ML20196H090
| ML20196H090 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/03/1998 |
| From: | Stephen Dembek NRC (Affiliation Not Assigned) |
| To: | Bowling M, Loftus P NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| TAC-MA3672, NUDOCS 9812080205 | |
| Download: ML20196H090 (6) | |
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December 3, 1998 Mr. Mirtin L Bowling, Jr.
Recov::ry Officer - Technical Services Northeast Nuclear Energy Company c/o Ms. Patricia A. Loftus Director-Regulatory Affairs i
P.O. Box 128 Waterford, CT 06385
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST - MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 (TAC NO. MA3672)
Dear Mr. Bowling:
By [[letter::B17413, Application for Amend to License DPR-65,revising TS Sections 3.3.2.1,3.4.6.2,3.4.8,3.6.2.1,3.6.5.1,3.7.6.1 & 3.9.15 as Result of Revised MSLB Analyses & Revised Determinations of Radiological Consequences of MSLB & LOCA|letter dated September 28,1998]], Northeast Nuclear Energy Company requested a license amendment regarding the control room ventilation system. The NRC staff has completed a preliminary review of your request and has identified issues that require additional information.
Please respond to the enclosed request for additionalinformation within 2 weeks of your receipt of this letter. This response schedule was agreed to by Ravi Joshi of your staff. Should a situation occur that would prevent you from meeting this due date, please contact me at 301-415-1455.
Sincerely, i
tephen bek, Project Manager Millstone Project Directorate Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-336
Enclosure:
As stated cc w/cncl: See next page Distribution:
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'%..'...,o December 3, 1998 Mr. Martin L. Bowling, Jr.
Recovery Officer - Technical Services Northeast Nuclear Energy Company c/o Ms. Patricia A. Loftus Director-Regulatory Affairs P.O. Box 128 Waterfoiti, CT 06385
SUBJECT:
- REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST-MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 (TAC NO. MA3672)
Dear Mr. Bowling:
By [[letter::B17413, Application for Amend to License DPR-65,revising TS Sections 3.3.2.1,3.4.6.2,3.4.8,3.6.2.1,3.6.5.1,3.7.6.1 & 3.9.15 as Result of Revised MSLB Analyses & Revised Determinations of Radiological Consequences of MSLB & LOCA|letter dated September 28,1998]], Northeast Nuclear Energy Company requested a license amendment regarding the control room ventilation system. The NRC staff has completed a preliminary review of your request and has identified issues that require additionalinformation.
Please respond to the enclosed request for additional information within 2 weeks of your receipt of this letter. This response schedule was agreed to by Ravi Joshi of your staff. Should a situation occur that would prevent you from meeting this due date, please contact me at 301-415-1455.
Sincerely,
/
Stephen Dembek, Project Manager Millstone Project Directorate Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-336
Enclosure:
As stated cc w/ encl: See next page
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Millst:ne Nucle:r Power St: tion i
Unit 2 ec.
i Lillian M. Cuoco, Esquire Mr. F. C. Rothen Senior Nuclear Counsel Vice President - Work Services l
Northeast Utilities Service Company Northeast Utilities Service Company P. O. Box 270 P. O. Box 128 Hartford, CT 06141-0270 Waterford, CT 06385 l
Mr. John Buckingham Emest C. Hadley, Esquire Department of Public Utility Control 1040 B Main Street Electric Unit P.O. Box 549 I
10 Liberty Square West Wareham, MA 02576 New Britain, CT 06051 Mr. John F. Streeter Edward L. Wilds, Jr., Ph.D.
Recovery Officer - Nuclear Oversight Director, Division of Radiation Northeast Utilities Service Company Department of Enviror. mental Protection P. O. Box 128 79 Elm Street Waterford, CT 06385 Hartford, CT 06106-5127 Mr. John Carlin Regional Administrator, Region i Vice President-Human Services U.S. Nuclear Regulatory Commission Northeast Utilities Service Company 475 Allendale Road P. O. Box 128 King of Prussia, PA 19406 Waterford, CT 06305 I
First Selectmen Mr. Allan Johanson, Assistant Director Town of Waterford Office of Policy and Management i
15 Rope Ferry Road Policy Development and Planning Waterford, CT 06385 Division 450 Capitol Avenue - MS# 52ERN Mr. Wayne D. Lanning, Director P. O. Box 341441 i
Millstone Inspections Hartford, CT 06134-1441 Office of the Regional Administrator 475 Allendale Road Mr. M. H. Brothers King of Prussia, PA 19406-1415 Vice President - Operations Northeast Nuclear Energy Company Charles Brinkman, Manager P.O. Box 128 Washington Nuclear Operations Waterford, CT 06385 ABB Combustion Engineering 12300 Twinbrook Pkwy, Suite 330 Mr. J. A. Pr ce i
Rockville, MD 20852 Director-U1it 2 Northeast huclear Energy Company Senior Resident inspector P.O. Box 123 Millstone Nuclear Power Station Waterford, CT 06385 c/o U.S. Nuclear Regulatory Commission P.O. Box 513 Niantic, CT 06357 l
Millst:ne Nucle:r Power St' tion Unit 2 -
cc:
1 Mr. Leon J. Olivier Attomey Nicholas J. Scobbo, Jr.
Chief Nucier Officer-Millstone Ferriter, Scobbo, Caruso, Rodophele, PC Northeast Nuclear Energy Company 1 Beacon Street,11th Floor P.O. Box 128 Boston, MA 02108 Waterford, CT 06385 l
Mr. J. P. McElwain Citizens Regulatory Commission Recovery Officer-Millstone Unit 2 ATTN: Ms. Susan Perry Luxton Northeast Nuclear Energy Company 180 Great Neck Road P. O. Box 128 '
Waterford, CT 06385 Waterford, Connecticut 06385 Deborah Katz, President Citizens Awareness Network P. O. Box 83 Shelbume Falls, MA 03170 The Honorable Terry Concannon Co-Chair Nuclear Energy Advisory Council Room 4035 Legislative Office Building Capitol Avenue Hartford, CT 06106 Mr. Evan W. Woollacott Co-Chair Nuclear Energy Advisory Council 128 Terry's Plain Road Simsbury, CT 06070 Little Harbor Consultants, Inc.
Millstone -ITPOP Project Office P. O. Box 0630 Niantic, CT 06357-0630 Mr. Daniel L. Curry Project Director Parsons Power Group inc.
2675 Morgantown Road Reading, PA 19607 I
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REQUEST FOR ADDITIONAL INFORMATION MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 DOCKET NO. 50-336 i
1.
The control room volume identified in the submittal is approximately 50% of the value shown in the current Final Safety Analysis Report (FSAR). Please explain how the volume has been reduced.
2.
The staff understands that you have modeled iodine removal by containment sprays as a single region model using spray lambdas that have been adjusted to account for the fact that the spray coverage is only 68%. Please provide a description of how this adjustment was made.
3.
The staff understands that the release from the affected steam generator was determined by (1) assuming the activity in the steam generator blows down in 750 seconds; and (2) multiplying the technical specifications (TS) limiting condition for operation (LCO) primary-to-secondary leakrate by the release duration of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> less 750 seconds. Also, the release from the intact steam generator was determined by multiplying the TS LCO primary-to-secondary leakrate by the release duration of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> with the iodine release reduced by 0.01 to account for partitioning. Please confirm our understanding.
4.
Page 14.8-11 of the FSAR addresses the radiological consequences of post-loss of-coolant accident (LOCA) containment purging. Your mark-up for Table 14.8.4-1 indicates i
that the X/O value has increased by a factor of five over that used previously, including that used in the purging analysis. However, it does not appear that you updated the purging analysis. The mark-up for Table 14.8.4-2 of the FSAR deletes the purge doses.
The staff understands that you will be making an additional submittal addressing the purge doses. Please confirm our understanding.
5.
The staff has reviewed your responses in Attachment 6 of your submittal. In your conclusion that starts on page 9 of Attachment 6, you noted that the control room dose assumptions of negligible bypass leakage (6.44E-6 scfm) were not questioned while a bypass leakage of 1.7% of the daily containment leakage rate was mandated for calculating the 10 CFR Part 100 offsite doses. Please explain why the control room dose calculation was not updated at that time to use the same assumption agreed to by the NRC staff for offsite doses. Since technical specifications represent the initial conditions assumed in design-basis accident analyses, why is the applicable TS not based on the more restrictive 6.44E-6 scfm?
6.
The amendment proposes to increase the infiltration rate for the control room by 30%.
Your amendment addresses the consequences from the main steamline break (MSLB) and LOCA at Unit 2. Please provide a statement addressing the impact of this increased infiltration in conjunction with other Unit 2 accidents and accidents at Unit 3. Please provide a statement addressing the impact that the increased Unit 2 MSLB doses have on the Unit 3 control room habitability.
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7.
Ynur submittal requested modification of the FSAR for Millstone, Unit 2, regarding iodine removal from the containment atmosphere. The modification consists of including credit for the elemental and particulate iodine removal by the containment sprays in addition to the iodine already removed by an instantaneous deposition on the containment walls. In i
Enclosure
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, the FSAR it is assumed that 50% of the iodine released from the damaged fuelis i
transferred to the containment and 50% of it is instantaneously deposited on the l
containment walls. The iodine available for removal by the containment sprays amounts, therefore, to 25% of the totaliodine released from the fuel. In Table 14.8.4-1 of the amended FSAR, you listed numerical values for removal coefficients for this lodine which could exist in elemental or particulate chemical form. In order to complete its review, the staff needs to have more information on your analysis. The following information is needed:
,3 a.
Detailed description of the calculations of the removal coefficients for elemental and particulate iodine by the containment sprays. The description should include: (a) the methodology used (whether it was based on Standard Review Plan (SRP) 6.5.2 or on some other methods), and (b) the parameters used for the containment and the containment spray system calculations.
b.
Description of the calculation of the decontamination factor for elementaliodine.
The description should include the methodology and the assumptions used in the calculation. As specified in SRP 6.5.2, the role of the decontamination factoris to determine the maximum amount of elementaliodine that could be removed from the containment atmosphere by sprays. This upper limit for iodine removal exists because, during spray operation, the water in the containment sump may reach saturation point and will not dissolve any more elemental iodine. Once this point is attained, containment sprays lose their iodine removal capability. In light of this consideration, you should describe how you used your calculated decontamination factor in determining the upper limit for elemental iodine removal from the containment atmosphere by sprays.
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