ML17309A460
| ML17309A460 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/22/1991 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17262A448 | List: |
| References | |
| NUDOCS 9104300197 | |
| Download: ML17309A460 (49) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9104300197 DOC.DATE: 91/04/22 NOTARIZED:
NO DOCKET SCIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSONFA.R.
Project Directorate I-3
SUBJECT:
Forwards answers to NRC 910321 station blackout questions.
DISTRIBUTION CODE:
A050D COPIES RECEIVED:LTR I
ENCL J SIZE'.
TITLE: OR Submittal: Station Blackout (USI A-44) 10CFR50.63, MPA A-22 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 >
RECIPIENT ID CODE/NAME PD1-3 PD INTERNAL: NRR PD1-4PM TAM NRR/DST/SELB NRR/DST/SRXBSE EXTERNAL: NRC PDR COPIES LTTR ENCL 1
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1 3
3 1
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TOTAL NUMBER OF COPIES REQUIRED:
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//r//r r/r Lier 01I>a ROCHESTER GAS AND ELECTRIC CORPORATION o
89 EAST AVENUE, ROCHESTER N. Y. 14649.0001 ROBERT C. MECREDY Vice Prerldent Clnna Nuclear Production TELERtONE AREACODE 7lB 546 2700 April 22, 1991 United States Nuclear Regulatory Commission Document Control Desk Attn:
Mr. Allen R. Johnson Project Directorate l-3 Washington, DC 20555
Subject:
10 CFR 550.63, Loss OfAllAlternating Current Power R. E. Ginna Nuclear Power Plant Docket Number 50-244
References:
R. C. Mecredy (RG&E) to T. E. Murley (NRC), April 17, 1989 R. C. Mecredy (RG&E) to T. E. Murley (NRC), July 10, 1990
Dear Mr. Johnson,
On March 21, 1991, Rochester Gas & Electric Corporation received a telefax transmitting eight questions pertaining to our above referenced submittals concerning 10 CFR 550.63, Loss OfAll Alternating Current Power.
Answers to these questions are attached.
Very truly yours, Robert C. Mecredy xc:
Mr. Allen R. Johnson (Mail Stop 14D1)
Project Directorate l-3 United States Nuclear Regulatory Commission Washington, DC 20555 Ginna Senior Resident Inspector gogo
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RG&E Answers To The NRC's March 21, 1991 Station Blackout Questions Page1 of 4 Target Emergency Diesel Generator (EDG) Reliability Provide a verification that the EDG target reliability of 0.975 will be maintained.
Response
As stated in our station blackout responses of April 17, 1989, and July 10, 1990, RG8 E has selected a target EDG reliabilityof 0.975. Established maintenance and testing practices have resulted in a calculated EDG reliability that has consistently exceeded this target value.
RG8E is committed to continuing these highly successful practices, and to meeting or exceeding the targeted EDG reliabilityof 0.975.
RG8 E plans to implement Nuclear Utility Management and Resources Council (NUMARC) Station Blackout Initiative 5A as soon as NRC Generic Issue B-56 is resolved.
Condensate inventory a.
The submittal states that the reactor will be cooled down.
Please indicate the degree of cooldown and depressurization required and the amount of condensate needed to accomplish the cooldown.
Response
Required condensate was calculated per NUMARC 87-00, Section 7.2.1.
This calculation assumed a 50'F per hour cooldown, utilizing both atmospheric relief valves.
Calculations have shown that this degree of cooldown would require 4.32 x 104 gallons of water; therefore, the total amount of condensate required, per the NUMARC 87-00 equation, is 76,823 gallons.
Verify that the three alternate sources of water for decay heat removal are available for use under SBO conditions.
Is a transfer pump necessary to utilize the 110,000 gallon outside storage tank?
Do these sources provide adequate NPSH for the turbine driven auxiliary feedwater pump?
Response
The outside condensate storage tank, the fire water system, and the city water system are available as alternate water sources under station blackout conditions, per procedure ER-AFW.1, Alternate Water Supply To The AFWPumps.
Transfer pumps are not necessary to fill the condensate storage tanks from the outside condensate storage tank; this has been confirmed by testing.
Tests have shown that all of these sources can be used to fillthe condensate storage tank at rates sufficient to remove decay heat from the reactor coolant system.
Since the alternate sources of water are all used to refill the normal water supply (i.e., the CST), adequate NPSH is assured.
RG&E Answers To The NRC's March 21, 1991 Station Blackout Questions Page 2 of 4 C.
The turbine driven auxiliary feedwater pump has a lube oil cooler cooled by service water.
In your submittal of July 10, 1990, you indicated that you intended to study the use of fire water as a backup for the service water. You also indicated that the evaluation would be completed by September 1, 1990.
What were the results of the evaluation?
Is a test still planned to be completed by June 1, 1991?
If fire water was determined not to be viable, what alternative plans have been made for the lube oil cooler water?
Response
The diesel driven fire water pump was evaluated per the criteria of NUMARC 87-00, Appendix B, and was found to be acceptable for use during station blackout scenarios.
