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MONTHYEARML13133A0322013-05-0303 May 2013 License Amendment Request for Changes to Technical Specification 3/4.7.5 Ultimate Heat Sink. Project stage: Request ML13170A4772013-06-26026 June 2013 Millstone Power Station, Unit Nos. 2 and 3 - Acceptance Review Results Regarding Ultimate Heat Sink License Amendment Request (TAC Nos. MF1779 and MF1780) Project stage: Acceptance Review ML13192A2402013-07-30030 July 2013 Acceptance Review Results Regarding Ultimate Heat Sink License Amendment Requests Project stage: Acceptance Review ML13347B0932013-12-19019 December 2013 Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3/4.7.5 Ultimate Heat Sink Project stage: RAI ML14023A6462014-01-15015 January 2014 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.5, Ultimate Heat Sink. Project stage: Response to RAI ML14139A1002014-05-19019 May 2014 LAR Ultimate Heat Sink Project stage: Other ML14154A0912014-05-28028 May 2014 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.5, Ultimate Heat Sink. Project stage: Response to RAI ML14178A5992014-07-11011 July 2014 Issuance of Amendment Proposed Changes to Technical Specification 3/4 7.5, Ultimate Heat Sink (Tac MF1780) Project stage: Approval 2013-07-30
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Category:Letter
MONTHYEARML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures IR 05000336/20234402024-01-11011 January 2024 Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only) ML24004A1052024-01-0404 January 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010 ML23361A0942023-12-21021 December 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report . ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23361A0312023-12-20020 December 2023 Intent to Pursue Subsequent License Renewal ML23352A0202023-12-18018 December 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23334A2242023-11-30030 November 2023 Request for Exemption from Enhanced Weapons Firearms Background Checks, and Security Event Notifications Implementation ML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23317A2702023-11-13013 November 2023 Core Operating Limits Report, Cycle 23 IR 05000336/20230032023-11-0606 November 2023 Integrated Inspection Report 05000336/2023003 and 05000423/2023003 ML23298A1652023-10-26026 October 2023 Requalification Program Inspection IR 05000336/20234202023-10-0404 October 2023 Security Inspection Report 05000336/2023420 and 05000423/2023420 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis IR 05000245/20230012023-09-19019 September 2023 Safstor Inspection Report 05000245/2023001 IR 05000336/20230102023-09-0808 September 2023 Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010 IR 05000336/20230052023-08-31031 August 2023 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005) ML23248A2132023-08-30030 August 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature. ML23242A0142023-08-30030 August 2023 Operator Licensing Examination Approval ML23223A0552023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel ML23223A0482023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Use Framatome Small Break and Realistic Large Break LOCA Evaluation Methodologies for Establishing COLR Limits IR 05000336/20230022023-08-0909 August 2023 Integrated Inspection Report 05000336/2023002 and 05000423/2023002 ML23188A0432023-07-31031 July 2023 Authorization and Safety Evaluation for Alternative Request No. IR-04-11 ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000336/20234012023-07-17017 July 2023 Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only) ML23175A0052023-07-12012 July 2023 Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps ML23193A8562023-06-28028 June 2023 Submittal of Updates to the Final Safety Analysis Reports ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23159A2202023-06-0808 June 2023 Associated Independent Spent Fuel Storage Installation Revision to Emergence Plan - Report of Changes IR 07200047/20234012023-06-0808 June 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401 2024-01-04
[Table view] Category:Technical Specifications
MONTHYEARML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures ML23072A0892023-05-0101 May 2023 (Amendments 346 & 286), North Anna 1 & 2 (Amnds 294 & 277), Surry 1 & 2 (Amnds 311 & 311), and Summer 1 (Amd 225) - Issuance of Amendments to Revise TSs to Adopt TSTF-554 Revise Reactor Coolant Leakage Requirements ML21280A3282021-10-0707 October 2021 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions ML20275A0002020-10-14014 October 2020 Issuance of Amendment No. 277 to Revise Technical Specification 6.8.4.g to Allow a One-Time Deferral of the Steam Generator Inspections ML20237H9952020-09-29029 September 2020 Issuance of Amendment No. 341 Revision to Technical Specification 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program ML20261H5982020-09-17017 September 2020 Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML20191A0042020-08-0707 August 2020 Issuance of Amendment No. 340 Revised Technical Specification Limits for Primary and Secondary Coolant Activity ML19126A0002019-05-28028 May 2019 Issuance of Amendment No. 273 Regarding Technical Specification Changes for Spent Fuel Storage and New Fuel Storage ML19042A2772019-03-21021 March 2019 Issuance of Amendment No. 272 Regarding Revision to Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels ML18100A0552018-04-0404 April 2018 License Amendment Request to Revise Technical Specification Action Statement for Loss of Control Building Inlet Ventilation Radiation Monitor Instrumentation Channels ML17038A0062017-02-0101 February 2017 Technical Specifications 2016 Annual Report ML17025A2182017-01-24024 January 2017 Issuance of Amendment Realistic Large Break Loss-of-Coolant Accident Analysis ML16354A4242016-12-14014 December 2016 License Amendment Request to Revise Technical Specification Surveillance Requirement 4.1.3.1.2 for Control Element Assembly 39 for the Remainder of Cycle 24 ML16208A0512016-07-26026 July 2016 Clean Technical Specifications (TS) Pages for Millstone Power Station 1 (Docket No. 05000245), Administrative Changes for TS (L53121) ML16068A3122016-03-31031 March 2016 Issuance of Amendment No. 326 to Revise Technical Specifications for Containment Leak Rate Testing ML16011A4002016-01-29029 January 2016 Issuance of Amendments Nos. 325 and 267 to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML15288A0042015-11-30030 November 2015 Issuance of Amendment No. 266: Implementation of WCAP-14333 and WCAP-15376, Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation Test Times and Completion Times ML15280A2422015-10-29029 October 2015 Issuance of Amendment No. 324 Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program, Adoption of TSTF-425,Rev 3 ML15245A4822015-10-0707 October 2015 Millstone Power Station, Surry Power Station, and North Anna Power Station - Issuance of Amendments to Revise the Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses ML15225A0102015-08-28028 August 2015 Issuance of Amendment No. 264 Surveillance Requirement 4.4.4.2, Reactor Coolant System Relief Valves ML15225A0082015-08-26026 August 2015 Issuance of Amendment No. 322 Revision to the Final Safety Analysis Report - Examination Requirements for ANSI B31.1.0 Piping Welds ML15187A3262015-07-29029 July 2015 Issuance of Amendment No. 321, Adoption of TSTF-426, Revision 5, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B & 6C ML15187A1862015-07-28028 July 2015 Issuance of Amendment No. 263, Regarding Technical Specification Changes to Auxiliary Feedwater System (MF4692) ML15187A0112015-07-27027 July 2015 Issuance of Amendment No. 262, Refueling Water Storage Tank Allowable Temperatures ML15209A7292015-07-21021 July 2015 Response to Second Request for Additional Information Regarding Proposed Technical Specification Change for Spent Fuel Storage ML15098A0342015-05-20020 May 2015 Issuance of Amendment No. 261, Delete Technical Specification Index and Make Other Editorial and Administrative Changes ML15093A0022015-05-20020 May 2015 Issuance of Amendment No. 320, Delete Technical Specification Index and Make Other Editorial and Administrative Changes ML15093A4412015-05-18018 May 2015 Issuance of Amendment No. 319, Use of Areva M5 Alloy Clad Fuel Assemblies ML15044A0442015-02-0909 February 2015 Revised Response to Request for Additional Information Regarding License Amendment Request for Proposed Technical Specification Changes of the Refueling Water Storage Tank Allowable Temperatures ML15021A1282015-01-15015 January 2015 Proposed License Amendment Requests to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML14301A1122014-10-22022 October 2014 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3 ML14154A0912014-05-28028 May 2014 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3/4.7.5, Ultimate Heat Sink. ML14073A0552014-04-0808 April 2014 Issuance of Amendment Calculated Containment Internal Pressure ML13346A7672013-12-18018 December 2013 Correction Letter to License Amendment Nos. 256 and 257 ML13155A1402013-05-28028 May 2013 Response to Request for Additional Information Regarding Proposed Technical Specifications Changes for Spent Fuel Storage ML13133A0322013-05-0303 May 2013 License Amendment Request for Changes to Technical Specification 3/4.7.5 Ultimate Heat Sink. ML13133A0332013-05-0303 May 2013 License Amendment Request for Changes to Technical Specification 3/4.7.11, Ultimate Heat Sink. ML12284A2132012-10-0404 October 2012 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3 ML12250A6642012-08-28028 August 2012 Correction to Proposed Technical Specifications to Adopt TSTF-510 ML12220A0122012-07-31031 July 2012 Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process ML12219A0732012-07-31031 July 2012 Proposed Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process ML12202A0402012-07-17017 July 2012 License Amendment Request Regarding Removal of a License Condition, Proposed Technical Specifications Bases Change and FSAR Change for Ultimate Heat Sink Temperature Measurement ML12110A1142012-04-12012 April 2012 License Amendment Request for Permanent Alternate Repair Criteria for Steam Generator Tube Inspection and Repair ML12097A2002012-04-0202 April 2012 License Amendment Request to Revise Snubber Surveillance Requirements ML12032A2242012-01-25025 January 2012 License Amendment Request to Relocate TS Surveillance Frequencies to License Controlled Program in Accordance with TSTF-425, Revision 3 ML11329A0032011-11-17017 November 2011 Proposed License Amendment and Exemption Request for Use of Optimized Zirlo Rod Cladding ML11193A2242011-07-0505 July 2011 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3, Attachment 3 Through Attachment 6, Marked-up TS Pages and TS Bases Pages ML11193A2232011-07-0505 July 2011 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3, Attachment 1 Through Attachment 3, Marked-up TS Page Changes 3/4 6-22 ML1102802082011-01-20020 January 2011 License Amendment Request to Revise Technical Specification (TS) 6.8.4.g, Steam Generator (SG) Program, and TS 6.9.1.7, Steam Generator Tube Inspection Report for Temporary Alternate Repair Criteria (H*) ML1022400642010-07-21021 July 2010 License Amendment Request to Revise Technical Specification 3/4.9.3.1, Decay Time 2024-01-12
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Text
Dominion Nuclear Connecticut, Inc.
5000 Dominion Boulevard, Glen Allen, VA 23060 SDominion Web Address: www.dom.com May 28, 2014 U. S. Nuclear Regulatory Commission Serial No.14-271 Attention: Document Control Desk NSSL/MLC RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR CHANGES TO TECHNICAL SPECIFICATION 3/4.7.5. "ULTIMATE HEAT SINK" By letter dated May 3, 2013, Dominion Nuclear Connecticut, Inc. (DNC) submitted a license amendment request (LAR) for Millstone Power Station Unit 3 (MPS3). The proposed amendment would modify Technical Specification (TS) 3/4.7.5, "Ultimate Heat Sink," to increase the current ultimate heat sink (UHS) water temperature limit from 75*F to 80'F and change the TS Action to state, "With the ultimate heat sink water temperature greater than 80'F, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />."
In a letter dated June 26, 2013, the Nuclear Regulatory Commission (NRC) provided DNC an opportunity to supplement the LAR identified above. Supplemental information was provided to the NRC in a letter dated July 2, 2013. In an e-mail dated September 5, 2013, the NRC transmitted a request for additional information (RAI) related to the LAR. DNC responded to the RAI in a letter dated October 2, 2013. In a letter dated December 19, 2013, the NRC transmitted a second RAI. DNC responded to the RAI in a letter dated January 15, 2014. In a letter dated April 23, 2014, DNC provided supplemental information to Section 5.3.2.3 of Attachment 1 of the LAR submittal of May 3, 2013. In an e-mail dated May 19, 2014, the NRC transmitted a third RAI. to this letter contains DNC's response to the third RAI.
If you have any questions or require additional information, please contact Wanda Craft at (804) 273-4687.
Sincerely,
- I, m
VICKI L. HULL Daniel G. Stoddard Notary Public Commonwealth of Virginia Senior Vice President - Nuclear Operations 140542 My Commission Expires Mayv31, v2014 v a v
. . . n COMMONWEALTH OF VIRGINIA )
)
COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Daniel G.
Stoddard, who is Senior Vice President - Nuclear Operations of Dominion Nuclear Connecticut, Inc. ' He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that company, and that the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this 0 - day of( /A_ , 2014.
My Commission Expires: 5 -- 3/ /4. " A(
Notary Publlic
Serial No.14-271 Docket No. 50-423 Page 2 of 2 Commitments made in this letter: None
Attachment:
- 1. Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specifications 3/4.7.5, "Ultimate Heat Sink" cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 Mohan Thadani Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 B1 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director, Radiation Division Department of Energy and Environmental Protection 79 Elm Street Hartford, CT 06106-5127
Serial No 14-271 Docket No. 50-423 Attachment 1 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specifications 3/4.7.5, "Ultimate Heat Sink" Dominion Nuclear Connecticut, Inc.
Millstone Power Station Unit 3
Serial No 14-271 Docket No. 50-423 Attachment 1, Page 1 of 3 Response to Request for Additional Information Regarding License Amendment Request for Changes to Technical Specifications 3/4.7.5, "Ultimate Heat Sink" By letter dated May 3, 2013, Dominion Nuclear Connecticut, Inc. (DNC) submitted a license amendment request (LAR) for Millstone Power Station Unit 3 (MPS3). The proposed amendment would modify Technical Specification (TS) 3/4.7.5, "Ultimate Heat Sink," to increase the current ultimate heat sink (UHS) water temperature limit from 75"F to 80OF and change the TS Action to state, "With the ultimate heat sink water temperature greater than 80'F, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />."
In a letter dated June 26, 2013, the Nuclear Regulatory Commission (NRC) provided DNC an opportunity to supplement the LAR identified above. Supplemental information was provided to the NRC in a letter dated July 2, 2013. In an e-mail dated September 5, 2013, the NRC transmitted a request for additional information (RAI) related to the LAR. DNC responded to the RAI in a letter dated October 2, 2013. In a letter dated December 19, 2013, the NRC transmitted a second RAI. DNC responded to the RAI in a letter dated January 15, 2014. In a letter dated April 23, 2014, DNC provided supplemental information to Section 5.3.2.3 of of the LAR submittal of May 3, 2013. In an email dated May 19, 2014, the NRC transmitted a third RAI. The response to this RAI is provided below.
RAI-1
The license amendment request (LAR) of May 3, 2013 requests a change to Surveillance Requirement (SR) 4.7.5, which does not now include the most current revision of SR 4.7.5.
The licensee is requested to provide the proposed change to SR 4.7.5 using the current revision.
DNC Response MPS3 Amendment 258, approved February 25, 2014, impacted Technical Specification page 3/4 7-13. The most current revision of page 3/4 7-13 is provided in Enclosure 1 of this attachment and is marked-up to indicate the proposed changes discussed in the license amendment request of May 3, 2013.
RAI-2
In the LAR for LCO 3.7.5 and SR 4.7.5, the licensee changed the parameterto be monitored from "averagewater temperature"to "watertemperature."
The licensee is requested to explain the technical reasons andjustify changing the parameter to be monitored as explained above.
Serial No 14-271 Docket No. 50-423 Attachment 1, Page 2 of 3 DNC Response At the time the LAR was submitted, the service water system had no remote temperature monitoring instrumentation available. However, the non-safety related circulating water system has remote temperature monitoring instrumentation in each circulating water inlet water box (six total). Since the circulating water pumps take water from the UHS near the suction of the service water pumps, the temperature recorded at the circulating water inlet water box was considered representative of service water inlet temperature. However, these instruments did not have a documented uncertainty. To obtain a higher confidence in the indication of UHS temperature, the in-service water box temperatures were averaged to determine UHS temperature. This was described in the existing bases of the Technical Specification as included in the original LAR submittal of May 3, 2013. However, as a result of the Millstone Unit 2 shutdown due to high UHS temperature in August 2012, the use of these instruments was reconsidered. Detailed measurements showed that the use of the circulating water inlet waterbox temperatures could be non-conservative by approximately 10 F. Therefore, as described in the May 3, 2013 LAR, remote indicating precision temperature monitoring instrumentation was installed at MPS3 at each train's service water inlet to the reactor plant closed cooling water (RPCCW) heat exchangers and the in-service instruments must be within the UHS temperature limit. This instrumentation provides more representative and precise indication of UHS temperature and is used to monitor compliance with the UHS Technical Specification in SR 4.7.5.
RAI-3
In the licensee's letter, dated January 15, 2014, as a response to request for additional information (RAI) 4, regardingthe ESF air conditioning unit (3HVQ ACUSIA, 1B, 2A, and 2B) condensers, the licensee explained the seemingly low service water flow rate of 25 gpm and 33.2 gpm by allowing the service water (SW) AT across the heat exchangers to increase to transfer the heat for condensing the R-22 Freon. With a SW inlet temperature of 80°F, the vendor data sheet has a AT of 15.7 0F, while the licensee's calculated AT's are 29.5°F and 24.4 0F. The licensee justified the seemingly low SW flow rate by allowing higher SW ATs.
