ML18156A131
| ML18156A131 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/29/2018 |
| From: | Gerald Bichof Dominion Energy Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 18-197 | |
| Download: ML18156A131 (17) | |
Text
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Dominion Energy Nuclear Connecticut, .Inc.
~ Dominion Rt 156, Rope Ferry Road, Waterford, CT 06385 DominionEnergy.com pr Energy MAY 2 9 2018 U.S. Nuclear Regulatory Commission Serial No.18-197 Attention: Document Control De~k NRA/WDC RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 3 PROPOSED ALTERNATIVE REQUEST P-06 FOR 'C' CHARGING PUMP TEST FREQUENCY Pursuant to 10 CFR 50.55a(z)(2), Dominion Energy Nuclear Connecticut, Inc. (DENG) requests an alternative to the requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) 2012 Edition, ISTB-3400, "Frequency of lnservice Tests," for Millstone Power Station Unit 3 (MPS3) for the 'C' charging pump, 3CHS*P3C.
In accordance with OM Code Table ISTB-3400-1, Group A pumps, which include the charging pumps, are required to be tested on a quarterly frequency. Due to the electrical configuration of 3CHS*P3C, performing the quarterly inservice test on this pump results in unavailability for the high pressure safety injection system each quarter.
DENG concludes that the requirement of ISTB-3400 and Table ISTB-3400-1 to perform a quarterly test on charging pump 3CHS*P3C presents a hardship without a compensating increase in the level of quality and safety. DENG proposes to perform quarterly testing of 3CHS*P3C during the time periods when the pump is required to be OPERABLE. DENG will continue to comply with all other aspects of the OM Code.
The justification for the proposed alternative and the supporting information is provided in Attachment 1. The 3CHS*P3C Preventative Maintenance Strategy is provided in . The mark up of changes to the Final Safety Analysis Report is provided in Attachment 3 for information only.
DENG requests expedited review of this proposed alternative request. Realignment of the charging pumps to support required quarterly testing results in pressure, temperature and flow transients on the reactor coolant pump (RCP) seals, which have been identified as contributors to RCP seal degradation. DENG recently identified a shift in the RCP seal differential temperature trend, which is a precursor to seal degradation. The RCP seals remain capable of performing their safety function. RCP seal replacement is planned at the next refueling outage. However, to minimize challenges to the RGP seals and to support continued plant operation, DENG requests expedited review of this proposed alternative by October 18, 2018. Quarterly tests for the. 'C' charging pump are scheduled for July 17, 2018 and October 19, 2018. ;4 D11
¢ ~~
, 'I Serial No.18-197 Docket No. 50-423 Page 2 of 2 The duration of this proposed alternative is for the remainder of the third 10-year inservice test interval and for the fourth 10-year inservice test interval that is scheduled to begin on December 2, 2018 and end on December 1, 2028.
This alternative request has been approved by the Facility Safety Review Committee.
If you have any questions regarding this submittal, please contact Wanda Craft at (804) 273-4687.
Sincerely,
/HJ7µ-.
Gerald T. Bischof~ U Senior Vice President - Nuclear Operations& Fleet Performance Attachments:
- 1. Proposed Alternative Request P-06 for 'C' Charging Pump Test Frequency.
- 2. 3CHS*P3C Preventative Maintenance Strategy
- 3. FSAR Changes (For Information Only)
Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd Suite 100 King of Prussia, PA 19406-2713 Richard V. Guzman Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C 2 11555 Rockville Pike Rockville, MD 20852-2738 NRG Senior Resident Inspector Millstone Power Station
Serial No.18-197 Docket No. 50-423 ATTACHMENT 1 PROPOSED ALTERNATIVE REQUEST P-06 FOR 'C' CHARGING PUMP TEST FREQUENCY MILLSTONE POWER STATION UNIT 3 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.
