ML20116K182
| ML20116K182 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 04/29/1985 |
| From: | Edelman M CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8505030203 | |
| Download: ML20116K182 (51) | |
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P.o. Box 5000 - CLEVELAND. OHlo 44101 - TELEPHONE (216) 622-9800 - ILLUMINATING BLOG. - 55 PUBLICSoVARE Semog The Best Location in the Nation MURRAY R. EDELMAN VICE PRESIDENT NUCMAR April 29, 1985 PY-CEI/NRR-0207L Mr. B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Response to Additional Staf f Questions Pertaining to the PNPP Initial Test Program
Dear Mr. Youngblood:
This letter and its attachments are provided in response to your staf f's questions (dated February 21, 1985) pertaining to the Initial Test Program for the Perry Nuclear Power Plant.
The information provided in the attachments will be incorporated into a future amendment to the FSAR. Also attached is a list of references for the Preoperational Test Program. If you have any questions, please feel free to call.
Very truly yours, Murray R. Edelman Vice President Nuclear Group MRE:njc Attachments cc: Jay Stiberg, Esq.
John Stefano (2)
J. Grobe S. Brown 8505030203 850429 MV PDR ADOCK 05000440 1 A PDR
y 640.57 Modify the Test Program schedule (FSAR Section 14.2.11) to re-(640.4) instate that preoperational and acceptance test results should (14.2.11) be reviewed and approved prior to fuel load, and that if any tests should be deferred until after fuel load, the following infor-mation and justification will be provided to the NRC: (1) a list of tests involved, (2) technical justification for these portions, and (3) anticipated completion date for each test.
Response
Section 14.2.11 (attached) has been revised to reflect these requirements.
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q The general seqcence shming major Testing Milestones is given in Figure 14.2-5. A Test Sequence Decument showing detailed testing activity interface has been prepared and distributed a: the Perry site. This d:cument is available for review at the Pe::y site.
Freeperati:nal and acceptance testing is scheduled to be complete pric: to l
fuel lead. Freeperational and ac:ep:ance esting shall be completed and the results reviewed, evaluated and a: proved prio: to the time that a sys on, subsyste= or component will be relied en to maintain the plan: in a safe l
cenditica, and pric: to entering an operating condi ica for which a system, subsystem or comp:nen is required :: be operable. If any tests shculd be I deferred until af ter fuel load, the follewing informatica and justifica:icn will be provided to the NRC: (1) a list of all tests or pc::icns of tests involved, (2) technical justification for these porticas and (3) a schedule for ce=pletion of each est. .
l Preoperatienal and acceptance tests that are ccepleted or partially cc=pleted after fuel load shall be subject to the star:up test ad inis::ativ'e con:rcis except that the procedure need not be revised to accoccodate any format require =ents.
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640.58 The Standby Diesel Generator Preoperational Test (FSAR Subsection (640.6) 14.2.12.1.31), or other test abstracts as appropriate, should be (1.8) modified to reflect the following positions stated in Regulatory (14.2.12) Guide 1.108, or FSAR Table 1.8-1 should be modified to provide expanded technical justification for any exception to this guide.
(1) Expand testing to explicitly cover testing of HPCS diesel (C.2.a).
(2) Correct FSAR Table 1.8-1 to delete the exception to performing the full-load-carrying capability test for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at the 2-hour load rating. Note that the Standby Diesel Generator Test properly incorporates testing at the 2-hour load rating (C.2.a.3).
Response
(1) HPCS Diesel Generator testing has been added to Section 14.2.12.1.15.
(2) Amendment 17 to PNPP's FSAR deleted the two hour 110 percent of continuous rated load test from the Division 1 and 2 diesel generator testing. Table 1.8-1 has been modified to provide expanded technical justification.
14.2.12.1.1; High Pressure Core Spray System (HPCS) Preoperational Test
- a. Test 07jectives
- 1. High Pressure Core Spray Sys:cm (excluding HPCS diesel genera:cr) a) To verify the ability of the High Pressure Core Spray Syste= to perform within design specifications in all modes.
b) To verify the proper operation of all controls, interlocks, alarms, and logic (including automatic initiation).
- 2. High Pressure Core Spray Diesel Generator a) To demonstrate tha: the HPCS diesel generator is capable of providing reliable electrical power during normal and simulated accident conditions.
b) To demonstrate the operability of the HPCS diesel generator auxiliary systems (e.g. , starting air, fuel oil, jacket water, lube oil, intake air supply, and exhaust system),
- b. Prerequisites
- 1. High Pressure Cere Spray System (excluding HPCS diesel generator) a) Individual ccmponent tests are complete, b) Instrument calibration has been completed.
c) Electrical power is available, d) The suppression pool and condensate storage tank are filled above the low water level to provide suction to the pu=p.
- 2. High Pressure Core Spray Diesel Generator a) Individual component tests are complete and have been approved.
b) Instrumentation is available, calibrated and operable.
c) Sufficient diesel fuel is available.
d) Engine liquid levels are sufficient to allow operation, e.g.,
lubrication oil and jacke: water, e) The following systems and/or components are available:
- 1) Pneumatic sources.
- 2) Emergency service water.
- 3) Electrical power.
- 4) EPOS diesel. generator rec = fire p ctection.
S) EPOS diesel generator :::m ventilatien.
- 6) E?CS diesel genera::: auxiliary systems are available.
- c. Tes: ?: cedure
- 1. Eigh Pressure Core S.::ay System (excluding EPOS diesel genera:::)
a) Cent:cis, alar:s and interlocks are functionally tested.
b) System operation will be cenducted in all modes of opera icn and includes au:c=atic transfer of pu=p suction from the condensate s:crage tank to the suppression pool for be:h codes of initiation (high suppressi:n pool level and low cendensata s::: age tank level).
c) Pu=p head flow characteristics and N?SE are checked for censistency and design specifications for the various =edes of operation.
d) Systes perfor=ance is determined.
e) Simulated signals vill be used to demonstrate e=ergency initia: ion.
f) The wa:er leg pu=p will be operated to maintain full EPOS pump discharge line.
- 2. High ?: essure Core Spray Diesel Generator a) Manual and au:=ma:ic opera:Lon is perfor=ed which includes operatica of the auxiliary syste=.
b) The largest single load and subsequently all leads are tripped f:cm the EPCS diesel genera:or.
c) The required consecutive star: and load tes:s are performed.
d) Full-load opera:Len of the EPCS diesel generator is performed for a: leas: 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
e) The rate of fuel consu=ption is measured.
f) Con::ols, alar:s, and interlocks are functionally tested,
- d. Acceptance Criteria
- 1. High Pressure Core Spray System (excluding EPOS diesel genera:::)
a) System au:c=stic initiatica operates properly.
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b) Controls af fecting the transfer of the HPCS pump suction water supplies operate properly.
c) System alarms operate properly.
d) System flow rates are within design specifications and NPSH is within specified limits for the various modes of operation.
e) Core spray pattern is acceptable.
f) Automatic systems function as per design specifications including valve sequencing, cycle times, and automatic initiation.
g) The water leg pump is capable of maintaining a full HPCS pump discharge line.
- 2. High Pressure Core Spray Diesel Generator a) Auxiliary systems operate properly.
b) HPCS diesel generator is automatically started on a simulated automatic actuation signal and attains required voltage and frequency within an acceptable time period.
c) Specified speeds and voltages are not exceeded during required load rejections.
d) HPCS diesel generator operates properly during the 24-hour load tests and temperatures are acceptable. This includes 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 110 percent of continuous rated load.
e) HPCS diesel generator maintains the required voltage and frequency during the 24-hour load test and a successful start functional capability test is performed at the completion of the 24-hour load test (within approximately 5 minutes).
f) HPCS diesel generator successfully completes the consecutive start and load test.
g) HPCS diesel generator synchronization and load transfer operate property.
This includes proper operation when tripped from the surveillance test mode.
h) Electrical interlocks between the HPCS diesel generator and its associated 4.16 kV bus operate properly.
- 1) The HPCS diesel generator is capable of being stopped and started manually from local and remote locations.
j) The rate of fuct consumption is such that the 7 day fuel storage inventory requirement is met.
TABLE 1.8-2 (Continued)
Regulatory Guide (Ref.; RRRC Category Degree of Conformance Reference l 1.108 - Revision 1 - 8/77; RRRC Cat. 2)
That "first-out" annunciation was not used.
The basis for this is the use of individual trip alarms, which give the operator adequate information for correct actions. Additionally, Technical Specifications and preoperational testing shall provide for testing of the stand-by diesel generators (DIV. I and DIV. II) in accordance with applicable sections of this regulatory guide except for Position C2a3. The standby diesel generator units (DIV. I and DIV.
II) shall demonstrate full load carrying capability for an interval of not less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a load equivalent to the continuous ratings of each standby diesel generator. The continuous rating of each standby diesel generator (7000KW) exceeds the maximum accident load (refer to Table 8.3.1). This continuous rating also exceeds the maximum load required for forced shutdown (refer to Table 8.3-1). Since the continuous ratings of the standby diesel generators exceed either the maximum accident load or the load required for forced shutdown. Testing at PNPP continuous ratings is an adequate demonstration of the standby diesel generators capabilities.
640.59 The Class IE 125 Volt D-C System Preoperational Test (FSAR Sub-(640.21) section 14.2.12.1.30) should demonstrate that loads necessary for (14.2.12) safe shutdown can be started and operated at the minimum battery voltage.
Response
The Perry Project is in the process of completing a Class IE Voltage Drop Evaluation (Calculation Program). This program includes evaluation of both 12$ VDC control and power circuits. The calculation for D.C. powered devices / equipment utilizes a battery voltage consistent with when the equipment is required to operate. A value of 113 VDC will be used for equipment / devices actuated in the interval between loss of AC power and diesel-generator breaker closure. A battery dischargevoltageexistingatthetimeofequipment/ device operation will be used for the remaining time. Devices or equipment calculated to have voltage less than their minimum rating will be tested to varify operation or physical changes will be made to increase the voltage at the devices or equipment.
When the evaluation is complete, Subsection 14.2.12.1.30 will be revised as necessary.
640.60 The Nuclear Boiler System Preoperational Test (FSAR Subsection (640.24) 14.2.12.1.1) should verify that ADS valve accumulators and (14.2.12) check valves perform as described in FSAR Subsection 5.2.2.4.1.
Response
The performance of the ADS valve accumulators and check valves as described in FSAR Subsection 5.2.2.4.1 will be verified.
Preoperational test abstract 14.2.12.1.1 has been revised to include verification that each ADS accumulator has sufficient capacity to provide 5 actuations of the associated ADS valve against atmospheric pressure, which is equivalent to demon-strate the design capacity of the accumulator to provide 2 actuations at 70 percent of maximum drywell design pressure.
Section 14.2.12.1.48 (Safety Related Instrument Air Test) has been revised to determine that the receiver capacity is sufficient to maintain the ADS accumulators charged for seven days.
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- b. Prerequisities
- 1. Individual component tests are complete and have been approved.
- 2. Instrument calibration is complete.
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- 3. Instrument air is available.
- 4. Electrical power is available.
- 5. Reactor vessel is available to receive water if actual level is to be checked.
- 6. The reactor coolant system pressure is at atmospheric for the ADS valve actuations.
- c. Test Procedure l
l 1. Water level instrumentation and system operation will be tested using simulated signals and by variations in actual vessel level.
- 2. Pressure instrumentation will be checked and system operations verified using simulated signals.
- 3. Main steam isolation valves will be tested for proper operation.
Accumulator capacity will be checked. MSIV closure times will be measured including delays of initiation logic.
- 4. Main steam relief valves will be tested for proper operation.
( 5. Nucient steam supply shutoff system operation will be verified, including containment isolation initiation logic for the following I signals; RPV Low Level, liigh Drywell Pressuru, MSL Space liigh Temperatura, MSL liigh Radiation, MSL liigh Flow, MSL Low Pressure, Reactor Building Vent Exhaust liigh Radiation, and manual actuation.
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- 6. Automatic depressurization logic functions will be verified.
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- 7. Each ADS valve will be actuated five (5) times with the associated accumulator charging air isolated.
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- 2. Nuclear steam supply shutoff system performs within design specification, includiog initiation of containment teolation for the following signals; RPV Low' Level,,Iligh Dryweil Pressure, MSL Space High Temperatufe, MSL High Radiation,' Mut hish Flow, MSL Low Pressure, Reactor Building Vent Exhaust High Radiation, and manual actuation. -
- 3. Automatic depressurization logic performs within specification.
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- 4. Main steam isolation valves perform within specification. MSIV valve operating times including delays of initiating logic are within limits of design specitications.
- 5. Main steam relief valves perform within specification. -
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- 6. RPV instrumentation performs in accordance with design specifications.
- 7. Each ADS accumulator is capable of opening the associated ADS valve five (5) times with the drywell at atmospheric pressure and with the accumulator charging air isolated. ,
14.2.12.1.2 Reactor Recirculation System Preoperational Test
- a. Test Objective 4
- 1. To verify proper flow path is established with the recirculation loops.
- 2. To verify proper operation of system equipment such as Flow (ontrol
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Valves, pump suction and discharge valves, sensors, alarms and interlocks.
