05000245/LER-1997-009, Forwards LER 97-009-00,documenting Condition That Was Discovered at Millstone Nuclear Power Station,Unit 1 on 970212.Util Commitments Made within Ltr,Listed

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Forwards LER 97-009-00,documenting Condition That Was Discovered at Millstone Nuclear Power Station,Unit 1 on 970212.Util Commitments Made within Ltr,Listed
Person / Time
ML20136H253
Site:	Millstone
Issue date:	03/14/1997
From:	Hinnenkamp P NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20136H257	List: 05000245/LER-1997-009, Forwards LER 97-009-00,documenting Condition That Was Discovered at Millstone Nuclear Power Station,Unit 1 on 970212.Util Commitments Made within Ltr,Listed 05000245/LER-1997-009-01, :on 970212,reactor low-low Level ECCS & Primary Containment Initiation Setpoints Were Not Conservative. Caused by Deficient Setpoint Methodology.Calculations Will Be Revised & TS Change Initiated
References
B16277, NUDOCS 9703190098
Download: ML20136H253 (1)
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LER-1997-009, Forwards LER 97-009-00,documenting Condition That Was Discovered at Millstone Nuclear Power Station,Unit 1 on 970212.Util Commitments Made within Ltr,Listed

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(ii)
2451997009R00 - NRC Website
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text

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Northeast hone officesa Hope Ferry Rd., Waterford, Cr i

Utilities System P.o. w 128 Waterford, CF 06385-0128 (860) 447-179I l

March 14,1997 l

Docket No. 50-245 B16277 Re: 10CFR50.73(a)(2)(ii)

[

t U.S. Nuclear Regulatory Commission l

Document Control Desk Washington, DC 20555 This letter forwards Licensee Event Report (LER)- 97-009-00, documenting an event that j

occurred at Millstone Nuclear Power Station, Unit No. I on February 12, 1997. This LER is j

submitted pursuant to 10CFR50.73(a)(2)(ii).

The following are Northeast Nuclear Energy Company's (NNECO's) commitments made with.in I

this letter. All other statements made within this letter are for information only.

1 B16277-1 NNECO commits to review all calculations that have been completed as part of the Setpoint Verification Program to determine if other non-conservative setpoints exist l

by May 1,1997.

i i

B16277-2 NNECO will submit a TS change request or perform a new analysis to ensure that Emergency Core Cooling System and Primary Containment. Isolation System i

actuation will occur consistent with the plant's design basis including consideration ofinstrument uncertainties by April 15,1997.

Very truly yours, i

NORTHEAST NUCLEAR ENERGY COMPANY l

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CChn 'm J

19005r,

- PTTTinnenkamT U 1-Director, Unit Operations -

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Attachment: LER 97-009-00 i

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cc:. Dr. W. D. Travers, Director, Special Projects l

- H. J. Miller, Region I Administrator.

