v t e Letter Sequence Request
TAC:MD2619, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (Approved, Closed)
Initiation Request, Request Acceptance... Administration Questions Answers 20 March 2007 7 February 2007 Results Approval Other: ML070610216, ML071790168, NG-06-0472, Technical Specification Change Request (TSCR-083): Adoption of TSTF-478, Rev. 0, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control, Affected Tech Specs: Section 3.6.3.1 and 3.6.3.2, TSTF-07-09, TSTF-478, Revision 1, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control
MONTHYEAR2007-02-07 [Table View]

Regarding Cancellation
Person / Time
ML071580133
Site:	Duane Arnold
Issue date:	06/01/2007
From:	Vanmiddlesworth G Duane Arnold
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NG-07-0466 LER 07-001-00
Download: ML071580133 (2)
v • d • e

LER-2007-001, Regarding Cancellation

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(v), Loss of Safety Function
3312007001R00 - NRC Website
v • d • e

text

FPL Energy Duane Arnold, LLC 3277 DAEC Road Palo, Iowa 52324 FPL Energy.

Duane Arnold Energy Center June 1, 2007 NG-07-0466 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Duane Arnold Energy Center Docket 50-331 License No. DPR-49 LER 331/2007-001 Cancellation Reference: Letter from G. Van Middlesworth (FPL Energy Duane Arnold) to USNRC, "License Event Report #2007-001-00," NG-07-0292, dated March 26, 2007, ML070860691.

On March 26, 2007, FPL Energy Duane Arnold submitted Licensee Event Report (LER) 50-331/2007-001 pursuant to 10 CFR 50.73(a)(2)(v)(D). This LER reported an unplanned inoperability of the High Pressure Coolant Injection (HPCI) system.

Subsequent detailed engineering analysis was performed to determine the impact of degraded HPCI pipe support EBB-5-SR-9 on the past operability of the HPCI system. The support was evaluated with respect to ASME Code Section III, Appendix F, operability criteria using a conservative HPCI transient loading and two different seismic load combinations:

1. Independent Support Motions (ISM) seismic method.

2. Design Basis seismic method.

Both load combinations include deadweight loads, thermal loads, and HPCI transient loads, in addition to the safe shutdown seismic loading. Using the design basis seismic method, operability criteria were not met. However, using a more realistic ISM method, the support and piping operability criteria are met, even using a conservative increased HPCI transient loading.

FPL Energy Duane Arnold considers the use of ISM analysis acceptable for this determination of HPCI system past operability. The ISM analysis was performed following guidance provided in NUREG-1061, "Report of the U.S. Nuclear Regulatory Commission Piping Review Committee / Seismic Design Task Group," using the Multi-Point Response Spectrum (MPRS) options in the ANSYS program. A test problem, taken from NUREG/CR-1677, "Piping Benchmark Problems - Dynamic Analysis Independent Support Motion Response Spectrum Method," was run using Single-Point Response Spectra and MPRS methodologies as model validation. Both cases matched the results reported in NUREG/CR-1677.

Based on the above, LER 50-331/2007-001-00 is formally withdrawn.

H Qc~/iU -

NG-07-0466 June 1, 2007 Page 2 of 2 In addition, the following commitment made in NG-07-0292, dated 3/26/07, "LER 2007-001,"

is being retracted:

Submit a supplement to LER 2007-001 that contains the completed safety significance of the subject event by 6/01/07.

If you have any questions, please call Steve Catron, Licensing Manager at (319) 851-7234.

Gary Van Middlesworth Site Vice President, Duane Arnold Energy Center FPL Energy Duane Arnold, LLC CC:

Administrator, Region III, USNRC Project Manager, DAEC, USNRC Resident Inspector, DAEC, USNRC

Licensee Event Report

Duane Arnold

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		Reporting criterion
05000331/LER-2007-001, Regarding Cancellation	Regarding Cancellation	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000331/LER-2007-002, Regarding Loss of Control of Control Building Boundary	Regarding Loss of Control of Control Building Boundary	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000331/LER-2007-003, Re Linear Indications Found During UT Examination of Safe-End to Nozzle Welds	Re Linear Indications Found During UT Examination of Safe-End to Nozzle Welds	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000331/LER-2007-004, Re Severe Weather Causes Grid Disturbance Resulting in Loss of Shutdown Cooling	Re Severe Weather Causes Grid Disturbance Resulting in Loss of Shutdown Cooling	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000331/LER-2007-005, Re Automatic Reactor Scram Due to Scram Discharge Volume High Water Level During Performance of a Surveillance Test	Re Automatic Reactor Scram Due to Scram Discharge Volume High Water Level During Performance of a Surveillance Test	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000331/LER-2007-006, From Duane Arnold Energy Center, Re Reactor Shutdown as a Result of Chemistry Excursion	From Duane Arnold Energy Center, Re Reactor Shutdown as a Result of Chemistry Excursion	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000331/LER-2007-007, Regarding Reactor Scram Due to 1A2 Non-essential Bus Lockout	Regarding Reactor Scram Due to 1A2 Non-essential Bus Lockout	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000331/LER-2007-008, Regarding Condition Prohibited by Technical Specifications; B Emergency Diesel Inoperable	Regarding Condition Prohibited by Technical Specifications; B Emergency Diesel Inoperable	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)(viii)(A)
05000331/LER-2007-009, Loss of Essential Bus Resulted in a Loss of Safety Function	Loss of Essential Bus Resulted in a Loss of Safety Function	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000331/LER-2007-010, Re Safety System Functional Failure of Alternate Preferred Offsite Power Source	Re Safety System Functional Failure of Alternate Preferred Offsite Power Source	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000331/LER-2007-011, Re Undervoltage Condition Resulted in the Actuation of the Emergency Diesel Generators	Re Undervoltage Condition Resulted in the Actuation of the Emergency Diesel Generators	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)

05000331/LER-2007-001, Regarding Cancellation

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