ML20086C607
ML20086C607 | |
Person / Time | |
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Site: | Salem ![]() |
Issue date: | 05/09/1973 |
From: | Betz J Public Service Enterprise Group |
To: | Kruesi F US ATOMIC ENERGY COMMISSION (AEC) |
Shared Package | |
ML20086C587 | List: |
References | |
NUDOCS 8311290027 | |
Download: ML20086C607 (2) | |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML18107A3441999-06-0101 June 1999
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Util Intends to Replace Keys in Actuators W/Keys of Steel ML18094A4421989-05-16016 May 1989 Part 21 Rept Re Defect in Solid State Protection Sys. During Mods in Solid State Protection Sys Cabinets,Noted That Two Wires Became Dislodged from Circuit Board.Visual Insp & Complete Pull Test Performed ML13316A0321988-12-22022 December 1988 Part 21 Rept Re Spot Welds on DB-50 Reactor Trip Breaker Secondary Contact Bracket Observed to Be Separated.Initially Reported on 881213.Utils Have Been Advised That Secondary Contact Bracket May Be Modified by Drilling Holes in Welds ML20153G0111988-05-0606 May 1988 Part 21 Rept Re Potential Defect in Bussman Buss KTK-R Fuse Blocks W/Part Numbers 2078,2079 & 2080.Purchasing Records Reviewed to Identify If Any Parts Were Actually Used or Shipped to Customers.Results Listed ML18093A8281988-05-0606 May 1988 Part 21 & Deficiency Rept Re Asea Brown Boveri,Power Distribution,Inc Low Voltage K-Line Circuit Breakers. 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Addl Info Encl ML20215G5351986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20215G6801986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires ML20140J4261986-03-31031 March 1986 Part 21 Rept Re Nuclear Valves Shipped to Pse&G.Internal Parts Lapped Which Could Reduce or Eliminate Nickel Plating Resulting in Seat Leakage & Shifting Problems ML20210G9921985-08-13013 August 1985 Part 21 Rept Re Failure of Isolated Worm Shaft Gear When Certain Critical Speeds Combined W/Repetitive Transfer of Actuator Clutch Mechanism from Manual (Handwheel) to Motor Drive Mode.Two Possible Solutions Noted ML20116E8481985-04-23023 April 1985 Part 21 Rept Forwarding Rev 1 to Insp Procedure for Investigating Emergency Diesel Generators for Fractured Welds on Air Deflectors.Rev Will Be Forwarded to Each Facility ML20092D9711984-06-15015 June 1984 Part 21 Rept Re Thermal Nonrepeatability & Other Calibr Errors in Barton Lot 1 Transmitters.Initially Reported on 840615.Transmitter Defects Identified & Expected Error Deviations Calculated.Utils Notified ML20082F3621983-11-17017 November 1983 Part 21 Rept Responding to IE Bulletin 83-06, Nonconforming Matls Supplied by Tube-Line Corp. 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Addl Support Will Be Completed by 800228 ML18081B0481979-12-21021 December 1979 Final Deficiency Rept Re Undetectable Failure in Engineered Safety Features Actuation Sys.Testing Procedures Revised to Include Testing of Permissive Circuitry P4 on Periodic Basis.Unit Will Be Tested Prior to Operation ML18081B0601979-12-0303 December 1979 Initial Deficiency Rept Re Potential Dropped Rod Events Leading to Calculated DNB Ratios Lower than Reported to NRC for Certain Westinghouse Plants.Util Is Investigating Condition for Applicability to Facility ML18081A3751979-10-0505 October 1979 Significant Deficiency Rept Re Containment Purge & pressure- Vacuum Relief Valves.Actuator Torque Values Were Insufficient to Move Valves from Open to Closed Positions W/ Design Differential Pressure of 60 Psi.Design Reviewed ML18081A3781979-10-0505 October 1979 Significant Deficiency Rept 79-06 Re Steam Generator Water Level Instrumentation.Pipe Breaks in Containment Could Lead to Elevated Temp Readings Which Could Result in Delayed Protection Sys Actuation.Setpoints to Be Changed ML18081A7551979-10-0404 October 1979 Interim Deficiency Rept Re Max Flow of RHR Pump During post- LOCA Mode.Caused by Low Sys Resistance to Pump Runout Conditions.Sys Resistance Increased by Placement of Resized Orifices ML18079A9521978-10-28028 October 1978 Deficiency Rept:On 780928,during Routine Design Review, Undersizing of Refueling Water Storage Tank Was Discovered. 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Initially Reported on 760402.Caused by Heavy Corrosion Buildup.Nine Units Replaced W/Pacific Scientific Units & 54 Units Replaced W/Combination of Redesigned Units 1999-06-01 Category:TEXT-SAFETY REPORT MONTHYEARLR-N99-0448, Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With1999-09-30030 September 1999
[Table view]Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With LR-N99-0449, Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20212B7221999-09-14014 September 1999 Safety Evaluation Supporting Amends 224 & 205 to Licenses DPR-70 & DPR-75,respectively LR-N99-0415, Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 9909131999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 LR-N99-0416, Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 05000272/LER-1999-006-02, :on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With1999-08-26026 August 1999
1999-09-30 |
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- John F. Betz Public Service Electric and Gas Company 80 Park Place Newark.N J. 07101 201/622-7000 '
Vice Prosident in Charge of Electnc operation May 9, 1973 U.
S.
Atomic Energy Commission Director of Regulatory Operations 7920 Norfolk Avenue Bethesda, Maryland 20014 Attention of Mr. Frank E. Kruesi Gentlemen:
REACTOR COOLANT PUMP INTERNALS NO. 1 UNIT SALEM NUCLEAR GENERATING STATION i
On April 13, 1973 during an AEC inspection.of the
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Salem Nuclear Gene rating Station site, it came-to our attention l
through your inspector that Westinghouse. Electric Corporation-l had requested the return of No..ll, 12,-13 and 14 Reactor j
Coolant Pump Internals for corrective action.
This was j
verbally reported to the Director.of Regulatory Operations, Region 1 on April 13, 1973 We stinghouse was immediately
+
requested to furnish an explanation-and -analysis of the; intended corrective actice.
'The following is quoted from' l
Westinghoust Electric Corporation letter dated April 19,,1973:
"In late 1971, Westinghouse became-aware i
that.a icv. pumps in service exhibited j
. appreciably higher' vibration ~ amplitudes than the*/ did when they were' checked.out.
during manufactureHat Cheswick,.even though these higher vibration amplitudes were.
withinJthe~ limits-of the pump: specification
'and the problem wasLonly associatedEwithia cmall. number of/pamps. EWestinghouse felt:
1 that it was in the be't laterestsfoff;ourselves.
s and our customers'to determine its.cause'and:
take the necessary-corrective action to insure long' bearing and pump seal life..The i
preventive' corrective actionito>be performed:
at Cheswick upon return.of-the.four: Unit 1.
-pumps'is as follows:
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8311290027 730612 r
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Atomic Ene rgy 5-9-73 Commission 1.
Impeller and coupling taper rates will be matched to shaft taper.
2.
Coupling will be installed on shaft and face machined true to center line of shaft.
3 The entire rotating assembly (coupling, chaft and impeller) will be balanced as a complete unit.
4.
Replace present coupling to motor bolts with a match weighted set.
"In addition to the above, the seal housing flange will be machined to accept an 0-Ring seal rather than the current gasket seal.
This will update the pump to a later revision and insure a better seal between the seal housing and the main flange.
"The pump internals for Unit 2 had the rework incorporated prior to their ship-ments to the Salem Site.
Therefore, these need not be returned to Cheswick."
To date, Westinghouse has done this identical rework for four other utilities and, in their opinion, this is an upgrading and does not constitute a deficiency that could adversely affect safety.
The return of this equipment to Salem is expected to be completed by August 1, 1973 If you have any further questions. on this subject, please feel free to contact us.
Very truly yours, I
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