ML12233A726

Entergy Pre-Filed Evidentiary Hearing Exhibit ENT000553, Entergy, Condition Report LO-LAR-2011-00174, Corrective Actions (Aug. 2011)

ML12233A726
Person / Time
Site:	Indian Point
Issue date:	08/20/2012
From:	Caputo C Entergy Nuclear Operations
To:	Atomic Safety and Licensing Board Panel
SECY RAS
References
RAS 23331, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01, LO-LAR-2011-00174
Download: ML12233A726 (4)

Text

Entergy CONDITION REPORT I LO-LAR-2011-00174 Originator:

Caputo, Charles M Originator Site Group: IP2 Projects Staff IP2 Originator Phone: 6656 Operability Required:

N Reportability Required:

N Supervisor Name: Curry,John J Discovered Date: 08/18/2011 15:02 Condition

==

Description:==

Initiated Date: 08/18/2011 15 :07 This LAR will be used to track the commitments required to implement License Renewal and ensure the commited actions are accomplished prior to the committed dates Immediate Action

Description:

Open LAR to track LRA commitments Suggested Action

Description:

Initated corrective actions to implement programs and other changes to meet the License Renewal conditions Entergy I CORRECTIVE ACTION I LO-LAR-2011-00174 CA Number: 23 Site J ___ . __ G_rou.!..IIP

__ _____ -.J1 _____ N_a_m_e Assigned By: Projects Staff IP2 Assigned To: IP2 IP2 P&C Eng Codes Mgmt IP2 Caputo, Charles M Azevedo,Nelson F Subassigned To : Originated By: Caputo, Charles M Performed By: Azevedo,Nelson F Subperformed By: Approved By: Closed By: Caputo, Charles M Current Due Date: 09/28/2011 CA Type: NRC COMMITMENT Plant Constraint:

OTHER CA

Description:

NRC Commitment

1. 33 8/2112011 13:53:42 9/20/2011 12:22:11 9/2112011 06:53:32 Initial Due Date: 09/28/2011 At least 2 years prior to entering the period of extended operation, for the locations identified in LRA Table 4.3-13 (lP2) and LRA Table 4.3-14 (lP3), under the Fatigue Monitoring Program, IP2 and IP3 will implement one or more of the following:

(1) Consistent with the Fatigue Monitoring Program, Detection of Aging Effects, update the fatigue usage calculations using refined fatigue analyses to determine valid CUFs less than 1.0 when accounting for the effects of reactor water environment.

This includes applying the appropriate Fen factors to valid CUFs determined in accordance with one of the following:

1. For locations in LRA Table 4.3-13 (IP2) and LRA Table 4.3-14 (lP3), with existing fatigue analysis valid for the period of extended operation, use the existing CUF. 2. Additional plant-specific locations with a valid CUF may be evaluated.

In particular, the pressurizer lower shell will be reviewed to ensure the surge nozzle remains the limiting component.

3. Representative CUF values from other plants, adjusted to or enveloping the IPEC plant specific external loads may be used if demonstrated applicable to IPEC. 4. An analysis using an NRC-approved version of the ASME code or NRC-approved alternative (e.g., NRC-approved code case) may be performed to determine a valid CUF. (2) Consistent with the Fatigue Monitoring Program, Corrective Actions, repair or replace the affected locations before exceeding a CUF of 1.0. Response:

The analyses required by this CA have been completed with the results documented in WCAP-19199-P for IP2 and WCAP-19200-P for IP3. No other corrective actions are required at this time. Subresponse

Closure Comments:

Entergy I CORRECTIVE ACTION I LO-LAR-2011-00174 CA Number: 62 Site r< .. ", .. J Name ______ ..

____ _____ ....... Assigned By: Projects Staff IP2 Assigned To: IP2 IP2 P&C Eng Codes Mgmt IP2 Caputo, Charles M Azevedo,Nelson F Subassigned To : Originated By: Caputo, Charles M Performed By: Sub performed By: Approved By: Closed By: Current Due Date: 09/27/2013 CA Type: NRC COMMITMENT Plant Constraint:

OTHER CA

Description:

NRC Commitment

1. 43 8/23/2011 22:03:24 Initial Due Date: 09/28/2013 IPEC will review design basis ASME Code Class 1 fatigue evaluations to determine whether the NUREG/CR-6260 locations that have been evaluated for the effects of the reactor coolant environment on fatigue usage are the limiting locations for the IP2 and IP3 configurations.

If more limiting locations are identified, the most limiting location will be evaluated for the effects of the reactor coolant environment on fatigue usage. IPEC will use the NUREG/CR-6909 methodology in the evaluation of the limiting locations consisting of nickel alloy, ifany. Response:

Subresponse

Closure Comments:

Entergy I CORRECTIVE ACTION I LO-LAR-2011-00174 CA Number: 64 Site

.. I ____ _________ . ___ __

________ __________ Name Assigned By: Projects Staff IP2 Assigned To: IP2 IP2 P&C Eng Codes Mgmt IP2 Caputo, Charles M Azevedo,Nelson F Subassigned To : Originated By: Caputo, Charles M Performed By: Subperformed By: Approved By: Closed By: Current Due Date: 09/27/2013 CA Type: NRC COMMITMENT Plant Constraint:

OTHER CA

Description:

NRC Commitment

1. 45 8/23/201122:17:37 Initial Due Date: 09/28/2013 I) IPEC will not use the NB-3600 option ofthe WESTEMS program in future design calculations until the issues identified during the NRC review of the program have been resolved.

2) During the Period of Extended Operations IPEC will not use the NB-3600 option of the WESTEMS program Program documents shall be revised or generated that ensures the program will be maintained during the PEO before closing this corrective action. Response:

Subresponse

Closure Comments: