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| | issue date = 02/16/1981 | | | issue date = 02/16/1981 |
| | title = Interim Deficiency Rept Re Heating,Ventilation & Air Conditioning for Class IE Motor Control Ctrs,Initially Reported on 801017.Design Change Has Been Developed.Final Rept Will Be Issued by 811231 | | | title = Interim Deficiency Rept Re Heating,Ventilation & Air Conditioning for Class IE Motor Control Ctrs,Initially Reported on 801017.Design Change Has Been Developed.Final Rept Will Be Issued by 811231 |
| | author name = CHIANGI N J | | | author name = Chiangi N |
| | author affiliation = CAROLINA POWER & LIGHT CO. | | | author affiliation = CAROLINA POWER & LIGHT CO. |
| | addressee name = OREILLY J P | | | addressee name = Oreilly J |
| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) | | | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| | docket = 05000400, 05000401, 05000402, 05000403 | | | docket = 05000400, 05000401, 05000402, 05000403 |
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| {{#Wiki_filter:'I vt e~ACCESSION NOR: I-AGIL:bo 400'-'o-HI So" 4tl2 50 H3 au'r H, IIAMt.GIiXaAt,"I'",N, J.REL''1'P NaMi O'AEICLYi J~P~REGULATORY INFORMATION DISTRroutrON SYSTEM (RrDs)6102250061 DOC, DATE: S1/02/16 NOTARLZED: | | {{#Wiki_filter:vte ~ 'I REGULATORY INFORMATION DISTRroutrON SYSTEM (RrDs) |
| NO Shearon Harris Nuclear Power Plant~Unit l~Carolina bhearon Harris Nuclear Power Plant~Unit 2~Carolina Shea'ron Harris Nuclear Power Ptantq Unit 3~Carolina 8hearon Harris Nuclear power I lant<Unit~1i Caro'lina auTHux at.FT'LraTioN Carolina Vower tc Light Co~AECII'IEN I AFFILIATION Region 2i Atlanta;Uf fice of the Director DOCKET¹05600400 oSootI4oi OSOOO4O2 osooo4o3 SUBJEC'l': | | ACCESSION NOR: 6102250061 DOC, DATE: S1/02/16 NOTARLZED: NO DOCKET ¹ I-AGIL:bo 400 Shearon Harris Nuclear Power Plant~ Unit l~ Carolina 05600400 |
| Interim deficienc condi.tfoning for r epoi ted on 60101 rept wi l 1 be issu DISTRIBUTION CODE: 8 019S TITLE: Construction Defici NOTES: y rept re heating~ventilation L air I t:lass IE'motor control ctrsiinitiat ly 7'esign change has been developed.Final ed by 811231.COPIES RECEIVED:LTR ENCL SIZE: ency Repor t (10CFA50.55E) | | '-'o-HI bhearon Harris Nuclear Power Plant~ Unit 2~ Carolina oSootI4oi So" 4tl2 Shea'ron Harris Nuclear Power Ptantq Unit 3~ Carolina OSOOO4O2 50 H3 8hearon Harris Nuclear power I lant< Unit ~1i Caro'lina osooo4o3 au'r H, IIAMt. auTHux at.FT'LraTioN GIiXaAt,"I'",N,J. Carolina Vower tc Light Co ~ |
| ACl ION INTERNAL: RECIPIENT 10 CODY7NAME A/D LICE NSNG 04 HUSHUROOKiM | | REL''1'P NaMi AECII'IEN I AFFILIATION O'AEICLYiJ ~ P ~ Region 2i Atlanta; Uf fice of the Director SUBJEC'l': Interim deficienc y rept re heating~ventilation L air I condi.tfoning for t:lass IE 'motor control ctrsiinitiat ly r epoi ted on 60101 7'esign change has been developed.Final rept wi l be issu ed by 811231. |
| ~06 AD/RC I/IE 17 0/DIP HUM FACI5 EDO 8 8'I'AFF i 9 HYU/GEO BH 22 LIC QUAL BR 12 NHI".POR'2 P O'I'EV 1$HE'lLt 01 b DE V 2'I COPIES t.TTR ENCL"i 1 1 i i 1 i i i i 1 i 1 i 1 RE'CIPIENT It)CODE/NAME YOUNbBLOOt)iB 05 HIILSONrJEllRY 07 ASLBP/J~HARD''DIRiDIV OP LIC EQUIP QUAL UR1'1Itt E 09 MPA 20 OELD 21 QA BR i4 RUTHERFORDpN | | 1 DISTRIBUTION CODE: 8 019S COPIES RECEIVED:LTR ENCL SIZE: |
| ~IE COPIES L'rTA ENCL 1 1 i i 1 1 i 1 i 1 i i 1 i i EXTERNAL: AGRS t48LC 16 08 16 16'1 1 LPDR 03 1 1 TOTAL NUMBER OF COPIES RE(QUIRED:
| | TITLE: Construction Defici ency Repor t (10CFA50.55E) |
| LTTt<39 ENGL 39 4 1, 4, d I 1 FGRM 21 Pile: SH N/2-18 Item 52 Carolina Power 8 Ught Company Ratefgh, N.C.27602 Pebruary 16, 1981 Mr.'ames P.O'Reilly United States Nuclear Regulatory Commission Region II 101 Marietta Street, Northwest Atlanta,, Georgia 30303 SHEARON HARRIS NUCLEAR POWER PLANT UNITS 1, 2, 3 AND 4 DOCKET NOS.50-400, 50-401, 50-402 AND 50-403 NONSAPETY HVAC POR CLASS 1E MOTOR CONTROL CENTERS-INTERIM REPORT | | NOTES: |
| | RECIPIENT COPIES RE'CIPIENT COPIES ACl ION 10 CODY7NAME A/D LICE NSNG 04 HUSHUROOKiM ~ 06 "i |
| | t.TTR ENCL It) CODE/NAME YOUNbBLOOt)iB 05 HIILSONrJEllRY 07 L'rTA ENCL 1 |
| | i 1 |
| | i INTERNAL: AD/RC I/IE 17 1 1 ASLBP/J ~ HARD'' 1 1 0/DIP HUM FACI5 i DIRiDIV OP LIC i |
| | '2 1 |
| | EDO 8 8'I'AFF i9 i EQUIP QUAL UR1'1 i HYU/GEO BH 22 1 Itt E 09 1 i LIC QUAL BR 12 i MPA 20 i NHI". POR i i OELD 21 O'I'EV i P |
| | HE b |
| | 'lLt DE V 1$ |
| | 01 2'I i |
| | i 1 |
| | 1 1 |
| | QA BR RUTHERFORDpN ~ |
| | i4 IE 1 |
| | i i EXTERNAL: AGRS 16 16 16 LPDR 03 1 1 t48LC 08 '1 1 TOTAL NUMBER OF COPIES RE(QUIRED: LTTt< 39 ENGL 39 |
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| ==Dear Mr.O'Reilly:== | | 4 1, |
| ~'er our November 24, 1980, interim report on the subject deficiency, we had indicated that all corrective action would be completed by Pebruary 15, 1981, at which time the final 10CPR50.55(e) report would be submitted. | | 4, d |
| The intent of this letter is to inform you that due to the extensive nature of the scope of the subject problem, all corrective action has not yet been completed. | | I1 |
| Attached is an interim report which provides an update of the problem investi-gation/resolution. | | |
| It is now anticipated that all corrective action excluding equipment qualification or relocation to environmentally controlled areas will be completed by May 1, 1981, and that the equipment qualification or relocation to environmentally controlled areas will be completed by December 31, 1981, at which time the final 10CPR50.55(e) report will be submitted. | | FGRM 21 Carolina Power 8 Ught Company Ratefgh, N.C. 27602 Pile: SH N/2-18 Item 52 Pebruary 16, 1981 Mr.'ames P. O'Reilly United States Nuclear Regulatory Commission Region II 101 Marietta Street, Northwest Atlanta,, Georgia 30303 SHEARON HARRIS NUCLEAR POWER PLANT UNITS 1, 2, 3 AND 4 DOCKET NOS. 50-400, 50-401, 50-402 AND 50-403 NONSAPETY HVAC POR CLASS 1E MOTOR CONTROL CENTERS - INTERIM REPORT |
| Thank you for your consideration in this matter." NJC/mt (3807)Attachment cc: Mr.G.Maxwell W/A Mr.V.Stello (2)W/A~Oi'ipl3ll Elgr78d l3y N.J.Chiangi gP"Cr.~<n~~M9!1~8 CD CD'l CD I N.J.Chiangi-Manager Engineering 6 Construction Quality Assurance go//,/ | | |
| SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.1 NONSAFETY HVAC FOR CLASS 1E MOTOR CONTROL CENTERS Interim Report No.2 February 13, 1981 Reportable Under 10CFR50.55(e) | | ==Dear Mr. O'Reilly:== |
| Prepared by: Carolina Power&Light Company l l | | |
| | ~ |
| | our November 24, 1980, interim report on the subject deficiency, we had |
| | 'er indicated that all corrective action would be completed by Pebruary 15, 1981, at which time the final 10CPR50.55(e) report would be submitted. The intent of this letter is to inform you that due to the extensive nature of the scope of the subject problem, all corrective action has not yet been completed. |
| | Attached is an interim report which provides an update of the problem investi-gation/resolution. It is now anticipated that all corrective action excluding equipment qualification or relocation to environmentally controlled areas will be completed by May 1, 1981, and that the equipment qualification or relocation to environmentally controlled areas will be completed by December 31, 1981, at which time the final 10CPR50.55(e) report will be submitted. |
| | Thank you for your consideration in this matter. |
| | NJC/mt (3807) |
| | Attachment Oi'ipl3ll Elgr78d l3y cc: Mr. G. Maxwell W/A N. J. Chiangi Mr. V. Stello (2) W/A~ |
| | N. J. Chiangi - Manager gP 8 |
| | CD Engineering 6 Construction Quality Assurance CD'l CD "Cr.~ |
| | <n~ |
| | I go/ / |
| | ~ M9 |
| | / |
| | 1 |
| | ~ |
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| | SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 NONSAFETY HVAC FOR CLASS 1E MOTOR CONTROL CENTERS Interim Report No. 2 February 13, 1981 Reportable Under 10CFR50.55(e) |
| | Prepared by: Carolina Power & Light Company |
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| ==SUBJECT:== | | ==SUBJECT:== |
| 10CFR50.55(e) | | |
| Reportable Item Shearon Harris Nuclear Power Plant (SHNPP)Nonsafety HVAC for Class lE Motor Control Centers ITEMS: SUPPLIED MCC's lA-35SA, MCC 1B-35SB, 2A-35SA&2B-35SB BY: Design-Ebasco Services, Inc.NATURE OF DEFICIENCY: | | 10CFR50.55(e) Reportable Item Shearon Harris Nuclear Power Plant (SHNPP) |
| Class lE Motor Control Centers are not cooled by safety-related HVAC, as stated in the SHNPP FSAR.DATE PROBLEM WAS CONFIRMED TO EXIST: October 17, 1980 PROBLEM REPORTED: October 17, 1980-CP&L (L.I.Loflin, K.V.Hate&R.K.Cothren)informed the NRC Region II office (Mr.J.-K.Rausch)by telephone that t'.he problem was"potentially reportable" under 10CFR50.55(e). | | Nonsafety HVAC for Class lE Motor Control Centers ITEMS: |
| October 27, 1980-CP&L (N.J.Chiangi)informed the NRC Region II office (Mr.J;K.Rausch)by telephone that the problem was reportable under 10CFR50.55(e). | | MCC's lA-35SA, MCC 1B-35SB, 2A-35SA & 2B-35SB SUPPLIED BY: Design Ebasco Services, Inc. |
| SCOPE OF PROBLEM: Equipment located in the common area of the Reactor Auxiliary Building (RAB)between Units 1&2 at Elevations 261 and 236 are not supplied with safety-related HVAC and may not be qualified for the room temperatures which will bereached in the event that electrical power and hence, ventilation, is lost~REASONS (S)PROBLEM WAS REPORTABLE: | | NATURE OF DEFICIENCY: |
| Class 1E equipment in the Unit One&Common Reactor Auxiliary Building is cooled by safety-related HVAC equipment in order to reduce the temperature extremes to which this equipment would be subjected in the event of a LOCA.The Motor Control Centers at the 261 elevation of the Units 1&2 Common RAB are 0 Class 1E and are qualified to a room temperature of 104 F.(40 C).The normal HVAC for this elevation, as well as the 236'ommon RAB elevation, has a Non-1E power supply.In theevent of a loss of HVAC, the temperature in the area of the Motor Control Centers could exceed 104 F (piping containing 120 F fluid passes through this area).Since the Motor 0 Control Centers are not qualified.for temperatures above 104 F, the continued functioning of the MCCs cannot be certified. | | Class lE Motor Control Centers are not cooled by safety-related HVAC, as stated in the SHNPP FSAR. |
| This condition deviates from the SHNPP FSAR Section 3.11.4.1 which states that"Plant areas containing ESF and RPS equipment and their~su ort~s stems are temperature oontrolled to provide a controlled environment even during the most severe DBA condition." Since the design of the Unit 1 and Common RAB has been approved and released for construction, this condition constitutes a significant deficiency which does not conform to the criteria and bases stated in the Safety Analysis Report.CORRECTIVE ACTION: A design change has been developed and issued for incorporation which adds safety-related HVAC units at the 286 elevation of the Unit 1 and Common Reactor Auxiliary Building.These HVAC units will provide safety-related ventilation to MCCs 1A-35SA, 1B-35SB, 2A-35SA, and 2B-35SB.In addition, the architect-engineer (Ebasco)prepared detailed temperature maps.of the plant in order to verify that no such condition existed'elsewhere in the plant.A detailed review of each equipment item against the temperature expected to exist in the area of the plant where the item is logated has~been completed, resulting in the identification of some ESF-related (Class lE)instrumentation which is presently not located in'nvironmentally-controlled areas.This equipment will be qualified to the maximum post-accident tempeiatures, determined for each location or will be relocated to environmentally-controlled areas.~v'e I}} | | DATE PROBLEM WAS CONFIRMED TO EXIST: October 17, 1980 PROBLEM REPORTED: |
| | October 17, 1980 CP&L (L. I. Loflin, K. V. Hate & R. K. |
| | Cothren) informed the NRC Region II office (Mr. J. -K. Rausch) by telephone that t'.he problem was "potentially reportable" under 10CFR50.55(e). |
| | October 27, 1980 - CP&L (N. J. Chiangi) informed the NRC Region II office (Mr. J; K. Rausch) by telephone that the problem was reportable under 10CFR50.55(e). |
| | SCOPE OF PROBLEM: |
| | Equipment located in the common area of the Reactor Auxiliary Building (RAB) between Units 1 & 2 at Elevations 261 and 236 are not supplied with safety-related HVAC and may not be qualified for the room temperatures which will bereached in the event that electrical power and hence, ventilation, is lost ~ |
| | REASONS (S) PROBLEM WAS REPORTABLE: |
| | Class 1E equipment in the Unit One & Common Reactor Auxiliary Building is cooled by safety-related HVAC equipment in order to reduce the temperature extremes to which this equipment would be subjected in the event of a LOCA. The Motor Control Centers at the 261 elevation of the Units 1 & 2 Common RAB 0 are Class 1E and are qualified to a room temperature of 104 F . |
| | (40 C). The normal HVAC for this elevation, as well as the 236'ommon RAB elevation, has a Non-1E power supply. In the event of a loss of HVAC, the temperature in the area of the Motor 0 |
| | Control Centers could exceed 104 F (piping containing 120 F fluid passes through this area). Since the Motor Control Centers are not qualified .for temperatures above 104 F, the continued functioning of the MCCs cannot be certified. |
| | |
| | This condition deviates from the SHNPP FSAR Section 3.11.4.1 which states that "Plant areas containing ESF and RPS equipment and their ~su ort ~s stems are temperature oontrolled to provide a controlled environment even during the most severe DBA condition." |
| | Since the design of the Unit 1 and Common RAB has been approved and released for construction, this condition constitutes a significant deficiency which does not conform to the criteria and bases stated in the Safety Analysis Report. |
| | CORRECTIVE ACTION: |
| | A design change has been developed and issued for incorporation which adds safety-related HVAC units at the 286 elevation of the Unit 1 and Common Reactor Auxiliary Building. These HVAC units will provide safety-related ventilation to MCCs 1A-35SA, 1B-35SB, 2A-35SA, and 2B-35SB. |
| | In addition, the architect-engineer (Ebasco) prepared detailed temperature maps. of the plant in order to verify that no such condition existed 'elsewhere in the plant. A detailed review of each equipment item against the temperature expected to exist in the area of the plant where the item is logated has ~ |
| | been completed, resulting in the identification of some ESF-related (Class lE) instrumentation which is presently not located in'nvironmentally-controlled areas. This equipment will be qualified to the maximum post-accident tempeiatures, determined for each location or will be relocated to environmentally-controlled areas. |
| | ~ v' e I}} |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML18016A9011999-04-12012 April 1999
Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected
ML20140G4481997-05-0101 May 1997
Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages
ML20115D2001996-07-0909 July 1996
Part 21 Rept Re Mfg Defect of Enterprise DSR-4 & DSRV-4 Edgs,Originally Mfg by Calcon Corp.Amot Control Corp Purchased Calcon Product Line & Maintains Design & Production.Valves Returned to Cooper Energy Svcs on 960131
ML20117G4641996-05-14014 May 1996
Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs
ML18022A9701995-09-29029 September 1995
Part 21 Rept Re Failure of Charging SI Pump Miniflow Check Valves.Caused by Cocking of Piston Towards Valve Outlet Port Due to Large Hydraulic Surge.Valves That Experienced Failures Replaced
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
ML20058K3841993-12-0909 December 1993
Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head
ML20127H2301993-01-15015 January 1993
Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites
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
ML20126B0421992-12-17017 December 1992
Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed
ML20125C7161992-12-0707 December 1992
Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl
ML20127P5861992-11-23023 November 1992
Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl
ML17289A6971992-06-26026 June 1992
Amend 1 to Part 21 Rept 158 Re gear-wear Induced Failures in engine-driven Jacket Water Pump in DSRV-16-4 Standby DG Sys. Initially Reported on 911029.Grand Gulf Station Observed Wear Characteristics in as Little as 500 Operating Hours
ML18010A5701992-03-23023 March 1992
Initial Part 21 Rept Re Defect in Anchor Darling Supplied Main Feedwater Preheater Bypass Isolation Valves.On 920112, All non-Q Components Replaced W/Suitable Components & Tested Satisfactorily.Next Rept Will Be Submitted by 920214
ML20094L1271992-03-13013 March 1992
Amend 1 to Part 21 Rept 159 Re Potential Defect in Power Cylinder Liner.Initially Reported on 920115.Caused by Liner/ Block Fit & Localized Matl Microstructure.All Drawings & Specs Revised to Address Matl Design Requirements
ML18010A5071992-01-16016 January 1992
Initial Part 21 Rept Re Deficiency in Actuator to Main Feedwater Preheater Bypass Isolation Valves.On 920107,2 H Surveillance Interval Was Commenced to Verify Actuator Components Were Functioning Properly
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
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
ML18005B0321989-08-25025 August 1989
Potential Part 21 Rept Re ITE-Siemens molded-case Circuit Breakers Not Holding Required Load,Resulting in Inoperability.Motor in-rush Current Tests Will Be Performed on S-4 Motor to Determine If Correct Breaker Utilized
ML18005B0081989-07-26026 July 1989
Part 21 Rept Re Potential Failure of Main Steam PORVs Supplied by Control Components,Inc.Initially Reported on 890719.Cause of Failure Speculated to Be Dirt or Corrosion Particles Preventing Ring from Sealing.Porv Trim Modified
ML20247P7991989-04-0404 April 1989
Part 21 Rept Re Atmospheric Dump Valves.Cause of Failure Speculative But Result of Piston Ring That Failed to Seal. Resolution to Problem Requires Increasing Pilot Valve Capacity & Reworking of Plug to Enlarge Pilot Flow Area
ML20207P0451988-10-0505 October 1988
Part 21 Rept 146 Re Defect in Left Intercooler Inlet Adapter on Standby Diesel Engine Generator.Recommends Utils Inspect Left Intake Manifold Drain as Part of Operating Plan.Addl Info Expected by 881015
ML18005A6551988-09-29029 September 1988
Part 21 Rept Re Deficiency in Control & Power Circuits for Dc motor-operated Valves Due to Lack of Surge Protection. Initially Reported on 880518.Interim Measures Established to Ensure Proper Operation of Valves Until Surge Installed
ML18005A4401988-05-18018 May 1988
Part 21 Rept Re Dc Motor Failure on Auxiliary Feedwater Limitorque Operated Valves.Plant Mod Will Be Implemented to Install Surge Protection for Shunt Coil Circuitry of Subject Dc Motors
ML20154J4101988-05-12012 May 1988
Addendum 1 to Supplemental Part 21 Rept 145 Re Potential Problem w/F-573-156 Pressure Sensor/Lube Oil Trip.Initially Reported on 880429.Addl 1-1/8-inch Diameter W/Deep Counterbone in Pressure Head Added to Activate Valve
ML20153B6191988-04-29029 April 1988
Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generators Supplied to Utils.Recommends Return of Subj Components in Onsite Warehouse Storage & Suggests Surveillance of Devices Already Installed
ML18004B9461987-09-22022 September 1987
Part 21 Rept Re Failure to Postulate Unavailability of Vital Dc Bus in Conjunction W/Auxiliary Feedwater (AFW) Isolation Design.Afw Isolation Logic Modified W/Westinghouse Involvement.Operation Will Resume Upon Completion of Mods
ML18004B8701987-07-0101 July 1987
Part 21 & Deficiency Rept Re LOCA Occurring During Modes 3 & 4.Initially Reported on 860815.Completion Date for Item Cannot Be Determined Due to Continued Westinghouse Owners Group Effort
ML20234C7351987-06-23023 June 1987
Supplemental Part 21 Rept Re Silicone Foam Seal Anomolies at Wolf Creek Generating Station
ML20216E4721987-05-28028 May 1987
Part 21 Rept 140 Re Potential Defect in Air Pressure Regulators Mfg by Bellofram.Dripwell Gasket May Fail Due to Mismachining of Gasket Seating Surface Causing Loss of Control Air & Starting Air Pressure
ML20207R7031987-03-11011 March 1987
Part 21 Rept Re Potential Defect in Static Exciter Voltage Regulator (Sevr) Reset Design.Recommends Mod to Control Circuits to Energize Sevr Upon Receipt of Emergency Start Signal.Mods Will Be Completed by 870331
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
ML20210E7901987-02-0404 February 1987
Part 21 Rept Re Incorrect Operation of Hfa Auxiliary Relays, Per 861114 GE Svc Advice Ltr 188.1.Relays Installed in Standby Diesel Generator Sys Af Plant.Svc Ltr Forwarded to Util
ML20215F0041986-12-12012 December 1986
Final Deficiency Rept,Item 233 Re Quantity of Electrical Separation Interactions That Remained Undetected After Installation Insp.Initially Reported on 860822.Remaining Separation Interactions Identified,Reworked & Reinspected
ML20213F8101986-11-10010 November 1986
Interim Deficiency Rept,Item 233,re Electrical Separation. Initially Reported on 860822.Addl Time Necessary to Submit Final Rept.Final Rept Expected on 861210
ML20215K5301986-10-14014 October 1986
Deficiency Rept,Item 234 Re Structural Steel Welds Not Meeting Project Acceptance Criteria.Initially Reported on 860921.Item Not Reportable Per 10CFR50.55(e) & 10CFR21, Confirming 861014 Telcon
ML20215K5651986-10-14014 October 1986
Deficiency Rept,Item 231 Re Use of Hylomar Thread Sealant in Stainless Steel Applications.Initially Reported on 860814. Item Not Reportable Per 10CFR50.55(e) Confirming 861014 Telcon
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
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
ML20214K4131986-10-0303 October 1986
Interim Deficiency Rept,Item 233 Re Electrical Separation. Initially Reported on 860822.Final Rept Will Be Issued by 861110
ML20214K8581986-09-29029 September 1986
Interim Deficiency Rept,Item 231 Re Hylomar Thread Sealant Exceeding Acceptable Chloride Limits.Initially Reported on 860814.Addl Time Required to Complete Testing.Next Rept Delayed Until 861010
ML20206U6661986-09-19019 September 1986
Interim Deficiency Rept,Item 233 Re 12 Electrical Separation Interactions on Two Conduits in Fuel Handling Bldg.Initially Reported on 860822.Separation Interactions Reworked & Reinsp.Next Rept Will Be Submitted by 861003
ML20210D6301986-09-11011 September 1986
Part 21 & Deficiency Rept,Item 232 Re LOCA Occurring During Modes 3 & 4.Initially Reported on 860815.Util Will Pursue Resolution W/Westinghouse Owners Group.Next Rept Will Be Submitted by 870701
ML20210D5301986-09-11011 September 1986
Deficiency Rept,Item 231 Re Hylomar Thread Sealant Used in Stainless Steel Applications Found to Exceed Acceptable Chloride Limits.Initially Reported on 860814.Testing Underway.Item Reportability Will Be Submitted by 860926
ML20212P3171986-08-14014 August 1986
Final Part 21 & Deficiency Rept,Item 230 Re Foreign Objects in Steam Generators B & C.Initially Reported in 860814 Telcon.Evaluation Completed.Condition Nonreportable Per 10CFR50.55(e) & 10CFR21
ML20205F6141986-08-13013 August 1986
Part 21 Rept Re Connecting Rod Bolts for Dsrv Engines.Listed Procedures Recommended for Next Connecting Rod Insp, Including Replacement of Bolts Due to Cracked Threads & Large Grooves & Galls in Threads
ML20212B5831986-08-0101 August 1986
Part 21 Rept Re Technical Noncompliance W/Matl Certification of Krueger (Div of Phillips Industries) Aluminum Extrusions Used at Nuclear Plants.Vendor to Perform Tensile Tests from Each Heat Number If use-as-is Condition Unacceptable
ML20203D0221986-07-14014 July 1986
Part 21 Rept Re Air Monitoring Sys Probes Exhibiting Blue Tip Rather than Normal White Tip & Insensitive to Chlorine. Caused by Improper Handling/Storage.Advisory Bulletin Encl. Item Not Reportable Per Part 21
ML20212D0081986-07-0909 July 1986
Final Deficiency Rept,Item 229,re Emergency Svc Water Pump a Trip.Initially Reported on 860609.Caused by Failure of Penetration Seal at Intake Structure.Seal Design Modified. Pump Disassembled & Inspected
1999-04-12
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML18017A9181999-10-0808 October 1999
LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr
ML18017A9151999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Shearon Harris Npp. with 991012 Ltr
ML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML18017A8671999-09-10010 September 1999
LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr
ML18017A8621999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Harris Nuclear Plant.With 990908 Ltr
ML18016B0481999-08-0404 August 1999
LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised
ML18017A8361999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Shearon Harris Nuclear Power Plant.With 990811 Ltr
ML18016B0151999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Shearon Harris Npp. with 990713 Ltr
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML18016A9801999-06-0404 June 1999
LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr
ML18016A9851999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990614 Ltr
ML18017A8981999-05-12012 May 1999
Technical Rept Entitled, Harris Nuclear Plant-Bacteria Detection in Water from C&D Spent Fuel Pool Cooling Lines.
ML18016A9581999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990513 Ltr
ML18016A9011999-04-12012 April 1999
Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected
ML18016A9111999-04-12012 April 1999
LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr
ML18016A8971999-04-0808 April 1999
LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr
ML18016A8941999-04-0505 April 1999
Revised Pages 20-25 to App 4A of non-proprietary Version of Rev 3 to HI-971760
ML18016A9101999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Shearon Harris Nuclear Power Plant.With 990413 Ltr
ML18016A8661999-03-31031 March 1999
Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept.
ML18017A8931999-02-28028 February 1999
Risks & Alternative Options Associated with Spent Fuel Storage at Shearon Harris Nuclear Power Plant.
ML18016A8551999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Shearon Harris Npp. with 990312 Ltr
ML18016A8261999-02-22022 February 1999
LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr
ML18016A8531999-02-18018 February 1999
Non-proprietary Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFP 'C' & 'D'.
ML18016A8111999-02-12012 February 1999
LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr
ML18016A7971999-02-0505 February 1999
LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr
ML18022B0631999-02-0404 February 1999
Rev 0 to Nuclear NDE Manual. with 28 Oversize Uncodable Drawings of Alternative Plan Scope & 4 Oversize Codable Drawings
ML20202J1161999-02-0101 February 1999
SER Accepting Relief Requests Associated with Second 10-year Interval Inservice Testing Program
ML18016A8041999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Shearon Harris Nuclear Power Plant.With 990211 Ltr
ML18016A7941999-01-29029 January 1999
LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor
ML18016A7801998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Shearon Harris Npp. with 990113 Ltr
ML18016A7671998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Shnpp,Unit 1.With 981215 Ltr
ML18016A9731998-11-28028 November 1998
Changes,Tests & Experiments, for Harris Nuclear Plant.Rept Provides Brief Description of Changes to Facility & Summary & of SE for Each Item That Was Implemented Under 10CFR50.59 Between 970608-981128.With 990527 Ltr
ML18016A8351998-11-28028 November 1998
ISI Summary 8th Refueling Outage for Shearon Harris Power Plant,Unit 1.
ML18016A7411998-11-25025 November 1998
Rev 1 to Shnpp Cycle 9 Colr.
ML18016A7211998-11-17017 November 1998
LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr
ML18016A7071998-11-0303 November 1998
Rev 0 to Harris Unit 1 Cycle 9 Colr.
ML18016A7201998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Shearon Harris Nuclear Power Plant.With 981113 Ltr
ML20154F8701998-10-0606 October 1998
Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves
ML18016A6201998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Harris Nuclear Power Plant.With 981012 Ltr
ML18016A5971998-09-21021 September 1998
Rev 1 to Harris Unit 1 Cycle 8 Colr.
ML18016A5881998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Shnpp,Unit 1.With 980914 Ltr
ML18016A5071998-07-31031 July 1998
Monthly Operating Rept for Jul 1998 for Shearon Harris Nuclear Plant.W/980811 Ltr
ML18016A9431998-07-0707 July 1998
Rev 1 to QAP Manual.
ML18016A4841998-07-0707 July 1998
LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys
ML18016A9371998-06-30030 June 1998
Technical Rept on Matl Identification of Spent Fuel Piping Welds at Hnp.
ML18016A4861998-06-30030 June 1998
Monthly Operating Rept for June 1998 for SHNPP.W/980715 Ltr
ML18016A4701998-06-30030 June 1998
LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11
ML18016A4491998-06-0808 June 1998
LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr
ML18016A4521998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Shearon Harris Nuclear Power Plant.W/980612 Ltr
ML18016A7711998-05-26026 May 1998
Non-proprietary Rev 2 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris Spent Fuel Pools 'C' & 'D'.
1999-09-30
[Table view] |
Text
vte ~ 'I REGULATORY INFORMATION DISTRroutrON SYSTEM (RrDs)
ACCESSION NOR: 6102250061 DOC, DATE: S1/02/16 NOTARLZED: NO DOCKET ¹ I-AGIL:bo 400 Shearon Harris Nuclear Power Plant~ Unit l~ Carolina 05600400
'-'o-HI bhearon Harris Nuclear Power Plant~ Unit 2~ Carolina oSootI4oi So" 4tl2 Shea'ron Harris Nuclear Power Ptantq Unit 3~ Carolina OSOOO4O2 50 H3 8hearon Harris Nuclear power I lant< Unit ~1i Caro'lina osooo4o3 au'r H, IIAMt. auTHux at.FT'LraTioN GIiXaAt,"I'",N,J. Carolina Vower tc Light Co ~
REL1'P NaMi AECII'IEN I AFFILIATION O'AEICLYiJ ~ P ~ Region 2i Atlanta; Uf fice of the Director SUBJEC'l': Interim deficienc y rept re heating~ventilation L air I condi.tfoning for t:lass IE 'motor control ctrsiinitiat ly r epoi ted on 60101 7'esign change has been developed.Final rept wi l be issu ed by 811231.
1 DISTRIBUTION CODE: 8 019S COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Construction Defici ency Repor t (10CFA50.55E)
NOTES:
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FGRM 21 Carolina Power 8 Ught Company Ratefgh, N.C. 27602 Pile: SH N/2-18 Item 52 Pebruary 16, 1981 Mr.'ames P. O'Reilly United States Nuclear Regulatory Commission Region II 101 Marietta Street, Northwest Atlanta,, Georgia 30303 SHEARON HARRIS NUCLEAR POWER PLANT UNITS 1, 2, 3 AND 4 DOCKET NOS. 50-400, 50-401, 50-402 AND 50-403 NONSAPETY HVAC POR CLASS 1E MOTOR CONTROL CENTERS - INTERIM REPORT
Dear Mr. O'Reilly:
~
our November 24, 1980, interim report on the subject deficiency, we had
'er indicated that all corrective action would be completed by Pebruary 15, 1981, at which time the final 10CPR50.55(e) report would be submitted. The intent of this letter is to inform you that due to the extensive nature of the scope of the subject problem, all corrective action has not yet been completed.
Attached is an interim report which provides an update of the problem investi-gation/resolution. It is now anticipated that all corrective action excluding equipment qualification or relocation to environmentally controlled areas will be completed by May 1, 1981, and that the equipment qualification or relocation to environmentally controlled areas will be completed by December 31, 1981, at which time the final 10CPR50.55(e) report will be submitted.
Thank you for your consideration in this matter.
NJC/mt (3807)
Attachment Oi'ipl3ll Elgr78d l3y cc: Mr. G. Maxwell W/A N. J. Chiangi Mr. V. Stello (2) W/A~
N. J. Chiangi - Manager gP 8
CD Engineering 6 Construction Quality Assurance CD'l CD "Cr.~
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SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 NONSAFETY HVAC FOR CLASS 1E MOTOR CONTROL CENTERS Interim Report No. 2 February 13, 1981 Reportable Under 10CFR50.55(e)
Prepared by: Carolina Power & Light Company
l l
SUBJECT:
10CFR50.55(e) Reportable Item Shearon Harris Nuclear Power Plant (SHNPP)
Nonsafety HVAC for Class lE Motor Control Centers ITEMS:
MCC's lA-35SA, MCC 1B-35SB, 2A-35SA & 2B-35SB SUPPLIED BY: Design Ebasco Services, Inc.
NATURE OF DEFICIENCY:
Class lE Motor Control Centers are not cooled by safety-related HVAC, as stated in the SHNPP FSAR.
DATE PROBLEM WAS CONFIRMED TO EXIST: October 17, 1980 PROBLEM REPORTED:
October 17, 1980 CP&L (L. I. Loflin, K. V. Hate & R. K.
Cothren) informed the NRC Region II office (Mr. J. -K. Rausch) by telephone that t'.he problem was "potentially reportable" under 10CFR50.55(e).
October 27, 1980 - CP&L (N. J. Chiangi) informed the NRC Region II office (Mr. J; K. Rausch) by telephone that the problem was reportable under 10CFR50.55(e).
SCOPE OF PROBLEM:
Equipment located in the common area of the Reactor Auxiliary Building (RAB) between Units 1 & 2 at Elevations 261 and 236 are not supplied with safety-related HVAC and may not be qualified for the room temperatures which will bereached in the event that electrical power and hence, ventilation, is lost ~
REASONS (S) PROBLEM WAS REPORTABLE:
Class 1E equipment in the Unit One & Common Reactor Auxiliary Building is cooled by safety-related HVAC equipment in order to reduce the temperature extremes to which this equipment would be subjected in the event of a LOCA. The Motor Control Centers at the 261 elevation of the Units 1 & 2 Common RAB 0 are Class 1E and are qualified to a room temperature of 104 F .
(40 C). The normal HVAC for this elevation, as well as the 236'ommon RAB elevation, has a Non-1E power supply. In the event of a loss of HVAC, the temperature in the area of the Motor 0
Control Centers could exceed 104 F (piping containing 120 F fluid passes through this area). Since the Motor Control Centers are not qualified .for temperatures above 104 F, the continued functioning of the MCCs cannot be certified.
This condition deviates from the SHNPP FSAR Section 3.11.4.1 which states that "Plant areas containing ESF and RPS equipment and their ~su ort ~s stems are temperature oontrolled to provide a controlled environment even during the most severe DBA condition."
Since the design of the Unit 1 and Common RAB has been approved and released for construction, this condition constitutes a significant deficiency which does not conform to the criteria and bases stated in the Safety Analysis Report.
CORRECTIVE ACTION:
A design change has been developed and issued for incorporation which adds safety-related HVAC units at the 286 elevation of the Unit 1 and Common Reactor Auxiliary Building. These HVAC units will provide safety-related ventilation to MCCs 1A-35SA, 1B-35SB, 2A-35SA, and 2B-35SB.
In addition, the architect-engineer (Ebasco) prepared detailed temperature maps. of the plant in order to verify that no such condition existed 'elsewhere in the plant. A detailed review of each equipment item against the temperature expected to exist in the area of the plant where the item is logated has ~
been completed, resulting in the identification of some ESF-related (Class lE) instrumentation which is presently not located in'nvironmentally-controlled areas. This equipment will be qualified to the maximum post-accident tempeiatures, determined for each location or will be relocated to environmentally-controlled areas.
~ v' e I
