ML110840267: Difference between revisions

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| document type = E-Mail, Request for Additional Information (RAI)
| document type = E-Mail, Request for Additional Information (RAI)
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| stage = RAI
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's RAI response letter dated March 9, 2011, Figure 1, the Modified Technical Specification (TS) Bases 3/4.4.9, states that WCAP-14040-NP-A, Rev. 2, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Curves
's RAI response letter dated March 9, 2011, Figure 1, the Modified Technical Specification (TS) Bases 3/4.4.9, states that WCAP-14040-NP-A, Rev. 2, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Curves
" is one of the methodologies used to evaluate the fracture toughness properties and to determine the allowable pressure-temperature relationships. However, in the response to CVIB-1.4-b, the methodology of WCAP-14040-NP-A, Rev. 4 is referenced with respect to the determination of the coolant-to-crack tip temperature differential. In addition, during the conference call on January 26, 2011, the licensee identified that the methodology used to generate the P-T limits was the same as that described in WCAP-15092, Rev. 3, which incorporates the provisions of Code Case N-588. WCAP-14040-NP-A, Rev. 2 does not incorporate the Code Case N-588 provisions, but WCAP-14040-NP-A, Rev. 4, incorporates the provisions of Code Case N-588.
" is one of the methodologies used to evaluate the fracture toughness properties and to determine the allowable pressure-temperature relationships. However, in the response to CVIB-1.4-b, the methodology of WCAP-14040-NP-A, Rev. 4 is referenced with respect to the determination of the coolant-to-crack tip temperature differential. In addition, during the conference call on January 26, 2011, the licensee identified that the methodology used to generate the P-T limits was the same as that described in WCAP-15092, Rev. 3, which incorporates the provisions of Code Case N-588. WCAP-14040-NP-A, Rev. 2 does not incorporate the Code Case N-588 provisions, but WCAP-14040-NP-A, Rev. 4, incorporates the provisions of Code Case N-588.
The Nuclear Regulatory Commission staff therefore requests the licensee to:  
The Nuclear Regulatory Commission staff therefore requests the licensee to:
: 1. Clarify which revision of WCAP-14040-NP-A is used as the basis for the P-T limit calculations for Turkey Point Units 3 and 4, (Rev. 2, Rev. 4, or a combination of both) and correct the TS bases as necessary.  
: 1. Clarify which revision of WCAP-14040-NP-A is used as the basis for the P-T limit calculations for Turkey Point Units 3 and 4, (Rev. 2, Rev. 4, or a combination of both) and correct the TS bases as necessary.
: 2. Confirm that the provisions of Code Case N-588 were used in the development of the P-T limits for Turkey Point, Units 3 and 4.
: 2. Confirm that the provisions of Code Case N-588 were used in the development of the P-T limits for Turkey Point, Units 3 and 4.
Jason Paige, Turkey Point Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: (301) 415-5888}}
Jason Paige, Turkey Point Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: (301) 415-5888}}

Revision as of 17:04, 30 April 2019

E-mail, EPU Regarding Vessels and Internals Integrity (Cvib) Requests for Additional Information - Round 2
ML110840267
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 03/25/2011
From: Paige J C
Plant Licensing Branch II
To: Abbatiello T
Florida Power & Light Co
Paige, Jason C, NRR/DORL,301-415-5888
References
Download: ML110840267 (1)
v • d • e


Text

From: Paige, Jason Sent: Friday, March 25, 2011 10:14 AM To: Abbatiello, Tom Cc: Abbott, Liz; Tiemann, Philip; Tomonto, Bob; Hanek, Olga; Hoffman, Jack

Subject:

Turkey Point EPU - Vessels and Internals Integrity (CVIB) Requests for Additional Information - Round 2 Tom, Below are requests for additional information (RAIs) regarding the Turkey Point extended power uprate license amendment request. On March 25, 2011, you stated that a call is not needed to discuss the draft RAIs sent to you via email. The below RAIs reflect the questions that were sent to you and agreed upon by Florida Power & Light Company (FPL). FPL agreed upon providing its responses within 30 days of the date of this email. If you have any questions, feel free to contact me.

CVIB-2.1 In the licensee

's RAI response letter dated March 9, 2011, Figure 1, the Modified Technical Specification (TS) Bases 3/4.4.9, states that WCAP-14040-NP-A, Rev. 2, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Curves

" is one of the methodologies used to evaluate the fracture toughness properties and to determine the allowable pressure-temperature relationships. However, in the response to CVIB-1.4-b, the methodology of WCAP-14040-NP-A, Rev. 4 is referenced with respect to the determination of the coolant-to-crack tip temperature differential. In addition, during the conference call on January 26, 2011, the licensee identified that the methodology used to generate the P-T limits was the same as that described in WCAP-15092, Rev. 3, which incorporates the provisions of Code Case N-588. WCAP-14040-NP-A, Rev. 2 does not incorporate the Code Case N-588 provisions, but WCAP-14040-NP-A, Rev. 4, incorporates the provisions of Code Case N-588.

The Nuclear Regulatory Commission staff therefore requests the licensee to:

1. Clarify which revision of WCAP-14040-NP-A is used as the basis for the P-T limit calculations for Turkey Point Units 3 and 4, (Rev. 2, Rev. 4, or a combination of both) and correct the TS bases as necessary.
2. Confirm that the provisions of Code Case N-588 were used in the development of the P-T limits for Turkey Point, Units 3 and 4.

Jason Paige, Turkey Point Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: (301) 415-5888

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