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| number = ML20070J716 | | number = ML20070J716 | ||
| issue date = 12/21/1993 | | issue date = 12/21/1993 | ||
| title = Rev 1 to Calculation P(T)-1195, Length of Operation of EDGs During Accident Conditions (Alternate Loading Schemes) | | title = Rev 1 to Calculation P(T)-1195, Length of Operation of EDGs During Accident Conditions (Alternate Loading Schemes) | ||
| author name = Faye W, Wyspianski L, Young R | | author name = Faye W, Wyspianski L, Young R | ||
| author affiliation = NORTHEAST NUCLEAR ENERGY CO. | | author affiliation = NORTHEAST NUCLEAR ENERGY CO. |
Latest revision as of 00:05, 24 May 2020
ML20070J716 | |
Person / Time | |
---|---|
Site: | Millstone ![]() |
Issue date: | 12/21/1993 |
From: | Faye W, Wyspianski L, Young R NORTHEAST NUCLEAR ENERGY CO. |
To: | |
Shared Package | |
ML20070J635 | List: |
References | |
P(T)-1195, P(T)-1195-R01, P(T)-1195-R1, NUDOCS 9407250281 | |
Download: ML20070J716 (46) | |
Text
.. . . -
- i. ,
l NORTHEAST UTILITIES SERVICE COMPANY f i
PfT)-1195 Rev.1 Calculation #:
Length of Operation of(Alternate Emergency DieselSchemes).
Loading Generators
Title:
During Accident Conditions
_(signed) Date M N Prepared by: I!A N u (printed)
L.Wysphd/ ski l
- (signed) Date / '
Y3 Reviewed by /dng Tl.04 (printed)
(Electrical) 9 _(signed) Date / '
// 3 -_ I Reviewed by:M Me d- "
(printed)
W.C. Faye (Mechanical)
/
__(signed) Date _ f Approved by:_ [*E (printed) !
C.J. Ashton [
Page Count: Body of Calc.-17 pages CCN# N/A _
-30 pages Attachments N/A Superseded by:
l 00 O -
Method of reviews fulf rotlied C l
\
VseiFied c omoroxtowI c-ak vfortons "e re Larrea e c Interface / Date
\
Distribution sent NPR i
i n.c. corber I
\. _
\
9407250281 940714 PDR ADOCK 05000423pop P
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\
l Calculation P(T)-1195 Rev.1 Page 2 of 17 i
Calculation Data Sheet tiusco Calc #: N/A (prefix) (sequential (suffix) Latest number) Revision # 1 A/E Calc # / other: P(T)-1195 CCN # N/A Superseded by: ff/A QA (y/n) Y Responsible discipline MECHANICAL Plant P.A. Component ID Computer Code used Rev ., # / level 3ECS*EG-A N/A N/A MP3. N/A N/A 3EOS*EG-B N/A N/A h
3EGr*TK1A 3ECF*TK1B PMMS Code Reference Structure System Component Reference Drawings Sh. Calculations DSL 25212-26917 L Q1-019-15?M3 DG DIE DES TNK NL-033 DFS NL-025 Comment:
1 Calculation P(T).1195 Rev.1 Page 3 of 17 FIGURE 7.2 CALCULATION CHECKLIST Calculation Number P('ll-1195 Rev.1
- 1. Prenaration Section Rev.0 ' Rev.1 ' Rev.2 1.1 Legible, reproducible, comprehensive 6.1.2 NN Nkt/
1.2 ID Logged in, retrievable .
6.1.3 A/P /E w
~
1.3 Documentation format and contents complete 6.1.4 Nk d 6d ;
1.4 As built verification 6.4.6 o& N 01/
- 2. Verification Section 2.1 Prepared in accordance with Section 6.1 6.2.2.1 M 7-2.2 Assumptions reasonable 6.2.2.2 sc.M 2.3 Method acceptable 6.2.2.3 & cot 2.4 Input data correct 6.2.2.4 wctG-2.5 Modeling adequate 6.2.2.5 4vc.%
2.6 Manual calculations correct 6.2.2.6 yc crs_.
2.7 Computer calculations correct 6.2.2.7 v@
2.8 Design requirements met _6.2.2.8 eve or 2.9 Solution correct 6.2.2.9 ucM.
2.10 Software valida'ed 6.2.2.10 v/#
i 2.11 Review method identified '6.2.2.11 WcpJr-
, 2.12 Documentation complete 6.2 wco;P
- 3. Acoroval hem SIGl.QH Preparer / independent reviewer qualified 6.1.1/6.3.1 674 In conformance with NEO 5.06 6.3.2 en5- . _ _
Level of documentation sufficient 6.3.3 un Level of verif. sufficient 6.3.4 us User Software Qualification 6.3.5 6/7 Correctness, completeness, accuracy and quality 6.3.6 a 's l
i
- . _ , - -, - x _
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Calculation P(T) 1195 Rev.1 Page 4 of 17 l
TABLE OF CONTENTS PAGE I. ANALYSIS OBJECTIVE 5 II. DESIGN INPUTS 6 III. ASSUMPTIONS 6 IV. METHOD OF CALCULATION 7 V. ANALYSIS 8
- 1. CASE I " LOP" Description of the operating equipment 8
- 3. Table 1 12
- 4. Table 2 13
- 5. Table 3 14
. 6. Fuel consumption rate graph 15 VI. SUMMA.RY OF RESULTS 16 VII. REFERENCES 16 VIII Attachments ,
17
- 1. Emergency Load Shedding - Table 8.3-1 sh. 5 of 6.
- 2. Emergency Load Shedding -Table 8.3-1 sh. 6 of 6
- 3. Telecon between W. Faye and G. Olsen of Colt Industries dated 2/10/84.
- 4. Memo NE-93-S AB-305 from D.A. Bajumpaa to L. Wyspianski dated August 19, 1993" Review of ECCS Equipment Operation for MP3 Emergency Diesel Generator Load Shedding Calculation".
- 5. Memo from K. Lum to L. Wyspianski dated 9/29/93 " Diesel Loading Table for MODES SA & 5B".
- 6. Memo from K. Lum to L. Wyspianski dated 11/18/93 " Diesel Generator Alternate Loading Schemes Calc. I T)-1195".
- 7. Comments on Calculation P(T)-1195 from Dave Bajumpa.
- 8. Interoffice Correspondence from P. Sheldon to L. Wyspianski.
1 Calculation P(T) 1195 Rev.1 Page 5 of 17 l
- 9. Memo GMB-89-R-521 from W.J. Faye to R.J. Young dated 10/12/1989.
- 10. Memo from K. Lum to L. Wyspianski dated 12/9/93 " Diesel Generator Alternate Loading Schemes Calc. P(T) 1195". i I
i1. Memo PSM3-92-905 dated 10/30/92 from J. Ferguson to C. Clement " Charging Pump i Operation During LOP".
- 12. Telecon between K. Covin and L. Wyspianski dated 12/20/93 " Comments on Calc. P(T)- ;
1195 Rev.1".
I. ANALYSIS OBJECTIVE The objective of this analysis is to give an example of the length of time each of the Emergency Diesel Generators (EDG) can operate under the following conditions:
- only the fuel stored in the underground storage tanks is available (fuel in the day tank and in the system is not considered)
- fuel in the storage tank is at the Technical Specification Level
- only usable fuel volume in the tank is considered
- both diesels continue opetating and use fuel from their respective tanks (crosstie is not used)
- redundant loads are shed from each bus to reduce fuel consumption and balance the electrical loads on each diesel This an example of possible load shedding scenarios. The actual load shedding which may be performed by the operators after an accident will depend on the actual plant response to the accident. This calculation should not be taken as a mandatory load shedding procedure.
The analysis is performed for two accident scenarios:
- 1. Loss of Offsite Power (LOP)
Calculation P(T) 1195 Rev.1 Page 6 of 17 II. DESIGN INPUTS:
- 1. Calc. No. 91-019-152M3 Rev.0 including CNN-001and 002 " Identification of Emergency Diesel Generator Run Times Under Varying Fuel Oil storage Levels"
- 2. Memo NE-93-SAB-305 from D.A. Bajumpaa to L. Wyspianski dated August 19, 1993" Review of ECCS Equipment Operation for MP3 Emergency Diesel Generator Load Shedding Calculation".- (Attachment 4)
- 3. Memo from K. Lum to L. Wyspianski dated 9/29/93 " Diesel Loading Table for MODES SA
& 5B" (Attachment 5).