The licensee did not address the effect of the corresponding higher SW temperatures across the condensers on the condensing effects of the R-22, but called the results "reasonable."
Provide definitive statements, as appropriate, regarding the operability of the ESF air conditioning units to perform their safety functions and remove design heat loads under accident conditions with an 80°F SW inlet temperature and the high SW ATs and low flow rates described in your RAI response. Describe any adverse effect on the R-22 condensing function with the higher SW AT and the ability of the ESF units to perform their safety functions.
DNC Response The acceptability of 80OF service water to the ESF air conditioning unit condensers (HVQ chillers) was evaluated in calculation 97-002, Rev 3, Addendum B. The HVQ chillers are
Serial No 14-271 Docket No. 50-423 Attachment 1, Page 3 of 3 Freon to water heat exchangers. When the service water side average temperature increases, the Freon side average temperature also increases to obtain the required heat removal rate. The following excerpts from this calculation address the concerns of the question:
- The refrigerant for the 3HVQ*ACUS1A, 3HVQ*ACUS2A, 3HVQ*ACUS1B, and 3HVQ*ACUS2B condensers is R-22 and the compressor Normal Operating Range Limit is 255 psig (269.7 psia).
" The condenser pressure vs. temperature relationship is defined by the saturated properties of R-22 for condensers 3HVQ*ACUS1A, 3HVQ*ACUS2A, 3HVQ*ACUS1B, and 3HVQ*ACUS2B.
" The highest calculated refrigerant temperature (based on 24.97 gpm of 80'F service water) for 3HVQ*ACUS1A and 3HVQ*ACUS1B is 116.98 OF. The refrigerant is R-22, at a saturated pressure of 264.3 psia, which is less than the 269.7 psia allowable pressure. Therefore, the condensing pressure of 3HVQ*ACUS1A and 3HVQ*ACUS1B is acceptable.
- The highest calculated refrigerant temperature (based on 33.15 gpm of 80°F service water) for 3HVQ*ACUS2A and 3HVQ*ACUS2B is 112.29 OF. The refrigerant is R-22, at a saturated pressure of 248.6 psia, which is less than the 269.7 psia allowable pressure. Therefore, the condensing pressure of 3HVQ*ACUS2A and 3HVQ*ACUS2B is acceptable.
Therefore, it is concluded that these chillers are fully capable of removing the required heat load at 80°F service water temperature assuming the worst case calculated flow rates.
Serial No 14-271 Docket No. 50-423 Enclosure 1 Marked-Up Technical Specifications Page Dominion Nuclear Connecticut, Inc.
Millstone Power Station Unit 3
Serial No 14-271 Docket No. 50-423 PLANT SYSTEMS 3/4.7.5 ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7.5 The ultimate heat sink (UHS) shall be OPERABLE with afu aierwage water temperature nf 1ev thnn nhr Onllnd tn SS. rr-l-With the UHS water temperature greater MODES 1, 2, 3, and 4. than 80 0 F, be in HOT STANDBY within 6 APPLICABILITY: I' hours and in COLD SHUTDOWN within the ACTION:
following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Iftho UHF tz:pzraturz do no.t drop below ;94 dur-ing thin p.iod..la*z,.... the ii.i;at LHOT STAoNDBY4 within the nz:4 6 heura and ini C-OLD SHUTDOWN withinl toe followitg 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Duiring ti ..... ,..if... .UH t...ratur
. ........ t.. o. 7:7R, plan th. plf.. in HO(T-ST10iDBY4 wAkithi 41h0 neif 6 hour- and 4in COLD SHUT:DOWZN withini the foqllowing 30-haere SURVEILLANCE REQUIREMENTS 4.7.5 The UHS shall be determined OPERABLE:
- a. At the frequency specified in the Surveillance Frequency Control Program by 4-I verifying the e,-enge water temperature to be within limits.
- b. At least once per 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> by verifying the twei'ge water temperature to be within lim its when the aereage water temperature exceeds -7.F MILLSTONE - UNIT.3 3/4 7-13 MIAmendment No. 449, m8 k-I