l S. Dembek, NRC Project Manager, Millstone Unit No. l 1

T. A. Eastick, Senior Resident Inspector, Millstone Unit No.1 t

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Licensee Event Report

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		Reporting criterion
05000245/LER-1997-001-02, :on 970110,liquid Radwaste Effluent Radiation Monitor Declared Inoperable Due to Leaking Automatic Isolation Valves.Valves Repaired	on 970110,liquid Radwaste Effluent Radiation Monitor Declared Inoperable Due to Leaking Automatic Isolation Valves.Valves Repaired	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000245/LER-1997-001, Forwards LER 97-001-00,documenting Event That Occurred at Millstone Nuclear Power Station,Unit 1 on 970110.Util Commitments Made within Ltr,Listed	Forwards LER 97-001-00,documenting Event That Occurred at Millstone Nuclear Power Station,Unit 1 on 970110.Util Commitments Made within Ltr,Listed	10 CFR 50.73(a)(2)(i)
05000423/LER-1997-001, Submits Commitments Re LER 97-001-00,documenting Condition Determined at Plant on 970104	Submits Commitments Re LER 97-001-00,documenting Condition Determined at Plant on 970104	10 CFR 50.73(a)(2)(i)
05000423/LER-1997-001-01, :on 970104,discovered Lack of Verbatim Compliance W/Ts SRs for 125 Volt Batteries & Battery Chargers.Caused by Misconception That Performing Surveillances Was Acceptable.Revised Procedures	on 970104,discovered Lack of Verbatim Compliance W/Ts SRs for 125 Volt Batteries & Battery Chargers.Caused by Misconception That Performing Surveillances Was Acceptable.Revised Procedures	10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii)
05000423/LER-1997-002, :on 970108,torquing of Battery Connections Not Performed as Part of Connection Tightness Checks Occurred. Caused by Lack of Effective Verification & Validation of Maint Procedure.Procedure Revised	on 970108,torquing of Battery Connections Not Performed as Part of Connection Tightness Checks Occurred. Caused by Lack of Effective Verification & Validation of Maint Procedure.Procedure Revised	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)
05000245/LER-1997-002, Forwards LER 97-002-00 Which Documents an Event That Occurred at Mnps,Unit 1 on 970114,per 10CFR50.73(a)(2)(iv). Commitments Made,Listed	Forwards LER 97-002-00 Which Documents an Event That Occurred at Mnps,Unit 1 on 970114,per 10CFR50.73(a)(2)(iv). Commitments Made,Listed	10 CFR 50.73(a)(2)(iv), System Actuation
05000245/LER-1997-002-02, :on 970114,inadvertent Shutdown Cooling Isolation Occurred During Sys Removal from Svc for Maint. Caused by Inadequacy in Preparation of Clearance Required to Perform Maint.Individuals Involved Have Been Counseled	on 970114,inadvertent Shutdown Cooling Isolation Occurred During Sys Removal from Svc for Maint. Caused by Inadequacy in Preparation of Clearance Required to Perform Maint.Individuals Involved Have Been Counseled	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000336/LER-1997-002, Forwards LER 97-002-00 Which Documents an Event That Occurred on 970108,per 10CFR50.73(a)(2)(ii).Commitments Made within Ltr,Listed	Forwards LER 97-002-00 Which Documents an Event That Occurred on 970108,per 10CFR50.73(a)(2)(ii).Commitments Made within Ltr,Listed	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000336/LER-1997-002-01, :on 970108,damper 2-HV-210 Could Not Be Manually Operated within Ten Minutes as Required in Accident Analysis.Caused by Inadequate Evaluation of Mechanical Binding.Damper Was Placed in Fail Open Position	on 970108,damper 2-HV-210 Could Not Be Manually Operated within Ten Minutes as Required in Accident Analysis.Caused by Inadequate Evaluation of Mechanical Binding.Damper Was Placed in Fail Open Position	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)
05000423/LER-1997-003, Forwards LER 97-003-00 Which Documents Condition That Was Determined at Mnps,Unit 3 on 970113,per 10CFR50.73(a)(2)(ii) (B).List of Commitments,Encl	Forwards LER 97-003-00 Which Documents Condition That Was Determined at Mnps,Unit 3 on 970113,per 10CFR50.73(a)(2)(ii) (B).List of Commitments,Encl	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000423/LER-1997-003-01, :on 970113,potential for Recirculation Spray Sys Piping Failure Occurred Due to RSS Pump Stopping & Restarting During Accident Conditions.Performed Evaluation of RSS Water Column Separation Issue	on 970113,potential for Recirculation Spray Sys Piping Failure Occurred Due to RSS Pump Stopping & Restarting During Accident Conditions.Performed Evaluation of RSS Water Column Separation Issue	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000336/LER-1997-003-01, Corrected Page One to LER 97-003-01:on 961216,discovered Discrepancy in Plant Procedure Utilized to Perform Periodic Insp of Fire Protection Sys Smoke Detectors.Caused by Failure to Properly Incorporate Ts.Ts Partially Revis	Corrected Page One to LER 97-003-01:on 961216,discovered Discrepancy in Plant Procedure Utilized to Perform Periodic Insp of Fire Protection Sys Smoke Detectors.Caused by Failure to Properly Incorporate Ts.Ts Partially Revised	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)
05000245/LER-1997-003, Forwards LER 97-003-00 Which Documents an Event That Occurred at Mnps,Unit 1 on 970306,per 10CFR50.73(a)(2)(i). Commitments Made within Ltr,Listed	Forwards LER 97-003-00 Which Documents an Event That Occurred at Mnps,Unit 1 on 970306,per 10CFR50.73(a)(2)(i). Commitments Made within Ltr,Listed	10 CFR 50.73(a)(2)(i)
05000245/LER-1997-003-02, :on 970306,svc Water Effluent Was Not Monitored Per Requirements of Ts.Caused by Inadequate Design Change Package.Procedures to Ensure That SW Effluent from Reactor Bldg Operated within Design Basis Revised	on 970306,svc Water Effluent Was Not Monitored Per Requirements of Ts.Caused by Inadequate Design Change Package.Procedures to Ensure That SW Effluent from Reactor Bldg Operated within Design Basis Revised	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)
05000336/LER-1997-004-01, :on 970123,violation of TS 3.1.2.3 Requirement for Number of High Pressure Safety Injection Pumps Capable of Injecting Into RCS Occurred.Caused by Personnel Error. HPSI Pumps Have Been Revised	on 970123,violation of TS 3.1.2.3 Requirement for Number of High Pressure Safety Injection Pumps Capable of Injecting Into RCS Occurred.Caused by Personnel Error. HPSI Pumps Have Been Revised	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii)
05000245/LER-1997-004-01, Forwards LER 97-004-01,documenting Closure of Commitment B16213-1.Includes Commitments Made within This Ltr	Forwards LER 97-004-01,documenting Closure of Commitment B16213-1.Includes Commitments Made within This Ltr	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000245/LER-1997-004-02, :on 970127,RBCCW Containment Isolation Sys Single Failure Vulnerability Occurred.Caused by Failure to Adequately Establish Design Basis.No Immediate CA Are Required	on 970127,RBCCW Containment Isolation Sys Single Failure Vulnerability Occurred.Caused by Failure to Adequately Establish Design Basis.No Immediate CA Are Required	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)
05000245/LER-1997-004, :on 970127,RBCCW Containment Isolation Valve May Not Close within Specified Time.Caused by Failure to Adequately Establish Design Basis.Plant Is in Cold Shutdown W/Reactor Defueled	on 970127,RBCCW Containment Isolation Valve May Not Close within Specified Time.Caused by Failure to Adequately Establish Design Basis.Plant Is in Cold Shutdown W/Reactor Defueled	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii)
05000423/LER-1997-004, :on 970114,lack of Verbatim Compliance with TS Surveillance Requirements for Molded Case Circuit Breakers Occurred.Caused by Addl Lack of Verbatim Compliance. Corrected 18 Month Surveillances Will Be Performed	on 970114,lack of Verbatim Compliance with TS Surveillance Requirements for Molded Case Circuit Breakers Occurred.Caused by Addl Lack of Verbatim Compliance. Corrected 18 Month Surveillances Will Be Performed	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii)
05000245/LER-1997-005-01, Forwards LER 97-005-01,documenting Closure of Commitment B16236-2 & B16236-3,including Commitments Made within Ltr	Forwards LER 97-005-01,documenting Closure of Commitment B16236-2 & B16236-3,including Commitments Made within Ltr	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000245/LER-1997-005, :on 970115,discovered That Radwaste Storage Bldg Vent Exhaust Fan HVE-14 Discharges Directly to Atmosphere.Caused by Inadequate Design Review.Operation of Exhaust Fan HVE-14 Was Prevented Immediately	on 970115,discovered That Radwaste Storage Bldg Vent Exhaust Fan HVE-14 Discharges Directly to Atmosphere.Caused by Inadequate Design Review.Operation of Exhaust Fan HVE-14 Was Prevented Immediately	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii)
05000336/LER-1997-005-02, :on 970204,inservice Test Instrumentation Did Not Meet Ansi/Asme Chapter XI Requirements.Caused by Inadequate Administrative Structure for IST Program. Procedure to Administer IST Program Was Implemented	on 970204,inservice Test Instrumentation Did Not Meet Ansi/Asme Chapter XI Requirements.Caused by Inadequate Administrative Structure for IST Program. Procedure to Administer IST Program Was Implemented	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000336/LER-1997-005, Forwards LER 97-005-00 Which Documents Event That Occurred at Mnps,Unit 2 on 970204.Commitments Made,Listed	Forwards LER 97-005-00 Which Documents Event That Occurred at Mnps,Unit 2 on 970204.Commitments Made,Listed	10 CFR 50.73(a)(2)(i)
05000423/LER-1997-005, Corrects Numbering Inconsistency in Commitments Addressing LER 97-005-00	Corrects Numbering Inconsistency in Commitments Addressing LER 97-005-00
05000245/LER-1997-006-01, :on 970131,failure to Exert Best Efforts to Restore Radwaste Effluent Line Radiation Monitor to Operable Status Occurred.Caused by Failure to Provide Clear Management Expectations.Management Will Be Provided	on 970131,failure to Exert Best Efforts to Restore Radwaste Effluent Line Radiation Monitor to Operable Status Occurred.Caused by Failure to Provide Clear Management Expectations.Management Will Be Provided	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)
05000423/LER-1997-006, :on 970117,RHR Suction Isolation Valves Open But Not Under Administrative Control as Required in Mode 4 by TS SR 4.6.1.1.a.Caused by Failure to Identify Conflict Between Requirements.Rhr Required Position Determined	on 970117,RHR Suction Isolation Valves Open But Not Under Administrative Control as Required in Mode 4 by TS SR 4.6.1.1.a.Caused by Failure to Identify Conflict Between Requirements.Rhr Required Position Determined	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)
05000423/LER-1997-006-01, Forwards LER 97-006-01 Per 10CFR50.73(a)(2)(i).Util Commitments in Response to 970117 Event Contained within Attachment 1	Forwards LER 97-006-01 Per 10CFR50.73(a)(2)(i).Util Commitments in Response to 970117 Event Contained within Attachment 1	10 CFR 50.73(a)(2)(i)
05000336/LER-1997-006-02, :on 970211,main Steam Line Break Inside Containment Event Could Result in Exceeding Design Pressure of Primary Containment During Certain Scenarios.Caused by Inadequate Evaluation.Ca Will Be Implemented	on 970211,main Steam Line Break Inside Containment Event Could Result in Exceeding Design Pressure of Primary Containment During Certain Scenarios.Caused by Inadequate Evaluation.Ca Will Be Implemented	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000245/LER-1997-006, Forwards LER 97-006-00,documenting Condition That Was Discovered at Millstone Nuclear Station,Unit 1 on 970131, Per 10CFR50.73(a)(2)(i).Util Commitments Made within Ltr, Listed	Forwards LER 97-006-00,documenting Condition That Was Discovered at Millstone Nuclear Station,Unit 1 on 970131, Per 10CFR50.73(a)(2)(i).Util Commitments Made within Ltr, Listed	10 CFR 50.73(a)(2)(i)
05000336/LER-1997-006, Forwards LER 97-006-00 Which Documents an Event That Occurred on 970211.Commitments Made within Ltr,Listed	Forwards LER 97-006-00 Which Documents an Event That Occurred on 970211.Commitments Made within Ltr,Listed	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000245/LER-1997-007, Forwards LER 97-007-00,documenting Condition That Was Discovered at Millstone Nuclear Power Station,Unit 1 on 970131,per 10CFR50.73(a)(2)(i) & 10CFR50.73(a)(2)(ii). Util Commitments Made within Ltr,Listed	Forwards LER 97-007-00,documenting Condition That Was Discovered at Millstone Nuclear Power Station,Unit 1 on 970131,per 10CFR50.73(a)(2)(i) & 10CFR50.73(a)(2)(ii). Util Commitments Made within Ltr,Listed	10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000336/LER-1997-007-02, :on 970308,inadequate Surveillance Procedure Used for Verifying Operability of RCS Vents.Caused by Failure to Incorporate TS SRs Into Plant Surveillance Procedures.Revised Surveillance Procedure	on 970308,inadequate Surveillance Procedure Used for Verifying Operability of RCS Vents.Caused by Failure to Incorporate TS SRs Into Plant Surveillance Procedures.Revised Surveillance Procedure	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000336/LER-1997-007, Provides List of Commitments for LER 97-007-00 Re Event That Occurred on 970308	Provides List of Commitments for LER 97-007-00 Re Event That Occurred on 970308	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000423/LER-1997-007, :on 970123,non-conservative Assumptions Used in TSs Shutdown Margin Curve Identified.Caused by Lack of Procedures for Generation & Documentation of Reactor Operational Info.Engineering Procedure Will Be Revised	on 970123,non-conservative Assumptions Used in TSs Shutdown Margin Curve Identified.Caused by Lack of Procedures for Generation & Documentation of Reactor Operational Info.Engineering Procedure Will Be Revised	10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)
05000245/LER-1997-008, Forwards LER 97-008-00,documenting Condition That Was Discovered at Millstone Nuclear Power Station,Unit 1 on 970203,per 10CFR50.73(a)(2)(ii).Util Commitments Made within Ltr,Listed	Forwards LER 97-008-00,documenting Condition That Was Discovered at Millstone Nuclear Power Station,Unit 1 on 970203,per 10CFR50.73(a)(2)(ii).Util Commitments Made within Ltr,Listed	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000423/LER-1997-008, :on 970124,TS 3.0.3 Action Statement for MSIV Closure Was Entered Due to TS Being Inconsistent W/Msiv Safety Function & Design.Submitted Proposed License Amend Request Ptscr 3-13-95	on 970124,TS 3.0.3 Action Statement for MSIV Closure Was Entered Due to TS Being Inconsistent W/Msiv Safety Function & Design.Submitted Proposed License Amend Request Ptscr 3-13-95	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)
05000336/LER-1997-008, Forwards LER 97-008-00,documenting Event Occurred at Unit 2 on 970310.Commitments Made within Ltr Listed as Submitted	Forwards LER 97-008-00,documenting Event Occurred at Unit 2 on 970310.Commitments Made within Ltr Listed as Submitted	10 CFR 50.73(a)(2)(i)
05000336/LER-1997-008-02, :on 970310,repts Review Facility Compliance W/ GL 96-01 for Reactor Protective Sys Received.Caused by Inadequate Program to Ensure Surveillance Procedures Fully Implement TS Requirements.Procedures Revised	on 970310,repts Review Facility Compliance W/ GL 96-01 for Reactor Protective Sys Received.Caused by Inadequate Program to Ensure Surveillance Procedures Fully Implement TS Requirements.Procedures Revised	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii)
05000245/LER-1997-008-01, :on 970203,discovered Starting Air Sys Operating Outside Design Basis.Caused by Failure to Properly Identify & Verify Design Basis.Design Basis Established & Documented in FSAR	on 970203,discovered Starting Air Sys Operating Outside Design Basis.Caused by Failure to Properly Identify & Verify Design Basis.Design Basis Established & Documented in FSAR	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)
05000336/LER-1997-009, Forwards LER 97-009-00,which Documents an Event That Occurred on 970325.Commitments Made within Ltr,Submitted	Forwards LER 97-009-00,which Documents an Event That Occurred on 970325.Commitments Made within Ltr,Submitted	10 CFR 50.73(a)(2)(i)
05000336/LER-1997-009-02, :on 970325,insufficient ESFAS Surveillance Testing,Per GL 96-01 Review Occurred.Caused by Inadequate Program to Ensure Surveillance Procedures Fully Implement TS Requirements.Procedures Will Be Revised	on 970325,insufficient ESFAS Surveillance Testing,Per GL 96-01 Review Occurred.Caused by Inadequate Program to Ensure Surveillance Procedures Fully Implement TS Requirements.Procedures Will Be Revised	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)
05000245/LER-1997-009-01, :on 970212,reactor low-low Level ECCS & Primary Containment Initiation Setpoints Were Not Conservative. Caused by Deficient Setpoint Methodology.Calculations Will Be Revised & TS Change Initiated	on 970212,reactor low-low Level ECCS & Primary Containment Initiation Setpoints Were Not Conservative. Caused by Deficient Setpoint Methodology.Calculations Will Be Revised & TS Change Initiated	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iii)
05000245/LER-1997-009, Forwards LER 97-009-00,documenting Condition That Was Discovered at Millstone Nuclear Power Station,Unit 1 on 970212.Util Commitments Made within Ltr,Listed	Forwards LER 97-009-00,documenting Condition That Was Discovered at Millstone Nuclear Power Station,Unit 1 on 970212.Util Commitments Made within Ltr,Listed	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000336/LER-1997-009-01, :on 970325,insufficient ESFAS Surveillance Testing,Per GL 96-01,noted.Caused by Inadequate Program to Ensure Sps Fully Implement TS Requirements.Operational Surveillances Will Be Revised	on 970325,insufficient ESFAS Surveillance Testing,Per GL 96-01,noted.Caused by Inadequate Program to Ensure Sps Fully Implement TS Requirements.Operational Surveillances Will Be Revised	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)
05000423/LER-1997-009-01, Forwards LER 97-009-01,documenting Condition Originally Determined Reportable at Unit 3 on 970123.Util Commitments in Response to Event Contained within Attachment 1 to Ltr	Forwards LER 97-009-01,documenting Condition Originally Determined Reportable at Unit 3 on 970123.Util Commitments in Response to Event Contained within Attachment 1 to Ltr	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)
05000336/LER-1997-010, Forwards LER 97-010-00,documenting Event Occurred at Unit 2 on 970112.Commitments Made within Ltr Listed	Forwards LER 97-010-00,documenting Event Occurred at Unit 2 on 970112.Commitments Made within Ltr Listed	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000423/LER-1997-010, :on 970129,electrical Calculation Discrepancies Identified in Min Voltage Analysis for Class 1E Electrical Sys.Caused by Lack of Configuration Mgt for Comprehensive Calculation Program.Program Being Revised	on 970129,electrical Calculation Discrepancies Identified in Min Voltage Analysis for Class 1E Electrical Sys.Caused by Lack of Configuration Mgt for Comprehensive Calculation Program.Program Being Revised	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)
05000245/LER-1997-010-01, :on 970214,determined LLRT Pressure Being Used May Be Less than Accident Pressure.Caused by Weakness in Mgt Commitment to App J Program.Llrts Modified	on 970214,determined LLRT Pressure Being Used May Be Less than Accident Pressure.Caused by Weakness in Mgt Commitment to App J Program.Llrts Modified	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000245/LER-1997-010, Forwards LER 97-010-00,documenting Event Occurred at Unit 1 on 970214.Commitments Made within Ltr Submitted as Listed	Forwards LER 97-010-00,documenting Event Occurred at Unit 1 on 970214.Commitments Made within Ltr Submitted as Listed	10 CFR 50.73(a)(2)(i)
05000336/LER-1997-010-02, :on 970112,heavy Dummy Fuel Assembly & Handling Tool Weight Exceeded TS Limit Occurred.Caused by Weight of Handling Tool Never Considered to Be Part of Load.Temporary Measure & Appropriate Procedures Revised	on 970112,heavy Dummy Fuel Assembly & Handling Tool Weight Exceeded TS Limit Occurred.Caused by Weight of Handling Tool Never Considered to Be Part of Load.Temporary Measure & Appropriate Procedures Revised	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)
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