Similar Documents at Surry |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML18153A1431997-06-10010 June 1997 Part 21 Rept Re Possible Machining Defect in Certain Stainless Steel Swagelok Tube Fitting Bodies.Facilities Have Been Notified About Possible Problem ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause ML20086A2751995-06-27027 June 1995 Part 21 Rept Re Several Incidents of Instrument Drift in Excess of Specified Limits for Rosemount Pressure Transmitter Model 1154SH9.Other Licensees Advised to Be Alert to Differences in Pressure Indication 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 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 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 ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced 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 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 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 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 ML20214M3181986-09-0404 September 1986 Potential Part 21 Rept Re Contromatics Actuator W/Jackscrew/ Handwheel Emergency Override Operator.Jackscrew/Handwheel Should Be Used for Emergency Manual Operation Only.Encl Ltr Also Sent to Listed Utils/Ae Firms 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 ML20125B1611985-06-0606 June 1985 Supplemental Part 21 Rept Re Addl Circuit Breakers,Furnished as Spares,W/Overcurrent Trip Devices That May Have Short Time Delay Band Lever.Items Require Insp & Replacement If Link Found Incorrect 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 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 ML20087P7951984-03-0808 March 1984 Interim Part 21 Rept Re Linear Converters Furnished by Pacific Air Products.Initially Reported on 840213.Vendor Investigation of Possible Causes of Excessive Wear Underway. Next Rept by 840730 ML20086L0921984-01-30030 January 1984 Part 21 Rept Re Linear Converter Device W/Possible Generic Defect.Initially Reported on 840116.Written Notifications Issued.Customer Responses Should Be Received by 840331.Final Rept Will Be Submitted by 840430 ML20086L0981984-01-17017 January 1984 Part 21 Rept Re Linear Converter Device W/Possible Generic Defect.Initially Reported on 840116.Preliminary Analysis Indicates Excessive Wear of Brass Shaft Guides.Next Rept Will Be Submitted within 90 Days.Supporting Info Encl ML20072N9891983-07-0808 July 1983 Interim Part 21 Rept Confirming 830705 Telcon Re Anomalies in Artificially Aged Apparatus (Using Ahrrenius Methodology W/Elevated Temp Aging).Deficiency Found During Qualification Testing for IEEE 323-1974.Draft Notices Encl ML20010C7321981-08-12012 August 1981 Part 21 Rept Re Incompatibility Between Crosby 6X10 & 8X10 Safety Relief Valve Solenoids.Vendor Will Inspect Assemblies Using Stricter Acceptance Criteria ML18139B1831981-03-11011 March 1981 Part 21 Rept,Originally Reported 790525,re Steam Generator Feet Bolt Hole Discrepancies.Corrosion Removed.Rusted & Galled Threads Cleaned by Running Helicoil Tap Into Bolt Holes Prior to New Helicoil Installation ML18139A8731980-11-19019 November 1980 Part 21 Rept Re S&W Notification That out-of-phase Transfer Might Occur When Emergency Buses Are Transferred from Offsite Power Source to Emergency Diesel Generators After Reaching Rated Speed & Voltage.Originally Reported 801114 ML19320D1951980-07-0202 July 1980 Part 21 Rept Re Existence of Nonconservative Assumption in Cold Shutdown Design Basis Boron Dilution Accident Analysis in Fsar.Caused by Use of Incorrect Sys Vol.Review Will Be Performed to Identify & Analyze Addl Accidents ML18114A6941979-06-14014 June 1979 Failure of Solenoid Operated Valves to Meet IE Bulletin 79-01 Environ Qualification Requirements.Environmentally Unqualified Valves Have Been or Will Be Replaced 1997-06-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18152A2811999-10-12012 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. ML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With 991012 Ltr ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 990915 Ltr ML18152B4421999-08-27027 August 1999 LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr ML18152B4411999-08-27027 August 1999 LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed ML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage. ML18152B3771999-08-13013 August 1999 LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms ML18152B3791999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 990811 Ltr ML18152B3911999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With 990713 Ltr ML18152B4341999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 990614 Ltr ML20195E2401999-05-31031 May 1999 Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag ML18152B4181999-05-18018 May 1999 LER 99-002-00:on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With 990518 Ltr ML18152B4161999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 990512 Ltr ML18152B4111999-04-28028 April 1999 LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr ML18152B6511999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2 ML18153A2741999-03-29029 March 1999 LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212 ML18153A2681999-03-19019 March 1999 LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr ML18152B7331999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With 990310 Ltr ML18152B5421999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With 990210 Ltr ML18151A3031999-01-29029 January 1999 ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements. ML18152B7261999-01-21021 January 1999 LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable ML18152B6011998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With 990115 Ltr ML18152B5781998-12-16016 December 1998 LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B5811998-12-16016 December 1998 LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B7121998-12-0404 December 1998 LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened ML18152B7041998-12-0101 December 1998 LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr ML18152B7081998-11-30030 November 1998 Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un. ML18152B5721998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With 981214 Ltr ML18152B6161998-11-0606 November 1998 LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable ML18152B6241998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With 981111 Ltr ML18152B6081998-10-23023 October 1998 LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely ML18152B6881998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With 981012 Ltr ML18153A3271998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2 ML18152B7811998-07-31031 July 1998 LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status ML18153A3161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2.W/980807 Ltr ML18152B7621998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Surry Power Station,Units 1 & 2.W/980707 Ltr ML18153A2581998-06-0303 June 1998 LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML18153A3141998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Surry Power Station,Units 1 & 2.W/980610 ML18152B8241998-05-22022 May 1998 LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed ML18152B8161998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Surry Power Station Units 1 & 2.W/980508 Ltr ML18152B7951998-04-29029 April 1998 LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6 ML18153A2511998-04-22022 April 1998 LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced ML18153A2521998-04-22022 April 1998 LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame ML20217P9941998-04-0707 April 1998 Safety Evaluation Granting Licensee Third 10-yr Inservice Insp Program Relief Requests SR-018 - Sr-024 ML18153A2951998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sps,Units 1 & 2.W/ 980408 Ltr ML18153A2391998-03-13013 March 1998 LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued ML18153A2341998-03-0909 March 1998 LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition ML18153A2301998-03-0606 March 1998 LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs ML18153A2251998-03-0404 March 1998 LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket 1999-09-30
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W g ?e VIRGINIA ELECTHIC AND POWER COMPANY i s' Rici Mono, VIRGINIA 202 61 June 27,1995 U. S. Nuclear Regulatory Commission Serial No.95-318 Attention: Document Control Desk NL&P/DAS Washington, D.C. 20555 Docket Nos. '50-280 50-281 License Nos. DPR-32 ,
DPR-37 Gentlemen:
VIRGINlA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 NOTIFICATION OF DEFECT IN ACCORDANCE WITH 10 CFR 21 ,
. Virginia Electric and Power Company (Virginia Power) has identified several incidents 4 of instrument drift in excess of specified limits for the Rosemount pressure transmitter Model 1154SH9. In accordance with 10 CFR 21.21, the following information is provided as written notification of an existing defect.
- 1. Name and address of the individual or individuals informing the Commission.
Mr. R. F. Saunders Vice President - Nuclear Operations Virginia Einctric and Power Company 5000' Dominion Boulevard Glen Allen, Virginia 23060
- 2. Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect.
Surry Power Station Units 1 and 2 Rosemount Pressure Transmitter Model 1154SH9
- 3. Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect.
Rosemount Aerospace Inc.
1256 Trapp Road Eagan, MN 55121 Attn: Mr. K. Ewald Business Unit Manager 300071 9507030139 950627 0 PDR ADDCK 05000280 /
p{p l S PDR
- 4. Nature of the defect or failure to comply and the safety hazard which is created or could be created by such defect or failure to comply.
In February 1995, Virginia Power initiated a root cause evaluation (RCE) to determine me cause of calibration discrepancies identified with the pressurizer pressure protection transmitters. During this evaluation, three spare Model 1154SH9 transmitters were tested in an oven to determine if they were affected by temperature variations. As a result of this testing and readings taken in the process racks, Virginia Power concluded that some Rosemount Model 1154SH9 pressure transmitters were exhibiting instrument drift greater than specification. This drift was due to changes in containment ambient temperature between calibration during shutdown and normal operations.