Serial No.18-197 Docket No. 50-423 Attachment 1, Page 1 of 4 Pump Alternative Request Number P-06 Millstone Power Station Unit 3
'C' Charging System Pump Test Frequency Proposed Alternative Request In accordance with 10 CFR 50.55a(z)(2)
Hardship or Unusual Difficulty without a Compensating Increase in Quality or Safety
- 1) ASME Code Component(s} Affected Pump: 3CHS*P3C System: Chemical Volume Control Charging Group: A Class: 2
ASME OM Code 2012 Edition (Fourth Interval)
- 3) Applicable Code Requirement(s}
ISTB-3400, "Frequency of lnservice Tests," requires that a Group A test be performed quarterly for 3CHS*P3C per Table ISTB-3400-1.
- 4) Reason for Request The Millstone Power Station Unit 3 (MPS3) charging pumps (3CHS*P3A/B/C) are classified as Group A pumps per ASME OM 2012 (the Code), Subsection ISTB paragraph 2000, Supplemental Definitions. Subsection ISTB, paragraph 3400, "Frequency of lnservice Tests" requires that a Group A test be performed quarterly for these pumps per Table ISTB-3400-1. Charging pump 3CHS*P3C serves as an installed spare pump that is not normally connected to any power source. Quarterly testing of 3CHS*P3C requires that one train of High Pressure Safety Injection (HPSI) be disabled to support electrically connecting 3CHS*P3C to a safety-related electrical bus for testing purposes. Unavailability is accrued for the HPSI safety function for the time the emergency core cooling system (ECCS) train is disabled. Approximately 20% of total HPSI unavailability is due to quarterly testing of 3CHS*P3C. Additionally, aligning 3CHS*P3C for testing is a complex evolution that involves entry into a 72-hour shutdown Technical Specifications (TS) action statement and close coordination between the control
Serial No.18-197 Docket No. 50-423 Attachment 1, Page 2 of 4 room and field personnel to execute the required breaker manipulations and realignment of cooling water to the charging pump oil cooler.
Pursuant to 10CFR50.55a(z)(2), Dominion Energy Nuclear Connecticut (DENG) is requesting NRG approval of a proposed alternative to the quarterly testing requirement of Table ISTB-3400-1 on the basis that the requirement to perform quarterly testing of 3CHS*P3C represents a hardship without a compensating increase in quality or safety.
- 5) Proposed Alternative and Basis for Use Proposed Alternative DENG proposes to perform the quarterly Group A test on 3CHS*P3C for the time periods when the pump is required to be OPERABLE to support continued plant operation. If it becomes necessary to use 3CHS*P3C, a quarterly Group A test will be performed prior to declaring the pump OPERABLE. Testing on a quarterly frequency would be performed until 3CHS*P3C is returned to its normal (spare) alignment. A pump comprehensive test will continue to be performed on a refueling outage frequency. Charging pump 3CHS*P3C is considered available provided a current satisfactory comprehensive test is documented. Existing preventive maintenance activities are shown in Attachment 2.
Basis for Use The MPS3 charging system design includes three hydraulically similar pumps.
MPS3 TS require two independent emergency core cooling system (EGGS) trains. Charging pumps 3CHS*P3A and 3CHS*P3B are normally aligned and credited for maintaining the two independent trains. Pumps 3CHS*P3A and 3CHS*P3B are each electrically connected to an independent safety-related electrical bus backed by an emergency power source. Charging pump 3CHS*P3C serves as an installed spare pump that is not normally connected to any power source. There is a dedicated breaker cubicle on each of the safety-related electrical buses that can be used to connect 3CHS*P3C to the associated bus.* To connect 3CHS*P3C, either 3CHS*P3A or 3CHS*P3B must be electrically disconnected by racking out the appropriate breaker and physically removing, relocating and reinstalling the affected breaker in the 3CHS*P3C pump breaker cubicle. Kirk key interlocks are provided to prevent having two charging pumps capable of starting on the same electrical bus. Additionally, cooling water must be aligned to the 'C' charging pump oil cooler to support pump operation.
