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MONTHYEARML0927304682009-09-28028 September 2009 Proposed License Amendment Request, TS 3.7.12 - ECCS Pump Room Exhaust Air Cleanup System (Preacs) Addition of Conditions/Action Statements Project stage: Request ML0930106062009-10-28028 October 2009 ECCS Pump Room Exhaust Air Cleanup System (Preacs). TS 3.7.12 - Acceptance for Review-TAC ME2413 and ME2414 Project stage: Acceptance Review ML1007003882010-03-11011 March 2010 Request for Additional Information #1, Regarding the License Amendment ECCS Room Exhaust Air Cleanup System (Preacs) TS 3.7.12 Project stage: RAI ML1009900882010-04-0808 April 2010 Response to Request for Additional Information Proposed License Amendment Request TS 3.7.12 - ECCS Pump Room Exhaust Air Cleanup System (Preacs) Addition of Conditions/Action Statements Project stage: Response to RAI ML1011601352010-04-26026 April 2010 E-mail Request for Additional Information #2 Regarding the License Amendment, North Anna, Unit 1 and 2, ECCS Pump Room Exhaust Air Cleanup System TS 3.7.12 Project stage: RAI ML1021800692010-07-0606 July 2010 Response to Precas Clarification Concerns from Phone Call Project stage: Request ML1025716272010-11-0101 November 2010 Issuance of Amendments 260 & 241 Regarding Change to Technical Specification (TS) 3.7.12, Emergency Core Cooling System (ECCS) Pump Room Exhaust Air Cleanup System (Preacs) Project stage: Approval ML1117300702011-06-15015 June 2011 Ny State Plants-ME4212, ME4213, ME4214, ME4267, and ME4330, ME4331, ME4332-NY State Comments on LARs for Cyber Security Plans for Nine Mile Point, Ginna, FitzPatrick, and Indian Point Plants Project stage: Other 2010-03-11
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Category:E-Mail
MONTHYEARML24107A9112024-04-15015 April 2024 NRC to Fws, Follow-up on Request for Concurrence for North Anna SLR ML24107A9122024-04-11011 April 2024 Fws to NRC, Follow-up on Request for Concurrence for North Anna SLR ML24087A0102024-03-26026 March 2024 NRR E-mail Capture - Verbal Relief for North Anna Unit 1 - (ASME Code), Section XI, Subsection IWB-2430 ML24087A0112024-03-23023 March 2024 NRR E-mail Capture - Draft RAIs for Reactor Coolant Pump (RCP) Relief Request (L-2024-LLR-0022) ML24107B1562024-02-20020 February 2024 Cherokee Nation E.Toombs Na Removal Request ML24044A2462024-02-0606 February 2024 001 Radiation Safety Baseline Inspection Information Request ML23320A1122024-01-18018 January 2024 NRC to Fws, Concurrence with Endangered Species Act Determinations for North Anna Power Station, Units 1 and 2, Subsequent License Renewal, Issuance of Draft Supplemental Environmental Impact Statement, and Opportunity for Public Comment ML23355A2722023-12-21021 December 2023 NRR E-mail Capture - Schedule Revision for Emergency Preparedness Staff Augmentation Times License Amendment Request ML23318A1172023-11-13013 November 2023 NRR E-mail Capture - Formal Issuance of RAIs for North Anna Technical Support Center (TSC) License Amendment Request (LAR) (L-2023-LLA-0006) ML23257A2092023-09-14014 September 2023 NRR E-mail Capture - Formal Issuance of 2nd Round RAIs for Surry Units 1&2 and North Anna Units 1&2 Emergency Plans LAR ML23243A9862023-08-31031 August 2023 NRR E-mail Capture - Draft RAIs for EP Staff Augmentation Times LAR (L-2022-LLA-0166) ML23219A1602023-08-0707 August 2023 003 Radiation Safety Baseline Inspection Information Request ML23171B0522023-06-20020 June 2023 NRR E-mail Capture - RAI for Review of Appendix F to DOM-NAF-2-P (Redacted) ML23075A0232023-03-15015 March 2023 NRR E-mail Capture - RAI - License Amend Req (LAR) to Revise Tech Spec (Ts) 3.6.8 Limiting Condition for Operation to Remove Refueling Water Chemical Addition Tank and Replace the Containment Sump Buffer North Anna, 1 and 2 (L-2022-LLA-0162 ML23067A2162023-03-0707 March 2023 NRR E-mail Capture - RAI for North Anna, 1 & 2, Surry 1 & 2, Millstone, 2 & 3, Request for Approval of App. F Fleet Report DOM-NAF-2-P, Qual of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion VIPRE-D Computer Code ML23060A0932023-03-0101 March 2023 NRR E-mail Capture - Formal Issuance of RAIs for Surry/North Anna Emergency Plans LAR ML23059A2282023-02-28028 February 2023 NRR E-mail Capture - Draft RAIs for Containment Buffer Change to Natb (L-2022-LLA-0162) ML23039A1712023-02-0808 February 2023 NRR E-mail Capture - Acceptance Review for Technical Support Center (TSC) Relocation (L-2023-LLA-0006) ML23018A0352023-01-17017 January 2023 NRR E-mail Capture - Acceptance Review for Fleet Report Re Appendix F of DOM-NAF-2-P (L-2022-LLT-0003) ML22342B1472022-12-0808 December 2022 NRR E-mail Capture - Acceptance Review for LAR Re NAPS Post LOCA Buffer Change (L-2022-LLA-0162) ML22335A4842022-12-0101 December 2022 NRR E-mail Capture - Acceptance Review for LAR North Anna Power Station - Units 1 and 2 and Surry Power Station - Units 1 and 2 Emergency Plan Staff Augmentation Times (L-2022-LLA-0166) ML22242A0452022-08-23023 August 2022 NRR E-mail Capture - Dominion GL 04-02 Response Draft RAIs (L-2017-LRC-0000) ML22174A3552022-06-23023 June 2022 NRR E-mail Capture - Acceptance Review for Dominion Fleet LAR to Implement TSTF-554 (L-2022-LLA-0078) ML22104A0252022-04-14014 April 2022 NRR E-mail Capture - Dominion Presentation Slides for April 21, 2022 Public Meeting on Emergency Preparedness Submittal for the North Anna Power Station and the Surry Power Station ML22083A2102022-03-24024 March 2022 NRR E-mail Capture - Draft RAI - Relief Request N2-14-LMT-003 Fourth Ten Year Inservice Inspection Interval ML22032A0962022-02-0101 February 2022 002 Radiation Safety Baseline Inspection Information Request ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22007A2672022-01-0707 January 2022 NRR E-mail Capture - North Anna, Unit 2, ASME Section XI Inservice Inspection Program Relief Request N2-14-LMT-003 Fourth Interval Third Period Limited Examinations (L-2021-LLR-0088) ML21335A0812021-12-0101 December 2021 NRR E-mail Capture - Acceptance Review for OMN-28 Request Alternative to ISTC-3700, Position Verification Testing (L-2021-LLR-0086) ML21334A1922021-11-30030 November 2021 NRR E-mail Capture - Audit Plan for Reactor Core Thermal-Hydraulics Using the VIPRE-D Appendix E Review ML21327A3652021-11-23023 November 2021 NRR E-mail Capture - Draft RAI for TSTF-577 LAR ML21326A1502021-11-22022 November 2021 NRR E-mail Capture - Acceptance Review for Relocation of Unit Staff Requirements to the QAPD LAR (L-2021-LLA-0195) ML21322A0962021-11-18018 November 2021 Final Request for Additional Information Set 5 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21312A0082021-11-0404 November 2021 Enclosure 2 - NAPS Draft SER Table A.1-1 Markup ML21312A0012021-11-0404 November 2021 Comments on North Anna Draft SER ML21312A0112021-11-0404 November 2021 Enclosure 3 - NAPS Draft SER Section 3 Comments ML21306A3302021-11-0202 November 2021 NRR E-mail Capture - Acceptance Review for TSTF-569 LAR ML21286A7372021-10-13013 October 2021 Additional Element Included in the Implementation Plan for the Surry Fuel Melt Safety Limit (SL) LAR ML21274A0022021-09-30030 September 2021 NRR E-mail Capture - Acceptance Review for TSTF-577 LAR (L-2021-LLA-0158) ML21312A0072021-09-21021 September 2021 Enclosure 1 - E-mail - Enclosure B - NAPS SER App a - Dominion Comments 9-21-2021 ML21312A0032021-09-21021 September 2021 Enclosure 1 - E-mail - Enclosure a - Dominion Table A4.4-1 Clean Version ML21312A0022021-09-21021 September 2021 Enclosure 1 - E-mail - NAPS SLR SER Appendix a for Dominion Review ML21256A0672021-09-13013 September 2021 Final Request for Confirmation of Information Set 2 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21152A1722021-09-0707 September 2021 NRC to Fws, NRC Issuance of Draft Environmental Impact Statement for North Anna Subsequent License Renewal, Opportunity for Public Comment, and Endangered Species Act Determinations ML21238A0942021-08-25025 August 2021 Draft Request for Additional Information Set Z - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21225A5512021-08-13013 August 2021 Discussion Point for Public Meeting Regarding Fire Protection Piping Cyclic Loading - Transmittal E-mail ML21195A2442021-07-13013 July 2021 NRR E-mail Capture - Draft RAI Appendix E to Topical Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML21188A1632021-07-0707 July 2021 Final Request for Additional Information Set 4 - North Anna SLRA Safety Review (EPID No. L-2020-SLR-0000) - Email ML21154A0152021-06-0101 June 2021 NRR E-mail Capture - Acceptance Review for Primary Grade Water LAR (L-2021-LLA-0082) ML21140A3682021-05-20020 May 2021 Response to North Anna Hardship (Temporary Staff Guidance Additional Guidance for FOF Inspections During the PHE) 2024-04-15
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From: Tom Shaub [tom.shaub@dom.com]
Sent: Tuesday, July 06, 2010 3:15 PM To: Sreenivas, V
Subject:
Response to PREACS clarification concerns from phone call V,
Here are the response to the clarifications you requested regarding the HHSI pump seals and operating conditions.
What is the HHSI pump seal model #?
10110534 FLOWSERVE - Seal, mechanical, size 3 1/4 , inboard, suction side, single pto, cartridge type, for a 2.5 rlij-11 pump consisting of the following: metal parts - 316 ss seal sleeve bore - chrome plated 316 ss rotating face - tungsten carbide stationary face - #5 carbon gland material - 316 ss gland connections - flush gland elastomer - epr sleeve elastomer - epr Our documented worst case seal leak was 1200 cc / hr. What was the cause of that seal leak? At what fluid temperature did this leak occur?
On 4 July 2005, leakage was identified from the outboard seal on U2 C HHSI pump, 2-CH-P-1C. The quantity of leakage was observed to be 20 ml/minute. A root cause evaluation was performed. It was determined that elevated vibrations caused the outboard seal leak on 2-CH-P-1C, and was not a fault with the manufacture or installation of the seal. A more extensive vibration analysis was performed and found the source of the elevated vibrations to be at the inboard end of the pump. Of the potential sources, only the gear-to-pump coupling would result in higher vibration readings at the outboard end of the pump. The elevated vibrations are a result of the gear-to-pump coupling. The gear-to-pump coupling had been installed in late December 2004 (six months prior to the seal leak). Installation was by skill-of-the-craft with no balance or alignment checks performed. Alignment checks are referring to the assembly of the coupling components to make the coupling, not alignment between the pump and gear. Corrective actions were implemented as a result of the root cause evaluation.
