Identified as Defective Tap Block. Recommends That Users Identified on Attachment 1 Page Verify Testing Per Instruction Listed on Encl Product Advisory Ltr ML20083R7961995-04-24024 April 1995 Interim Part 21 Rept Re Contact Failure of Square D Type Kpd Relay Used in Diesel Generator Control Panel.Relays Replaced at Plant.Review of Matter Expected to Be Completed on 950508 ML20077C2801994-11-21021 November 1994 Deficiency Rept Re Defective Yokes P/N 342849 Mfg by Copes- Vulcan,Inc.Affected Utilities Notified & Defective Yokes Will Be replaced.Copes-Vulcan Also re-inspected All Yokes in Inventory & Verified Yokes Acceptability ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20055J0741990-07-24024 July 1990 Part 21 Rept Re Error in Westinghouse ECCS Decay Heat Model. Initially Reported on 900712.Error Resulted in Nonconservative Decay Heat Source & Does Not Constitute Actual Operational Safety Concern.Meeting Scheduled NRC-90-3528, Part 21 Rept Re Potential Problem in Decay Heat Model of Wcobra/Trac Computer Code.Model Corrected & Calculations Initiated.Recalculations of App K Analyses for Plants Will Be Completed by 9007231990-07-16016 July 1990 Part 21 Rept Re Potential Problem in Decay Heat Model of Wcobra/Trac Computer Code.Model Corrected & Calculations Initiated.Recalculations of App K Analyses for Plants Will Be Completed by 900723 ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML20246K6681989-05-30030 May 1989 Part 21 Rept Re Defects Discovered in Nbfd & BF-type Relays Ordered from Westinghouse.Relays Returned to Mfg to Perform Extensive Functional Testing of Relays Installed & QA Audit of Vendor to Evaluate Relay Dedication Process Scheduled ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys ML20236X3451987-11-25025 November 1987 Part 21 Rept Re Use of Potentially Unqualified Extension Cable W/Environmentally Qualified Solenoid Valves at Plant, Per 871118 Request.Replacement of GE Cable in Unit 1 Completed During Fall Outage ML20235U0271987-10-0707 October 1987 Part 21 Rept Re Westinghouse Plant Steam Generator Tubes Susceptible to High Cycle Fatigue Failure Similar to 870715 Event at North Anna Unit 1.Caused by Mean Stress in Tube & Superimposed Alternating Stress ML17261A5301987-06-18018 June 1987 Part 21 Rept Re Potential Util Failure to Comply W/Component Containment Isolation Licensing Commitment If Proposed Mods to Component Cooling Water Sys Instituted.Utils Advised to Evaluate Containment Isolation Sys ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20198E2811985-10-30030 October 1985 Followup Part 21 & Deficiency Rept Re Signal Failure Potential in Safety Injection Recirculation Path.Initially Reported on 850724.Control Logic for Valves Will Be Changed ML20134Q1741985-08-29029 August 1985 Part 21 Rept Re Potential Maint Issues Associated w/Anker-Holth Snubbers.Owners of Anker-Holth Snubbers Will Be Informed of Problems & Sent Revs to Technical Instruction Manuals to Include Procedures for Seal & Fluid Maint ML20132H1261985-07-24024 July 1985 Deficiency & Part 21 Rept Re Failure of Westinghouse Power Supply Breaker in Remote Control Circuitry for Air Operated Valves.Manual Handwheel Operators Will Be Manipulated to Override Remote Operators & Maintain Valves Open ML20100K9741985-04-12012 April 1985 Part 21 Rept Re Malfunction in X-SAM Safety Sys Supplied Per Topical Rept on Nuclear safety-related Crane Being Installed in England.Air Pressure Being Used to Release Brake Abnormally Low Due to Valve Malfunction ML20092L1421984-06-21021 June 1984 Part 21 Rept Re Static Load Rating on Anker-Holth,Baxter Hydraulic Suppressor.Caused by Failure of Torrington self-aligning Ball Bushing.Recommends Replacement W/ Paul-Monroe Hydraulics Part PA-89492 & PA-89493 ML20091N8511984-06-0505 June 1984 Part 21 Rept Re Static Load Rating on Anker-Holth/McDowell Wellman Engineering Hydraulic Suppressor Assembly.Caused by Failure of Torrington self-aligning Ball Bushing.Recommends Replacment W/Paul Monroe Hydraulics Part PA-89467 