- 3. To verify the low speed motor generator sets operate within dasign specifications.
- 4. To verify proper jet pump perfornance.
- 5. To verify proper operation of the Recirculation Flow Control System.
Subsequent operation of the system during the Startup Test Phase will demonstrate that the system will control flow at operating conditions up to and including rated volumetric flow.
640.61 The Safety-Related Instrument Air Test (FSAR Subsection 14.2.12.
(640.41) 1.48) should include or reference loss-of-air tests similar to
.(14.2.12) those described in the Non-Safety Related Instrument Air System Loss of Instrument Air Acceptance Test (FSAR Subsection 14.2.12.
3.15.2). Note that Regulatory Guide l.68.3, Preoperational
-Testing of Instrument and Control Air Systems, can be used in lieu of Regulatory Guide 1.80.
Response
Section 14.2.12.1.48 has been revised to describe loss-of-air tests similar to those described in Section 14.2.12.3.15.2.
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e 14.2.12.1.48 Safety Related Instrument Air 1
- a. Test Objective i
To, verify the c.bility of the Safety Related Instrument air system to perform J I within design specifications b.- Prerequisites
- 1. Individual component tests are complete.
'~2. Instrument calibration is complete.
- 3. Electrical power is available.
- c. Test Procedure
- 1. The air compressor package will be' verified capable of providing compressed air to pressurize the Safety Related Instrument Air system.
- 2. The controls and operation of the system will be verified.
- 3. The loss of instrument air, by simulating both pipe break and moisture freezind will be tested.
- d. Acceptance Criteria-
- 1. The air compressor is capable of pressurizing the receiver tank to design
,, pressure within the designed time limit.
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- 2. System pressure capability is within design specification.
,. 3. The in-line receivers are capable of maintaining the ADS accumulators y properly charged for the required time period.
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- 4. System capabiltiy is maintained for both sudden and slow loss of air i
pressure.
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640.62 Modify the Shutdown from Outside the Control Room Test (FSAR (640.51) Subsection 14.2.12.2.25) to include test initiation with the (1.8). turbine generator in operation and plant systems in normal (14.2.12) configuration (automatic controls in operation), or modify your exception to position C.3 of Regulatory Guide 1.68.2, as stated in FSAR Table 1.8-1,' to provide expanded technical justification (explain how this test might result in damage to plant equipment) for not performing this test in accordance with Regulatory Guide 1.68.2.
Response
The Shutdown from Outside the Control Room Test (FSAR Subsection 14.2.12.2.25) has been modified to include test initiation with the Turbine Generator in operation and Plant Systems in normal configuration for the power level at which the test will be performed (approximately 10-25% power).
The Exception to position C.3 of Regulatory Guide 1.68.2 in FSAR Table 1.8-1 (attached) has been deleted.
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Tant 2 1.8-1 (Continued)
Re ference Degree of Conformance .
3 gulatory Guide (Rev.;RilRC Category)
- 1. 6 fl .1 - (Itevision I - t /77 RitRC Cat. 1)'
.PHPP conforms .to this guide with the exception 14.0 Preoperational and initial startup.
testing of feedwater anil condensate to conanitments o f Pos i t ion C. I -
s y s t erns for boiling unter reactor power - "Preoperational Testing", since both'the condensate and feeduater systems are plants . classified as nonsafety for testability purposes.
1.611.2 - (Itevision 1 - 7 / 7(l;IlllRC Ca t . 1)
PIIPP conforms to this guide. 14.0 Initial startup test program to demonstrate remote shutdown capability F for water-cooled nuclear power plants en 1.69 - (Itevision 0 - 12/73;RRRC Cat. 1) 12.0
-PHPP. conforms to this guide.
Concrete radiation shields for nuclear power plants 1.70 - (Itevision 3 - !!/711;ItRRC Cat. 1)
PHPP FSAR conforms to this. guide. FSAlt Standard format and content of safety analysis reports for surclear power plants-
640.63 The Turbine Trip and Generator Load Rejection Test (FSAR (650.56) Subsection 14.2.12.2.24) should be initiated by opening the main breaker such that the T-G will be subjected to the maximum overspeed condition, or modify FSAR Table 1.8-1 to provide technical justification for exception to Regulatory Guide 1.68, Appendix A.5.n.n.
Response
The method described in the Turbine Trip and Generator Load Rejection Test (FSAR Subsection 14.2.12.2.24) has been revised to state the generator load rejection will be initiated by opening the generator output breakers. This method will subject the turbine generator to maximum ,
overspeed conditions by removing all load from the generator during full power operation. This revision is reflecte;l in Amendment 16 to the FSAR (attached).
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14.2.12.2.24 Test Number 27 - Turbine Trip and Generator Load Rejection
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- s. Test Objective The purpose of this test is to demonstrate the response of the reactor and
- its control systems to protective trips in the turbine and generator.
- b. Prerequisites and Initial Conditions r
t The HPCS and RCIC systems are operable. ERIS is available. The Steam Bypass and Pressure Control System is in the NORM mode of operation. The preoperational tests have been completed as applicable.
- c. Test Instruction ,
Turbine trip (closure of the main turbine stop valves within -0.1 second) and generator load rejection (closure of the main turbine control valves in about 0.1 to 0.2 second) will be performed at selected power levels during the Startup Test Program. At low power levels (<40 percent), reactor protection is provided by high neutron flux and high vessel pressure scrams.
At higher power levels (>40 percent), the reactor will scram by sensing loss l of stop and control valve hydraulic fluid pressure in anticipation of valve closure. Backup scram action is provided by high neutron flux and high vessel pressure.
A generator load rejection will be performed at low power level, such that nuclear boiler steam generation is within bypass value capacity, to demonstrate scram avoidance. At an intermediate power level, in excess of bypass capacity, a manual turbine trip will be performed, and the response of the plant to this trip and scram will be determined. A generator load rejection will also be performed at near 100% power.
Generator load rejections shall be initiated by opening the generator output e o
breakers. '1he resultant automatic plant actions (e.g., turbine control
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valve fast clesure, recirculation pump trip, reactor trip) will be analyzed
- b for proper response.
14.2-146 Am. 16 (2-4-85)
640.64 Our review of the initial test program description disclosed (640.57) that the operability of several of the systems and components (14.2.12) listed in Regulatory Guide 1.68 (Revision 2), Appendix A may not be adequately demonstrated by the initial test program. Expand FSAR Subsection 14.2.12 (Individual Test Descriptions) to address the following items:
Preoperational Testing R.G. 1.68 FSAR Appendix A Section Description 1.e.10 10.4.7.2 Feedwater heaters and drains and associated 1.j.17 temperature, level and bypass control systems 1.e.Il 10.4.6.5 Condensate cleanup system 1.e.12 10.4.2.5 Main condenser evacuation system 1.j.25 7.7.1.8 Process computer 1.1.8 9. 3.2.4 Process sampling system 1.m.1 9.1.3 Siphon breakers on fuel pool lines and 1.m.3 operability and leak tests of sectionalizing devices and drains and leak tests of gaskets or bellows in the refueling canal and fuel storage pool 1.n.18 9.2.6.2 Freeze protection heater on condensate storage tank recirculation line Startup Testing 5.n 4.4.6.1.4 Loose parts monitoring 5.f.f. 9.4.3.2.2 Steam tunnel cooling system
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Response
1.e.10 The feedwater heater drain regulator valves and high 1.j.17 level' bypass valven are all tested during IC&R testing with the exception that the Hot Surge Tank of the Direct Contact
. Heater (IN21-B004) is tested in the Condensate System Test
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(N21).
-1.e .11 ' Section 14.2.12.3.(attached) has been. revised to include additional. abstracts for the Condensate Filtratian System and the Condensate Darineralization System 1.e.12- .Section- 14.2.12.3 (attached) has been revised to include an abstract for the Condenser Air Removal System L 1.j .25 ~ Section 14.~2.12.3 (attached) has been revised to include an abstract for the Process Computer i
- 1.1.8 bection 14.2.12.3 (attached) has been revised to include an abstract for the Process Sampling System
-1.m.1' Sections 14.2.12.1.13 and 14.2.12.1.21 (attached) have been revised to include siphon breakers for the fuel pool.
1.m.3- Section 14.2.12.1.21 has been' revised to include leak ~ testing of the fuel pool and refueling canal-gates
.1.n.18 This is a tube and shell heat exchanger and was acceptance tested as part of the Building Heat System (P55).
5.m ' The test abstract for Loose Parts Monitoring System (FSAR Section 14.2.12.2.57)(attached).was added in Amendment 16 to the FSAR.
5.f.f 'In addition to preoperational testing, further tecting is to be conducted during the startup test program as described in FSAR Section 14.2.12.2.36 (attached). This startup test abstract for Integrated HVAC testing was added in Amendment 16 to the FSAR.
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l N23 Condensate Filtration System
- a. Test Objective
- 1. To demonstrate the ability of the condensate filtration system to maintain condensate feedwater chemistry and proper operation of system controls.
- 2. The condensate system is operable and lined up to recirculate water to the hotwell.
- 3. Instrument and service air is available.
- 4. Electrical power is available.
- 5. Condensate storage and transfer is available with enough water to support this test.
- 6. Backwash receiving tank is available.
- 7. The process sampling system is available.
- c. Test Procedure
- 1. The filter units are placed in operation and their controls are operated.
- 2. Effluent water purity is determined.
- 3. System flow rates are measured for each filter unit.
- d. Acceptance Criteria
- 1. Each filter unit produces effluent water of the proper quality.
- 2. The condensate filtration bypass valve operates properly, based on flow during test conditions, to maintain specified differential pressure.
- 3. The On-line, Hold, and Backwash process operates properly for each filter unit.
- 4. System controls, interlocks, and alarms operate properly.
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N62' Condenser' Air Removal
- a. Obj ectives
- 1. To demonstrate the operability of the condenser air removal system.
'b. Prerequisites
- 1. The condensate system is operable and lined up to recirculate water to the condenser.
- 2. The auxiliary boilers are operable and lined up to supply scaling steam.
- 3. The main and auxiliary condenser are available.
- 4. Instruments and controls are calibrated and operated.
- 5. Instrument air is available.
6.. Electrical power is available.
- 7. The Off-Gas System and the Off-Gas Building Exhaust System is available.
- 8. The Turbine Building Closed Cooling Water System is available,
- c. Test Procedure
- 1. The mechanical vacuum pumps are operated to establish an initial vacuum.
- 2. -The mechanical vacuum pumps interlocks are functionally tested.
- 3. Various performance parameters are measured.
- 4. The condenser vacuum breakers are operated.
- 5. . Simulated high radiation signals will be used to initiate isolation.
- 6. The steam jet air ejectors (SJAE) intercondenser level control valves are
~
functionally tested.
d.. Acceptance Criteria
- 1. ' The SJAE intercondenser level control valves maintain proper water level in the SJAI's intercondenser loop seals.
,2. The. system controls, interlocks and alarms operate properly.
- 3. The condenser vacuum pumps trip and the suction valves close on simulated high mainsteam line radiation.
C91 Process Computer
- a. Test Objective
'Do demonstrate the proper operation of computer input / output logic and operator displays.
b'. Prerequisites
- 1. Individual component tests are complete.
- 2. ~ Computer system installed and operational.
3 .' _ Electrical power is available.
- 4. Computer software for input / output channels are operable to the extent necessary for performance of this test.
- c. Test Procedures
- 1. Input signals are either simulated at the Input / Output cabinet or transmitted by installed instrumentation.
- 2. Output signals are either monitored at the Input / Output cabinet-or by-actuation of field devices.
- d. Acceptance Criteria
'1. The computer response correctly to input signals.
- 2. Computer outputs operate properly.
3 .~ Operator displays are satisfactory.
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N33/35 . Process Sampling System
- a. Test Objective
- 1. To demonstrate the process sampling system provides adequate process samples to the various installed analytical monitoring equipment and grab sample stations.
- b. Prerequisites
- 1. Instrumentation and controls are calibrated and operable.
- 2. Electrical power'is available.
- 3. Applicable sample cooling water is available.
- 4. - Applicable waste receiving is available.
- 5. Service air is available.
- c. Test Procedure
- 1. Each sample station is operated as available.
- 2. -Grab samples are drawn from all grab sample points as available.
- 3. System alarms are activated.
d.- Acceptance Criteria
- 1. Sample lines are unobstructed and provide adequate sample flows. ,
- 2. Grab sample valves operate properly.
- 3. System alarms operate properly.
- 4. Sample pressures and temperatures are maintained within specified values.
(Certain sample pressures, temperatures and flowrates are deferred until after fuel load such that more representative process samples are available).
Notei Chemical fumehoods are tested for proper flow during the applicable HVAC test.
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14.2.12.1.13 Residual ~ Heat Removal System (RHR) Preoperational Test
- a. Test Objective To verify the ability of the Residual Heat Removal System to perform within design specifications in all modes of operation.
- b. Prerequisites
- 1. Individual component tests are complete.
- 2. Instrument calibration is complete.
- 3. Electrical power is available.
- 4. Demineralized water is available in the suppression pool, the spent fuel pool and the reactor vessel.
15 . The reactor vessel is available to receive water.
