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Category:NRC TECHNICAL REPORT
MONTHYEARML20248F0001989-09-29029 September 1989 Debris in Containment Recirculation Sumps, Technical Review Rept ML20204J6141988-08-31031 August 1988 AEOD/E807, Pump Damage Due to Low Flow Cavitation ML20245B6061988-08-31031 August 1988 Inadequate NPSH in HPSI Sys in Pwrs, Engineering Evaluation Rept ML20196G5251988-06-15015 June 1988 Technical Review Rept T809, Blocked Thimble Tubes/Stuck Incore Detector ML20245H9601988-04-15015 April 1988 BWR Overfill Events Resulting in Steam Line Flooding, AEOD Engineering Evaluation Rept ML20148D0671988-03-17017 March 1988 Headquarters Daily Rept for 880317 ML20148B3291988-03-14014 March 1988 Headquarters Daily Rept for 880314 ML20196H6351988-03-0808 March 1988 Headquarters Daily Rept for 880308 ML20196G8881988-03-0303 March 1988 Headquarters Daily Rept for 880303 ML20147E3961988-01-0606 January 1988 Rept of Interview W/Rg Lagrange on 841206 & 14 to Discuss Info Contained in B Hayes 841017 Memo Identifying Series of Submittals Received from Util Between 1980 & 1984 ML20147E3211988-01-0606 January 1988 Rept of Interview W/Rg Lagrange to Discuss Gpu 830520 & s Re Environ Qualification equipment.Marked-up 850409 Statement from H Hukill Also Encl ML20237L3001987-08-24024 August 1987 AEOD/E709 Engineering Evaluation Rept Re Auxiliary Feedwater Trips Caused by Low Suction Pressure.Draft Info Notice Encl ML20235C9311987-06-23023 June 1987 Rept to ACRS Re Humboldt Bay Unit 3 - Core II ML20212F6581986-12-31031 December 1986 Technical Review Rept, Degradation of Safety Sys Due to Component Misalignment &/Or Mispositioned Control/Selector Switches ML20212D9091986-12-23023 December 1986 Localized Rod Cluster Control Assembly (Rcca) Wear at PWR Plants, Engineering Evaluation Rept ML20212B0321986-12-17017 December 1986 Emergency Diesel Generator Component Failures Due to Vibration, Engineering Evaluation Rept ML20214R4851986-10-0909 October 1986 Initial OL Review Rept for Seabrook Station Unit 1 ML20212K6641986-08-0707 August 1986 Inadvertent Recirculation Actuation Signals at C-E Plants, Technical Review Rept ML20206H0871986-03-0303 March 1986 Allegation Review Data Sheet for Case 4-85-A-013 Re Const Activities.Addl Info Requested from Alleger.Case Closed Due to Lack of Response.Related Info Encl ML20206H0761986-01-21021 January 1986 Allegation Review Data Sheet for Case 4-84-A-085 Re Alteration of Personnel Records.Based on Resolution of Allegation 4-84-A-094,case Closed ML20137X6151986-01-0909 January 1986 Engineering Evaluation of Deficient Operator Actions Following Dual Function Valve Failures ML20234F5601985-12-17017 December 1985 Draft Hazards Analysis ML20234F4751985-12-17017 December 1985 Licensing of Power Reactors by Aec ML20214T2211985-11-25025 November 1985 Initial OL Review Rept:Millstone Point Unit 3 ML20206H0621985-10-15015 October 1985 Allegation Review Data Sheet for Case 4-85-A-045 Re Inadequate Handling/Installation Procedures for Equipment, Vendor Control Programs & Spare Parts.Based on Insp Rept 50-482/85-22,case Closed ML20206H0371985-10-0202 October 1985 Allegation Review Data Sheet for Case 4-85-A-044 Re Lack of Effective QA Programs & QC Insps.Based on Insp Rept 50-482/85-22,allegation Closed IR 05000482/19850191985-09-30030 September 1985 Allegation Review Data Sheet for Case 4-85-A-050 Re Mishandling of Document Control Program.Concerns Addressed in Insp Rept 50-482/85-19.Dept of Labor & Allegation Cases Closed ML20206H0131985-09-27027 September 1985 Allegation Review Data Sheet for Case 4-84-A-076 Re Vague Administrative Procedures,Calibr Program Not Working,Test Engineer Authority & Harassment.Based on Insp Rept 50-482/85-03,case Closed ML20137B1231985-09-16016 September 1985 HPCS Sys Relief Valve Failures, Engineering Evaluation Rept ML20206G8431985-09-0303 September 1985 Allegation Review Data Sheet for Case 4-84-A-013 Re Improper Termination of Employee Due to Refusal to Weld Laminated Pipe.Welding non-safety Related.Case Closed on 850827.W/ 840315 Telcon Record & Addl Info IR 05000482/19850311985-08-28028 August 1985 Allegation Review Data Sheet for Case 4-85-A-077 Re 6 Rem Exposure in Containment Bldg Due to Pipe Break.Allegation Investigated During Insp 50-482/85-31 on 850715-19 & Found Unsubstantiated ML20206G8051985-08-27027 August 1985 Allegation Review Data Sheet for Case 4-84-A-114 Re Drugs Planted at Plant.Evidence Destroyed in Testing.Based on Insp Rept 50-482/85-03 & Mullikin 850429 Memo,Case Closed ML20206G7781985-08-27027 August 1985 Allegation Review Data Sheet for Case 4-84-A-195 Re Quality First.Fuel Load Issue Resolved in Insp Rept 50-482/85-10. Technical Issues to Be Resolved Prior to Full Power Licensing.Case Closed w/850815 Memo to File ML20209G3051985-08-0909 August 1985 Closure of ECCS Min Flow Valves, Engineering Evaluation Rept.Recommends IE Issue Info Notice to Remind Licensees of Importance of Min Flow Bypass Capability as Essential Pump Protection Feature ML20206H1021985-07-30030 July 1985 Allegation Review Data Sheet for Case 4-84-A-008 Re Improper Const Practices.Insp Rept 50-482/84-12 Issued on 841012 & Closeout Ltr Sent on 850405 ML20206H0801985-07-30030 July 1985 Allegation Review Data Sheet for Case 4-84-A-007 Re Intimidation of QC Inspector.Forwards Documents Closing Allegation.W/O Encls ML20147E4401985-06-20020 June 1985 Rept of Interview W/Cw Smyth on 850510.Smyth Advised of Unfamiliarity W/Environ Qualification Program in Technical Sense & W/Documentation Needed to Qualify Individual components.Marked-up Lw Harding Statement Encl ML20199G0701985-05-0303 May 1985 Partially Withheld Statement of Decision Re Allegation AQ-38 Concerning Alleged Harassment of QC Inspectors Upon Observation of Weld Defects on vendor-inspected Restraints. Allegation Substantiated.Addl Allegation Repts Encl ML20147H0101985-04-16016 April 1985 Draft Summary Rept for Regional Evaluation of Texas Utils Electric Co,Comanche Peak Steam Electric Station ML20206G9151985-03-12012 March 1985 Allegation Review Data Sheet for Case 4-84-A-015 Re Harassment of Mechanical/Welding QC Inspector for Writing Nonconformance Rept Re Improper Welding Amperage by Superintendent.Util Rept Issued & Case Closed ML20147G9901985-01-31031 January 1985 Summary Rept for Regional Evaluation of Texas Utils Electric Co,Comanche Peak Steam Electric Station ML20205Q7691985-01-18018 January 1985 Status Rept Mechanical/Piping Area. Related Info Encl ML20206G8861985-01-0909 January 1985 Allegation Review Data Sheet for Case 4-85-A-004 Re Electrical Installations.Insp Required.Related Info Encl ML20214R5681984-12-31031 December 1984 Shoreham Nuclear Power Station Initial OL Readiness Assessment ML20214T7251984-11-30030 November 1984 Summary Rept for Regional Evaluation of Diablo Canyon Unit 2 ML20206G8131984-10-0303 October 1984 Allegation Review Data Sheet for Case 4-84-A-102 Re Visual Insp Through Paint,Unfair Intimidation to Produce Results, Rejection of Previous Inspected Welds,Defective Welds & Missing Beams.Addl Info Encl ML20206G7731984-10-0101 October 1984 Allegation Review Data Sheet for Case 4-84-A-098 Re Qa/Qc Program Allegations Re Matl Verification, post-ok Reviews by Engineers & Improper Verification of Snubber Transaction Assemblies ML20206H2431984-09-13013 September 1984 Allegation Review Data Sheet for Case 4-84-A-89 Re Kickbacks & Coverups in QA Dept.State of Ks Interested.No Federal Regulations Violated If Kickback Allegations true.W/840912 Telcon Record.Related Info Encl ML20205Q7591984-08-31031 August 1984 Preliminary Summary of Allegations for Comanche Peak Steam Electric Station,Units 1 & 2 ML20206H2321984-08-17017 August 1984 Allegation Review Data Sheet for Case 4-84-A-80 Re False Resume Submitted to Louisiana Power & Light Co W/Plant Listed as Former Place of Employment 1989-09-29
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18094B3211990-02-28028 February 1990 Annual Operating Repts for 1989 for Salem & Hope Creek Generating Stations ML20012A9011990-02-27027 February 1990 Suppls 900213 10CFR21 Rept Re Chilled Water Sys Operation. Evaluation of Crystal River Determined That Postulated High Energy Line Break in Intermediate Bldg May Be Subj to Steam Loads Higher than Normal Loads,Causing Rising Water Temp ML20011F1941990-02-22022 February 1990 Part 21 Rept Re Abb 27/59 Relay Catalog Series 211L.Solder Connections to Printed Wiring Runs on Bottom of Circuit Board Deteriorated Due to Thermal Stress.No Actual Failure Occurred & Relays to Be Changed at Next Outage ML20011F5971990-02-22022 February 1990 Part 21 Rept Re Solder Connections in Abb 27/59 Relays Deteriorated Due to Thermal Stress,Causing Bonding of Printed Wiring Pattern to Glass Epoxy Circuit Board.Interim Circuit Board W/Larger Pads & Higher Wattage Will Be 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 ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20006A8231990-01-10010 January 1990 Errata to Rev 3 to BAW-1543, Master Integrated Reactor Vessel Surveillance Program Consisting of Revised Tables 3-20 & E-1 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 ML17347B4621989-12-31031 December 1989 App a to USI A-46 & Generic Ltr 87-02. ML18094B1471989-10-25025 October 1989 Emergency Plan Annual Exercise 1989 for Artificial Island on 891025. W/One Oversize Drawing ML19325E0861989-10-16016 October 1989 Followup Part 21 Rept Re Class 1E Battery Chargers W/ Transformers Running at Temps Exceeding Those Used in Qualification Rept When Operating at or Near Full Load Rating of Equipment.Listed Corrective Actions Underway ML19351A2941989-10-0909 October 1989 Part 21 Rept Re Potential of Ambient Compensated Molded Case Circuit Breakers to Deviate from Published Info. Instantaneous Trip Check Will Be Instituted on All Class 1E Thermal/Magnetic Ambient Breakers Prior to Shipment ML20248G8291989-10-0202 October 1989 Rev 19 to YOQAP-I-A, Operational QA Program ML17347B3821989-09-30030 September 1989 Monthly Operating Repts for Sept 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2.W/891016 Ltr ML19351A4191989-09-30030 September 1989 Mark-BW Reload LOCA Analysis for Catawba & McGuire Units. ML19327C0681989-09-30030 September 1989 Nuclear Safety & Compliance Semiannual Rept Number 11,Apr- Sept 1989. W/891027 Ltr ML19325C9521989-09-29029 September 1989 Part 21 Rept Re Potential Common Failure of SMB-000 & SMB-00 Cam Type Torque Switches Supplied Prior to 1981 & 1976. Vendor Recommends That Switch W/Fiber Spacer Be Replaced ML20248F0001989-09-29029 September 1989 Debris in Containment Recirculation Sumps, Technical Review Rept ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating ML20248D1571989-09-13013 September 1989 Rev 56 to QA Program ML20247K2531989-09-11011 September 1989 Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively ML20247E3761989-09-0707 September 1989 Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML17347B3341989-08-31031 