- 4. Calc. No. NL-033 Rev. 2 including CNN-1, " Emergency Diesel Generator Loading and Starting kVA Calculation"
- 5. Memo from K. Lum to L. Wyspianski dated 11/18/93 " Diesel Generator Altemate Loading Schemes Calc. P(T)-1195" (Attachment 6).
- 6. Comments on Calculation P(T)-1195 from Dave Bajumpa (Attachment 7).
- 7. Interoffice Correspondence from P. Sheldon to L. Wyspianski (Attachment 8).
- 8. Memo GMB-89 R 521 from W.J. Faye to R.J. Young dated 10/12/1989 (Attachment 9).
- 9. Memo from K. Lum to L. Wyspianski dated 12/9/93 " Diesel Generator Alternate Loading Schemes Cale. P(T)-1195" ( Attachment 10).
- 10. Memo PSM3-92-905 dated 10/30/92 from J. Ferguson to C. Clement " Charging Pump Operation During LOP" (Attachment 11).
I1. Telecon between K. Covin and L. Wyspianski dated 12/20/93 " Comments on Calc. P(T).
I195 Rev.1"(Attachment 12).
III. ASSUMPTIONS:
- 1. Both diesel generators run fully loaded for the first eight hours i.e. loads are unchanged from the normal response to an accident. No load shedding occurs during first eight hours. This allows the plant to be stabilized and gives time to evaluate plant status.
- 2. No single failure of the energized equipment occurs during the accident.
- -. . _ ~ .- . - . . . - - .. - _ . - -
Calculation P(T) 1195 Rev.1 Page 7 of 17 IV. METIIOD OF CALCULATION
- 1. Diesel Loads are established for periods of time throughout the postulated accidents i.e. LOP and LOP with DBA for both diesels. Loads remain steady during each period. The loads for both accidents for various time periods are summarized in Table 2. Table 2 was prepared using Microsoft Excel. Loads for each period are summarized in the bottom end later transferred to Table 3 (file link). The detailed description of the equipment operating during the accident as well as time periods is contained in the body of the calculation.
The two cases that are analyzed are LOP and LOP with Containment DepressurizaJon Accident (CDA- Large Break LOCA). The loads for each load center or piece of equipment are based on the latest diesel loading tables established by electrical calculation NL-025 and NL-033 (design inputs 3,4 & 5) for cases l A and 5B (Case SB has a higher load for RHR pump than 5A). The loads are summarized in Table 1. For the first eight hours of the accident for both postulated scenarios these loads are unchanged from the normal response to the accident.
After eight hours operators can take action and reduce the loads on the both generators. All equipment essential to safe shutdown continues to operate but redundant loads are eliminated leaving both diesels partially loaded. In case of any equipment failure its redundant equipment on the opposite train can be started as both emergency buses will remain energized. It should be noted that the analysis assumes availability of both diesel generators. Failure of one diesel would require the other diesel to be fully loaded but in this case fuel stored in the failed diesel generators underground storage tank would be available for the operating diesel. This would extend its operation considerably depending on the time of failure.
- 2. The fuel consumption rate is established for each period of time based on the engine load assumed for this period.
The fuel consumption rate for different loads was provided by the diesel manufacturer, Colt Pielstick. The data (from Rev. O of this calculation)in form of a graph is depicted on page 15. A straight line function was developed to approximate the data. This straight line.
approximation is converted into a equation which can be used to calculate the fuel consumption rate for any diesel load. The chart and the equation were developed using Cricket Graph software. Inspection of the chart indicates that the formula will provide conservative fuel consumption rates for loads between 2000 kW and 4600 kW. This is the kW range for which the fuel consumption is calculated in this analysis.
- 3. The fuel consumption for each period of time is calculated. The total fuel consumed is limited
- to 29180 gal which is the usable fuel volume available in the underground storage tank at the Technical Specification controlled level (DI 1 CNN-001 pg. 9). Table 3 provides the actual operating time in days for both diesels and for both accident scenanos.
The table was developed using Microsoft Excel software. Time periods are shown in the first column. The second column contains the duration of each period in hours. The loads in the third column are transferred from Table 2. The fuel consumption column contains the equation for the fuel consumption rate as described in Section 2. The fuel used column is a result of the
! multiplication of the duration and the fuel consumption rate except for the last row in each table where the fuel volume used up to this point is deducted from the available volume of
, 29180 gal and then divided by the consumption rate for the specified load resulting in the duration of the last period. The duration hours are then summarized and divided by 24 resulting in the total operating time expressed in days.
- 4. The assumed load shedding tables are depicted in chart form (graphs) and are included in the
! calculation as attachments 1 and 2.
i
i Calculation P(T).1195 Rev.1 Page 8 of 17 V. CALCULATION
- 1. CASE I " LOP" Description of the operating equipment.
- 1. Control Building Water Chiller (3HVK*CHLIB) immediately energizes and runs for the duration. The redundant unit does not run per assumption #2 (DI 9). The chiller is required to cool air spaces and maintain electrical equipment within their qualification parameters.
- 2. Neither Quench Spray Pump (3QSS*P3A&B) energize for this case. Here is no increase in containment pressure, nor fission product release to the containment environment which necessitates quench spray operation.
- 3. A minimum of one Residual Heat Removal pump (RHS*PI A or B) is energized at 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and continues to operate for the duration. Reactor Coolant System (RCS) is on natural circulation due to loss of power to RCS pumps. (DI 2).
- 4. Safety Injection Pumps (3SIH*PI A & B) are not required to operate, since no loss of reactor coolant is assumed and no failures in the charging system is postulated.
- 5. Both Component Cooling Water Pumps (3CCP*P1 A&B, or A&C, or B&C) immediately energize per assumption #1 and run for the duration (DI 6).
- 6. Both Auxiliary Feedwater pumps (3FWA*PI A&B) immediately energize and run for 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />. At that time both pumps are stopped (DI 2).
7.Two Service Water pumps (3SWP*PI A.B,C,D) one per train immediately energize and remain on for the duration supplying cooling water to two diesels, CCP, and various air conditioning units.
- 8. None of four recirculation spray pumps (3RSS*PI A,B,C,D) actuate on a LOP event since there is no containment pressure, increase nor fission product release to the containment.
- 9. One Charging Pump (3CHS*P3A or B or C)immediately energizes and remains on for the duration. The redundant pump does not operate per assumption #2 (DI 9 & 10).
- 10. Motor Control Centers 3EHS*MCCI A1,lB1, l A2,1B2, I A4, IB4 and 1 AS, IB5 immediately energize and remain on for the duration, regardless of the loads powered from these MCCs. The main load associated with Motor Control Centers 3EHS* l A4 &
IB4 is the post accident hydrogen recombiner, which is not required to operate for LOP event. The evaluation of shedding individual loads was considered not appropriate.
- 11. 4kV/480V Cable Loss, Load Center Transformer Loss and Small Miscellaneous Transformer Loss are treated as continuous loads for the duration and are included on both trains.
- 12. Both Containment Recirculation Fans (3HVU-FNI A, B) powered from emergency buses immediately energize and run for the duration (the C fan is powered from the normal bus and is not available) (DI 9 & 11).
- 13. Motor Control Centers 3EHS*MCCI A3 and IB3 immediately energize and remain on for the duration, regardless of the loads powered from these MCCs. The evaluation of 9
1 Calculation P(T)-1195 Rev.1 Page 9 of 17 ll shedding individual loads was considered not appropriate. Note: These MCCs include Auxiliary Building electric heaters.
- 14. Both sets of pressurizer heater bundles (3RCS*HI A&B) are immediately energized and )
remain on for the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after that time one bundle can be deenergized. One bundle meets cooldown requirements (DI2). ;
- 15. One Fuel Building Filter (3HVR*FLT-2A/B) and a respective exhaust fan is assumed .
to run for the duration. The other filter train is 100% redundant and is not energized per assumption #2 (DI 9) The filters are started manually.
- 16. One Auxiliary Building Filter unit (3HVR*FLTR-1 A/B) and a respective exhaust fan 4
immediately energize and mn for duration. The A train is the lead train. The B train will come on in case of the A train failure. The other unit is not powered per assumption #2 (DI 9).
- 17. One Spent Fuel Pool Cooling pump (3SFC*PI A or B) is immediately energized and
, runs for the duration per assumption #2 (DI 9).
I8. Motor Control Centers 3EHS*MCC3A1,3A2,3B 1 and 3B2 immediately energize and remain on for the duration, regardless of the loads powered from these MCCs. The evaluation of shedding individual loads was considered not appropriate.
- 19. One Auxiliary Building Exhaust Fan (3HVR*FN6A/B) as stated in para 16, immediately energize and mn foniuration. The other unitis not powered per assumpdon #2 (DI 9).
i
- 20. One train of the Fuel Building Exhaust Fans (3HVR*FN10Al and 2,10B1 and 2) as stated in para 15, are started manually immediately and run for the duration. The other unit is not powered per assumption #2.
- 21. Two Control Rod Drive Mechanism Cooling Fans (3HVU-FN2A & 2B) are energized and run for the duration ( Note: a minimum of one CRDM fan is required to prevent possible degradation of CRDM coil insulation)(DI i1).
- 22. One Instrument Rack Room and Computer Room Air Condidoning unit -
(3HVC*ACU2A OR B)immediately energizes and remains on for the duration. The redundant unit is not powered per assumption #2 (DI 9). ,
- 23. Instrument Air Compressor 3IAS-C1B is energized for the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per assumption
- 2. It may be intermittently used thereafter.
- 1. Control Building Water Chiller (3HVK*CHLIB)immediately energizes and runs for the duradon. The redundant unit does not run per assumption #2. The chiller is required to cool air spaces and maintain electrical equipment within their qualificadon parameters.
- 2. Both Quench Spray Pump (3QSS*P3A&B) energize for this case and run for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Although the system is designed redundantly, two 100% capacity pumps, both pumps run per assumption #1. The pumps are automatically deenergized upon depletion of the RWST. This is conservatively assumed to occur at 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (DI 2).
Calculation P(T) 1195 Rev.1 Page 10 of 17 l
1
- 3. Both Residual Heat Removal pumps (RHS*PI A and B) are immediately energized as low head safety injection pumps and run for one hour at which time thev are i automatically stopped upon preset RWST level instrumentation signal (DI 2). All ECCS systems are designed with two 100% capacity trains. Although one pump is requimd to I mitigate the DB A, both pumps are energized per assumption #1. l 4
1
- 4. Both Safety Injection Pumps (3SIH*PI A & B) immediately energize per assumption #1. l One pump is manually deenergized at 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the remunmg pump contmues for the i duration fulfilling minimum ECCS requirements (DI 2).
- 5. One Component Cooling Water Pump (3CCP*PI A, B, C,) is required at the fourth hour to support spent fuel pool cooling. Under DB A conditions the fuel pool is allowed to heat up to 140*F before cooling is reinstated (DI 7 & 8). Therefore the pump starts at 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and runs for the duration. The second service water pump on the same train is also required to operate for this condition (DI 7).
- 6. Both Auxiliary Feedwater pumps (3FWA*PI A&B) immediately energize and run, the pump on train "A" for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, the pump on train "B" for 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />. After that time both pumps are stopped (DI 2).
- 7. One Service Water pump (3SWP*PI A,B,C,D) on train "A" immediately energizes and l remains on for the duration, two Service Water pumps operate on train "B"- one starts immediately. The second pump starts at 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to support the spent fuel cooling system operation. _-
- 8. All four recirculation spray pumps (3RSS*PI A,B,C,D) start with an 11 minute delay, but ;
for this calculation they are conservatively assumed to start at time zero. Two pumps (one on each train) are manually secured at 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
- 9. Two Charging Pumps (3CHS*P3 A, B, C) one on each train immediately energize per assumption #1. One pump is manually secured after 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The remaining pump ]
continues operating for the duration (DI 2 & 10).
- 10. Motor Control Centers 3EHS*MCCI Al,lB1, I A2,1B2, l A4, IBland 1 A5, IB5, immediately energize and remain on for the duration, regardless of the loads powered from these MCCs. The main load associated with Motor Control Centers 3EHS* 1 A4 &
IB4 is the post accident hydrogen recombiner, which is required to operate for LOCA event. The recombiners are not required until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the event. For conservatism they are assumed to start at 8 and 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> (DI 4 and 7). The evaluation of other individual loads was considered not appropriate.
I1. 4kV/480V Cable Loss, Load Center Transformer Loss and Small Miscellaneous Transformer Loss are treated as continuous loads for the duration and are included on both trains.
- 12. Containment Recirculation Fans (3HVU-FNI A, B) are not safety related (accident mitigating) and hence are not energized for the DB A (DI 9).
- 13. Motor Control Centers 3EHS*MCCI A3 and IB3 immediately energize and remain on for the duration, regardless of the loads powered from these MCCs. The evaluation of shedding individual loads was considered not appropriate. Note: These MCCs include Auxiliary Building electric heaters.
Calculation P(T)-1195 Rev.1 Page 11 of 17
- 14. Pressurizer heater bundles (3RCS*H1 A&B) are not required for accident mitigation and hence are not energized for the DB A (DI 2).
- 15. One Fuel Building Filter (3HVR*FLT-2A/B) and a respective exhaust fan ce energized at I hour. The unit is required to filter the gases that become liberated as the fuel pool heats up (see para 5 and 17). The redundant Glter is not energized per assumption #2.
- 16. One Auxiliary Building Filter unit (3HVR*FLTR J A/B) and a respective exhaust f.
immediately energize and run for duration. The A train is the lead train. The B trai, will come on in case of the A train failure. The other unit is not powered per assumption #2 (DI 9).
- 17. One Spent Fuel Pool Cooling pump (3SFC*PI A or B) is manually energized at 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and runs for the duration. Also see para 5,7 and 15.
- 18. Motor Control Centers 3EHS*MCC3Al,3A2,3B 1 and B2 immediately energize and remain on for the duration, regardless of the loads powered from these MCCs. The evaluation of shedding individual loads was considered not appropriate.
- 19. One Auxiliary Building Exhaust Fan (3HVR*FN6A/B) as stated in para 16, immediately energizes and runs for duration. The other unit is not powered per assumption #1 @I 9).
- 20. One train of the Fuel Building Exhaust Fans (3HVR*FN10Al and 2,10B1 and 2) as stated in para 15, energizes after one hour and runs for the duration. The other unit is not powered per assumption #2.
- 21. The control rod drive mechanisms are not exercised during DBA. Therefo*e there is no need for the CRDM cooling fans (3HVU-FN2A & B) to operate. They are not encruized.
- 22. Or.e Instruraent Rack Room and Computer Room Air Conditioning unit I,3HVC* ACU2A OR B)immediately energizes and remains on for the duration. The redundant unit is not powered per assumption #2 (DI 9).
".3. Instrument Air Compressor 3IAS-C)B is energized for the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per assumption
- 2. It may be intermittently used thereafter.
TABLE 1 EDG LOADS (FROM Dl 3)
EQU'P. EQUIP.
EDG "A" EDG "B" MARK NO. KW MARK NO. KW 3HVK'CHLI A ' 03 3HVK*CHL1B o 303 3OSS*P3A 305 30SS*P3B 305 3RHS*PI A 380/352 3RHS*PIB 380/352 3SlH'P1 A 354 3SlH'PIB # 354 3CCP*PI A 479/300 3CCP*P1B 479/300 3FWA*P1 A 469 3FWA*P1B 469 3SWP*PI A/C 452 3SWP*P18/D 452 3RSS*P1 A/C 359 3RSS*P18/D 359 3CHS'P3A/C 527 3CHS*P38/C 527 3EHS*MCC1 A1 113 3EHS*MCC181 115 3EHS*MCCI A2 192 3EHS*MOC182 175 3EHS'MCCI A4 '79 KW WITHOUT /101 KW WITH H2 REC. 3EHS*MCC1B4 '6 > KW WITHOUT /91 KW WITH H2 REC.
3EHS*MCC; AS 22 3EHS*MCC185 22 4kw4sov cable Less "39.38 4kv/4aov c.bi. Loss **39.38 Load Ce nier Tr. Loss "30.88 toad center Tr. Loss **30.88 Sm. hisc. Tr. Loss "2.5 sm. Misc. Tr. Loss "2.5 3HV'J FN1 A 150 3HVU FN1B 150
- 3EHS-MCC1 A3 221 3EHS MCC183 47 3RCS*H1 A 346 3RCS*H1B 346 3HVR*FLT2A 150 3HVR'FLT2B 150 3HVR'FLTI A 180 3HVR*FLT1 B 180 3SFC*P1 A 97 3SFC*PIB ,, 97 3EHS*MCC3A1 328 3EHS*MCC381 391 3EHS*MCC3A2 138 3EHS'MCC382 64 3HVR'FN6A 69 3HVR*FN6B 69 3HVR*FN10A1 118 3HVR'FN1081 118 l 3HVU FN2A 103 3HVU FN2B 103 ;
3HVC*ACUra 57 3HVC'ACU2B 57 3lAS C1B 120 per DI 4
" per 015 i I
I i
l l
l CALC. No. P(T)-1195 Rev.1 Page 12 of 17
TABLE 2 EDG LOADS FOR LOP AND LOP WITH DBA EDG "A" LOP / EDG "B" LOP / LOSS OF POWER LOSS OF POWER WITH DBA EQUIPMM CDA EOU1PMN CDA TRAIN "A" TRAIN "B" TRAIN "A" TRAIN "B" MARK NO. KW MARK NO. KW 0-1 1-8 8-14 14-36 36 0-6 6-8 8-14 14- 01 1-4 4-8 8 0-1 14 4-8 8-9 9 3HVK*CHL1A 303 3HVK*Cni'B 303 303 303 303 303 303 303 303 303 303 3OSS*P3A 305 3OSS P3B 305 305 305 305 305 3RHS-PI A 352isso 3RHS*P1B Isessoo 352 352 352 380 380 3SlH'P1 A t e ss354 3SlH*PI B iss3:4 354 354 354 354 354 354 354 3CCP*P1A 4 70isoo 3CCP P1B 4 70isoa 479 479 479 479 479 479 479 479 479 300 300 300 3FWA*P1 A 469 3FWA*P1B 435 469 469 469 469 469 469 469 469 469 469 469 469 3SWP-P1 A/C 452 3SWP*P18/D 452 452 452 452 452 452 452 452 452 452 452 452 452 452 452 452 904 904 904 3RSS*P1 A/C 359 3RSS*P18/D 359 718 718 718 359 718 718 718 359 359 3CHS*P3A/C 39s/527 3CHS*P38/C 3991527 399 399 399 399 399 527 527 527 527 527 527 527 i 3D4T4CC1A1 113 3EHS*MCC181 115 113 113 113 113 113 115 115 115 115 113 113 113 113 115 115 115 115 115 3EHS*MCC1 A2 192 3EHS*MCC182 175 192 192 192 192 192 175 175 175 175 192 192 192 192 175 175 175 175 175 3EHS*MCC1A4 79/101 3EHS*MCC1B4 69/91 79 79 79 79 79 69 69 69 69 79 79 79 101 69 69 69 69 91 3EHS*MCC1A5 22 3EHS*MCC185 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22 22
<=v/4sov cab. Loss 39 4kvueov cab.Los, 39 39 39 39 39 39 39 39 39 39 39 39 39 39 39 39 39 39 39 t oad ctr. Tr. toss 31 ;oad car. Tr. Loss 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 31 sm. u.sc. Tr. tees 3 sa uisc. Tr. Loss 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3HVU-FNI A 150 3HVU-FN1B 150 150 150 150 150 150 150 150 150 150 3EHS-MCCIA3 ?21 3EHS-MCC183 47 221 221 221 221 221 47 47 47 47 221 221 221 221 47 47 47 47 47 3RCS*H1 A 336 3RCS*HIB 346 346 346 346 346 346 346 3HVR*FLT2A 150 3HVR*FLT2B 150 150 150 150 150 150 150 150 150 150 3HVR*FLT1 A 180 3HVR*FLT1B 180 180 180 180 180 180 180 180 180 180 3SFC*PI A 97 3SFC P1B 97 97 97 97 97 97 97 97 3EHS*MCC3A1 32e 3EHS*MCC381 j 391 328 328 328 328 328 391 391 391 391 328 328 328 328 391 391 391 391 391 3EHS*MCC3A2 138 3EHS*MCC382 l 64 138 138 138 138 138 64 64 64 64 138 138 138 138 64 64 64 64 64 3tWR*FN6A 69 3HVR*FN6B 69 69 69 69 69 69 69 69 69 69
- tvR*F N1041&2 118 RfVR*f N100112 118 118 118 118 118 118 118 118 118 118 3HVU-FN2A 103 3HVU-FN2B 103 103 103 103 103 103 103 103 103 103 3HVC*ACU2A 57 3HVC*ACU2B 57 57 57 57 57 57 57 57 57 57 31AS-C1B 120 120 120 120 120 120 TOTAL 4081 4081 3735 3266 3266 3532 3884 3764 3295 4620 4240 3466 3129 4641 4529 5073 3713 3266 CALC. No. P(T)-119o REV.1 Page 13 of 17 i
i TABLE 3 LOAD SHEDDING A
TIME LOSS OF POWER TRAIN *A' DURATION LOAD (HR) FUEL CONSUMf7 TION FUEL USED (HR) (KW) 0-1 1.00 GAlJHR GAL.
4081.00 294.47 18 7.00 294.47 8-14 4081.00 294.47 6.00 3735.00 2061.28 14-36 22.00 270.25 3266.00 1621.49 36- 84.15 237.42 3266.00 5223.20 HOURS 120.15 237.42 19979.57 DAYS 5.0 29180.00 TIME LOSS OF POWER TRAIN 'B' DURATION LOAD l
(HR) (HR) FUELCONSUMPTION FUELUSED 06 (KW) GAL /HR I 6.00 3532.00 GAL.
6-8 2.00 256.04 3884.00 1536.23
! 8-14 6.00 280.68 3764.00 561.36 14-106.28 272.28 3295.00 1633.67 239.45 25448.75 HOURS t 120.28 DAYS 5.0 29180.00 TIME LOSS OF POWER WITH DBA TRAIN *A' DURATION LOAD (HR) (HR) FUEL CONSUMPTION FUELUSED 0-1 (KW) GAL /HR 1.00 4620.00 GAL.
1-4 3.00 332.20 332.20 48 4240.00 305.60 2.00 3466.00 916.79 8- 120.39 251.42 502.84 3129.00 227.83 27428.17 FOURS l 126.39 DAYS 5.3 29180.00 TIME LOSS OF POWER WITH DBA TRAIN *B' DURATION LOAD (HR) (HR) FUEL CONSUMPTION FUELUSED 01 (KW) <
1-4 3.00 333.67 333.67 4-8 4529.00 325.83 2.00 5073.00 977.48 89 1.00 363.91 3713.00 727.82 9- 113.19 268.71 3266.00 268.71 HCORS 120.19 237.42 l 26872.32 DAYS 5.0 ,
29180.00, Calc. P(T) 1195 Rev.1 Page 14 of 17
FUEL CONSUMPTION FOR VARIOUS LOADS
- y = 0.070x + 8.798 Linear Equation for Data Points 400 ~
3 (r
-J s v
- q 350 7 l
300 f[
/ ,-
J g_ v 250 o4 GAL /HR u
f g,
200 p j
, b 1 ,
F 150
/
b J 100
/
/
50 [
l 3
~
/
'O !
i 0 1000 2000 3000 4000 5000 6000 DIESEL LOAD in KW a i
Straight line Data points ~~4"'
approximation l Fuel consumption rates (Re f.1) l Load Ib/BHPxhr Gen, eff. kW(elec.) BHP gal /hr 100 % 0.376 0.967 4986 6914.4 361.1 75% 0.362 0.968 3740 5181.1 260.5 50% 0.372 0.964 2493 3468.0 179.2 25% 0.420 0.947 1247 1765.8 103.0
- - 110 % 0.376 0.966 5485 7614.3 397.6 ,
1 l BHP =kWe x 1.341 (HP/kW)/eff. gal /hr= BHP x (Ib/BriPxhr)/7.2 Calc. No.P(T)-1195 Rev.1 Page 15 of 17
Calculation P(T) Il95 Rev.1 Page 16 of 17 VI.
SUMMARY
OF RESULTS The Emergency Diesel Ge.ncrators can operate without refueling utilizing load shedding scheme for the following periods of time:
Diesel A in case of LOP for 5.0 days Diesel B in case of LOP for 5.0 days Diesel A in case of LOP with DBA for 5.3 days Diesel B in case of LOP with DBA for 5.0 days VII.
REFERENCES:
- 1. Telecon buween W. Faye and G. Olsen of Colt Industries dated Feb.10,1984 providing fuel consumption rate.
- 2. Letter to the NRC - Docket No. 50-423 /B14598 dated Sept. 30,1993.
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l Calculation P(T)-1195 'b.1 Page 17 of 17 VIII. ATTACIIMENTS
- 1. Emergency Load Shedding - Table 8.3-1 sh. 5 of 6. Ipage
- 2. Emergency Load Shedding - Table 8.3-1 sh. 6 of 6 1page
- 3. Telecon between W. Faye and G. Olsen of Colt Industries 3 pages
- 4. Memo NE-93-SAB-305 from D.A. Bajumpaa to L. Wyspianski dated August 19, 1993" Review of ECCS Equipment Operation for MP3 Emergency Diesel Generator Load Shedding Calculation". 3 pages
- 5. Memo from K. ! um to L. Wyspianski dated 9/29/93 " Diesel Loading Table for MODES 5A & 5B". 2 pages
- 6. Memo from K. Lum to L. Wyspianski dated 11/18/93 " Diesel Generator 10 pages Alternate Loading Schemes Calc. P(T)-1195"(Revised 12/13/93).
- 7. Comments on Calculation P(T)-1195 from Dave Bajumpa 2 pages
- 8. Interoffice Correspondence from P. Sheldon to L. Wyspianski. Ipage
- 9. Memo GMB-89 R-521 from W.J. Faye to R.J. Young dated 10/12/1989. 1page
- 10. Memo from K. Lum to L. Wyspianski dated 12/9/93 " Diesel Generator 3 pages Alternate Loading Schemes Calc. P(T)-1195" (Revised 12/14/93).
I1. Memo PSM3-92-905 dated 10/30/92 from J. Ferguson to CcClement 3 pages
" Charging Pump Operation During LOP".
- 12. Telecon between K. Covin and L. Wyspianski dated 12/20/93 " Comments 1page on Calc. P(T)-1195 Rev.1".
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cd. P(T)-//15~9 eel AHachnk'?/3 Py 3 cf 3 PAGE 3 0F) C AIJ., DATE 7-[/0[8 4
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CC'01"O"O~' REVIEWED BY [ - ..o
- a. k. a. au:
(} p August 19, 1993 M. s. 6NW NE-93-SAB-305 0' A' 0' W. L V.- M. V. B. To: L. Wyspianski h. A. D. t I l' From: D. A. Bajumpaa h'ohJ g syfrW Ext. 3062 v
Subject:
Review of ECCS Equipment Operation for MP3 Emergency Diesel Generator Load Shedding Calculations
Reference:
- 1) PSM3-93-1015, " Emergency Diesel Load Shedding Calculation Assumptions", L. Wyspianski, 6/26/93.
- 2) Stone and Webster Engineering Corporation Calculation 12179 P(T)-1195, " Length of Operation of Emergency Diesel Generators During Accider.t Conditions (Alternate Loading Schemes)"- 6/4/85.-
- 3) Stone and Webster Eng3naering Corpo7;ation Calculation 12179_-US(B; -2.95-4, "RWST Draw-down Rates and Switchover Levels", 5/21/85.
- 4) Westinghouse Letter, NEU-93-542, 3/16/93.
As requested in Reference 1, Safety Analysis has completed its review of the assumptions on the operation c,f ECCS Equipment following two events, a Loss of Power (LOP) with a Containment Depressurization Actuation (CDA), which is also known as a Loss of Coolant Accident (LOCA), and a LOP event by itself. This memo documents the results of that review. The Reference 2 Calculation calculated the length of time the , emergenc'y diesel generators can operate without refueling utilizing the emergency diesel load shedding provided in FSAR Table 8.3-1 i
.(sheets 5 & 6 of 6) for the above two events in 1985. Since 1985 these load shedding FSAR figures have been modified in the areas of the fuel pool cooling pump for both events and in the associated Train B Reactor Plant Component Cooling Water (RPCCW) Pump and go,nev e-eo
Mc. P(T)-//qs Rev. J AHadwred4 Py 2o,c5 4 1 NE-93-SAB-305 August 19, 1993 l l Service Water Pump for the LOCA case (FSAR dated February 1988) . l The assumptions regarding the operation of the ECCS equipment remains unchanged since the Reference 2 calculation was performed. i I A discussion of the operation of the ECCS equipment for each of the two cases follows.
- s. ingle failure occursNote that this following the evaluation initiation ofassumes these events. that no 7
CASE 1: LOSS OF COOLANT ACCIDENT. ] 1) Time for Automatic Termination of the RHR Pumps: One hour after a LOCA, the Reference 2 analysis assumed that the , Residual Heat Removal (RHR) pumps are automatically terminated on 4 low refueling water storage tank level. From Reference 3, the RHR i pumps are automatically tripped when the RWST volume decreases to a nominal volume of 519,910 gallons. Starting from the tech spec maximum RWST water volume of 1,207,000 gallons and assuming that both trains of the RHR pumps, the Quench Spray System (QSS) pumps, the safety Injection (SI) pumps and the Charging Pumps are delivering flow at their design flows (RHR and QSS pumps - 4000 gpm; SI pumps - 425 gpm; charging pumps - 150 gpm), the one hour time to RHR pump termination is acceptable. _
- 2) Time for Automatic termination of the QSS pumps.
l The empty. QSS pumps automatically tripped when the RWST is escentially - Assuming that both ECCS trains are operating at their design flows, the RWST would empty in significantly less than four hours (calculated value approximately 2 hours. ) for a design basis
'Large Break LOCA (no throttling of ECCS flows). LOCAs of smaller break size would require the pumps to operate for longer than 2 hours.
Consequently, the 4 hour time for QSS pump termination identified in Reference 2 is considered representative of a reasonable range of smaller break LOCAs.
- 3) Time for the operator termination of the Train A Steam Generator Auxiliary at 8 hours.
Feedwater (AFW) Pump at 4 hours, and the Train B AFW Pump Only a limited amount of AFW is required for Large Break LOCA events,The AFW. with the smaller break sizes requiring a larger amount of termination of train A AFW at 4 hours is acceptable.
. Step 22 of the Loss of Reactor or Secondary Coolant EOP (EOP 35 E-
- 1) directs the operator to transfer to hot leg recirculation 9 hours this time.
after the initiation of the event. AFW is not needed after ' Therefore, train B AFW should be terminated at 9 hours instead of the 8 hours stated in Reference 2. l r
. Calc. Pf'7}-//Wtee, f MacAnud 4 ,oy .3 of 5 NE-95-5AB-305 August 19, 1993
- 4) Time for operator termination of the Train B SI pump, Reactor Plant Component hours. Cooling Water (RPCCW) pump, and Charging pump at 8 One train of ECCS is required to mitigate LOCA transients. The operator termination of the above train B equipment is acceptable as the train A equipment is operating.
CASE 2: LOSS OF POWER EVENT. The Reference 2 evaluation of the LOP event assumes that the train B steam generator AFW pump is manually stopped by the operator at 8 hours, and the train A AFW pump is manually terminated at 36 hours when the RHR system is activated. Reference 4 identifies that the Demineralized Water Storage Tank (DWST) hours sizing is currently based upon aligning the RHR system 16 after a reactor trip. Therefore, the assumption of termination appropriate. of AFW and RHR alignment 36 hours after a LOP is not 36 hours. RHR would be initiated by the operator earlier than In fact, if the plane were to be cooled down at the maximum rate of 100 degrees F/ hour identi'fied by Tech Spec 3/4.4.9, then the RCS could potentially enter RHR as early as'two hours after the LOP. A more reasonable early time for RHR initiation following a LOP is 6 hours following a LOP to allow. time for boration (Reference 4). Therefore, we recommend an initiation of RHR 6 hours after the LOP. Reference 4 indicates that with only one train of RHR operating, AFW is required simultaneous with RHR operation, in order to limit RPCCW temperature. Reference 4 identifies that AFW must operate in conjunction LOP. with RHR until 14 hours after the initiation of the After 14 hours, AFW is no longer required. . We firsttherefore 14 hoursrecommend following theboth trains of AFW remain operating for the LOP. The Reference 2 analysis assumes that the train A pressurizer back up heaters are shut off by the operator 8 hours after a LOP, and , that event. the train B back up heaters remain on for the duration of the One train of back up heaters is adequate to control RCS pressure following a LOP. Therefore the timing of the heater termination is acceptable. I l Should Ext. 3062. you have any questions or comments feel free to call me at l DAB /ajs cc: M. S. Etre M. S. Kai l
Cal.c . /*(T)-//95 rev:1 ANachmenf $* 9P /of? ( Interoffice Memo To: Les Wyspianski 6800 - From: Kenneth Lum x5193 Date: September 29,1993
Subject:
Diesel Loading Table for Modes S A and 5B Attached is a table for Diesel Generator Loading for Modes SA and SB for both Train A and Train B. Ifyou have any questions, don't hesitate to call me.
