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MONTHYEARML0515302522005-06-0202 June 2005 6/2/05, Diablo Canyon, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: RAI ML0603803682006-02-0909 February 2006 Request for Additional Information Response to Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized- Water Reactors. Project stage: RAI ML0923107632009-10-15015 October 2009 Request for Additional Information Regarding Supplemental Response to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: RAI ML1000501312010-01-11011 January 2010 Notice of Meeting with Pacific Gas and Electric Company to Discuss Diablo Canyon'S Planned Response to Request for Additional Information Supplemental Response to Generic Letter 2004-02 Project stage: RAI ML1003206952010-01-21021 January 2010 Draft Response to Second Round Request for Additional Information Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors. Project stage: Draft Request ML1003206882010-01-21021 January 2010 Draft RAI Responses to RAI Questions 5, 7.12 and New RAI 24 for Discussion Project stage: Draft Response to RAI ML1003501822010-02-0303 February 2010 Revised Request for Additional Information 24 Response from Licensee Project stage: Request ML1003501752010-02-0303 February 2010 E-mail from the Licensee Revised Response to RAI 24 Project stage: Response to RAI ML1002904292010-02-16016 February 2010 1/27/2010 Summary of Conference Call with Pacific Gas and Electric Company to Discuss Diablo Canyon Power Plant'S Planned Response to Request for Additional Information Supplemental Response to Generic Letter 2004-01 Project stage: RAI 2010-01-11
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Category:- No Document Type Applies
MONTHYEARML22278A2962022-10-0505 October 2022 FAQ 22-02- Diablo Canyon Scram - Final Approved ML22276A2402022-10-0303 October 2022 1) FAQ Response Provided by NEI ML22179A0302022-06-22022 June 2022 Plants 1 and 2 - Response to Public Questions Regarding Unit 1 Reactor Vessel Neutron Embrittlement Coupon Testing - June 28, 2022 ML22166A4442022-06-15015 June 2022 Plants 1 and 2 - Response to Public Questions Regarding Unit 1 Reactor Vessel Neutron Embrittlement Coupon Testing - June 15, 2022 ML22206A2602022-05-23023 May 2022 FAQ 22-02- Diablo Canyon Scram - Proposed ML22144A1442022-05-23023 May 2022 FAQ 22-02 - Diablo Canyon Scram ML21060B1842021-03-0101 March 2021 Enclosure 1 - 1-26-21 Diablo Canyon Renewal pre-app Meeting Attendee List ML20141L7102020-05-14014 May 2020 NRC-2019-000279 - Resp 4 - Interim, Agency Records Subject to the Request Are Enclosed. (Released Set of 2014-0488 3, Part 2 of 2) ML20141L7092020-05-14014 May 2020 NRC-2019-000279 - Resp 4 - Interim, Agency Records Subject to the Request Are Enclosed. (Released Set of 2014-0488 3, Part 1 of 2) ML20141L7142020-05-14014 May 2020 NRC-2019-000279 - Resp 4 - Interim, Agency Records Subject to the Request Are Enclosed. (Released Set of 2014-0488 5, Part 2 of 2) ML20141L7152020-05-14014 May 2020 NRC-2019-000279 - Resp 4 - Interim, Agency Records Subject to the Request Are Enclosed. (Released Set of 2014-0488, Parts 1 and 2) ML20141L7162020-05-14014 May 2020 NRC-2019-000279 - Resp 4 - Interim, Agency Records Subject to the Request Are Enclosed. (Released Set of 2015-0071, Part 1 of 2) ML20141L7132020-05-14014 May 2020 NRC-2019-000279 - Resp 4 - Interim, Agency Records Subject to the Request Are Enclosed. (Released Set of 2014-0488 5, Part 1 of 2) ML20141L7122020-05-14014 May 2020 NRC-2019-000279 - Resp 4 - Interim, Agency Records Subject to the Request Are Enclosed. (Released Set of 2014-0488 4, Part 2 of 2) ML20141L7112020-05-14014 May 2020 NRC-2019-000279 - Resp 4 - Interim, Agency Records Subject to the Request Are Enclosed. (Released Set of 2014-0488 4, Part 1 of 2) ML20141L7172020-05-14014 May 2020 NRC-2019-000279 - Resp 4 - Interim, Agency Records Subject to the Request Are Enclosed. (Released Set of 2015-0071, Part 2 of 2) ML20141L7182020-05-14014 May 2020 NRC-2019-000279 - Resp 4 - Interim, Agency Records Subject to the Request Are Enclosed. Released Set of New OE Docs (for NRC-2019-000279 Item 2) ML20262G9682020-03-19019 March 2020 Health Order 3.19.2020 ML16314A9642016-11-0909 November 2016 Summary of Hydrodynamic Effect in Spent Fuel Pool Auxiliary Building ML16314A9732016-11-0909 November 2016 Pacific Gas and Electric Company Checking Columns in Auxiliary Building Unit 1 for 7.5M Hosgri Vertical Acceleration ML16314D3162016-11-0909 November 2016 