RG&E is planning to conduct a test by July 1, 1991, to verify the time required to establish a lineup that will allow directing fire water to the turbine driven auxiliary feedwater pump oil cooler and bearings.
RG&E has previously shown by testing that the turbine driven auxiliary feedwater pump can run for at least two hours without any service water cooling to its bearings and oil cooler, and that the fire water system can deliver substantial flow to the service water system piping.
Class 1E Battery Capacity Provide the battery loads and the battery capacity calculation which was performed to verify that the installed Class 1E batteries have sufficient capacity to provide power for all connected loads during a four hour SBO event.
Response
The requested information and analyses are included in Attachment 1. As noted on the cover memo, several of the larger DC loads on the station batteries are being removed during the refueling outage that is now underway. Therefore, the attached analyses are conservative.
Compressed Air Is the backup nitrogen supply to the atmospheric steam dump valves (ADVs) sufficient to support ADVoperation for four hours during an SBO event?
Response
The backup nitrogen supply consists of six nitrogen bottles for each of the atmospheric relief valves.
This backup system was sized to provide eight hours supply of nitrogen to the atmospheric relief valves following a loss of all power.
~
RG&E Answers To The NRC's March 21, 1991 Station Blackout Questions Page 3 of 4 b.
Provide the results of your evaluation of the area of the ADVs during manual operation.
Response
A calculation utilizing NUMARC 87-00 methodology was completed for the atmospheric relief valve area in the Intermediate Building. A copy of this calculation is included in Attachment 2.
5.
Loss Of Ventilation a.
Describe the analyses that were done to verify that the control room temperature does not reach 120'F during a four hour SBO event.
Provide the initial conditions
- assumed, heat sources and sinks, and assumptions utilized.
Response
A copy of the control room heatup analysis is included in Attachment 3.
Was NUMARC 87-00 methodology utilized in calculating the steady state temperature of the steam driven AFW pump room?
If not, describe the methodology used.
Response
NUMARC87-00 methodology was used to calculate the steady state temperature of the turbine driven auxiliary feedwater pump area.
A copy of this calculation is included in Attachment 4.
6.
Containment Isolation Provide a list ofthe containment isolation valves of concern.
Containment isolation valves of concern are those valves which can not be excluded by the criteria given in RG 1.155 or NUMARC 87-00.
An example of such a valve would be a normally closed valve (not locked closed) that fails "as is." Provide the actions to be taken for each valve to effect containment isolation during an SBO and verification that these actions are contained in plant procedures.
Response
A list of all containment isolation valves, along with the NUMARC 87-00 criteria used to exclude them, is included in Attachment 5.
RG&E Answers, To The NRC's March 21, 1991 Station Blackout Questions Page 4 of 4 Reactor Coolant Inventory Describe the method used to assess reactor coolant system inventory for four hours following onset of a SBO.
Response
Asimulation using the TREAT code was run for the projected station blackout scenario.
A summary of this simulation and a selection of plots from the simulation results is included in Attachment 6. The station blackout transient was also evaluated with MAAP 3.0B Revision 17; similar results were obtained.
b.
What primary system RCP leak rate was assumed?
Response
The TREATsimulation assumed a loss of 25 gpm per reactor coolant pump seal, per NUMARC87-00, and an additional 11 gpm loss, per the maximum losses allowed in the Ginna Technical Specifications.
This resulted in a total loss of 61 gpm at time zero.
What are the conditions of the reactor coolant system at the end of the SBO event?
Response
Per Question 7a, above, selected plots from the TREAT output are attached.
Quality Assurance List SBO response equipment and identify the QA program associated withthe equipment.
Response
A list of the equipment required to respond to a station blackout is included in Attachment 7.
This list identifies the QA classification of each of these components.
Of the items classified as, "Not Nuclear Safety," Bus 15 and Bus 15, Unit 3A are used to power a charging pump from the Technical Support Center diesel generator.
The TREAT analysis of station blackout has shown that this pump is not required to maintain natural circulation flow in the reactor coolant system during a four hour station blackout; therefore, this equipment is not required to operate.
The outside condensate storage tank and the series of manual valves used to route water from the outside CST to the main condensate storage tanks are also classified as, "Not Nuclear Safety."
Since this is one of three possible methods of getting water to the condensate storage tanks during a station blackout, and the other two sets of equipment are already used for Appendix R, RG&E does not believe that reclassifying the outside CST and the manual valves is necessary.
Design Analysis Ginna Station Sizing of Vital Batteries Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 EWR 3341 Prepared by:
'~/~+kg
, v "OATK Reviewed by:
C OATE Approved hy:
Z 1Z90 OATK DA5 9 '3PP197 Page i 42 92
Revision Status Sheet Latest Rev.
Page Latest Rev.
- Page, Latest Rev.
5 6
8 10 l3 14 15 16 17 19 20 Design Analysis 3341 Page ii Revision Date XXZZXZZX Gi'rI'r-.
4Z 91
The objective of this analysis is to provide a basis for the capacity of Ginna Station vital batteries, designated 1A and 1B.
This analysis replaces the previous basis document (analyses),
"Class 1E Battery Testing Program",
EWR 3341, Rev.
1, dated 9/9/85. It is based on IEEE Standard 485-1983, "Recommended Practice for Sizing Large Lead Storage Batteries for Generating Stations and Substations".
This standard utilizes the sizing method, developed by E.A. Hoxie, Reference 3.4.
Due to the treatment of momentary
- loads, the method is considered very conservative.
1.2 1.3 1.4 This analyses will provide the basis for ongoing battery load tracking.
Electrical Engineering project review practice will assure that this analysis, including the duty cycles and supporting tables, and the sizing worksheets, are revised when accumulated load changes become significant with respect to battery capacity margin.
This analysis will establish a basis for the Battery Service Test.
The battery duty cycle as tabulated below will be the basis for the test load profile.
The Service Test load profile should envelope the duty cycle with the exception of momentary loads.
Momentary loads are all assumed to continue for one minute in the duty cycle without regard to actual duration, which may be a fraction of a second,.
This is a conservative assumption appropriate to si'zing batteries (Hoxie method),
however a more realistic simulation of momentary loads may be used for the Service Test.
This analysis will establish a basis for battery capacity consistent with the blackout duration (4
hours) determined appropriate for Ginna Station pursuant'to 10CPR50.63, "Station Blackout".
This requirement is described in Reference 3.7.
2.0 Desi n In uts 2.1 IEEE Standard 485-1983, Sizing Large Lead Storage Batteries for Generating Stations and, Substations.
2.2 RG&E Dwg. No. 33013-756, Sh. l.
2.3 RG&E Dwg. No. 33013-756, Sh.
2.
2.4 RG&E Dwg. No. 10905-236 2.5 2.6 RG&E Dwg. No.
RG&E Dwg. No.
10905-237 10905-238 Design Analysis EWR 3341 Page 1
Revision Date W/e /e~
2.7 2.8 3.0 RG&E Dwg. No. 10905-239 RG&E Dwg.
No..
21945-357.
Referenced Documents 3.1 3.2 3.3 3.4 3.5 o
3.6 3.7 3.8 4.0 IEEE Standard 485-1983, Sizing Large Lead Storage Batteries for Generating Stations and. Substations.
Letter from Dennis L. niemann, USNRC, to Leon D. White Jr.
RG&E, dated 4/18/79, topic UIII-3.AStation Battery Test Requirement.
Letter from Dennis M. Crutchfield, USNRC, to John E.
- Maier, RG&E, dated 7/31/81, Safety Evaluation for SEP Topic VIII-3.A, Station Battery Capacity Test Requirements (Ginna).
E.A. Hoxie, "Some Discharge Characteristics of Lead.
Acid Batteries",
AIEE Transactions (Applications and Industry), vol. 73, pp 17-22, 1954.
Handbook of Modern Electronics and Electrical Engineering.
GNB Battery Specification Sheets, Switchgear and General Industrial Power Cells, Type NAX and NCX, Capacities 600 A. H. to 2550 A. H.
Letter to T.E. Murley, NRC, from R.C. Mecredy, RG&E, 10CFR50.63, Station Blackout, R.E.
Ginna Nuclear Power
- Plant, dated April 17, 1989.
Letter form R.L. Steele, Westinghouse, to C.E. Platt, RG&E, dated 4/19/71, Station Battery Test.
Assumntions 4.1 4.2 It is assumed that the inventory of d.c.
loads contained in this analysis is complete.
This assumption is supported.
by a review of battery charger currents taken during surveillance inspections, performed over the past year, which indicated currents between 100 and 108 amps.
This is in good agreement with the analysis data.
For the purpose of sizing the battery it is assumed that all a.c.
power sources are lost for a period of two hours, after which time the diesel generators become available and those circuit breakers required, to energize the a.c.
system from the diesels are closed.
This assumption (2hrs) is based on requirements stated.
in Reference 3.3. It will be shown that this time can Design Analysis ENR 3341 Page 2
Revision Date
4.3 4.4 be extended to four hours without changing the cell sizing requirement.
It is assumed that five percent (20) of the approximately 400 d.c. solenoid valves are energized from each battery at any time, and that each solenoid draws 0.25 amps.
After accounting for all other loads, this assumption provides good agreement with the observed battery charger loads.
The large d.c. continuous duty motor loads are designed with current limiting resistor networks to limit starting inrush current.
The inrush current for the turbine d.c.
lube oil pump has been measured at 625
- amps, which is 1.72 times the running current. It will be assumed that starting inrush current for the other large d.c. continuous duty motors (for which there is no data) is 2 times running current.
This assumption is based on standard design practice for d.c. motors which limits starting inrush current to 2 x running current due to commutation limitations (see p.
3252 of Reference 3.5). It should be noted that motor operated valve motors do not have current limiting resistors to limit inrush current.
MOV inrush currents have been measured during the MOVATS testing program and 'the analysis data was taken from this source.
Computer Codes 6.0 6.1 The capacity factors, K, utilized in the Cell Sizing Worksheet are calculated using a least squares polynominal curve routine.
