ML052930041

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Request for Additional Information Related to the Proposed Extended Power Uprate for Ginna Nuclear Power Plant
ML052930041
Person / Time
Site: Ginna 
(DPR-018)
Issue date: 10/25/2005
From: Steve Jones
Plant Systems Branch
To: Richard Laufer
NRC/NRR/DLPM/LPD1
HERNANDEZ R, NRR/DLPM/PDI-1 301-415-1079
References
TAC MC7382
Download: ML052930041 (4)


Text

October 25, 2005 MEMORANDUM TO: Richard J. Laufer, Section Chief Project Directorate I-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM:

Steven R. Jones, Acting Chief /RA/

Balance-of-Plant Section Plant Systems Branch Division of Systems Safety and Analysis

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED EXTENDED POWER UPRATE FOR GINNA NUCLEAR POWER PLANT (TAC NO. MC7382)

The attached request for additional information (RAI) relates to Rochester Gas &

Electric Corp. (the licensee) license amendment request dated May 7, 2005. The attached RAIs cover sections 2.5.4.1, 2.5.4.2, and 2.5.4.3 of the licensees submital and sections 2.5.4.4 and 2.5.4.5 will be included among our final round of RAIs that is scheduled to be completed by November 30, 2005.

Docket Nos.

50-244

Attachment:

As Stated CONTACT: R. Hernandez, NRR/DSSA/SPLB 415-1079

MEMORANDUM TO: Richard J. Laufer, Section Chief Project Directorate I-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM:

Steven R. Jones, Acting Chief Balance-of-Plant Section Plant Systems Branch Division of Systems Safety and Analysis

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROPOSED EXTENDED POWER UPRATE FOR GINNA NUCLEAR POWER PLANT (TAC NO MC7382)

The attached request for additional information (RAI) relates to Rochester Gas &

Electric Corp. (the licensee) license amendment request dated May 7, 2005. The attached RAIs cover sections 2.5.4.1, 2.5.4.2, and 2.5.4.3 of the licensees submital and sections 2.5.4.4 and 2.5.4.5 will be included among our final round of RAIs that is scheduled to be completed by November 30, 2005.

Docket Nos.

50-244

Attachment:

As Stated CONTACT: R. Hernandez, NRR/DSSA/SPLB 415-1079 DISTRIBUTION: ADAMS SPLB R/F SJones RHernandez PMilano ADAMS Accession Number: ML052930041 OFFICE SPLB:DSSA:NRR SC:SPLB:DSSA NAME RHernandez SJones DATE 10/25/05 10/25/05 OFFICIAL RECORD COPY

ATTACHMENT REQUEST FOR ADDITIONAL INFORMATION PLANT SYSTEMS BRANCH DIVISION OF SYSTEMS SAFETY AND ANALYSIS EXTENDED POWER UPRATE REQUEST GINNA NUCLEAR POWER PLANT DOCKET NOS. 50-244 (TAC. NOS. MC7382)

The NRC staff reviewed the licensees submittal and determined that additional information is required in order to complete the evaluation of the licensees proposed EPU.

2.5.4.1 Spent Fuel Pool Cooling System 1.

Because the alternate SFP makeup capability is not quite adequate for the worst-case boil-off rate of 52.8 gallons per minute, the Ginna Station EPU Licensing Report indicated that the off-load time can be delayed until the boil-off rate is reduced to less than 50 gallons per minute. Please confirm that the criteria in the TRM and in the UFSAR for performing normal and full core offloads will be revised to include verification that both the normal and the alternate SFP makeup capability will exceed the maximum SFP boil-off rate that could occur should there be a complete loss of SFP cooling.

2.

The evaluation discussed in the Ginna Station EPU Licensing Report is based on the worst-case decay heat load that is generated from 1321 fuel assemblies. Ginna TS 4.3.3 currently permits up to 1879 fuel assemblies to be stored in the SFP. Explain why the worst-case decay heat load analysis is not consistent with the current TS.

2.5.4.2 Service Water System 1.

Please confirm that the results of heat exchanger performance monitoring per GL 89-13 recommendations demonstrate acceptable performance for EPU conditions.

2.5.4.3 Component Cooling Water System 1.

The Ginna EPU Licensing Report indicates that administrative controls will be used to limit the CCW outlet temperature from the residual heat removal (RHR) heat exchangers during normal plant cooldown evolutions following EPU operation to 170 EF.

Please explain why it is necessary to impose this new temperature limit for EPU operation and discuss how it will be implemented and managed.

2.

Please explain what impact the proposed EPU will have on the flow-induced vibration considerations discussed in Section 9.2.2.4.1.6 of the Ginna UFSAR, including a discussion of any additional limitations that must be relied upon.

3.

Section 9.2.2.4.3 of the Ginna UFSAR indicates that following a LOCA, one CCW pump and one CCW heat exchanger are capable of accommodating the heat loads. However, the Ginna EPU Licensing Report indicates that both CCW heat exchangers are relied upon for decay heat removal during the recirculation mode following a LOCA. Please explain this apparent inconsistency.

2 4.

Please explain what impact the proposed EPU will have on the capability of the CCWS to cool the plant to cold shutdown conditions within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in accordance with Appendix R requirements as described in Section 9.2.2.4.3 of the Ginna UFSAR.