August 1989 Monthly Operating Repts for Aug 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2.W/890913 Ltr ML20246D6871989-08-14014 August 1989 Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks ML20248C0731989-08-0303 August 1989 Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants ML18008A0311989-07-31031 July 1989 NTH-TR-01 Decrease in Heat Removal by Secondary Sys. ML17347B2731989-07-31031 July 1989 Monthly Operating Repts for Jul 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2 ML19327B4011989-07-31031 July 1989 Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel. ML20246P7111989-07-17017 July 1989 Part 21 Rept Re Quench Cracks in Bar of A-SA-193 Grade B7 Component.Quench Cracks Found in One Bar of Matl.Listed Purchasers Informed of Potential Defect.Next Rept Will Be Submitted When Addl Info Becomes Available 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 ML17347B2741989-06-30030 June 1989 Corrected Monthly Operating Repts for June 1989 for Turkey Point Units 3 & 4 ML17347B1851989-06-30030 June 1989 Monthly Operating Repts for June 1989 for St Lucie Units 1 & 2 & Turkey Point Units 3 & 4.W/890717 Ltr ML20246D6711989-06-30030 June 1989 Criticality Analysis of Byron/Braidwood Fresh Fuel Racks ML20247H0711989-06-30030 June 1989 Description & Verification Summary of Computer Program, Gappipe ML20246L2571989-06-26026 June 1989 Safety Evaluation Supporting Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20247H0791989-06-22022 June 1989 App to Description & Verification Summary of Computer Program,Gappipe ML18151A5411989-06-21021 June 1989 Updated Operational QA Program Topical Rept. ML20245B6651989-06-15015 June 1989 Part 21 Rept 150 Re Potential Defect in Component of Dsr Standby Diesel Generator.Cause of Failure Determined to Be Combination of Insufficient Lubrication to Bushings.Listed Course of Action Recommended at Next Scheduled Engine Maint ML18101A4931989-06-13013 June 1989 Radiological Emergency Preparedness Exercise Evaluation Rept. ML17345A7241989-06-0909 June 1989 Rev 15 to Topical QA Rept. ML20247N0621989-05-31031 May 1989 Production Training Dept,Braidwood,Malfunctions & Initial Conditions ML17345A7501989-05-31031 May 1989 Monthly Operating Repts for May 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2 ML20247K3011989-05-12012 May 1989 Leak-Before-Break Evaluation for Carbon Steel Piping ML20247L1841989-05-12012 May 1989 Leak-Before-Break Evaluation for Stainless Steel Piping, Byron & Braidwood Nuclear Power Stations Units 1 & 2 ML17345A6851989-04-30030 April 1989 Monthly Operating Repts for Apr 1989 for Turkey Point Units 1 & 2 & St Lucie Units 1 & 2.W/890515 Ltr ML17345A7531989-04-30030 April 1989 Corrected Monthly Operating Rept for Apr 1989 for St Lucie Unit 2 ML18094A3551989-04-30030 April 1989 Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles. 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 ML20245J0751989-04-25025 April 1989 Safety Evaluation Supporting Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20244D8161989-04-13013 April 1989 Part 21 Rept Re Failure of Rosemount Transmitters.All Failed Transmitters Replaced,Inservice Test Procedure Prepared & Monthly Test of All 12 Transmitters in RCS Throughout Cycle 2 Operation Will Be Performed.Review Continuing 1990-02-28
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SAFETY ISSUg8 3 BODECA BAY REACTOR 1
- 1. The Bodega Bay reactor proposed by PG&E is similar in all important i design e.oncepts to several other successfully operating reactors.
- 2. There are no innovations, new principles or concepts of any substance !
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in this application. For example, most of the systems follow the )
, design concepts and principles already in successful une in other plants, including such systems ass, 4, Wgj,lj y,im/A :n ~ ri~ dj'~'" < f
) # g',/g - (gf the* pressure v6ssel W_ h the primary system pi the core design ,
the control system the inetrissentation system .*
,1#jgo p'y],fjr the poison injection system ,
- .,,./y / l emergency cooling systems the auxiliary power system *[ j, ' ,,
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radiation monitoring y; 1 ( ,J/, .4 ;
waste treatment, storage, disposa l.
3.
$ fM & J r*) n . % A J 2.., D k s- W ',: ' j^ ~ ~ C Matters on which some thought will'be given as the detailed design is finalized includes
- a. The thickness of fuel element cladding, now entatively proposed as 11 mils. The applicant may decide later o use thicker cladding. g If th(Deladding is used, the occurrence of fa lures before intended cad of life, which would release fission products into the primary ;
n- j coolant, might force uneconomical shutdowns. j ;The% > 4 be no re would 3 i
substantial he.sards, and the eventual outcome would depend on i economic balances to the operator. j I
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1 l- b. Design of control blades,now under study, may result in in'breased assurance that inadvertent blade drop-out would e s
g not occur, Nf/*WAw n ,a n ). M *
- c. The design details on the over-all contaimsent volmes' and on individual penetrations of containment must be developed to :
mee w te a initial and subsequent periodic pressure and leek test measurements to an extent which has not.previoisslyr been
. required N This p.um dods6 .n fu 7./' L A o not ari from extra hazards. in this plant .
nor from less favorable site, but from realization that procedures -
in previous plants have not been adequate.
- d. The number and location of isolation valhs' in the primary system pipes-leaving the suppression pool containment have not been finally settled. M/ 7 ) i"7 p brAJ '- .a t)"~~j f a R -* ~-
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- e. The applicant proposes to operate with a higher percentage of steam voltane in the core.t'han has been customary. Further analytical, work and some limited and controlled initial' operations of the h plant will eventually determine whether or. not this is feasible.)f 'Y u.,,.f A 1.h g JA bsa veh vr..-s,:4 .r..4:u 4 . O .
l 4. There are ab systems on which research and development mund.u be y.,,
doney, to settle concepts, principles and general arrangements.
- 5. On some matters, further work and collection of infonsation must be done in finalising design details,
- s. Where and to what extent internal baffles are needed in the suppression pool will be determined by experiments now 3
in progress at Hoss Landing.
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- b. 'An environmental monitoring program, including surveys of ocean 4 9
currents, marine life, etc. as well as radioactivity levels is I i
being conducted to provide a reference level for determination /
whether any changes occur later as' a result of plant operation.-
- c. Detailed meteorological observations are being made to provide Infomation needed in detemining operating procedures and license limitations.
- 6. Accident calculations and site characteristics lead ' to determination of contaimeent pressure and leakage specifications 'and to containment voltanes, as follows: _. _ _.._ -. .-
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The plant dry well and suppression pool are designed to these values i
respectively, and, we believe, are adequate.
- 7. The site for this reactor is an excellent one in all respects but one, naaely, the proximity to the well-known St. Andreas earthquake, which runs \@ P feet to the northeast of the proposed reactor location. The population distribution is favorable, the isolation distance factors are well within acceptable ranges, the meteorology, 'though not good for certain portions of the time, is as good or better than that in California generally, and, with the isolation distances, the contaimeent characteristics already described, and generally known ap successfully proven plant characteristics, is considered acceptable The on (.fM 4 ') ly rea issue yet to be cattled, either in plant location or i.n the extra and additional design safeguards on otherwise adequate plant systems, is the proeimity of the plant to the St. Andreas fault and the implications this has for the plant.
xl Except for the earthquake question, the site & design features would pemit Eranting of a construction permit forthwith. Because of the question,'however, on which further data remain to be assembled, the acceptability' of the site is not -
settled, and if a9ceptable, chether and to what extent extra safeguards and -
structural reinforcements on components and systems also remain to be detemined.
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