Comment Sheets ML16285A3232016-10-12012 October 2016 ROP PI Frequently Asked Questions (Faqs): 13-07 ML16179A2192016-06-27027 June 2016 LTR-16-0333-1 - Oedo Ticket - Edward D. Halpin, Senior Vice President, Generation and Chief Nuclear Officer, Pacific Gas and Electric Company, Letter Request to Suspend NRC Review of Diablo Canyon Power Plant License Renewal Application ML16084A6102016-03-30030 March 2016 MSFHI Tables 1&2 Final 3-24-2016 ML16054A0092016-02-12012 February 2016 FOIA/PA-2015-0294 - Resp 2 - Final, Agency Records Subject to the Request Are Enclosed. Part 8 of 8 ML16054A0072016-02-12012 February 2016 FOIA/PA-2015-0294 - Resp 2 - Final, Final Response #2, Records Already Publicly Available ML16054A0112016-02-12012 February 2016 FOIA/PA-2015-0294 - Resp 2 - Final, Agency Records Subject to the Request Are Enclosed. Part 3 of 8 ML16054A0142016-02-12012 February 2016 FOIA/PA-2015-0294 - Resp 2 - Final, Agency Records Subject to the Request Are Enclosed. Part 6 of 8 ML16054A0082016-02-12012 February 2016 FOIA/PA-2015-0294 - Resp 2 - Final, Agency Records Subject to the Request Are Enclosed. Part 1 of 8 ML16054A0152016-02-12012 February 2016 FOIA/PA-2015-0294 - Resp 2 - Final, Agency Records Subject to the Request Are Enclosed. Part 7 of 8 ML16054A0102016-02-12012 February 2016 FOIA/PA-2015-0294 - Resp 2 - Final, Agency Records Subject to the Request Are Enclosed. Part 2 of 8 ML16054A0122016-02-12012 February 2016 FOIA/PA-2015-0294 - Resp 2 - Final, Agency Records Subject to the Request Are Enclosed. Part 4 of 8 ML16054A0132016-02-12012 February 2016 FOIA/PA-2015-0294 - Resp 2 - Final, Agency Records Subject to the Request Are Enclosed. Part 5 of 8 ML15344A4322016-01-12012 January 2016 DCPP Section 106 Checklist ML15237A3352015-08-21021 August 2015 Attachment 3 - A.15-02-023 Supplemental Testimony of John Geesman ML15237A3342015-07-14014 July 2015 Attachment 1 - A.15-02-023 Prepared Testimony of John Geesman ML15237A3232015-07-14014 July 2015 Attachment 2 - A.15-02-023 Prepared Testimony of Sam Blakeslee ML15070A6082015-03-11011 March 2015 Response to NRC Request for Info. Pursuant to 10 CFR 50.54(f) Seismic Aspects of Recommendation 2.1 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident: Seismic Hazard Screening Report. Part 2 of 2 DCL-15-034, Final Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 Flooding. Part 2 of 22015-03-11011 March 2015 Final Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 Flooding. Part 2 of 2 ML15014A1602015-01-14014 January 2015 Attachment 2 - NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process ML15014A1532015-01-14014 January 2015 Attachment 1- NEI Comments on NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process ML14349A3872014-12-11011 December 2014 FOIA/PA-2014-0059 - Resp 2 - Final. Group C (Records Being Released in Part) ML14302A8062014-10-29029 October 2014 Enclosure - Ninety-Day Response to NRC Request for Additional Information - National Fire Protection Association Standard 805 ML13130A2282013-05-10010 May 2013 Safety Injection Issue Summary Pump 2-1 Issue Information DCL-13-021, Performance Demonstration Initiative (POI) Program Alternatives and Their Bases with Respect to ASME Code Section Xi, Appendix Viii Supplement 11 Requirements2013-03-0505 March 2013 Performance Demonstration Initiative (POI) Program Alternatives and Their Bases with Respect to ASME Code Section Xi, Appendix Viii Supplement 11 Requirements ML13078A2972013-03-0505 March 2013 Enclosure 1, Inservice Inspection (ISI) Relief Request REP-1 U2, Revision 2 in Accordance with 10 CFR 50.55a(a)(3)(i) ML13078A2932013-03-0505 March 2013 Performance Demonstration Initiative (POI) Program Alternatives and Their Bases with Respect to ASME Code Section Xi, Appendix Viii Supplement 11 Requirements DCL-12-119, Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.3 Seismic Unit 2, Part 2 of 32012-11-27027 November 2012 Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.3 Seismic Unit 2, Part 2 of 3 ML12333A2692012-11-27027 November 2012 Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.3 Seismic Unit 2, Part 3 of 3 ML12333A2662012-11-27027 November 2012 Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.3 Seismic Unit 1. Part 2 of 2 2022-06-22
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NRC RAI 24:
One additional question has arisen in the staffs review of other licensees submittals for GL 2004-02, and the staff requests that the Diablo Canyon licensee address it.
Specifically:
The potential for deaeration of the coolant as it passes through the debris bed should be considered. Please provide an evaluation of the potential for deaeration of the fluid as it passes through the debris bed and strainer and whether any entrained gasses could reach the pump suction. If detrained gasses can reach the pump suction, please evaluate whether pump performance could be affected as described in Appendix A of Regulatory Guide 1.82, Revision 3.
PG&E Response:
Deaeration is not expected to be a concern for the DCPP sump. Evaluation of the dissolved air content of the sump water can be evaluated using the solubility curves for nitrogen. From 167 to 212 degrees F at 400 psia, the dissolved gas fraction of nitrogen is 0.28 ml/g. At the same temperature and 100 psia, the value is 0.08 ml/g. Since the solubility relationship is effectively linear to 0 psia, the effective degassing of sump fluid is (0.28-0.08)/(400-100) = 0.00067 ml/gram of water per psi of pressure drop.
(Industrial And Engineering Chemistry, Volume 44)
The maximum screen pressure drop is 33 inches or 1.2 psid which provides the most conservative deaeration. Thus, assuming that the sump water is saturated at the elevated pressure and temperature conditions present inside containment at the start of recirculation, the total void fraction of the water flowing through the sump downstream of the sump screen would be 0.00067 ml/gram/psi X 1.2 psid = 0.0008, or 0.08 percent void fraction. The deaeration would manifest itself as microbubbles which do not have much buoyancy and would remain entrained in the flow and not accumulate in the sump structure.
As the void migrates down the RHR suction pipe, the hydrostatic pressure from the sump to the pump inlet (a 30 foot drop) will compress the entrained bubbles and further reduce the void fraction. NUREG/CR-2792, An Assessment of Residual Heat Removal and Containment Spray Pump Performance Under Air and Debris Ingesting Conditions, states that For a wide range of operating flow rates RHR and CS pumps should handle volumetric air quantities up to 2% with negligible degradation in performance. The void fraction of 0.08 percent established above is much less than the void fraction threshold of concern discussed in NRC Generic Letter (GL) 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.
NUREG/CR-2792 also recommends adjusting the NPSH requirement for the presence of air: The relationship recommended is NPSHR-air/water = NPSHR-water X (1 + 0.5 X Air Fraction). With a maximum void fraction of 0.08 percent, the increase factor for
NPSHR is 1 + 0.5 X 0.08 = 1.04. The 33-inch maximum head loss for the screen is when both RHR pumps running together at a total flowrate of 7,769 gpm. Under these conditions, each RHR pump is running at approximately 3,900 gpm. The NPSHR for these pumps at 3,900 gpm is 16 feet. With an adjustment factor of 1.04, the NPSHR under the deaeration conditions would be16 feet X 1.04 or 16.6 feet which is much less than the 24 feet of NPSHR assumed in the NPSH margin evaluation. Since the NPSHR used in the NPSH margin evaluation is very conservative, the impact due to deaeration as the as the sump fluid passes through the debris bed is considered negligible Any actions taken to address GL 2008-01 will be more than sufficient to address the concerns raised in this RAI. Therefore, deaeration across the sump screen does not present a challenge to the operation of the emergency core cooling system pumps.