ML100330039

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ME1819, RAIs from Eicb on LAR Changes to TS Requirements for Testing of the RHR (Shutdown Cooling Mode) System Containment Isolation Reactor Pressure - High Function
ML100330039
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 02/02/2010
From: Bhalchandra Vaidya
Plant Licensing Branch 1
To: Eugene Dorman, Joseph Pechacek
FitzPatrick
vaidya B, NRR/Dorl/lpl1-1, 415-3308
References
TAC ME1819
Download: ML100330039 (2)


Text

From: Vaidya, Bhalchandra Sent: Tuesday, February 02, 2010 7:27 AM To: 'Dorman, Eugene'; 'Pechacek, Joseph' Cc: Salgado, Nancy; Kemper, William; Garg, Hukam

Subject:

James A. FitzPatrick Nuclear Power Plant, ME1819, LAR - Request for Additional Information (EICB)

By application dated July 31, 2009, Entergy proposed license amendment to change James A Fitzpatrick Nuclear Power Plant, Technical Specifications (TSs). The proposed change revises the TS and associated Bases to modify the TS Surveillance Requirements (SR) for testing of the Residual Heat Removal System Shutdown Cooling (SDC) mode Containment Isolation, Reactor Pressure - High Function by replacing the current requirement to perform TS SR 3.3.6.1.3, perform channel calibration with TS SRs 3.3.6.1.1 perform channel check, 3.3.6.1.2, perform channel functional test, 3.3.6.1.4, calibrate the trip units, and 3.3.6.1.5, perform channel calibration. This change was needed to support the plant modification to increase the reliability of SDC isolation logic by changing the source of the reactor pressure high input signal.

The NRC Instrumentation and Controls Branch (EICB) has reviewed the submittals and has determined that the following additional information is needed to complete the review.

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(1) Provide the summary calculation for the new design employing inputs from the existing reactor steam dome pressure transmitters instead of the existing pressure switches.

The summary calculation should provide setpoint methodology and the basis for calculating design limit, limiting setpoint, nominal setpoint, allowable value, acceptable as found tolerance band, and acceptable as left band.

(2) Describe the measures to be taken to ensure that the associated instrument channel is capable of performing its specified safety functions in accordance with applicable design requirements and associated analysis. Include in your discussion information on the controls you employ to ensure that the as left trip setting after completion of periodic surveillance is consistent with your setpoint methodology. Also, discuss the plant corrective action processes (including plant procedures) for restoring channels to operable status when channels are determined to be inoperable or operable but degraded. If the controls are located in a document other than the TS (e.g., plant test procedure), describe how it is ensured that the controls will be implemented.

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Please contact me to setup a tele-conference to ascertain that you understand the request and also to obtain a firm commitment for the response to this request.

Thanks, Bhalchandra K. Vaidya Licensing Project Manager NRC/NRR/DORL/LPL1-1 (301)-415-3308 (O) bhalchandra.vaidya@nrc.gov E-mail Properties

Mail Envelope Properties ()

Subject:

James A. FitzPatrick Nuclear Power Plant, ME1819, LAR - Request for Additional Information (EICB)

Sent Date: 02/02/2010 6:54:20 AM Received Date: 02/02/2010 7:26:00 AM From: Vaidya, Bhalchandra Created By: Bhalchandra.Vaidya@nrc.gov Recipients:

EDorman@entergy.com ('Dorman, Eugene')

Tracking Status: None JPechac@entergy.com ('Pechacek, Joseph')

Tracking Status: None Nancy.Salgado@nrc.gov (Salgado, Nancy)

Tracking Status: None William.Kemper@nrc.gov (Kemper, William)

Tracking Status: None Hukam.Garg@nrc.gov (Garg, Hukam)

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 16531 02/02/2010 Options Expiration Date:

Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received: