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Category:Letter
MONTHYEARIR 05000336/20240032024-11-0707 November 2024 Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001 ML24289A0152024-10-21021 October 2024 Review of the Fall 2023 Steam Generator Tube Inspection Report 05000423/LER-2024-001, Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary2024-10-14014 October 2024 Loss of Safety Function and Condition Prohibited by Technical Specifications for Loss of Secondary Containment Boundary IR 05000336/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000336/2024402 and 05000423/2024402 (Cover Letter Only) ML24281A1102024-10-0707 October 2024 Requalification Program Inspection 05000423/LER-2023-006-02, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-09-26026 September 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2192024-09-16016 September 2024 Decommissioning Trust Fund Disbursement - Revision to Previous Thirty-Day Written Notification ML24260A1952024-09-16016 September 2024 Response to Request for Additional Information Regarding Proposed Amendment to Support Implementation of Framatome Gaia Fuel ML24248A2272024-09-0404 September 2024 Operator Licensing Examination Approval ML24240A1532024-09-0303 September 2024 Summary of Regulatory Audit Supporting the Review of License Amendment Request for Implementation of Framatome Gaia Fuel IR 05000336/20240052024-08-29029 August 2024 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Reports 05000336/2024005 and 05000423/2024005 IR 05000336/20240022024-08-13013 August 2024 Integrated Inspection Report 05000336/2024002 and 05000423/2024002 ML24221A2872024-08-0808 August 2024 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of Cask Registration for Spent Fuel Storage IR 05000336/20244412024-08-0606 August 2024 Supplemental Inspection Report 05000336/2024441 and 05000423/2024441 and Follow-Up Assessment Letter (Cover Letter Only) ML24212A0742024-08-0505 August 2024 Request for Withholding Information from Public Disclosure - Millstone Power Station, Unit No. 3, Proposed Alternative Request IR-4-13 to Support Steam Generator Channel Head Drain Modification ML24211A1712024-07-25025 July 2024 Associated Independent Spent Fuels Storage Installation, Revision to Emergency Plan - Report of Change IR 05000336/20244032024-07-22022 July 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000336/2024403 and 05000423/2024403 IR 05000336/20245012024-07-0101 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000336/2024501 and 05000423/2024501 ML24180A0932024-06-28028 June 2024 Readiness for Additional Inspection: EA-23-144 IR 05000336/20240102024-06-26026 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000336/2024010 and 05000423/2024010 ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 IR 05000336/20244402024-06-24024 June 2024 Final Significance Determination for Security-Related Greater than Green Finding(S) with Assessment Follow-up; IR 05000336/2024440 and 05000423/2024440 and Notice of Violation(S), NRC Investigation Rpt 1-2024-001 (Cvr Ltr Only) ML24176A1782024-06-20020 June 2024 Update to the Final Safety Analysis Report ML24176A2622024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24280A0012024-06-20020 June 2024 Update to the Final Safety Analysis Report (Redacted Version) ML24281A2072024-06-20020 June 2024 Update to the Final Safety Analysis Report, Revision 37 (Redacted Version) 05000336/LER-2024-001, Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications2024-06-10010 June 2024 Control Room Air Conditioning Unit Inoperable Due to Refrigerant Overcharge Resulting in a Condition Prohibited by Technical Specifications ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24165A1292024-06-0505 June 2024 ISFSI, 10 CFR 50.59 Annual Change Report for 2023 Annual Regulatory Commitment Change Report for 2023 ML24128A2772024-06-0404 June 2024 Issuance of Amendment No. 290 to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and Core Operating Limits Report for Use of Framatome Gaia Fuel (EPID L-2023-LLA-0074) (Non-Proprietary) ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24110A0562024-05-21021 May 2024 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2023-LLE-0013) (Letter) ML24109A0032024-05-21021 May 2024 Issuance of Amendment No. 289 to Revise Technical Specifications to Use Framatome Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limit (EPID L-2023-LLA-0065) (Non-Proprietary) ML24142A0952024-05-20020 May 2024 End of Cycle 22 Steam Generator Tube Inspection Report 05000423/LER-2023-006-01, Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-20020 May 2024 Pressurizer Power Operated Relief Valve Failed to Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications ML24141A2432024-05-20020 