As far as the fluid temperature, the seal leak occurred during normal operation, and the HHSI pump suction temperature is approximately 100ºF. However, this seal leak was considered Accident Leakage, and therefore, the leakage that was logged in the ECCS Leakage Log, was 2928 cc / hr (1200 CC/hr x 2.44). See below for explanation of Accident Leakage.
What is the difference in this leakage at fluid temperature assumed in a design basis accident?
The North Anna ECCS Leakage Log, 1-LOG-20 and 2-LOG-20, accounts for the difference in leakage that could be expected if the ECCS system were in the recirculation mode following a DBA. During normal operations, the most conservative pressure seen by the seals of the High Head Safety Injection (HHSI) pumps is due to lowest allowed VCT pressure and weight of water due to height. This conservatively equates to the square root of 160.8 (Low Head Safety Injection (LHSI) system pressure during recirculation) divided by 27 (lowest normal operating pressure at the suction of the HHSI pumps due to VCT pressure and weight of water due height) which provides a conversion factor of 2.44. Only those leaks in the LHSI system from the discharge of the pumps to the LHSI containment penetrations and to the suctions of the HHSI pumps, including HHSI pump seal leakage, require this correction factor and an
ACCIDENT LEAKAGE entry in the ECCS Leakage Log. This conversion to accident leakage is dependent on pressure and not fluid temperature.
What is the mission time for the HHSI pumps?
In support of our GSI-191 containment sump effort we analyzed the operation of the all ECCS pumps and seals for 30 days. In all instances the pumps and associated seals were capable of performing their safety function i.e., provide the required flow and limit leakage to acceptable levels. The evaluation for the HHSI pumps concluded that there would be no noticeable change in leak rates until at least 60% of the carbon ring nose is worn away. This ring is checked periodically to ensure adequate seal life (30 days of operation) during a DBA.
Although the mission time is 30 days for the HHSI pumps, in both SBLOCA and LBLOCA scenarios, the HHSI pumps would mostly likely not be run for 30 days.
For the SBLOCA the HHSI pumps would supply water until the plant is depressurized. This could include the use of the HHSI pump and LHSI pump in piggyback mode of operation if the plant is not depressurized before the RWST is emptied. However, plant procedures require an aggressive plant depressurization; the plant can be easily depressurized within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the HHSI pumps would no longer be necessary to provide core cooling.
For the LBLOCA the HHSI and LHSI pumps start and run on the SI. Both the HHSI and LHSI will continue to run through the injection phase into the recirculation phase (several hours). At that point core cooling is maintained by the flow from one HHSI and LHSI. If RCS pressure is low, one LHSI pump is sufficient to maintain adequate recirculation flow and cooling. (UFSAR 6.3.3.1.3)
Dominion Resources Services, Inc.
Thomas Shaub Technical Consultant Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060 Phone: (804) 273-2763 Fax: (804) 273-3715 E-mail: Tom.Shaub@dom.com (new e-mail address)
CONFIDENTIALITY NOTICE: This electronic message contains information which may be legally confidential and or privileged and does not in any case represent a firm ENERGY COMMODITY bid or offer relating thereto which binds the sender without an additional express written confirmation to that effect. The information is intended solely for the individual or entity named above and access by anyone else is unauthorized. If you are not the intended recipient, any disclosure, copying, distribution, or use of the contents of this information is prohibited and may be unlawful. If you have received this electronic transmission in error, please reply immediately to the sender that you have received the message in error, and delete it. Thank you.
April R. Thorpe, Contract Secretary Plant Licensing Branch 2-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Phone: 301-415-1688 Fax: 301-415-1222 April.Thorpe@nrc.gov E-mail Properties Mail Envelope Properties (1108E05267A25F458B14F9B1D036C5970E59EF62)
Subject:
Response to PREACS clarification concerns from phone call Sent Date: 7/6/2010 3:16:15 PM Received Date: 7/6/2010 3:16:15 PM From: Tom Shaub Created By: tom.shaub@dom.com Recipients:
V.Sreenivas@nrc.gov (Sreenivas, V)
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Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received: