ML110420278

Correction of Safety Evaluation Associated with Amendment No. 207 Regarding Technical Specification Conversion to ITS Format

ML110420278
Person / Time
Site:	Kewaunee
Issue date:	02/11/2011
From:	Feintuch K Plant Licensing Branch III
To:	Heacock D Dominion Energy Kewaunee
Feintuch K, NRR/DORL/LPL2-1, 415-3079
References
TAC ME2139
Download: ML110420278 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 11, 2011 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Energy Kewaunee, Inc.

Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

KEWAUNEE POWER STATION (KPS) - CORRECTION OF SAFETY EVALUATION ASSOCIATED WITH AMENDMENT NO. 207 REGARDING TECHNICAL SPECIFICATION CONVERSION (TAC NO. ME2139)

Dear Mr. Heacock:

On February 2, 2011, the Nuclear Regulatory Commission (NRC) staff issued Amendment No. 207 to Facility Operating License No. DPR-43 for KPS. The amendment converted the KPS Technical Specifications (TSs) to the Improved Technical Specifications format.

Subsequent to issuance, we noted that the safety evaluation (SE) associated with the amendment contains a number of typographical errors. Accordingly, for page 3-8, we are re-issuing a corrected page (enclosed). The correction of these typographical errors does not change the NRC staff's conclusion regarding Amendment No. 207.

As a reminder, the corrected information is directly related to compliance with the TS requirement 5.5.16, "Setpoint Control Program." Specifically, the corrections apply to the values of the Nominal Trip Setpoint (NTSP), As-Found Tolerance (AFT), and As-Left Tolerance (AL T) for the affected function(s). The NRC staff has not approved processing changes to KPS instrumentation setpoints under 10 CFR 50.59 using an approved setpoint methodology as described in Option B of TSTF-493. In accordance with TS 5.5.16.b. NRC approval using 10 CFR 50.90 is required to change the listed values of the NTSP, Allowable Value, AFT, and AL T (as applicable) for each Function described in Paragraph a of TS 5.5.16.

If you have any questions regarding this corrected page, please contact me at 301-415-3079.

Sincerely, Karl Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305

Enclosure:

Revised Page 3-8 as stated cc w/encl:

Distribution via ListServ

3-8 Steam Generator Water Level Low Low Trip/Auxiliary Feedwater Initiation:

AL: 0.0% Narrow Range (NR) Level AV: 4.087% NR Level L TSP: 4.496% NR Level AFT Limit: 15.88% NR Level NTSP: 17.0% NR Level AFT: +/- 1.12% Level ALT: +/- 0.5% Level Steam Generator Water Level High High:

AL:

100.00% NR Level AV: 92.486% NR Level L TSP: 92.077% NR Level AFT Limit: 67.62% NR Level NTSP: 66.50% NR Level AFT: +/- 1.12% NR Level ALT: +/- 0.50% NR Level Safeguards Bus Undervoltage (Loss of Voltage):

NTSP: 101.69 VAC (84.47% of bus voltage)

AFT: +/- 0.241 VAC (+/- 0.200% of bus voltage)

ALT: +/- 0.200 VAC (+/- 0.166% of bus voltage)

Time Delay NTSP: 1.75 seconds Time Delay AFT: +/- 0.25 seconds Time Delay ALT: +/- 0.10 seconds (Not credited in Safety Analysis)

Safeguards Bus Second Level Undervoltage (Degraded Voltage):

Analysis)

NTSP: 112.93 VAC (93.80% of bus voltage)

AFT: +/- 0.215 VAC (+/- 0.179% of bus voltage)

ALT: +/- 0.200 VAC (+/- 0.166% of bus voltage)

Time Delay NTSP: 6.72 seconds Time Delay AFT: +/- 0.68 seconds Time Delay ALT: +/- 0.10 seconds Forebay Level:

(Not credited in Safety Analysis)

(Not credited in Safety NTSP: 162" Water Level (equivalent to 566 feet 0" above sea level)

AFT: +/- 9" Water Level ALT: +/- 4.5" Water Level Containment Purge and Vent System Radiation Particulate Detector and Radioactive Gas Detector Containment Ventilation Isolation: (Not credited in Safety Analyses) (Not within scope of Setpoint Control Program)

NTSP: High Alarm setpoint is set conservative with respect to 2.2 E+5 Counts/Min +

Background, based on limits established in the Offsite Dose Calculation Manual AFT Limit: (2.2 E+5 Counts per minute + Background)

AL T Limit: 8.00E+4 Counts per minute Corrected by letter dated 2/11/2011

February 11, 2011 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Energy Kewaunee, Inc.

Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

KEWAUNEE POWER STATION (KPS) - CORRECTION OF SAFETY EVALUATION ASSOCIATED WITH AMENDMENT NO. 207 REGARDING TECHNICAL SPECIFICATION CONVERSION (TAC NO. ME2139)

Dear Mr. Heacock:

On February 2,2011, the Nuclear Regulatory Commission (NRC) staff issued Amendment No. 207 to Facility Operating License No. DPR-43 for KPS. The amendment converted the KPS Technical Specifications (TSs) to the Improved Technical Specifications format.

Subsequent to issuance, we noted that the safety evaluation (SE) associated with the amendment contains a number of typographical errors. Accordingly, for page 3-8, we are re-issuing a corrected page (enclosed). The correction of these typographical errors does not change the NRC staff's conclusion regarding Amendment No. 207.

As a reminder, the corrected information is directly related to compliance with the TS requirement 5.5.16, "Setpoint Control Program." Specifically, the corrections apply to the values of the Nominal Trip Setpoint (NTSP), As-Found Tolerance (AFT), and As-Left Tolerance (ALT) for the affected function(s). The NRC staff has not approved processing changes to KPS instrumentation setpoints under 10 CFR 50.59 using an approved setpoint methodology as described in Option B of TSTF-493.

In accordance with TS 5.5.16.b. NRC approval using 10 CFR 50.90 is required to change the listed values of the NTSP, Allowable Value, AFT, and AL T (as applicable) for each Function described in Paragraph a of TS 5.5.16.

If you have any questions regarding this corrected page, please contact me at 301-415-3079.

Sincerely, IRAJ Karl Feintuch, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305

Enclosure:

Revised Page 3-8 as stated cc w/encl: Distribution via ListServ DISTRIBUTION:

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