This software is documented in Appendix 2.
Analvsis Battery Duty Cycle 6.1.1 The loads representing the battery duty cycles are shown in Figures A1 and B1.
Individual loads are shown on Tables Al and B1.
The loads are further broken down in Tables A2 and B2, Motor Loads, Tables A3 and B3, D.C. special
- Loads, and Tables A4 and, B4, D.C.
Miscellaneous Loads.
6.1.2 6.2 6.2.1 Circuit breaker tripping is described in Appendix 1 and an inventory of tripping loads is provided.
Cell Sizing Calculation Cell sizing is performed using the cell sizing work sheet from IEEE Std. 485.
These work sheets a'e designated Table A5 and B5 for the A and B battery respectively.
Design Analysis EWR 3341 Page 3
Revision t
6.2.2
~
~
6.2.3 6.2.4 The load data for entry on the work sheet is obtained, from the battery duty cycle, Figures A1 and Bl.
/
The battery data is obtain from the GNB Battery Specification Sheets, Reference 3.6.
The capacity rating factor, K, is calculated as the ratio of the battery ampere-hour capacity (1200 A.H.)
to the discharge rate to 1.75 VPC at 25'C appropriate for the time interval T as given in the sizing worksheet.
6.2.5 The temperature correction factor is 1.02.
This is based on Table 1 of IEEE Std. 485-1983 and the design of the temperature control system for the battery rooms which is set to maintain temperature at 75'F (23.94C)
+
24F.
6.2.6 The design margin is entered as 1.0, since the battery is already installed.
After completing the sizing calculation the existing margin is determined.
6.2.7 6.2.8 For the "A" battery an aging factor of 1.25 is used to allow for the degradation in battery capacity permissible at end, of the 20 year design life. It should be noted'that battery discharge tests performed in 1987 did, not indicate any capacity degradation and since this battery is relatively new, the aging allowance can at this time be considered an additional capacity margin.
This analysis should be revised. to account for the results of the future discharge tests.
For the "B" battery an aging-factor of 1.10 is used, since the loading does not permit the standard 1.25.
This will reduce the design life of the battery by approximately one half until the duty cycle is adjusted to decrease the load during the first minute of discharge.
Since the battery showns no indication of capacity degradation at this time it is fully capable of performing its safety function.
- However, a plan to reduce the d.c.
loads by transfering non-class 1E
This would provide for the full design life and provide margin for uncertainty and additional loads.
7.0 Results 7.1 The cell sizing, calculations documented in the worksheets show that battery cell size is sufficient for it to perform its design safety function.
If the duration of loss of all A.C. power is extended from two to four hours the duration of the appropriate Design Analysis EWR 3341 Page 4
Revision Date
~c'~ ~ R~
period is increased by two hours.
Review of the sizing work sheet shows that the existing battery cell size is still adequate as shown, on cell sizing worksheets, Tables ASA and B5A.
The battery, therefore, meets requirements established in 10CFR50.63, "Station Blackout".
7.3 7.4 7.5 7.6 The "B" battery is currently limited in design life due to loading.
Modifications to this system should be planned.
Consideration should be given to removing large non-Class 1E loads from both vital batteries and placing them on the TSC battery.
Electrical engineering design review practice should specifically address d.c.
load. tracking to assure that no significant loads are added without revision of this analysis.
The limiting loads are the turbine d.c. lube oil pump on "A" battery and the circulating water discharge valve operators on "B" battery.
These loads have been present since plant start up.
The original 1050 A-H batteries would not have had adequate capacity using the current conservative criteria of this analysis.
The TSC battery was significantly oversized in order to serve as an emergency backup for either vital battery.
Loss of all A.C. procedures, ECA-O.O, call for use of the TSC backup in the event of d.c. voltage falling below 105U (1.75 UPC).
This feature of the Ginna D.C.
system provides additional margin for emergencies exceeding the plant design bases.
Design Analysis ERR 3341 Page 5
Revision Date
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Table A1 "A" Battery Duty Cycle.for Loss of all A.C.
Battery Train Designation A
Load number description inverter 1A miscellaneous turbine d.c.
lube oil pmp.
(running current) feedwater pmp.
d.c. l.o.
pump (running current)
MOV operation (3505A, Table A2) breaker tripping Amps 9
120UDC/105UDC 50/57 55/44 105/106 364/na 37/na 9/na 107/na 116/na duration 2 hr (4 hr)+
2 hr (4 hr)*
1 hr 12 min 3 min 1 min motor inrush (above NOUS (3505A) turbine l.o pump f.w. pmp. d.c. l.o d.g. field flash breaker closing running current) 41/na 261/na pmp.
37/na 339/na 17.2/15 52/52 "worst case" 1 min 1 min (end od 2hr period) 4 hr duration for compliance with Station Blackout commitment Design Analysis EMR 3341 Page 7
Revision Date
Table A2 D.C. Motor Loads on "A" Battery during Loss of All A.C.
motor running current (Amps) inrush current (Amps)
Turbine D.C. l.o.
pump Feedwater 1A d.c. l.o. pump MOVs(*)
3505A, Turbine driven aux.
feed pmp.
stm adm. vlv.