- l cc:
R.J. Young S.I.Stricker l l l l l 1 I l l
- . . _ _ _ - - . . .. - -. =. DIESEL LOAD TABLE TRAIN A > TRAIN B > MODES SA/5B LOADS MARK NO. KW SOURCE CALC. MARK NO. KW SOURCE CALC CONT. BLDG.WTR.CHLR 3HVK*CHL1 A 303 NL-033 3HVK'CHL1 B 303 NL-033 i QUENCH SPR.PMP. 3OSS*P3A 305 NL-033 3OSS *P3B 305 NL-033 RESID.HT. REMOVAL PMP. 3RHS*P1A 352/380 NL-033 3RHS'P1B 352/380 NL-033 SAFETY INJ. PUMP 3SlH'P1 A 354 NL-033 3SlH'P1B 354 NL-033 REACT. PLT. COMP. COOL.WTR.PMP 3CCP'P1A 300 NL-033 3CCP*P1B 300 NL-033 STM. GEN. AUX.FDWTR. PUMP 3FWA*P1 A 469 NL-033 3FWA
- P1B 469 NL-033 SERVICE WTR. PMP. 3SWP'P1 A/C 452 NL-033 3SWP'P18/D 452 NL-033 CONT. RECIRC. PUMP 3RSS *P1 A/C 359 NL-033 g
3RSS*P1B/D 359 NL-033 b CVCS CHARG. PUMP 3'CHS
- P3A/C 527 NL-033 3CHS *P3B/C 527 NL-033 ,D MOTOR CONTROL CENTER MOTOR CONTROL CENTER 3EHS*MCC1 A1 3EHS*MCC1 A2 113 T' gl92 NL-033 NL-033 3EHS*MCC181 3EHS*MCC182 115 175 NL-025 NL-025 g
MOTOR CONTROL CENTER 3EHS*MCC1 A4 101 NL-033 3EHS*MCC1B4 3 L 91 NL-025 MOTOR CONTROL CENTER 3EHS'MCC1 A5 22 NL-033 .3EHS
- MCC185 22 NL-025 LOAD.CTR. TRANSFORMER LOSSES 56 NL-033 56 NL-033 g k'
CONT.RECIRC. FAN 3HVU-FN1 A 150 NL-033 3HVU-FN1B 150 NL-033 MOTOR CONTROL CENTER 3EHS-MCC1A3 221 NL-033 3EHS*MCC183 47 NL-025 PRESS. HTR. B/U GROUP A/B 3RCS*H1A 346 NL-033 3RCS*H1B 346 NL-033 3 FUEL BLDG. FLTR. ASSBLY. 3HVR
- FLT-2A 150 NL-033 3HVR
- FLT-2B 150 NL-033 N AUX. BLDG. AIR FLTR. UNIT 3HVR *FLT-1 A 180 NL-033 3HVR
- FLT-1 B 180 NL-033 ;
FUEL POOL COOL. FAN 3SFC*P1A 97 NL-033 3SFC*P1B 97 NL-033 u' MOTOR CONTROL CENTER 3EHS*MCC3A1 328 NL-033 3EHS*MCC3B1 391 NL-025 Ss MOTOR CONTROL CENTER 3EHS*MCC3A2 138 NL-033 3EHS*MCC3B2 64 NL-025 3-AUX. BLDG.EXH. FAN 3HVR*FN6A 69 NL-033 3HVR *FN6B 69 NL-033 FUEL BLDG.EXH. FAN 3HVR*FN10A1 ,118 1. NL-033 3HVR*FN1081 118 NL-033 7 CONT. ROD DRV. MECH. COOL. FAN 3HVU-FN2A 103 NL-033 3HVU-FN2B 103 NL-033 (A CONT. BLDG. AIR CONDEN. UNIT 3HVC*ACU2A 57 NL-033 3HVC*ACU2B 57 NL-033
- INSTRUMENT AIR COMPRESSOR 31AS-C1B 120 NL-033 g.
NOTES: 1. The kW ratings are taken from modes SA/5B when Calc. NL-033 is listed as the source document. N Where two numbers are listed there are different values for these two modes and they are listed respectively.
- 2. MCC's 3EHS*MCC1 A4 and 1B4 are shown with Hydrogen Recombiners "ON'with a demand factor of 0.5 for 22.5kW. {\j
- 4. change m Rce CNN-! fo CeAc. NL -033 g.w. - i
-(d.e. P(T)-I/15Rev. I r 1' A 440.dwear E l
l Interoffice Memo To: Les Wyspianski x6800 From: Kenneth Lum x5193 Date: November 18,1993 (Revised 12/13/93 to indicate preferrec l
Subject:
Diesel Generator Alternate Loading Schemes - Calculation : Calculation NL-033 will be revised in the future to include losses from tl sources: Loss: KW Loss:
Reference:
PoWF.: 4kV/480V Cable Loss: RUN i 4 coa i 4kV 13.32 Subtract Xmfr Load Loss ( z.ossi Attach. B) from Total 4kV Attach. A) 480V 26.06 Attachment A - Opal Printc jjg, Load Center Transformer Loss: Load 15.43 Attachment B - Opal Printc 32R Load Center Transformeri No Load 15.45 - Attachment C - Transforme Small Miscellaneous Transformers: 2.5 Attachment D - Loss Tabul OPAL MILLt Small Misc. Transformers Total Losses: 72.76KW These losses can be presented within the cale as follows: 4kV/480V Cable Loss: 39.38kW Load Center Transformer Loss: 30.88kW Small Miscellaneous Transformer Loss: 2.5kW The Load Center Transformer Loss is already included in the calculation should be removed at the same time the above losses are added to better loading. CC: R.J. Young .
cade. pyr)-y9sRes. I M. C py 40f/0 Attachment B Page1 of1 7~wsemez bSSes GL3ad h) POWER TECHNOLOGIES INC. POWER SISTEM SIMULATOR,PSS/U VERSION 6.2 RUN 621, RN3343, CABLE Z AT 90 C, FILE: RN3343.CAS CDA RECIRC. MODE THEN LOP FED'A'FROM EDG TRAIN OCT 28 1993 THU, M LOSSES ON TRANSFORMERS 09:59 FROM TO CON TYPE 1-PH SECTION LOAD LOSSES N KVA KW KVAR KW KVAR 34011XH 34C11XL XFMR34 3'),Y -34C31XH 333. 34C31XL XFMR31 168.0 81.6 0.32 333. 728.8 2.33 N - 34C41XH 34C41XL XFMR32 333. 404.1 6.38 44.48
/ 34C51XH 34C51XL XFMR33 502.8 20.8 333. 777.4 297.5 2.34 16.89 } ___. -
6.39 46.47
\
15.43 110.17 TOTAL OPAL LOAD MANAGEMENT SYSTEM MILLSTONE UNIT 3 STATION i 30gg gg fgM /$$ < Auoopr no ioAD xrmR i wss. j 1 l l l l
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Attachment C Page 1 of 4 03-13-92 04:2 .
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$ l APPt.ftQINtlV l IN3tCONOS j APPLIED PCTINTIAL TISTS . gggg yg,, Tact t M60 12 50 k (cw ycqTAcI INOV01: PCTENTI AL TWO TIME 5 8ATED VQt.TAGE AOM013 #ULL WINotNG TEST AT e - ego MtRT: FOM 7200 CYCLf3* mauAnxs Purchase Order No.: 2425-300-243 (E243) Equipment Name: Ventilsted Dry Type Transfermer :ta V Lead Center Mark Nc.1 3EJ5 *US-aA (-0) w' d J.O. No.: 12179 6 Millstone Nuclear Power S,tatien - Unit 3 pq SEp. t 7 O
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, PEPORT OF TRANSFORP ER TESTS hUi *
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j Stone t, Webster / Northeast _ Utilities .- usc.nu.No. 33-49988-Ag % 4 p>ggy_ 9/3/82 PpMCHA!!M'3 CMOER NC. g ,g, N g, 70-}gg7g l [vpg . .' A rwasg 3 sig;2 60 INsutArinc ut:lut.! Air ! 3mes.cH.V. xvA 1000 votTAct__ h180 wtNothe ~ l' V . - xvA -- iBoo yegyggg tigoy n7;
.C !!!! TAN;I3. LCS3EI.lMP,E.D ANCt. AND ARGULATION CCMAt0:LD TO 100 e; n g.3 STANcts. Exc! TING CUAM ENT, LC3113 AND IMPtOANCI-4suf en norm 64 tst*nig, wtwew sturw, e ghted. Lc tws and emtatien are bened on g
t-mnaree rN owrements. F e' three casu tesaslotmers the reshuness sie the sum of t.'re t* tree phases in serie,s. .' 7t E5f frANOI IN CHM S E EXCITE NO LCAD
) SIMl A1. g_1m . xy WINCIN01 SSINI L WAD uo' .J AT17M AT 100% 70- r} g g gy l ~
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..s TAP VOLTAGES SY MATto Tt3T l g
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j l APPLIED POTENTIAL TLIT! HICH VOLTACI 4160 12 60 LCW VCLTACL 480Y/277 4 60 t' INOV013 POTENTIA L
,3 TIIT TWO TIME! RATED VOLTAGE ACA033 FULL WINOING: , AT ggg HgAT: FCR 7700 CY"LIS.
n MAnxs Purchase Order No. : 2 4 2 5- 300-243' (E 243) Equipment Name: Ventilated Dry Type Transfermer 450 V Lead Center Mark No. : 3EJS *US-3A (-0) g. W- ( J.O. No.: 12179 igO Millstone Nuclear Pcwer S4ation - Unit 3 SU. \ 7 O Northeast Nuclear Energy C'empany
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WINDING VCLT RATING TEST VOLTAGE DURATION OF TE.ST y Appt.3so tN xv tNsscoNos APPLIED PQTINTIAL TESTS , , , i, gicgyotyAeg 4160 12 60 tL 480Y/277 4 60-
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- g. W. p h ( f h 73 WUS AOS-14 (-%) 90 ci O,
{, M111 stone Nuclear Power Station - Unit 3 Northeast Nuclear Energy $ g3 g i - t, 4 , l
**' Tested in accordance with NEMA TR-27.
I Mnby etttlP < % CTED* Hetf o^at s esmf erdsen tnig eu w;Y thet thk is e trw #wat eg ,,en y,m t,,m,, ,4,,m.,4 i3. e.,q i, A4 6 s w. . bei+d on fseiery tests rna69 la secoth *4th the tetrit svwd i g ,o O M je y l, f c, 6/l7/82 Am d t,._,,,,- .
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M . p(7)-o7fAw./ AM. 6 py. 9 #0 Attachment D Page1of2 bsses tos ,o FM Nvsc. I RwsFreeme25 A review of the MCC loading tables la NL-033 found 14 lighting and distribution transformers (5 to 25 kVA). The total kW fosses for all of these transfonners is approximately2.5 kW. See aEtous for the method used to calculate the kW losses. These losses were not included in Calculation NL-033 because of the small magnitude. This philosophyis consistent with the other NU nuclear units. DEMAND KVA - Taken from the MCC loading tables in Cale. NL 033 - KW LOAD - Calculated from DEMAND KVA, assum!ng a 0,90 pf. Effielency of distribution transformers Is assumed to be 97% (see below). . KW LOSS = #"
.97 - KW LOAD XFMR NP DEMAND KW KW XFMR I.D. KVA KVA LOAD LOSS-3SCV'XD250* 15 5 4.5 0.139 3 LAD
- EXL10 10 8 7.2 0.223 3 LAC +EXL10 5 4 3.8 0.111 3 LAC'EXL30 to 8 7.2 0.223 3LAT* EXL10 10 8 7.2 0.223 3SCV*XDH2A' 25 15 13.5 0.418 3SCV'XD10*
15 5 4.5 0.139 3SCV*XO100' 15 - 5 4.5 0.139 3SCV*XO240* 15 5 4.5 0.139 3 LAW'EXL10 5 4 3.6 0.111 3SCV'XD90' 15 5 4.5 0.139 3 LAP'EXL10 10 8 7.2 0.223
- %AR* EXL10 10 8 7.2 0.223 1
3SCV*XD50' 15 5 4.5 0.139 2.449 Total kW losses
- Desed on field measurement.
A transformor efficiency of 97% is conservative based on IEEE Red Book (98-99% off.) and telecon with a vendor HEV1 - DUTY ELECTRIC (Soo attached).
N07-17-93 E012:47 E10 Engineering ; Gk.. P(7~)-#93~ Rev. / FM H0. 203 685 5434 P. 0B i TI i 4 dz' l. d 9,9 / 0 o / / 0 e m m m . u.., . PROJEC T TELEPHONE MEMORANDUM _D_
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- Chronological File
SUMMARY
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YYPit'AL cfftctsacy of smALL bRV 7YPM
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Calc. P(T)-//95Rev. / Mlachmed 9t ag. /of/ NORTHEAST UTILmES g_- 1 1%~%~A'r~ $ k ' J ~~. -- October 12, 1989 GMB-89-R-521 ,,
'IO: R. J. Young Berlin, N019 r a rt: 7xc.6f W. C. raye Berlin, WOO 6 Extension 5966 Cool /h SUIkTECT: REVISICNS TO MP-3 DIESEL IDADING KR SPDTP FUEL POOL VD SYSTD1 (SFC) NO HYDROGD4 RECOGI?ER SYSTTM (ENR)
The FSAR tables for diesel loading of the spent fuel pool cooling system (SFC) have the Src pu.:ps starting at four hours for some accidents and 16 hours for others. The original design of the Src system assumed the pu=ps would be off for four hours. If we assume the pu=ps are off for 16 hours, the pool may overheat. Can you look into the possibility of starting the Src pu=ps at four hours for all accidents?. This would require a CCP pu=p and two SWP pu=ps in that train to be operating to support pool cooling. We latest load shedding calculation P(T)-1195 supports -this mode c5 operation. For some reason, it was not incorporated into the rSAR. I also noticed one other change. n e start up times for the hydrogen reco=biners have been changed from four days to 24 hours. This has been calculated in calculation 88-RPS-607GM, Rev. 1. Could you get ne an answer on the Src system by October 207
~
2 anks for the help. , HCr:jk cc R. P. Necci J. H. rerguson G. E. Cornelius G. N. Betancourt D. T. McDaniel J. A. Langan osto citu.1-as B Pt.1
=.~ -_ .- - -_. . . - . _. .-. - . ._
Qu!c,f(f)-N15AA'/ A M men &/0 p7.io/3 Interoffice Memo To: Les Wyspianski x6800 From: Kenneth Lum x519 Date: December 9,1993 Revised 12/14/93 for clarification.
Subject:
Diesel Generator Alternate Loading Schemes - Calculation P(T)-1195 Reference attached pages for additional comments to the subject calc. CC: R.J. Young
DIESEL LOAD ESK REMARKS LSK 3HVK'CHL1A 05DZ These are 100% capacity subsystems. 22-12 07KJ Each Chiller relies on the output of the Chiller on the opposite train. When one reaches parameters, other is shutdown. - 3HVK*CHL1B 05EA There is an 80 second time delay in the Diesel Generator Sequence. 22-12 hl 07KJ There are time delays in the control circuits to reduce the likelihood 3CHS*P3A 05CS of both chillers starting and running at the same time. For an LOP, the last pump that was running is loaded by the Oiesel d 26-02.3 NJ t Generator. Y-l 3CHS*P3B 05CT For a CDA, both pumps start initially. Manually shutdown one pump as 26-02.3 dI required. Both pumps normally run during LOCA as part of the 3CHS*P3C 05CU Safety injection System. 26-02.3 h 05CV Pump C is a swing pump that is interchangeable with A or B. h' E 3HVU-FN1A 06BA Both fans start initially. Manually shutdown one fan 22-27 . 06BAZ as required. !
- 06AMQ Actuation on LGP only and SIS and/or LOP, not CDA Recirc then LOP. .
3HVU-FN1B 06BB
- 22-27 06BBA b-06AMQ d l 3HVR*FLT2A 06AFG Filter unit is slaved with 3HVR*FN10A1/A2. 22-01 s 3HVR*FLT2B 06AFH Filter unit is slaved with 3HVR*FN1081/B2. 22-01 g
- 3HVR*FLT1A 06AFE Filter unit is slaved with 3HVR*FN6A. 22-01 [
\-
3HVR*FLT1B 06AFF Filter unit is slaved with 3HVR*FN6B. 22-01 I { l - - -
1 t DIESEL LOAD ESK REMARKS LSK 3SFC*P1A 06AG Operator may manually start either or both (not likely both). 34-01 ; l 3SFC*P1B 06AH 34-01 3HVR*FN6A 06SB Starts first. 22-01 3HVR*FN6B 06SC Starts on FN6A failure. 22-01 l 3HVR*FN10A1 06SH Start one bank only manually, if one bank fails 22-01 3HVR*FN10A2 06BAF then other starts. Only one manual start. } ( 3HVR*FN10B1 3HVR*FN1082 06SJ 06 BAG 22-01 k q S 3HVU-FN2A 06AV Both fans start on Sequenced Safeguard Signal. 22-27 D 06BAW Actuation on LOP only and SIS and/or LOP, not CDA Recirc then LOP. b 06AMQ N ' A 3HVU-FN2B 06AW . 22-27 * ' 06BAX ; 06AMQ w ( t 3HVC*ACU2A 06VK Slaved with 3HVK'P1 A with 180 second time delay. 22-09 j One unit will shutdown based on flow / temp of opposite train unit. s D 3HVC*ACU2B 06VL Normally the operation of one unit will prevent the opposite unit 22-09 from operating. l Q-i h l 0 . N w '
jm-2-92 MON 7:55 N.U.(Eng.)
- j. Calc. P(1)-n95~ Rev /
FAX NO. 2036653753 P0 1 NORTHEAST UTitJTIES AMadeunHJ Py /q? 3 c, , , _ _ _ _ d~ e . L =c= w =_ =w i y u g rm lAMJ October 30,1992 PSM3-92-905 To: C. Clement From: hcrgusonotn W by)Dtfy Berlin N020 Ext. 5815 i
Subject:
Ch9erine Pomn Omration Durine LOR I
References:
STONE & WFRS7TsR_
- 1. LSK-24 9.4A & 3B
- 2. LSK-26-2.3A & 3B
- 3. ESK-5CS, CT, & CU lYESTINGHOUSH
! 1. Interlock Descriptions and Logic Diagram
- 2. Drawings- 271c796 Sheets 29,3031 & 32 NORTHEAST rmLITTES_
- l. MP3 FSAR Chapter 7, Section 7.3.1.5 "ESF and Essentral Auxiliary Support System" 2.Memo
- 3. OD.i-427-1 A "Ernergency Generator toading Se
- 4. Memo, E. Oswald to C. Clement, dated 1Gr28/92,qu_enen' ISSUE: M. Kai to C. Clement, dated 10/30/92, NE-92-SAB 363NE.92-SAB.361 During the design review for PDCR (MP#.92103) which propos ,
i' modibcations es certain design operations will need toto the turn on aAuxillary second Char Building Ventilation, a request we brought certain outsido air temperatures. At this time,ging Pump aner a loss of power (that LOP), for them off. The purpose of this memoranda s s to tum one of is to evalusta ifst r ng a second Charging design base documentation support , oes the MP3 anLOP. only one Charging g.,nv
- 1, rov- 2-v2 n0N 7:55 N.V.(Enc.)
Qz(c, f'(7)~ -//(106tl. lFAX NO. 203665375)
$Cbmec&O W.)R. 03 IIISTORY: i To review the design basis of the Charging Pamp design,it was a rc< ulrement to search Nuclear Records for allinfonustion from the Westinghouse file. In L974, Westinghouse issued (Ref 2) to S&W for incorporation into Millstone Unit 3. Als design was for the Centrifugal Charging Pumps to be started automatically upon a
- blackout f or tho following reasom A continued supply of seal injection water to the reactor coolant ps tt destred subsequent to a blackout. Since the ch pumps are safeguards equipment. cach is energ y n separate emer y bus and dieselupon loss of outside power. If a e pump not previously running would not start underb1 tcondidens,failum of the diesel connected to the running pump would result in loss of sealinjection flow; therefore proper logic as required by this interlock will attempt to start both Centnfugal Charging Pumps automatically upon loss of outsido power, assuring sealinjection flow. If both Charging Pumps are energized, the only operator action equired is to shut down one pump Dased on this Logic & Interlock information, Westinghouse developed the Millstone Unit 3 Elementary Wiring Diagrams. Dese diagrams specifIcall state in the design (LOP contact) along with the associated notes that both Ch Pumps are requfred to be started after an LOP. %cse dmwings were sent to S&W r incorporadon into Millstone Unit 3 under a Westinghouse letterhead. As of today, these drawings are in the Northeast Utilities drawing system and are showing a LOP contact for all three pumps to start after nn LOP. Based on this information from Westinghouse, a review was performed on the S&W documentation. The leading document for S&W is the Logic Diagram. nts diagram shows the (SSS) safeguard start signal to start the putnp under safety signals along with an LOP condition, but not an LOP signal alone. This design also shows in the electrical ESK's for all three Charging Pumps. Also, revicwing the Millstone FSAR and the sequencer OIM, both documents state that the design is one pump starting after an LOP.
Based on reviewing both sets of documentation,it was concluded that the Westinghouse design requires both Charging Pumps starting after an LOP nnd the S&W design only requires one Charging Pump to start. norefore, the issue is which drawing is correct,is the existing design safe, and what is necessary to correct the problem. To review the design process of S&W, a review of the system drawings and conversations with the original S&W design team were performed. Part of the effort was to review historical letters between Westinghouse and S&W for discussions on the control logic for the Charging Pumps. This review tumed up no formalletters on this issue, The Westinghouse letters were issued to S&W forinformation and use only. Also, discussions recollection of the desig,n was on)ly one pump starting and not two. O that one pump was startmg with a suetion path off the VCT was required for relief of stress within the system. Reviewing the Teledyne stress packages did not support this. ' Therefore, there is no information at this time on why S&W designed into the system a one pump start and not two after an LOP. Because this is a Westinghouse requirement, phone calls were made to other Westinghouse plants to arify their design. Phone calls wem placed to Commanche Peak, Seabrook Station, and Beaver Valley, and all three plants stated that both Charging Pumps start after an LOP. Pse2
i
, '. !'0V- 2-92 tion 7:56 ftU.(Eng.)
FAX 110. 2038653753 P 04 [ g ) f & -// 9[ 06V. I Y U b MS O I S e f f d f~3 AS. BUILT DESIGN: Based on Engineering review of the Charging Pump System and a review of the drawing, the operation Is asfollows: During normal cpration, one Charging Pum p is running and charging flow is centrolled automatically by the pressurizccIcVel. On a:oss of power (LOP) the Charging Pumps are not stripped from the bus and do not receive a start signal after a LOP only. The Charging Pump that was running will restart when emergency diesel generator breaker is closed (powerrestored). EOP requires the operator to confirm that the Charg*mg Pump is running and to stan the redundant pump if the pump previously ranning fails to start. Two Charging Pumps are actuated by the sequenced safeguard signal whenever the following conditions exist:
- SIS or SIS and LOP
'
- CDA or CDA andLOP
- SIS recirculationmode and then LOP
- CDA recirculation mode and then IJJP CONCLUSION:
Within the Northeast Utilities Millstone Unit 3 design systern, there exists two designs on how the Charging Pumps operate. The current Emergency Generator Lead Sequence Charging Pump logic meets Mllistone 3 design basis documents as promulgated by the
' NRC. Internal documentation from the corresponding period is not available to provide the basis for the existing charging pump actl'. don on an LOP.
RECOMMENDATION: Because the existing design meets all the requirements within the Millstone Unit 3 FSAR,- operations is trained for this condition along with the EOP's, PSD Eng'meering has concluded that this is not a startup issuo for Millstone Unit 3. Also, to support this recom mendation, Reactor Engineerin adequate and also not a startup issue, g and the PRA group has concluded that this desi Engineering is proposing two solutions to provide a consistent design for the Unit. The first recommendation is to update all Westinghouse documentation showing the as. built configuration of the Chargin Westinghouse prior to the change.g Pump controls. This willinclude concurrence from The second recommendation is to initiate a Project Assignment (PA) to modify the diesel sequencers, nis modification will add an LOP si nal for each Charging Pump which will be separated from the Safeguard Start Signal (SS . His design will put the Unit in compliance with the Westinghouse design and th )S&W documentation will be revised to reflect the Westinghouse quirements. , This is an initia' .ssesmed and will be revised as additional information is available, cc: R. Young H. Risley G. Olsen P, Austin D. McDaniel R. D eich R. Joshi D. Gerbet page 3
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