Provides Commitment Made Re Suppl to LER 95-008 Concerning Nonconservative Bias in Heat Balance Methodology for Calculating Core Thermal Power
Person / Time
ML20134M039
Site:	Fermi
Issue date:	11/15/1996
From:	Gipson D DETROIT EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20134M042	List: 05000341/LER-1995-008, Provides Commitment Made Re Suppl to LER 95-008 Concerning Nonconservative Bias in Heat Balance Methodology for Calculating Core Thermal Power 05000341/LER-1996-008, :on 951213,one Megawatt Thermal Nonconservative Bias Found in Core Thermal Power Calculation.Caused by Heat Pump Seal Purge Flow Being Considered Insignificant During Original Heat Balance & Thermal Power Calculation
References
CON-NRC-96-0100, CON-NRC-96-100 NUDOCS 9611220177
Download: ML20134M039 (2)
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LER-1995-008, Provides Commitment Made Re Suppl to LER 95-008 Concerning Nonconservative Bias in Heat Balance Methodology for Calculating Core Thermal Power

Event date:
Report date:
3411995008R00 - NRC Website
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4 Dougfra R. Gipson e

2 Sernor Wce Pressent '

Nuclear Generanon Fermi 2 6400 North Dune Hghway Newport, Michigan 48166

- (313) 686-5249 Ncvember 3.5, 1996 NRCA6-0100 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. CJ 20555 References: 1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43

2) Detroit Edison letter to NRC, i

Licensee Event Report No.95-008, NRC-95-0112, dated January 12,1996

Subject:

Licensee Event Report (LER) No. 95-008-01

]

As committe<i to in Reference 2, Detroit Edison is submitting the enclosed supplement, LEP, No. 954008-01 regarding a nonconservative bias in the heat

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balance methodolcgy for calculating core thermal power The condition--

discussed in this LER was identified as a result of similar discoveries at other plants 1

The following commitment is being made in this supplement:

Detroit Edison has actively participated in discussions with General Electric and industry groups to address this issue and to follow industry developments related to the heat balance and core thermal power calculation methodology, Detroit

]

Edison has decided to incorporate the effects of Control Rod Drive (CRD) i purge flow to the Reactor Recirculation Pump seals into reactor heat balance calculations by a modification to the Process Computer and Manual Heat

'l Balance calculation methodologies via a change to the Radiative Heat Loss l

Constant. This action will be completed by May 30,1997.

'n 9611220177 961115 PDR ADOCK 05000341 8

PDR

November 15,1996 NRC-96-0100 Page 2

If you have any questions, please contact Mari Jaworsky, Licensing Compliance Engineer, at (313) 586-1427.

Sincerely, l

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cc: A. B. Beach l

M. J. Jordan A. J. Kugler A. Vegel M. V. Yudasz, Jr.

Region III l

Wayne County Emergency Management Division i

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Licensee Event Report

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		Reporting criterion
05000341/LER-1995-001, :on 950211,wide Range Reactor Water Level Recorder Indicated 10 Inch Reactor Water Level Decreased Due to Inadequate Test Controls.Controlled Diagnostic Monitoring Instruments to Prevent Similar Conditions	on 950211,wide Range Reactor Water Level Recorder Indicated 10 Inch Reactor Water Level Decreased Due to Inadequate Test Controls.Controlled Diagnostic Monitoring Instruments to Prevent Similar Conditions	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 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A)
05000341/LER-1995-002, :on 950216,RCIC Turbine Exhaust Line Vacuum Outboard Isolation Valve E51-F062 Closed Due to Personnel Error.Relay E51K63 Replaced & Surveillance Procedure 44.020.235 Reperformed	on 950216,RCIC Turbine Exhaust Line Vacuum Outboard Isolation Valve E51-F062 Closed Due to Personnel Error.Relay E51K63 Replaced & Surveillance Procedure 44.020.235 Reperformed	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)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000341/LER-1995-003, :on 950228,unusual Event Declared & Terminated When Mode Switch Placed in Shutdown Completing Plant shut- Down in Accordance W/Tss.Caused by Gradual Draining Down of Div 2 Rwl.Performed Verification of Valves	on 950228,unusual Event Declared & Terminated When Mode Switch Placed in Shutdown Completing Plant shut- Down in Accordance W/Tss.Caused by Gradual Draining Down of Div 2 Rwl.Performed Verification of Valves	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)
05000341/LER-1995-004, :on 950409,unexpected Reactor Water Level 2 & ESF Actuations Occurred After Planned Scram.Caused by Selection of Parameters Used in Post Scram FW Logic Mod Per Engineering Design Package 9207 Installed During RF04	on 950409,unexpected Reactor Water Level 2 & ESF Actuations Occurred After Planned Scram.Caused by Selection of Parameters Used in Post Scram FW Logic Mod Per Engineering Design Package 9207 Installed During RF04	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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000341/LER-1995-005, :on 950425,reactor Tripped Due to High Neutron Flux.Caused by Reactor Pressure Transient.Tested Circuit Boards to Attempt Further Cause Determination to Component Level	on 950425,reactor Tripped Due to High Neutron Flux.Caused by Reactor Pressure Transient.Tested Circuit Boards to Attempt Further Cause Determination to Component Level	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)
05000341/LER-1995-006, :on 950602,main Turbine Trip Occurred Due to False Overspeed During Mechanical Overspeed Test.Revised Procedure 27.112.01 to Incorporate Holding Overspeed Reset Pushbutton Depressed at Least 15 Seconds	on 950602,main Turbine Trip Occurred Due to False Overspeed During Mechanical Overspeed Test.Revised Procedure 27.112.01 to Incorporate Holding Overspeed Reset Pushbutton Depressed at Least 15 Seconds	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 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A)
05000341/LER-1995-007, :on 950928,TS Violation Occurred.Caused by Procedure Deficiency.Appropriate Surveillance Test Procedures Will Be Revised to Include Positive Verification	on 950928,TS Violation Occurred.Caused by Procedure Deficiency.Appropriate Surveillance Test Procedures Will Be Revised to Include Positive Verification
05000341/LER-1995-008, Provides Commitment Made Re Suppl to LER 95-008 Concerning Nonconservative Bias in Heat Balance Methodology for Calculating Core Thermal Power	Provides Commitment Made Re Suppl to LER 95-008 Concerning Nonconservative Bias in Heat Balance Methodology for Calculating Core Thermal Power

05000341/LER-1995-008, Provides Commitment Made Re Suppl to LER 95-008 Concerning Nonconservative Bias in Heat Balance Methodology for Calculating Core Thermal Power

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