364 410 625 (measured) 74 (est) 50 (measured,)
749
- The D.C. motor operated valves are shown on RGRE drawing 10905-254.
Of these valves only 3505A,
- 3504A, and. 3996 will be required to operate on loss of all A.C. 3505A is powered from battery "A"', the other valves are powered, from battery "B".
The current data is based on MOVATS test records.
Design Analysis EWR 3341 Page 8
Revision Date
Table A3 D.C. "Special" Loads on "A" Battery During Loss of All A.C.
Amps Remarks Inverter lA (Hain DC Dist. Pnl.)
50 This is the measured load.
during normal full power operation.
All inverter loads remain after loss of A.C.
Field. flashing current for the diesel generator
- 17. 2 The field excitation circuit is shown on RG&E drawing 33013-1737 Sh.
2.
This is actually the drawing for the "B:
diesel but the excitation circuits are identical for both diesels.
Since the field flashing current must dxop to zero before diesel generator breaker closure can occur, only the "worst case" current for either field flashing or breaker closure is used for the final one minute of the duty cycle.
The "worst case" is the closing current for the DB 75 (Bus 14) and the DB 50 (Bus
- 18) which total 52 amp' Design Analysis ERR 3341 Page 9
Revision Date 3 Hf9~
Table A3 (Cont)
Amps Control Board
( Control Bd Panel 1A)
- 5. 0 Alarm System (Annunciators)
Remarks The annunciator panels can draw 20 amps if all windows in all panels are illuminated.
Normally only a few windows are energized, however on loss of all a.c.
it will be assumed that 1/4 of the windows are lit.
Diverse C.I. Rack (Control Bd. Panel lA) 4.0 It will be assumed that containment, isolation does not occur concurrent with loss of all A.C.
However the relays are normally energized so that the relay load will always be present.
Solenoid, Valves (Various Panels) 5.0 There are approximately 400 solenoid valves.
It is estimated that at any time 20 (5% of these are energized from "A" battery and each draw 0.25 amp.
This estimate is based on reconciling battery charger current with other known loads.
Design Analysis EWR 3341 Page 10
-Revision Date
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Table A4 Miscellaneous Loads on "A" Battery During Loss of All A.C.
-Hain Fuse Cabinet indicator lgts.
relays (amps)
(amps) brkr (trip/close) other (amps) 0 Main D.C. Distribution Panel 1A P.A. sys. inverter Battery Rm. vent 5.1 10 7.7 Control Board Panel 1A MQ-483 inverter Diverse C.I. rack Control Bd. Alm. Sys.
2.0 4 (See Special Loads)
(See Special Loads) 5.2 Aux. Bldg D.C.
Dist. Pnl.
1A 4.4 Bldg. D.C.
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1A1 1.2 Reactor trip switchgear Aux. Bldg D.C.
Dist. Pnl.
1A2 Diesel Gen lA Dist. Pnl.
1.25 Screenhouse D.C.
Dist. Pnl.
LA 1.8 Various Panels Solenoid Valves.
( See Special Loads )
Subtotal 20.7 27.9 Total 55 Design Analysis EWR 3341 Page 11 Revision Date E /~ /'ro
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Table Bl "B" Battery Duty, Cycle for Loss of all'.C.
Battery Train Designation B
Load number description Amps 9
12QVDC/1Q5VDC duration inverter lB miscellaneous air side seal oil back up pump turb. driven aux feed pmp. d.c. l.o.
pmp.
none feedwater pmp.
'd.c. l.o.
pump 50.0/57 64.8/56.7 73.0/63.9 23.0/20.1 210.8/197.7
- 37. 0/na 2 hr (4 hr)"
2 hr (4 hr) 2 hr (4 hr) 2 hr (4 hr) 1 hr.
12 min 136.9/na NOV operation (3504A, Table B2) breaker tripping 694/na 107.0/na na motor inrush (above running current)
MOVS (3504A, 3996) 71/na Air Side Seal Oil 73/na B.U.
Pump f.w. pump. d.c. l.o pmp.
37/na T.D. aux f.w. pmp. d.c 23/na l.o.
pmp.
circ.
pmp. disch. vlvs.
490/na 3 min 1 min d.g. field flash breaker closing 17.2/15 1 min 52/52 "worst (end of case" 2hr period,)
4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> duration for compliance with Station Blackout commitment.
Design Analysis ERR 3341 Page 15 Revision Date
Table B2 D.C. Motor K.oads on "B"-Battery during Z,oss of All A.C.
motor Air Side Seal Oil Back Up Pump running current (Amps) inrush current (Amps) 146 (est)
Feedwater 1A d.c. l.o.
pump 37 Turbine Driven Aux Feedwater 23 74 (est) 46 (est}
MOVs(*)
3504A, Turbine driven aux. feed pmp.
stm adm. vlv.
3996, Turbine driven aux.
feed pmp. disc. vlv
,3150, 3151, Circulating water pump disch. vlvs.