Affected transmitters exhibited a zero shift in the negative direction of between 6 '
and 15 psig. This shift was greater than the 5.8 psig shift expected for such temperature variation as specified in Rosemount Product Data Sheet PDS 2631/4631 Rev 8/93 and the Part 21 letters from Rosemount to Virginia Power on May 27,1993 and August 31,1993. Although this instrument drift was not safety significant for Surry, it was a causal factor in an incident in which Unit 2 pressurizer pressure channels had been set outside of Technical Specification limits. Accordingly, it was determined that given the variability observed in instrument drift and the multiple examples of occurrence, this condition could have the potential to be safety significant in other similar safety-related applications at other facilities dependent on plant specific setpoint margins.
Specific applicability with respect to safety systems or licensee facilities is not known.
- 5. The date on which the information of such defect or failure to comply was obtained.
April 26,1995
- 6. In the case of a basic component which contains a defect or fails to comply, the number and location of all such components in use at, supplied for, or being supplied for one or more facilities or activities subject to the regulation in this part.
There are twelve Model 1154SH9 pressure transmitters at Surry: three installed in Unit 1 for pressurizer pressure, three installed in Unit 2 for pressurizer pressure, and six spares. Only the three Unit 2 pressurizer pressure transmitters and one spare have exhibited excessive instrument drift and are therefore affected by this notification. There are seven Model 1154SH9 pressure transmitters at North Anna: three installed in Unit 1 for pressurizer pressure, three installed in Unit 2 for pressurizer pressure and one spare.
Excessive instrument drift has not been observed in the transmitters presently installed. (One previous Unit 2 transmitter, which had exhibited excessive shift, was replaced earlier with a spare.)
- 7. The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action.
o As stated above, Virginia Power performed an RCE which resulted in the identification of the excessive instrument drift concern, the variability of the degree of drift between individual transmitters, and the individual transmitter applicability (i.e. not all Model 1154SH9 transmitters exhibit excessive drift).
Individual instrument channels-identified as subject to the excessive drift phenomena were evaluated to ensure continued operability by establishing that the individual transmitter drift was within overall channel setpoint margins.
The NRC was advised of our preliminary findings in a meeting with Region ll on April 24,1995. Copies of our RCE were provided to the resident inspectors.
The industry was notified of our RCE findings in an INPO Network entry made oriJune 15,1995, which addressed various calibration enors identified with the pressurizer pressure protection transmitters.
We will continue to work with the manufacturer and intend to ship one of the transmitters exhibiting excessive drift for future investigations of the condition we have observed.
- 8. Any advice related to the defect or failure to comply about the facility, activity or basic component that has been, is being or will be given to purchasers or licensees.
Virginia Power advises other licensees to be alert to differences in pressure indication between individual Model 1154SH9 transmitters as well as between functional groupings of Model 1154SH9 transmitters and other related but non-Model 1154SH9 pressure indications. Either circumstance might indicate the presence of excessive shift. Furthermore for temperature sensitive applications, consideration should be given in the interim to temperature testing Model 1154SH9 transmitters prior to use to determine actual temperature related shifts.
Should you have any questions or require additional information, please contact Mr. M. L. Bowling, Manager Nuclear Licensing and Programs, at (804) 273-2699.
Very truly yours, R. F. Saunders Vice President - Nuclear Operations 1
I
.d' i cd: U. S. Nuclear Regulatory Commission.
Region 11 ,
'101 Marietta Street, N. W.
Suite 2900 :
Atlanta, Georgia 30323 -
Mr. M. W. Branch +
NRC Senior Resident inspector Suny Power Station
' Mr. R. D. McWhorter NRC Senior Resident Inspector ;
North Anna Power Station -
Mr. K. Ewald - '
Business Unit Manager Rosemount Aerospace Inc.
1256 Trapp Road ~
Eagan, Minnesota 55121 i
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l 1
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