May 2024 Response to Request for Additional Information Regarding Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment No. 15 IR 05000336/20240012024-05-14014 May 2024 Integrated Inspection Report 05000336/2024001 and 05000423/2024001 and Apparent Violation ML24123A2042024-05-0202 May 2024 Pre-Decisional Replay to EA-23-144 05000423/LER-2023-006, Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications2024-05-0202 May 2024 Pressurizer Power Operated Relief Valve Failed to Stroke Open During Surveillance Testing Resulting in a Condition Prohibited by Technical Specifications IR 05000336/20244012024-04-30030 April 2024 Security Baseline Inspection Report 05000336/2024401 and 05000423/2024401 (Cover Letter Only) ML24123A1222024-04-30030 April 2024 Inservice Inspection Program - Owners Activity Report, Refueling Outage 22 ML24116A0452024-04-25025 April 2024 Special Inspection Follow-Up Report 05000336/2024440 and 05000423/2024440 and Preliminary Finding(S) of Greater than Very Low Significance and NRC Investigation Report No. 1-2024-001 (Cover Letter Only) ML24116A1742024-04-24024 April 2024 Annual Radiological Environmental Operating Report ML24114A2662024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report ML24103A0202024-04-22022 April 2024 Summary of Regulatory Audit in Support of License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits ML24106A2032024-04-15015 April 2024 2023 Annual Environmental Operating Report ML24088A3302024-04-0404 April 2024 Regulatory Audit Plan in Support of License Amendment Request to Implement Framatome Gaia Fuel ML24093A2162024-04-0101 April 2024 Response to Request for Additional Information Regarding License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits 2024-09-04
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis ML23123A2792023-05-0202 May 2023 License Amendment Request to Use Framatome Small Break and Realistic Large Break Loss of Coolant Accident Evaluation Methodologies for Establishing Core Operating Limits and Exemption Request for Use of M5 Cladding ML23013A2242023-01-13013 January 2023 Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure Temperature Limitation Figures ML22362A1022022-12-28028 December 2022 Proposed License Amendment Request to Supplement Spent Fuel Pool Criticality Safety Analysis ML22146A0272022-05-25025 May 2022 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant. ML22096A2212022-04-0606 April 2022 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process ML21294A3382021-10-21021 October 2021 Proposed Amendment to Relocate Unit Staff Qualification Requirements from Technical Specifications to Nuclear Facility Quality . ML21053A3422021-02-22022 February 2021 Proposed License Amendment Request to Clarify Shutdown Bank Technical Specification Requirements and Add Alternative Control Rod Position Monitoring Requirements ML20343A2432020-12-0808 December 2020 Proposed License Amendment Request Revise Reactor Core Safety Limit to Reflect WCAP-17642-P-A, Revision 1 ML20343A2592020-12-0808 December 2020 Supplement to Proposed License Amendment Request to Revise the Millstone Unit 2 Technical Specifications for Steam Generator Frequency ML20324A7032020-11-19019 November 2020 Proposed License Amendment Request Measurement Uncertainty Recapture Power Uprate ML20310A3242020-11-0505 November 2020 Proposed License Amendment Request, Addition of Analytical Methodology to the Core Operating Limits Report for a Large Break Loss of Coolant Accident (LBLOCA) ML20282A5942020-10-0808 October 2020 Proposed License Amendment Request to Revise the Millstone Unit 2 Technical Specifications for Steam Generator Inspection Frequency ML20224A4572020-08-11011 August 2020 Connecticut. Inc. Millstone Power Station Unit 3, Proposed License Amendment Request for a One-Time Extension of the Millstone Unit 3 Steam Generator Inspections ML20121A2172020-04-30030 April 2020 Proposed Technical Specifications Change Battery Surveillance Requirements ML20105A0782020-04-14014 April 2020 Supplement to License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Components ML20065K9762020-03-0303 March 2020 License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML20063L8232020-03-0303 March 2020 License Amendment Request to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation ML19353A0222019-12-17017 December 2019 License Amendment Request to Revise TS 6.25, Pre-Stressed Concrete Containment Tendon Surveillance Program ML19304A2942019-10-22022 October 2019 Supplement to Proposed License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the Millstone Unit 3 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Componen ML19217A2082019-07-30030 July 2019 Proposed License Amendment Request to Revise Integrated Leak Rate Test (Type a) and Type C Test Intervals ML19109A1002019-04-11011 April 2019 Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month. ML19023A4272019-01-17017 January 2019 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML18128A0492018-05-0303 May 2018 License Amendment Request Regarding Proposed Technical Specifications Changes for Spent Fuel Storage and New Fuel Storage 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 ML17284A1792017-10-0404 October 2017 Proposed License Amendment Request to Revise Integrated Leak Rate Test (Type a) and Type C Test Intervals ML17171A2322017-06-15015 June 2017 License Amendment Request to Revise the Company Name ML17018A0002017-02-0707 February 2017 Issuance of Amendment Technical Specification Surveillance Requirement 4.1.3.1.2 for Control Element Assembly 39 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 ML16159A2592016-09-0606 September 2016 Enclosure 1 Millstone Power Station, Unit No. 1 Issuance of Amendment Administrative Changes and Corrections to the Technical Specifications ML16153A0262016-05-25025 May 2016 Proposed License Amendment Request Realistic Large Break Loss of Coolant Accident Analysis ML16153A0272016-05-25025 May 2016 ANP-3316(NP), Revision 0, Millstone, Unit 2, M5 Upgrade, Realistic Large Break Loca Analysis Licensing Report. ML16153A2342016-05-23023 May 2016 Supplement to License Amendment Request for Administrative Changes to the Permanently Defueled Technical Specifications ML16034A3582016-01-26026 January 2016 License Amendment Request, Spent Fuel Pool Heat Load Analysis ML16029A1682016-01-25025 January 2016 License Amendment Request to Revise ECCS TS 3/4.5.2 and FSAR Chapter 14 to Remove Charging ML15246A1172015-08-31031 August 2015 Supplement to License Amendment Request to Revise TS 6.19, Containment Leakage Testing Program ML15246A1182015-08-31031 August 2015 License Amendment Request to Revise Technical Specification 5.6.3, Fuel Storage Capacity ML15246A1242015-08-27027 August 2015 Connecticut, Inc. Millstone Power Station Unit 2 Supplement to License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3 ML15183A0222015-06-30030 June 2015 License Amendment Request for Removal of Severe Line Outage Detection from the Offsite Power System ML15134A2442015-05-0808 May 2015 License Amendment Request to Adopt Dominion Core Design and Safety Analysis Methods and to Address the Issues Identified in Westinghouse Documents NSAL-09-5, Rev. 1, NSAL-15-1, and 06-IC-03 ML15065A3342015-02-26026 February 2015 Changes to Technical Specification Bases ML15021A1282015-01-15015 January 2015 Proposed License Amendment Requests to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation ML14310A1872014-10-31031 October 2014 License Amendment Request to Revise the Final Safety Analysis Report - Examination Requirements for ANSI B31.1.0 Piping Welds ML14301A1122014-10-22022 October 2014 License Amendment Request to Relocate TS Surveillance Frequencies to Licensee Controlled Program in Accordance with TSTF-425, Revision 3 ML14188B1892014-06-30030 June 2014 License Amendment Request to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B & 6C. ML14133A0092014-05-0808 May 2014 License Amendment Request, Implementation and Engineered WCAP-15376, Reactor Trip System Instrumentation Test Times and Engineered Safety Feature Actuation System Instrumentation Test and Completion Times ML14093A0282014-03-28028 March 2014 License Amendment Request for Administrative Changes to the Permanently Defueled Technical Specifications ML14093A0262014-03-28028 March 2014 License Amendment Request for Administrative Changes and Corrections to the Technical Specifications ML14093A0272014-03-28028 March 2014 License Amendment Request for Administrative Changes and Corrections to the Technical Specifications ML14070A3462014-03-0606 March 2014 Changes to Technical Specification Bases 2023-09-26
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Dominion Nuclear Connecticut, Inc.
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\Y.ltcli;,rd, CI06385 August 4, 2005 U.S. Nuclear Regulatory Commission Serial No. 05-049A Attention: Document Control Desk NLOS/PRW RO One White Flint North Docket No. 50-336 11555 Rockville Pike License No. DPR-65 Rockville, Maryland 20852-2738 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2 SUPPLEMENT TO LICENSE AMENDMENT REQUEST (LBDCR 05-MP2-001)
TRlSODlUM PHOSPHATE TECHNICAL SPECIFICATION In a letter dated February 25, 2005, Dominion Nuclear Connecticut, Inc. (DNC) provided a request to amend the Millstone Power Station Unit 2 (MPS2) operating license to modify the technical specification surveillance requirement for trisodium phosphate (TSP) to remove the granularity term and chemical detail.
In a facsimile dated July 7, 2005, the NRC provided a draft request for additional information (RAI) asking DNC to clarify certain items in DNCs February 25, 2005 submittal. In a phone conversation held on July 12, 2005, Dominion agreed to provide a response to the draft RAI by August 5, 2005. The attachment to this letter provides the supplemental information requested.
The additional information provided in this letter does not affect the conclusions of the safety summary and significant hazards considerations discussion in the DNC letter dated February 25, 2005.
Should you have any questions regarding this submittal, please contact Mr. Paul R. Willoughby at (804) 273-3572.
Very truly yours, Eugene S. Grecheck Vice President - Nuclear Support Services Attachments: (1)
Commitments made in this letter: None
Serial No. 05-049A Docket No. 50-336 Supplement to License Amendment Request Trisodium Phosphate Technical Specification Page 2 of 3 cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-141 5 Mr. V. Nerses Senior Project Manager - Millstone Unit 2 U.S. Nuclear Regulatory Commission One White Flint North 1 1555 Rockville Pike Mail Stop 8C2 Rockville, MD 20852-2738 Mr. S. M. Schneider NRC Senior Resident Inspector Millstone Power Station Director Bureau of Air Management Monitoring and Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127
Serial No. 05-049A Docket No. 50-336 Supplement to License Amendment Request Trisodium Phosphate Technical Specification Page 3 of 3 COMMONWEALTH OF VIRGINIA )
)
COUNTY OF HENRICO 1 The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Eugene S. Grecheck, who is Vice President - Nuclear Support Services 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 4% day of 4- , 2005.
My Commission Expires:
Y 0 Notary Public (SEAL)
Serial No. 05-049A Docket No. 50-336 ATTACHMENT LICENSE AMENDMENT REQUEST (LBDCR 05-MP2-0011 TRlSODlUM PHOSPHATE TECHNICAL SPECIFICATION SUPPLEMENTAL INFORMATION MILLSTONE POWER STATION UNIT 2 DOMINION NUCLEAR CONNECTICUT, INC.
Serial No. 05-049A Docket No. 50-336 Supplement to License Amendment Request Trisodium Phosphate Technical Specification Attachment Page 1 of 3 LICENSE IENT REQUEST (LBDCR 05-MP2-001)
TRlSODlUM PHOSPHATE TECHNICAL SPECIFICATION SUPPLEMENTAL INFORMATION By letter dated February 25, 2005, Dominion Nuclear Connecticut, Inc. (DNC) submitted a request to modify the Technical Specification surveillance requirement for trisodium phosphate (TSP). The NRC has developed the following question during its review of the DNC letter.
NRC Question In page 4 of the February 25, 2005 submittal, DNC stated: "Past testing on compacted TSP indicates that even if the TSP crystals become compressed and partially fused together] rapid dissolution is still assured. Please justify your statement and provide more specific information on how you arrived at your results.
DNC ResDonse Dominion Nuclear Connecticut, Inc. (DNC) affirms the statement regarding rapid dissolution of compressed trisodium phosphate (TSP) crystals based on the following :
- 1. Initial testing conducted by Combustion Engineering in the early 1970's.
- 2. Surveillance testing conducted at Millstone Power Station Unit 2 (MPS2) since March 1999.
Testina Conducted bv Combustion Enaineerinq As clarification to the information discussed with the NRC in the phone conversation of July 12, 2005, the temperatures used in CE's testing were 200°F and 185°F. During the phone call, DNC indicated the testing was done at 200°F and 85°F based on a table in the CE documents summarizing the test results.
However, a more detailed review of the documents indicates that the cited 85°F in the table is a typo, and that the testing was done at 185°F. In the introductory paragraph describing the testing, CE says a number of tests were performed to measure the rate of solution of TSP "near the boiling point of water." And, in the experimental method write-up, CE says, "Tests were performed by immersing the pellets in stagnant and flowing water at 185°F and 200°F."
To reiterate the information provided in the phone call, Combustion Engineering formed standard-size cylindrical TSP pellets from granulated trisodium phosphate. Pellets were formed by compression of the granulated TSP at
Serial No. 05-049A Docket No. 50-336 Supplement to License Amendment Request Trisodium Phosphate Technical Specification Attachment Page 2 of 3 pressures of 5000, 10,000 and 20,000 psia. The TSP pellets were then immersed in warm water as described above. The pellets were completely dissolved within approximately six minutes with no solution agitation, and within approximately two minutes with solution agitation.
DNC Surveillance Testinq To reiterate the information provided during the phone conversation of July 12, 2005, samples are taken from the surface of the TSP in the baskets and then placed in room temperature water without agitation for dissolution. DNC samples the surface of the TSP as this material is more likely to be adversely affected by containment conditions than the bulk of the TSP material beneath the surface layer. The surveillance time limit for dissolution is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
In 1998, Millstone determined the required volume of TSP needed to be increased. Two of the five TSP baskets were replaced with larger baskets, and additional TSP was added to increase the TSP volume to the requisite value. A scribe mark on each basket indicates the fill level to meet the minimum allowable volume requirement. The basket fill is verified each refueling outage by Operations personnel. Should the level of TSP be below the required fill level indicated for the associated basket, more TSP is placed in the baskets along with the TSP already there. Even though the level of the TSP may decrease over time, the same mass of TSP remains in the baskets, but is compressed. Adding more TSP actually increases the mass of TSP available for neutralization of the coolant in the containment sump during accident conditions.
During the phone conversation of July 12, 2005, DNC indicated that it believed no TSP had been added to the baskets since 1998. However, a detailed review of the completed TSP level surveillances since September 1998 indicates that TSP has been added to one of the five baskets twice since 1998 (in April 2000, and again in April 2005),and once to one other basket (in April 2005). Both of the baskets that required additional TSP were the two larger baskets installed in 1998. These two baskets (5 x 5 x 4.5 deep) replaced two smaller baskets (5 x 5 x 1.5 deep) as noted previously. DNC believes the required TSP additions to these two baskets is the result of settling/compression of the additional TSP volume added in 1998. The three other TSP baskets (of the original 5 x 5 x 1.5 deep design) in containment have not had any material added to them since before 1998.
Serial No. 05-049A Docket No. 50-336 Supplement to License Amendment Request Trisodium Phosphate Technical Specification Attachment Page 3 of 3 Millstone has verified TSP buffering capability at MPS2 five times since increasing the required volume of TSP during the extended outage. The results of the surveillances are as follows:
0 March 19, 1999: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 46 minutes for 0.6718 grams to dissolve in 75.6"F water without stirring May 1, 2000: lhour and 29 minutes for 0.6797 grams to dissolve in 79°F water without stirring 0 Feb., 19, 2002: 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 5 minutes for 0.6700 grams to dissolve in 72.7"F water without stirring Oct. 27, 2003: 20 minutes for 0.6514 grams to dissolve in 78.9"F water without stirring April 24, 2005: 51 minutes for 0.6690 grams to dissolve in 76.3"F water without stirring As evidenced by the above, there is a substantial variation in the recorded time for TSP dissolution during these surveillance tests. This is most likely due to the way the dissolution portion of the surveillance is conducted. Typically, the Chemistry technicians performing the surveillance place the TSP into the water, record the start time, and then perform other functions, intermittently checking the TSP to see when dissolution is complete. The technicians do not continuously monitor the TSP and thus may record a bounding time and not the exact time dissolution is complete. The compaction of the TSP sample may also play some role in the recorded dissolution time, but it is believed this is a minor impact compared to the lack of continuous monitoring of the solution.
The difference in dissolution times between the CE tests conducted with no solution agitation (-6 minutes) and the surveillances performed at MPS2 (220 minutes) is believed to be the result of the difference in solution temperatures.
The CE tests were conducted in hot water (185°F and 200°F solutions); whereas, the MPS2 surveillance is conducted in room temperature water (77 k 5°F). The Merck Index) indicates that TSP is soluble in 3.5 parts room-temperature water and 1 part boiling water.
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(') The Merck Index: An EncvcloDedia of Chemicals, Druas, and BioloaicalS, 10th Edition, by Martha Windholz, et. al., Merck and Company, Inc., 1983. TSP is monograph number 8503 (sodium phosphate, tribasic) on page 1240.