(See Special Z,oads) 7.9 120 270 50 (measured) 37.9 (measured) 610 (est)
Design Analysis EWR 3341 Page 16 Revision Date
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Table B3 D.C. "Special" Loads on "B" Battery During Los's of All A.C.
Inverter 1B (Main DC Dist. Pnl.)
Field flashing current for the diesel generator Amps Remarks 50 Same as in 1A 17.2 Same as in 1A Control Board Alarm System (annunciators)
(Control Bd Panel 1B)
Diverse C.I. Rack (Control Bd. Panel 1A)
Solenoid Valves (Various Panels) 5.0 4.0 5.0 Same as in 1A Same as in 1A Same as in A Circulating water pump disch.
vlv. motor operators 120.0 (running)
Both circulating water pump disch.
valve motor operators are supplied from this battery.
These are 6.6HP motors.
There is currently no data on inrush current.
It is therefore estimated as 5x running current.
Design Analysis ENR 3341 Page 17 Revision Date R I-'r f-i-
Table B4 D.C. Miscellaneous Loads on "B" Battery During Loss of All A.C.
indicator lgts.
(amps) relays (amps) brkr (trip/close) other (amps)
-Hain Fuse Cabinet, Main D.C. Distribution Panel 1B 0.8 Cont.
rm. emerg. lgts.
5.8 Control Board Panel lB 2.0 Steam dump vlvs/
TDAFWP gov. ind.
Vent sys.
rad.
mon.
Cont. bd. alarm sys.
Diverse C. Z. rack Cont.
bd annunciator (AVT, SAFW) 1.31 0.4 0.23 5.0 (See Special Loads)
(See Special Loads) 4.0 1.13
. Bldg D.C.
- t. Pnl.
1B 4.2 Aux. Bldg. Q.C.
Dist. Pnl.
1B1 1.2 Reactor trip switchgear (Trip) 2 Diesel Gen 1B Dist. Pnl.
- 1. 25 Screenhouse D AC.
Dist. Pnl.
1B 1.0 Turb. Bldg D.C Gist Pnl 3.5 Various Panels Solenoid Valves.
(See Special Loads)
Unknown miscellaneous loads 26.4 37.2 64 '
Total Battery charger load data from surveillance inspections indicated a total d.c.
load of 109 amp.
The unknown load added to the known loads (without d.c control room lignts).
~
Subtotal 21.6 4
2 Design Analysis EWR 3341 Page 18 Revision Date
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ee anal MKKi kfPHRERK.
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Appendix ROCHESTER GAS AND ELECTRIC CORPORATION INTEROFFICE CORRESPONDENCE December 1,
1989
SUBJECT:
Station Blackout DC Current Requirements, Breakers TQ:
George Daniels The maximum DC current requirements for breaker operation following a station blackout of Ginna Station's 4160 and 480 volt buses are as follows:
immediately Bus 11A 12A 13 14 18 A~ms 0
5 28 24 12 Bus 11B 12B 15 16 17 s
0 0
28 26 16 Total 69 70 after 15 seconds 11A 11B 37 These currents represent, the trip coil requirements and assumes all breakers existing on the buses are energized prior to the station blackout and no safety injection signal.
If safety injection is concurrent with the station blackout an additional 9.5 amps will be required for both 12A and 12B and an additional 2 amps for both 14 and 16.
Once the diesel generators are up to speed and voltage the DC requirement to load the lE buses onto the generators is 104
- amps, 52 for 14 18 and 52 for 16 6 17.
This represents the closing coil requirements of the diesel generator breakers.
Once the 1E buses are reenergized each additional breaker that is closed will require 20 amps DC.
//~ed< (X>@A Theodore H. ~tiller Electrical Engineer Attachment xc:
Elec.
Eng. File w/attach.
Ginna Station Station Blackout (loss of voltage)
Breaker Condition Bus 11A Load Sta.
Trans 13 Cond.
Booster Pmp 1C Circ. Water Pmp 1A Heater Drain Pmp 1A Cond.
Pmp 1C Cond.
Pmp 1A Feed Water Pmp lA Reactor Coolant Pmp 1A Aux Bldg. Exh.
Fan lA Aux. Trans 11 Bus 12A Feed Position 1
~2 3
5 6
7 8
9 10 11 Condition Traps after 15 seconds Not tripped No breaker Bus 11B Bus 12 B Feed Aux Trans 11 Aux. Bldg. Exh.
Fan lB Reactor Coolant Pmp 1B Feed Water Pmp 1B Cond.
Pmp 1B Heater Drain Pmp lB Circ Water Pmp 1B Cond.
Booster Pmp 1B Sta.
Trans l5 Bus 1'ie 11A 21 22 23 24 25 26 27 28 29 30 31 No breaker Not tripped Trips after 15 seconds Not tripped Bus 12A Bus Tie llA Bus Feed Sta.
Trans l8 Sta.
Trans 14 Cond.
Booster Pmp 1A Bus 12B 12 13 14 15 16 Vo trip No breaker No trip unless SI Trips Sta.
Trans 16 Sta.
Trans 17 Bus Feed Bus Tie 11B 17 18 19 20 No trip unless SI II No breaker No trip
Bus 13 Ltg Trans 1B5 Cont.
Rod Shroud 1A II Cont. Pnl.
MCC AVC-2 Pwr Dist. Pnl AVC-10 Spare Spare Aux. Pwr Sup.
1A Chiller Comp.
1A MCC 1A Aux. Bldg Sup Air Hdlg Ltg. Trans 1A Sta.
Serv. Air Comp Instr. Air Comp 1A Pwr Pnl SEP-2B Rod Drive MG 1A PTs Sta.
Trans 13 Bus Tie 14 Bus 15 PTs Sta Trans 15 Bus Tie 16 Rod Drive MG 1B Instr. Air Comp 1B MCC 1F Turb.
Rm. Crane Tech.
Support Ctr.
Ltg. 7rans 1B Chiller Comp lB Aux. P<<r.
Sup lA MCC 1B Instr. Air Comp.
1C Spare Pwr Pnl SEP 4G Future MCC 1K Cont.
Rod Shroud Fan 1B 6A.
6B 6C 6D 7A 7B 7C 7D 8A.
8B 8C 8D 9A, 9B 9C 9D 10A 10B 10C 1A 1B 1C 2A 2B 2C 2D 3A 3B 3C 3D 4A 4B 4C 4D 5A 5B 5C 5D Trips (DB 25) tl Vo trip (manual bkr)
Trips (DB 25)
Trips (DB 25)
No breaker Trips (DB 50)
No breaker No breaker Trips (DB 50)
No breaker Trips (DB 25)
Vo trip (manual bkr)
Bus 14 PTs Sta.
Trans 14 EDG 1A SIP 1C Bus Tie 14-13 Bus Tie 14-16 SIP 1A
,Containment Spray Pmp 1A Cont.
Fan 1D Aux. Bldg. Exh.
Fan 1G Spare AFWP 1A RHR 1A Heater S/G Control ilCC 1C Component Cooling Pmp lA Charging Pmp 1A Cont.
Fan 1A Spare SAFWP 1C Spare 18A 18B 18C 19A 19B 19C 20A 20B 20C 21A 21B 21C 22A 22B 22C 23A 23B 23C 24A 24B 24C No breaker Trips (DB 75)
No'trip Trips (DB'0)
II No trip (manual)
Trips (DB 50)
No trip Trips (DB 50)
No trip No trip unless SI Trips (DB 50)
Bus 16 PTs Sta Trans 16 EDG 1B SIP 1B Bus Tie 16-15 Bus Tie 14-16 SIP 1C Containment Spray Pmp 1B Cont.
Fan 1B Cont.
Fan 1C Spare AFWP 1B RHR 1B Charging Pmp 1B Charging Pmp 1C Heater S/G Backup Component Cooling Pmp 1B
."ICC 1D Spent Fuel Pit Pmp 2
Spare SAFW Pmp 1D 11A 11B 11C 12A 12B 12C 13A 13B 13C 14A 14B 14C 15A 15B 15C 16A 16B 16C 17A 17B 17C No breaker Trips (DB 75)
No trip (DB 75)
Trips (DB 50)
II Trips (DB 75)
Trips (DB 50)
Bus 14 preferred source No trip Trips (DB 50)
No trip unless SI No trip Trips (DB 50)
Trips (DB 50)
Bus 18 Intal e Heater 1A Intake Heater 1C SWP 1A SWP lc Spare Spare
'ACC 1G Spare PTs Sta Trans 18 EDG 1A 29A 29B 29C 29D 30A 30B 30C 30D 31A 31B 31C Trips (DB 25)
Trips (DB 25)
No breaker Trips (DB 50)
No trip (DB 50)
Bus 17 PTs Sta Trans 17 EDG 19 Spare Spare NCC 1G Fire Pmp Intake Heater 1B Intake Heater 1D SWP 1B SWP 1D Spare Bus.Tie 17-18 25A 25B 25C 26A 26B 26C 26D 27A 27B 27C 27D 28A 28B No breaker Trips (DB 50)
No trip (DB 50)
Trips (DB 25)
Bus 18 preferred source Trips (DB 25)
Current Requirements for breaker trips and closures are from Design Analysis g5, DC System Load Survey, ERR 3341, Rev 0, December 21,
- 1987, page one of Attachment I, attached.
DC LOAD DATA SHEET QEV~IC ',
MANUF.
JQTQTG SOURCE AMPS 125VDC 4
3000 DH MOTOR RELEASE COXL TRIP COIL X RELAY (SZ.OO)
Y RELAY (SZ F 00)
I 4KV 1200 BRKR D
CLOSING COIL TRXP COIL X RELAY (SZ.OO)
Y RELAY (SZ 00) 5A 27 ohms 27 ohms 18 watts 18 watts 32A 27 ohms 18 watts 18 watts Conserv-Est W Telecon, 9/17/87 W Telecon, 9/17/87 Cat Sec 8221 Cat.
