ML15055A181: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 31: Line 31:
  "The TVA Model is a mass and energy balance model that includes mass and energy inputs to the Reactor Pressure Vessel (RPV) from injection sources and decay heat and transfer of energy from the RPV to the suppression pool via the Safety Relief Valves (SRVs). The computer code solves the mass and energy balance for the Suppression Pool andRPV. The developed code allows for various operating parameters to be entered. The code takes these inputs and performs an integration of several mass, temperature, and pressure differential equations. The output is the results of these differential equations."
  "The TVA Model is a mass and energy balance model that includes mass and energy inputs to the Reactor Pressure Vessel (RPV) from injection sources and decay heat and transfer of energy from the RPV to the suppression pool via the Safety Relief Valves (SRVs). The computer code solves the mass and energy balance for the Suppression Pool andRPV. The developed code allows for various operating parameters to be entered. The code takes these inputs and performs an integration of several mass, temperature, and pressure differential equations. The output is the results of these differential equations."
Please provide response to item (A)1 through (A)7 below OR item (B).
Please provide response to item (A)1 through (A)7 below OR item (B).
  (A) The following information is requested regarding the TVA Model in order for the NRC staff to review its specific application for determining the NFPA 805 Case 3 long term suppression pool temperature response.  
(A) The following information is requested regarding the TVA Model in order for the NRC staff to review its specific application for determining the NFPA 805 Case 3 long term suppression pool temperature response.
: 1. Confirm that the TVA Model is qualified to the requirements of 10 CFR Part 50 Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants" with error reporting in accordance with 10 CFR Part 21, "Reporting of Defects and Noncompliance"  
: 1. Confirm that the TVA Model is qualified to the requirements of 10 CFR Part 50 Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants" with error reporting in accordance with 10 CFR Part 21, "Reporting of Defects and Noncompliance"
: 22. Provide technical justification for using TVA Model instead of SHEX model for determining the NFPA 805 Case 3 suppression pool temperature response  
: 22. Provide technical justification for using TVA Model instead of SHEX model for determining the NFPA 805 Case 3 suppression pool temperature response
: 3. Sources of mass and sources of energy input for NFPA Case 3 in the TVA Model  
: 3. Sources of mass and sources of energy input for NFPA Case 3 in the TVA Model
: 4. Decay heat model used in the TVA Model  
: 4. Decay heat model used in the TVA Model
: 5. Assumptions used for NFPA 805 Case 3 in the TVA Model and comparison with the assumptions in SHEX long term suppression pool temperature response analysis for analyzing NFPA 805 Cases 1  
: 5. Assumptions used for NFPA 805 Case 3 in the TVA Model and comparison with the assumptions in SHEX long term suppression pool temperature response analysis for analyzing NFPA 805 Cases 1  


and 2  6. Inputs used for NFPA 805 Case 3 in the TVA Model and comparison with the inputs in SHEX long term suppression pool temperature response analysis for analyzing NFPA 805 Cases 1 and 2  
and 2  6. Inputs used for NFPA 805 Case 3 in the TVA Model and comparison with the inputs in SHEX long term suppression pool temperature response analysis for analyzing NFPA 805 Cases 1 and 2
: 7. Explain how the Adder 5.9 oF, given in response to SCVB-RAI-12(b), for the change in suppression pool temperature was calculated (B) Perform the NFPA 805 Case 3 analysis using General Electric-Hitachi Super Hex (SHEX) code using the same inputs and assumptions as in Case 1 and Case 2, Residual Heat Removal (RHR) heat exchanger k- factor of 270 BTU/sec-°F, and RHR Service Water (RHRSW) initiation time 2 hours. Provide results of peak suppression pool temperature, minimum Net Positive Suction Head (NPSH) available (NPSHa), and the margin between the NPSHa and NPSH required (NPSHr).
: 7. Explain how the Adder 5.9 oF, given in response to SCVB-RAI-12(b), for the change in suppression pool temperature was calculated (B) Perform the NFPA 805 Case 3 analysis using General Electric-Hitachi Super Hex (SHEX) code using the same inputs and assumptions as in Case 1 and Case 2, Residual Heat Removal (RHR) heat exchanger k- factor of 270 BTU/sec-°F, and RHR Service Water (RHRSW) initiation time 2 hours. Provide results of peak suppression pool temperature, minimum Net Positive Suction Head (NPSH) available (NPSHa), and the margin between the NPSHa and NPSH required (NPSHr).
REFERENCE  1. Letter from TVA to NRC dated December 17, 2014, "Response to NRC Request for Additional Information Regarding the License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Plant, Units 1, 2, and 3 (TAC Nos. MF1185, MF1186, and MF1187) - Probabilistic Risk Assessment Follow Up (162-Day Responses)", (ADAMS Accession No. ML14363A056).
REFERENCE  1. Letter from TVA to NRC dated December 17, 2014, "Response to NRC Request for Additional Information Regarding the License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Plant, Units 1, 2, and 3 (TAC Nos. MF1185, MF1186, and MF1187) - Probabilistic Risk Assessment Follow Up (162-Day Responses)", (ADAMS Accession No. ML14363A056).

Revision as of 00:08, 28 April 2019

Follow Up RAI Regarding Attachment X of NFPA 805 LAR
ML15055A181
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 02/21/2015
From: Saba F E
Plant Licensing Branch II
To: Williams G R
Tennessee Valley Authority
References
Download: ML15055A181 (3)


Text

1 NRR-PMDAPEm Resource From: Saba, Farideh Sent: Saturday, February 21, 2015 4:06 PM To: Williams, Gordon Robert (grwilliams1@tva.gov)

Cc: Schrull, Edward Dustin (edschrull@tva.gov);

Green, Kimberly; Sallman, Ahsan; Miller, Barry; Helton, Shana

Subject:

Follow up RAI regarding Attachment X of NFPA 805 LAR Importance:

HighHi Gordon, The NRC staff has reviewed the response to SCVB-RAI-12 in licensee's letter dated December 17, 2014 (ADAMS Accession No. ML14363A056). In order for the staff to complete its review, response to the follow up RAI number SCVB-RAI-13, below, is requested.

In accordance with NRC policy, the incoming documents were checked for the presence of proprietary material, and no information marked proprietary was identified in the follow up RAI.

Draft follow up RAI was emailed to you on January 21, 2015. You have informed me that you do not request a clarification call. I also agreed with your proposed response date of March 27, 2015.

REQUEST FOR ADDITIONAL INFORMATION - Round 3 BY CONTAINMENT AND VENTILATION BRANCH REVIEW OF NFPA 805 TRANSITI ON REPORT ATTACHMENT X BROWNS FERRY UNITS 1, 2, & 3 DOCKET NOS. 50-259, 50-260, & 50-296

SCVB-RAI-13

Refer to response to SCVB-RAI-12(c) in Reference 1 that states:

"The TVA Model is a mass and energy balance model that includes mass and energy inputs to the Reactor Pressure Vessel (RPV) from injection sources and decay heat and transfer of energy from the RPV to the suppression pool via the Safety Relief Valves (SRVs). The computer code solves the mass and energy balance for the Suppression Pool andRPV. The developed code allows for various operating parameters to be entered. The code takes these inputs and performs an integration of several mass, temperature, and pressure differential equations. The output is the results of these differential equations."

Please provide response to item (A)1 through (A)7 below OR item (B).

(A) The following information is requested regarding the TVA Model in order for the NRC staff to review its specific application for determining the NFPA 805 Case 3 long term suppression pool temperature response.

1. Confirm that the TVA Model is qualified to the requirements of 10 CFR Part 50 Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants" with error reporting in accordance with 10 CFR Part 21, "Reporting of Defects and Noncompliance"
22. Provide technical justification for using TVA Model instead of SHEX model for determining the NFPA 805 Case 3 suppression pool temperature response
3. Sources of mass and sources of energy input for NFPA Case 3 in the TVA Model
4. Decay heat model used in the TVA Model
5. Assumptions used for NFPA 805 Case 3 in the TVA Model and comparison with the assumptions in SHEX long term suppression pool temperature response analysis for analyzing NFPA 805 Cases 1

and 2 6. Inputs used for NFPA 805 Case 3 in the TVA Model and comparison with the inputs in SHEX long term suppression pool temperature response analysis for analyzing NFPA 805 Cases 1 and 2

7. Explain how the Adder 5.9 oF, given in response to SCVB-RAI-12(b), for the change in suppression pool temperature was calculated (B) Perform the NFPA 805 Case 3 analysis using General Electric-Hitachi Super Hex (SHEX) code using the same inputs and assumptions as in Case 1 and Case 2, Residual Heat Removal (RHR) heat exchanger k- factor of 270 BTU/sec-°F, and RHR Service Water (RHRSW) initiation time 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Provide results of peak suppression pool temperature, minimum Net Positive Suction Head (NPSH) available (NPSHa), and the margin between the NPSHa and NPSH required (NPSHr).

REFERENCE 1. Letter from TVA to NRC dated December 17, 2014, "Response to NRC Request for Additional Information Regarding the License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Plant, Units 1, 2, and 3 (TAC Nos. MF1185, MF1186, and MF1187) - Probabilistic Risk Assessment Follow Up (162-Day Responses)", (ADAMS Accession No. ML14363A056).

Thanks, Farideh Farideh E. Saba, P.E.

Senior Project Manager NRC/ADRO/NRR/DORL 301-415-1447 Mail Stop O-8G9A Farideh.Saba@NRC.GOV

Hearing Identifier: NRR_PMDA Email Number: 1891 Mail Envelope Properties (36CF286628C20846A68047F2463233090141FFBC09C5)

Subject:

Follow up RAI regarding Attachment X of NFPA 805 LAR Sent Date: 2/21/2015 4:05:31 PM Received Date: 2/21/2015 4:05:00 PM From: Saba, Farideh Created By: Farideh.Saba@nrc.gov Recipients: "Schrull, Edward Dustin (edschrull@tva.gov)" <edschrull@tva.gov> Tracking Status: None "Green, Kimberly" <Kimberly.Green@nrc.gov>

Tracking Status: None "Sallman, Ahsan" <Ahsan.Sallman@nrc.gov> Tracking Status: None "Miller, Barry" <Barry.Miller@nrc.gov> Tracking Status: None "Helton, Shana" <Shana.Helton@nrc.gov> Tracking Status: None "Williams, Gordon Robert (grwilliams1@tva.gov)" <grwilliams1@tva.gov> Tracking Status: None

Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 4231 2/21/2015 4:05:00 PM

Options Priority: High Return Notification: No Reply Requested: Yes Sensitivity: Normal Expiration Date: Recipients Received: