L-MT-08-042, Extended Power Uprate: Acceptance Review Supplemental Information Package 5: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| (One intermediate revision by the same user not shown) | |||
| Line 3: | Line 3: | ||
| issue date = 06/05/2008 | | issue date = 06/05/2008 | ||
| title = Extended Power Uprate: Acceptance Review Supplemental Information Package 5 | | title = Extended Power Uprate: Acceptance Review Supplemental Information Package 5 | ||
| author name = O'Connor T | | author name = O'Connor T | ||
| author affiliation = Nuclear Management Co, LLC | | author affiliation = Nuclear Management Co, LLC | ||
| addressee name = | | addressee name = | ||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:Montkelh Nuclear Generatina Plant EwnmltdrdtbWEtrwllones Operated by Nudear Management Company, LLC June 5,2008 L-MT-08-042 10 CFR 50.90 U. S. Nuclear Regulatory Commission | {{#Wiki_filter:Montkelh Nuclear Generatina Plant EwnmltdrdtbWEtrwllones Operated by Nudear Management Company, LLC June 5,2008 L-MT-08-042 10 CFR 50.90 U. S. Nuclear Regulatory Commission A T N : Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License License No. DPR-22 Monticello Extended Power Uprate (USNRC TAC MD83981: | ||
Acceptance Review Supplemental lnforrnation Package 5 | |||
==References:== | ==References:== | ||
I) NMC Letter to USNRC, "License Amendment Request: Extended Power Uprate," dated March 31,2008 2) NMC Letter to USNRC, "Monticello Extended Power Uprate (USNRC TAG MD8398): Acceptance Review Supplement Regarding Radiological Analysis," dated May 20,2008 3) NMC Letter to USNRC, "Monticello Extended Power Uprate (USNRC TAC MD8398): Acceptance Review Supplemental Information," dated May 28, 2008 4) NMC Letter to USNRC, 'Monticello Extended Power Uprate (USNRC TAC MD8398): Acceptance Review Supplemental Information Package 3," dated May 30,2008 5) NMC Letter to USNRC, "Monticello Extended Power Uprate (USNRC TAC MD8398): Acceptance Review Supplemental Information Package 4," dated June 3,2008 Pursuant to | I)NMC Letter to USNRC, "License Amendment Request: Extended Power Uprate," | ||
763.295. | dated March 31,2008 2 ) NMC Letter to USNRC, "Monticello Extended Power Uprate (USNRC TAG MD8398): Acceptance Review Supplement Regarding Radiological Analysis," | ||
dated May 20,2008 | |||
: 3) NMC Letter to USNRC, "Monticello Extended Power Uprate (USNRC TAC MD8398): Acceptance Review Supplemental Information," dated May 28, 2008 | |||
: 4) NMC Letter to USNRC, 'Monticello Extended Power Uprate (USNRC TAC MD8398): Acceptance Review Supplemental Information Package 3," dated May 30,2008 | |||
: 5) NMC Letter to USNRC, "Monticello Extended Power Uprate (USNRC TAC MD8398): Acceptance Review Supplemental Information Package 4," dated June 3,2008 Pursuant to 10 CFR 50.90, Nuclear Management Company, LLC (NMC), requested in Reference 1 approval of amendments to the Monticello Nuclear Generating Plant (MNGP) Renewed Operating License (OL) and Technical Specfications (TS) to increase the maximum power level authorized from 1775 megawatts thermal (MWt) to 1870 MWt, an approximate five percent increase in the current licensed thermal power (CLTP). The proposed request for Extended Power Uprate (EPU) represents an increase of approximately 12 percent above the Original Licensed Thermal Power (OLTP). The Monticello EPU application was supplemented on May 20, 2008, May 28,2008, May 30,2008, and June 3,2008 by References 2 , 3 , 4 and 5. | |||
2807 West County Road 75 Monticello, Minnesota 563624637 Telephone: 763.295.5151 Fax: 783.295.1454 | |||
Document Control Desk Page 2 In a teleconference held May 2, 2008, the NRC staff indicated that additional information would be necessary for the Electrical Engineering Branch (EEEB) to complete the acceptance review of the Monticello EPU license amendment request (IAR). The questions were formalized and emailed to NMC on May 15,2008. On May 28,2008, NMC submitted responses (Reference 3) to EEEB Questions 2,3,and 4. of this letter contains the response to EEEB Question I. | |||
NMC has reviewed the No Significant Hazards Consideration and the Environmental Consideration submitted with Reference 1 relative to the enclosed supplemental information. NMC has determined that there are no changes required to either of these sections of Reference 1. | |||
Commitment Summan, This letter makes no new commitments and does not change any existing commitments. | |||
I declare under penalty of perjury that the foregoing is true and correct. | |||
on June 5 A 008. | |||
resident, Monticello Nuclear Generating Plant Company, LLC cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce Enclosure | |||
Enclosure 1 to L-MT-08-042 Electrical Engineering Branch Question 1 and Response 1 | |||
Enclosure 1 | |||
: 4) EEEB - ELECTRICAL ENGINEERING BRANCH NRC Question | |||
: 1) In Section 2.3 of the LAR under the section titled 'Outside Containment', the licensee stated the following: | |||
"The total integrated doses (normal plus accident) for EPU conditions were evaluated and determined not to adversely affect qualification of most of the EQ equipment located outside of containment. Equipment not qualified to the new environmental conditions at EPU will be reanalyzed, re-qualified, or replaced prior to implementation of EPU." | |||
In order for the Electrical Engineering Branch (EEEB) to start its review, the full EQ analysis must be completed. This includes any reanalysis, re-qualification, or replacement of equipment. The licensee must also describe how the equipment was evaluated (e.g., calculations, assessments, etc.) and show how the equipment remains bounded (i.e., provide the original design parameters and the updated values including the supporting calculations). | |||
NMC Response: | NMC Response: | ||
The responses to EEEB Questions 2, 3 and 4 were submitted in Monticello letter L-MT-08-039 on May 28, 2008. The following response is regarding EEEB Question 1. | The responses to EEEB Questions 2, 3 and 4 were submitted in Monticello letter L-MT-08-039 on May 28, 2008. The following response is regarding EEEB Question 1. | ||
Introduction The following information provides more detail regarding the analyses that have been completed relative to the qualification of electrical equipment outside containment. As required, the analyses have addressed the radiation, pressure, temperature and flooding effects from operation at extended power uprate (EPU) conditions. This information describes how the equipment was evaluated and notes where further action, per the applicable regulatory criteria and the Monticello Environmental Qualification (EQ) | |||
Introduction The following information provides more detail regarding the analyses that have been completed relative to the qualification of electrical equipment outside containment. As required, the analyses have addressed the radiation, pressure, temperature and flooding effects from operation at extended power uprate (EPU) conditions. This information describes how the equipment was evaluated and notes where further action, per the applicable regulatory criteria and the Monticello Environmental Qualification (EQ) Program, is necessary prior to implementation of EPU. | Program, is necessary prior to implementation of EPU. | ||
Normal Temperature Evaluation An evaluation was completed to assess the impact EPU will have on the normal design temperatures of the Reactor Building. A calculation supports the normal area temperature data for the EQ Program. This calculation uses both survey data and calculated data as inputs. For the Drywell and the Steam Chase, a calculation provides a basis for the normal ambient temperatures. The EPU evaluation indicates no change in normal Drywell temperatures for EPU and a slight increase in normal Steam Chase temperature (less than one degree). This small temperature increase is bounded by the temperature value currently used in the EQ program for the steam chase. Normal plant area ambient temperature will continue to be assessed by the EQ program in lieu of using the maximum design temperature for assessing qualified lifetimes. As such, there is no impact of EPU conditions on normal plant temperature inputs to qualified life assessments. | |||
Normal Temperature Evaluation An evaluation was completed to assess the impact EPU will have on the normal design temperatures of the Reactor Building. A calculation supports the normal area temperature data for the EQ Program. This calculation uses both survey data and calculated data as inputs. For the Drywell and the Steam Chase, a calculation provides a basis for the normal ambient temperatures. The EPU evaluation indicates no change in normal Drywell temperatures for EPU and a slight increase in normal Steam Chase temperature (less than one degree). This small temperature increase is bounded by the temperature value currently used in the EQ program for the steam chase. Normal plant area ambient temperature will continue to be assessed by the EQ program in lieu of using the maximum design temperature for assessing qualified lifetimes. As such, there is no impact of EPU conditions on normal plant temperature inputs to qualified life assessments. | Page 1 of 19 | ||
Page | |||
Enclosure 1 Normal Radiation Dose The EPU evaluation for radiation levels generally indicates an increase of 13 percent for the Reactor Building dose and no change for most Turbine Building normal doses as the result of EPU (some areas of Turbine Building have dose rate increases). This evaluation provides survey data for most plant areas and identifies the applicable increase effect for each plant area outside the Drywell. | |||
The current basis for normal radiation doses in the EQ program is provided by calculation. This calculation documents actual survey dose rate data for all of the Reactor Building and the Turbine Building. The tables below relate the normal radiation doses in the calculation for reactor and turbine building. | The current basis for normal radiation doses in the EQ program is provided by calculation. This calculation documents actual survey dose rate data for all of the Reactor Building and the Turbine Building. The tables below relate the normal radiation doses in the calculation for reactor and turbine building. | ||