The process is then reversed to restore the system to its normal operational alignment. The time required to complete this evolution is approximately 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
Aligning 3CHS*P3C for operation is not credited as the primary' mitigation strategy for any Final Safety Analysis Report (FSAR) Chapter 15 accident analysis as the time required to place 3CHS*P3C in service exceeds the
Serial No.18-197 Docket No. 50-423 Attachment 1, Page 3 of 4 response time assumptions for functions credited for Chapter 15 accident mitigation. In its normal (spare) alignment, 3CHS*P3C is considered available for use but does not meet MPS3 TS requirements to be considered OPERABLE.
Should 3CHS*P3C be placed into service during normal plant operations, (3CHS*P3A or B inoperable) it would become the credited component for FSAR Chapter 15 event mitigation and would be subject to all performance testing requirements specified in the MPS3 TS.
Alignment of 3CHS*P3C is listed as a contingency action in station Abnormal and Emergency Operating Procedures. A decision to use 3CHS*P3C while operating within the Abnormal and Emergency Operating Procedure network would be based on specific plant conditions and circumstances that exist at the time.
Should plant operators elect to align .3CHS*P3C during an abnormal or emergency event, performance of a quarterly test may be deferred until after plant conditions are stabilized.
Additionally, MPS3 TS Bases for entry into the 14-day allowed outage time (TS 3.8.1.1.b ACTION) for an emergency power source out of service require 3CHS*P3C be available to replace an inservice charging pump, if necessary.
The proposed alternate testing plan does not affect the availability of the spare pump to fulfill these functions. Charging pump 3CHS*P3C would be considered available provided a current satisfactory comprehensive test is documented.
Extending the interval between tests will not degrade the performance of 3CHS*P3C. The charging pumps (3CHS*P3A/B/C) are located in the controlled environment of the MPS3 auxiliary building. The charging pumps are constructed of materials specifically selected to be compatible with the chemistry of the pumped fluid (borated water). The charging system fluid chemistry is monitored and maintained to meet reactor coolant system water quality requirements and therefore is not expected to cause any degradation of the pump internals over time. When idle, the pump bearings will not be subjected to wear and therefore would not be expected to degrade. As shown in Attachment 2, preventative maintenance tasks have been established to monitor for degradation of the lubricating oil through routine sampling and analysis for indicators of breakdown of the lubricant properties as well as the presence of wear products. Pump vibration data is also collected and analyzed for indications of bearing wear or pump alignment problems whenever a pump is put in service and periodically while it remains in service.
In 2016, Dominion submitted a formal Code Inquiry to ASME to clarify the intent of the 2001 Edition through 2003 Addenda of the OM Code in regards to testing of 3CHS*P3C. The response to the Code Inquiry was issued on March 26, 2017 as OM Code Interpretation Number OM-17-01. While this relief request references the 2012 Edition of the OM Code, the relevant Code requirements have not changed. Review by the Code Committee determined that it was not
Serial No.18-197 Docket No. 50-423 Attachment 1, Page 4 of 4 the intent of the Code to require testing of components, 1) not connected to an emergency power source, and 2) not required to be OPERABLE.
DENG concludes that the requirement of ISTB-3400 and Table ISTB-3400-1 to perform a quarterly test on charging pump 3CHS*P3C, which results in increased unavailability of the HPSI system, presents a hardship without a compensating increase in the level of quality and safety. DENG will continue to comply with all other aspects of the OM Code, such as comprehensive pump tests and post maintenance tests. The proposed alternative to perform the quarterly test prior to placing charging pump 3CHS*P3C into normal service with the existing preventive maintenance activities shown in Attachment 2 provide continued assurance of pump performance and an acceptable level of quality and safety without increased HPSI system unavailability.
