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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 2, 2014 Mr. Lawrence Coyle Site Vice President Entergy Nuclear Operations, Inc. James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 2, 2014 Mr. Lawrence Coyle Site Vice President Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093


==SUBJECT:==
==SUBJECT:==
JAMES A. FITZPATRICK NUCLEAR POWER PLANT-REQUEST FOR ADDITIONAL INFORMATION REGARDING 10 CFR 50.55a REQUEST PRR-05 (TAC NO. MF3680)  
JAMES A. FITZPATRICK NUCLEAR POWER PLANT- REQUEST FOR ADDITIONAL INFORMATION REGARDING 10 CFR 50.55a REQUEST PRR-05 (TAC NO. MF3680)


==Dear Mr. Coyle:==
==Dear Mr. Coyle:==
By letter dated February 21, 2014, Entergy Nuclear Operations, Inc., the licensee, requested an alternative to the requirements of the American Society of Mechanical Engineers Operation and Maintenance of Nuclear Power Plants Code related to testing of the residual heat removal pumps at the James A. FitzPatrick Nuclear Power Plant. The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI}. Based on our discussions we understand that a response to the RAI will be provided within 30 days of the date of this letter. Please contact me at (301) 415-1364 if you have any questions on this issue. Docket No. 50-333  
 
By letter dated February 21, 2014, Entergy Nuclear Operations, Inc., the licensee, requested an alternative to the requirements of the American Society of Mechanical Engineers Operation and Maintenance of Nuclear Power Plants Code related to testing of the residual heat removal pumps at the James A. FitzPatrick Nuclear Power Plant.
The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI}. Based on our discussions we understand that a response to the RAI will be provided within 30 days of the date of this letter.
Please contact me at (301) 415-1364 if you have any questions on this issue.
Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333


==Enclosure:==
==Enclosure:==


Request for Additional Information cc w/encl: Distribution via Listserv Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION ALTERNATE REQUEST PRR-05 ENTERGY NUCLEAR OPERATIONS, INC. JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333  
Request for Additional Information cc w/encl: Distribution via Listserv
 
REQUEST FOR ADDITIONAL INFORMATION ALTERNATE REQUEST PRR-05 ENTERGY NUCLEAR OPERATIONS, INC.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333


==Reference:==
==Reference:==


Letter from C.M. Adner of Entergy Nuclear Operations, Inc. to NRC, "James A. FitzPatrick Nuclear Power Plant lnservice Testing Program 10 CFR 50.55a Request PRR-05" dated February 21, 2014 (Agencywide Document Access and Management System (ADAMS) Accession Number ML14057A553).
Letter from C.M. Adner of Entergy Nuclear Operations, Inc. to NRC, "James A. FitzPatrick Nuclear Power Plant lnservice Testing Program 10 CFR 50.55a Request PRR-05" dated February 21, 2014 (Agencywide Document Access and Management System (ADAMS)
RAI PRR-05-1 Alternative request PRR-05 states that three vibration points are available from December of 1998 to present. However, Figures 12 through 20 in the submittal of PRR-005 do not contain data from the third vibration point (V3, axial direction) for pumps 1 OP-38 and 1 OP-3C. Please provide figures showing V3 (axial direction) as a function of time from December 1998 to present and a sample spectral analysis of the data measured in the V3 direction for pumps 1 OP-38 and 1 OP-3C. RAI PRR-05-2 Alternative request PRR-05, under "Consultation  
Accession Number ML14057A553).
-Pump Manufacturer I Vibration Expert," states that the pump vendor was contacted during the initial investigation of the cause for failed vibration acceptance criteria.
RAI PRR-05-1 Alternative request PRR-05 states that three vibration points are available from December of 1998 to present. However, Figures 12 through 20 in the submittal of PRR-005 do not contain data from the third vibration point (V3, axial direction) for pumps 1OP-38 and 1OP-3C. Please provide figures showing V3 (axial direction) as a function of time from December 1998 to present and a sample spectral analysis of the data measured in the V3 direction for pumps 1OP-38 and 1OP-3C.
Under "Basis for Code Alternative Alert Values," alternative request PRR-05 states that the basis for the 0.408 inches per second (ips) alert limit comes from the Technical Associates of Charlotte recommendations for vertical pumps. Is this recommendation applicable to all vertical pumps or were these recommendations developed specifically for residual heat removal (RHR) pumps 1 OP-3A, 1 OP-38, 1 OP-3C, or 1 OP-3D? Please provide any comments the pump vendor had regarding the recommended vibration alert values. RAI PRR-05-3 Alternative request PRR-05 proposes an alternative alert level for pumps 1 OP-3A, 1 OP-38, 1 OP-3C, and 1 OP-3D. To date, the ASME OM Code alert range value of 0.325 ips has been exceeded only on pumps 1 OP-38 and 1 OP-3C. Please provide justification on why the alternative request is necessary for RHR pumps 1 OP-3A and 1 OP-3D. Enclosure Mr. Lawrence Coyle Site Vice President Entergy Nuclear Operations, Inc. James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 July 2, 2014
RAI PRR-05-2 Alternative request PRR-05, under "Consultation - Pump Manufacturer I Vibration Expert,"
states that the pump vendor was contacted during the initial investigation of the cause for failed vibration acceptance criteria. Under "Basis for Code Alternative Alert Values," alternative request PRR-05 states that the basis for the 0.408 inches per second (ips) alert limit comes from the Technical Associates of Charlotte recommendations for vertical pumps. Is this recommendation applicable to all vertical pumps or were these recommendations developed specifically for residual heat removal (RHR) pumps 1OP-3A, 1OP-38, 1OP-3C, or 1OP-3D?
Please provide any comments the pump vendor had regarding the recommended vibration alert values.
RAI PRR-05-3 Alternative request PRR-05 proposes an alternative alert level for pumps 1OP-3A, 1OP-38, 1OP-3C, and 1OP-3D. To date, the ASME OM Code alert range value of 0.325 ips has been exceeded only on pumps 1OP-38 and 1OP-3C. Please provide justification on why the alternative request is necessary for RHR pumps 1OP-3A and 1OP-3D.
Enclosure
 
July 2, 2014 Mr. Lawrence Coyle Site Vice President Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093


==SUBJECT:==
==SUBJECT:==
JAMES A. FITZPATRICK NUCLEAR POWER PLANT-REQUEST FOR ADDITIONAL INFORMATION REGARDING 10 CFR 50.55a REQUEST PRR-05 (TAC NO. MF3680)  
JAMES A. FITZPATRICK NUCLEAR POWER PLANT- REQUEST FOR ADDITIONAL INFORMATION REGARDING 10 CFR 50.55a REQUEST PRR-05 (TAC NO. MF3680)


==Dear Mr. Coyle:==
==Dear Mr. Coyle:==
By letter dated February 21, 2014, Entergy Nuclear Operations, Inc., the licensee, requested an alternative to the requirements of the American Society of Mechanical Engineers Operation and Maintenance of Nuclear Power Plants Code related to testing of the residual heat removal pumps at the James A. FitzPatrick Nuclear Power Plant. The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). Based on our discussions we understand that a response to the RAI will be provided within 30 days of the date of this letter. Please contact me at (301) 415-1364 if you have any questions on this issue. Docket No. 50-333  
 
By letter dated February 21, 2014, Entergy Nuclear Operations, Inc., the licensee, requested an alternative to the requirements of the American Society of Mechanical Engineers Operation and Maintenance of Nuclear Power Plants Code related to testing of the residual heat removal pumps at the James A. FitzPatrick Nuclear Power Plant.
The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). Based on our discussions we understand that a response to the RAI will be provided within 30 days of the date of this letter.
Please contact me at (301) 415-1364 if you have any questions on this issue.
Sincerely,
                                              /RAJ Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333


==Enclosure:==
==Enclosure:==


Sincerely, /RAJ Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLICRidsNrrDor1Lpl1-1 LPL 1-1 Reading File RidsAcrsAcnw_MaiiCTR RidsRgn1 MaiiCenter RidsNrrPMFitzPatrick RidsNrrLAKGoldstein RidsNrrDoriDpr ABurritt, R 1 ADAMS ACCESSION NO.: ML14164A538 OFFICE LPL 1-1/PM LPL1-1/LA EPNB/BC NAME DPickett KGoldstein TLupold by email dated DATE 06/25/2014 06/24/2014 05/30/2014 OFFICIAL RECORD COPY LPL 1-1/BC BBeasley 07/2/2014}}
PUBLICRidsNrrDor1Lpl1-1       RidsNrrPMFitzPatrick LPL 1-1 Reading File           RidsNrrLAKGoldstein RidsAcrsAcnw_MaiiCTR           RidsNrrDoriDpr RidsRgn1 MaiiCenter           ABurritt, R 1 ADAMS ACCESSION NO.: ML14164A538 OFFICE         LPL 1-1/PM     LPL1-1/LA       EPNB/BC          LPL 1-1/BC NAME           DPickett       KGoldstein       TLupold by       BBeasley email dated DATE           06/25/2014     06/24/2014       05/30/2014       07/2/2014 OFFICIAL RECORD COPY}}

Latest revision as of 04:25, 4 November 2019

Request for Additional Information Regarding 10 CFR 50.55A Alternate Request PRR-05 (Tac No. MF3680)
ML14164A538
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 07/02/2014
From: Pickett D
Plant Licensing Branch 1
To: Coyle L
Entergy Nuclear Operations
Pickett D
References
TAC MF3680
Download: ML14164A538 (3)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 2, 2014 Mr. Lawrence Coyle Site Vice President Entergy Nuclear Operations, Inc.