Reactor Building, Normal 60 Year Doses Current EQ Program Basis Projected 60 year Normal EPU Dose RB Volume | Reactor Building, Normal 60 Year Doses Current EQ Program Basis Projected 60 year Normal EPU Dose Predicted EPU Dose Current Dose rate Effect EPU 60 yr RB Volume Rate Survey 60 year (survey) (see Dose (Rad) | ||
(Spec) mR/Hr date Dose (Rad) mR/Hr note) (see note) 1 (B.1.4) 200 01/18/03 1.39E+05 160 180.8 9.51E+04 2 (B.1.4) 200 01/18/03 1.39E+05 Not surv 3 (B.1.4) 100 12/29/02 6.94E+04 50 56.5 2.97E+04 4 (B.1.4) 100 12/29/02 6.94E+04 Not surv 5 (B.1.3) 1 08/18/02 6.94E+02 Not surv 6 (B.1.2) 1000 12/21/02 6.94E+05 100 113 5.94E+04 7 (B.1.10) 1 06/26/00 6.94E+02 Not surv 8 (B.1.2) 46 12/21/03 3.19E+04 3 3.39 1.78E+03 9 (B.1.6) 120 12/15/02 8.33E+04 50 56.5 2.97E+04 10 (B.1.6) 90 12/15/02 6.25E+04 30 33.9 1.78E+04 11 (B.1.6) 140 01/19/03 9.72E+04 60 67.8 3.57E+04 12 (B.1.6) 150 01/19/03 1.04E+05 30 33.9 1.78E+04 13 (B.1.8) 80 01/12/03 5.55E+04 20 22.6 1.19E+04 14 (B.1.9/11) 160 08/03/02 1.11E+05 60 67.8 3.57E+04 15 (B.1.9) 350 03/10/02 2.43E+05 50 56.5 2.97E+04 16 (B.1.7) 4000 07/01/98 2.78E+06 2000 2260 1.19E+06 17 (B.1.9) 4 12/29/02 2.78E+03 4 4.52 2.38E+03 18 (B.1.10) 400 01/21/03 2.78E+05 55 62.15 3.27E+04 19 (B.1.10/12) 42 12/29/02 2.92E+04 4 4.52 2.38E+03 20 (B.1.8) 80 01/18/03 5.55E+04 30 33.9 1.78E+04 21 (B.1.14) 100 02/08/03 6.94E+04 30 33.9 1.78E+04 22 (B.1.14) 80 12/15/02 5.55E+04 1 1.13 5.94E+02 Page 2 of 19 | |||
Enclosure 1 Reactor Building, Normal 60 Year Doses Current EQ Program Basis Projected 60 year Normal EPU Dose Predicted EPU Dose Current Dose rate Effect EPU 60 yr RB Volume Rate Survey 60 year (survey) (see Dose (Rad) | |||
(Spec) mR/Hr date Dose (Rad) mR/Hr note) (see note) 23 (B.1.14) 80 02/10/02 5.55E+04 1 1.13 5.94E+02 24 1 01/18/03 6.94E+02 Not surv 25 1 12/15/02 6.94E+02 1 1.13 5.94E+02 26 18 01/18/03 1.25E+04 4 4.52 2.38E+03 27 (B.1.13/15) 260 08/12/02 1.81E+05 30 33.9 1.78E+04 28 (B.1.5) 40 01/04/02 2.78E+04 40 45.2 2.38E+04 29 (B.1.5) 20 01/04/02 1.39E+04 20 22.6 1.19E+04 30 (B.1.5) 800 01/04/02 5.55E+05 80 90.4 4.75E+04 31 (B.1.5) 2200 01/04/02 1.53E+06 2200 2486 1.31E+06 32 (B.1.5) 1600 01/04/02 1.11E+06 1600 1808 9.51E+05 33 (B.1.13) 680 08/12/02 4.72E+05 3 3.39 1.78E+03 34 (B.1.18) 40 12/15/02 2.78E+04 6 6.78 3.57E+03 35 (B.1.17) 5 12/15/02 3.47E+03 4 4.52 2.38E+03 36 (B.1.21) 1 08/26/02 6.94E+02 1 1.13 5.94E+02 37 (B.1.21) 1 08/26/02 6.94E+02 1 1.13 5.94E+02 38 (B.1.21) 1 08/26/02 6.94E+02 1 1.13 5.94E+02 39 (B.1.21) 1 08/26/02 6.94E+02 1 1.13 5.94E+02 40 (B.1.16) 2 08/26/02 1.39E+03 1 1.13 5.94E+02 41 (B.1.16) 2 01/18/03 1.39E+03 1 1.13 5.94E+02 42 (B.1.16) 20 12/15/02 1.39E+04 1 1.13 5.94E+02 43 (B.1.19) 700 12/27/02 4.86E+05 500 565 2.97E+05 44 (B.1.20) 200 12/27/02 1.39E+05 5 5.65 2.97E+03 45 (B.1.19) 2 12/27/02 1.39E+03 2 2.26 1.19E+03 46 (B.1.19) 200 12/27/02 1.39E+05 6 6.78 3.57E+03 47 (B.1.19) 1 12/27/02 6.94E+02 Not surv 48 36 02/06/03 2.50E+04 7 7.91 4.16E+03 Note: EPU 60-year basis dose was determined by increasing the shown dose rate by 13 percent taken over the number of hours over 60 years (365.25 days/year used to account for leap years). No equivalent 60 year dose was determined for areas where the EPU evaluation did not provide dose rate values. As illustrated above, the projected 60-year normal dose due to EPU is bounded by the specified doses used in the current EQ Program for the Reactor Building. | |||
Page 3 of 19 | |||
Enclosure 1 Turbine Building, Normal 60 Year Doses Current EQ Program Basis Normal Dose Projected 60 year Normal EPU Dose Current Dose Rate Survey 60 year survey EPU EPU 60 yr TB Volume mR/Hr Date Dose (Rad) (mRem/hr) Effect Dose (Rad) 1 (B.1.24) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 2 (B.1.24) 1 12/18/02 6.94E+02 1 1130% 5.94E+03 Increase 3 (B.1.24) 1 12/18/02 6.94E+02 1 1130% 5.94E+03 Increase 4 (B.1.24) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 5 (B.1.24) 8 12/18/02 5.55E+03 1-2 No 1.05E+03 change 6 (B.1.24) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 7 (B.1.24) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 8 (B.1.24) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 9 (B.1.24) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 10 (B.1.24) 2 12/18/02 1.39E+03 1 No 2.63E+03 1-5 change 11 (B.1.24) 200 01/29/03 1.39E+05 1 - 10 No 1.58E+04 30 change 12 (B.1.24) 120 05/01/02 8.33E+04 5 - 30 No 1.58E+04 change 13 (B.1.24) 2400 02/07/02 1.67E+06 2 - 1500 25 - 33% 1.05E+06 Increase 14 (B.1.24) 4000 07/01/98 2.78E+06 5 - 1800 Up to 1.07E+07 1130% | |||
Increase 15 (B.1.24) 8 12/18/02 5.55E+03 1 No 5.26E+02 change 16 (B.1.24) 8 12/18/02 5.55E+03 1 No 5.26E+02 change 17 (B.1.24) 8 12/18/02 5.55E+03 1 No 5.26E+02 change 18 (B.1.24) 8 12/18/02 5.55E+03 1 No 5.26E+02 change 19 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 20 (B.1.23) 46 11/13/02 3.19E+04 Not No surveyed change 21 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change Page 4 of 19 | |||
Enclosure 1 Turbine Building, Normal 60 Year Doses Current EQ Program Basis Normal Dose Projected 60 year Normal EPU Dose Current Dose Rate Survey 60 year survey EPU EPU 60 yr TB Volume mR/Hr Date Dose (Rad) (mRem/hr) Effect Dose (Rad) 22 (B.1.23) 12 11/13/02 8.33E+03 1 No 5.26E+02 change 23 (B.1.23) 1 12/18/02 6.94E+02 1-2 No 1.05E+03 change 24 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 25 (B.1.23) 2 12/04/02 1.39E+03 1 1130% 5.94E+03 Increase 26 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 27 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 28 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 29 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 30 (B.1.23) 8 02/06/02 5.55E+03 1 No 5.26E+02 change 31 (B.1.23) 1 02/06/02 6.94E+02 1 No 5.26E+02 change 32 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 33 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 34 (B.1.23) 1 03/28/02 6.94E+02 1 No 5.26E+02 change 35 (B.1.23) 1 03/28/02 6.94E+02 1 No 5.26E+02 change 36 (B.1.23) 1 03/28/02 6.94E+02 1 No 5.26E+02 change 37 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 38 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 39 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 40 (B.1.23) 60 12/18/02 4.17E+04 1-2 No 1.05E+03 change 41 (B.1.22) 80 05/08/00 5.55E+04 1-3 No 1.58E+03 change 42 (B.1.22) 3000 05/08/00 2.08E+06 1 - 1000 2 - 9% 1.72E+06 10 - 3000 Increase Page 5 of 19 | |||
Enclosure 1 Turbine Building, Normal 60 Year Doses Current EQ Program Basis Normal Dose Projected 60 year Normal EPU Dose Current Dose Rate Survey 60 year survey EPU EPU 60 yr TB Volume mR/Hr Date Dose (Rad) (mRem/hr) Effect Dose (Rad) 43 (B.1.23) 1 12/18/02 6.94E+02 Not No surveyed change 44 (B.1.22) 3000 05/08/00 2.08E+06 1 - 1000 2 - 9% 1.72E+06 10 - 3000 Increase Note: EPU 60-year basis dose was determined by increasing the highest shown dose rate by the EPU Effect value and then multiplying by the number of hours over 60 years (365.25 days/year used to account for leap years). No equivalent 60 year dose was determined for areas where the EPU evaluation did not provide dose rate values. | |||
Based on the above, it is observed that the projected 60 year normal doses in Turbine Building Volumes 2, 3, 10, 14, 23, and 25 will increase from the current specified EQ Program data. These volumes, with the exception of 14, remain below the radiation harsh classification threshold as defined by the EQ program. | |||
Accident Radiation Doses The EPU evaluation of the impacts of radiation on equipment qualification and the supporting vendor calculation performed by Alion provides the bases for EPU impacts on the EQ program from post-LOCA accident doses. The resulting EPU doses and the indicated increases by location are shown below. | |||
% EPU Dose EPU 180-day TID, LOCATION Increase (Rads) | |||
Drywell 2.5 5.44E+07 HPCI Room - Elevation 896' 7.3 2.73E+06 RCIC Room - Elevation 896' 7.5 1.82E+06 RHR Rooms - Elevation 896' 4.3 2.72E+07 RWCU Pump Room - Elevation 962' 7.8 2.52E+06 Torus Compartment - Elevation 896' 3.5 1.19E+07 Main Steam Chase - Elevation 935' 7.3 2.73E+06 LPCI Valve Injection Room - Elevation 7.8 2.52E+06 935' Reactor Building - Elevation 935' E 7.8 2.52E+06 Reactor Building - Elevation 935' W 7.8 2.52E+06 Reactor Building - Elevation 935' SE 7.8 2.52E+06 Reactor Building - Elevation 935' SW 7.8 2.52E+06 Reactor Building - Elevation 962' S 7.8 2.52E+06 Reactor Building - Elevation 962' E 7.8 2.52E+06 Reactor Building - Elevation 962' NW 7.8 2.52E+06 Page 6 of 19 | |||
Accordingly, the revised combined 60-year normal doses and the 180-day accident doses under EPU have the potential to impact the qualification of EQ components in the Reactor Building. Using the methods prescribed in the individual EQ calculation files for operating time and distance factors, the revised normal and accident doses were evaluated and compared to the qualified dose as indicated below (for conservatism, the normal dose was increased by +13 percent). For the equipment located in the Drywell, Beta dose was also considered. The Beta dose specified in the Monticello EQ Program is taken from the DOR Guidelines (Division of Operating Reactors - | Enclosure 1 Reactor Building - Elevation 985' N 7.9 1.29E+04 Reactor Building - Elevation 985' SW 7.9 1.29E+04 Reactor Building - Elevation 985' SE 7.9 1.29E+04 Reactor Building - Elevation 1001' N 7.9 1.29E+04 Reactor Building - Elevation 1001' S 7.9 1.29E+04 Standby Gas Treatment Room - Elevation 8.3 2.03E+08 985' Turbine Building Operating Deck - | ||
0.0 <1.00E+04 Elevation 951' Turbine Building Condenser Room - | |||