- 6) Duration of Proposed Alternative This proposed alternative is requested for the remainder of the third 10-yar inservice test interval and for the MPS3 fourth 10-year 1ST interval that is scheduled to begin on December 2, 2018 and end on December 1, 2028.
Serial No.18-197 Docket No. 50-423 ATTACHMENT 2 3CHS*P3C PREVENTATIVE MAINTENANCE STRATEGY MILLSTONE POWER STATION UNIT 3 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.
Serial No.18-197 Docket No. 50-423 Attachment 2, Page 1 of 1 3CHS*P3C PREVENTATIVE MAINTENANCE STRATEGY PM Description Location Cycle Status RE94626 EEQ, 60A Pump Motor And Motor Main Lead Replacement M33CHS*P3C ACTIVE RE618954 PM, lR - POMA (energized), health and condition monitoring M33CHS*P3C 3R20 ACTIVE of motor RE618902 PM, 2R - POMA (de-energized), health and condition M33CHS*P3C 3R22 ACTIVE monitoring of motor RE618669 PM, 8R - Charging Pump Motor Overhaul M33CHS*P3C 3R29 ACTIVE RE614565 I
EEQ, 39A(J) - SKV PWR Cable & Raychem Kit Replacement M33CHS*P3C ACTIVE RE613970 PM, 4R - Grease & Inspect Couplings - (Gear/ Pump & Motor M33CHS*P3C 3R24 ACTIVE
/ Gear)
RE610041 SI, 2R -- 3CHS*P3C (VT-2) Exam, VT-2 Exam of 3CHS*P3C & M33CHS*P3C 3R20 ACTIVE associated components.
RE609575 PM, lSR - Replace 0-Rings on Gear/ Pmp Coupling, - Inspect M33CHS*P3C 3R36 ACTIVE 0-Rings on Motor/ Gear Coupling RE609004 PM, lR - Motor Oil Change M33CHS*P3C 3R20 ACTIVE RE608085 RT, 6 Month - Seal Reservoir/Drain Line Cleaning M33CHS*P3C ACTIVE RE607891 PM, lR - Gear Box & Reservoir Oil Sample M33CHS*P3C 3R19 ACTIVE RE607058 PM, 4.SA - 3CHS*P3C {34C22) Relay & Meter Calibrations M33CHS*P3C ACTIVE
Serial No.18-197 Docket No. 50-423 ATTACHMENT 3 FSAR CHANGES (FOR INFORMATION ONLY)
MILLSTONE POWER STATION UNIT 3 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.
Serial No.18-197 Docket No. 50-423 Attachment 3, Page 1 of 7 MPS3FSAR TABLE 1.7-1 ELEMENTARY DIAGRAMS (CONTINUED)
(Refer to Plant Document Control for latest Document Rev. and Date)
NUSCO SWEC Drawing Drawing Number Number 25212-32001 12179-ESK- Diagram Title Sh. 5BY SBY US Fdr Bkr [3ENS* ACE-BC], 34D4-2 Sh.5CJ SCI Service Wtr Pump [3SWP*P1A]
Sh. 5CK 5CK Service Wtr Pump [3SWP*P1B]
Sh. 5CL 5CL Service Wtr Pump [3SWP*P1C]
Sh. 5CM 5CM Service Wtr Pump Sh. 5CN 5CN Cntmt Recirc Pump [3RSS*P lA]
Sh.SCP SCP Cntmt Recirc Pump [3RSS*P1B]
Sh. 5CQ 5CQ Cntmt Recirc Pump [3RSS*P1C]
Sh. 5CR 5CR Cntmt Recirc Pump [3RSS*P1D]
Sh. 5CS 5CS Charging Pump P3A [3CHS*P3A]
Sh. 5CT 5CT Sh. 5CU 5CU Sh. 5CV 5CV Sh. 5DA 5DA Reactor Plant Comp Cooling Wtr Pp [3CCP*P1A]
Sh. 5DB 5DB Reactor Plant Comp Cooling Wti Pp [3CCP*P1B]
Sh. 5DC 5DC Reactor Plant Comp Cooling Wtr Swing Pp [3CCP*P1C]
Sh. 5DD 5DD Reactor Plant Comp Cooling Wtr Swing Pp [3CCP*P1C]
Sh. 5DE 5DE Residual Heat Removal Pump PlA [3RHS*P1A]
Sh. 5DF 5DF Residual Heat Removal Pump PlB [3RHS*P1B]
Sh. 5DG 5DG Quench Spray Pump P3A (3QSS*P3A)
Sh. 5DH 5DH Quench Spray Pump P3B (3QSS*P3B)
