ML20140B570
| ML20140B570 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway  |
| Issue date: | 09/04/1981 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| SLNRC-81-84, NUDOCS 8109140247 | |
| Download: ML20140B570 (25) | |
Text
e SNUPPS Standardized Nuclear Unit Power Plant System 5 Choke Cherry Road Nicholas A. Petrick Rockville, Maryland 20850 Executive Director m emoi September 4, 1981 SLNRC 81-84 FILE: 0541 SUBJ:
CSB Review Mr. Harold R. Denton, Director Office of Nuclear Reactor P.egulation U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Docket Hos. STN 50-482, STN 50-453, and STN 50-486
Reference:
SLNkC 81-79, dated August 31, 1981, EQB/CSB Review
Dear Mr. Denton:
In discussions with Dr. Gordon Edison, NRC project manager for the SNUPPS applications, it was learned that additional infonnation was required in order for the Containment Systems Branch to complete their review of the SNUPPS FSAR. The attached FSAR change provides the requested information and will be incorporated in the next revision to the SNUPPS FSAR. Please note that this letter modifies information transmitted by the referenced letter. Also note that the information to be added to FSAR page 18.2-39 was requested by the Equipment Qualification Branch and information on page 18.2-55 was requested by the Radiation Assessment Branch.
Very truly yours, hb N 0
Is.
N. A. Petrick
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Enclosure:
FSAR pages c4
)dvis.yg'is,'s^, fy cc: J. K. Bryan UE h g % s$s G. L. Koester KGE N'
D. T. McPhee KCPL D. F. Schnell UE W. A. Hansen NRC/ CAL T. E. Vandel NRC/WC L. Kripps El
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8109140247 810904 PDR ADOCK 05000482 A
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I SLNRC 81-84 bec: A. C. Passwater UE G. P. Rathbun KGE P. A. Ward B
J. H. Smith E
W. L. Luce W
r Enclosure to SLNRC 81-84 FSAR Changes I
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SNUPPE e.echanical devices to seal or lock the valve closed, or to prevent power from being supplied to the valve operator.
Checking the valve position light in the control room is an adequate method for verifying every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> that the purge valves are closed.
18.2.11.2 Discussion The containment isolation system and the containment isolation actuation are described in Sections 6.2.4, 7.3.2, and 7.3.8.
18.2.11.3 SNUPPS Response All lines penetrating the conte;nment are identified in Figure 6.2.4-1, Sheets 1 through 74.
These figures also identify the actuation signal (s) for isolation of those lines requiring isolation.
The logic design for containment isolation is such that resetting of the containment isolation signal will not result in the loss of containment isolation.
Once the initial-ing signal is reset, individual valves can be opened from the CN N k control room, if required.
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N Plant procedures will discuss the raethods used to ensure that manual valves are in the proper position.
Table 18.2-2 identifies systems as either essential or non-essential.
Essential systems are those systems required to have isolation valves open for either safe shutdown or mitigation of the consequences of an accident.
The greatest number of lines are automatically isolated upon initiation of a containment isolation signal, Phase A (CIS-A),
which also initiates a feedwater isolation signal (FWIS) and a steam generator blowdown isolation signal (SGBSIS).
A CIS-A is initiated when a safety injection signal (SIS) is initiated.
The diverse parameters sensed to initiate an SIS are low steam line pressure, low pressurizer pressure, and high containment pressure (Hi-1).
The CIS-A logic is shown on Figure 7.2-1, Sheet 8.
The main steam and related lines are automatically isolated upon initiation of a steam line isolation signal (SLIS).
The diverse parameters sensed to initiate an SLIS are either low steam line pressure or high negative steam pressure rate and high containment pressure (Hi-2).
The SLIS logic is shown on Figure 7.2-1, Sheet 8.
Rev. 6 18.2-38 8/81
=.
i Insert A Reopening of isolation valves is performed on a valve-by-valve or line-by-line basis.
