ML093100484

Request for Additional Information Revisions to Loss-of-Power Diesel Generator Start Instrumentation Limiting Safety System Settings and Diesel Generator Load Test Value

ML093100484
Person / Time
Site:	Ginna
Issue date:	11/10/2009
From:	Pickett D Plant Licensing Branch 1
To:	John Carlin Ginna
Pickett D
References
TAC ME0291
Download: ML093100484 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. John T. Carlin Vice President RE. Ginna Nuclear Power Plant RE. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519 SUB"IECT: REQUEST FOR ADDITIONAL INFORMATION RE: REVISIONS TO LOSS-OF POWER DIESEL GENERATOR START INSTRUMENTATION LIMITING SAFETY SYSTEM SETTINGS AND DIESEL GENERATOR LOAD TEST VALUE (TAC NO. ME0291)

Dear Mr. Carlin:

By letter dated December 19,2008, as supplemented on January 22 and July 24,2009, RE.

Ginna Nuclear Power Plant, LLC submitted Technical Specification (TS) changes for the RE.

Ginna Nuclear Power Plant. The proposed changes would (1) correct an error in TS Table 3.3.2-1, "Engineered Safety Feature Actuation System Instrumentation," (2) revise the loss-of power diesel generator start instrumentation limiting safety system settings in Surveillance Requirement (SR) 3.3.4.2 of TS 3.3.4, "Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation," and (3) revise the diesel generator load test value in SR 3.8.1.3 of TS 3.8.1, "AC [Alternating Current] Sources - MODES 1, 2, 3, and 4."

The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided and has determined that additional information is needed to complete its review. Enclosed is the NRC staff's request for additional information (RAI). As discussed with your staff, we understand that you intend to respond to this RAI within 3 weeks of the date of this letter.

Please contact me at 301-415-1364 if you have any questions.

Sincerely,

.~ V ,~--.cL:rt Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244

Enclosure:

As stated cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION REVISIONS TO TECHNICAL SPECIFICATIONS LIMITING CONDITIONS FOR OPERATION 3.3.2, 3.3.4, AND 3.8.1 R.E. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 In response to Question #11c in the licensee's letter dated July 24,2009, it was stated that "Attachment 6 contains individual Diesel Loading Simulation results for A and B Diesel Generator in three different scenarios. For each diesel, a baseline (where the containment spray pump does not come on), a "most likely" and a "worst case scenario" are provided."

The NRC staff could not find the requisite response (voltage and frequency simulation) in of the licensee's submittal. Please provide analysis for the worst case voltage and frequency transients of the diesel generator, if a containment spray pump is started coincident with another large load, and compare the voltage and frequency variation limits to those recommended in Regulatory Guide 1.9.

Also, explain how the UV (undervoltage) relays provide the same level of UV protection when the loads are fed from onsite emergency diesel generator source.

Enclosure

November 10, 2009 Mr. John 1. Carlin Vice President RE. Ginna Nuclear Power Plant RE. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RE: REVISIONS TO LOSS-OF POWER DIESEL GENERATOR START INSTRUMENTATION LIMITING SAFETY SYSTEM SETTINGS AND DIESEL GENERATOR LOAD TEST VALUE (TAC NO. ME0291)

Dear Mr. Carlin:

By letter dated December 19, 2008, as supplemented on January 22 and July 24,2009, RE.

Ginna Nuclear Power Plant, LLC submitted Technical Specification (TS) changes for the RE.

Ginna Nuclear Power Plant. The proposed changes would (1) correct an error in TS Table 3.3.2-1, "Engineered Safety Feature Actuation System Instrumentation," (2) revise the loss-of power diesel generator start instrumentation limiting safety system settings in Surveillance Requirement (SR) 3.3.4.2 of TS 3.3.4, "Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation," and (3) revise the diesel generator load test value in SR 3.8.1.3 of TS 3.8.1, "AC [Alternating Current] Sources - MODES 1, 2, 3, and 4."

The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided and has determined that additional information is needed to complete its review. Enclosed is the NRC staff's request for additional information (RAI). As discussed with your staff, we understand that you intend to respond to this RAI within 3 weeks of the date of this letter.

Please contact me at 301-415-1364 if you have any questions.

Sincerely, IRA!

Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244

Enclosure:

As stated cc w/encl: Distribution via Listserv Distribution:

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