Notice of Violation from Insp on 980302-0409.Violation noted:post-mod Test Procedure Did Not Incorporate Requirements Contained in Design DocumentsML20236L538 |
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Millstone ![Dominion icon.png](/w/images/b/b0/Dominion_icon.png) |
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06/11/1998 |
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NRC (Affiliation Not Assigned) |
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ML20236L533 |
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References |
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50-336-98-202, EA-98-271, NUDOCS 9807130063 |
Download: ML20236L538 (5) |
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Category:NOTICE OF VIOLATION OF A REGULATION
MONTHYEARML20207F1521999-05-25025 May 1999 Notice of Violation from Investigation Rept 1-94-021 on 940506-960329.Violation Noted:Between 740831-910407,licensee Made Changes to Facility Described in Safety Analysis Rept for Refueling Core Offloads Without Performing Evaluation ML20205M7201999-04-0606 April 1999 Notice of Violation from NRC OI Case 1-96-002 & Conclusions of Millstone Independent Review Team.Violation Noted. E Debarba,Deliberately Discriminated Against Supervisor in Performance Engineering Group at Millstone Station ML20205M7351999-04-0606 April 1999 Notice of Violation from Investigation in Case Numbers 1-96-002 & 1-97-007.Violation Noted:Licensee Discriminated Against Supervisor in Performance Engineering Group at Plant Due to Involvement in Protected Activities ML20207M1131999-03-0909 March 1999 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $88,000.Violation Noted:Employment of Two Contractor Employees Terminated in Aug 1997,in Part Because Individuals Raised Concerns Re MOV Program Manual ML20199C6381999-01-0707 January 1999 Notice of Violation from Insp on 981006-1123.Violation Noted:On or Before 981120,conduit 9-15,in Fire Area A-24,not Sealed & Tested in Accordance with Astme E-119,fire Endurance Test ML20195H6901998-11-18018 November 1998 Notice of Violation from Insp on 980818-1005.Violation Noted:Engineering Evaluations Not Performed When RCS Heatup Rate Limit Exceeded on 951217 & When RCS Cooldown Rate Limit Exceeded on Three occasions,940424,0728 & 951215 ML20155B1521998-10-23023 October 1998 Notice of Violation from Insp on 980810-0903.Violation Noted:Design Basis,As Described in FSAR Chapter 14,Accident Analyses Had Not Been Correctly Translated Into Plant Procedures & Acceptance Criteria ML20154D1151998-09-11011 September 1998 Notice of Violation from Insp on 980413-24-0511-15,27-29, 0609-11 & 23-25.Violation Noted:Program Implemented TS 6.8.4.a,failed to Include Provisions to Reduce Leakage from RSS Heat Exchangers to SW Sys ML20237B0741998-08-12012 August 1998 Notice of Violation from Insp on 980428-0629.Violation Noted:Licensee Failed to Direct Test Personnel to Close & Lock RHR Outboard Drain Valve ML20237D3041998-08-12012 August 1998 Notice of Violation from Insp on 980413-0508.Violations Noted:Two Examples Identified Where Licensee Not Performing Leakage Testing of safety-related Valves in Sys That Could Contain Highly Radioactive Fluids During Accident ML20249C6931998-06-19019 June 1998 Notice of Violations from Combined Insp on 980301-0427. Violations Noted:Prior to 980424,instrument Min Accuracy of Wind Speed Channels Were Not Measured as Required by Table 3.3-8 of Unit 2 TS 3/4.3.3.4 ML20249B0421998-06-12012 June 1998 Notice of Violations from Insp on 980413-24.Violations Noted:Only 1 RCS Loop Operable W/Plant in Mode 4 on 980407 ML20236L5381998-06-11011 June 1998 Notice of Violation from Insp on 980302-0409.Violation noted:post-mod Test Procedure Did Not Incorporate Requirements Contained in Design Documents ML20249B0811998-06-11011 June 1998 Notice of Violation from Insp on 980209-20.Violation Noted: Between 1992 & 1993,appropriate C/A Not Taken to Prevent Recurring Air Binding Problems for Boric Acid Transfer Pumps ML20249B2171998-05-26026 May 1998 Revised Notice of Violation from Insp on 980101-0228. Violations Noted:As of 980210,21 nonsafety-related SOVs in High Pressure & Low Pressure Safety Injection Sys & Four nonsafety-related SOV in RCS Not Included in EQ Program ML20248E5951998-05-26026 May 1998 Notice of Violation from Insp on 980101-0228.Violation Noted:On 980225,NRC Determined That Written Equipment Control Procedures Were Not Established to Process Revs to Sys Valve Lineups ML20248A7781998-05-22022 May 1998 Notice of Violation from Insp on 980302-31 & 980412. Violation Noted:Structural Steel Support Members Did Not Meet 3-h Fire Barrier Criterion,In That on & Before 980304, Columns D2-54,D2-53 & A4-52 Had Gaps in Fire Rated Coating ML20248F3061998-05-0808 May 1998 Notice of Violation from Insp on 980223-0306.Violation Noted:Listed Examples Were Identified Where Requirements of 10CFR50 App B,Criterion Xvi, Corrective Action, Were Not Met ML20247D8561998-05-0606 May 1998 Notice of Violation from Insp on 980223-26.Violation Noted: Between 1988 & 980226,licensee Failed to Maintain Adequate PASS Program That Ensured Capability to Obtain & Analyze Samples Under Post Accident Conditions ML20217M9091998-04-0808 April 1998 Notice of Violation from Insp on 980209-27.Violation Noted:As of 980227,measures Were Not Established to Assure That Design Basis of safety-related MOVs Was Correctly Translated Into Specifications,Drawings & Instructions ML20216F9841998-04-0303 April 1998 Notice of Violation from Insp on 980105-0206.Violation Noted:Certain Measures for Verifying Adequacy of Plant Design Inadequate ML20216G0921998-04-0101 April 1998 Notice of Violation from Insp on 971027-980128.Violation Noted:Licensee Failed to Perform & Include in Written Records,Safety Evaluations for Approx 250 Changes to FSAR Made Between mid-1996 & mid-1997 ML20196J5911998-03-0909 March 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:As of Sept 1997, Condition Adverse to Quality Existed at Facility Which Had Not Been Promptly Identified & Corrected ML20203H0981998-02-25025 February 1998 Notice of Violation from Insp on 971201-31.Violation Noted: on 971222,equipment Located in safety-related Area,Unit 2 Control Room,Not Restrained in Accordance W/Attachment 3 in Procedure Oa 8 ML20198F0501997-12-30030 December 1997 Notice of Violation from Insp on 970825-29.Violation Noted: as of 970829,adequate Dose Assessment Methods Were Not in Use.Page 23 of Incoming Submittal Was Not Included ML20202J7221997-12-10010 December 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $2,100,000.Violation Noted:Licensee Did Not Translate Design Features Into Work Instructions & Did Not Verify Adequacy of Designs ML20202J7891997-12-0505 December 1997 Notice of Violation from Insp on 970818-29 & 0908-19. Violations Noted:During NRC Insp That Ended 970919,listed Instances Were Identified Where Requirements of TS 6.8.1a Were Not Met ML20202A7491997-11-21021 November 1997 Notice of Violation Form Insp on 970722-1001.Violation Noted:On 971215 Activities Affecting Quality Were Not Prescribed by Documented Instructions,Procedures or Drawings ML20216C7471997-08-29029 August 1997 Notice of Violation from Insp on 970529-0721.Violation Noted:On Several Occasions in May & June 1997,overcoat Window Was Exceeded by 45 Minutes to 2 Hours & 41 Minutes ML20210S8701997-08-29029 August 1997 Notice of Violation from Insp on 970520-0721.Violations Noted:Overcoat Window Was Exceeded by 45 Minutes to 2 H & 45 Minutes ML20141E3101997-06-24024 June 1997 Notice of Violation from Insp on 970311-0519.Violation Noted:Since Commencement of Operations at Unit 1,applicable Regulatory Requirements & Design Basis Not Correctly Translated Into Drawings & Procedures ML20140F1121997-06-11011 June 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Licensee Identified Seven Incidents Where Items Containing Safeguards Info Had Not Been Under Control of an Authorized Individual ML20140C5551997-04-11011 April 1997 Notice of Violations from Insp on 970101-0310.Violations Noted:Since Commencement of Operations,Unit 1 Failed to Determine Concentration of Nuclides in Gaseous Effluents Released from Radwaste Storage Bldg Through Exhaust Fan ML20137F3921997-03-24024 March 1997 Notice of Violation from Insp on 961222-970208.Violations Noted:When Repeatedly Depressurizing Unit 2 RHR Sys from 970123-30,operators Did Not Properly Implement Procedures as Required ML20135E6111997-02-24024 February 1997 Notice of Violation from Insp on 961026-1231.Violation Noted:Individual Gained Access to PA W/O Having Authorized or Hand Geometry Confirmed ML20134G3911997-02-0303 February 1997 Notice of Violation from Insp on 961112-22.Violation Noted: Licensee Failed to Establish & Implement Procedure to Verify That Design Basis Relative to Ventilation Air Supply Involving Radwaste Was Maintained as Described by UFSAR IR 07100128/20120021997-01-0606 January 1997 Notice of Violation from Insp on 771128-1202.Violation Noted:Licensee Did Not Test Addl 10 Snubbers for Each Found Inoperable Per Procedure 2733B,hydraulic Snubber Functional Test,Rev 0,770601 ML20135C9951996-12-0303 December 1996 Notice of Violation from Insp on 960827-1025.Violation Noted:All Valves Classified as Containment Isolation Boundaries Did Not Receive Monthly Verification to Insure They Are in Closed Position ML20128M1941996-10-0909 October 1996 Notice of Violation from Insp on 960506-10.Violation Noted; Licensee Failed to Control SGI as Required on 951105 ML20149K7331994-07-13013 July 1994 Notice of Violation & Proposed Imposition of Civil Penalties in Amount of $220,000.Violation Noted:Licensee Failed to Take Action to Address Condition Until 891117,when FWCI Was Inoperable IA-97-223, Notice of Violation & Proposed Imposition of Civil Penalties in Amount of $220,000.Violation Noted:Licensee Failed to Take Action to Address Condition Until 891117,when FWCI Was Inoperable1994-07-13013 July 1994 Notice of Violation & Proposed Imposition of Civil Penalties in Amount of $220,000.Violation Noted:Licensee Failed to Take Action to Address Condition Until 891117,when FWCI Was Inoperable ML20059G0631993-12-23023 December 1993 Notice of Violation from Insp on Stated Date.Violation Noted:Written Licensee Procedures Were Not Established or Implemented Re Testing for Drugs ML20058D3371993-11-22022 November 1993 Notice of Violation from Insp on 930818-0928.Violation Noted:Seismic Brace in Count Rate Module of Radiation Monitor RM-8156 Not Reinstalled During Instrument Calibr ML20058Q0601993-10-15015 October 1993 Notice of Violation from Insp on 920512-14.Violation Noted. Licensee Determined That Records Required to Be Maintained by Commission Regulations or License Conditions Not Complete & Accurate in All Matl Respects ML20057E2971993-09-20020 September 1993 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Noncompliance Noted:During 1991-1992 LORT Program,Facility Failed to Ensure Personnel Licensed Per 10CFR55 Had Completed Requalification Program ML20056H2491993-09-0101 September 1993 Notice of Violation from Insp on 930719-23.Violation Noted: Measures to Assure Conditions Adverse to Quality Not Taken to Promptly Correct Deficiency of Failure to Follow Procedures as Evidenced by Listed Actions ML20056G3681993-08-26026 August 1993 Notice of Violation from Insp on 930614-25.Violation Noted: Dynamic Tests for Seventeen safety-related MOVs Performed in Accordance W/Test Procedures That Did Not Incorporate Requirements & Acceptance Limit for Determining Operability ML20128D6071993-02-0101 February 1993 Notice of Violation from Insp on 921028-1222.Violation Noted:Bypass Jumpers Not Initiated for Scaffolding Installed for Greater than 90 Days as Required by Procedure ACP 2.19 ML20127D8451993-01-11011 January 1993 Notice of Violation from Insp on 920706-24.Violation Noted: on 920706,implementation Plan of Plant Design Change Record 2-123-91 Was Not Translated Correctly Into Work Order M2-92-06984 ML20126K0671992-12-28028 December 1992 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $62,500.Violation Noted:Between 920711 & 0824, Two Independent Trains of Abfs Not Operable 1999-05-25
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000245/19990081999-09-14014 September 1999 Insp Repts 50-245/99-08,50-336/99-08 & 50-423/99-08 on 990615-0809.Four Violations Noted & Being Treated as Ncvs. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000423/19990071999-08-27027 August 1999 Insp Rept 50-423/99-07 on 990614-0715.Violations Noted & Being Treated as Ncvs.Major Areas Inspected:Review of C/A Program Using IP 40500, Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems IR 05000336/19990061999-07-19019 July 1999 Insp Repts 50-336/99-06 & 50-423/99-06 on 990420-0614.Ten Violations Occurred & Being Treated as non-cited Violations. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000336/19982191999-06-10010 June 1999 Insp Rept 50-336/98-219 on 981214-18,990126-29,0208-19 & 0301-05.Noncited Violations Identified.Major Areas Inspected:Exam of Licensee Corrective Action Implementation IR 05000245/19990051999-06-0404 June 1999 Errata to Insp Repts 50-245/99-05,50-336/99-05 & 50-423/99-05,consisting of Figure 1 ML20207G1211999-06-0303 June 1999 Insp Repts 50-245/99-05,50-336/99-05 & 50-423/99-05 on 990302-0419.No Violations Noted.Major Areas Inspected: Operations,Maint,Engineering & Plant Support ML20207F1521999-05-25025 May 1999 Notice of Violation from Investigation Rept 1-94-021 on 940506-960329.Violation Noted:Between 