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Insert B The containment isolation setpoint pressure (Hi-1) that initiates containmert isolation (CIS-A) for non-essential penetrations has been reduced to the minimum compatible with normal operating conditions. The l
Technical Specifications will establish a limit for containment pressure during normal operations. The Technical Specifications also will contain the setpoint for Hi-1 which will be based on the normal operation limit and instrument drift and accuracy.
If any justifications are required i
for the Hi-1 pressure setpoint, they will be provided during the course of the review of proposed Technical Specifications.
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i nt inside The lines supplying component cooling water to equ pme A CIS-B is initiated by the containment is isolated by CIS-B.It is not diverse,
- tuation, but is (Hi-3).
high containment pressureinitiated only after initiation of a containment sp which does utilize diversity.
Sheet 8.
initiation The containment purge system will be isolated upon (CPIS).
The diverse of a containment purge isolation signal t inment parameters sensed to initiate a CPIS are high con arad diation The CPIS level, or a CIS-A signal.
40
- GE M 5 E E.1-t 7.3-1, Sheet 2.
trol All containment isolation valves are provided with conManual actuation sw switches on the main control board. SLIS, and CPIS.
In are provided for initiation of CIS-A,these systems are redundant and meet addition to diversity, safety-grade (Class 1E) criteria.
18.2.11.4 Conclusion tisfies the The design for the containment isolation system sa requirements of Item II.E.4.2 of NUREG-0737.
Rev. 5 7jg1 18.2-39
INSERT C The guidelines used for operability of containment purge isolation valves intended for use during plant operation comply with NRC criteria.
Documentation of operability will be provided at least four months prior to fuel load of the first SNUPPS unit. If the NRC is not satisfied with demonstrated operability, the SNVPPS plants will meet the Staif Interim Position of October 23, 1979 and mechanically unrestricted operability will be demonstrated by the first refueling. The shutdown purge system isolation valves will meet SRP 6.2.4, item II.3.f during operational conditions 1,2,3, and 4. Furthermore, these valves will be verified to be closed in accordance with NUREG-0737, item II.E.4.2.
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SNUPPS 9
Containment Radiation Monitors The SNUPPS design meets the recommendations of Table II.F.1-3.
l The design includes two physically separated Class 1E contain-ment radiation monitors.
The monitors are designated as O-GT-RE-59 and 0-GT-RE-60.
The detectors will be located inside the containment.
Indication is provided in the control room for each monitor, which is powered from a vital lE power source.
One channel will be provided with a recorder, which is powered from vital 1E power sources.
Each monitor will have a range up to 10?
R/hr for gamma radiation.
The monitors will be sensitive down to 60 kev photons.
The response of the monitors will be essentially flat (120%) for energies between.1 Mev and 3 Mev.
The equipment will be seismically qualified for the location in which it is installed.
The components will be environmentally qualified for the environmental conditions to which they will be subjected.
Calibration of the monitors will be addressed in procedures.
Additional information regarding the details of the design will be provided at least 4 months prior to fuel load of the first SNUPPS unit.
Containment Pressure Indication The SNUPPS design provides a dual range, redundant, continuous indication of containment pressure with both ranges (0 to 60 psig and -5 to 180 psig) indicated and recorded in the control room at the same time.
The extended range indication loops will be Class 1E.
As a minimum, their range will be from minus 5 psig to three times the containment design pressure of 60 psig.
The response time of the containment pressure control room indication is 10 seconds for both the narrow and wide-range instrument channels.
The accuracy of both the narrow and wide range channels is 14 percent of scale.
The pressure monitor instrumentation will meet the design and qualification criteria of NUREG-0737, Appendix B in accordance with the WCAP 8587 quali-fication reference of Table 3.11(B)-3, Sheet 24B.
Containment Water Level Indication The SNUPPS design includes in the control room continuous indication of the containment water level.
This instrumenta-tion will be redundant and designed and qualified in accordance with Class lE requirements to meet the requirements of NUREG-l 0737, Appendix B.
