ML23292A214

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1 to Updated Final Safety Analysis Report, Questions and Responses 005.1 Through 005.6
ML23292A214
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 10/12/2023
From:
Susquehanna
To:
Office of Nuclear Reactor Regulation
Shared Package
ML23291A105 List: ... further results
References
PLA-8081
Download: ML23292A214 (1)


Text

SSES-FSAR QUESTION 005.1 The statement in Section 5.2.1.1 of the FSAR with regard to your compliance with 10 CFR Part 50, Section 50.55a, Codes and Standards Rule, is incorrect as a number of Quality Group A components within the reactor coolant pressure boundary are not in conformance with the applicable ASME Boiler and Pressure Vessel code and addenda as required by the rule.

In Amendment 13 to the Susquehanna Steam Electric Stations' FSAR and in your letter ER 100450, File 040-2, received by the Staff on March 1, 1974, you provided an analysis of anticipated deviations from the codes and standards rule requirements set forth in the provisions of Section 50.55a, 10 CFR Part 50, based on a Construction Permit Date of November 2, 1973, for the Susquehanna reactor pressure vessels, reactor recirculation piping, reactor recirculation system pumps, main steam line isolation valves, and main steam safety/relief valves. Based on this information and on certain additional commitments relative to the reactor pressure vessels, the AEC in a letter dated June 20, 1974, in accordance with paragraph 50.55a (a)(2)(ii), granted approval for relief from the rule for these components and acceptance of the ASME Section III Code and Addenda specified in Amendment 13 to the FSAR and letter ER 100450, File 040-2.

Revise Section 5.2.1.1. of the FSAR to correctly reflect the status of each Quality Group A component within the reactor coolant pressure boundary.

RESPONSE

For response see Subsection 5.2.1.1 and Table 5.2-10.

Rev. 46, 06/93 005.1-1

SSES-FSAR QUESTION 005.2 In Table 3.2-1 of the FSAR identify the applicable principal construction codes and standards in those cases where this information is now missing throughout the table.

RESPONSE

Table 3.2-1 has been revised to provide the requested information.

Rev. 46, 06/93 005.2-1

SSES-FSAR QUESTION 005.3 The B31.1 component code identified in Table 3.2-1 of the FSAR for the diesel lube oil system piping and valves is inconsistent with the Quality Group C (Safety Class 3) classification for these components. The diesel generator lubrication system piping is also identified in Section 9.5.7.1 of the FSAR as designed in accordance with ASME Section III, Class 3. Resolve this inconsistency and revise the FSAR as appropriate.

RESPONSE

Section 9.5.7.1 of the FSAR has been revised to resolve this inconsistency.

Rev. 51, 02/97 005.3-1

SSES-FSAR QUESTION 005.4 The quality group (safety class) classification, seismic classification, component code and quality assurance requirements for the components of the Emergency Service Water System have been omitted from Table 3.2-1. Revise Table 3.2-1 to include this information.

RESPONSE

Table 3.2-1 of the FSAR has been revised to include this information.

Rev. 46, 06/93 005.4-1

SSES-FSAR QUESTION 005.5 The quality group (safety class) classification, seismic classification, component code and quality assurance requirements for the spray pond system piping has been omitted from Table 3.2-1. Revise Table 3.2-1 to include this information.

RESPONSE

Table 3.2-1 of the FSAR has been revised to include this information.

Rev. 46, 06/93 005.5-1

SSES-FSAR QUESTION 005.6 Verify that all components within the reactor coolant pressure boundary as defined in 10 CFR Part 50.2(v) are classified Quality Group A in compliance with the Codes and Standards Rule, Section 50.55a of 10 CFR Part 50, or as a minimum, are classified Quality Group B if the components meet the exclusion requirements of the rule.

RESPONSE

Section 3.1.2.2.5 of the FSAR has been revised to resolve this concern.

Rev. 46, 06/93 005.6-1