ML20212G989

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Forwards Current Draft Response to Ci 3.3.2.2-1 to Be Used as Example for OI Vs License Condition Vs Commitment Situation
ML20212G989
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 04/28/1999
From: Shaw D
BALTIMORE GAS & ELECTRIC CO.
To: Dave Solorio
NRC
Shared Package
ML20212G964 List:
References
NUDOCS 9909300181
Download: ML20212G989 (2)


Text

m M:td R Ges n # 4'e E;SGAmsLMlM94G%#6 4K9 4%$ @T46 P.01/01 April 28,1999 k.

To:

Dave Solorio Phone: 301-415-1973 Fax: 301-415-2279 From:.

Don Shaw Phone: 410-495-4028 Fax 410-495-6946 Pages:

1 (just this coverpage)

Comments:

Dave, To help us work through the OI vs License Condition vs Commitment situation, I have attached our current draft response to CI 3.3.3.2.2-1 as an example.
Thanks,

. Don cA m.. ear,1 - 133n 1 b

10 CFR Section 54.21(a)(3) requires that for each component subject to AMR, the applicant demonstrate that the effects of aging will be adequately managed. De staff concem pertains to how the applicant demonstrated that fatigue will be adequately managed for the safety injection (SI) piping. Section 5.15 of the LRA indicates that the applicant identified the potential for thermal stratification in the piping between the Si tank check valves and the loop inlet check valves. De LRA also indicates that the applicant will complete an engineering review of the industry task group reports regarding thermal stratification to determine whether $1 piping changes are necessary and to determine the impact of such changes on fatigue usage parameters used by the CCNPP fatigue monitoring program (FMP). In NRC Question Nc. 7.21, the staff asked that the applicant indicate whether the plans for the engineering review include reanalysis for thermal stratification and that the applicant describe the manner by which the time limited aging analysis (TLAA) for these fatigue analyses will satisfy the requirements of 10 CFR 54.21(c). De applicant responded that the engineering review of the SI piping between the Si tank check valves and the loop inlet check valves does include a reanalysis for thermal stratification.

De applicant further indicated that this review will determine if the components are bounded by other components in the FMP, and if they are not bounded, they will be added to the FMP. The applicant should discuss the results of the evaluation, identify additional locations added to the FMP, and describe the controlling transients and parameters monitored for the locations added to the FMP. The applicant should complete the thermal stratification analysis of the SI piping and modify the FMP as necessary.

h BGE's nuclear design engineering organization has a formal action item to complete the evaluation for these items. De current scheduled completion is mid 2003, with any changes to the FMP currently scheduled to be completed by the and of 2003.

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i NRC Staff Comments on Baltimore Gas and Electric Company's (BGE)

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