0.0 <1.00E+04 Elevations 907', 911' & 931' Cond Phase Separator Room 3.7 1.19E+07 Waste Collector Tank Room 7.7 3.87E+06 The accident doses developed in the subject EPU evaluation are supported by vendor calculation (ALION). The vendor calculation develops scaling factors on the original plant dose calculations developed in response to the Three Mile Island action plan. For the Reactor Building and Drywell, the EPU effective accident dose increase was shown to range from 2.5 to 8.3 percent with the 180-day integrated accident dose shown above. | |||
For the Turbine Building, the calculation indicates that there were no original plant dose calculations developed for general areas of the Turbine Building. For comparison, the calculation indicates 1-hour dose rates of less than 500 mRem/hour for vital access areas of the Administrative Building that experience shine from the Reactor Building. | |||
For conservatism, the accident dose was always listed as being <1.0E+04 Rad. | |||
Accordingly, the revised combined 60-year normal doses and the 180-day accident doses under EPU have the potential to impact the qualification of EQ components in the Reactor Building. Using the methods prescribed in the individual EQ calculation files for operating time and distance factors, the revised normal and accident doses were evaluated and compared to the qualified dose as indicated below (for conservatism, the normal dose was increased by +13 percent). For the equipment located in the Drywell, Beta dose was also considered. The Beta dose specified in the Monticello EQ Program is taken from the DOR Guidelines (Division of Operating Reactors - Guidelines for Evaluating Environmental Qualification of Class 1E Electrical Equipment in Operating Reactors) as an unshielded 200 Mrad dose, which was developed from a 4,100 MWth reactor. Therefore, considerable margin is included in the Beta dose as it applies to Monticello. | |||
Page 7 of 19 | |||
Enclosure 1 EPU EPU Normal Accident Beta Dose Gamma Dose Total EPU Qual. Note Equipment Title (rad) TID (rad) (rad) TID (rad) Dose (rad) | |||
Allen Bradley 7.84E+02 4.33E+06 4.33E+06 2.51E+08 Terminal Boards ASCO Solenoid 1.57E+05 2.83E+07 2.84E+07 2.00E+08 Valves (Normally Energized) Group 1 ASCO Solenoid 9.41E+04 1.25E+07 1.25E+07 2.00E+08 Valves (Normally Energized) Group 2 ASCO Solenoid 1.79E+07 5.44E+07 2.00E+07 9.23E+07 2.00E+08 Valves (Normally Energized) Group 3 ASCO Solenoid 3.14E+05 2.53E+06 2.85E+06 2.00E+08 Valves (Normally Energized) Group 4 ASCO Solenoid 1.79E+07 5.44E+07 Shielded 7.23E+07 2.00E+08 Valves (Normally De-energized) Group 1 ASCO Solenoid 1.18E+05 1.25E+07 1.26E+07 2.00E+08 Valves (Normally De-energized) Group 2 ASCO Pressure 1.18E+05 1.25E+07 1.26E+07 1.93E+07 Switches ASCO Temperature 7.84E+02 1.08E+07 1.08E+07 1.50E+07 Switches Automatic Valve 2.79E+06 5.00E+06 Shielded 7.79E+06 7.79E+06 Note Solenoid Valves Barksdale Pressure 1.57E+05 6.50E+06 6.66E+06 1.00E+07 Switch Barton Pressure 1.57E+05 5.42E+05 6.99E+05 3.00E+06 Switches RHR Barton Pressure 1.30E+05 2.53E+06 2.66E+06 3.00E+06 Switches, Non-RHR Barton Pressure 3.14E+05 2.53E+06 2.85E+06 1.00E+07 Switches 580A-0, 580A-1 E.F. Johnson Banana 3.14E+06 HELB only 3.14E+06 4.70E+06 Plug G.E. Cable (Butyl 1.57E+05 2.83E+07 2.84E+07 4.00E+07 type) | |||
G.E. Cable SIS & SI- 1.79E+07 5.44E+07 2.00E+07 9.23E+07 2.00E+08 Note 58109 Control G.E. Cable SI-58081 7.84E+03 2.17E+07 2.17E+07 2.44E+07 Control General Electric 1.57E+05 2.72E+07 2.74E+07 3.00E+07 Note Motors Page 8 of 19 | |||
Enclosure 1 EPU EPU Normal Accident Beta Dose Gamma Dose Total EPU Qual. Note Equipment Title (rad) TID (rad) (rad) TID (rad) Dose (rad) | |||
General Electric 1.79E+07 5.44E+07 Shielded 7.23E+07 1.00E+08 Containment Penetrations General Electric 7.84E+02 2.03E+08 2.03E+08 2.20E+08 Note Terminal Blocks General Electric 3.60E+05 3.60E+05 1.00E+06 MCCs Hevi-Duty Electric 7.84E+02 4.71E+06 2.00E+06 2.00E+06 Note Transformer General Electric Fan 7.84E+02 1.08E+06 1.08E+06 1.00E+06 Note Motors Limitorque Motor 1.79E+07 5.44E+07 2.00E+06 7.43E+07 2.00E+08 Operators (DOR) | |||
(MO-2397) | |||
Limitorque Motor 3.14E+06 2.75E+06 5.89E+06 2.00E+07 Operators (DOR) | |||
(MO-2107) | |||
Limitorque Motor 1.79E+07 5.44E+07 2.00E+07 9.23E+07 2.00E+08 Operators (50.49) | |||
Limitorque Motor 3.14E+06 2.75E+06 5.89E+06 1.00E+07 Operators (50.49) | |||
Limitorque Motor 1.18E+05 1.25E+07 1.26E+07 2.00E+07 Operators (50.49) | |||
Limitorque Motor 1.79E+07 5.44E+07 2.00E+07 9.23E+07 2.27E+08 Operators (50.49) | |||
Limitorque Motor 1.18E+05 1.25E+07 1.26E+07 2.00E+07 Operators (50.49)(MO-4229 & | |||
MO-4230) | |||
Magnetrol Level 1.18E+05 1.25E+07 1.26E+07 2.20E+08 Switches McDonnell & Miller 7.84E+02 5.40E+06 5.40E+06 5.00E+06 Note Flow Switches MicroSwitch Limit 7.84E+02 1.07E+07 1.07E+07 1.00E+07 Note Switches Namco Limit 1.79E+07 5.44E+07 Shielded 7.23E+07 2.04E+08 Switches (50.49) | |||
Namco Quick 1.79E+07 5.44E+07 1.00E+08 1.72E+08 2.04E+08 Disconnects EC210 Raychem NEIS Seals 1.18E+05 1.25E+07 1.26E+07 5.00E+07 Raychem Low 1.79E+07 5.44E+07 1.00E+08 1.72E+08 2.25E+08 Voltage Splices Robertshaw Level 3.14E+05 3.25E+05 6.39E+05 2.00E+06 Switch Rockbestos Coax 1.79E+07 5.44E+07 1.00E+08 1.72E+08 2.00E+08 Cable Page 9 of 19 | |||
Enclosure 1 EPU EPU Normal Accident Beta Dose Gamma Dose Total EPU Qual. Note Equipment Title (rad) TID (rad) (rad) TID (rad) Dose (rad) | |||
Rosemount Pressure 1.18E+05 1.25E+07 1.26E+07 4.40E+07 Transmitter Rosemount 1153 1.57E+05 2.83E+07 2.84E+07 2.62E+07 Note Series B Rosemount Conduit 1.18E+05 1.25E+07 1.26E+07 1.11E+08 Seals Rotork "A" Range 1.57E+05 1.62E+06 1.78E+06 4.00E+06 Actuators (DOR) | |||
Rotork Valve 1.57E+05 2.83E+07 2.84E+07 1.84E+08 Operators (50.49) | |||
Static O-ring 5.33E+05 5.74E+06 6.27E+06 8.00E+06 Yarway Level 3.14E+05 3.40E+05 6.54E+05 1.00E+06 Samuel Moore 7.84E+02 1.08E+08 1.08E+08 2.00E+08 Instrument Cable Valcor Solenoid 1.10E+05 1.25E+07 1.26E+07 5.90E+07 Valves DG O'Brien Electrical 1.79E+07 5.44E+07 Shielded 7.23E+07 2.20E+08 Penetrations DG O'Brien Electrical 1.79E+07 5.44E+07 1.25E+07 8.48E+07 1.25E+08 Penetrations (Plugs) | |||
Reliance Motors 1.57E+05 2.83E+07 2.84E+07 2.00E+08 Tavis Flow 7.84E+02 1.08E+06 1.08E+06 1.40E+06 Transmitter ITT Grinnel/Conoflow 7.84E+02 5.42E+06 5.42E+06 1.00E+07 Transducer Consolidated Control 3.14E+05 7.58E+04 3.90E+05 5.00E+05 Relays General Atomic 1.79E+07 5.44E+07 2.00E+08 2.72E+08 Not Rad Radiation Detector Sensitive Kerite 1.57E+05 2.83E+07 2.84E+07 2.20E+08 Cable/Termination Westinghouse Starter 1.25E+05 2.53E+06 2.66E+06 5.00E+06 and Transformer GOULD 7.84E+02 4.33E+06 4.33E+06 1.00E+07 CONTACTOR/ | |||
DISCONNECT Eaton Thermocouple 1.79E+07 5.44E+07 1.00E+08 1.72E+08 2.00E+08 Extension Cable Brand Rex 600V 1.79E+07 5.44E+07 1.00E+08 1.72E+08 2.00E+08 Instrument Cable (Dywell) | |||
Brand Rex 600V 7.84E+03 1.08E+08 1.08E+08 2.00E+08 Instrument Cable (RB) | |||
Boston Control Cable 7.84E+03 1.08E+08 1.08E+08 2.00E+08 Page 10 of 19 | |||
Enclosure 1 EPU EPU Normal Accident Beta Dose Gamma Dose Total EPU Qual. Note Equipment Title (rad) TID (rad) (rad) TID (rad) Dose (rad) | |||
CONAX Electrical 1.79E+07 5.44E+07 2.25E+07 9.48E+07 2.25E+08 Connector Seal CONAX RTDs 1.18E+05 1.25E+07 1.26E+07 2.27E+08 Patel Conduit Seals 1.79E+07 5.44E+07 2.00E+07 9.23E+07 2.00E+08 (Drywell) | |||
Patel Conduit Seals 7.84E+03 1.08E+08 1.08E+08 2.00E+08 (Contact SBGT Filters) | |||
Patel Conformal 1.18E+05 1.25E+07 1.26E+07 2.00E+07 Coating (outside Drywell) | |||
Patel Conformal 1.79E+07 5.44E+07 2.00E+08 2.72E+08 3.06E+08 Coating (Drywell) | |||
EGS Grayboot 1.79E+07 5.44E+07 2.00E+07 9.23E+07 2.08E+08 Electrical Connectors EGS Quick 1.79E+07 5.44E+07 1.00E+08 1.72E+08 2.00E+08 Disconnect Raychem/Swagelok 1.57E+05 2.83E+07 2.84E+07 5.00E+07 Conduit Seals Weed 1.79E+07 5.44E+07 2.00E+08 2.72E+08 3.06E+08 Thermocouples Rome Cable Type 3.60E+04 3.25E+05 3.61E+05 5.00E+08 SIS Eaton Cutler- 5.33E+05 5.29E+05 1.06E+06 1.43E+06 Hammer Relays PEI/FENWAL 1.18E+05 1.25E+07 1.26E+07 5.00E+07 Temperature Switch ITT-Royal PVC Cable 5.33E+05 2.53E+06 3.07E+06 1.00E+07 Okonite Control 3.14E+05 2.53E+06 2.85E+06 1.00E+07 Cable Triangle Triolene 3.14E+05 7.58E+04 3.90E+05 3.90E+05 Control Cable MNGP-A Cable 1.57E+05 2.83E+07 2.84E+07 5.00E+07 MNGP-B Cable 1.57E+05 2.83E+07 2.84E+07 4.10E+07 Amphenol 5.33E+05 3.79E+06 4.32E+06 6.00E+06 Connectors Pyco Temperature 3.14E+04 2.53E+06 2.57E+06 2.20E+08 Elements SOR Pressure 5.33E+05 2.53E+06 3.07E+06 3.30E+07 Switches General Electric 5.33E+05 2.17E+06 2.70E+06 2.20E+08 Terminal Blocks Patel P-1 Thread 1.79E+07 5.44E+07 2.00E+08 2.72E+08 1.50E+09 Sealant Rockbestos Firewall 1.79E+07 5.44E+07 1.00E+08 1.72E+08 2.00E+08 SR Cable Page 11 of 19 | |||
Valves | Enclosure 1 EPU EPU Normal Accident Beta Dose Gamma Dose Total EPU Qual. Note Equipment Title (rad) TID (rad) (rad) TID (rad) Dose (rad) | ||
Rockbestos Firewall 1.79E+07 5.44E+07 1.00E+08 1.72E+08 2.00E+08 III/SIS Cable Rockbestos Firewall 1.57E+05 2.83E+07 2.84E+07 1.30E+08 EP Cable Valcor MSIV 3.14E+04 8.66E+04 1.18E+05 5.00E+07 Solenoid Valves Core Spray & RHR 1.57E+05 2.83E+07 2.84E+07 5.77E+07 High Voltage Termination Dow Corning 3-6548 3.60E+04 HELB only 3.60E+04 1.36E+06 Silicone RTV Foam Loctite PST 580 1.79E+07 5.44E+07 Shielded 7.23E+07 7.37E+07 Note Thread Sealant Scotch 130C and 69 7.84E+03 1.08E+08 1.08E+08 1.83E+08 Electrical Tape Fisher E/P 1.57E+05 4.33E+06 4.49E+06 6.00E+06 Transducer Cutler-Hammer 1.24E+05 2.52E+06 2.65E+06 2.80E+06 Note Motor Starter/Control Transformer ASCO Scram 7.85E+04 HELB only 7.85E+04 8.55E+04 Solenoid Pilot Valves Note: Additional supporting qualification analysis to be performed and documented in EQ qualification file and/or equipment to be replaced/modified prior to EPU implementation. | |||
EPU HELB Evaluation HELB is discussed in PUSAR Section 2.2.1. Under the EPU evaluation for HELB, several high energy break or critical crack scenarios were considered for the Reactor Building. These included feedwater, reactor water cleanup, and control rod drive breaks and cracks in various areas. The EPU evaluation for HELBs, in combination with supporting calculations, provides the bases for temperatures, pressures and flood levels used for evaluation of HELBs in the Reactor and Turbine Buildings. The safe-shutdown equipment located in any Turbine Building locations made harsh (i.e. the peak HELB temperature greater than 140°F) as a result of EPU are being determined and evaluated. | |||
From the evaluation for Reactor Building EPU event cases, the following peak conditions are obtained as compared to the current EQ Program Basis values for the respective Reactor Building Volume: | |||
Page 12 of 19 | |||
Enclosure 1 Current EQ Program Basis Data EPU Data RB Temp Press Liquid Temp Press Liquid Volume (°F) (psia) (ft) (°F) (psia) (ft) Comment 1 142.97 14.86 0.05 114.2 14.81 0.4 Note 2 142.97 14.85 0.01 115.2 14.8 0 3 143.8 14.98 0.05 115.7 14.83 0.4 Note 4 144.4 14.97 0 135.6 14.82 0 5 256 15.15 0.05 121.3 14.81 0.5 Note 6 263.6 15.63 3.95 157.2 14.8 0.6 7 240.4 15.19 4.38 184.5 14.84 0.8 8 <140 14.99 0 140.7 14.8 0.6 Note 9 187.6 15.59 0.01 127.4 14.79 0.5 Note 10 159.9 15.59 0 127.2 14.79 0.5 Note 11 158.7 15.59 0 127.3 14.79 0.5 Note 12 193 15.59 0.01 127.6 14.79 0.5 Note 13 127.3 14.88 0.24 166.2 14.8 0 Note 14 153.3 14.83 0.27 174.7 14.8 0 Note 15 209.6 15.3 0.05 180.2 14.8 0 16 311.3 21.16 6.68 213.1 15.22 8.8 Note 17 222.4 15.14 0 130.6 14.79 0 18 208.1 15.11 0.68 209.7 14.83 0 Note 19 175.9 15.13 0.53 209.3 14.83 0.1 Note 20 112.5 15.14 0 179.4 14.8 0.1 Note 21 112.2 14.87 0 108 14.79 0 22 170.4 14.84 0 184 14.79 0 Note 23 143.7 14.87 0 164 14.79 0 Note 24 104 14.7 0 104.4 14.7 0 25 145.8 14.85 0 183.5 14.79 0 Note 26 109.1 14.89 0 104.4 14.7 0 27 203.6 14.99 0.01 211.7 14.83 0 Note 28 216.7 15.85 0.38 213.3 15.03 1.6 Note 29 214.6 15.85 0.3 213.5 15.4 1.7 Note 30 220.5 17.2 0.27 218.2 16.52 1.4 Note 31 188.3 17.19 0.27 213 16.52 1.4 Note 32 164.1 15.85 0.19 219.8 17.09 1.7 Note 33 128.3 14.99 0 211.7 14.83 0 Note 34 168.3 14.83 0.005 191.4 14.79 0 Note 35 207.8 14.84 0.02 199.2 14.79 0 36 142.4 14.88 0 141.6 14.79 0 37 112.8 14.88 0 143.9 14.8 0 Note Page 13 of 19 | |||
Enclosure 1 Current EQ Program Basis Data EPU Data RB Temp Press Liquid Temp Press Liquid Volume (°F) (psia) (ft) (°F) (psia) (ft) Comment 38 100 14.7 0 100.3 14.7 0 39 215.3 14.87 0.01 112.2 14.8 0 40 126.2 14.84 0 127.7 14.8 0 41 106.9 14.88 0 104.4 14.7 0 42 204.7 14.85 0.01 198.8 14.79 0 43 128.3 14.83 0.01 122.2 14.78 0 44 160.8 14.82 0.01 138.1 14.78 0 45 169.7 14.85 0.01 198.6 14.78 0 Note 46 219.2 14.86 0.02 106.2 14.77 0 47 101.5 14.84 0 187.8 14.78 0 Note 48 131.1 14.8 0.01 137.3 14.76 0 Note: Additional supporting qualification analysis to be performed and documented in EQ qualification file and/or equipment to be replaced/modified prior to EPU implementation. | |||
EPU HELB Temperature Review From the table above, it is observed that the peak EPU liquid break HELB temperatures for Reactor Building Volumes 13, 14, 18, 19, 20, 22, 23, 24, 25, 27, 31, 32, 33, 34, 37, 38, 40, 45, 47, and 48 exceed the currently specified peak HELB temperature provided by the current EQ Program basis data. The peak EPU (or pre-EPU) HELB temperature in Reactor Building Volumes 24, 38, 40, and 48 are less than the harsh/mild threshold temperature of 140°F, so these areas remain mild. Based on EQ end device location and required performance, the impact of EPU HELB conditions focuses on Reactor Building Volumes 13, 14, 18, 19, 20, 22, 27, 31, 32, 33, and 34. | |||
Qualified RB Temp. EPU Peak Equipment Title Volumes (°F) Temp (°F) Note ASCO Solenoid Valves 18, 19 346 209.7 (Normally Energized) | |||
ASCO Solenoid Valves 31 346 213 (Normally De-energized) | |||
ASCO Pressure Switches 14, 19, 31 210 213 Note Barksdale Pressure Switch 14, 18, 212 211.7 22, 33 Barton Pressure Switches 14, 19 212 209.3 Barton Pressure Switches 14, 18 200 209.7 Note 580A-0, 580A-1 G.E. Cable (butyl rubber SI- 13, 14, 18, 340 211.7 58007/58136) 19, 20, 22, 27, 33, 34 Page 14 of 19 | |||
Switches 7. | Enclosure 1 Qualified RB Temp. EPU Peak Equipment Title Volumes (°F) Temp (°F) Note GE Cable (PE type SI-58081) 13, 14, 18, 236 211.7 19, 20, 22, 27, 33, 34 GE Cable (XLPE type, SI- 13, 14, 18, 340 219.8 57275/58109) 19, 20, 22, 27, 31, 32, 33, 34 General Electric Containment 14, 18 340 209.7 Penetrations General Electric Terminal 13, 14, 18, 340 219.8 Blocks 19, 20, 22, 27, 31, 32, 33, 34 Limitorque MOVs (50.49, class 13, 19, 20, 340 213 RH, AC motor) 22, 31 Limitorque MOVs (50.49, class 13, 32 340 219.8 RH, DC motor) | ||
Limitorque Fibrite Switches 13, 19, 20, 420 219.8 22, 31, 32 Namco Limit Switches (EA740 31 352 213 w/o EC210) | |||
Namco Limit Switches (EA180 18, 19, 31 361 213 w/o EC210) | |||
Raychem NEIS Seals 18, 19, 31 366 213 Raychem WCSF-N Splices 13, 14, 18, 350 219.8 19, 20, 22, 27, 31, 32, 33, 34 Robertshaw Level Switch 18 220 209.7 (DOR) | |||
Rockbestos Coax Cable 13, 14, 18, 346 219.8 19, 20, 22, 27, 31, 32, 33, 34 Rosemount 1153 Series A 33, 34 340 211.7 Transmitter (DOR) | |||
Rosemount 1153 Series B 14, 18, 19, 318 211.7 22, 27, 33, 34 Rosemount Conduit Seals 14, 18, 22, 420 211.7 27, 33 Rotork Valve Operators (50.49) 14, 31, 33 385 213 Static O-ring (DOR) 22, 33 212 211.7 Yarway Level (DOR) 14, 18 250 209.7 Page 15 of 19 | |||
Solenoid Valves | Enclosure 1 Qualified RB Temp. EPU Peak Equipment Title Volumes (°F) Temp (°F) Note Samuel Moore Instrument 13, 14, 18, 340 219.8 Cable 19, 20, 22, 27, 31, 32, 33, 34 Valcor Solenoid Valves 18, 19 365 209.7 DG O'Brien Electrical 14, 19 320 209.3 Penetrations DG O'Brien Electrical 14, 19 345 209.3 Penetrations (Plugs) | ||
Reliance Motors 14, 19 464 209.3 Consolidated Control Relays 18 223.1 209.7 Westinghouse Starter and 14, 19 260 209.3 Transformer Eaton Thermocouple Extension 14 375 174.7 Cable Brand Rex 600V Instrument 13, 14, 18, 385 219.8 Cable 19, 20, 22, 27, 31, 32, 33, 34 Boston Control Cable 13, 14, 18, 340 219.8 19, 20, 22, 27, 31, 32, 33, 34 Patel Conduit Seals 18 354 209.7 EGS Grayboot Electrical 31 450 213 Connectors EGS Quick Disconnect 13, 14, 18, 435 219.8 19, 20, 22, 27, 31, 32, 33, 34 Raychem/Swagelok Conduit 14, 18, 19, 340 211.7 Seals 22, 33, 34 Eaton Cutler-Hammer Relays 22, 33, 34 232 211.7 ITT-Royal PVC Cable (DOR) 14, 18, 19, 211 211.7 Note 22, 33 Okonite Control Cable 14, 18, 19, 211 209.7 22 Triangle Triolene Control Cable 18, 19 211 209.7 (DOR) | |||
MNGP-A Cable (DOR) 13, 14, 18, 230 211.7 19, 20, 22, 27, 33, 34 MNGP-B Cable (DOR) 14, 19 211 209.3 Page 16 of 19 | |||
Switches | Enclosure 1 Qualified RB Temp. EPU Peak Equipment Title Volumes (°F) Temp (°F) Note Amphenol Connectors (DOR) 14, 18, 19, 266 211.7 22, 33 SOR Pressure Switches 14, 22, 33 350 211.7 (50.49) | ||
General Electric Terminal 22, 33, 34 340 211.7 Blocks (50.49) | |||
Patel P-1 Thread Sealant 13, 14, 18, 400 219.8 19, 20, 22, 27, 31, 32, 33, 34 Rockbestos Firewall SR Cable 13, 14, 18, 351 219.8 19, 20, 22, 27, 31, 32, 33, 34 Rockbestos Firewall III/SIS 13, 14, 18, 342 219.8 Cable 19, 20, 22, 27, 31, 32, 33, 34 Rockbestos Firewall EP Cable 13, 14, 18, 320 219.8 19, 20, 22, 27, 31, 32, 33, 34 Loctite PST 580 Thread 14, 18, 19, 364 219.8 Sealant 20, 22, 27, 31, 32, 33, 34 Scotch 130C and 69 Electrical 13, 14, 18, 372 219.8 Tape 19, 20, 22, 27, 31, 32, 33, 34 Cutler-Hammer Motor 14, 19 253 209.3 Starter/Control Transformer ASCO Scram Solenoid Pilot 14, 18 277 209.7 Valves Note: Additional supporting qualification analysis to be performed and documented in EQ qualification file and/or equipment to be replaced/modified prior to EPU implementation. | |||
Post-LOCA Heat-up in the Reactor Building The Reactor Building post-LOCA heat-up temperatures are provided in the associated EPU evaluation. The EPU data as compared to the current post-LOCA heat-up (PLHU) data is presented below. It is observed that most post-LOCA area temperatures are relatively benign and will not present particular challenges to the EQ components that are generally tested or analyzed to much higher accident temperatures at their location. | |||
However, additional supporting qualification analysis to be performed and documented Page 17 of 19 | |||
Enclosure 1 in EQ qualification file and/or equipment to be replaced/modified prior to EPU implementation. | |||
RB Volume Current PLHU Temp. (°F) EPU PLHU Temp. (°F) 1 110.0 104.3 2 110.0 106.2 3 129.1 129.7 4 129.1 129.5 5 109.9 107.4 6 140.4 140.6 7 116.3 123.6 8 106.2 111.9 9 160.4 177.5 10 159.9 177.5 11 158.7 177.5 12 157.3 177.5 13 112.6 112.7 14 107.6 112.3 15 106.3 108.7 16 135.2 141.5 17 106.1 108.9 18 109.3 114.9 19 106.3 114.9 20 112.6 113.1 21 112.2 107.8 22 106.7 114.1 23 106.4 113.8 24 104 104 25 113.9 114.1 26 109.1 109.7 27 109.1 115.4 28 120 121.3 29 120.1 121.1 30 120.2 128 31 120.2 129.7 32 120.2 120.7 33 115.6 115.4 34 107.9 114.2 35 107.8 114.2 36 134.4 120.5 37 112.8 120.5 Page 18 of 19 | |||
Enclosure 1 RB Volume Current PLHU Temp. (°F) EPU PLHU Temp. (°F) 38 100 100 39 126.3 134.5 40 105.6 113.2 41 106.9 109.8 42 104.6 114.2 43 109.7 110.9 44 108.1 112.1 45 104 114 46 107.2 110.3 47 100 113.7 48 103.9 113.2 | |||
==SUMMARY== | |||
Calculations were prepared to evaluate the impact of EPU conditions on equipment for radiation, temperature, pressure and flood level for safety related equipment. These calculations and related results are described above. The majority of issues will be addressed by revisions to the EQ files that support continued qualification of existing equipment with the new EPU conditions. EQ file updates will be completed as required by 10 CFR 50.49 prior to EPU implementation. Any required modifications or replacement of equipment will also be completed prior to EPU implementation. | |||
Page 19 of 19}} | |||
Calculations were prepared to evaluate the impact of EPU conditions on equipment for radiation, temperature, pressure and flood level for safety related equipment. These calculations and related results are described above. The majority of issues will be addressed by revisions to the EQ files that support continued qualification of existing equipment with the new EPU conditions. EQ file updates will be completed as required by 10 CFR 50.49 prior to EPU implementation. Any required modifications or replacement of equipment will also be completed prior to EPU implementation.}} | |||
Latest revision as of 17:00, 14 November 2019
| ML081570467 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 06/05/2008 |
| From: | O'Connor T Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-MT-08-042, TAC MD8398 | |
| Download: ML081570467 (22) | |
Text
Montkelh Nuclear Generatina Plant EwnmltdrdtbWEtrwllones Operated by Nudear Management Company, LLC June 5,2008 L-MT-08-042 10 CFR 50.90 U. S. Nuclear Regulatory Commission A T N : Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License License No. DPR-22 Monticello Extended Power Uprate (USNRC TAC MD83981:
Acceptance Review Supplemental lnforrnation Package 5
References:
I)NMC Letter to USNRC, "License Amendment Request: Extended Power Uprate,"
dated March 31,2008 2 ) NMC Letter to USNRC, "Monticello Extended Power Uprate (USNRC TAG MD8398): Acceptance Review Supplement Regarding Radiological Analysis,"
dated May 20,2008
- 3) NMC Letter to USNRC, "Monticello Extended Power Uprate (USNRC TAC MD8398): Acceptance Review Supplemental Information," dated May 28, 2008
- 4) NMC Letter to USNRC, 'Monticello Extended Power Uprate (USNRC TAC MD8398): Acceptance Review Supplemental Information Package 3," dated May 30,2008
- 5) NMC Letter to USNRC, "Monticello Extended Power Uprate (USNRC TAC MD8398): Acceptance Review Supplemental Information Package 4," dated June 3,2008 Pursuant to 10 CFR 50.90, Nuclear Management Company, LLC (NMC), requested in Reference 1 approval of amendments to the Monticello Nuclear Generating Plant (MNGP) Renewed Operating License (OL) and Technical Specfications (TS) to increase the maximum power level authorized from 1775 megawatts thermal (MWt) to 1870 MWt, an approximate five percent increase in the current licensed thermal power (CLTP). The proposed request for Extended Power Uprate (EPU) represents an increase of approximately 12 percent above the Original Licensed Thermal Power (OLTP). The Monticello EPU application was supplemented on May 20, 2008, May 28,2008, May 30,2008, and June 3,2008 by References 2 , 3 , 4 and 5.
2807 West County Road 75 Monticello, Minnesota 563624637 Telephone: 763.295.5151 Fax: 783.295.1454
Document Control Desk Page 2 In a teleconference held May 2, 2008, the NRC staff indicated that additional information would be necessary for the Electrical Engineering Branch (EEEB) to complete the acceptance review of the Monticello EPU license amendment request (IAR). The questions were formalized and emailed to NMC on May 15,2008. On May 28,2008, NMC submitted responses (Reference 3) to EEEB Questions 2,3,and 4. of this letter contains the response to EEEB Question I.
NMC has reviewed the No Significant Hazards Consideration and the Environmental Consideration submitted with Reference 1 relative to the enclosed supplemental information. NMC has determined that there are no changes required to either of these sections of Reference 1.
Commitment Summan, This letter makes no new commitments and does not change any existing commitments.
I declare under penalty of perjury that the foregoing is true and correct.
on June 5 A 008.
resident, Monticello Nuclear Generating Plant Company, LLC cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce Enclosure
Enclosure 1 to L-MT-08-042 Electrical Engineering Branch Question 1 and Response 1
Enclosure 1
- 4) EEEB - ELECTRICAL ENGINEERING BRANCH NRC Question
- 1) In Section 2.3 of the LAR under the section titled 'Outside Containment', the licensee stated the following:
"The total integrated doses (normal plus accident) for EPU conditions were evaluated and determined not to adversely affect qualification of most of the EQ equipment located outside of containment. Equipment not qualified to the new environmental conditions at EPU will be reanalyzed, re-qualified, or replaced prior to implementation of EPU."
In order for the Electrical Engineering Branch (EEEB) to start its review, the full EQ analysis must be completed. This includes any reanalysis, re-qualification, or replacement of equipment. The licensee must also describe how the equipment was evaluated (e.g., calculations, assessments, etc.) and show how the equipment remains bounded (i.e., provide the original design parameters and the updated values including the supporting calculations).
NMC Response:
The responses to EEEB Questions 2, 3 and 4 were submitted in Monticello letter L-MT-08-039 on May 28, 2008. The following response is regarding EEEB Question 1.
Introduction The following information provides more detail regarding the analyses that have been completed relative to the qualification of electrical equipment outside containment. As required, the analyses have addressed the radiation, pressure, temperature and flooding effects from operation at extended power uprate (EPU) conditions. This information describes how the equipment was evaluated and notes where further action, per the applicable regulatory criteria and the Monticello Environmental Qualification (EQ)
Program, is necessary prior to implementation of EPU.
Normal Temperature Evaluation An evaluation was completed to assess the impact EPU will have on the normal design temperatures of the Reactor Building. A calculation supports the normal area temperature data for the EQ Program. This calculation uses both survey data and calculated data as inputs. For the Drywell and the Steam Chase, a calculation provides a basis for the normal ambient temperatures. The EPU evaluation indicates no change in normal Drywell temperatures for EPU and a slight increase in normal Steam Chase temperature (less than one degree). This small temperature increase is bounded by the temperature value currently used in the EQ program for the steam chase. Normal plant area ambient temperature will continue to be assessed by the EQ program in lieu of using the maximum design temperature for assessing qualified lifetimes. As such, there is no impact of EPU conditions on normal plant temperature inputs to qualified life assessments.
Page 1 of 19
Enclosure 1 Normal Radiation Dose The EPU evaluation for radiation levels generally indicates an increase of 13 percent for the Reactor Building dose and no change for most Turbine Building normal doses as the result of EPU (some areas of Turbine Building have dose rate increases). This evaluation provides survey data for most plant areas and identifies the applicable increase effect for each plant area outside the Drywell.
The current basis for normal radiation doses in the EQ program is provided by calculation. This calculation documents actual survey dose rate data for all of the Reactor Building and the Turbine Building. The tables below relate the normal radiation doses in the calculation for reactor and turbine building.
Reactor Building, Normal 60 Year Doses Current EQ Program Basis Projected 60 year Normal EPU Dose Predicted EPU Dose Current Dose rate Effect EPU 60 yr RB Volume Rate Survey 60 year (survey) (see Dose (Rad)
(Spec) mR/Hr date Dose (Rad) mR/Hr note) (see note) 1 (B.1.4) 200 01/18/03 1.39E+05 160 180.8 9.51E+04 2 (B.1.4) 200 01/18/03 1.39E+05 Not surv 3 (B.1.4) 100 12/29/02 6.94E+04 50 56.5 2.97E+04 4 (B.1.4) 100 12/29/02 6.94E+04 Not surv 5 (B.1.3) 1 08/18/02 6.94E+02 Not surv 6 (B.1.2) 1000 12/21/02 6.94E+05 100 113 5.94E+04 7 (B.1.10) 1 06/26/00 6.94E+02 Not surv 8 (B.1.2) 46 12/21/03 3.19E+04 3 3.39 1.78E+03 9 (B.1.6) 120 12/15/02 8.33E+04 50 56.5 2.97E+04 10 (B.1.6) 90 12/15/02 6.25E+04 30 33.9 1.78E+04 11 (B.1.6) 140 01/19/03 9.72E+04 60 67.8 3.57E+04 12 (B.1.6) 150 01/19/03 1.04E+05 30 33.9 1.78E+04 13 (B.1.8) 80 01/12/03 5.55E+04 20 22.6 1.19E+04 14 (B.1.9/11) 160 08/03/02 1.11E+05 60 67.8 3.57E+04 15 (B.1.9) 350 03/10/02 2.43E+05 50 56.5 2.97E+04 16 (B.1.7) 4000 07/01/98 2.78E+06 2000 2260 1.19E+06 17 (B.1.9) 4 12/29/02 2.78E+03 4 4.52 2.38E+03 18 (B.1.10) 400 01/21/03 2.78E+05 55 62.15 3.27E+04 19 (B.1.10/12) 42 12/29/02 2.92E+04 4 4.52 2.38E+03 20 (B.1.8) 80 01/18/03 5.55E+04 30 33.9 1.78E+04 21 (B.1.14) 100 02/08/03 6.94E+04 30 33.9 1.78E+04 22 (B.1.14) 80 12/15/02 5.55E+04 1 1.13 5.94E+02 Page 2 of 19
Enclosure 1 Reactor Building, Normal 60 Year Doses Current EQ Program Basis Projected 60 year Normal EPU Dose Predicted EPU Dose Current Dose rate Effect EPU 60 yr RB Volume Rate Survey 60 year (survey) (see Dose (Rad)
(Spec) mR/Hr date Dose (Rad) mR/Hr note) (see note) 23 (B.1.14) 80 02/10/02 5.55E+04 1 1.13 5.94E+02 24 1 01/18/03 6.94E+02 Not surv 25 1 12/15/02 6.94E+02 1 1.13 5.94E+02 26 18 01/18/03 1.25E+04 4 4.52 2.38E+03 27 (B.1.13/15) 260 08/12/02 1.81E+05 30 33.9 1.78E+04 28 (B.1.5) 40 01/04/02 2.78E+04 40 45.2 2.38E+04 29 (B.1.5) 20 01/04/02 1.39E+04 20 22.6 1.19E+04 30 (B.1.5) 800 01/04/02 5.55E+05 80 90.4 4.75E+04 31 (B.1.5) 2200 01/04/02 1.53E+06 2200 2486 1.31E+06 32 (B.1.5) 1600 01/04/02 1.11E+06 1600 1808 9.51E+05 33 (B.1.13) 680 08/12/02 4.72E+05 3 3.39 1.78E+03 34 (B.1.18) 40 12/15/02 2.78E+04 6 6.78 3.57E+03 35 (B.1.17) 5 12/15/02 3.47E+03 4 4.52 2.38E+03 36 (B.1.21) 1 08/26/02 6.94E+02 1 1.13 5.94E+02 37 (B.1.21) 1 08/26/02 6.94E+02 1 1.13 5.94E+02 38 (B.1.21) 1 08/26/02 6.94E+02 1 1.13 5.94E+02 39 (B.1.21) 1 08/26/02 6.94E+02 1 1.13 5.94E+02 40 (B.1.16) 2 08/26/02 1.39E+03 1 1.13 5.94E+02 41 (B.1.16) 2 01/18/03 1.39E+03 1 1.13 5.94E+02 42 (B.1.16) 20 12/15/02 1.39E+04 1 1.13 5.94E+02 43 (B.1.19) 700 12/27/02 4.86E+05 500 565 2.97E+05 44 (B.1.20) 200 12/27/02 1.39E+05 5 5.65 2.97E+03 45 (B.1.19) 2 12/27/02 1.39E+03 2 2.26 1.19E+03 46 (B.1.19) 200 12/27/02 1.39E+05 6 6.78 3.57E+03 47 (B.1.19) 1 12/27/02 6.94E+02 Not surv 48 36 02/06/03 2.50E+04 7 7.91 4.16E+03 Note: EPU 60-year basis dose was determined by increasing the shown dose rate by 13 percent taken over the number of hours over 60 years (365.25 days/year used to account for leap years). No equivalent 60 year dose was determined for areas where the EPU evaluation did not provide dose rate values. As illustrated above, the projected 60-year normal dose due to EPU is bounded by the specified doses used in the current EQ Program for the Reactor Building.
Page 3 of 19
Enclosure 1 Turbine Building, Normal 60 Year Doses Current EQ Program Basis Normal Dose Projected 60 year Normal EPU Dose Current Dose Rate Survey 60 year survey EPU EPU 60 yr TB Volume mR/Hr Date Dose (Rad) (mRem/hr) Effect Dose (Rad) 1 (B.1.24) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 2 (B.1.24) 1 12/18/02 6.94E+02 1 1130% 5.94E+03 Increase 3 (B.1.24) 1 12/18/02 6.94E+02 1 1130% 5.94E+03 Increase 4 (B.1.24) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 5 (B.1.24) 8 12/18/02 5.55E+03 1-2 No 1.05E+03 change 6 (B.1.24) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 7 (B.1.24) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 8 (B.1.24) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 9 (B.1.24) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 10 (B.1.24) 2 12/18/02 1.39E+03 1 No 2.63E+03 1-5 change 11 (B.1.24) 200 01/29/03 1.39E+05 1 - 10 No 1.58E+04 30 change 12 (B.1.24) 120 05/01/02 8.33E+04 5 - 30 No 1.58E+04 change 13 (B.1.24) 2400 02/07/02 1.67E+06 2 - 1500 25 - 33% 1.05E+06 Increase 14 (B.1.24) 4000 07/01/98 2.78E+06 5 - 1800 Up to 1.07E+07 1130%
Increase 15 (B.1.24) 8 12/18/02 5.55E+03 1 No 5.26E+02 change 16 (B.1.24) 8 12/18/02 5.55E+03 1 No 5.26E+02 change 17 (B.1.24) 8 12/18/02 5.55E+03 1 No 5.26E+02 change 18 (B.1.24) 8 12/18/02 5.55E+03 1 No 5.26E+02 change 19 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 20 (B.1.23) 46 11/13/02 3.19E+04 Not No surveyed change 21 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change Page 4 of 19
Enclosure 1 Turbine Building, Normal 60 Year Doses Current EQ Program Basis Normal Dose Projected 60 year Normal EPU Dose Current Dose Rate Survey 60 year survey EPU EPU 60 yr TB Volume mR/Hr Date Dose (Rad) (mRem/hr) Effect Dose (Rad) 22 (B.1.23) 12 11/13/02 8.33E+03 1 No 5.26E+02 change 23 (B.1.23) 1 12/18/02 6.94E+02 1-2 No 1.05E+03 change 24 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 25 (B.1.23) 2 12/04/02 1.39E+03 1 1130% 5.94E+03 Increase 26 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 27 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 28 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 29 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 30 (B.1.23) 8 02/06/02 5.55E+03 1 No 5.26E+02 change 31 (B.1.23) 1 02/06/02 6.94E+02 1 No 5.26E+02 change 32 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 33 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 34 (B.1.23) 1 03/28/02 6.94E+02 1 No 5.26E+02 change 35 (B.1.23) 1 03/28/02 6.94E+02 1 No 5.26E+02 change 36 (B.1.23) 1 03/28/02 6.94E+02 1 No 5.26E+02 change 37 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 38 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 39 (B.1.23) 1 12/18/02 6.94E+02 1 No 5.26E+02 change 40 (B.1.23) 60 12/18/02 4.17E+04 1-2 No 1.05E+03 change 41 (B.1.22) 80 05/08/00 5.55E+04 1-3 No 1.58E+03 change 42 (B.1.22) 3000 05/08/00 2.08E+06 1 - 1000 2 - 9% 1.72E+06 10 - 3000 Increase Page 5 of 19
Enclosure 1 Turbine Building, Normal 60 Year Doses Current EQ Program Basis Normal Dose Projected 60 year Normal EPU Dose Current Dose Rate Survey 60 year survey EPU EPU 60 yr TB Volume mR/Hr Date Dose (Rad) (mRem/hr) Effect Dose (Rad) 43 (B.1.23) 1 12/18/02 6.94E+02 Not No surveyed change 44 (B.1.22) 3000 05/08/00 2.08E+06 1 - 1000 2 - 9% 1.72E+06 10 - 3000 Increase Note: EPU 60-year basis dose was determined by increasing the highest shown dose rate by the EPU Effect value and then multiplying by the number of hours over 60 years (365.25 days/year used to account for leap years). No equivalent 60 year dose was determined for areas where the EPU evaluation did not provide dose rate values.
Based on the above, it is observed that the projected 60 year normal doses in Turbine Building Volumes 2, 3, 10, 14, 23, and 25 will increase from the current specified EQ Program data. These volumes, with the exception of 14, remain below the radiation harsh classification threshold as defined by the EQ program.
Accident Radiation Doses The EPU evaluation of the impacts of radiation on equipment qualification and the supporting vendor calculation performed by Alion provides the bases for EPU impacts on the EQ program from post-LOCA accident doses. The resulting EPU doses and the indicated increases by location are shown below.
% EPU Dose EPU 180-day TID, LOCATION Increase (Rads)
Drywell 2.5 5.44E+07 HPCI Room - Elevation 896' 7.3 2.73E+06 RCIC Room - Elevation 896' 7.5 1.82E+06 RHR Rooms - Elevation 896' 4.3 2.72E+07 RWCU Pump Room - Elevation 962' 7.8 2.52E+06 Torus Compartment - Elevation 896' 3.5 1.19E+07 Main Steam Chase - Elevation 935' 7.3 2.73E+06 LPCI Valve Injection Room - Elevation 7.8 2.52E+06 935' Reactor Building - Elevation 935' E 7.8 2.52E+06 Reactor Building - Elevation 935' W 7.8 2.52E+06 Reactor Building - Elevation 935' SE 7.8 2.52E+06 Reactor Building - Elevation 935' SW 7.8 2.52E+06 Reactor Building - Elevation 962' S 7.8 2.52E+06 Reactor Building - Elevation 962' E 7.8 2.52E+06 Reactor Building - Elevation 962' NW 7.8 2.52E+06 Page 6 of 19
Enclosure 1 Reactor Building - Elevation 985' N 7.9 1.29E+04 Reactor Building - Elevation 985' SW 7.9 1.29E+04 Reactor Building - Elevation 985' SE 7.9 1.29E+04 Reactor Building - Elevation 1001' N 7.9 1.29E+04 Reactor Building - Elevation 1001' S 7.9 1.29E+04 Standby Gas Treatment Room - Elevation 8.3 2.03E+08 985' Turbine Building Operating Deck -
0.0 <1.00E+04 Elevation 951' Turbine Building Condenser Room -
0.0 <1.00E+04 Elevations 907', 911' & 931' Cond Phase Separator Room 3.7 1.19E+07 Waste Collector Tank Room 7.7 3.87E+06 The accident doses developed in the subject EPU evaluation are supported by vendor calculation (ALION). The vendor calculation develops scaling factors on the original plant dose calculations developed in response to the Three Mile Island action plan. For the Reactor Building and Drywell, the EPU effective accident dose increase was shown to range from 2.5 to 8.3 percent with the 180-day integrated accident dose shown above.
For the Turbine Building, the calculation indicates that there were no original plant dose calculations developed for general areas of the Turbine Building. For comparison, the calculation indicates 1-hour dose rates of less than 500 mRem/hour for vital access areas of the Administrative Building that experience shine from the Reactor Building.
For conservatism, the accident dose was always listed as being <1.0E+04 Rad.
Accordingly, the revised combined 60-year normal doses and the 180-day accident doses under EPU have the potential to impact the qualification of EQ components in the Reactor Building. Using the methods prescribed in the individual EQ calculation files for operating time and distance factors, the revised normal and accident doses were evaluated and compared to the qualified dose as indicated below (for conservatism, the normal dose was increased by +13 percent). For the equipment located in the Drywell, Beta dose was also considered. The Beta dose specified in the Monticello EQ Program is taken from the DOR Guidelines (Division of Operating Reactors - Guidelines for Evaluating Environmental Qualification of Class 1E Electrical Equipment in Operating Reactors) as an unshielded 200 Mrad dose, which was developed from a 4,100 MWth reactor. Therefore, considerable margin is included in the Beta dose as it applies to Monticello.
Page 7 of 19
Enclosure 1 EPU EPU Normal Accident Beta Dose Gamma Dose Total EPU Qual. Note Equipment Title (rad) TID (rad) (rad) TID (rad) Dose (rad)
Allen Bradley 7.84E+02 4.33E+06 4.33E+06 2.51E+08 Terminal Boards ASCO Solenoid 1.57E+05 2.83E+07 2.84E+07 2.00E+08 Valves (Normally Energized) Group 1 ASCO Solenoid 9.41E+04 1.25E+07 1.25E+07 2.00E+08 Valves (Normally Energized) Group 2 ASCO Solenoid 1.79E+07 5.44E+07 2.00E+07 9.23E+07 2.00E+08 Valves (Normally Energized) Group 3 ASCO Solenoid 3.14E+05 2.53E+06 2.85E+06 2.00E+08 Valves (Normally Energized) Group 4 ASCO Solenoid 1.79E+07 5.44E+07 Shielded 7.23E+07 2.00E+08 Valves (Normally De-energized) Group 1 ASCO Solenoid 1.18E+05 1.25E+07 1.26E+07 2.00E+08 Valves (Normally De-energized) Group 2 ASCO Pressure 1.18E+05 1.25E+07 1.26E+07 1.93E+07 Switches ASCO Temperature 7.84E+02 1.08E+07 1.08E+07 1.50E+07 Switches Automatic Valve 2.79E+06 5.00E+06 Shielded 7.79E+06 7.79E+06 Note Solenoid Valves Barksdale Pressure 1.57E+05 6.50E+06 6.66E+06 1.00E+07 Switch Barton Pressure 1.57E+05 5.42E+05 6.99E+05 3.00E+06 Switches RHR Barton Pressure 1.30E+05 2.53E+06 2.66E+06 3.00E+06 Switches, Non-RHR Barton Pressure 3.14E+05 2.53E+06 2.85E+06 1.00E+07 Switches 580A-0, 580A-1 E.F. Johnson Banana 3.14E+06 HELB only 3.14E+06 4.70E+06 Plug G.E. Cable (Butyl 1.57E+05 2.83E+07 2.84E+07 4.00E+07 type)
G.E. Cable SIS & SI- 1.79E+07 5.44E+07 2.00E+07 9.23E+07 2.00E+08 Note 58109 Control G.E. Cable SI-58081 7.84E+03 2.17E+07 2.17E+07 2.44E+07 Control General Electric 1.57E+05 2.72E+07 2.74E+07 3.00E+07 Note Motors Page 8 of 19
Enclosure 1 EPU EPU Normal Accident Beta Dose Gamma Dose Total EPU Qual. Note Equipment Title (rad) TID (rad) (rad) TID (rad) Dose (rad)
General Electric 1.79E+07 5.44E+07 Shielded 7.23E+07 1.00E+08 Containment Penetrations General Electric 7.84E+02 2.03E+08 2.03E+08 2.20E+08 Note Terminal Blocks General Electric 3.60E+05 3.60E+05 1.00E+06 MCCs Hevi-Duty Electric 7.84E+02 4.71E+06 2.00E+06 2.00E+06 Note Transformer General Electric Fan 7.84E+02 1.08E+06 1.08E+06 1.00E+06 Note Motors Limitorque Motor 1.79E+07 5.44E+07 2.00E+06 7.43E+07 2.00E+08 Operators (DOR)
(MO-2397)
Limitorque Motor 3.14E+06 2.75E+06 5.89E+06 2.00E+07 Operators (DOR)
(MO-2107)
Limitorque Motor 1.79E+07 5.44E+07 2.00E+07 9.23E+07 2.00E+08 Operators (50.49)
Limitorque Motor 3.14E+06 2.75E+06 5.89E+06 1.00E+07 Operators (50.49)
Limitorque Motor 1.18E+05 1.25E+07 1.26E+07 2.00E+07 Operators (50.49)
Limitorque Motor 1.79E+07 5.44E+07 2.00E+07 9.23E+07 2.27E+08 Operators (50.49)
Limitorque Motor 1.18E+05 1.25E+07 1.26E+07 2.00E+07 Operators (50.49)(MO-4229 &
MO-4230)
Magnetrol Level 1.18E+05 1.25E+07 1.26E+07 2.20E+08 Switches McDonnell & Miller 7.84E+02 5.40E+06 5.40E+06 5.00E+06 Note Flow Switches MicroSwitch Limit 7.84E+02 1.07E+07 1.07E+07 1.00E+07 Note Switches Namco Limit 1.79E+07 5.44E+07 Shielded 7.23E+07 2.04E+08 Switches (50.49)
Namco Quick 1.79E+07 5.44E+07 1.00E+08 1.72E+08 2.04E+08 Disconnects EC210 Raychem NEIS Seals 1.18E+05 1.25E+07 1.26E+07 5.00E+07 Raychem Low 1.79E+07 5.44E+07 1.00E+08 1.72E+08 2.25E+08 Voltage Splices Robertshaw Level 3.14E+05 3.25E+05 6.39E+05 2.00E+06 Switch Rockbestos Coax 1.79E+07 5.44E+07 1.00E+08 1.72E+08 2.00E+08 Cable Page 9 of 19
Enclosure 1 EPU EPU Normal Accident Beta Dose Gamma Dose Total EPU Qual. Note Equipment Title (rad) TID (rad) (rad) TID (rad) Dose (rad)
Rosemount Pressure 1.18E+05 1.25E+07 1.26E+07 4.40E+07 Transmitter Rosemount 1153 1.57E+05 2.83E+07 2.84E+07 2.62E+07 Note Series B Rosemount Conduit 1.18E+05 1.25E+07 1.26E+07 1.11E+08 Seals Rotork "A" Range 1.57E+05 1.62E+06 1.78E+06 4.00E+06 Actuators (DOR)
Rotork Valve 1.57E+05 2.83E+07 2.84E+07 1.84E+08 Operators (50.49)
Static O-ring 5.33E+05 5.74E+06 6.27E+06 8.00E+06 Yarway Level 3.14E+05 3.40E+05 6.54E+05 1.00E+06 Samuel Moore 7.84E+02 1.08E+08 1.08E+08 2.00E+08 Instrument Cable Valcor Solenoid 1.10E+05 1.25E+07 1.26E+07 5.90E+07 Valves DG O'Brien Electrical 1.79E+07 5.44E+07 Shielded 7.23E+07 2.20E+08 Penetrations DG O'Brien Electrical 1.79E+07 5.44E+07 1.25E+07 8.48E+07 1.25E+08 Penetrations (Plugs)
Reliance Motors 1.57E+05 2.83E+07 2.84E+07 2.00E+08 Tavis Flow 7.84E+02 1.08E+06 1.08E+06 1.40E+06 Transmitter ITT Grinnel/Conoflow 7.84E+02 5.42E+06 5.42E+06 1.00E+07 Transducer Consolidated Control 3.14E+05 7.58E+04 3.90E+05 5.00E+05 Relays General Atomic 1.79E+07 5.44E+07 2.00E+08 2.72E+08 Not Rad Radiation Detector Sensitive Kerite 1.57E+05 2.83E+07 2.84E+07 2.20E+08 Cable/Termination Westinghouse Starter 1.25E+05 2.53E+06 2.66E+06 5.00E+06 and Transformer GOULD 7.84E+02 4.33E+06 4.33E+06 1.00E+07 CONTACTOR/
DISCONNECT Eaton Thermocouple 1.79E+07 5.44E+07 1.00E+08 1.72E+08 2.00E+08 Extension Cable Brand Rex 600V 1.79E+07 5.44E+07 1.00E+08 1.72E+08 2.00E+08 Instrument Cable (Dywell)
Brand Rex 600V 7.84E+03 1.08E+08 1.08E+08 2.00E+08 Instrument Cable (RB)
Boston Control Cable 7.84E+03 1.08E+08 1.08E+08 2.00E+08 Page 10 of 19
Enclosure 1 EPU EPU Normal Accident Beta Dose Gamma Dose Total EPU Qual. Note Equipment Title (rad) TID (rad) (rad) TID (rad) Dose (rad)
CONAX Electrical 1.79E+07 5.44E+07 2.25E+07 9.48E+07 2.25E+08 Connector Seal CONAX RTDs 1.18E+05 1.25E+07 1.26E+07 2.27E+08 Patel Conduit Seals 1.79E+07 5.44E+07 2.00E+07 9.23E+07 2.00E+08 (Drywell)
Patel Conduit Seals 7.84E+03 1.08E+08 1.08E+08 2.00E+08 (Contact SBGT Filters)
Patel Conformal 1.18E+05 1.25E+07 1.26E+07 2.00E+07 Coating (outside Drywell)
Patel Conformal 1.79E+07 5.44E+07 2.00E+08 2.72E+08 3.06E+08 Coating (Drywell)
EGS Grayboot 1.79E+07 5.44E+07 2.00E+07 9.23E+07 2.08E+08 Electrical Connectors EGS Quick 1.79E+07 5.44E+07 1.00E+08 1.72E+08 2.00E+08 Disconnect Raychem/Swagelok 1.57E+05 2.83E+07 2.84E+07 5.00E+07 Conduit Seals Weed 1.79E+07 5.44E+07 2.00E+08 2.72E+08 3.06E+08 Thermocouples Rome Cable Type 3.60E+04 3.25E+05 3.61E+05 5.00E+08 SIS Eaton Cutler- 5.33E+05 5.29E+05 1.06E+06 1.43E+06 Hammer Relays PEI/FENWAL 1.18E+05 1.25E+07 1.26E+07 5.00E+07 Temperature Switch ITT-Royal PVC Cable 5.33E+05 2.53E+06 3.07E+06 1.00E+07 Okonite Control 3.14E+05 2.53E+06 2.85E+06 1.00E+07 Cable Triangle Triolene 3.14E+05 7.58E+04 3.90E+05 3.90E+05 Control Cable MNGP-A Cable 1.57E+05 2.83E+07 2.84E+07 5.00E+07 MNGP-B Cable 1.57E+05 2.83E+07 2.84E+07 4.10E+07 Amphenol 5.33E+05 3.79E+06 4.32E+06 6.00E+06 Connectors Pyco Temperature 3.14E+04 2.53E+06 2.57E+06 2.20E+08 Elements SOR Pressure 5.33E+05 2.53E+06 3.07E+06 3.30E+07 Switches General Electric 5.33E+05 2.17E+06 2.70E+06 2.20E+08 Terminal Blocks Patel P-1 Thread 1.79E+07 5.44E+07 2.00E+08 2.72E+08 1.50E+09 Sealant Rockbestos Firewall 1.79E+07 5.44E+07 1.00E+08 1.72E+08 2.00E+08 SR Cable Page 11 of 19
Enclosure 1 EPU EPU Normal Accident Beta Dose Gamma Dose Total EPU Qual. Note Equipment Title (rad) TID (rad) (rad) TID (rad) Dose (rad)
Rockbestos Firewall 1.79E+07 5.44E+07 1.00E+08 1.72E+08 2.00E+08 III/SIS Cable Rockbestos Firewall 1.57E+05 2.83E+07 2.84E+07 1.30E+08 EP Cable Valcor MSIV 3.14E+04 8.66E+04 1.18E+05 5.00E+07 Solenoid Valves Core Spray & RHR 1.57E+05 2.83E+07 2.84E+07 5.77E+07 High Voltage Termination Dow Corning 3-6548 3.60E+04 HELB only 3.60E+04 1.36E+06 Silicone RTV Foam Loctite PST 580 1.79E+07 5.44E+07 Shielded 7.23E+07 7.37E+07 Note Thread Sealant Scotch 130C and 69 7.84E+03 1.08E+08 1.08E+08 1.83E+08 Electrical Tape Fisher E/P 1.57E+05 4.33E+06 4.49E+06 6.00E+06 Transducer Cutler-Hammer 1.24E+05 2.52E+06 2.65E+06 2.80E+06 Note Motor Starter/Control Transformer ASCO Scram 7.85E+04 HELB only 7.85E+04 8.55E+04 Solenoid Pilot Valves Note: Additional supporting qualification analysis to be performed and documented in EQ qualification file and/or equipment to be replaced/modified prior to EPU implementation.
EPU HELB Evaluation HELB is discussed in PUSAR Section 2.2.1. Under the EPU evaluation for HELB, several high energy break or critical crack scenarios were considered for the Reactor Building. These included feedwater, reactor water cleanup, and control rod drive breaks and cracks in various areas. The EPU evaluation for HELBs, in combination with supporting calculations, provides the bases for temperatures, pressures and flood levels used for evaluation of HELBs in the Reactor and Turbine Buildings. The safe-shutdown equipment located in any Turbine Building locations made harsh (i.e. the peak HELB temperature greater than 140°F) as a result of EPU are being determined and evaluated.
From the evaluation for Reactor Building EPU event cases, the following peak conditions are obtained as compared to the current EQ Program Basis values for the respective Reactor Building Volume:
Page 12 of 19
Enclosure 1 Current EQ Program Basis Data EPU Data RB Temp Press Liquid Temp Press Liquid Volume (°F) (psia) (ft) (°F) (psia) (ft) Comment 1 142.97 14.86 0.05 114.2 14.81 0.4 Note 2 142.97 14.85 0.01 115.2 14.8 0 3 143.8 14.98 0.05 115.7 14.83 0.4 Note 4 144.4 14.97 0 135.6 14.82 0 5 256 15.15 0.05 121.3 14.81 0.5 Note 6 263.6 15.63 3.95 157.2 14.8 0.6 7 240.4 15.19 4.38 184.5 14.84 0.8 8 <140 14.99 0 140.7 14.8 0.6 Note 9 187.6 15.59 0.01 127.4 14.79 0.5 Note 10 159.9 15.59 0 127.2 14.79 0.5 Note 11 158.7 15.59 0 127.3 14.79 0.5 Note 12 193 15.59 0.01 127.6 14.79 0.5 Note 13 127.3 14.88 0.24 166.2 14.8 0 Note 14 153.3 14.83 0.27 174.7 14.8 0 Note 15 209.6 15.3 0.05 180.2 14.8 0 16 311.3 21.16 6.68 213.1 15.22 8.8 Note 17 222.4 15.14 0 130.6 14.79 0 18 208.1 15.11 0.68 209.7 14.83 0 Note 19 175.9 15.13 0.53 209.3 14.83 0.1 Note 20 112.5 15.14 0 179.4 14.8 0.1 Note 21 112.2 14.87 0 108 14.79 0 22 170.4 14.84 0 184 14.79 0 Note 23 143.7 14.87 0 164 14.79 0 Note 24 104 14.7 0 104.4 14.7 0 25 145.8 14.85 0 183.5 14.79 0 Note 26 109.1 14.89 0 104.4 14.7 0 27 203.6 14.99 0.01 211.7 14.83 0 Note 28 216.7 15.85 0.38 213.3 15.03 1.6 Note 29 214.6 15.85 0.3 213.5 15.4 1.7 Note 30 220.5 17.2 0.27 218.2 16.52 1.4 Note 31 188.3 17.19 0.27 213 16.52 1.4 Note 32 164.1 15.85 0.19 219.8 17.09 1.7 Note 33 128.3 14.99 0 211.7 14.83 0 Note 34 168.3 14.83 0.005 191.4 14.79 0 Note 35 207.8 14.84 0.02 199.2 14.79 0 36 142.4 14.88 0 141.6 14.79 0 37 112.8 14.88 0 143.9 14.8 0 Note Page 13 of 19
Enclosure 1 Current EQ Program Basis Data EPU Data RB Temp Press Liquid Temp Press Liquid Volume (°F) (psia) (ft) (°F) (psia) (ft) Comment 38 100 14.7 0 100.3 14.7 0 39 215.3 14.87 0.01 112.2 14.8 0 40 126.2 14.84 0 127.7 14.8 0 41 106.9 14.88 0 104.4 14.7 0 42 204.7 14.85 0.01 198.8 14.79 0 43 128.3 14.83 0.01 122.2 14.78 0 44 160.8 14.82 0.01 138.1 14.78 0 45 169.7 14.85 0.01 198.6 14.78 0 Note 46 219.2 14.86 0.02 106.2 14.77 0 47 101.5 14.84 0 187.8 14.78 0 Note 48 131.1 14.8 0.01 137.3 14.76 0 Note: Additional supporting qualification analysis to be performed and documented in EQ qualification file and/or equipment to be replaced/modified prior to EPU implementation.
EPU HELB Temperature Review From the table above, it is observed that the peak EPU liquid break HELB temperatures for Reactor Building Volumes 13, 14, 18, 19, 20, 22, 23, 24, 25, 27, 31, 32, 33, 34, 37, 38, 40, 45, 47, and 48 exceed the currently specified peak HELB temperature provided by the current EQ Program basis data. The peak EPU (or pre-EPU) HELB temperature in Reactor Building Volumes 24, 38, 40, and 48 are less than the harsh/mild threshold temperature of 140°F, so these areas remain mild. Based on EQ end device location and required performance, the impact of EPU HELB conditions focuses on Reactor Building Volumes 13, 14, 18, 19, 20, 22, 27, 31, 32, 33, and 34.
Qualified RB Temp. EPU Peak Equipment Title Volumes (°F) Temp (°F) Note ASCO Solenoid Valves 18, 19 346 209.7 (Normally Energized)
ASCO Solenoid Valves 31 346 213 (Normally De-energized)
ASCO Pressure Switches 14, 19, 31 210 213 Note Barksdale Pressure Switch 14, 18, 212 211.7 22, 33 Barton Pressure Switches 14, 19 212 209.3 Barton Pressure Switches 14, 18 200 209.7 Note 580A-0, 580A-1 G.E. Cable (butyl rubber SI- 13, 14, 18, 340 211.7 58007/58136) 19, 20, 22, 27, 33, 34 Page 14 of 19
Enclosure 1 Qualified RB Temp. EPU Peak Equipment Title Volumes (°F) Temp (°F) Note GE Cable (PE type SI-58081) 13, 14, 18, 236 211.7 19, 20, 22, 27, 33, 34 GE Cable (XLPE type, SI- 13, 14, 18, 340 219.8 57275/58109) 19, 20, 22, 27, 31, 32, 33, 34 General Electric Containment 14, 18 340 209.7 Penetrations General Electric Terminal 13, 14, 18, 340 219.8 Blocks 19, 20, 22, 27, 31, 32, 33, 34 Limitorque MOVs (50.49, class 13, 19, 20, 340 213 RH, AC motor) 22, 31 Limitorque MOVs (50.49, class 13, 32 340 219.8 RH, DC motor)
Limitorque Fibrite Switches 13, 19, 20, 420 219.8 22, 31, 32 Namco Limit Switches (EA740 31 352 213 w/o EC210)
Namco Limit Switches (EA180 18, 19, 31 361 213 w/o EC210)
Raychem NEIS Seals 18, 19, 31 366 213 Raychem WCSF-N Splices 13, 14, 18, 350 219.8 19, 20, 22, 27, 31, 32, 33, 34 Robertshaw Level Switch 18 220 209.7 (DOR)
Rockbestos Coax Cable 13, 14, 18, 346 219.8 19, 20, 22, 27, 31, 32, 33, 34 Rosemount 1153 Series A 33, 34 340 211.7 Transmitter (DOR)
Rosemount 1153 Series B 14, 18, 19, 318 211.7 22, 27, 33, 34 Rosemount Conduit Seals 14, 18, 22, 420 211.7 27, 33 Rotork Valve Operators (50.49) 14, 31, 33 385 213 Static O-ring (DOR) 22, 33 212 211.7 Yarway Level (DOR) 14, 18 250 209.7 Page 15 of 19
Enclosure 1 Qualified RB Temp. EPU Peak Equipment Title Volumes (°F) Temp (°F) Note Samuel Moore Instrument 13, 14, 18, 340 219.8 Cable 19, 20, 22, 27, 31, 32, 33, 34 Valcor Solenoid Valves 18, 19 365 209.7 DG O'Brien Electrical 14, 19 320 209.3 Penetrations DG O'Brien Electrical 14, 19 345 209.3 Penetrations (Plugs)
Reliance Motors 14, 19 464 209.3 Consolidated Control Relays 18 223.1 209.7 Westinghouse Starter and 14, 19 260 209.3 Transformer Eaton Thermocouple Extension 14 375 174.7 Cable Brand Rex 600V Instrument 13, 14, 18, 385 219.8 Cable 19, 20, 22, 27, 31, 32, 33, 34 Boston Control Cable 13, 14, 18, 340 219.8 19, 20, 22, 27, 31, 32, 33, 34 Patel Conduit Seals 18 354 209.7 EGS Grayboot Electrical 31 450 213 Connectors EGS Quick Disconnect 13, 14, 18, 435 219.8 19, 20, 22, 27, 31, 32, 33, 34 Raychem/Swagelok Conduit 14, 18, 19, 340 211.7 Seals 22, 33, 34 Eaton Cutler-Hammer Relays 22, 33, 34 232 211.7 ITT-Royal PVC Cable (DOR) 14, 18, 19, 211 211.7 Note 22, 33 Okonite Control Cable 14, 18, 19, 211 209.7 22 Triangle Triolene Control Cable 18, 19 211 209.7 (DOR)
MNGP-A Cable (DOR) 13, 14, 18, 230 211.7 19, 20, 22, 27, 33, 34 MNGP-B Cable (DOR) 14, 19 211 209.3 Page 16 of 19
Enclosure 1 Qualified RB Temp. EPU Peak Equipment Title Volumes (°F) Temp (°F) Note Amphenol Connectors (DOR) 14, 18, 19, 266 211.7 22, 33 SOR Pressure Switches 14, 22, 33 350 211.7 (50.49)
General Electric Terminal 22, 33, 34 340 211.7 Blocks (50.49)
Patel P-1 Thread Sealant 13, 14, 18, 400 219.8 19, 20, 22, 27, 31, 32, 33, 34 Rockbestos Firewall SR Cable 13, 14, 18, 351 219.8 19, 20, 22, 27, 31, 32, 33, 34 Rockbestos Firewall III/SIS 13, 14, 18, 342 219.8 Cable 19, 20, 22, 27, 31, 32, 33, 34 Rockbestos Firewall EP Cable 13, 14, 18, 320 219.8 19, 20, 22, 27, 31, 32, 33, 34 Loctite PST 580 Thread 14, 18, 19, 364 219.8 Sealant 20, 22, 27, 31, 32, 33, 34 Scotch 130C and 69 Electrical 13, 14, 18, 372 219.8 Tape 19, 20, 22, 27, 31, 32, 33, 34 Cutler-Hammer Motor 14, 19 253 209.3 Starter/Control Transformer ASCO Scram Solenoid Pilot 14, 18 277 209.7 Valves Note: Additional supporting qualification analysis to be performed and documented in EQ qualification file and/or equipment to be replaced/modified prior to EPU implementation.
Post-LOCA Heat-up in the Reactor Building The Reactor Building post-LOCA heat-up temperatures are provided in the associated EPU evaluation. The EPU data as compared to the current post-LOCA heat-up (PLHU) data is presented below. It is observed that most post-LOCA area temperatures are relatively benign and will not present particular challenges to the EQ components that are generally tested or analyzed to much higher accident temperatures at their location.
However, additional supporting qualification analysis to be performed and documented Page 17 of 19
Enclosure 1 in EQ qualification file and/or equipment to be replaced/modified prior to EPU implementation.
RB Volume Current PLHU Temp. (°F) EPU PLHU Temp. (°F) 1 110.0 104.3 2 110.0 106.2 3 129.1 129.7 4 129.1 129.5 5 109.9 107.4 6 140.4 140.6 7 116.3 123.6 8 106.2 111.9 9 160.4 177.5 10 159.9 177.5 11 158.7 177.5 12 157.3 177.5 13 112.6 112.7 14 107.6 112.3 15 106.3 108.7 16 135.2 141.5 17 106.1 108.9 18 109.3 114.9 19 106.3 114.9 20 112.6 113.1 21 112.2 107.8 22 106.7 114.1 23 106.4 113.8 24 104 104 25 113.9 114.1 26 109.1 109.7 27 109.1 115.4 28 120 121.3 29 120.1 121.1 30 120.2 128 31 120.2 129.7 32 120.2 120.7 33 115.6 115.4 34 107.9 114.2 35 107.8 114.2 36 134.4 120.5 37 112.8 120.5 Page 18 of 19
Enclosure 1 RB Volume Current PLHU Temp. (°F) EPU PLHU Temp. (°F) 38 100 100 39 126.3 134.5 40 105.6 113.2 41 106.9 109.8 42 104.6 114.2 43 109.7 110.9 44 108.1 112.1 45 104 114 46 107.2 110.3 47 100 113.7 48 103.9 113.2
SUMMARY
Calculations were prepared to evaluate the impact of EPU conditions on equipment for radiation, temperature, pressure and flood level for safety related equipment. These calculations and related results are described above. The majority of issues will be addressed by revisions to the EQ files that support continued qualification of existing equipment with the new EPU conditions. EQ file updates will be completed as required by 10 CFR 50.49 prior to EPU implementation. Any required modifications or replacement of equipment will also be completed prior to EPU implementation.
Page 19 of 19