ML052200254

Request for Additional Information Regarding Relaxed Axial Offset Control, R. E. Ginna Nuclear Power Plant

ML052200254
Person / Time
Site:	Ginna
Issue date:	08/11/2005
From:	Milano P NRC/NRR/DLPM/LPD1
To:	Korsnick M Ginna
Milano P, NRR/DLPM , 415-1457
References
TAC MC6867
Download: ML052200254 (6)

Text

August 11, 2005 Mrs. Mary G. Korsnick Vice President R.E. Ginna Nuclear Power Plant R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING RELAXED AXIAL OFFSET CONTROL, R.E. GINNA NUCLEAR POWER PLANT (TAC NO. MC6867)

Dear Mrs. Korsnick:

By letter dated April 29, 2005, R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC), submitted an application to the Nuclear Regulatory Commission (NRC) requesting an amendment to the technical specifications for the R.E. Ginna Nuclear Power Plant. Specifically, the proposed amendment would allow the use of the relaxed axial offset control and the heat flux hot channel factor surveillance methodologies.

The NRC staff has reviewed the information supporting the proposed amendment and has determined that additional information is required in order for the staff to complete its review.

The specific questions are found in the enclosed request for additional information (RAI).

During a telephone call on August 10, 2005, the Ginna LLC staff indicated that a response to the RAI would be provided within 45 days.

Please contact me at (301) 415-1457 if you have any questions on this issue.

Sincerely,

/RA/

Patrick D. Milano, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244

Enclosure:

RAI cc w/encl: See next page

August 11, 2005 Mrs. Mary G. Korsnick Vice President R.E. Ginna Nuclear Power Plant R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING RELAXED AXIAL OFFSET CONTROL, R.E. GINNA NUCLEAR POWER PLANT (TAC NO. MC6867)

Dear Mrs. Korsnick:

By letter dated April 29, 2005, R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC), submitted an application to the Nuclear Regulatory Commission (NRC) requesting an amendment to the technical specifications for the R.E. Ginna Nuclear Power Plant. Specifically, the proposed amendment would allow the use of the relaxed axial offset control and the heat flux hot channel factor surveillance methodologies.

The NRC staff has reviewed the information supporting the proposed amendment and has determined that additional information is required in order for the staff to complete its review.

The specific questions are found in the enclosed request for additional information (RAI).

During a telephone call on August 10, 2005, the Ginna LLC staff indicated that a response to the RAI would be provided within 45 days.

Please contact me at (301) 415-1457 if you have any questions on this issue.

Sincerely,

/RA/

Patrick D. Milano, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244

Enclosure:

RAI cc w/encl: See next page DISTRIBUTION:

PUBLIC R. Laufer P. Milano OGC PDI-1 Reading File J. Nakoski S. Little ACRS DLPM DPR K. Wood J. Trapp, R-I Accession Number: ML052200254 OFFICE PDI-1/PM SRXB/SC PDI-1/LA PDI-1/SC NAME PMilano JNakoski MOBrien for SLittle JBoska for RLaufer DATE 08/11/05 07/27/05 08/11/05 08/11/05 OFFICIAL RECORD COPY

R.E. Ginna Nuclear Power Plant cc:

Mr. Michael J. Wallace President Ms. Thelma Wideman, Director R.E. Ginna Nuclear Power Plant, LLC Wayne County Emergency Management c/o Constellation Energy Office 750 East Pratt Street Wayne County Emergency Operations Baltimore, MD 21202 Center 7336 Route 31 Mr. John M. Heffley Lyons, NY 14489 Senior Vice President and Chief Nuclear Officer Ms. Mary Louise Meisenzahl Constellation Generation Group Administrator, Monroe County 1997 Annapolis Exchange Parkway Office of Emergency Preparedness Suite 500 1190 Scottsville Road, Suite 200 Annapolis, MD 21401 Rochester, NY 14624 Kenneth Kolaczyk, Sr. Resident Inspector Mr. Paul Eddy R.E. Ginna Nuclear Power Plant New York State Department of U.S. Nuclear Regulatory Commission Public Service 1503 Lake Road 3 Empire State Plaza, 10th Floor Ontario, NY 14519 Albany, NY 12223 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Peter R. Smith, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Carey W. Fleming, Esquire Senior Counsel - Nuclear Generation Constellation Generation Group, LLC 750 East Pratt Street, 17th Floor Baltimore, MD 21202 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271

REQUEST FOR ADDITIONAL INFORMATION REGARDING REVISED AXIAL OFFSET CONTROL R.E. GINNA NUCLEAR POWER PLANT, LLC R.E. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 In a letter dated April 29, 2005 (Agencywide Documents Access and Management System, Accession No. ML051300330), R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC), submitted an application for a proposed amendment to the technical specifications (TSs) for the R.E. Ginna Nuclear Power Plant to allow use of relaxed axial offset control (RAOC) and heat flux hot channel factor (FQ) methodologies in accordance with Westinghouse Report, WCAP-10216-P-A, Relaxation of Constant Axial Offset Control FQ Surveillance Technical Specification. The Nuclear Regulatory Commission (NRC) staff has the following questions regarding the information in the application.

1. Provide the results of the RAOC analysis (permissible axial flux differentials).

2. WCAP-10216-P-A delineates a calculational procedure for determining the final RAOC limit. In its review of the application, the NRC staff does not find evidence that the procedure was explicitly followed.

Provide a description of how the calculational procedure of WCAP-10216-P-A was followed. Justify any exceptions to the calculational procedure in WCAP-10216-P-A.

3. On page A-16 of WCAP-10216-P-A, under paragraph 2, FQ Analysis, it is stated, Each power shape generated in Section C.1, above is analyzed to determine if LOCA

[loss-of-coolant accident] constraints are met or exceeded. The peaking factor, FQT, is determined using standard synthesis methods as described in WCAP-8385 ...

However, in the application, Ginna LLC is deleting WCAP-8385 from the list of approved methodologies.

Identify the methodology that is the replacement for WCAP-8385. Provide the justification for that replacement.

4. Provide a description of the derivation of the f 1(I) and f2(I) functions.

5. Provide the results of the FQ analysis (i.e., the permissible FQ and the W(Z) function).

6. When establishing the FQ(Z) surveillance, WCAP-10216-P-A states that the measured FQ(Z) is increased by appropriate uncertainties to account for manufacturing tolerances and measurement uncertainties. WCAP-10216-P-A later states those uncertainties to be 3 percent and 5 percent, respectively. Ginna LLC has adopted these uncertainties as appropriate for its application.

Provide a description of how these uncertainties are appropriate for the licensee.

Enclosure

7. The proposed application for the RAOC/FQ surveillance requirements indicates that the supporting analysis was performed at extended power uprate (EPU) conditions. Ginna LLC has indicated that it intends to implement the RAOC/FQ surveillance changes regardless of the approval outcome of its EPU application. To that end, the April 29 application states in several locations that, ...supporting analyses performed for the EPU bounds operation at the current power level. However, there is no information provided to support this statement. In order to implement the EPU, Ginna LLC will be making a number of changes to its facility and analyses. Some of those changes could affect the analyses used to support the acceptability of the RAOC/FQ surveillance changes. It is the synergistic combination of these changes that has led Ginna LLC to determine that the RAOC/FQ surveillance changes were acceptable. Absent those synergistic effects, the analysis used to support the April 29 application may not bound the current conditions.

Provide a description of how the supporting analyses performed for the EPU bounds operation at the current power level. Include the following:

a. A complete listing of inputs, assumptions, and methodologies used in the analysis of the RAOC/FQ surveillance application.

b. Identify the current condition and the RAOC/FQ surveillance supporting analysis values for each, highlighting any differences.

c. Explain the impact of all differences. Include a justification as to why the RAOC/FQ surveillance application supporting analysis condition bounds the current condition,

d. Explain the impact should any change not be implemented where there was a difference between current conditions and RAOC/FQ surveillance application supporting analysis conditions.