ML20082P9851983-12-0101 December 1983 Part 21 Rept Re Nonconforming 1-1/4x12-inch Anchor Bolts Mfg by Hilti,Inc.Bolts Incorrectly Marked.Installed Bolts Will Be Properly Restamped.Remaining Bolts Returned to Manufacturer.Item Not Reportable Per Part 21 ML20084A3021973-10-29029 October 1973 Deficiency Rept Re Backseating Disc Mislocation Problem on Darling 2-inch Gate Valves.Downstream Seat Protruded from Valve Body Such That Fully Withdrawn Valve Disc Could Catch Lip of Seat Ring When Reinserting.Nsss Supplier Notified ML20085M3901973-10-0101 October 1973 Significant Deficiency Rept Re Weld Failure on High Pressure Svc Water Valve in Unit 2.Initially Reported on 730601. Vendor Weld Stress Analysis Calculations Reviewed.Table of Acceptable Weld Sizes Prepared 1997-03-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARNPL-99-0569, Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with ML20212D5961999-09-15015 September 1999 Safety Evaluation Supporting Licensee IPEEE Process.Plant Has Met Intent of Suppl 4 to GL 88-20 NPL-99-0051, Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with NPL-99-0449, Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with ML20196J4251999-06-30030 June 1999 Safety Evaluation Authorizing Proposed Alternatives Described in Relief Requests VRR-01,ROJ-16,PRR-01 & VRR-02 ML20209D2691999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbnps,Units 1 & 2 ML20196F3341999-06-22022 June 1999 Safety Evaluation for Implementation of 422V+ Fuel Assemblies at Pbnp Units 1 & 2 ML20195F9781999-06-10010 June 1999 Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1 ML20209D2751999-05-31031 May 1999 Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0328, Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with NPL-99-0273, Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With ML20196F3521999-04-30030 April 1999 Non-proprietary WCAP-14788, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt - NSSS Power) NPL-99-0193, Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with NPL-99-0134, Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with ML20207D6751999-02-22022 February 1999 Assessment of Design Info on Piping Restraints for Point Beach Nuclear Plant,Units 1 & 2.Staff Concludes That Licensee Unable to Retrieve Original Analyses That May Have Been Performed to Justify Removal of Shim Collars ML20206R9001999-01-13013 January 1999 SER Accepting Nuclear Quality Assurance Program Changes for Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0008, Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with NPL-99-0091, 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with1998-12-31031 December 1998 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with ML20198C7671998-12-10010 December 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME BPV Code,1986 Edition,Section XI Requirement IWA-2232, to Use Performance Demonstration Initiative Program During RPV Third 10-yr ISI for Plant,Unit 2 NPL-98-1006, Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20195J5101998-11-16016 November 1998 Proposed Revs to Section 1.3 of FSAR for Pbnp QA Program ML20198J5941998-11-0303 November 1998 1998 Graded Exercise,Conducted on 981103 NPL-98-0948, Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With NPL-98-0880, Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored1998-10-21021 October 1998 Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored ML20154M9121998-10-14014 October 1998 Unit 1 Refueling 24 Repair/Replacement Summary Rept for Form NIS-2 ML20154L6751998-10-14014 October 1998 Unit 1 Refueling 24 ISI Summary Rept for Form NIS-1 NPL-98-0826, Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20151W3851998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbnp Units 1 & 2 NPL-98-0653, Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4471998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 2 ML20151W4541998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 1 ML20236Q3161998-07-10010 July 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements PTP-3-01 & PTP-3-02 ML20236L6771998-07-0707 July 1998 Safety Evaluation Approving Wepco Implementation Program to Resolve USI A-46 at Point Beach NPP Units 1 & 2 NPL-98-0558, Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 2 ML20151W4261998-06-30030 June 1998 Corrected Page to MOR for June 1998 for Pbnp Unit 2 ML20151W4221998-05-31031 May 1998 Corrected Page to MOR for May 1998 for Pbnp Unit 2 NPL-98-0481, Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4011998-04-30030 April 1998 Corrected Page to MOR for April 1998 for Pbnp Unit 2 NPL-98-0356, Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20217F3131998-04-17017 April 1998 Safety Evaluation Accepting Proposed Alternative to ASME Code for Surface Exam of Nonstructural Seal Welds,For Plant, Unit 1 ML20216D7071998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3981998-03-31031 March 1998 Corrected Page to MOR for March for Pbnp Unit 2 NPL-98-0209, Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable1998-03-30030 March 1998 Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable ML20217A8501998-03-19019 March 1998 SER Accepting Proposed Changes Submitted on 980226 by Wiep to Pbnp Final SAR Section 1.8 Which Will Impact Commitments Made in Pbnp QA Program Description.Changes Concern Approval Authority for Procedures & Interviewing Authority ML20216J0101998-03-17017 March 1998 Safety Evaluation Accepting Third 10-yr Inservice Insp Interval Relief Request RR-1-18 for Plant NPL-98-0159, Monthly Operating Repts for Feb 1998 for Point Beach Nuclear Plant,Units 1 & 21998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3891998-02-28028 February 1998 Corrected Page to MOR for Feb 1998 for Pbnp Unit 2 ML20216D7121998-02-28028 February 1998 Revised Corrected MOR for Feb 1998 for Point Beach Nuclear Plant,Unit 2 NPL-98-0084, Monthly Operating Repts for Jan 1998 for Point Beach Nuclear Plant,Units 1 & 21998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20198L1151998-01-0808 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Point Beach Nuclear Plant,Units 1 & 2 1999-09-30
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~ p l ,_ October 29, 1973 Mr. John F. O' Leary, Director ,
Directorate of Licensing U. S. Atomic Energy Ccmmission Washington, D. C. 20545
Dear Mr. O' Leary:
DOCKET NOS. 50-266 AND 50-301 FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 POINT BEACG NUCLEAR PLANT BACKSEATING DISC MISLOCATION PROBLEM ON 2" DARLING VALVES In accordance with Section 15.6.6.A.3.b of the Technical Specifications for Point Beach Nuclear Plant (Facility Operating License Nos. DDR-24 and DPR-27), this report describes a possibic generic probicm with a category of 2" gate valves in-stalled at Point Beach Nuclear Plant. The valves in question are 2", No. S-350 WDG welding end, outside screw and yoke, double disc gate valves with lip seals, and are manufactured by the l Darling Valve and Manufacturing Company. The valves used at Point Beach Nuclcar Plant are safety class I, ASA series 1500 ,
lb. valves.
- An investigation of excess letdown line leakage on September 15, 1973, lead to an inspection and subsequent repair of valve 11.OV-1299 on Unit 1 (excess letdown system root valve) on September 26, 1973. Inspection of the valve disclosed that its dowr.itream seat protruded from the valve body such that if the valve disc was fully withdrawn from the guides, as allowed by itt backscating ring, the disc could catch the " lip" of the seat ring when reinserting. Four marks on the lip of the down-stream seat ring indicated that the disc had caught there during previous valve closings. Internal damage to the valve consisted cf a fine vertical crack at the 12 o' clock position in the upper portion of the downstream seat ring. Two locating pins between the upstream and downstream discs of the split disc valve were found to be slightly bent also and some facial scratches to the down stream disc were evident. There was no metal loss involved in the damage.
O Mr. John F. O' Leary
.O October 29, 1973 Repair of the valve involved rounding the lip of the seat ring to prevent future hangups of the disc. The thin ver-tical crack during in the downstream seat could not be fully lapped out the repair. Accordingly, a manual valve was added to the system downstream of IMov-1299 to back up the root valve. Valve IMOV-1299 thereby remains effective and operable as a remotely controlled root shutoff valve, but is considered not totally 1 capable of effceting completely tight shutoff without some through-leskage, j
At the time, measurements indicated that the location of the backseating could not be assuredly ringdetermined.
on the valve stem was too low but this If such was the case, this would the valve was fully open ard backscated. the seat rings when allow the split discs to fully clear The tendency for inter-forence to occur between the downstream disc and seat during i
l valve closing could be expected to increase if there was flow through the valve, creating a differential pressure which could swing the loose hrnging disc onto the lip of the seat.
at Point Beach Nuclear Plant.There are six similar 2" Darling valves in each unit 1299 valve, valves 270A & B (normally In addition to the open) areabove mentioned installed on the reactor coolant pump seal return lines. These valves are. rarely operated in the life of the plant. Also, valves 598 and 599 on the reactor coolant system drain line are of this type. These valves are never operated during normal pressurized and power operation.
the normal letdown line.The sixth,similar valve on each unit is MOV-427 on '
in the event of low pressurizer level and,The function of valve in closing, 427 cause is to close the closure an of the containment isolation valves 200 A, B and C, via interlock.
port are containmentNone of the Darling icolation valves. valves described in this re-down on October Valve 13,IMOV-427 was investigated during a Unit 1 shut-fully close remotely.1973, af ter it was reported that it would not ber 28, 1973, had shown that at approximately one-half shut andManual again just prior to closing, Tests were conducted at that time to verify that 1Mov-427 wasthe valve oper capable lation signalof performing its primary for the letdown line. function of initiating an iso-The slightest movement of the valve off its backseat was found to be sufficient to activate the interlocks and close the AOV-200 letdown isoletion valves.
Measurements indicated that the discs of 1MOV-427 when e
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3-O ctober O 29, 1973 Mr. John F. O' Leary e
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l open *o simi-backscated cleared the seat rings and icft the va veInspection of the upper showed n lar problems as experienced in 1MOV-1299. i Before damage to valve IMOV-427 other thand ina 1MOV-1299. slight unded mark to aidngin edge of the seat ring, similar to that founclosing up the v guiding the discs down between5/16" less than the maximum back-the seats.
switch was then set for 2-1/4", Valve cycling tests were then con-seating position of 2-9/16".
ducted satisfactorily. cycled During the same shutdown, valve disc hangup. At IMOV-270B wasthe manually with no evidence of stickiness or 13,erience 1973, it was and tele-completion of repair of IMOV-427, on Octoberthat, indeed, a concluded frem measurements taken, opercting exp t locations phone discussions with the valve manufacturer, dimensi With these confirmations, investigation on a sche-on twelvethe stem.
valves of this type would requ re i
l dule commensurate with the plant operating schedu ill bees.
Valves IMOV-1299, 2MOV-1299 and 2MOV-427 wValve IMOV-1299 electrically limited similarly to IMOV-427. i nt shutdown fol-vill be completely changed out during a convenwill eNewnot valve permitstens with back-lowing the receipt of a new valve. l t have been ordered seats located so that full opening of the va ve onvenient shut-the discs to lose the guide effecttheofstems theofsea these sand will o downs.*
The service of the 598, that it is not considered necessary to change h unit.
valves until the next refueling shutdown of eac has been in-The nuclear steam supply system supplier l es.
formed about the probicms encountered with these va v Very truly yours,
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- # vt Senior Vice President Sol Burstein cc: Mr. James G. Keppler Regional DirectorDirectorate of Regulatory Operations, .
Region III -
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