A single range will be used to monitor both l
the containment normal sump level and the containment water j
level.
The range will be 13 feet, which covers 6 inches from Rev. 7 18.2-55 9/81
SNUPPS TABLE 7.5-1 ENGINEERED SAFETY FEATURES - DISPLAYS LEGENDS Readout / Display Location Type of Readout / Display I - Linear scale indicator or log scale indicator CB - Control board (main)
SC - System cabinets in control room R - Recorder ++
L - Indicator light LP - Local panel A - Control room annunciator or computer alarm C - CRT display on demand via plant computer
- - Safety related Number of Channels channel Indicated Accuracy
% of Full Readout / Display Type of Displayed Parameter Readout / Display Available Required Range Scale Locations Engineered Safety Feature System Actuat M Reactor coolant system pressure I #, R 2
1 0-3,000 psi 14.3*
CB, LP, SC (pressurizer)
Containment pressure I #, R 2
1 0-60 psig 14 CB, SC Containment pressure (extended I #, R 2
1 180 psig 14 CB range)
Steam generator pressure I #, R 2 per loop 1 per loop 0-1,300 psia 114*
CB, LP (steam line)
Reactor coolant system I #, R 2
1 0-700 F 14*
CB, SC wide range temperature (hot)
Reactor coolant system I #, R 2
1 0-700 F 14*
CB, LP wide range temperature (cold)
Refueling water storage tank I #, R 2
1 0-100 %
14*
CB, SC level Boric acid tan.s level I #, R 2 per tank I per tank 0-100 %
14*
CB, SC Steam generator water level I #, R 2 per loop 1 per loop 0-100 %
135*
CB, SC, LP Control room air intake - gaseous I #, A, R 2
1 107 to 108 125 SC pCi/cc radioactivity control room air intake - chlorine content I#, A 2
1 0 to 10 ppm 125 CB, LP Containment gaseous radio-I#, A, R
2 1
10~7 to 10 8 125 SC pCi/cc activity Rev. 7 9/81
SNUPPS CONTAINMENT ISOLATION VALVES - The containment purge system is the only containment HVAC system which penetrates the The supply and exhaust system both contain containment.
These valves are air-operated butterfly four isolation valven.
valves.
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debris DEBRIS SCREENS - As shown on Figure 9.4-6, Sheet 4, screens are provided on the containment side of the minipurge supply and exhaust isolation valves to prevent the erdry of lightweight debris which could preclude tight valve closure.
The piping which contains the screens is ANSI B31.1 (150 pound design pressure) piping which is seismically analyzed in accor-The screens dance with Position C.3 of Regulatory Guide 1.29.
are located approximately two pipe diameters away from the isolation valves and are inherently designed to withstand post-LOCA differential pressures due to their rugged design and the negligible pressure drop through the screen material (No. 2 The screen
.063 inch wire with a 76.4 percent free area).
- mesh, material is welded over the 17-inch-diameter opening in a \\-
inch-thick flange which is bolted into place.
The purge isolation valves and debris screens are located adja-l cent to the containment wall, outside of the secondary shield and are protected from missiles which could be postulated
pipe diameter away from the screens on the containment side.
T1.ese dampers and the connecting piping provide additional pro-tection for the wire mesh screens.
CONTAINMENT COOLERS - See Section 6.2.2.2.
HYDROGEN MIXING FANS - See Section 5.2.2.2.
ISOLATION DAMPERS - Where a means of system isolation is The required, parallel-blade-type dampers are utilized.
type of operator employed is dependent upon the specific design and/or usage; requirements.
FLOW CONTROL DAMPERS - Opposed-blade-type dampers are utilized, In as necessary, to provide a means of system balancing.
However, some utilize gcneral, these are manually operated.
power operators to allow compensation for changes in system resistance occurring during system operation.
BACKDRAFT DAMPERS - Backdraft dampers are employed, where l
required, to prevent system backflow.
