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{{#Wiki_filter:" 0 UNITED STATES Q 0 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Richard L. Anderson Vice President NextEra Energy Duane Arnold Energy Center 3277 DAEC Road Palo, lA 52324-9785 January 17, 2014 SUBJECT: CORRECTION LETTER-DUANE ARNOLD ENERGY CENTER REGARDING INTERIM STAFF EVALUATION AND REQUEST FOR ADDITIONAL INFORMATION FOR RELIABLE SPENT FUEL POOL INSTRUMENTATION (ORDER NUMBER EA-12-051) (TAC NO. MF1001) *Dear Mr. Anderson: On November 26, 2013 (Agencywide Documents Access and Management System (ADAMS) *Accession No. ML 13323B443), the U.S. Nuclear Regulatory Commission (NRC) issued an interim staff evaluation and request for additional information (RAI) regarding the overall integrated plan for implementation of Order EA-12-051, Reliable Spent Fuel Instrumentation for Duane Arnold Energy Center (DAEC). Following the issuance of the evaluation, the NRC staff was informed by NextEra Energy Duane Arnold, LLC (the licensee) that the numbering sequence for the RAis was not correct. RAI , numbers 13 and 14 were missing as a result of the numbering sequence going from RAI number 12 to RAI number 15. RAI numbers 15 and 16 have* been renumbered as RAI numbers 13 and 14 respectively. Enclosed, please the replacement for page number 22 for the evaluation. The NRC staff determined that this error was entirely administrative in nature, and was inadvertently introduced, and it did not have any effect on the overall evaluation. We regret any inconvenience that this may have caused.
{{#Wiki_filter:" 0 UNITED STATES Q 0 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Richard L. Anderson Vice President NextEra Energy Duane Arnold Energy Center 3277 DAEC Road Palo, lA 52324-9785 January 17, 2014  
R. L. Anderson Q 0 -2-Should you have any questions, please feel free to contact me at Mahesh.Chawla@ nrc.qov or 301-415-8371. Docket No. 50-331 Enclosure: Replacement page number 22 for the Interim Staff Evaluation cc w/encl: Distribution via Listserv Sincerely, Mahesh Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 0 0 Q 0 RAI #13 ;;, Please provide the following: -22-Q 0 a) Further information describing the maintenance and testing program the licensee will establish and implement to ensure that regular testing and calibration is performed and verified by inspection and audit to demonstrate conformance with design and system readiness requirements. Include a description of plans to ensure necessary cha.nnel checks, functional tests, periodic calibration, and maintenance will be conducted for the level measurement system and its supporting equipment. b) A description of the NextEra/DAEC procedure/process to implement the guidance in NEI 12-02 section 4.3 regarding compensatory actions for one or both functioning channels. c) A description of the compensatory actions planned in the event that one of the instrument channels cannot be restored to functional status within 90 days. (This information was previously requested as RAI-11 in the NRC letter dated September 16, 2013.) RAI #14 Please provide a description of the in-situ calibration process at the SFP location that will result in the channel calibration being maintained at its design accuracy. 3.15
 
* Instrument Reliability NEI-12-02 states, in part, that A spent fuel pool level instrument channel is considered reliable when the instrument channel satisfies the design elements listed in Section 3 [Instrument Design Features] of this guidance and the plant operator has fully implemented the programmatic features listed in Section 4 [Program Features]. In its OIP, the licensee stated that the reliability of the primary and backup instrument channels will be assured by conformance with the guidelines of NRC JLD-ISG-2012-03 and NEI 12-02. Upon acceptable resolution of the RAis noted above, the NRC staff will be able to make a conclusion regarding the reliability of the SFP instrumentation. 4.0 CONCLUSION The NRC staff is unable to complete its evaluation regarding the acceptability of the licensee's plans for implementing the requirements of Order EA 12 051 due to the need for additional information as described above. The NRC staff will issue an evaluation with its conclusion after the licensee has provided the requested information. Enclosure 0 (} R. L. Anderson -2-0 Q Should you have any questions, please feel free to contact me at Mahesh.Chawla@nrc.gov or 301-415-8371. Docket No. 50-331 Enclosure: Sincerely, /RAJ Mahesh Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Replacement page number 22 for the Interim Staff Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL3-1 Reading RidsNrrDeEicb Resource RidsNrrDssSbpb Resource RidsNrrPMDuaneArnold Resource CRoque-Cruz, NRR GCasto, NRR RKuntz, NRR BPurnell, NRR RidsAcrsAcnw_MaiiCTR Resource RidsNrrDorllpl3-1 Resource RidsNrrLAMHenderson Resource RidsRgn3MaiiCenter Resource DRahn, NRR MMitchell, NRR CHunt, NRR ADAMS Accession No.: ML 14007 A215 OFFICE LPL3-1/PM LPL3-1/LA NAME MChawla MHenderson DATE 01/14/14 01/10/14 OFFICE DE/EICB/BC LPL3-1/BC NAME JThorp RCarlson DATE 01/14/14 r 01/17/14 OFFICIAL RECORD COPY SBPB/BC GCasto 01/14/14 LPL3-1/PM MChawla 01/17/14   
==SUBJECT:==
CORRECTION LETTER-DUANE ARNOLD ENERGY CENTER REGARDING INTERIM STAFF EVALUATION AND REQUEST FOR ADDITIONAL INFORMATION FOR RELIABLE SPENT FUEL POOL INSTRUMENTATION (ORDER NUMBER EA-12-051) (TAC NO. MF1001) *
 