740831-910407,licensee Made Changes to Facility Described in Safety Analysis Rept for Refueling Core Offloads Without Performing Evaluation ML20196K2621999-05-24024 May 1999 EN-99-020:on 980525,notice of Violation & Exercise of Enforcement Discretion Will Be Issued to Licensee.Action Based on Severity Level III Problem Consisting of Four Individual Violations Involving Refueling Outage PNO-I-99-022, on 990509,Millstone Unit 2 Established Reactor Criticality.Nrc Staff Providing Augmented Insp Coverage of Restart Activities,Including round-the-clock Observations of Licensee Activities During Key Operational Evolutions1999-05-11011 May 1999 PNO-I-99-022:on 990509,Millstone Unit 2 Established Reactor Criticality.Nrc Staff Providing Augmented Insp Coverage of Restart Activities,Including round-the-clock Observations of Licensee Activities During Key Operational Evolutions IR 05000336/19990031999-05-10010 May 1999 Insp Rept 50-336/99-03 on 990322-26.No Violations Noted. Major Areas Inspected:Review of Actions Taken by Util to Resolve Significant Issues List Item 21,fire Protection ML20206F4601999-04-30030 April 1999 Insp Rept 50-336/99-04 on 990315-31.Violation Noted.Major Areas Inspected:Monitored Licensee Activities During Plant Transition Between Operational Modes,Both During Normal & off-normal Working Hours PNO-I-99-016, on 990406,operators Initiated Plant Cooldown from Normal Operating Pressure & Temp in Mode 3,hot Standby. Cooldown Was Necessary to Minimize Further Degradation of Bonnet Pressure Seal for Valve 2-SI-652 & to Repair Valve1999-04-0707 April 1999 PNO-I-99-016:on 990406,operators Initiated Plant Cooldown from Normal Operating Pressure & Temp in Mode 3,hot Standby. Cooldown Was Necessary to Minimize Further Degradation of Bonnet Pressure Seal for Valve 2-SI-652 & to Repair Valve ML20205M7201999-04-0606 April 1999 Notice of Violation from NRC OI Case 1-96-002 & Conclusions of Millstone Independent Review Team.Violation Noted. E Debarba,Deliberately Discriminated Against Supervisor in Performance Engineering Group at Millstone Station ML20205M7351999-04-0606 April 1999 Notice of Violation from Investigation in Case Numbers 1-96-002 & 1-97-007.Violation Noted:Licensee Discriminated Against Supervisor in Performance Engineering Group at Plant Due to Involvement in Protected Activities IR 05000245/19990021999-04-0202 April 1999 Insp Repts 50-245/99-02,50-336/99-02 & 50-423/99-02 on 990112-0301.Violations Noted.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000336/19990011999-03-29029 March 1999 Insp Rept 50-336/99-01 on 990117-0217.Violations Noted.Major Areas Inspected:Licensee C/A Program Implementation Using Guidance of NRC IP 40500, Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems ML20205J0941999-03-12012 March 1999 Rept of Review of Millstone Units 1,2 & 3:Allegations of Discrimination in NRC Ofc of Investigations Cases 1-96-002, 1-96-007,1-97-007 & Associated Lessons Learned ML20207M1131999-03-0909 March 1999 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $88,000.Violation Noted:Employment of Two Contractor Employees Terminated in Aug 1997,in Part Because Individuals Raised Concerns Re MOV Program Manual ML20205G6161999-03-0909 March 1999 EN-99-010:on 990309,notice of Proposed Imposition of Civil Penalty in Amount of $88,000 Issued to Licensee.Action Based Upon Severity Level II Problem Involving Discrimination Against Two Contractor Employees at Millstone MOV Dept IR 05000245/19980061999-03-0101 March 1999 Insp Repts 50-245/98-06,50-336/98-06 & 50-423/98-06 on 981123-990111.No Violations Noted.Major Areas Inspected: Operations,Maintenance,Engineering & Plant Support PNO-I-99-006, on 990128,operators Inadvertently Reduced Spent Fuel Pool Water Level by Two Inches When Purification of Spent Fuel Pool Water Initiated.Operators Held Shift Briefing to Discuss Realigning Purification Sys1999-01-29029 January 1999 PNO-I-99-006:on 990128,operators Inadvertently Reduced Spent Fuel Pool Water Level by Two Inches When Purification of Spent Fuel Pool Water Initiated.Operators Held Shift Briefing to Discuss Realigning Purification Sys IR 05000245/19982171999-01-22022 January 1999 Evaluation Repts 50-245/98-217,50-336/98-217 & 50-423/98-217 Conducted on 981026-30.Areas Evaluated:Whether NNECO Has Improved Sufficiently & Has Demonstrated Sustained Performance in Maintaining safety-conscious Work Environ PNO-I-99-004, on 990115,carbon Dioxide Was Inadvertently Discharged Into Unit 3 Cable Spreading Room,Containing Electrical Wiring.Ambulance Reported to Site as Precautionary Measure.Licensee Assembled Event Review1999-01-20020 January 1999 PNO-I-99-004:on 990115,carbon Dioxide Was Inadvertently Discharged Into Unit 3 Cable Spreading Room,Containing Electrical Wiring.Ambulance Reported to Site as Precautionary Measure.Licensee Assembled Event Review IR 05000336/19980051999-01-0707 January 1999 Insp Repts 50-336/98-05 & 50-423/98-05 on 981006-1123. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20199C6381999-01-0707 January 1999 Notice of Violation from Insp on 981006-1123.Violation Noted:On or Before 981120,conduit 9-15,in Fire Area A-24,not Sealed & Tested in Accordance with Astme E-119,fire Endurance Test PNO-I-99-001, on 981231,Millstone Unit 2 Began Reloading Fuel Into Reactor After Extended Shutdown.Millstone Unit 3 Went Critical on 981230,after Forced Outage Due to Inadvertent MSIV Closure During Surveillance Testing at Power1999-01-0404 January 1999 PNO-I-99-001:on 981231,Millstone Unit 2 Began Reloading Fuel Into Reactor After Extended Shutdown.Millstone Unit 3 Went Critical on 981230,after Forced Outage Due to Inadvertent MSIV Closure During Surveillance Testing at Power PNO-I-98-062, on 981211,Millstone Unit 3 Tripped from 100% Reactor Power During MSIV Partial Stroke Testing.Solenoid Valve Integral to MSIV Failed to Reopen When Licensed Operator Released Test Switch1998-12-15015 December 1998 PNO-I-98-062:on 981211,Millstone Unit 3 Tripped from 100% Reactor Power During MSIV Partial Stroke Testing.Solenoid Valve Integral to MSIV Failed to Reopen When Licensed Operator Released Test Switch ML20195H6901998-11-18018 November 1998 Notice of Violation from Insp on 980818-1005.Violation Noted:Engineering Evaluations Not Performed When RCS Heatup Rate Limit Exceeded on 951217 & When RCS Cooldown Rate Limit Exceeded on Three occasions,940424,0728 & 951215 IR 05000245/19982161998-11-18018 November 1998 Insp Repts 50-245/98-216,50-336/98-216 & 50-423/98-216 on 980818-1005.Violations Noted.Major Areas Inspected: Operations,Maintenance,Engineering & Plant Support IR 05000336/19982031998-11-0505 November 1998 Insp Rept 50-336/98-203 on 980824-0904.No Violations Noted. Major Areas Inspected:Effectiveness of Configuration Mgt Plan ML20155B1521998-10-23023 October 1998 Notice of Violation from Insp on 980810-0903.Violation Noted:Design Basis,As Described in FSAR Chapter 14,Accident Analyses Had Not Been Correctly Translated Into Plant Procedures & Acceptance Criteria IR 05000336/19982131998-10-23023 October 1998 Insp Rept 50-336/98-213 on 980810-0903.Violations Noted. Major Areas Inspected:Certain Aspects of Accident Mitigation Sys IR 05000245/19982151998-10-14014 October 1998 Evaluation Repts 50-245/98-215,50-336/98-215 & 50-423/98-215 on 980824-28.Major Areas Evaluated:Whether Licensee Has Improved Sufficiently & Has Demonstrated Sustained Performance in Maintaining safety-conscious Work Environ IR 05000336/19980041998-10-0101 October 1998 Insp Rept 50-336/98-04 on 980914-18.No Violations Noted. Major Areas Inspected:Mov Program Associated with GL 89-10 IR 05000245/19982121998-09-25025 September 1998 Insp Repts 50-245/98-212,50-336/98-212 & 50-423/98-212 on 980630-0817.No Violations Noted.Major Areas Inspected: Operations,Maintenance,Engineering & Plant Support IR 05000423/19982111998-09-11011 September 1998 Insp Rept 50-423/98-211 on 980413-24,0511-15,27-29,0609-11 & 23-25.Violation Noted.Major Areas Inspected:Evaluation of Licensee C/As & Other ICAVP Process Activities ML20154D1151998-09-11011 September 1998 Notice of Violation from Insp on 980413-24-0511-15,27-29, 0609-11 & 23-25.Violation Noted:Program Implemented TS 6.8.4.a,failed to Include Provisions to Reduce Leakage from RSS Heat Exchangers to SW Sys IR 05000424/19980061998-09-10010 September 1998 Insp Repts 50-424/98-06 & 50-425/98-06 on 980628-0815.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support PNO-I-98-039, 980812,Millstone Unit 3 Was Shutdown to Repair Small Leak on Afws Discharge Noted.Current Leakage Does Not Exceed Regulatory Requirements & Shutdown Not Required by Tech Specs.Licensee Issued Press Release on 9808111998-08-12012 August 1998 PNO-I-98-039:980812,Millstone Unit 3 Was Shutdown to Repair Small Leak on Afws Discharge Noted.Current Leakage Does Not Exceed Regulatory Requirements & Shutdown Not Required by Tech Specs.Licensee Issued Press Release on 980811 ML20237D3041998-08-12012 August 1998 Notice of Violation from Insp on 980413-0508.Violations Noted:Two Examples Identified Where Licensee Not Performing Leakage Testing of safety-related Valves in Sys That Could Contain Highly Radioactive Fluids During Accident IR 05000245/19982081998-08-12012 August 1998 Insp Repts 50-245/98-208,50-336/98-208 & 50-423/98-208 on 980428-0629.Violations Noted.Major Areas Inspected: Operations,Maint,Engineering & Plant Support ML20237B0741998-08-12012 August 1998 Notice of Violation from Insp on 980428-0629.Violation Noted:Licensee Failed to Direct Test Personnel to Close & Lock RHR Outboard Drain Valve IR 05000336/19982011998-08-12012 August 1998 Insp Rept 50-336/98-201 on 980413-0508.Violations Noted. Major Areas Inspected:Licensee Ability to Identify & Resolve Deficiencies Focusing,But Not Limited To,Period of CMP Implementation & ICAVP at Parsons Power Group,Inc PNO-I-98-026, on 980701,Millstone Unit 3 Criticality Update Made.Nrc Staff Continues to Provide Augmented Insp of Unit 3 Restart Activities,Including round-the-clock Coverage of Key Operational.Licensee Plans No Press Release1998-07-0101 July 1998 PNO-I-98-026:on 980701,Millstone Unit 3 Criticality Update Made.Nrc Staff Continues to Provide Augmented Insp of Unit 3 Restart Activities,Including round-the-clock Coverage of Key Operational.Licensee Plans No Press Release PNO-I-98-025, on 980630,unit 3 Established Reactor Criticality,However Reactor Was Shut Down When Control Room Operator Noticed Spiking Intermediate Range Monitor.Licensee Troubleshooting1998-06-30030 June 1998 PNO-I-98-025:on 980630,unit 3 Established Reactor Criticality,However Reactor Was Shut Down When Control Room Operator Noticed Spiking Intermediate Range Monitor.Licensee Troubleshooting IR 05000245/19982071998-06-19019 June 1998 Insp Repts 50-245/98-207,50-336/98-207 & 50-423/98-207 on 980301-0427.Violations Noted.Major Areas Inspected:Maint, Operations,Engineering & Plant Support ML20249C6931998-06-19019 June 1998 Notice of Violations from Combined Insp on 980301-0427. Violations Noted:Prior to 980424,instrument Min Accuracy of Wind Speed Channels Were Not Measured as Required by Table 3.3-8 of Unit 2 TS 3/4.3.3.4 IR 05000423/19970831998-06-12012 June 1998 Insp Rept 50-423/97-83 on 980413-24.Violations Noted. Major Areas Inspected:Readiness of Plant Hardware,Staff & Mgt Programs to Support Safe Restart & Continued Operation of Plant Unit 3 ML20249B0421998-06-12012 June 1998 Notice of Violations from Insp on 980413-24.Violations Noted:Only 1 RCS Loop Operable W/Plant in Mode 4 on 980407 IR 05000423/19970821998-06-11011 June 1998 Insp Rept 50-423/97-82 on 980209-20.Violations Noted.Major Areas Inspected:Corrective Actions Processes 1999-09-14
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NOTICE OF VIOLATION Northeast Nuclear Energy Company Docket No. 50-336 Millstone Nuclear Power Station License No. DPR-65 Unit 2 EA 98-271 During an NRC inspection conducted on March 2 through April 9,1998, violations of NRC requirements were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violations are listed below:
A. 10 CFR Part 50, Appendix B, Criterion XI, " Test Control," requires that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate j the requirements and acceptance limits contained in applicable design documents. i Contrary to the above:
- 1. A post-modification test procedure did not incorporate the requirements contained in design documents. Test procedure SP 21206A, " Instrument Air Accumulator Check Valve Test,"
Rev. 3, dated November 5,1997, tested the backup air accumulators for valves 2-RB-13.1A/B l
but did not incorporate the requirements and acceptance limits contained in calculation 97-ENG-01823-M2, " Verification of Accumulator Size for Valves 2-RB-13.1A and 13.18," Rev. O, dated August 13,1997, and modification PDCR 2-064-95, " Air Accumulator for 2-RB-13.1 A & B," Rev.
1, dated August 20,1997. The test did not verify that the air accumulated leak-tightness was sufficient to hold the valve in the closed position for 90 minutes with a starting pressure of 90 pounds per square inch gauge (psig) and a final pressure of 60 psig.
- 2. _ All testing required to demonstrate that the reactor building closed cooling water I system (RBCCW) will perform satisfactorily in service was not identified. A periodic test to verify j adequate flow to each component serviced by RBCCW had not been established. Procedure SPROC 97-2-19, "RBCCW Building Closed Cooling Water System Flow Balance," Rev. 2, dated March 2,1998, only required a one-time flow balance be performed.
- 3. A written test procedure did not incorporate acceptance limits. Preventive maintenance l
procedure MF 2701J-96, " Service Water Cooled Heat Exchangers Subject to GL 89-13,"
Rev. 3, dated April 21,1997, provided instructions for periodic maintenance and inspection of i the service water cooled heat exchangers. The procedure did not provide acceptance limits for the as-found cleanliness of the RBCCW heat exchangers.
This is a Severity Level IV violation (Supplement 1).
B. 10 CFR 50, Appendix B, Criterion XVI, " Corrective Action" requ' ires that conditions t
adverse to quality be promptly identified and corrected.
Procedure RP-4, " Corrective Action Program," Rev. 6, Change 1, dated April 1,1998, requires that conditions adverse to quality be identified and promptly corrected.
9907130063 980611 PDR ADOCK 05000336 G PDR I.
O Contrary to the above:
- 1. A condition adverse to quality had not been adequately corrected. Condition report M2-97-0489, *RBCCW System Design Pressure Can Be Exceeded at Low Flows," dated March 27,1997, stated that RBCCW system pressure could exceed design pressure during pump swapping. - Operating Procedure OP 2330A, "RBCCW System," Rev.19, dated March 9,1998, was changed to alleviate the pressure spiking. The procedure was not tested
- for effectiveness at low flows and was inconsistent with Final Safety Analysis Report (FSAR)
Section 9.4.4.2 requirements and with surveillance test requirements.
- 2. A condition adverse to quality had not been identified nor corrected. Technical Specification (TS) 3.8.1.1 requires two sources of offsite power be supplied to the switchyard, whereas 10 CFR Part 50, " General Design Criterion 17.," Appendix A, requires that two sources be supplied to the safety buses. LER 95-035, dated October 5,1995, reported that the licensee procedures had not required them to enter a TS limiting condition for operation with less than two power paths from the switchyard to the onsite safety busses. The licensee procedures were changed at that time but the need for a TS change was not identified nor corrected.
This is a Severity Level IV violation (Supplement 1).
C. 10 CFR Part 50, Appendix B, Criterion Vlli, " identification and Control of Materials, Parts, and Components," requires that measures be established for the identification and control of materials, parts, and components, and that the identification be maintained.
Contrary to the above, the identification and control of a valve was not maintained.: In several databases, letdown heat exchanger RBCCW outlet temperature control valve, 2-RB-402, had two' different identification numbers. The valve was identified as 2-RB-402 and 2-CH-223.
Valve 2-RB-402 was identified as safety-related, whereas 2-CH-223 was not.
This is a Severity Level IV violation (Supplement I).
D.. 10 CFR Part 50, Appendix B, Criterion V, " Instructions, Procedures, and Drawings,"
states in part that activities affecting quality be prescribed by documented instructions and be accomplished in accordance with those instructions.
Contrary to the above:
- 1. An instance was noted where the two RBCCW pump trains (Facilities 1 and 2) did not meet the electrical separation criteria specified in FSAR Section 8.7 and the licensee specification SP-M2-EE-0016, " Electrical Separation Specification- Millstone Unit 2," Rev.1, dated September 9,1997. The separation criteria required 18 inches of free air space horizontally between redundant cable trays. For cables Z12AA20, Z2LAA20, Z24LA60, and Z16HT35 on Standards drawing 25203-34031, Rev. 7, there was approximately 9 inches of free air space horizontally.
I e
- 2. Two pressure indicators, PI-6324 and PI-6325, and their respective tubing, were incorrectly classified as nonsafety-related and nonseismic. FSAR section 5.2.8.2.1 and specification SP-ME-668, Rev. 4, dated May 23,1997, required these instruments and tubing to be seismic and safety-related.
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- 3. An example of originally-installed small bore piping which was not installed in accordance with the applicable piping isometric drawing was identified. A 3/4-inch by a %-inch reducing elbow was installed instead of a 3/4-inch elbow and a 3/4-inch by a %-inch reducer as specified by DCN No. DM2-00-0640-97, "HPSI 41 A Seal / Bearing Coolers C . ' ling Water Supply and Retum Pipe Replacement," dated August 12,1997. Additionally, a pipin; support was installed differently than required. The support, Hanger No. 6, was shown on l drawing 25203-22200 SH.491315E, Rev. 00, dated March 3,1982. The drawing showed a frame type restraint but the installed restraint was a cantilever arrangement. Additionally, the drawing showed a 4-inch and a 2-inch angle members, but the installation was made of a 6-inch square tube and a 6-inch wide flange members. Likewise, anchor base plate locations, sizes, and concrete fastener sizes were different than shown on the drawing.
- 4. There were two examples of recent modification work where piping supports were not installed in accordance with their drawings. The supports,25203-22200-611087 and 25203-22200-611100, were shown on DCN Number DM2-00-0919-97 *HPSI Pump P-41A Seal / Bearing Cooling Water Supply and Return Piping Supports," Rev. O, dated October 10,1998. The actualinstallations differed from the drawing in that the assemblies were rotated 90 degrees from that shown.