.c. Test-Procedures
- 1. Logic and interlock tests will be performed for all modes of operation to verify proper operation. These tests will be performed with the pumps locked out amd will include actuation from each
~
possible source. All associated events will be monitored.
- 2. The residual heat removal pumps will be tested to verify their performance is within design specifications. Pump head flow characteristics and NPSH are checked for consistency with design specifications for the various modes of operation.
- 3. The rystem will be. aligned and flow established for each of the following modes or functions:
.a) . Low pressure coolant injection. A simulated automatic initiation signal will be used for this test.
b) Suppression pool cooling.
c) Shutdown cooling.
d) Test mode.
e) Augmented fuel pool cooling.
- 4. Flow through the containment spray nozzles will be verified by conducting an air-flow test using flow paths which meet or overlap the boundaries of the water-flow test paths to demonstrate that there is' no blockage in the flow path,
- 5. Performance of the water leg pump will be verified to be within design specifications.
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- 6. 'Fles cu cf all siphen breakers associated with the augmented e pcol ecoling =cde will be observed.
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14.2.12.1.21 (G41) Fuel Pool Cooling and Cleanup System (FFCC) Preoperational Test.
- a. Tes: Objective To verify the ability of the Fuel Pool Cooling and Cleanup System to perform within the design specifications, and to demonstrate the Fuel Pool Gates are operable with acceptable leakage rates. l
- b. Prerecuisi:es
- 1. Individual co=ponent tests are complete.
- 2. Instrument calibration is co=plete.
- 3. Electrical power is available.
- 4. Condensate storage and transfer equipment is available.
- 5. Nuclear closed cooling system is available.
- c. Test Procedure
- 1. Controls, annunciators, logic and interlocks will be tested for proper operation.
- 2. Fuel pool filter /demineralizer performance will be verified in the following modes: -
a) Precoat b) Backwash c) Standby recirculation d) Normal operation
- 3. Flow to the spent fuel pool will be established and system ability to maintain level will be verified.
4 The ability of the containment isolation valves to perform within design specification will be verified.
- 3. Fuel pool cooling and cleanup pump perfor=ance will be verified to be within design specification.
- 6. Flow out of the all FPCC siphon breakers will be observed.
- 7. The Fuel Pool Gates are subjected to full hydrostatic head and leakage is determined.
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- d. Acceptance Criteria Acceptance Criteria for Level 2:
Conductivity, oxygen, pH and sodium instrumentation readouts agree with
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14.2.12.2.57 Test Number 133 - Loose Parts Monitoring System
- a. Test Objective To obtain a full range of baseline data for the Loose Parts Monitoring System (LPMS).
- b. Prerequisites and Initial Conditions The preoperation test has been completed. The LPMS is lined up for manual operation.
- c. Test Instruction During steady state operation at various power levels baseline data will be taken on all 12 channels of the Loose Parts Monitoring System. This will include a cassette recording, a waveform plot and a loose part printout for each power level. The system will be placed in the manual i
mode of operation and, using the appropriate operating procedure for l guidance, the required data will be obtained.
l j d. Acceptance Criteria l
. Acceptance Criteria for Level 2:
l Baseline data has been satisfactorily obtained at the specified power levels.
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14.2-173s Am. 16 (2-4-85)
14.2.12.2.36 Test Number.100 - Integra:ed HVAC
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- a. Tes: Objec:ive T: de=cns::ste the ability cf ven:lla:ica sys:ers to . sin:ain specified Uni: 1.and c:::c: area ta--a-=" es and relative humidi:y wi:hin specified limits during plan: cperation. Specific aspects of cer: sin ventila:i:n sys:ers opera:icn will also be demonstrated.
- b. Prerequisi:es and Initial cendi:icns Applicable preoperational tests have been c =pleted. Ventila: ion systems are lined-up and operating. Outside at=ospheric condi:icns are stable.
Required tes equipment is available and calibrated. Any abnormal sources of plant heat, such as large steam packing-leaks, have been identified and their effect on the test evaluated.
- c. Test Ins:ruction e
First at a icv power level, and then at a high power level, data vill be recorded to de=castra:e preper operation of plant ventilation systems.
- d. Acceptance Cri:eria Acceptance Criteria fer Level 2:
Re:orded da:a vill be compa ed to CAI specified te=perature and rela:ive humidi:y li=its.
14.2.12.2.37 Tes: Na=ber 113 - Service Water System
- a. Tes: Objective The purpose of this tes: is to de castra:e that the service water sys:em can pr: vide a. sufficient. amount of coeling va:er :o the hes: leads it supplies.
14.2-173 A=. 16 (2-4-85)
640.65 The following startup test abstracts should be modified to (640.58) clarify the noted items:
(14.2.12)
(1) The Control Rod Drive System Test )FSAR Subsection 14.2.12.2.5) Level 1 acceptance criteria should describe the allowable number of slow and inoperative CRDs.
(2) The RCIC System Test (FSAR Subsection 14.2.12.2.12) Level 1 acceptance criteria should clarify reference to Figure 4.2-7.
If this reference should be Figure 14.2-7, then this figure should be reinstated.
-(3) The Water Level Reference Leg Temperature Test (FSAR Subsection 14.2.12.2.13.1) appears to have omitted Level 2 acceptance criteria for the Shutdown Range and Fuel Range level instrument systems.
(4) The Recirculation System - Trip of Two Pumps (FSAR Subsection 14.2.12.2.27.2) acceptance criteria reference Figure 14.2-6, which no longer addresses the concerns of this test. Either reinstate the appropriate figure, or modify the test to delete reference to Figure 14.2-6 and further modify Figure 14.2-6 to reference the test abstract to which it refers.
Response
(1) The limitation on the number of slow CRDs has been added to 14.2.12.2.5.. The limitation on the total number of slow and inoperative CRDs is a test acceptance criteria, and is covered in the Technical Specifications.
(2) Section 14.2.12.2.12 should reference Figure 14.2-7, which has been reinstated.
(3) The Water Level Reference Leg Temperature Test (FSAR 14.2.12.2.13.1) does not include an acceptance criteria for the Fuel Range because it is not practical to obtain the assumed calibration conditions (Post-accident conditions'in the drywell and containment) for this range, as it is detrimental to equipment. The Water Level Reference Leg Temperature Test (FSAR 14.2.12.2.13.1) Level 2 acceptance criteria was revised in Amendment 16 to the FSAR (attached) to include all other ranges.