==Dear Mr. Anderson:==
On November 26, 2013 (Agencywide Documents Access and Management System (ADAMS) *Accession No. ML 13323B443), the U.S. Nuclear Regulatory Commission (NRC) issued an interim staff evaluation and request for additional information (RAI) regarding the overall integrated plan for implementation of Order EA-12-051, Reliable Spent Fuel Instrumentation for Duane Arnold Energy Center (DAEC). Following the issuance of the evaluation, the NRC staff was informed by NextEra Energy Duane Arnold, LLC (the licensee) that the numbering sequence for the RAis was not correct. RAI , numbers 13 and 14 were missing as a result of the numbering sequence going from RAI number 12 to RAI number 15. RAI numbers 15 and 16 have* been renumbered as RAI numbers 13 and 14 respectively. Enclosed, please the replacement for page number 22 for the evaluation. The NRC staff determined that this error was entirely administrative in nature, and was inadvertently introduced, and it did not have any effect on the overall evaluation. We regret any inconvenience that this may have caused.
R. L. Anderson Q 0 Should you have any questions, please feel free to contact me at Mahesh.Chawla@ nrc.qov or 301-415-8371. Docket No. 50-331  
 
==Enclosure:==
Replacement page number 22 for the Interim Staff Evaluation cc w/encl: Distribution via Listserv Sincerely, Mahesh Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 0 0 Q 0 RAI #13 ;;, Please provide the following: -22-Q 0 a) Further information describing the maintenance and testing program the licensee will establish and implement to ensure that regular testing and calibration is performed and verified by inspection and audit to demonstrate conformance with design and system readiness requirements. Include a description of plans to ensure necessary cha.nnel checks, functional tests, periodic calibration, and maintenance will be conducted for the level measurement system and its supporting equipment. b) A description of the NextEra/DAEC procedure/process to implement the guidance in NEI 12-02 section 4.3 regarding compensatory actions for one or both functioning channels. c) A description of the compensatory actions planned in the event that one of the instrument channels cannot be restored to functional status within 90 days. (This information was previously requested as RAI-11 in the NRC letter dated September 16, 2013.) RAI #14 Please provide a description of the in-situ calibration process at the SFP location that will result in the channel calibration being maintained at its design accuracy. 3.15
* Instrument Reliability NEI-12-02 states, in part, that A spent fuel pool level instrument channel is considered reliable when the instrument channel satisfies the design elements listed in Section 3 [Instrument Design Features] of this guidance and the plant operator has fully implemented the programmatic features listed in Section 4 [Program Features]. In its OIP, the licensee stated that the reliability of the primary and backup instrument channels will be assured by conformance with the guidelines of NRC JLD-ISG-2012-03 and NEI 12-02. Upon acceptable resolution of the RAis noted above, the NRC staff will be able to make a conclusion regarding the reliability of the SFP instrumentation.  
 
==4.0 CONCLUSION==
The NRC staff is unable to complete its evaluation regarding the acceptability of the licensee's plans for implementing the requirements of Order EA 12 051 due to the need for additional information as described above. The NRC staff will issue an evaluation with its conclusion after the licensee has provided the requested information. Enclosure 0 (} R. L. Anderson 0 Q Should you have any questions, please feel free to contact me at Mahesh.Chawla@nrc.gov or 301-415-8371. Docket No. 50-331  
 
==Enclosure:==
Sincerely, /RAJ Mahesh Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Replacement page number 22 for the Interim Staff Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL3-1 Reading RidsNrrDeEicb Resource RidsNrrDssSbpb Resource RidsNrrPMDuaneArnold Resource CRoque-Cruz, NRR GCasto, NRR RKuntz, NRR BPurnell, NRR RidsAcrsAcnw_MaiiCTR Resource RidsNrrDorllpl3-1 Resource RidsNrrLAMHenderson Resource RidsRgn3MaiiCenter Resource DRahn, NRR MMitchell, NRR CHunt, NRR ADAMS Accession No.: ML 14007 A215 OFFICE LPL3-1/PM LPL3-1/LA NAME MChawla MHenderson DATE 01/14/14 01/10/14 OFFICE DE/EICB/BC LPL3-1/BC NAME JThorp RCarlson DATE 01/14/14 r 01/17/14 OFFICIAL RECORD COPY SBPB/BC GCasto 01/14/14 LPL3-1/PM MChawla 01/17/14   
}}
}}

Revision as of 09:45, 5 April 2018

Correction Letter - Duane Arnold Energy Center Regarding Interim Staff Evaluation and Request for Additional Information for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) (TAC No. MF1001)
ML14007A215
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 01/17/2014
From: Chawla M L
Plant Licensing Branch III
To: Anderson R L
NextEra Energy Duane Arnold
Chawla M L
References
EA-12-051, TAC MF1001
Download: ML14007A215 (4)


Text

" 0 UNITED STATES Q 0 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Richard L. Anderson Vice President NextEra Energy Duane Arnold Energy Center 3277 DAEC Road Palo, lA 52324-9785 January 17, 2014

SUBJECT:

CORRECTION LETTER-DUANE ARNOLD ENERGY CENTER REGARDING INTERIM STAFF EVALUATION AND REQUEST FOR ADDITIONAL INFORMATION FOR RELIABLE SPENT FUEL POOL INSTRUMENTATION (ORDER NUMBER EA-12-051) (TAC NO. MF1001) *

Dear Mr. Anderson:

On November 26, 2013 (Agencywide Documents Access and Management System (ADAMS) *Accession No. ML 13323B443), the U.S. Nuclear Regulatory Commission (NRC) issued an interim staff evaluation and request for additional information (RAI) regarding the overall integrated plan for implementation of Order EA-12-051, Reliable Spent Fuel Instrumentation for Duane Arnold Energy Center (DAEC). Following the issuance of the evaluation, the NRC staff was informed by NextEra Energy Duane Arnold, LLC (the licensee) that the numbering sequence for the RAis was not correct. RAI , numbers 13 and 14 were missing as a result of the numbering sequence going from RAI number 12 to RAI number 15. RAI numbers 15 and 16 have* been renumbered as RAI numbers 13 and 14 respectively. Enclosed, please the replacement for page number 22 for the evaluation. The NRC staff determined that this error was entirely administrative in nature, and was inadvertently introduced, and it did not have any effect on the overall evaluation. We regret any inconvenience that this may have caused.

R. L. Anderson Q 0 Should you have any questions, please feel free to contact me at Mahesh.Chawla@ nrc.qov or 301-415-8371. Docket No. 50-331

Enclosure:

Replacement page number 22 for the Interim Staff Evaluation cc w/encl: Distribution via Listserv Sincerely, Mahesh Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 0 0 Q 0 RAI #13 ;;, Please provide the following: -22-Q 0 a) Further information describing the maintenance and testing program the licensee will establish and implement to ensure that regular testing and calibration is performed and verified by inspection and audit to demonstrate conformance with design and system readiness requirements. Include a description of plans to ensure necessary cha.nnel checks, functional tests, periodic calibration, and maintenance will be conducted for the level measurement system and its supporting equipment. b) A description of the NextEra/DAEC procedure/process to implement the guidance in NEI 12-02 section 4.3 regarding compensatory actions for one or both functioning channels. c) A description of the compensatory actions planned in the event that one of the instrument channels cannot be restored to functional status within 90 days. (This information was previously requested as RAI-11 in the NRC letter dated September 16, 2013.) RAI #14 Please provide a description of the in-situ calibration process at the SFP location that will result in the channel calibration being maintained at its design accuracy. 3.15

  • Instrument Reliability NEI-12-02 states, in part, that A spent fuel pool level instrument channel is considered reliable when the instrument channel satisfies the design elements listed in Section 3 [Instrument Design Features] of this guidance and the plant operator has fully implemented the programmatic features listed in Section 4 [Program Features]. In its OIP, the licensee stated that the reliability of the primary and backup instrument channels will be assured by conformance with the guidelines of NRC JLD-ISG-2012-03 and NEI 12-02. Upon acceptable resolution of the RAis noted above, the NRC staff will be able to make a conclusion regarding the reliability of the SFP instrumentation.

4.0 CONCLUSION

The NRC staff is unable to complete its evaluation regarding the acceptability of the licensee's plans for implementing the requirements of Order EA 12 051 due to the need for additional information as described above. The NRC staff will issue an evaluation with its conclusion after the licensee has provided the requested information. Enclosure 0 (} R. L. Anderson 0 Q Should you have any questions, please feel free to contact me at Mahesh.Chawla@nrc.gov or 301-415-8371. Docket No. 50-331

Enclosure:

Sincerely, /RAJ Mahesh Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Replacement page number 22 for the Interim Staff Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL3-1 Reading RidsNrrDeEicb Resource RidsNrrDssSbpb Resource RidsNrrPMDuaneArnold Resource CRoque-Cruz, NRR GCasto, NRR RKuntz, NRR BPurnell, NRR RidsAcrsAcnw_MaiiCTR Resource RidsNrrDorllpl3-1 Resource RidsNrrLAMHenderson Resource RidsRgn3MaiiCenter Resource DRahn, NRR MMitchell, NRR CHunt, NRR ADAMS Accession No.: ML 14007 A215 OFFICE LPL3-1/PM LPL3-1/LA NAME MChawla MHenderson DATE 01/14/14 01/10/14 OFFICE DE/EICB/BC LPL3-1/BC NAME JThorp RCarlson DATE 01/14/14 r 01/17/14 OFFICIAL RECORD COPY SBPB/BC GCasto 01/14/14 LPL3-1/PM MChawla 01/17/14