Sh.SDI SDI Safety Injection Pump PlA [3SIH*P1A]
Sh. 5DK 5DK Safety Injection Pump PlB [3SIH*P1B]
Sh. 5DR 5DR EmerDiesel GenBkr [3ENS*ACB-G-A] 15G-14U-2 Sh. 5DS 5DS EmerDiesel GenBkr [3ENS*ACB-G-B] 15G-15U-2 Sh. 5DX 5DX Stm Gen Aux Fdwtr Pp Mot Driven PIA [3FWA*PIA]
03/29/18 1.7-35 Rev. 30.3
Serial No.18-197 Docket No. 50-423 Attachment 3, Page 2 of 7 MPS3FSAR Uncertainties such as NPSH variation between similar pumps and test inaccuracies were considered but not included in the calculation due to the adequate margin between available and required NPSH and the conservatism in calculated pipe loss.
Potential pumps runout due to suction pressure boost during recirculation mode is precluded by the throttling of the ECCS branch line throttling valves.
Residual Heat Removal Pumps Tue (RHS) pumps are started automatically on receipt of an SIS signal. Tue pumps deliver water to the RCS from the RWST during the injection phase. Each pump is a single stage vertical position centrifugal pump.
A minimum flow bypass line is provided down stream of the RHS heat exchangers for the pumps to recirculate and return the pump discharge fluid to the pump suction should these pumps be started with their normal flow paths blocked. Once flow greater than approximately 1,542 gpm is established to the RCS, the bypass line is automatically closed. This line prevents dead heading of the pumps and permits pump testing during normal operation.
Tue RHS pumps are discussed further in Section 5.4.7. A pump performance curve is given on Figure 6.3-3. This pump performance curve is the one used in the Safety Analysis, therefore, the pump heads analyzed will differ from the actual design values given in Table S.4-8.
Tue pumps have a self-contained mechanical seal which is normally cooled by the component cooling water system. However, after a LOCA, cooling water is not supplied or required, because the pumps are pumping water having a maximum temperature of 75°F. Tue RHS pumps are not utilized in the recirculation phase.
Centrifugal Charging Pumps ~
I?~
In the event of an accident, tfie charging pumps are started automatically on receipt of an SIS and are automatically aligned to take suction from the RWST during injection. However, the charging pumps will not automatically inject into the reactor coolant cold legs unless there is also a c9ld leg injection permissive [(P-19) - pressurizer pressure low] signal present to open the charging pumps to RCS cold leg injection headers parallel isolation valves. During recirculation, suction is provided from the containment recirculation pump discharge.
Tue charging pumps deliver flow to the RCS at the prevailing RCS pressure. Each centrifugal charging pump is a multistage centrifugal diffuser design (barrel type casing) with vertical suction and discharge nozzles. The pumps lubricating oil coolers are cooled by the charging pumps seal cooling subsystem (Section 2.2.4).
A minimum flow bypass line is provided on each pump discharge to recirculate flow to the pump suction after cooling via the seal water heat exchanger during normal plant operation. Tue minimum flow bypass line contains two valves in series which close on receipt of the SIS. Two alternate miniflow paths are provided for the two operable charging pumps when the normal 03/29/18 6.3-7 Rev. 30.3
Serial No.18-197 Docket No. 50-423 Attachment 3, Page 3 of 7 MPS3FSAR TABLE 6.3-10 FAILURE MODE AND EFFECTS ANALYSIS - EMERGENCY CORE COOLING SYSTEM -ACTIVE COMPONENTS ECCS FAILURE OPERATION EFFECT ON SYSTEM FAILURE DETECTION COMPONENT MODE PHASE OPERATION* METI!OD REMARKS
- 1. Motor operated gate Fails to close on Injection-cold legs of Failure reduces redwidancy of Valve position indication (open to Valve is electrically interlocked wilh valve LCV-112B demand RC loops prmdding VCT discharge isolatiqn closed position change) at CB. Valve isolation valve LCV-112D. Valve (LCV-l 12C analogous) No effect on safety for system close JX)sition monitor light and alann closes on actuation by a SIS signal operation~ isolation valve for group monitoring of components provided isolation valve LCV-l l 2D (LCV-112C) and check valve 8440 at CB. is at a full open positioIL provides backup tank discharge (Analogous train LCV-112C is isolation electrically interlocked with LCV-ll 2E.)
- 2. Motor operated gate Fails to open on Injection-cold legs of Failure reduces redtmdancy of Valve position indication (closed to Valve is electrically interlocked wi1h valve LCV-112D demand RC loops providing fluid flow from RWSf to open position change) at CB. Valve the instrumentation that monitors (LCV-112E analogous) suction ofHHSJ/CH pumps. No open position monitor light and alann fluid level of the VCT. Valve opens safety effect on system operation. for group monitoring of components upon actuation by a SIS signal or Alternate isolation valve at CB. upon actuation by a "Low-Low-(LCV- l l 2E) opens to provide Level" VCT signal.
back'llp flow path to suction of HHSJ/
CH pumps.
Fails to deliver Injection and Failure reduces redundancy of HHSJ/CH pmnp discharge header One HHSJ/CH pmnp is used for working fluid recirculation cold providing emergency coolant to the flow (Fl-911) at CB. Openpmnp normal charging of RCS during legs of RC loops RCS at prevailing incident RCS switchgear circuit breaker close plant operation. Pump circuit pressure. Fluid flow from HHSJ/CH position monitor light for group breaker aligned to close on actuation Pump !'3ft-will be lost Minimmn monitoring of components at CB. by SIS signal.
Two charging pumps are required to automatically flow requirements at prevailing high Conunon breaker trip alann at CB.
start. 3CHS~P3A and 3CHs*p3a are normally RCS pressures will be met by SJ/
aligned electrically. 3CHS"P3C, considered an CH Pump !'31l-ff-Pt,-~,'\' ~ - - ~
installed spare, is not normally electrically connected. the redundant delivery.
- 4. Motor operated globe Fails to close on Injection-cold legs of Failure reduces redt.mdancyof Same method of detection as that Valves are normally open and closed valve8110(8111A,B,C demand RC loops providing isolation of HHSJ/CH stated for Item 2. upon actuation by a SIS.
analogous) pump mini.flow line. No effect on safety for system operatioIL Alternate isolation valve (8111 A,B&C) in miniflow line provides backup isolation 03/29/18 6.3-45 Rev. 30.3
Serial No.18-197 Docket No. 50-423 Attachment 3, Page 4 of 7 MPS3FSAR
- d. IEEE Standard 279-1971, Paragraph 4.17:
The safety injection pumps have manual controls on the main control board and at the switchgear. A REMOTE/LOCAL control transfer switch at the switchgear is alarmed in the control room when LOCAL is selected.
- e. IEEE Standard 279-1971, Paragraphs 4.9 and 4.10:
One train at a time is taken out of service and periodically tested in accordance with the Technical Specifications.