(4) The test acceptance criteria has been revised to delete reference to the figure in Section 14.2.12.2.27.2d in Amendment 16 (attached). Figure 14.2-6 was no longer applicable to any test abstract and was deleted.
i Test Conditions Reactor Pressure with Core Loaded psig (kg/cm9)
Action 0 600(42.2) 800[56.2) Rated Position Indication all Insert / Withdraw a) Single CRD Continuous Modes all b) Gang Groups Continuous Modes all Coupling all Friction all all Cooling Water Flow Rates (Total) 1 Individual CRD Scram 4* 4* all Individual CRD Scram 4**
NOTE: Single CRD scrams should be performed with charging valve closed.
- Refers to four CRDs selected for continuous monitoring based on slow normal accumulator pressure scram times as determined from pre-operational testing, or unusual operating characteristics. The "four selected CRDs" must be compatible with the requirements of both the withdrawal sequence and the installed rod movement limitations systems.
- d. Acceptance Criteria Acceptance Criteria for Level 1:
- 1. Each CRD must have a normal withdrawal speed of less than or equal to 3.6 inches per second, indicated by a full 12-foot stroke in greater than or equal to 40 seconds.
- 2. The scram insertion time of each control rod from the fully withdrawn position, based on de-energization of the scram pilot valve solenoids at time zero, shall not exceed the acceptance criteria provided in the General Electric Startup Test Specifications. This includes the limit that the total number of " slow" drives (per the General Electric Startup Test Specification) shall not exceed 7.
i
If any Level I criteria are not met, the reactor will only be allowed to operate up to a restricted power level defined by Figure 14.2-7 until the problem is resolved.
Acceptance Criteria for Level 2:
- 1. The turbine gland seal system shall be capable of preventing steam leakage to the atmosphere.
- 2. The delta P switches for the RCIC steam supply line high-flow isolation trip shall be calibrated to actuate at the value specified in the plant Technical Specifications (about 300%).
- 3. The speed and flow control loops shall be adjusted so that the decay ratio of any RCIC system related variable is not greater than 0.25.
- 4. In order to provide an overspeed and isolation trip avoidance margin, the transient start first and subsequent speed peaks shall not exceed 5 percent above the rated RCIC turbine speed.
14.2.12.2.13 Test Number 16A - Selected Process Temperatures
- a. Test Objective The purpose of this test is to assure that the measured bottom head drain temperature corresponds to bottom head coolant temperature during normal operation, to identify any reactor operating modes that cause temperature stratification, to determine the minimum position of the flow control valves which will prevent coolant temperature stratification in the reactor pressure vessel bottom head region, and to familiarize plant personnel with the temperature differential limitations of the reactor system.
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- 2. The recirculation pump in an idle loop must not be started, active loop flow must not be raised, and power must not be increased unless the idle loop suction temperature is within 50 F of the active loop suction temperature. If two pumps are idle, the loop suction temperature must be within 50 F of the steam dome temperature before pump startup.
Acceptance Criteria for Level 2:
i During two pump operation at rated core flow, the bottom head temperature as measured by the hottom head drain line thermocouple should be within 30 F of the recirculatioe loop temperatures.
14.2.12.2.13.1 Test Number 16B - Water Level Reference Leg Temperature
- a. Test Objective The purpose of this test is to measure the reference leg temperature at rated temperature and pressure and steady-state, and ensure recalibration of the instruments if the measured temperature is different than the value assumed during the initial calibration. Temperature data will also be taken during open vessel testing to verify acceptance criteria for the Shutdown Range water level instrumentation. The Fuel Range reference leg temperatures will not be verified since this range is calibrated for post-accident conditions.
- b. Prerequisites and Initial Conditions Containment and drywell cooling systems are in normal operation and the temperature in the vicinity of the reference legs is steady-state. The preoperational tests have been completed as applicable and system instrumentation has been calibrated.
- c. Test Procedure To monitor the reactor vessel water level, five level instrument systems are provided. These are:
- 1. Shutdown Range
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(~ 3. Wide Range l
4.. Fuel Range .
- 5. Upset Range These systems are used respectively as follows:
- 1. Water level measurement in cold, shutdown conditions.
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Feedwater flow and water level control functions.
- 3. Safety functions.
- 4. Post accident indication.
- 5. -Level indication during transients.
The test will be done at rated temperature and pressure and under steady-state conditions and will verify that the reference leg temperature of the instrument is the value assumed during initial calibration. The atmosphere in the vicinity of the reference l'egs will be measured. This will be considered to be the temperature of the reference legs. Data taken during open vessel testing will be used to verify the acceptance criteria for the Shutdown Range level instrumentation.
- d. Acceptance Criteria Acceptance Criteria for Level 2:
i The difference between the actual reference leg temperatures (s) and the value(s) assumed during initial calibration shall be less than that amount
- which will result in a scale end point error of 1 percent of the instrument span for each range.
- 2. The simula:ed he:: flux marb-in := avoid a scram shall be 1 5.0 percen:
" during :he one pu=p trip for recovery.
- 3. The APRM =ar;in to av id a s::a shall be 17.5 percen: during :he ene pu=p trip recovery.
- 4. The time fr:m :ero pu=p speed to full pump speed shall be grea:er than 3 sec:nds.
14.2.12.2.27.2 Test Number 303 - RPT Trip of Two Pumps
- a. Tes: Objec:ive The purpose of this tes is to record and verify accep able perfer:ance of the recirculatice two pump trip circui:ry and to demons:ra:e sat:s:accory recirculation loop flow coas down.
- b. Prerequisites and' Initial Condi:icas Ccre flow is >95 rercen: N3R. ERIS is available to coni::: the L?RM channels near the li=iting fuel bundles. The preopera:icnal tests have been c:=ple:ed,
- c. Test Instruction With the rese:c operating betueen 55 percen: and 65 percen core pcwer, a turbine c:n:rol valve fas closure will be simula:ed. The' recirculation pu=ps will autecatically transfer fr = the 60 E: power supply :o :he low frequency cctor generator supply. The transien: will be recorded, analy:ed, and cc pared to the ac:ep ance criteria.
- d. Acceptance Cri:eria Acceptance Cri:eria for Level 1:
The :wo pump drive flew coastdown transient during :he firs: 3 se::nds mus:
specifica: ion. l be bounded by the ll=l:ing curves provided by CE in the tes:
As. 16 (2-4-35) 14.2-156
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'640.66 The Full Reactor Isolation Test (FSAR Subsection 14.2.12.2.22.2)
'(640.59) and FSAR Table 14.2-2 should commit to conducting the simultaneous (1.8) full closure of all MSlVs at Test Condition 6 (95% power), or (14.2.12) technical justification should be provided in FSAR Table 1.8-1 for exception to Regulatory Guide 1.68, Appendix A.5.m.m.
