ML19253B365
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| ML19253B365 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/10/1979 |
| From: | Brown S VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| References | |
| 747A, NUDOCS 7910150457 | |
| Download: ML19253B365 (1) | |
Similar Documents at North Anna | |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217H8711997-10-15015 October 1997
[Table view]Part 21 Rept Re Potential Safety Hazard for Some 3/4 Sch 40 Pipe Shipped to CP&L & VA Power Corp.Matl Has Been Found to Have Areas Where Wall Thickness Falls Below Minimum Allowed by SA 312 Specification.Customers Have Been Notified ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H7911997-09-30030 September 1997 Part 21 Rept Re Failure of Weldment Associated w/lube-oil Piping Sys on 970804 at Millstone,Unit 2.Root Cause Is Not Yet Known.Quality of Weldment Is Being Considered.Listed Util Sites Affected ML18153A1431997-06-10010 June 1997 Part 21 Rept Re Possible Machining Defect in Certain Stainless Steel Swagelok Tube Fitting Bodies.Facilities Have Been Notified About Possible Problem ML18153B0841994-09-26026 September 1994 Suppl to 940902 Initial Part 21 Rept Re Defect W/Governor Valves Used in turbine-driven Pumps Mfg by Dresser-Rand to Formally Addresss Written 30 Day Rept Requirement of 10CFR21(c)(3)(ii) ML18153B0601994-09-0202 September 1994 Initial Part 21 Rept Re Steam Drive AFW Pump Governor Valve Mfg by Dresser-Rand.Maint Procedure to Stroke Governor Valve Stem Performed Weekly & Monitoring of Corrosion Build Up in Gland Seal Leakoff Area Performed Weekly ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical ML20044G5431993-05-26026 May 1993 Part 21 Rept Re Rosemount Model 1154 Series H Pressure Transmitters W/Temp Performance Characteristics Not in Compliance W/Specs.Vendor in Process of Notifying Customers.Sample Notification Ltr to Util Encl ML20126F8081992-12-22022 December 1992 Part 21 Rept Re Possible Condition of Gag Plug in Cap of Valves That Cause Valves Not to Lift to Requirement for Providing Full Capacity.Affected Customers Notified.Removal of Caps &/Or Gag Plugs Recommended ML18153D0811992-08-0303 August 1992 Interim Part 21 Rept Re Analysis of Klockner-Moeller Model NZM6-63,480 Volt Circuit Breakers.Initially Reported on 920701.Lever Fracture Should Be Examined to Determine If Any Cleaning Sprays or Purifying Agents Have Been Used ML20101L9661992-07-0101 July 1992 Part 21 Rept Re Discovery of Klockner-Moeller 480-volt Breaker in Tripped Condition Due to Fracture of Plastic Arm within Breaker.Two of Three Failed Breakers Sent to Mfg for Analysis.Results Expected by End of Jul 1992 ML20059M1751990-09-24024 September 1990 Supplemental Part 21 Rept 1 Re Defect in Coltec Industries, Inc Connecting Rod Assemblies Nuts/Bolts on Model 38TD8-1/8 Emergency Generators.Initially Reported on 851120.Nuts/bolts for Assemblies at Stated Plants Inspected & Replaced ML20012C1051990-03-0707 March 1990 Part 21 Rept Re Several Failures of Fairbanks Morse Engine Div Piston Pins/Bushings on Upper Pistons.Caused by Incorrect Surface Pattern on Piston Pins.Piston Pins Under Listed Purchase Orders to Be Removed & Replaced ML18153C1011990-02-0202 February 1990 Part 21 Rept Re Two of Three Pc Cards in GE Type SLV11A1 Over/Undervoltage Relays Failing to Produce Output.Short Between Leads Would Result in Damage to Component 1C5. Sketch of Threshold Detection Board Encl 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 ML20246K7401989-04-26026 April 1989 Part 21 Rept Re Incorrectly Stamped Name Plates on Certain Asco Nuclear Qualified Valves.Vendor Will Contact Each Affected Facility & Furnish Correctly Stamped Plates & in Near Future Discontinue Sale of Rebuild Kits for Valves ML20205F3211988-10-10010 October 1988 Part 21 Rept Re Potential Deviation from Tech Spec Concerning Ry Indicators Due to Operating Temp Effect on Analog Meter Movement.Initially Reported on 