This testing will consist of manually starting the pump during normal surveillance of the system or the breaker for the pump will be in the test position. Once the pump is running or the breaker is in the test position, the AUTO start and tripping is verified using the emergency generator load sequencer with safety signals generated internally or externally to the sequencer.
- 3. Charging Pumps an installed spare Normally, one ch rging pump is running. During a loss-of-coolant accident (LOCA), two c ging pumps operate as part of the safety injection system. The third pump is ~pump with a breaker cubicle on each emergency bus that is normally empty. The ~pump uses the breaker of the pump which is not in service. Mechanical an eylock switches prevent the pump from being placed on Train A and Train B em gene buses at the same time.
installed spare On a loss-of-power (LOP) signal the charging pump that is running is not stripped from the emergency bus; therefore, the pump starts immediately when power is restored. The pumps are started automatically on receipt of a sequenced safeguard signal.
Manual controls are provided on the main control board and at the switchgear for the charging pumps. An annunciator is alarmed on the main control board when local control is selected. ESF status lights indicate when a charging pump is running.
Ammeter and indicator lights are located at the switchgear and on the main control board.
Bypass and inoperable alarms are provided in accordance with Regulatory Guide 1.47.
Each charging pump has an auxiliary lube oil pump with a local STOP-AUTO control switch. The auxiliary lube oil pumps start automatically when AUTO is selected on low lube oil pressure, or when the associated charging pump is stopped. The auxiliary lube-oil pump stops automatically whert AUTO is selected 03/29/18 7.3-10 Rev. 30.3
Serial No.18-197 Docket No. 50-423 Attachment 3, Page 5 of 7 MPS3FSAR and lube oil pressure is above a predetennined pressure and the associated charging pump is started.
Analysis
- a. IEEE Standard 279-1971, Paragraph 4.2: an installed spare There are three charging pumps, 3CHS*P3A, B, and C. The C pump is -a-
,s.wi,a.g.pump. Normally, two charging pumps (3CHS*P3A and B) have their breakers racked in and one of the two is running. In the event that the A or B pump fails, its breaker is racked out and racked into the C pump cubicle (Tr!lin A or B). Mechanical and electrical interlocks prevent the C pump from being connected to two buses at the same time.
Power is supplied to the charging pumps from two separate emergency buses. No single failure at the system level will prevent charging pump safety injection.
- b. IEEE Standard 279-1971, Paragraph 4.4:
Equipment qualifications are discussed in Sections 3.10 and 3.11.
- c. IEEE Standard 279-1971, Paragraph 4.13:
A bypass and inoperable annunciator in the control room is alarmed when any of the following conditions exists for Train A or B:
Charging pump A, B, or C control switch in pull to lock or loss of control power or breaker racked out.
Charging pump cubicle ventilation system bypassed.
(Auxiliary circuits associated with the inlet and outlet ventilation dampers for the charging pump cubicles do not provide input to bypass annunciator.)
Bypass push button depressed for charging pumps safety injection.
Charging pump header isolation valve not full open.
RWST to charging pump valve circuit breaker open.
VCT to charging pump valve circuit breaker open.
Charging pumps to reactor cold legs isolation valve circuit breaker open.
03/29/18 7.3-11 Rev. 30.3
Serial No.18-197 Docket No. 50-423 Attachment 3, Page 6 of 7 MPS3FSAR TABLE 7.4-1 INSTRUMENTS AND CONTROLS OUTSIDE CONTROL ROOM FOR COLD SHUTDOWN (CONTINUED)
Description Mark No.