TORNADO DAMPERS - Tornado dampers are employed where isolation from the effects of extreme wind or tornado conditions is These dampers close with the flow produced by the required.
differential pressure associated with the tornado or high winds and are considered passive since they do not have actuation devices.
9.4-68
SNUPPS PIPING - The piping of each spray header contains a test connection.
Air can be introduced into this connection to Check valves immediately upstream verify spray nozzle flow.
of each spray ring header prevent system contamination due to pressurization in the containment and provide containment isolation backup protection.
A containment spray peep test line between the pumps' dis-charges and the RWST is installed for periodic testing.
6.2.2.1.2.3 System Operation The CSS has two phases of operation, which are initiated sequentially following system actuation; they are the in-jection phase and the recirculation phase.
INJECTION PHASE ihe CSS is actuated either manually from the control room or on the coincidence of two-out-of-four contain-ment Hi-3 pressure signals.
Both containment spray pumps start and the motor-operated spray ring header isolation valves open to begin the injection The same coincident signal opens the motor-operated phase.
additive eductor suction valves to the sodium hydroxide tank.
A summaJf of the accident chronology for the containment spray system is provided in Tables 6.2.2-3 and 6.2.2-3a for the injection phase of a LOCA and MSLB inside the containment, respectively.
The containment spray pump inlet nozzle, located at El. 1,970, takes suction from the RWST, located at El. 2,000'-6",
through More than 95 percent of the pump dis-locked open valves.
charge is directed to the containment spray ring headers.
the These headers are located at elevations up to 2,201 feet, highest practical level to maximize iodine removal (discussed The headers are located outside of and in Section 6.5.2).
above the internal containment structures which serve as missile barriers and are thereby protected from missiles The remaining portion of the generated during a LOCA or MSLB.
containment spray pump discharge is bypassed through the spray additive eductors where it is used as the motive flow to draw the spray additive solution from the containment spray addi-tive tank and direct it to the containment spray pump suction.
The containment spray additive tank supplies the spray addi-tive solution to the eductor through a motor-operated valve.
Further discussion of the operation of the spray additive If the level in subsystem is provided in Section 6.5.2.2.3.
the NaOH tank reaches low-low prior to switching to the recir-culation phase, the spray additive tank isolation valves will be automatically closed to prevent N from being drawn into 2
the pump suction.
Rev. 7 6.2.2-6 9/81
~
SNUPPS On coincidence of two-out-of-four low level signals from the the emergency core cooling system RWST level transmitters, (ECCS) pumps switch suction to the containment recirculation The low level setpoint sump, as described in Section 6.3.2. usable gallons remain in the RWST.
indicates that 120,000 Switchover for the spray pumps is manually initiated when f,
the low-low level in the RWST is reached.
The low-low level Switchover ini-indicates imminent depletion of the RWST.
I tiated at the time of the low-low level alarm ensures that the system piping remains full of water and that adequate The RWST low-low NPSH for the spray pumps is maintained.
level alarms and level indicators inform the operator of the need to make this switchover.
The time length of the containment spray injection phase is given in Table 6.2.2-4.
These times are based on the minimum RWST volume and are given for credible combinations of minimum and maximum containment spray and ECCS operation The containment spray and runout flow rates of these pumps.
additive design flow rate is given in Table 6.5-2.
RECIRCULATION PHASE - The recirculation phase initlated by the operator manually shifting containment spray pump suction The from the RWST to the containment recirculation sump.
accident chronology for the containment spray system for the l
recirculation phase of a LOCA is provided in Table 6.2.2-3.
The RWST sr cien line valves remain open during the switchover to the rreirculation phase to preclude the loss of supply to the containment spray pumps in the highly unlikely event that the isolation valve in the recirculation line is delayed The operator then remote manually closes the in opening.
If the motor-operated valves in the RWST suction lines.
predetermined amount of spray additive defined in Section l
6.5.2 has been added, a permissive signal from the spray additive tank level switches allows the operator to remote manually close the motor-operated valves in the spray additive If supply lines to the containment spray additive eductor.this min reached, the valves cannot be manually closed.
The suction line from the containment recirculation sump to the spray pump is a sloped line which precludes air from The single valve in the containment entering the system.
sump recirculation line for the containment spray pump is The flow encapsulated and located outside the containment.
paths from the spray pumps are the same as in the injection Check valves are providad in the recirculation sump suction lines to prevent the establishment of a flow path phase.
between the RWST and the containment sump.
Rev. 7 9/81 6.2.2-7
d SNUPPS TABLE 6.2.2-3
SUMMARY
OF ACCIDENT CHRONOLOGY FOR CONTAINMENT SPRAY SYSTEM FOR LOSS-OF-COOLANT ACCIDZNT Injection Phase Time (Sec)
Action 0.0 Event, SIS signal, and start diesel generators.
Containment pressure reaches Hi-1 containment 3.0 pressure setpoint (6 psig), assuming worst case LOCA or MSLB inside the containment.
Time includes instrument lag time.
Diesel generators attain rated speed and 10.0 voltage, including actuation instrument lag time.
Hi-3 containment pressure setpoint (30 psig) attained.
12.0 Sequencer energizes motor control centers to open motor-operated valves in spray additive tank discharge and spray header isolation valves.
Maximum valve opening time is 15 seconds.
25.0 Sequencer applies power to containment spray pumps.
Slowest spray header motor-operated isolation 27.0 valves reach full open position.
Containment spray pumps attain operating 29.0 speed and design flow.
Flow is delivered to the containment.
l 560.0 When containment pressure drops below 30 psig, reset containment spray actuation signal (CSAS).
The worst case LOCA inside the containment is assumed l
NOTES: to occur at time zero.
Using conservative analyses, spray flow will be delivered to all spray nozzles within 25 seconds after the spray pump starts; however, 35 seconds is assumed for conserva-tism.
Rev. 7 9/81
TABLE 6.2.2-3 (Sheet 3)
SUMMARY
OF ACCIDENT CHRONOLOGY FOR CONTAINMENT SPRAY FOR MAIN STEAM LINE BREAK WITH OFFSITE PCWER AVAILABLE (CASE 6 AND CASE 12) (1)
Time (Sec)
Action Case 6 Case 12 Break occurs, blowdown from all steam generators.
0 0
2) 14.4 17.5 Containment pressure HI-1 setpoint reached.
Initiates SI. CIS-A, feedline isolation, etc.
Since offsite power is available, the load sequencer starts and provides power te the CSS containment isolation valve immedt tely and 15 seconds later ser is supplied to the containment spray pump.
(The CSS components do not actuete until CSMS is generated by a containment HI-3 pressure signal).
103.3 160 Containment pressure HI-3 setpoint reached. CSAS generated which simultaneously opens the containment isolrtion valves and starts the spray pumps.
107.3 164 Containment spray pumps reach operating speed. The flow rate has rapidly increased toward runout conditions as flow fills pipe. The resistance of the partially open containment isolation valve rapidly decreases as the circular vedge arises.
118.3 175 Containment isolation valve teaches the first open position. Runout flow rates are conservatively assumed as flow continues to fill the spray headers which offer little flow resistance.
d 133.3 190 All air is vented from the last spray nozzle as the headers become water
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solid. The system flow rate rapidly reduces from runout conditions to the design flow rate as the nozzles impose the design pressure drop shown on Figure 6.5-1.
1800 1800 MASS and ENERGY addition to the containment ends, containment pressure reduces. Containment spray may be terminated.
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II Table 6.2.1-58 provides information on 16 steam breaks analyzed for containment pressure and temperature analyses and includes the times at which HI-l and HI-3 containment pressures are j
reached for each case.
q (2)
As described in Section 15.1.5, low steam line pressure could initiate safety injection sooner than HI-1; however, the use of HI-l is conservative.
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FIGURE 6144 PAGE 70 OF 74 g
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