ML073410651
| ML073410651 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/07/2007 |
| From: | Gerald Bichof Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 07-0790, LBDCR 07-MP2-013, LBDCR 07-MP3-033 | |
| Download: ML073410651 (11) | |
Text
Dominion Nuclear Connecticut, Inc.
'i1l01l Dominion Boulevard, Glen Allen, Virginia 25060 Web Address: www.dom.com December 7, 2007 Serial No.
MPSNVEB Docket Nos.
U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 07-0790 Rev. 2' 50-336 50-423 License Nos. DPR-65 NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNITS 2 AND 3 APPLICATION FOR TECHNICAL SPECIFICATION IMPROVEMENT REGARDING CONTROL ROOM HABITABILITY LBDCRS 07-MP2-013 AND 07-MP3-033 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION On July 13, 2007, Dominion Nuclear Connecticut, Inc. (DNC) submitted a request for an amendment to the Technical Specification (TS) for Millstone Power Station Units 2 and 3 (MPS2 and MPS3) (Serial No.
07-0440).
The proposed amendment would revise TS requirements related to Control Room envelope habitability.
The NRC staff forwarded a request for additional information in a November 21, 2007 letter (TAC Nos. MD6115 and MD6116) regarding the proposed meaning and the technical justification for the term "recently irradiated fuel." The proposed meaning for the term "recently irradiated fuel" for MPS2 is fuel that has occupied part of a critical reactor core within the previous 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />.
For the MPS3 current analysis of record, the proposed meaning is fuel that has occupied part of a critical reactor core within the previous 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />.
Following the proposed stretch power uprate for MPS3 identified in license amendment request letters dated July 13, 2007 (Serial Nos. 07-0450 and 07-0450A), which is currently undergoing NRC review, the proposed meaning will be fuel that has occupied part of a critical reactor core within the previous 350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br />.
The technical justification for defining the decay time for recently irradiated fuel is provided in the attachments to this letter. contains Fuel Handling Accident (FHA) analysis data for MPS2 and Attachment 2 contains FHA analysis data for MPS3.
07-0790 Control Room Habitability Supplemental Information Page 2 of 3 The additional information provided in this letter does not affect the conclusions of the Significant Hazards Consideration discussion in DNC's original submittal dated July 13, 2007.
Should you have any further questions in regard to this submittal, please contact Mr. Thomas Shaub at (804) 273-2763.
Sincerely, Vice President - Nuclear Engineering Attachments: (2) 1.
MPS2 FHA Analysis Data 2.
MPS3 FHA Analysis Data Commitments made in this letter: None COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Gerald T.
Bischof, who is Vice President -
Nuclear Engineering 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 7';"" day of idEe..
,2007.
My Commission Expires:
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Notary Public MARQARET t. IEHNE1T Notary PubtJcj~f30.;\\
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~ My CommtlllOn Exptret Aug 31. 2001
07-0790 Control Room Habitability Supplemental Information Page 3 of 3 cc:
U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ms. C. J. Sanders NRC Project Manager U.S. Nuclear Regulatory Commission, Mail Stop 08B3 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Mr. S. W. Shaffer NRC Senior Resident Inspector Millstone Power Station Director Bureau of Air Management Monitoring and Radiation Division Department of Environmental Protection 79 Elm St.
Hartford, CT 06106-5127
07-0790 Control Room Habitability Supplemental Information ATTACHMENT 1 MPS2 FUEL HANDLING ACCIDENT ANALYSIS DATA DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2
07-0790 Control Room Habitability Supplemental Information Page 1 of 2 Fuel Handling Accident Data Millstone Power Station Unit 2
Background:
On July 13, 2007, Dominion Nuclear Connecticut, Inc. (DNC) submitted a request for an amendment to the Technical Specification (TS) for Millstone Power Station Units 2 and 3 (MPS2 and MPS3).
The proposed amendment would revise the TS requirements related to Control Room envelope habitability.
This attachment contains Fuel Handling Accident (FHA) analysis input data for Millstone Power Station Unit 2 (MPS2), providing additional information regarding the term "recently irradiated fuel".
Discussion:
The recently irradiated fuel dose analysis was performed with a controlled version of the computer code RADTRAD-NAI 1.1a (QA).
Innovative Technology Solutions of Albuquerque, New Mexico developed the RADTRAD code for the NRC.
The original version of the NRC RADTRAD code was documented in NUREG/CR-6604. The Numerical Applications, Inc. (NAI) version of RADTRAD was originally derived from NRC/ITS RADTRAD, version 3.01.
Subsequently, RADTRAD-NAI was changed to conform to NRCIITS RADTRAD, Version 3.02 with additional modifications to improve usability.
The RADTRAD-NAI code is maintained under NAl's QA program, which conforms to the requirements of 10CFR50, Appendix B. The RADTRAD-NAI 1.1a (QA) computer code was used in the MPS2 Alternate Source Term (AST) submittal, which was approved by the NRC in Amendment 298, dated May 31,2007.
To define the decay time for "recently irradiated fuel," the MPS2 Fuel Handling Accident (FHA) was analyzed using inputs approved in Amendment 298.
In the recently irradiated FHA, the MPS2 control room was assumed not to isolate and the control room emergency ventilation assumed not to operate.
The FHA analysis determined 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> of decay was required to ensure control room doses do not exceed the limit of 5 rem TEDE as defined in Regulatory Guide (RG) 1.183 and 10CFR50.67. The inputs assumed in the recently irradiated FHA are listed in the table on page 2.
07-0790 Control Room Habitability Supplemental Information Page 2 of 2 MPS2 FHA I t
npu s Noble gas inventory (Curies)
Xe-131m 8.615E+05 Xe-133m 4.808E+06 Xe-133 1.569E+08 Xe-135m 3.104E+07 Xe-135 5.658E+07 Xe-137 1.316E+08 Xe-138 1.316E+08 Kr-83m 1.080E+07 Kr-85 1.194E+06 Kr-85m 20451 E+07 Kr-87 4.860E+07 Kr-88 6.865E+07 Kr-89 8.593E+07 Iodine inventory (Curies) 1-130 5.101E+06 1-131 7.719E+07 1-132 1.105E+08 1-133 1.504E+08 1-134 1.666E+08 1-135 1o407E+08 Core release fraction 1-131 12%
Kr-85 30%
Other Halogens 10%
Other Noble Gases 10%
Iodine chemical form Elemental 57%
Organic 43%
Decontamination factor Iodine 200 Noble Gases 1
Peaking factor 1.83 Release rate 8289%/day (99.9% of activity released within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)
Fuel damaae 1 assembly Dose conversion factors FGR11 and FGR12 Control room volume 35,656 ft3 Unfiltered intake flow rate into control room 800 cfm o-8 hour control room XlQ 3.00E-03 sec/m3 Control room breathing rate 3.5E-04 m3/sec Occupancy factors 0- 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1.0 24 - 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> 0.6 96 - 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> 004 The resulting dose to control room occupants from a MPS2 recently irradiated FHA, assuming 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> of decay and no control room isolation or emergency ventilation is 4.86 rem.
07-0790 Control Room Habitability Supplemental Information ATTACHMENT 2 MPS3 FUEL HANDLING ACCIDENT ANALYSIS DATA DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3
07-0790 Control Room Habitability Supplemental Information Page 1 of 4 Fuel Handling Accident Data Millstone Power Station Unit 3
Background:
On July 13, 2007, Dominion Nuclear Connecticut, Inc. (DNC) submitted a request for an amendment to the Technical Specification (TS) for Millstone Power Station Units 2 and 3 (MPS2 and MPS3).
The proposed amendment would revise the TS requirements related to Control Room envelope habitability.
This attachment contains Fuel Handling Accident (FHA) analysis input data for Millstone Power Station Unit 3 (MPS3), providing additional information regarding the term "recently irradiated fuel".
Discussion:
The recently irradiated fuel handling accident dose analysis was performed with a controlled version of the computer code RADTRAD-NAI 1.1a (QA).
Innovative Technology Solutions of Albuquerque, New Mexico developed the RADTRAD code for the NRC.
The original version of the NRC RADTRAD code was documented in NUREG/CR-6604.
The Numerical Applications, Inc.
(NAI) version of RADTRAD was originally derived from NRCIITS RADTRAD, version 3.01.
Subsequently, RADTRAD-NAI was changed to conform to NRC/ITS RADTRAD, Version 3.02 with additional modifications to improve usability.
The RADTRAD-NAI code is maintained under NAI's QA program, which conforms to the requirements of 10CFR50, Appendix B.
The RADTRAD-NAI 1.1 a (QA) computer code was used in the MPS3 Alternate Source Term (AST) submittal that was approved by the NRC in Amendment 232, dated September 15, 2006.
RADTRAD-NAI 1.1a (QA) was also used in the GSI-191 submittal (Amendment 233) and the Stretch Power Uprate (SPU)
License Amendment Request submitted on July 3, 2007.
Two independent "recently irradiated fuel" FHA's were analyzed.
To define the decay time for "recently irradiated fuel", the FHA was analyzed using current design FHA inputs as approved in Amendment 232, as well as FHA inputs in the recent SPU submittal.
The current design basis MPS3 FHA uses the AST and core power of 3,636 MWt.
On July 3, 2007 Dominion submitted a request for a license amendment to increase the unit's authorized core power from 3411 MWt
07-0790 Control Room Habitability Supplemental Information Page 2 of 4 to 3650 MWt. The submitted SPU design basis MPS3 FHA uses AST and a core power of 3723 MWt (102% of 3650MWt).
In the recently irradiated FHA analyses the MPS3 control room was assumed not to isolate and the control room emergency ventilation assumed not to operate.
The current design FHA analysis determined 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> of decay are required to maintain control room doses below the limit of 5 rem TEDE as defined in Regulatory Guide (RG) 1.183 and 10CFR50.67.
The inputs assumed in the current design FHA are listed in Table 1 and are the same used in Amendment 232.
The SPU FHA analysis determined 350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> of decay are required to ensure control room doses do not exceed the 5 rem limit.
The inputs used in the SPU FHA are listed in Table 2 and are the same assumed in the recently submitted SPU License Amendment Request.
The SPU FHA analysis also assumed the unavailability of control room isolation and the control room emergency ventilation system.
See page 3 of this attachment for Table 1 - MPS3 FHA Inputs (Current Design).
See page 4 of this attachment for Table 2 - MPS3 FHA Inputs (SPU).
07-0790 Control Room Habitability Supplemental Information Page 3 of 4 Table 1 - MPS3 FHA Inputs (Current Design)
Noble gas inventory (Curies)
Xe-133 1.980E+08 Xe-135m 3.589E+07 Xe-135 6.440E+07 Xe-138 8.610E+07 Kr-85 1.075E+06 Kr-85m 2.590E+07 Kr-87 4.755E+07 Kr-88 7.060E+07 Iodine inventory (Curies) 1-131 9.710E+07 1-132 1.416E+08 1-133 2.008E+08 1-134 2.146E+08 1-135 1.864E+08 Core release fraction Halogens 8%
Noble Gases 10%
Iodine chemical form Elemental 57%
OrQanic 43%
Decontamination factor Iodine 200 Noble Gases 1
Peaking factor 1.7 Release rate 8289%/day (99.9% of activity released within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)
Fuel damage 1 dropped assembly plus 50 rods in the impacted assembly Dose conversion factors FGR11 and FGR12 Control room volume 2.38E+05 ft3 Unfiltered intake flow rate into control 1595 cfm room o-8 hour control room XlQ 2.82E-03 sec/m3 Control room breathinQ rate 3.5E-04 m3/sec Occupancy factors 0-24 hours 1.0 24 - 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> 0.6 96 - 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> 0.4 The resulting dose to control room occupants from a MPS3 recently irradiated FHA, assuming core power of 3636 MWt, 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> of decay and no control room isolation or emergency ventilation is 4.74 rem.
07-0790 Control Room Habitability Supplemental Information Page 4 of 4 Table 2 - MPS3 FHA Inputs (SPU)
Noble gas inventory (Curies)
Xe-133 2.030E+08 Xe-135m 3.660E+07 Xe-135 5.600E+07 Xe-138 8.460E+07 Kr-85 1.050E+06 Kr-85m 2.270E+07 Kr-87 4.140E+07 Kr-88 6.110E+07 Iodine inventory (Curies) 1-131 9.890E+07 1-132 1.450E+08 1-133 2.030E+08 1-134 2.130E+08 1-135 1.890E+08 Fuel damage 1 dropped assembly plus 19 rods in the impacted assembly. 67% of the rods do not comply with footnote 11 of RG 1.183.
Core release fractions 33% of the rods meet RG 1.183 1-131 8%
Kr-85 10%
All others 5%
67% of rods exceed RG 1.183 1-131 12%
Kr-85 30%
All others 10%
Iodine chemical form Elemental 57%
Organic 43%
Decontamination factor Iodine 200 Noble Gases 1
Peaking factor 1.7 Release rate 8289%/day (99.9% of activity released within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)
Dose conversion factors FGR11 and FGR12 Control room volume 2.38E+05 ft3 Unfiltered intake flow rate into control room 1595 cfm o-8 hour control room XlQ 2.82E-03 sec/m3 Control room breathing rate 3.5E-04 m3/sec Occupancy factors 0- 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1.0 24 - 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> 0.6 96 - 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> 0.4 The resulting dose to control room occupants from a MPS3 recently irradiated FHA, assuming SPU 102% core power of 3723 MWt, 350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> of decay and no control room isolation or emergency ventilation is 4.83 rem.