881006.Customers Verbally Notified on 881006-07 ML20153F4151988-08-12012 August 1988 Part 21 Rept Re Procurement of Heat Tracing Matls from Nelson Electric Corp Not Meeting 10CFR21 Requirements. Initially Reported on 880810.Nelson Electric Corp Removed from Approved safety-related Vendor List 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 ML20207T8061987-02-20020 February 1987 Part 21 & Deficiency Rept Re Defect in Recirculation Spray Hxs.Initially Reported on 870218.Original HX Design Did Not Consider External Pressurization of Diaphragm Seal Plate W/O Presence of Internal Pressure as Balance.Mods Scheduled ML20211E1661987-01-28028 January 1987 Part 21 & Deficiency Rept Re Rockwell Engineering Co Steel Columns W/Laminations in Web.Initially Reported on 861112. Ultrasonic Testing of Suspect Matls Completed.Action Plan to Replace 13 Defective Columns Summarized ML20214H7521986-11-12012 November 1986 Part 21 Rept Re Potential Defect in New Svc Water Spray Array Support Sys Mfg by Inland Steel Co.Initially Reported on 861107.Positive Identification & Ultrasonic Testing of Suspect Matls Will Be Completed by 861201 ML20214F9771986-11-0707 November 1986 Part 21 Rept Re New Svc Water Spray Array Sys Supports Supplied by Inland Steel Co.Util Will Provide Positive Identification & Ultrasonic Testing Results of Suspect Matl. Identification Process Will Be Complete by 861201 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 ML20197J6371986-05-12012 May 1986 Part 21 Rept Re Possibility of Power Supply hang-up When Energizing Slv Relays.Changes Made in Power Supply Circuitry.Slv Relays,W/Mods Incorporated in Latest Designs, Extensively Tested W/O Power Supply Failures ML20137X3891986-02-27027 February 1986 Part 21 Rept Re Possible Defect in Model KMG-HRH Noble Gas Radiation Monitor W/Enhanced Detector Model KDGM-HR. Initially Reported on 860222.Vendor Will Request Utils for Listed Plants to Determine If Monitors Defective ML20137S4441985-11-26026 November 1985 Part 21 Rept Re Unparallel Fitup of Nut to Mating Surface of Connecting Rod Cap & Nonperpendicular Faces of Nuts to Thread Pitch Line.Nuts & Bolts in Assembled Calvert Cliffs Onsite Spare Engine Will Be Replaced ML20133B2511985-09-16016 September 1985 Part 21 Rept Re Defective Electronically Coded Vinyl Key Cards,Pyrotronics Model 1310,used for Security Electronic Access Control Sys.Initially Reported on 850913.Five Defective Cards Destroyed.New Cards Will Be Tested ML20126C6901985-06-0505 June 1985 Part 21 Rept Re Generator Failure.Concurs W/Encl Louis Allis That Interpolar Connectors Be Removed ML20127N0621985-05-13013 May 1985 Part 21 Rept Re Incorrect Short Time Delay Band Lever Inadequately Installed in Low Voltage K-line Circuit Breaker Electromechanical Overcurrent Trip Device.Visual Insp to Determine If Correct Lever Installed Recommended RBG-18701, Attachment of Final Deficiency Rept DR-138 Re ITE-Gould Type 2150 Overload Relays Out of Calibr.Relays Sent Back & Replaced w/L10 Overload Relays.Response to Request for Addl Info Re Surry & North Anna SPDS Encl1984-08-20020 August 1984 Attachment of Final Deficiency Rept DR-138 Re ITE-Gould Type 2150 Overload Relays Out of Calibr.Relays Sent Back & Replaced w/L10 Overload Relays.Response to Request for Addl Info Re Surry & North Anna SPDS Encl ML20094D9061984-07-19019 July 1984 Interim Deficiency Rept,Item 176 Re Kerite Co Single Conductor Power Cables Damaged,But Undetected by Insp & Testing.Initially Reported on 840619.Final Rept by 841215 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 ML20088A6231984-03-28028 March 1984 Part 21 Rept Re Abnormal Wear on Linear Converter Units Mfg & Furnished to Power Generating Facilities.Caused by Actuator Hunting.All Customers Provided Field Lubrication Procedure ML20081C5111984-03-0909 March 1984 Part 21 Rept Re Status Update Concerning Abnormal Wear on Linear Converters.Test Program Underway.Results of Investigation Indicate Excessive Wear Caused by Hunting of Control Circuitry ML20086N0421984-01-0202 January 1984 Final Part 21 Rept Re Potential Problem Concerning Radiography of Branch Connection Welds Covered by Reinforcing Pads.Welds at Byron,Braidwood & North Anna Acceptable.Weld 7 at Clinton Reradiographed PLA-1902, Interim Deficiency Rept Re Isolation of Nitrogen Makeup Sys. Also Reportable Per Part 21.Initially Reported on 830912. Permanent Design Mod Will Be Implemented.Final Rept Will Be Submitted in Dec 19831983-10-10010 October 1983 Interim Deficiency Rept Re Isolation of Nitrogen Makeup Sys. Also Reportable Per Part 21.Initially Reported on 830912. Permanent Design Mod Will Be Implemented.Final Rept Will Be Submitted in Dec 1983 ML20086N2381983-10-0404 October 1983 Supplemental Part 21 Rept Re Radiographic Record Evaluation, Supplying Addl Data to 830624 Submittal.Records Show That 90 Degree Branch Connections Furnished to North Anna 1 & 2 Jobsites.No Nozzles Supplied to Zimmer.Related Info Encl PLA-1872, Second Interim Deficiency Rept Re GE Reactor Mode Switch. Initially Reported on 830407.Mode Switch Redesigned.Sample Will Be Independently Tested.Also Reported Per Part 21.Final Rept Will Be Submitted by Dec 19831983-09-30030 September 1983 Second Interim Deficiency Rept Re GE Reactor Mode Switch. Initially Reported on 830407.Mode Switch Redesigned.Sample Will Be Independently Tested.Also Reported Per Part 21.Final Rept Will Be Submitted by Dec 1983 ML20023E0541983-05-27027 May 1983 Deficiency Rept Re Narrow Range Resistance Temp Detectors Installed to Meet License Condition Failing to Operate.Cause Under Investigation.Detectors Replaced.Testing Modified Until Design Revised.Also Reportable Per Part 21 ML20023C5101983-05-0606 May 1983 Final Deficiency Rept Re Nonconforming Class IE Radiation Monitoring Sys Electronic Modules Mfg by Victoreen,Inc Due to Breakdown of QA Program.Initially Reported on 820917. Vendor Revised QA Program Reviewed & Approved ML20050A8921982-03-12012 March 1982 Interim Part 21 Rept Re 1/2-inch & 3/8-inch Plates Used in Category 1 Seismic Supports,Initially Reported 820310. Supports Containing 3/8-inch Plates Examined & hands-on Search of 1/2-inch Matl Conducted.Reportable Per Part 21 ML20039C1441981-12-18018 December 1981 Final Deficiency Rept Re Failure of RHR Sys LPCI Injection Valve 1F017-B,initially Reported 811120.Locking Mechanism Devised to Attach anti-rotation Pin to Stem Collar.Also Reported Per Part 21 ML20011A7131981-10-19019 October 1981 Final Deficiency Rept Re Inlet Piping Configurations for Pressurizer Safety Relief Valves W/Large Pressure Drops Possibly Leading to Valve Chatter,Initially Reported 810916. Inlet Piping Design Will Be Revised to Limit Pressure Loss ML20010G6761981-09-0909 September 1981 Final Deficiency Rept Re Available NPSH for Recirculation Spray Pumps,Originally Reported on 770812.Recirculation Spray Pump Arrangement Has Been Modified to Set Pumps Lower in Elevation.Assumptions Used Are Conservative ML20010C6111981-08-14014 August 1981 Part 21 Rept Re Potential for Stress Corrosion Cracking of Anchor Bolts,Originally Reported on 810813.Utils That Have Plants for Which Vendor Has Supports & Restraints Design Responsibility Will Be Notified of Problem ML20010J1801981-08-13013 August 1981 Supplemental Deficiency Rept Re Max Dose Rates on Containment Floor Exceeding Values Presented in FSAR, Initially Reported 780428.Addl Schielding Adequate to Reduce Max Containment Dose Rates.Supporting Documentation Encl ML20009F9571981-07-20020 July 1981 Interim Deficiency Rept Re Structural Integrity of Certain RCS Attached Pipe Not Verified for Postulated Breaks in RCS Piping,Originally Reported on 810129.Actions Will Be Taken to Ensure Adequacy of Design.Also Reported Per Part 21 ML20003E4191981-03-30030 March 1981 Interim Deficiency Rept Re Spurious Opening of Turbine Bypass Valves,Initially Reported 810309.Opening of Valves Could Result in DNBR Limits Being Exceeded.Also Reported Per Part 21 1997-09-30 Category:TEXT-SAFETY REPORT MONTHYEARML20217N9281999-10-20020 October 1999
[Table view]Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised ML20217H3631999-10-14014 October 1999 Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su ML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20217D6851999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for North Anna Power Station,Units 1 & 2.With ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML20216E5011999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Naps,Units 1 & 2. with ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML20210S1411999-07-31031 July 1999 Monthly Operating Repts for July 1999 for North Anna Power Station.With ML20210Q9931999-07-31031 July 1999 Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud ML20209E5641999-06-30030 June 1999 Monthly Operating Repts for June 1999 for North Anna Power Stations,Units 1 & 2.With ML20195G1901999-05-31031 May 1999 Monthly Operating Rept for May 1999 for NAPS Units 1 & 2. with ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20206Q6671999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for North Anna Power Station,Units 1 & 2.With ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML20205K3041999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for North Anna Power Station,Units 1 & 2.With ML20207K5921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for North Anna Power Station,Units 1 & 2.With ML20207E1731999-02-18018 February 1999 Informs Commission of Status of Preparations of IAEA Osart Mission to North Anna Nuclear Power Plant Early Next Year ML20205A0241998-12-31031 December 1998 Summary of Facility Changes,Tests & Experiments,Including Summary of SEs Implemented at Plant During 1998,per 10CFR50.59(b)(2).With ML20199C8781998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for North Anna Power Station,Units 1 & 2.With ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant ML20198J5561998-12-0303 December 1998 ISI Summary Rept for North Anna Power Station,Unit 1 1998 Refueling Outage Owner Rept for Inservice Insps ML20197G8551998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for North Anna Power Station,Units 1 & 2.With ML20196G1381998-11-0303 November 1998 Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit ML20195D0571998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for North Anna Power Station,Units 1 & 2.With ML20154L0691998-10-14014 October 1998 COLR for North Anna Power Station Unit 1 Cycle 14 Pattern Xy ML20155J6911998-10-0909 October 1998 Staff Response to Tasking Memorandum & Stakeholder Concerns ML20154H4001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for North Anna Power Station,Units 1 & 2.With ML20151X8011998-09-10010 September 1998 Special Rept:On 980622,groundwater Level at Piezometer P-22 Was Again Noted to Be Above Max Water Level by 0.71 Feet. Increased Frequency of Piezometer Monitoring & Installed Addl Piezometers at Toe of Slope Along Southwest Section ML20151W4711998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for North Anna Power Station Units 1 & 2.With ML20237A4341998-07-31031 July 1998 Monthly Operating Repts for July 1998 for North Anna Power Station,Units 1 & 2 ML20236V1251998-07-14014 July 1998 ISI Summary Rept for Naps,Unit 2,1998 Refueling Outage Owners Rept of Isis ML20236K5531998-07-0707 July 1998 SER Accepting Request for Change in ISI Commitment on Protection Against Pipe Breaks Outside Containment ML20236M3381998-06-30030 June 1998 Monthly Operating Repts for June 1998 for North Anna Power Station,Units 1 & 2 ML20248M1011998-05-31031 May 1998 Monthly Operating Repts for May 1998 for North Anna Power Station,Units 1 & 2 ML20248C8831998-05-29029 May 1998 SER Accepting Alternatives Proposed by Licensee for Use of Code Case N-535,pursuant to 10CFRa(a)(3)(i) in ASME Section XI Inservice Insp Program ML20247K9281998-05-15015 May 1998 Special Rept:On 980428,letdown PCV Exhibited Slow Response When C RCP Was Started.Cause to Be Determined.Review of Operating Procedure Will Be Performed to Determine If Enhancements Are Necessary ML20216A8971998-05-0606 May 1998 Rev 0 to Cycle 13 Pattern Ud COLR for North Anna Unit 2 ML20247F4441998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for North Anna Power Station,Units 1 & 2 ML20217B5321998-04-20020 April 1998 Safety Evaluation Supporting Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Plant Reactor Vessel Head Penetrations for part-length CRDMs ML20217H9611998-04-0707 April 1998 Special Rept:On 980216,groundwater Level at Piezometer P-22, Again Noted to Be Above Max Water Level by 0.41 Feet.Design Package for Installation of Addl Standpipe Piezometers at Toe of Slope Southeast Section,Developed ML20216B1891998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for North Anna Power Station,Units 1 & 2 ML20216E8801998-03-0606 March 1998 Safety Evaluation Authorizing Licensee Request for Relief from ASME Code Requirements,Paragraph IWA-2400(c) (Summer Edition W/Summer 1983 Addenda),For Upcoming Naps,Unit 1 Outage,Per 10CFR50.55a(a)(3)(ii) ML20216E2561998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for North Anna Power Station,Units 1 & 2 ML20199J6431998-02-0202 February 1998 Safety Evaluation Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 SW Piping for North Anna,Unit 1,as Submitted in ISI Relief Request NDE-46 on 971218 ML20202D5811998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for North Anna Power Station,Units 1 & 2 ML20198S7571998-01-15015 January 1998 Safety Evaluation Accepting Licensee Request for Approval to Repair Flaws IAW GL-90-05 for ASME Code Class 3 Svc Water Piping ML20198P1351997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for North Anna Power Station,Units 1 & 2 1999-09-08 |
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Ve co VIRG4NI A ELECTRIC AND POWER COMP ANY, RICHMOND, VIRGINI A 23261 October 10, 1979 Mr. James P. O'Reilly, Director Serial No. 7/7A Office of Insoection & Enforcement PSELC/SCJ:mac: wang U. S. Nuclear Regulatory Conmission Region II Docket No. r0-130 101 Marietta Street, Suite 3100 Atlanta, Georgia 29303
Dear "r. O'Reilly:
On September 10, 1979, a racort was made under tha orovisions of 100FRSO.5E(e) concernino the Emergency Diesal Generator Fan Ccoling System.
During a review of equipment soccifications and the subsequent analysis of local meteoroloqical data, it was esccvered that ambiert tencerature ranges exist which exceed the original design limits of the Fan Cooling Systam. This ,
nacassitates that seasonal blade pitc5 anale changes be mde to insure that the fan irive shaft coupling horsapower limit of 130 H.P. is not exceeded.
Powaver, the Emergency Diesel Generator must be in a secutad mode to nWe the manual blade oitch changes.
To eliminate this time consurmina crocedure and the subsacuent unavailability of the Emergency Diesel Generators, the manufacturer (Fairbanks Morse) has engineered a modification to the current fan drive shaft couoling that will increase the f an drive shaft torsional load carrying capability from 180 to 230 H.P. This will allow the Emergency Diesel Generator to operate throughout the vear at a fixed blade pitch angle without overloading the 'an drive shaft. The modification involves the addition of two Solts to the current 'our bolt couclino desicn.
This letter is an interim 30-day *eport on this subje-t and a final report will be submitted when the corractiva action is co731ste. If additional information is required for your review, please notify us.
Verytruly/yours,
. 8 5' : ' '* * , '
l .W'
.
Sam C. 3r wn, Jr.
Senior Vice President ?cwer Station Engineering and Construction cc: Vr. Victor Stello, Director Office of Inspection t Enforcement Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation 1i5i 271 % \
7 91015 0 + /
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