Response
The Full Reactor Isolation Test will be performed at Test Condition 6 (95% power), as indicated in FSAR Table 14.2-2 and FSAR Subsection 14.2.12.2.22.2. Additionally FSAR Subsection 14.2.12.2.22.2c describes the full isolation as the simultaneous full closure of all MSIVs. This meets Pegulatory Guide 1.68, Appendix A.5.m.m.
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2 640.67 The System Preoperational Vibration Test (FSAR Subsection (640.60) 14.2.12.4.1)'should1be modified to delete the note after
'(14.2.12) Test Objective 4. I't is not appropriate for the eitgineer to determine.what portions of the test,may be waived. Any test deviations should be processed through normal review and approval '
channels. ,
g R_esponse The Sys' tem Preoperation Vibration Test (FSAR Subsection 14.2.12.4.1) has been removed.to Startup Test 122, (FSAR Subsection 14.2.12.2.46). This abstract has been modified to
, delete the note af ter Test Objective 4.
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640.68 The following preoperational and acceptance test abstracts (640.61) should be modified to clarify the noted items:
(14.2.12)
(1) The reference to drywell leakage testing in FSAR Subsection 14.2.12.1 should reference item 640.30, not 640.31.
(2) The Condensate System Acceptance Test (FSAR Subsection 14.2.12.3.8) should reference item 640.17, not 640.43.
(3) The Containment Vessel Chilled Water System Test (FSAR Subsection 14.2.12.3.14) should reference item 640.44, not 640.14.
(4) The acceptance test abstracts contained in the Q&R Section 14.2 should be deleted as they have been revised and incorporated into FSAR Subsection 14.2.12 as preoperational or acceptance test abstracts.
Response
(1) The reference to drywell leakage testing in FSAR Subsection 14.2.12.1 has been corrected to reference Item 640.30, (attached).
(2) The Condensate System Acceptance Test (FSAR Subsection 14.2.12.3.8) has been corrected to reference item 640.17, (attached).
(3) The Containment Vessel Chilled Water System Test (FSAR Subsection 14.2.12.3.14) has been corrected to reference Item 640.44, (attached).
(4) The acceptance test abstracts contained in the Q&R Section 14.2 have been deleted.
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- Master Parts I *ist (M?L)
S ster Name Section P'1 Cocling T:ver Makeup Isola: ion 11.2.12.1.56 Emergency Service ~44:er Screen 'Jash Sys:e= .57 P49 C51 - Solid Radwaste Oispesal Sys:em .55 C22 Redundan: Rea :itity Con:::1 System .59 Pos: A::iden: Radia:icn Monitoring Sys:em .60 019 Feedva:er Leakage Centrol Sys:em .61 N273 Penetra:ica Pressuri:2:ica System .62 P53 Post Acciden: Samt.lin5 System .63 P37 ,
R14A AT*45 Class lE Uninterruptible Power Supply .64 Emergency and Essential Lighting System .65 171 C
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- 1 The Dryuell Leakage Tes: is described in See:icn 6.2.6.5.1. ]
t 14.2.12.1.1 Nuclear Boiler Syste= Preopera:icnal Test l l
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- a. .e t s t O. .ojective To verify the ability of the' Nuclear Sciler System to perform within design specifica:icn. ,
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(b) Proper system controls, indications and alarms are verified to f function correctly.
(c) Fan auto-trip and auto-start signals function correctly.
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- d. Acceptance Criteria
- 1. System fans perform satisfactory and delivered specified air quantities.
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- 2. System instrument controls function per design requirements. 3
. 3. System interlocks function as required and designed.
14.2.12.3.8 Condensate System Acceptance Test (N21)
( a. Test Objective
- 1. To demonstrate that the condensate system pumps are capable of supplying the designed flow of condensate at designed head.
- 2. To demonstrate that the condensate system is capable of maintaining the condenser hotwell within normal operating units. s 1
3
- 3. To operationally verify the interlocks and alarms associated with
- the hot surge tank.
- b. Prerequisites 4
- 1. Individual component tests have been completed.
N.
14.2-177j Am. 16 (2-4-85)
- 2. Instru=ent calibra: ion is complete.
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- 3. a Electrical power is av'ilable.
14 De ineraliced water is available.
- 5. Instrument air is available.
- 6. >The turbine. building closed cooling,.condensa:e transfer and storage and feedwater systems are available.
Test Procedure-c..
- 1. The hotwell pumps.and the condensate booster pumps will be operated to verify that each pu=p' supplies design ~ flow at design head.
- 12. The ho:vell level control functions -ill be verified by varying the hot'vell level. S e
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- 3. The ho:. surge tank level instru=enta: ion will be verified rela:ive
.to alar =s and associated interlocks by. varying the-hot surge tank-
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- 4. The condensate system will be operated at full. flow and pe=p suction pressures will be corrected for the worst case condi: ion relative to-
- verification of N?S*d available.
'd. Acceptance Criteria
- 1. The he:well level control' system maintained the level in the hotwell within normal-operating limits.
- 2. The in:erlocks and alar:s associated with the hot surge tank-actuated at the design values.
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I 14.2-177k Am. 16 (2-4-85) 1 l
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14.2.12.3.14 Containment Vessel Chilled Water System (PS0)
- a. Test Objective Te verify the ability of'the Centainment Vessel Chilled Water Systen to perict: vithin design specifications.
- b. Prerequisites
- 1. Indiviudal ce=ponent testing has been completed.
- 2. Instrc=ent calibration and loop checks are completed.
- 3. Test instru=entation is available and is calibrated.
- 4. Instrument air is available; e
d
- 5. Electrical power is available. ,
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- 6. Nuclear closed eccling water system is available.
,7. Contain=ent vessel cooling ventilation system is available.
- 8. In service inspection room ventilation system is available.
- c. Test Procedure
- 1. P cper operation of the Containment Vessel Chilled Water System is verified as follows:
(a) Chilled water pe=p capacities are verified for design sp=.
(b) Centainment isolation valves function correctly and operate within prescribed time.
14.2-177t
(c) System respends'c rrectly to manual isciation signal.
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-(d) System respends corre::iy to automatic isolation signal. e d
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_(e) .Pr:per system c:n:rcis, indica: ions and alar:s are verified to functica'ecrree:Ly.
- d. Acceptance Cri:eria 1.- System pumps perform satisfae:orily and deliver specified water flows.
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- 2. System instruments control function per design requirements.
14.2.12.3.15 Non-Safety Related' Instrument Air and Loss of Instrument Air Accep:ance Tests 14.2.12.3.15.1 Non-Safety Related Instrucent Air Acceptance Test
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- a. Tes: Objectives 1.- Verify'the ins:ru=ent air (IA) system is capable of supplying air at the required flow, pressure, temperature and dew point. ;.
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- 2. Verify proper operation and centrol for the manual and aute=atic modes of operation of the IA cc= pressor.
- 3. -Verify proper operatien of redundan: componen:s.
- b. Prerequisites
- 1. Instru=ent calibration complete.
- 2. Electric pcwer.available.
- 3. Required supper: systems are available.
14.2-177u
1 FSAR PREOPERATIONAL TEST PROGRAM REFERENCES FSAR REF.
RMPL _ SYSTEM B13 Reactor System (Internals) 14.2.12'.1.33 B21 Nuclear Boiler 14.2.12.1.1 B33 Reactor Recirculation 14.2.12.1.2 C11 Control Rod Drive Hydraulic 14.2.12.1.3 i
Rod Control & Information 14.2.12.1.50-C22I Redundant Reactivity Control 14.2.12.1.59' C34 Feedwater Control 14.2.12.1.4 C41 Standby- Liquid Control 14.2.12.1.5 C51 Neutron Monitoring 14.2.12.1.6,& 14.2.12.1.7 (SRM,-IRM, LPRM, APRM & TIP)
C61 Remote Reactor Shutdown 14.2.12.1.8
, Division 2 Remote Shutdown Note 1, 2 C71 Reactor Protection 14.2.12.1.9 t
D17 . Plant Radiation Monitoring System 14.2.12.1.10 D19 Post Accident Radiation Monitoring 14.2.12.1.60 D21 Area Radiation Monitoring System 14.2.12.1.11 q
D23 Containment Atmosphere Monitoring 14.2.12.1.12 E12 Residual Heat Removal 14.2.12.1.13 EIS- Containment Spray 14.2.12.1.13.c.4 E21 Low Pressure Core Spray 14.2.12.1.14 E22 High Pressure-Core Spray 14.2.12.1.15 E31 Leak Detection 14.2.12.1.16 q E32 MSlV Leakage Control 14.2.12.1.17 f
_l...
-c 1
E51 ' Reactor Core Isolation-Cooling 14.2.12.1.18 & 6.2.6.3 E53 Containment Isolation -14.2.12.1.1.c.5 and 6.2.6.3 E61: Integrated Leak Rate Test 14.2.12.1
. Local Leak Rate Test 6.2.6.2 Containment Structural Integrity Test 14.2.12.1 E62' Drywell Leak Test 14.2.12.1 E64 Shield Building Leak Rate Test 14.2.12.1.43'
-E66 Drywell Structure Integrity Test 14.2.12.1.44 E67 Control Room Leakage 14.2.12.1.25 Fil Fuel Servicing Equipment 14.2.12.1.45 F12 ' Servicing. Aids 14.2.12.1.45 F13 Reactor Vessel Servicing Equipment 14.2.12.1.45
~ F14 In-Vessel Servicing Equipment 14.2.12.1.45' FIS- Refueling Equipment 14.2.12.1.45 F16 Storage Equipment 14.2.12.1.45 F17 Under Reactor Vessel Servicing Equipment 14.2.12.1.45
-F42 Fuel Transfer Equipment 14.2.12.1.19 G33 Reactor Water Cleanup 14.2.12.1.20 G36 RWCU Filter /Demineralizers 14.2.12.1.20 G41 Fuel Fool Cool and Cleanup 14.2.12.1.21 G43 Suppression Pool Makeup 14.2.12.1.22 G50 Liquid Radwaste System 14.2.12.1.23 G51 Solid Radwaste Disposal System 14.2.12.1.58 L51' Reactor Building Polar Crane 14.2.12.1.51 and Fuel Handling Area Crane 14.2.12.1.52 M11 Containment Vessel Cooling System 14.2.12.1.54 M13 Drywell Cooling System 14.2.12.1.55
c.
M15 ~ Annulus Exhaust Gas Treatment 14.2.12.1.24 M16 Drywell Vacuum Relief 14.2.12.1.46 M17 Containment Vacuum Relief 14.2.12.1.47 M23 MCC Switchgear & Misc. Area HVAC 14.2.12.1.35 M24 Battery Room Exhaust 14.2.12.1.35 M25 Control Room HVAC 14.2.12.1.25 M26 Control Room Emergency Recirculation 14.2.12.1.25 M28 Emergency Pump Area Cooling 14.2.12.1.36 M32 Emergency Service Water Pump House Ventilation 14.2.12.1.37 M36 Off-Gas Building Exhaust 14.2.12.1.38 M39 ECCS Pump Room Cooling 14.2.12.1.39 M40 Fuel Handling Area Ventilation 14.2.12.1.40 M43 Diesel Generator Building Ventilation 14.2.12.1.26 M51 Combustible Gas Control 14.2.12.1.41 M56 Hydrogen Control Note 1 M98 Engineered Safety Features Systems, 6.5.1.4 & 9.4.2.4 In Place Filters N27B 'Feedwater Leakage Control System 14.2.12.1.61 N64 Offgas System 14.2.12.1.27 P41 Service Water Cooling Tower Makeup Isolation Valves 14.2.12.1.56 P42 Emergency Closed Cooling 14.2.12.1.28 P45 Emergency Service Water 14.2.12.1.29 P47 Control Complex Chilled Water 14.2.12.1.42 P49 Emergency Service Water Screen Wash 14.2.12.1.57 P53 Penetration Pressurization 14.2.12.1.62 Personnel Airlock Leakage Control System 6.2.6.2 P57 Safety-Related Instrument Air 14.2.12.1.48 P72 Plant Underdrain System 14.2.12.1.34
P87 -Post. Accident Sampling 14.2.12.1.63
-R14A Class 1E Uninterruptible Power Supply (RRCS) '14.2.12.1.64 Metal Clad ~Switchgear 14.2.12.1.49
-R22 R23. 480 Volt Load Centers 14.2.12.1.49 R24 Motor Control Centers 14.2.12.1.49 R25 Dist. Panels - 120, 240, & 480 V 14.2.12.1.49 R42 Class 1E 125 Volt DC 14.2.12.1.30 R43 Standby Diesel Generator 14.2.12.1.31
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R44' Standby Diesel Generator Starting Air 14.2.12.1.31 R45 Standby Diesel Generator Fuel Oil 14.2.12.1.31 R46 Standby Diesel Generator Jacket Water Cooling 14.2.12.1.31 R47 Standby Diesel Generator. Lube 011 14.2.12.1.31 R48. ' Standby Diesel Generator Exhaust / Intake / Crankcase 14.2.12.1.31 R71 Emergency Lighting 14.2.12.1.65
~R76 ECCS Integrated Initiation with LOSP 14.2.12.1.32 NOTES: 1. New or revised system as a result of changed regulatory requirements.
- 2. Test abstract.will be added to FSAR Chapter 14 in Amendment 19.
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