James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT- REQUEST FOR ADDITIONAL INFORMATION REGARDING 10 CFR 50.55a REQUEST PRR-05 (TAC NO. MF3680)

Dear Mr. Coyle:

By letter dated February 21, 2014, Entergy Nuclear Operations, Inc., the licensee, requested an alternative to the requirements of the American Society of Mechanical Engineers Operation and Maintenance of Nuclear Power Plants Code related to testing of the residual heat removal pumps at the James A. FitzPatrick Nuclear Power Plant.

The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI}. Based on our discussions we understand that a response to the RAI will be provided within 30 days of the date of this letter.

Please contact me at (301) 415-1364 if you have any questions on this issue.

Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION ALTERNATE REQUEST PRR-05 ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333

Reference:

Letter from C.M. Adner of Entergy Nuclear Operations, Inc. to NRC, "James A. FitzPatrick Nuclear Power Plant lnservice Testing Program 10 CFR 50.55a Request PRR-05" dated February 21, 2014 (Agencywide Document Access and Management System (ADAMS)

Accession Number ML14057A553).

RAI PRR-05-1 Alternative request PRR-05 states that three vibration points are available from December of 1998 to present. However, Figures 12 through 20 in the submittal of PRR-005 do not contain data from the third vibration point (V3, axial direction) for pumps 1OP-38 and 1OP-3C. Please provide figures showing V3 (axial direction) as a function of time from December 1998 to present and a sample spectral analysis of the data measured in the V3 direction for pumps 1OP-38 and 1OP-3C.

RAI PRR-05-2 Alternative request PRR-05, under "Consultation - Pump Manufacturer I Vibration Expert,"

states that the pump vendor was contacted during the initial investigation of the cause for failed vibration acceptance criteria. Under "Basis for Code Alternative Alert Values," alternative request PRR-05 states that the basis for the 0.408 inches per second (ips) alert limit comes from the Technical Associates of Charlotte recommendations for vertical pumps. Is this recommendation applicable to all vertical pumps or were these recommendations developed specifically for residual heat removal (RHR) pumps 1OP-3A, 1OP-38, 1OP-3C, or 1OP-3D?

Please provide any comments the pump vendor had regarding the recommended vibration alert values.

RAI PRR-05-3 Alternative request PRR-05 proposes an alternative alert level for pumps 1OP-3A, 1OP-38, 1OP-3C, and 1OP-3D. To date, the ASME OM Code alert range value of 0.325 ips has been exceeded only on pumps 1OP-38 and 1OP-3C. Please provide justification on why the alternative request is necessary for RHR pumps 1OP-3A and 1OP-3D.

Enclosure

July 2, 2014 Mr. Lawrence Coyle Site Vice President Entergy Nuclear Operations, Inc.

James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT- REQUEST FOR ADDITIONAL INFORMATION REGARDING 10 CFR 50.55a REQUEST PRR-05 (TAC NO. MF3680)

Dear Mr. Coyle:

By letter dated February 21, 2014, Entergy Nuclear Operations, Inc., the licensee, requested an alternative to the requirements of the American Society of Mechanical Engineers Operation and Maintenance of Nuclear Power Plants Code related to testing of the residual heat removal pumps at the James A. FitzPatrick Nuclear Power Plant.

The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). Based on our discussions we understand that a response to the RAI will be provided within 30 days of the date of this letter.

Please contact me at (301) 415-1364 if you have any questions on this issue.

Sincerely,

/RAJ Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-333

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLICRidsNrrDor1Lpl1-1 RidsNrrPMFitzPatrick LPL 1-1 Reading File RidsNrrLAKGoldstein RidsAcrsAcnw_MaiiCTR RidsNrrDoriDpr RidsRgn1 MaiiCenter ABurritt, R 1 ADAMS ACCESSION NO.: ML14164A538 OFFICE LPL 1-1/PM LPL1-1/LA EPNB/BC LPL 1-1/BC NAME DPickett KGoldstein TLupold by BBeasley email dated DATE 06/25/2014 06/24/2014 05/30/2014 07/2/2014 OFFICIAL RECORD COPY

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