- 5. An FSAR change request had not been initiated as required by Procedure RAC 03,
" Changes and Revisions to Final Safety Analysis Reports," Rev.0, dated December 18,1997.
The flow for the shutdown coolers described in FSAR Table 9.3-1 were not revised to reflect the reduction of the design basis minimum design flow from 4820 gallons per minute (gpm)
(2.41 x 105 pounds per hour) to 3500 gpm (approximately 1.75 x 105 pounds per hour). A request to change FSAR Table 9.3-1 had not been made.
This is a Severity Level IV violation (Supplement 1).
E. 10 CFR Part 50, Appendix B, Criterion lil, " Design Control," requires in part that measures be established to assure that the design basis is correctly translated into specifications, drawings, procedures, and instructions.
Contrary to the above, for RBCCW radiation monitor, RM 6038, the design basis alarm setpoint calculation assumptions for flow were not translated into operating procedures. OPS Form 2669A-2, " Unit 2 Aux Building Rounds," Rev. 25, did not specify the flows assumed in the setpoint calculation. Similarly, the " Millstone Two Radiation Monitor Manual," dated Jurse 27,1997, provided an inadequate setpoint calculation bases for the RM-6038 alarm setpoint in that it did not assume flow dilution. Additionally, Operations Form 2654K, "Rediation Monitor Setpoint Verification," Rev. 3, did not provide guidance for dealing with postulated conditions of high background radiation levels which could result in a nonconservative setpoint.
This is a Severity Level IV violation (Supplement 1).
F. 10 CFR Part 50, Appendix B, Criterion V, " Instructions, Procedures, And Drawings,"
requires that activities affecting quality be prescribed by procedures of a type appropriate to the circumstances.
Contrary to the above, the annunciator response procedures for the RBCCW system contained
. numerous inconsistencies, had widely differing levels of detail, and exhibited poor integration with existing operating and abnormal operating procedure instruction (AOP) 2564, " Loss Of RBCCW," Rev. 3. The problems identified are detailed in the inspection report.
l This is a Severity Level IV violation (Supplement 1).
G. 10 CFR Part 50, Appendix B, Criterion VI, " Document Control," requires that measures be established to control issuance of documents, such as instructions, procedures and drawings, including changes thereto, which prescribe activities affecting quality. These measures shall assure that documents, including changes, are distributed to and used at the prescribed location.
~ Contrary to the above, the full-size Unit 2 piping and instrumentation diagrams maintained in the Controlled Document Library on the third floor of building 475 had not been updated since May 1997.
This is a Severity Level IV violation (Supplement 1).
H. 10 CFR 50.59, " Changes, Tests, and Experiments," permits changes to be made in the facility as described in the FSAR, and requires that records of the changes be maintained, and that the records include a written safety evaluation which provides the bases for the -
determination that the change did not involve an unreviewed safety question. A proposed change involves an unreviewed safety question if the probability of occurrence or the consequences of a malfunction of equipment evaluated in the safety analysis report may be increased.
NRC " Safety Evaluation of the Millstone Point Nuclear Power Station," dated May 10,1974, Section 7.10, approved 12 inches as the electrical cable separation criteria in panels.
FSAR Section 8.7.3.1 described the same separation criteria.
Contrary to the above, a safety evaluation erroneously concluded that a reduction in the plant-wide electrical separation criteria was not an unreviewed safety question. Design Change Record (DCR) M2-96-068, " Electrical Separation Specification-Millstone Unit 2," Rev 0, dated
. September 8,1997, revised SP-M2-EE-0016, Rev. O, dated September 9,1996. The change reduced the electrical cable separation criteria from 12 to 6 inches in cabinets. The DCR included a Safety Evaluation No. S2-EV-97-0018, Rev.1, dated September 8,1997, which concluded that there was not an unreviewed safety question. The reduction in separation could increase the probability of a previously evaluated malfunction of equipment.
This is a Severity Level IV violation (Supplement 1).
O Pursuant to the provisions of 10 CFR 2.201, Nor+heast Nuclear Energy Company is hereby required to submit a written statement or explanation within 30 days of receipt of the letter transmitting this Notice of Violation to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, D.C. 20555, with a copy to the Director, Special Projects Office, Office of Nuclear Reactor Regulation, and a copy to the NRC Resident inspector at the Millstone Nuclear Power Station, Unit 2. This reply should be clearly marked as a " Reply to a Notice of Violation," and should include for each violation (1) the reason for the violation, or, if i contested, the basis for disputing the violation, (2) the corrective steps that have been taken j and the results achieved, (3) the corrective steps that will be taken to avoid further violations,-
and (4) the date when full compliance will be achieved. Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response, if an adequate reply is not received within the required time specified in this Notice, an order or a Demand for information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.
Dated at Rockville, Maryland this 11th day of June,1998 l
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