Main Strn Pressure Relieving Valve 3MSS*PV20D Miscellaneous Controls ASP Section 2/Non-Train White Indicator Light (Steam Line Safety Injection Blocked, Trairt A)
White Indicator Light (Steam Line Safety Injection Blocked, Train B)
White Indicator Light (Pressurizer Safety Injection Blocked, Train A)
White Indicator Light (Pressurizer Safety Injection Blocked, Train B)
Safety-Related Controls on 4160V Emergency Switchgear Motor-Driven Aux 3FWA*P1A, Train A FdwtrPumps 3FWA*PlB, Train B Charging Pumps 3CHS*P3A, Train A 3CHS*P3B, Train~~ ~
3CHS*P3C, ~-Pump Service Water Pumps 3SWP*P1A, Train A 3SWP*P1C, Train A 3SWP*P1B, Train B 3SWP*P1D, Train B Reactor Plant Component Cooling Pumps 3CCP*P1A, Train A 3CCP*P lB, Train B 3CCP*P1C, Swing Pump Control Building Chilled Water Pumps 3HVK*P1A, Train A 3HVK*P1B, Train B RHRPumps 3RHS*P1A, Train A 3RHS*P1B, Train B LocaL Manual Valve Control Adjustable travel limiters 3RHS*FCV618, Train A (to be used during safety grade cold shutdown with single failure loss of one train of RHS and 3RHS*FCV619, Train B loss of all instrument air.)
03/29/18 7.4-17 Rev. 30.3
Serial No.18-197 Docket No. 50-423 Attachment 3, Page 7 of 7 MPS3FSAR Each emergency generator is capable of being manually paralleled with the unJt station service system under nonaccident conditions. The emergency generators are capable of being manually paralleled with the off site AC power source under post-accident conditions. Provisions are made in the emergency AC power system design to prevent the inadverte.nt electrical interconnection of the emergency generators by providing key interlocks for breakers for t h e ~ charging
- and ~
Reactor Plant Component Cooling pumps and the SBO Diesel Generator.
spare swing Each emergency generator diesel engine is provided with cooling by means of a shell and tube heat exchanger cooled by water from the service water system. TI1e emergency generators are self-cooled, forced air ventilated. A complete description of the cooling water system is given in Section 9.5.5.
Each diesel engine is provided with a dedicated air starting system consisting of two separate air starting subsystems. Engine cranking is accomplished by two stored air supplies with sufficient capacity to start the engine without using an air compressor. Fast starting and load pickup are facilitated by electric heaters which keep the engines warm when they are not running. A complete description of the air starting system is given in Section 9.5.6.
The fuel oil system for the emergency generators' diesel engines have a storage capacity suitable for operating one emergency generator at post-accident load for approximately six days. Two fuel oil storage tanks, which contain fuel for the emergency generators, are buried underground. Each diesel engine is equipped with an independent fuel day tank with a capacity of approximately 493 gallons at the shutoff level for the two fuel oil transfer pumps. This corresponds to approximately 60 minutes of engine operation at the 2,000 hr. rating of 5335 kW. At the lowest level with auto makeup capability, there is approximately 278 gallons of fuel in the tank which is sufficient for 27 minutes of engine operation at the 2,000 hr. rating. In the standby condition, a minimum of 493 gallons of fuel is maintained. This independent fuel day tank is filled by transferring fuel from a fuel oil storage tank. Two motor-driven fuel oil transfer pumps powered from their associated emergency generator, ensures that an operating emergency generator has a continuous supply of fuel. These two full capacity transfer pumps are operated automatically at preset level points in the corresponding day tank.
Complete information on the fuel oil system is given in Section 9.5.4.
The emergency generators are located in separate rooms in the emergency generator enclosure (Figure 8.3-1). Within these rooms, the emergency generators, including associated starting equipment and .other auxiliaries, are completely isolated from one another by means of a 2-foot concrete wall designed to prevent any event occurring at one emergency generator from affecting the other. There are no openings or common passageways between the rooms.
The emergency generator enclosure is a Seismic Category I structure and is capable of withstanding tornado generated missiles. Additional details on the building structure are given in Section 3.8.
Each of the rooms has a separate drainage system to prevent liquids from flowing from one room to the other. The separate drainage system for each diesel is sized to accommodate any release of 03/29/18 8.3-12 Rev. 30.3