Sec. 8221 Conserv.
Est.
W Telecon, 9/17/87 Cat. Sec. 8221 Cat.
Sec. 8221 5
4 ~ 63 4'3 0.144 0 '44 32 4 ~ 63 0 ~ 144 0 ~ 144 480V 75A BRKR DB CLOSE COXL TRZP COIL X RELAY (SZ.OO)
Y RELAY (SZ.OO) 32A 2A 18 watts 18 watts W AD 33-760 W AD 33-760 Cat.
Sec. 8221 Cat.
Sec. 8221 32 2
Oe 144 0 ~ 144 480V 50A
& 15 BRKR DB CLOSE COIL 20A TRXP COIL 2A X RELAY (SZ.OO) 18 watts Y RELAY (SZ.OO) 18 watts P AD 33-760 W AD 33-760 Cat.
0.144 0 ~ 144 480V 25 CLOSE COXL TRIP COIL X RELAY (SZ. 00)
Y RELAY (SZ.OO) 23A 2A 18 watts 18 watts W AD 33-760 W AD 33-760 Cat.
Sec. 8221 Cat.
Sec. 8221 23 2
0 ~ 144 0.144 MOTOR STARTERS SIZE 00-2 SIZE 3
SIZE 4
SIZE 5
18 watts 35 watts 35 watts 20 watts W Cat.
Sec. 8221 9.
30 3/17/80 It It
- 0. 144 0'8 0.28 0.16 MOTORS 7 '6A/HP HP x 746
.8(125U) 7.46A/HP
Appendix 2
Computer Software Documentation'he computer programs utilized in this analysis are classified as Type 4 in accordance with Appendix B of QN 330 (draft).
Type 4: Computer Software Package Documentation Summary 1.
Title of Report or Analysis Siskin of Vital Batteries 2.
Author
, G.N. Daniels 3.
Verification of Program (s)
(a)
(1)
Name of Program:
LEAST.PAS (2)
Description (include source code location):
The program performs a least squares fit of a sixth order polynomial to a data set.
Zn this case the data is the set of battery discharge currents to 1.75 VPC for the NAX 1200 cell.
The source code is available in the Turbo Pascal Numerical Methods Toolbox, from Borland Software.
The input and output of this program are attached to this appendix.
(3)
Algorithm Bases Found in text, page N/A Reference N/A (4)
Numerical Methods
- Used,
==
Description:==
Least Squares polynomial curve fit.
(ii)
(iii)
Reference Chene and Kincaid 1985 362-387 Other N/A (b)
( 1)
Name of Program:
BATDSCH:BAS (2)
Description (include source code location):
Appendix 2 (cont.)
Computer Software Documentation This is a short BASlC program which evaluated a
polynomial expression for battery discharge current and calculates the capacity for factor K.
The source code is attached to this appendix.
(3)
Algorithm Bases:
N/A (4)
Numerical Methods Used,:
None
- )1Q l.'
54r 0
~0 l QO a{'a f Q1l<ts I
0(.)0 0(.!0 (J(J(.)
0(l(l 000
(. 000{300 0000000 i:)(.)000(.<A OAQ(30(30 00{$00{.)0
(:!OAAOOO iynnmi al L-ash 3qua(-es i=it
- rue!'} W '
3< 'f Ql Qe(
~ <g(B }
< 'I.<re(
Gf}ts 1)<
1
<=<a<at.'nr.
( <en'
~.-: ant.
~ ~
-.'. ".1( nt t '1(:"nt.'
~
< ~
.-:aua)-e amp)" u::1rnat: ion:
~gQf 0
0 'A
",')".<~l! 4( i(3<i.<')~E~l
~ $
i"'3:7$.: 1'==- '
7 >.c'~41150'=E-'<~
'7851 -0456E-<<:
5~'P7<
.:.'P-'3a( }E- </
i yO
'/
0000 00{.)0 0(.)00
<r)0( )A
< l( l<'(
Least SQual 35 I
1 t 1. ~~00{gOAA(.){.)E+O.=.
l. 060(3{300(.)(3(.!.=+(3-;
)3 ~ D: i.l(.!(.)Q(.)Oi.<OE+C}
is ( )(.)0(p(3C)(.)(3(}(}E+(y.
0~os )000( }0{JOE~<".l'~
l F~ ( )( <()OF l( )OE~<}~B'l Chai Ga'"6'{5 1492E-.:}
- 1. 86264514(7'ZE- )(P 1
~ Gn
(=->~1 4'))>E -i )
- t.. 8('645 l4~RE-Oq
.'i:-'ILa'(:1 CL<;
< ~ <,<<"
~)-W<
~ <
~
$ i Q~~Q, P~ QQ
.0 PRINT "enter disch current time in minutes"
!0 INPUT T 30 I=1388.6879914¹ 29.291408406¹
~ T
~.61228778315¹
" T"2
.0089336411502¹ 7"3 -.000062985120456¹
~ T"4
.0000001569703949¹
'l T"5 35 KT = 1200/I
)0 PRINT "disch current=";I;"
INT "KT="'KT