ML19341C577
| ML19341C577 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway  |
| Issue date: | 02/24/1981 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| SLNRC-81-011, SLNRC-81-11, NUDOCS 8103030770 | |
| Download: ML19341C577 (32) | |
Text
{{#Wiki_filter:.. ..- .- _. _ _ . . . - _ . -_. .- -. _- . -_ - - _ . . .. - . ._
- _.
'
- e'Ns i g\7 j
SNUPPS ff gI /I &
'
Standardised Nuclear Unit Power Mont System q
]/ pf , /J h s ch.h. ch.try R e 9 k s. IS8/ g Nicleofas A. Petrick i Roshwille. Meryland 20060 b~1 \
cd8% Enecutive Director (301)seewoo1o 4 % %.' 7
%*>
T;7 . j February 24, 1981 SLNRC 81- 011 FILE: 0541 ,
- SUBJ
- NRC Request for Additional '
, Information - SNUPPS FSAR l , Mr. Harold R. Denton, Director -l Office of Nuclear Reactor Regulation i U. S. Nuclear Regulatory Comission 4 Washington, D. C. 20555 I Docket Nos: STN 50-482, STN 50-483, and STN 50-486 i
Reference:
NRC (Tedesco) letter to J. K. Bryan and G. L. Koester 1 dated January 7,1981
Dear Mr. Denton:
The referenced letter requested additional information regarding the SNUPPS FSAR. The enclosure to this letter provides the requested information. This information will be incorporated into the next j revision to the FSAR. 4 I Ver truly yours, 1 ~. b RN-<s c
; Nicholas A. Petri RLS/mtk Enclosure
,
cc: J. K. Bryan UE Sobl.5 l G. L. Koester KGE
/ !
1 D. T. McPhee KCPL
'
T. Vandel NRC/WC // f W. Hansen NRC/ CAL I l < i ' A 81os ann 770
- _ - -
- _- _
._- -_ - ..
-- _ - - _ - -_ . . - . . _ . .
n u. - - _-. _- __ ~ _
.-_-_ _ - -_ _ .. . - _ _
3
'
.
I. 4 Q450.00 , In your description of the control room htbitability system, include the j provisions for emergency food, water and medical supplies. 1 , RESP 0NSE
'
The response to this question will be provided in the Site Addenda. ' i - Callaway: A non-perishable food supply capable of sustaining 5 men for 10 days shall be maintained within the confines of the control room envelope. A supply of bottled water shall be maintained within the 1 confines of the control room envelope and shall be !
'
available in quantities sufficient to reconstitute any dried food and to serve as a source of drinking i
! water for 5 men for 10 days. Standard-man values shall be used for the drinking water consumption rate. , An emergency medical supply kit shall be permanently installed within the confines of the control room envelope and shall be equivalent to the M&A Stan--
dard Type D Unit first aid kit. Wolf Creek: Emergency supplies will be maintained on site to take care of the needs of 25 individuals for one d week. These supplies will consist of dehydrated, i frozen and/or canned food. Sealed containers of 4 potable water will also be stored. A standard 36 unit first aid kit plus an emergency stretcher will be available. I ! i
.
! __ i _ __ _ . , . _ . . _ _ __ , - ._
___ _ . - __ _ ,
.
- I .
l . Q450.01 In the evaluation of toxic gas protection, document
- - (6.4) the degree of leaktightness of the control room
- isolation dampers.
RESPONSE
The total leak-tightness of the control room and its poten-tial leakage paths are discussed in FSAR Section 9.4.1.2.3 under EMERGENCY OPERATION. The calculated total leakage with a 1/4-inch w.g. differential pressure is 80 cfm, of which approximately 95 percent is attributable to the d ?ors. The remaining leakage paths are both individually and c411ec-tively insignificant in terms of total control room leakage. Nonetheless, the following specific criteria were included in the control room isolation damper procurement specification to ensure that the required leak-tightness is provided:
- a. For dampers with a surface area equal to or greater than 2 ft2 , the maximum allowable leakage at a pressure differential of 6 inches w.g. is 20 cfm/ft 2 ,
,
- b. For dampers with a surface area of less than 2 ft 2, but greater than 1 ft2 , the maximum allowable leakage at a differential pressure of 6 inches w.g.
is 30 cfm/ft 2,
- c. For dampers with a surface area of less than 1 ft 2, the maximum allowable leakage at a differential pressure of 6 inches w.g. is 30 cfm.
Q450.02 Provide a description and drawing showing the j (6.4) locations of control room outside air inlets i relative to potential radiation releases.
RESPONSE
The control room has two sources of outside air. The normal l source of outside air is provided by the control building supply air unit which draws from the intake plenum located on top of the auxiliary building. This intake plenum is identified as an HVAC penthouse located between building column lines A-3 and A-1, and A-J and A-H on FSAR Figure i 1.2-14. The emergency source of outside air is provided by J the control room pressurization system which draws air from intake louvers located on the w.ast wall of the control . building. These louvers are shown on FSAR Figures 1.2-24 (grid H-4) and 1.2-28 (grid E-3). The relative locations of all power block buildings and the location of the radiation release points are shown on FSAR Figure 1.2-1. FSAR Figure 11.3-2 identifies the release points of potentially radioactive gaseous effluents. l
__ _ _ . _ ._
^
I l
-
.
The normal control building air intake is located approxi-mately 113 feet horizontally and 138 feet below the unit vent discharge point; 385 feet horizontally and 15 feet above the radwaste building vent discharge point; and 39 feet (nearest exhaust vent) to 318 feet (farthest exhaust vent) horizontally and 57 feet below the turbine building
- exhaust fan discharge points.
The control room pressurization system intakes are located approximately 243 feet herizontally and 202 feet below the unit vent discharge point; 339 feet horizontally and 49 feet below the radwaste building vent discharge point; and 185 feet (nearest exhaust vent) to 403 feet (farthest exhaust vent) horizontally and 121 feet below the turbine building extlaust fan discharge points. , Q450.03 In your analysis of toxic gas protection for Control Room Personnel, provide the number and type of respiratory devices, the type of operator training for respiratory use, the estimated time for donning or deploying , the equipment, the length of time the equipment can be used, the equip-
>
ment testing and maintenance provisions. l
RESPONSE
The response to this question will be provided in the Site Addenda. Callaway: Eight self contained breathing apparatus' stations shall be maintained in the control room envelope. In addition, 60 fully charged replacement air pack bottles shall be stored in the control room envel-ope. The compressed air bottles shall be placed so as not to cause damage to vital equipment or interference with operation if they fail. Operator training on these devices shall be in compliance with ANSI Z88.2-1980. Since respiratory protection equipment will be maintained within the control room, time required to don the equipment is mini-mal. The above specified equipment will supply air : for 5 operators for 6 hours. Testing and mainten- l ance provisions shall be in accordance with the manufacturer's reconinendations. l l W * %
. - - .
*
. Wolf Creek: i There will be 6 self contained breathing apparatus stored in the control room. An 8-hour supply of air, which indludes spare bottles for changeout, will be available. Standard annual respiratory protection training will be required and the equip-ment will be inventoried and cleaned on a monthly basis. It is estimated that the length of time for deploying and donning the equipment is 1 to 5 minutes. Q450.04 List the areas, equipment and materials in the zone (6.4) serviced by the control room emergency ventilation system.
RESPONSE
The control room emergency ventilation systems consist of the control room air-conditioning system, the control room filtration system, and the control room pressurization system. The control room air-conditioning system and the control room filtration system serve only the control room and the adjacent control room air-conditioning equipment rooms (FSAR Figures 1.2-13 and 1.2-25). The pressurization system serves the ESF switchgear rooms (FSAR Figure 1.2-24), the mechanical and electrical equipment rooms (FSAR Figure 1.2-24), the lower cable spreading room (FSAR Figure 1.2-25), the upper cable spreading room (FSAR Figure 1.2-26), and the control room air-conditioning equipment rooms. All major equipment located in those areas is shown on the above referenced figures. Q450.05 Discuss how the control room design precludes the (6.4) buildup of noxious gases from control room equip-ment such as gases from batteries.
RESPONSE
There is no equipment located within the control room boundry, such as batteries, which emits noxious gases. The only potential sources for the release of any gases into the control room are the discharge of the fire extinguishers, the discharge of the Halon system into the cable trenches and chases, and leakage of the control room air-conditioning unit refrigerant. The release of any one of these gases would not result in a toxicity level which would be hazard-ous to the control room operators. For a discussion of the control room ventilation, refer to FSAR Section 9.4.1. 1
-
_-_-
- -.
1 I I l l Q450.06 In Section 6.4.5, the testing and inspection of (6.4) the control room habitability systems is described. In particular, the last paragraph states: "The control room is classified as Type B per Regula-tory Guide 1.78. Since the air exchange rate exceeds 0.06 air exchanges per hour for the control , room, periodic testing of the control room pressuriza-tion system is not required per the exclusion provisions of the regulatory guide." Apparently, there is some confusion as to the applicability of Regulatory Guide 1.95 (and 1.78) to the control room ventilation design for radio-logical protection. For a control room outside air makeup rate during emergency pressurization less than 0.25 volume change per hour (as in Callaway), SRP Section 6.4 recommends the following: (1) acceptance test to verify adequate pressure, (2) supporting calculations to verify ade-quate air flow, and (3) periodic verification testing. If this guidance is not followed, justify the departures.
RESPONSE
- a. FSAR Section 14.2.12.1.45 provides a discussion of the initial test program for the control building HVAC system. This test program will provide assurance that the control room pressurization fans will maintain the control room pr'ssure e at the required positive pressure.
- b. Detailed design calculations for control room leakage rates and required pressurization system design condi-tions have been performed.
- c. The control room pressurization system flow rate for the SNUPPS control room is an optimized value, based on detailed design calculations, which provides acceptable protection for the control room operators during both radiological and toxic gas accidents. The pressuriza-tion makeup rate provides for approximately 0.24 volume changes per hour. Periodic verification testing of the '
pressurization system is, therere, not justified in l this case. j l l w== -
.
- d. During the PSAR review, the issue of periodic testing of '
the pressurization system flow was discussed in detail as open item B-8, " Outstanding Issues and Positions for I the Callaway Plant," for Supplement 1 to the Callaway SER. During a meeting with the NRC staff on June 26, 1975, the NRC staff agreed that periodic testing is not required for the SNUPPS units based on the adequacy of a 400 cfm pressurization flow rate. Refer to the NRC meeting summary dated September 8, 1975. Q450.07 In Section 6.5.2.2.3 of the SNUPPS FSAR, it stated (6.5.2) that the containment spray system recirculation flow is manually initiated. It is the staff's position that the containment spray switchover be automatic. Justify your departure from this position.
RESPONSE
The method of switchover of the SNUPPS ECCS systems and the containment spray system from injection to recirculation evolved from a totally manual design to one of limited and reasonable operator action during the PSAR stage. The current design provides for the automatic switchover to the recirculation mode for the RHR pumps followed by manual realignment of the containment spray pumps, the centrifugal charging pumps, and the high head safety injection pumps. The necessary indications and the sequence of events for the switchover of the containment spray system are described in FSAR Section 6.2.2.1.2.3. The sequence of events for the switchover of the ECCS systems is described in FSAR Section 6.3.2.8. FSAR Table 6.2.2-4 provides the minimum duration of contain-ment spray flow in the injection mode for the various assumed flow conditions. These durations provide an adequate time frame for the necessary operator actions required for ECCS and containment spray system management. The current design was found to be acceptable by the NRC at the PSAR stage and is the basis, in that regard, for the issuance of the SNUPPS cps. This design continues to be in substantial compliance with all published regulations, and we are aware of no regulations or technical basis for re-quiring automatic switchover to the recirculation mode. The thermal-hydraulic analyses provided in FSAR Section 6.2.1 and the radiological consequences of the accidents analyzed in FSAR Chapter 15.0 demonstrate the adequacy of l the existing containment spray system. I l w - .- . .
. _ . .
i 450.08 With respect to rod ejection accident, provide (15.4.8(A)) ' the transient time for the depressurization of the primary system to the termination of primary to secondary leakage. >
RESPONSE
'
Primary and secondary pressuret are egualized at 1100 seconds following the accident, thus terminating primary to secondary leakage in the steam generators. Refer to Figures 450.08-1 and 450.08-2. i
.
3 y -,-: - y
- -
- -
-- .- _ _ _ _
l Y J. -
.
l 1
-
i
.
0*0GLI
.
l *
.
-
.
f 0*00GI
' ..
.
-
.
.
l
.
.
'
,
- 1 l - ~~
0*0SZI l ,
.
- .
i, n u ...--
---
0*0001
$M mv 4
;
!, 1
.
m M > 'l u B 4 i w mc i i
$
QH ! ) 8 m m' id
' ; M 4o>N ,
i H H c4 I og ;. 0*054 -wm 4m i 1
!
w w I . nm : i < ow 1 1 I e ! I m o e
!
;
I
' 0*005
.
0*05Z
-
-
-
/ 7 ,
>
0*o 1
- o. o. o. o. o. o. i i
o e o o o o i I o o o o o n o e o n N N N N (Visa) aunssava sou
.
Os41
- 0*00S1
.
'
U w ' 1 0*05Z1 g H .
' .
.
$ .
I, w
- m5 '
l 0*0001 7 m d M. a
- w , h SzS i n v
4om i -wE m 9 o I
-- --- - - .
0*054
-
7-0$ e I e 2 1 I E O 0 00s f
.
%
- l I
r 0*0sz k
< l
--- --
0*0 d d d d d R 8
~
E
~
8
~
8
~
(Visa) aunssaud Auvan00as volVuaNaD mra15
_. .. . _.
- - -
450.09 The following information is currently missing (15.6.3) from the Callaway FSAR and is needed to ccmplete , our review. For the steam generator tube rupture accident provide the following figures: 1 (1) SGTR break flow rate vs Time (2) SGTR integrated tube leak mass vs Time (3) Primary system pressure vs Time (4) Secondary system pressure vs Time (5) PORV flow rate vs Time (6) MS Safety valve flow rate per steamline vs Time (7) Atmospheric dump valve flow rate vs time (8) Steam generator steaming rate vs Time (9) Reactor coolant temperature vs Time (10) Feedwater flow rate into the steam generators vs Time (11) Water level in the affected steam generator relative to the top of the tube bundle vs Time. Also, provide the mass of secondary coolant in a steam generator.
RESPONSE
Refer to revised Section 15.6.3. In view of the fact that the steam generator tube material is Inconel-600 and is a highly ductile material, it is considered that the assumption of a complete severance is somewhat con-servative. The more probable mode of tube failure would be
- one or more minor leaks of undetermined origin. Activity in the steam and power conversion system is subject to continual surveillance, and an accumulation of minor leaks which exceed the limits established in the Technical Specifications is not permitted during the unit operation. ,
The recovery sequence for a SGTR is discussed in Section 15.6.3.2.
- -
l
_ _
.
The operator is expected to determine that a SGTR has occurred and to identify and isolate the affected steam generator on a restricted time scale to minimize contamination of the secondary system and ensure termination of radioactive release to the atmosphere from the affected unit. The recovery procedure can be carried cut on a time scale which ensures that break flow to the secondary system is terminated before water level in the affected steam generator rises into the main steam pipe. Sufficient indications and controls are provided to enable the operator to carry out these functions satisfactorily. Consideration of the indications provided at the control board, together with the magnitude of the break flow, leads to the conclusion that the accident diagnostics and isolation procedure can be completed within 30 minutes of accident initiation for the design basis event. Assuming normal operation of the various plant control systems, the following sequence of events is initiated by a tube rupture:
- a. Pressurit - low pressure and low level alarms are Octuated aim 'rging pump flow increases in an attempt to ma pressurizer level. On the sec-ondary side, tnet, ' steam flow /feedwater flow mismatch before trip a. ' -edwater flow to the affected steam generator is reduceo ' to the additional break flow, which is now bein, ;ptied to that unit.
- b. Decrease in RCS pressure (Figure 15.6-3a) due to continued loss of reactor coolant inventory leads to a reactor trip signal generated by low pressurizer pressure overtemperature at. Resultant plant cool-down (Figure 15.6-3B) following reactor trip leads to a rapid change of pressurizer level (Figure 15.6-3E),
and the safety injection signal, initiated by low pressurizer pressure, follows soon after the reactor trip. The safety injection signal automatically terminates normal feedwater supply and initiates auxiliary feedwater addition.
- c. The steam generator blowdown liquid monitor and/or the condenser offgas radiation monitor will alarm, indicating a sharp increase in radioactivity in the secondary system, and will automatically terminate steam generator blowdown.
- d. The reactor trip automatically trips the turbine, and if offsite power is available the steam dump valves open, permitting steam dump to the condenser. In the event of a coincident station blackout (loss of offsite power), as assumed in the transients presented in this section, the steam dump valves would auto-matically close to protect the condenser. The steam generator pressure (Figure 15.6-3C) would rapidly increase, resulting in steam discharge to the atmo-sphere through the steam generator safety power-
.
I operated relief valves. In Figure 15.6-3F, the steam flow is presented as a function of time. The flow is constant initially until reactor trip, followed by turbine trip, which results in a large decrease in flow, but a rapid increase in steam pressure to the safety / relief valve setpoints.
- e. ,Following reactor trip, the continued action of auxiliary feedwater supply and berated safety in-jection flow (supplied from the refueling water storage tank) provide a heat sink which absorbs the decay heat.
- f. Safety injection flow results in increasing the pres-surizer water level (Figure 15.6-3E); the rate of which depends upon the amount of operating auxiliary equipment.
15.6.3.2 Analysis of Effects and Consequences Method of Analysis Mass snd energy balance calculations are performed to determine primary-to-secondary mass release and to determine the amount of steam vented from each of the steam generators, using LOFTRAN (Ref. 1). In estimating the mass transfer from the RCS through the broken tube, the following assumptions are made:
- a. Reactor trip occurs automatically as a result of low pressurizer pressure or overtemperature At. Loss of offsite power occurs at reactor trip.
- b. Following the initiation of the safety injection signal, two centrifugal charging pumps are actuated and are assumed in the analyses to continue to deliver flow for 30 minutes.
- c. After reactor trip, the break flow reaches equilibrium when incoming safety injection flow is balanced by outgoing break flow, as shown in Figure 15.6-3. The rasultant break flow is assumed to persist from plant trip until 30 minutes after the accident. No operator actions are assumed.
d ., The steam generators are controlled at the power- I operated relief valve setting. )
- e. The operator identifies the accident type and termin-ates break flow to the affected steam generator within 30 minutes of accident initiation.
The above assumptions, suitably conservative for the design basis tube rupture, are made to maximize doses and do not explicitly model operator actionr for recovery. 1 1
.
Key Recovery Sequence The recovery sequence to be followed consists of the following major operator actions:
- a. Identification of the faulted steam generator
- b. Isolation of the faulted steam generator
- c. Assuring subcooling of the RCS fluid to approximately 50 F below no load temperature
- d. Controlled depressurization of the RCS to a value equal to the faulted steam generator pressure
- e. Subsequent termination of safety injection flow Results Figure 15.6-3 illustrates the flow rate that would result through the ruptured steam generator tube. The previous assumptions lead to an estimate of 89,240 pounds for the total amount of reactor coolant transferred to the secondary side of the faulted steam generator as a result of a tube rupture accident. The integrated steam flow is 61,700 pound released through the safety / power-operated relief valves.
The folloving is a list of figures of pertinent time dependent parameters: Figure 15.6-3a - Core Pressure Figure 15.6-3b - Reactor Coolant System Temperature , Figure 15.6-3c - Steam Generator Pressure (Faulted Steam Generator) Figure 15.6-3d - Steam Generator Temperature (Faulted Steam Generator) Figure 15.6-3e - Pressurizer Water Volume Figure 15.6-3f - Steam Generator Flow (Faulted Steam Generator) Figure 15.6-3g - Feedwater Flow to Faulted Steam Generator Figure 15.6-3h - Faulted Steam Generator Safety / Relief Valve Flow Rate Figure 15.6-3i - {aultedSteamGeneratorBreakFlowRate Figure 15.6-3j - Steam Generator Mass Figure 15.6-3k - Faulted Steam Generator Liquid Volume
.
The DNB calculations performed with LOFTRAN (Ref.1) indicate that DNB limits are met. In Table 15.6-1, the sequence of events are presented. These events are the normal plant response to the normal plant setpoints. Loss of offsite power at reactor trip and no operator actions were assumed. 15.6.3.3 ' Radiological Consequences 15.6.3.3.1 Method of Analysis 15.6.3.3.1.1 Physical Modr' The evaluation of the radiological consequences due to a pos-tulated steam generator tube rupture (SGTR) assumes a complete severance of a single steam generator tube while the reactor is operating at full rated power and a coincident loss of offsite power. Occurrence of the accident leads to an increase in contamination of the secondary system due to reactor coolant leakage through the tube break. A reactor trip occurs auto-matically, as a result of low pressurizer pressure. The reactor trip will automatically trip the turbine. The resulting sharp increase in radioactivity in the secondary system will be detected by radiation monitors (refer to Section 11.5), which will automatically terminate steam generator
- b. The noble gas activity in the reactor coolant is based on 1-percent failed fuel, as provided in Table 11.1-5.
- c. The secondary coolant activity is based on the dose equivalent of 0.1 pCi/gm of I-131.
The following assumptions and parameters are used to calculate the activity released and the offsite doses following an SGTR:
- a. The total amount of discharge of reactor coolant into the .econdary s system through the rupture is 89,240 l pounds.
- b. It is assumed that 17 percent (Ref. 25) of the reactor coolant that flows to the affected steam generator flashes to steam and is immediately released to the environment. No credit has been taken for scrubbing.
- c. The 1-gpm primary-to-secondary leak is assumed to occur to the unaffected steam generators.
- d. All noble gas activity in the reactor coolant which is transported to the secondary system via the tube rupture and the primary-to-secondary leakage is assumed to be immediately released to the environment.
.
- e. At 30 minutes after the accident, it is assumed that the RCS and steam generator pressures are equalized and below the steam generator relief valve set pressure.
Thus, the affected steam generator has been totally isolated, and all primary-to-secondary leakage has been terminated to the unaffected steam generators.
- f. The iodine partition faction between the liquid and steam in the steam generator is assumed to be 0.01.
- g. The steam releases from the steam generators are assumed to be as follows:
Affected steam generator (0-30 mins) 61,700 lbs Unaffected steam generator (0-2 hrs) 454,000 lbs Unaffected steam generaeor (2-8 hrs) 1,200,000 lbs
- h. Offsite power is lost.
- i. Eight hours after the accident, the RHR system is assumed to be in operation to cool down the plant.
Thus, no additional steam release is assumed.
- j. Radioactive decay during the release of activity is conservatively ignored for all isotopes, except for the following which have extremely short half-lives:
Kr-89, Xe-137, Xe-135m, and Xc-138. No decay during transit or ground deposition was considered.
- 18. Letter NS-TMA-2014, dated December 11, 1978, Anderson, T. M.
(Westinghouse) to Tedesco R. L. (NRC).
- 19. Johnson, W. J. and Thompson, C. M., " Westinghouse Emergency Core Cooling System Evaluation Model - Modified October 1975 Version," WCAP-9168 (Froprietary) and WCAP-9169 (Non-Proprietary), September 1977.
- 20. " Westinghouse ECCS Evaluation Model Sensitivity Studies,"
WCAP-8341 (Proprietary) and WCAP-8342 (Non-Proprietary), July 1974.
- 21. Salvatori, R., " Westinghouse ECCS - Plan Sensitivity Studies, WCAP-8340 (Proprietary) and WCAP-8356 (Non-Proprietary), July 1974.
- 22. Johnson, W. J., Massie, H. W., and Thompson, C. M.,
" Westinghouse ECCS-Four Loop Plant (17x17) Sensitivity Studies," WCAP-8565-P-A (Proprietary) and WCAP-8566-A (Non-Proprietary), July 1975.
- 23. Letter NS-TMA-2030, dated February 12, 1979, Anderson, T. M.
(Westinghouse) to Denton, H. R. (NRC).
- 24. DiNunno, J. J., et al., " Calculation of Distance Factors for Power and Test Reactor Sites," TID-14844, Division of l Licensing and Regulation, AEC, Washington, D.C., 1962.
l
- _ . .
- 25. USNRC NUREG-0409, " Iodine Behavior in a PWR Cooling System Following a Postulated Steam Generator Tube Rupture Accident," by Postma A. K. and Tam P. S., dated January 1978.
.
TABLE 15.6-1 TIME SEQUENCE OF EVENTS FOR INCIDENT WHICH RESULTS IN A DECREASE IN REACTOR COOLANT INVENTORY Time Accident Event (sec) Inadvertent opening of a pressurizer safety valve Safety valve opens fully 0.0 Overtemperature AT reactor trip setpoint reached 13.8 Minimum DNBR occurs 15.0 Rods begin to drop 15.8 Steam generator tube rupture Tube rupture occurs 0.0 Reactor trip signal 253.1 Rod motion 255.1 Feedwater terminated 255.1 Steam generator safety / relief valves opened 258.0 Safety injection signal 434.6 Safety injection 459.6 Auxiliary feedwater injection 496.0 Operstor takes actions to isolate and cooldown 1800.0
. _ - - - -
_ _ .
. _ _
TABLE 15.6-4 PARAMETER USED IN EVALUATING THE RADIOLOGICAL CONSEQUENCES OF A STEAM GENERATOR TUBE RUPTURE (SGTR) I. Source Data
- a. ' Core power level, MWt 3,565
- b. Steam generator tube 1 leakage, gpm
- c. Reactor coolant iodine activity:
- 1. Case 1 Initial activity equal to
'
dose equivalent of 1.0 pCi/gm of I-131 with an assumed iodine spike that increases the rate of
-
iodine release into the reactor coolant by a
-
factor of 500
- 2. Case 2 ?.n assumed pre-accident iodine spike, which has resulted in the dose equivalent of 60 pCi/gm of I-131
- d. Reactor coolant noble gas Based on 1-percent failed activity, both cases fuel as provided in Table 13.1-5
- e. Secondary system initial Dose equivalent of activity 0.1 pCi/gm of I-131
- f. Reactor coolant mass, lbs 5.3E+5
- g. Steam generator mass l'.089E+5 (each), lbs
- h. Offsite power Lost
- i. Primary-to-secondary 30 minutes leakage duration II. Atmospheric Dispersion Factors See Table 15A-2 III. Activity Release Jata
- a. Affected steam generator
- 1. Reactor coolant dis-charged to steam gener-ator, lbs 89,240 i
_ _ . TABLE 15.6-4 (Sheet 2)
- 2. Flashed reactor coolant, 17 percent
- 3. Iodine partition factor 1.0 for flashed fraction of
. reactor coolant
- 4. Total steam release, 61,700 lbs
- 5. Iodine partition factor 0.01 for the nonflashed fraction of reactor coolant that mixes with the initial iodine activity in the steam generator
- 6. Isolation time, mins 30
- b. Unaffected steam generators
- 1. Primary-to-secondary 250 leakage, lbs
- 2. Flashed reactor coolant, 0 percent
- 3. Feedwater flow rate, lbs 0-2 hours 441,000 2-8 hours 1,253,000
- 4. Total steam release, lbs 0-2 hours 454,000 2-8 hours 1,200,000
- 5. Iodine partition factor 0.01
- 6. Isolation time, hrs 8
- c. Activity released to the environment *
- 1. Case 1 \
Isotope 0-2 hr (Cil 0-8 hr (Ci) I-131 6.53E+1 , 6.58E+1 I-132 1.12E+2 1.12E+2 I-133 1.28E+2 1.29E+2 I-134 1.34E+2 1.34E+2 I-135 1.07E+2 1.07E+2 Xe-131m 8'.10E+0 8.10E+0 Xe-133m 4.44E+1 4.44E+1 Xe-133 2.21E+3 2.21E+3 Xe-135m 2.70E+0 2.70E+0 Xe-135 1.34E+2 1.34E+2 Xe-138 8.20E+0 8.20E+0 Kr-83m 1.02E+1 1.02E+1 Kr-85m , 4.78E+1 4.78E+1 _
. - - - - ._ -
, l l l j TABLE 15.6-5 y l t RADIOLOGICAL CONSEQUENCES OF A l STEAM GENERATOR TUBE RUPTURE *
- Doses (rem)
.
Callaway Wolf creek
- 1. Case 1 Exclusion Area Boundary (0-2 hr)
Thyroid, rem 9.7E+0 7.3E+0 Whole body, rem 5.6E-2 4.2E-2 Low Population Zone Outer Boundary (duration) Thyroid, rem 1.3E+0 1.0E+0 Whole body, rem 7.3E-3 5.9E-3
- 2. Case 2 Exclusion Area Boundary (0-2 hr)
Thyroid, rem 5.5E+1 4.lE+1 Whole body, rem 9.3E-2 7.0E-2 Low Population Zone Outer Boundary (duration) Thyroid, rem 7.1E+0 5.7E+0 Whole body, rem 1.2E-2 1.0E-2
*The effects of the revised primary-to-secondary mass transfer and the effects of the revised secondary side release on the activity released to the environment are being evaluated. The cevised activity releases and radiological consequences of a steam generator tube rupture will be provided in a subsequent revision of the FSAR.
.
l
.
6+ +me
-
e-gmy .g
,. .. - .. . . _ . . . - - . _ _ _ - - . - - . _ . _- -, - - _-. = - = . - - - . - . . - . . - _ _ I I, .
.
. . 6= - --
7 . ;- -- - =.EU =3 ( =1 g g :1_ ^ .L=uf-ET.-Mi=i=q,.:==i =..= 1gs _ :_ 1. - - -
'
~.:-
. _. . . =.. -:- .__ ;= . - _._._-,..__y.._....__
L_.
._ . _ .
;- ._ ; . _ . . . . . . . ' - _ :_ p _.__ .a.r.-.c...-..=..=n.-_=.=_.._==,;=.a . _ : . . .. . :_
. . . . . . . . _ _ _ . _ _ . . .
-- ..._: :. n . :._ .. :. ..: _ . . . _ .
l:-l .-f.-:. .r~_._ ' n~ u.; W-d:# O E- r _. i :!.- M := = M "=-f :- . D .'ii
~ .p.,..x_...=.
- - . . .. . ._._up.--:.-. :}:.. _. . _.. - . . . _ . _.- _. __.. . ._ . h. . .. . p+ _:_-5 ~-b._:.:@_%ff
.
, . _
- ~
-
.. . - _ . _
,:.. .. .
; . . :. =. _. ; = =m := . m:= . .T.=.=_r........_=4. =. . _- :t..=_ _=. .. . ]=. . .=_
_ . . . . ;-._ _.:.&_:
.. .:} ._ . .
- '- ...? -
^.: = ?--- .: *
~~.: . . _
--
.
-
h'. L ". . . _= v2- .- _ _ .. . _. _ _ ._._ ._=_. _
.
.. '
_._ .__ _. .._ _ . . _ _ _ _ _
- -
. r . - . " :. -- r .--
_ . . _ . .
; ; . : :L ... _ L .: .17
..: : - .:.;.~::=.=. ._
r r . -. . . . . _ . - _ . . :t= : - - - t=n -j=- =- *::- r _.y
- - - - - ---' - -
.__..3.
-- -
- -
q:.u. _ a : :[=.------"--4
- - - - ~ - .=: x =r .3
- ._.. =
i ' *:, 1 ._. * :' l. *:).:. Q@ &_= : f_:j~~ h[- _'.}.}' ~~@Eiii~.;:,1Q.Q:.#j~5_" Q::=1=f.=]_[.[:.= ." =~~f}f:[-Q~.(f- _.
.g.....
_
.,
' m ?, g _. ...._?---.__._
. . . . = _ . - _ . .
.. . . . . _ . ._ ._
. . . . ..
. . ._ ._ - m. = _ _: . . .g :- _- ,. - . : q
. . . . . . _ .
. .; : . = . . _ .,g. _ . _ _ . --
.
.r-- . .v. - - -- -- . , .
l .e : j . ---. _*. . .:. t r_ - -e .- - _r .u_
, .
-- --- - - -- - - - -- -- --
-- - - -
> u_
- ... :. . . a:_ ._. 2 = l : :. . . k.== . :. . - : :- . _..:>=:=
*_.' .=.2=._.=.=_t. t..: .u. = a...n-~ y:: . s>. = ::1. c.
. =.1'?:
- 1. =. . . . .:-- . ::. - - p .:.: :-- M . t-_ i. == :- == : - - : : - .: s _ 2. .
p....... +- . -. . . . =_. - p* .:r :.r.v- . -k .%=. i . . = . .p. . - -I ---I_...__... q... s,
.
g>;c*-. : , -:=-- _ 1=..-- ..=.1.
-
- -
. r ::. :
t=- .. . ._ a. _ : = 1-
- l ...
- U_11.s _ NC - -n . -FL_%. . . . . . n .a. . . u, ._ . . . .._ ,-- . .. _._ - - - - -
~t.. -r _~_ .h;~M.tM.- _. - _il"u;AL.ICHAR ,T -4 -
i _ . = . _ . _ ._ .. =f.2. 3T. A i , &_ t.R12htW - - - - [=- __:. =4 =_. =.: _.1 =. =._ =. =. . y =. _:. J. Ic-. _--t :_ .p .t;.------ Ir:- . -g
.
, - - .
= =. u :=.y#=._ .-.-
- - -- t - _. _.
=~-& =-- c.4-- - _ . _ _.r"-- [=--- 2r -if --M' -
_ _ =r-- - - r - 4
! ; :-= =t= : .P::.gfeg.9. .. . . _ _ =-t-
_
-
= ==t:= tra_
-h --- = - t "
~3._----
-
- . = ; =: - -m % = = =;=. =--
r _:&-. .
-
j
. =: - ~ - = ,.; .== --t: = -.----T.-----n. w ___4 h- - : _~ _w- . =_=+t== - - - _ _ . : :
---
.:==
--=- :. i . :.== r --S+ :=-- ==t1.==: ---- . r- -- - .__. . .;=- - -* \~m.mp. _ 4 --
r - = t . -- d _ _ _ _ -- =t- . X N . . _ --
-
w a _ _ . _ .*- 1=_- :..-._ms. --_ .. .._ - r- . a ' _
- -~-
- = = a == . :==*=== --
_,12.: p-- -- - :.:== =.' =j_-- - ~-* ---- ' ~~ 2m:-~ --
--^ ~ ~ - ~* ~ ? -
"'~-
Z~*>~'- -- -# ~ ~ - ~ - ~
" * - - #'2 -----"
o. u
,. "_
== x =:
. -
-
"P L : %u =.:. :9 Mt .=
-
-- = =_=.----r.=.=_==a
- = =t- .= =.'- t=* =t z.:1.
- t- ,- -- :~~+ - -
= 12- m =t=m . p===t--
-
=L T=L_ .-- -
w-- - -
- --* :=-t- ~~t=- ?
. -- -- ---.;=-*--*====t-_T.,=--__-.----~ _ - - ~ =
- :r_-+-
c =rt-_ = _ a _ qd._._:-._.-= . .. . __. __ p :: t= 2.:
- == .=g. .- =p==.==
. .: - . :== - 7= s1._-
-
. _ . _ . . . _
M : - W=====.r=r
- F - ---v - - .= --+--V= R-~~ a- :- --
E=: ==- :=_-- . . t . :::. . y :~. =- -
- _
- - =: = = - = t _ . . a - _--t-- - _=__ . ._c.N n[:__ u-- == __._. - ..A
._.- i =:=t ==- j. -- _ ,. _n- - - - - - :==r ..
j:
._
7m- ---M L _..._. - _ = ::;:= - -~-- ~:-+---+--- L: - ; p=_ =_~* t = .. . r t.q _ u== ===
. .":=t : r:; -=_= u:= =. m =r==z =;- = L_- ._ _' __= ht_ .___ ._ ._ t- : = r.-
6=.;.- ! - - t-- - -- __4_.__ __._ u__ _ = =__i_ _ -
.- ~ ~ ~
.- _T__. :_t- -
f n- =: :-- :.-
--- --
[=.- =.._4=
. : ..tp = n=ter.---
,. : :- .-2::::=. ~- }_= = : :=~2=+--*.- -- - " - -- w - - .-~ - =t ~:--- .-- f .::._.L.. _. ===7 u..._____. __u__.
--
._ : : s : =~_ y _- --2 -= = : : : g=_ .= s = = :;= = :.t =: == = --R&==; = =t ,= : - - ------ --4 +. -- _ :.t _ _ - -
_= ,a . 2. _. 4 c _ __a __=- - -- -
=. = 1 = .
-
.
=. = =:1 = ._ ,_ - _ 4---- --
_- ..-===: ._.
>
_ _. \m --: _r- : ==r
-
== ==
--
_=<=
=: m :. =:=:_
.
= q;.:=. .===_re_ : = .:=- -~ ..r.=_ =.== \===m- =r. :rt . -=-21 -r= = rr_a. . . . =. : : = k . . =~ L _ . . t=. __ __.a___.__-..
c = =i=: =1-
- r__=_.
-
r--- l= t _J =.1----J.
- ::= .t =
. , . . . .
r, r=__-f n ;.: f_..- =t::: ===n
~_.__ n 0 n y : -- '- :=._ . . . _ . . _ . _- . "1 r===7::f
-
1- --=r:-:=\ r' = .=21.= _
. . . _x. r- - +-f = __.; r_ . .t.;=4 ,
j
=..
j t a.
. ( * - - 1 3 .- * - := == '-
---+-_.? =.=r=__-: t.. .._l rm_- _-_- - - =h.: r t. p-=_=__ _i\_~_==.h.: :=__-
.._ . . . ___ - - . T _ . _ . . _ _ _=.=t . . . _ _. _: :_r ==d d
._..._..*..._-.___ _._.___._.3.___,._'_1._.._,_____, -
,
-
} =__.t . .: t. _ ;. .: .,A" :_=. .= _ =. .=. f.__=_r_ .__._3.-._y_._.:.t._.-.-
, _ _ ._. . :___ =1:.. :__=.l=_ .. _:_ - _. . . . .
. _ . .. . _ . _ _ _ _. f,/_.
. _._.___,__._.=.r_:..---i--.
__._
. _ _ _ ._. __ __a__.__ . _ .. . c _ n_._
-- -* - - - - - -
- =_ j J ,
[=.=_.=- -- tu- l_ . :=?} n .c.. : =. t.=. :=- :.=- 2 .= r { - - - - ---- - 4=. .; 1 ==_. _ +t -- _b; .W - :-+t=r --^ _- =t - -- :-- -
-t - ;. __~
=t._.._---_.a_.
. . _ _ _ _ _ 8=__
,
j _ _ _ _ . _ ........ _ _ _ _ _ . _ ..L- :-__p. =_== f _ .*
'
, ..
I _.__.4_ _ _ .g.._. ..___.._ (. _ _. , _ . P t .. , . . .
..
'
.._._._.y._..-..._.....4...Y...-.
_ _ . . _ _T_.._..:~_~~_--.__'..S. _.. _ . . . . .-_ '_._ .=*. . _ - ' .. ' : ). _. _.=j=_. ~ 4 = ._ _=_, _ _ $ 2 _ -_ * ' _ _ L- . _:: _ . _;.=a. ._- ._, _
;
s t == = :- =: =Lr==. =-- /- !._ r_=_2.-- p .: ---t. - ~ t -
- p. -_- 3. - -- . .._.-4: _
;
-
}
.
-
c. p_ - . _. :..S _
- _m.
t .-. e==
.__a / c w y
- ===. .=_ .=.rt
.=_.._.-.. -- =~ r =_~=t;---- ._
.
. ==x=. .=k==_.> -.
__ :-- _. =tr.Jz _ _ _ ._- _=_-;=
- ~ag. = =.1
.
f
}
. ,__.:..
$ _.
-
=: .-
. _ _ . _ ._ : .T ;m.1 _."_: . -
_ .. a.:._ . .. _;. _=_ _rj_- _-. _ =. ._ ._=f.=.
; : - _=_::t =_= ..
8 _. , - ___.t___._r___. . . g-;_-2.
.
_-.j.. _
.=_._.r..- _.4.,_. .. _ r_._ F-,,.-. :
- 7. b [*~ -]- ~~
~
~
*
[.* '_. - * --[kE f
--
5f r -f=b d,- - *5f.= _ _ } _ -[ e m. . _ _ _ . . _ _ _ . _ , _ _ _ . , _ _ _ . _ _ _ .._ .,_. __r._____,._. _ __.w __'-
"s ,-.--...--_Q=._=.. ; a. =.. =._~..~.~=.4'.._:__=_.j._.'.=_%.==.=_=_.,:_*_=,4=.'.g=___~.'_._^*--'_~.y-_=.=_.y,_.._'_~_.y
-. .
. . , >
-
_1~_~_=_ . . . . _ _, , f,f j.c.y .*;! - g @ q~-- .
; .~=.p = [ 22 % - @ .2_ h '_. $ (_ ~ [ g =^[ %[.- Q-M ~-i.-- y _;.==.'jf. ~( ~T .g g
{ U L= ' = Ee .c._. c. =n - s= =3 i
, =. :m ==- .== r=
tid =4=Q=dEM/d=lE-4 ==Ei=#i ==L=i_ =Wi===i=-Eist-s-#r#E_-f=i=f=?=_2==
% __p_ ==. =4
<- -
- - . .
. . ._ .=. =_ a..._.__..._..__...=__._=_.._:_=:_=..~..=..,____
.=.=.g: _ ==.:,.:..,pu_. -_ _a3 : :_ = j . _ _ ._r =:= .
l % T .._ t --,_- ,-
==:~._=... . . ..=.__
.
.
}t-- ==p:::=.
-
__t:f(r ==f _. _ r
.
.=_ . =_
.
- -- :- -..w._.._
lp ... _ . . _ _
,
; __q - - - r=n..T.*- ----p--=.-_:7h_.._..____.-_--
= - - = - - - ~ - - -. . _ _ . . . _ . _.._ 3 := ---- --- . _ y . ._
- - - _ . . j . . . .._ -- .p- . .-- p":. ::- ~-n . . . . j _-._ _4r v- ..- . -_a.
---- w-.. -:-
.
1 Cs- r- .- - - - + - - -
- .
-
*. . . :. .-- . . . . .. ( : ,J U . 7_? = = - = =:: ! *== ' -- ---- - .=u- . =-~;; = .== =.=: Q_ . =. . L' =.=_: _=-t_- w_- Cy.==; p _- _m---- s -
_ . ..--+y n = . **_ _ . . .=. 3- y =.__: : ._.__u=___. _..._
-
y -. . . . . _ . . ._ _,.=._=.=_=__-t-==;
.. .. _ . _ . .
. -
. . . , _ . _ . . .
...._.......;..___ _
.._.._
W: * - - L. :;_ 7. J_. =. _. . ! =_=_=. _. f. .=. ~~_- - Ma
- . . . . . . ..
'
/ ,' 4. .._-I"__-"__.3,_-_t_=-9-=;_-_--i__,_._3.._.%_._.;-'$.._=._,t=.=._*-_._.._..,
. .. m_ _
4
-
_. . . .. _ $
,. ,
-
* - -
..- ..- = -- r.=.m r :.=-
-
-', .- =-1 __ ;=_ = __ _r_ f_=1
-
- \ =:===.y_c== . . _ _b_._.,_ _ _ .__ ' .. _ 1=== r=.p ==._ t=:_m _=1_ =:.=w . . . u . . - ==- =__
.
-
t__c
< k, i
-_ .- . __ E==.=_-._ _. - . . _ . .
1 l
.", ...1....="; - .._. . = . . .. _ .. __. . . _. _ ..._
_
;
. _ _.:._._y_.: .-
..._.__.[..- r: . . -. _=. 9 =*_M.__.
_.
- - .
-' = r =j._ _..===&..__-_=.=_.k,_..=.,... .__:p_: .z:= s_ 0_ __ _. . ,_._j-...a...___
,_ . .
__ 7
=:_= q=n-._ .. ..\==;.mpwyrewppcys_cygg yprrge-mz_= --T,:_==
~ ----~-.-,--=-:==-:-.u.==._. - -
. .=. :- =w. . _:- f= =- n.
_=
- e.
'.
-
== _
_.._.._...___,_.,__._4__.__.r__.___.2=----==:r.--=.---rr-==. ,' p m.. ,.. ._ ,1 r y =- =----- - := 3_ __.,~ .___.___ :nng,.mgg gy=g ygy==-V:_t_ _ . . _ - = _ _ - _- - - -
. . _ . . . . . . _ _
-
_ = ,t-:= = _ .; ==m _ =:-. = _ = = .t -- ~- ._ , _ _ =.=r =~ , - > __ __ y=- -- ,
,
,
= . . =
. = = - == := :== 5==.= _ =2c== =:=== _ .
-s-===;_ m. -
._ r .. w == ._ i =:- m . __. .__
,
- --
--- -
r 1. 2 - - - =t=-
~-
~-
l mr. . : . :n== ; .= = : = ==== =- - =_ :-r_:_ =-=.=t = = : _g =_ =": ===.:._ m;,_- - r_=.p_= . . = ==;= m__r==:__:=~g_ ::= .;- , -
- '
s . _
=__
._
_ _ . _ r =:= r=_= _ ___.m t- ._ _ a~ __ t
..__..,._.__.--.._.___....__.,_f~.._f-.*._-[..._-n__..L.~.._..
_ .
. . _ . . . . . _ _ . . . . _ , _ _ . _ - - -
. . . _--_. f. *:; _ . =_: T. _=. .__. ^_ : *
..=..=..._._-4.~__...-. .. :t ::.:.
_ . ... _.. a . . . .g .. .._.y . . .y p p
. .
. . - . _ _ , _ . . .
. . .
. . . . I /=--::U. - .J . : = *. =: :7 : = ;- =. 11 = ;.=. . .= = : -r
--
=7.=w. == Tt.,.-=.t_==;=*..=.-:-- . _._:4_ _ _ =
- f}fy ::.- = :.;- L $'l f_=. .:. t- 4-- l y ^ . . - . 17 ., _
-r: - 1 = = ' T '. -' P'* :-- . y - M , .-1 -*- -'9 C- = 1 - :f[ : - -.'-*4---
.
- t:= n_
[ == ,< = .=
,.
= -:r=- . =;cn=; ,= - t. = u= .= _ i=r= ==m:==: .==.r=. -
= . = _- .1 - . -----=-_,_ :=_=_i =. == = r-; =- _ + ::-4: . =--.=i ;-n r = ~. = r =p=_1.,=__ .= +v_=- ._..a. =u ==-
=.=..!Pl== .T . ["*.A=1E/=_: W.U/'i / = d 55 3 .a 7;; = ;=J ' -- - 8 ~ ~.J =
,
I-..=-~~.:='.;...'.~i.l.*.=J-;_-- [ . = . =1 :n 1. .=:-~.= = : .m _= = s == ~. =: = =-- _ = = ._ =]* , --~ = F =.a=! ! ? .- ~ ~ ~ -- -^ ^~=== = 4. .:== n _- .4 p _p_-J.; =i=j;it5. :j;W_;T ;=Q$=2 f"=.jf=[:p= rp=p=fE-i =.T-r.~~=[U= q =_=-T 5% '"=if < [ :'.E. ;. . fir;
.
- k=- :: .L:-.- . . _ :::= =. = s .=_. = ._! --pgg_y=gy
-
. a .=753-w.. - . w =- xwAKWJD_nbnvwD=MA = = u . . := : = == = ~ : =.= 1S5 = =B. &= = = *= - +=.==; ="
-
, =1
, er9.
a + 4 :. : .- :. =. = : .= ===a F-.:,--m- . i _.- ..- - : - .=m == . c =:
- v -t t: == t = : t- m = e =u ---- =p- : =y. _:.~-F= :r a,I=u : :
- -==_ =__*---=t=---==.q.=;==._=.=,-==
.
/ \ <
i i--, a y an== ta.,=--iu.a. nam .. _ _ ,__ ....,w--o v g .e - ., . , . . _ - 3- . . 9 1 1
. , . . , . . _ . _ . . _. - . . , - - - ._ . . -. - . _ . _ _ _, __- . , , . . . . _ - ._
_ _ _ _ . _ _ . _ _ _ _ _. .. . _ . . _ _ ___ _.. __ _. , i 7/ i . i i i 7 t
.
FIGDRE 15.6-3A > CORE PRESSURE .
.
.
_ . . .. - . . .. a s a .
, 2 C.nn
... . n. . .
1, .
.
2000.0 - -
;
<
-
a m
$
c: 1500.0 -- D IM .
,
O w C:
'
w 1000.00 - - C" C U
.,
. .
i 500.00 -- l l. i 0.0 ' '
g:
.
l
.
o c) o O C.r .
.
. - C o C o o o o.
= O O V. m o 1D C =-* ~
+
1 * ,
, .
,
s .
.-
TIME (SEC) {' ,
, *
..s
- u, r.g
.
--> .* -
- c 7.-
. r 0, *
. .. **pr
-
- h ajW e.
*
.
~ '. 6 ' .* 2. 2 - .
.
.; e-
. - e, s . e . * . . '
i +* .. / . g - - 3 , i
. -
+ -. - w _s_ .p__, .. _. , , , - , . ,. .pm ._ .
FIGURE 15.6-3B REACTOR COOLANT SYSTDi TEMPERATURE
.
..d Cv .
-
eJw
#MA
'., $ --
P
.
/w_ lIC r LEO
- --L CCD LEG c ::a esa rJ w _.
A b O w EaJ E# w w b-
* =[O.
.
M 2 m k
'
g C"
.. u* .", ..
$
-
r. t' t ., Uw _
-
*; C R 60 * * .
-s. w- _e ,
C O . O D C O C c Q
- o o a m O C O - % l
- 1 1
TLE(SEC) l l
_ _ __ _ _ _ __ _ _ _ l l l FIGURE 15.6-3C FAULTED STEAM GENERATOR PRESSURE
'
1300 0 '
'
12:0.0 -- 1iC0 C'-
-
- 1. nm. -C . . .
A
<
m a.
- .: . ...C.--
.
$
= EP,3.CO -
w M w
-s w,
, . . , ,;-
600.0: -- c, ~, n . C ' . ' '
,
C 6 C d* C C g C C C O D O C4
. O O tru C - **
Q in
-
TIME (SEC) l [ l
l
FIGURE 15.6-3D FAULTED STEAM GENERATOR TEMPERATURE
-
rea EwV- Ww e n .. , 8 I eAA A . ! C.s GD # CR.9
. A .n O $E4 C
v I, *, S PO , w..- ws E
;5 m
, e a. ~~
% :.: es . G .s
*vs.nn
-n *w .
' '
- 2. :s . .v.CA. 6 6'*
.
6 o o . O O O o o o O C
. O O O C
"
C O O. TIME (SEC) l .
- -_ __ - ___ _ .__ _ _ _ _ _ _ _ _
l l 1 l 1 FIGURE 15.6-3E PRESSURIZER WATER VOLUME 1200.O i ,
\
,aaa~ e ,%
b%%% A O +
, . .e u - s v
g /
> E.c-
.a a 7
x W H
<
3
%
N 430.00 -- N
>.s M
C v3 t,/3 S!
~
200 CO -
. , .
1 U.0 . 0
-
C O
-
o
=
O O . O o O O O O Q
. O O O g
"
O D O.
~
TIME (SEC) 1 I l l
.
l . 1 l 1 FIGURE 15.6-3F FAULTED STEAM GENERATOR FLOW RATE
' '
1200 0 ' - 1000 CO -- c w-Lc.w nvk,J __
^
U W v3 hv2. ~ d U g a 3 4C0. CC -- S i
> >
200.00 - - I i
\
0.0 -) C
.
C O n
.
C C . C O O C C C o
- O O D %
~ %
O C O. TIME (SEC)
.
.. - . _ .- -. -. . _ _ - . _ _ . . _ .- . . . _ . . _ _
.
l l l l
<
4 .. FIGURE 15.6-3G FEEDWATER FLOW TO FAULTED STEAM GENERATOR * >
*...? ^ . . r,s
*-- :....*....._.
,
.. .
. -.
.
1000. CD -- n u w 8 .F * *, . v .* .. m s e a v .
.
w H g r w- *. 0 .i - - 8a
%
5 400.00 - H 4:
$
w w
- 200.00 -
_ 0.0 < :
'
s i c o e o o o
. . O. I o e o c
. O C Ln @
- ;
o n c-
-
1 ' TDfE(SEC) .
- INCLUDES BREAK FIDW
)
v
,n, ,- , ,, _
y _- - - - -. - ,.
FIGURE 15.6-3H FAULTED STEAM GENERATOR SAFETY / RELIEF VALVE FLOW RATE 3.:c :, . .: , .__.-...:-____.. - _ . . . _ . - . _
.
900.00 -- e, ,, _ www v. A [w 700.00 -- s
#lQ d E;;. C3 -
w H
- c. m a,
[ .m .-
.. . u. v .,.
3 o w
- ~ 400.00 --
w
>
d se- m
.'E w' . e
- w.
M i ! t 253. &C '- e
< l' vs 100.0C -
l
-
- 0. C
'
- .
.
o a o o o . o. o O C C o o Q
.
C o O in Q C C, - . TIME (SEC)
_ _ __ _ _ ____ _____________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _
. *
, f 4
1 E i l , k I
'
FIGURE 15.6-3I FAULTED STEAM GENERATOR BREAK FLOW RATE i !
i i I ' ,; c e c ; g .. .. . ! l E. V* 08.9 1 w.. kN 1
,
I
.
t
<
2 - m ( c.v n.ra
- w. __
! o w
V3
%
CI3 A
".'.fn
.s wsF.o,
.
4
& ,
B a - -,
- w C ,V . U Us . ~ ~
i 4
-
sc 10.000 --
)
' O.0
'
H E o O O o O O - O Q i O O O O %
. O O O to Q # ~
O D
-
. l TIME (SEC) i 1 i l l l < l l l 1 ' - - - - - - -
. .._...%a. . _ ... ._ .w..--- - -
, E
.. _
.
FIGURE 15.6-3J STEAM GENERATCR MASS
' '
3 3.00 : 2 50 <- n m m m 2.(h '* o
-
6 FA O: ~T*2 D
? STENA GGdE.*AYCR 1.59 .,
S
- ,1
,
'
g i.00 -- N' w < o UMAFFECTED Q N 5.CQ .. S~&AM GniJ2fATOR m
' ' ' '
0.0 . o O O o
,
I C O ,
. - C o O C C O Q
. O O O %
-
C o O %
# s TIME (SEC)
'
i
l l i I l i
-_ .__
._
, . . _ , . . - . - _ _ , - -
.- . . . _ ._ _ _- . _. .
. . * - . ~ . . . . . . ..-
- - - - -
_. , t e6
- O p :=_ i ---g--=.,.......r~- : = ::.r- ;=j - - j.r - I=r - =:.- .L. t =:; , _____{-- ._.p__..._ ? ---- t,._ _;.4.--t-~----i. :
-
5 f ,' O , . .r ; _ w u.._. ._ .4 x. -_.f--- =L : ;=52. . - *r;;.{ = - .:.:= . . ..t. . .. : . "
*-
__;g__..-._._...__..
-
i 1._.. . _ . - - . _ _. _ . . 1 b22
-
'
;=.;_ ."._;_.;;;=. . .~-_-w-
'.il-f'3_ _. .1----.=_ . ._ . _I. -
-
_ __M_ . N:#'U~12 _;_~_ L._y__. ___, -.__ _ _ -. . - _ .--- ,_ _.-. .. .- .. - ..- . ._ _ ,t_ =__ _ _ ; .-I_E_~'7 . ,, 'C_C.T.-{. 235 ct' ~.~-:-? . _. . I~!~-9'C2W-r _ , l,
'I
"
i
/
_ . ._ _ z_. = = =r__= ;:_- = L : =r - n: = _ t -t -- _- . __ =t= _ L ._ _2_n _ . .: __=s= == -=- =- -= - - -- - - - - - - - - - - - -
-
.__.___.._.___...._____..,.__.:___.a._g._____._.r=._~._..-.'_-__+.,_'._'T.._.._'._"_"t_'~r..1..__:_.'._----m'-___;.8._=rr;I 5E-'-- . _C7: E. _ .q _ _ _. . 4 *_ r . _
1--. .. _ _ a : - - -.L . . _ _ . . .
-'_7.=__ g. =_ . . . .F____R. . . .
. . .
- ;. ,
..__v._.n . _ . _ _ _ . .
z-
- . . . . =n -- . _ _. ____
, i :
..=_. __ .. _..;:=f. ..=_. :.c __ . . . _ ;__. r - . . __ __ , . . . i r - : t. _=. =
. .. .4. . -t.. .:.. _:_:2_2_1_ ._.__r.__,_. _ 'l,. _ - . g _ . - . _--.g
. - . . _::. .g . ._ _ L_ . =. : .._:: . ..
g_ ;__ . . .. {_=_ __*- .=. g=. *
._._._~_t=.=.._.=_.L_=__Q._.-_/.._.T_!_-=.1_-_".._=_._-_
.
____.__.;__
.
. .
.+
_
.
- _._- _.=_ g_ . .]_.g._.7 !_.! q . ._J U__g.
.
g.... J
.
.. . ~~~~_!_'
. . .
_ .:.1._ ,,. _.
.._.
_ __L.0.
=. _= , _ Z _I- .==:-
4.-...-e._,__
- . 1- _ 7.C
_. _ -- $.1_2. ._*=_J_- t . . _ ~2"..] ,;, ,
===._= :-- -z= r -=--==: - =---
_
=-==.p=:.: _- _. . _ . -- r-.==~-- ====+l
=
-
_.= = =: __ =.t ui_ . - - ==.: - : .=- _===1.
- - ~ = : =1
- _- JE =. t =. :+
_=__. p- - - - _ _ . _ =_== t r = :-L __ _ 3.
=.=. =_ _._y , . _ . . _ - . . _ . . _ _ _ _ . _ . _ . . , _ . . _
.
.
( . 7 . =:- t _ =-- ~2* = t- n t = = -- - - t =-- r '; . -". -. 12 . *
..__. z., _ - _. . ;;g.,
ta _ a = ; ___.;_g;._...-;.=-._._-..ma.;;.._ t----- t = - --- . _ = k *. t .5- 1 '- . . . . : ] ___;,
- _ . . -
- - k -- - ' - - ' ' - -
=.
- _ __=_: : ~l..T_-.. 1. '
_
- .".I.=_ s c=._=_=...:._._*_---
. _ _ _. .Q_._l..__.__..__.._.7-._.-__- ~'-*-'_-_.y,-':___~*t._._-_"._...-'.__.__L..__-~-~L..='.*g-.=.-".L..:_g'=.._--;
t,__ ..- _. .. . ..
.
.
y.. - _ .
- '- -
--- 6_r , , L.- =_IT J- ; :R- U . .LC-
==r. C' = gt= :' --
':- .r'-!.= !
.
;==__y ___{c_4.2.-
.,- =2 _J: __\.s* =. - = - - = - =. ._ - _. -t- .=m- f = =_. : :' sm. :-1-=5 = 4.=. =. =.x=----=--
= . = -
.
---t== _ - f,
-- ~ -- -
r._ e - :
=.r- . -
=ga=y.=_=-. _ . 3. _==mr
----
=-
=
=- - n ,_ m - t-
=.=_.. pw i__._g_ _.= r=_=.=ahr ----t _ _ _._= _ - _ _--
_ - . .. _- . _;
.
-- - ry= c __ _ , .--
_i_ __,;
, _ _ .
_a_ 'T . t.__. . _ c_ tr - .
-
..-*---+ =t; ,_ t __
g- -t X; + - - - -
- _ _ -:, -- - . ,- _y ; r*- -
--
= g;*-----r-----
Q __m -
- -
+--
A__2-2 . g *-t - N--y _,_._ 5 . , .
.4 . _ . . .- _. a. ..__._u_-. . ._ I _ .a_7.- __ :-
_ 4 _ _-t. -._a_
=_ . .3_.. 1 . =t- r . _; _ . . _.A
._. .p .--+--r_\6-------- - - - - - -
-F---- -
_J----9----6-----t .n ' - - - [
'~~1"'
_"~~~~~^ ' I'~~ ~ ~ ~ ~ ~ " --------A~~' ---- ' - - ' - - - - - - + - - -~'"-
' ' ' ~ ' -
C
-
---t.."----s
- - - -
g:-
-
. + -j -- - := {_, - -
-p" u -* __. =- li =*
.
t 5.____ = O=T. _ = - p1 - _ _ . _ i . -- - _ --- --t-- t----- =% 2r- . _= in _ . . .___r ____..,__v_r______.__.__.__..___..__y___.,____p_=_,_.._
-
2 ._ .
-
D ._ :=
= _....__=__ _ N_
m ,. i ___ .
;= :hzt _._.r .-.
-
==.._-t=2=.+
.
== = , - , - - m ._p _ _r= _ _ . .
=
' T _ _. Q - _-- ;
-*
._c---
-
. _ . .
-
V= -
=. - _ rs. _.
-
~_. __ N.__ __ =__:= = k =_n=:+-- = r_=4-- - r _g;. _.=.= - =-
____- i
.
_ _ _ _
$.__._&___,_.._..__._&_ _ _ _ _ _ _ _ _ _ _ --\_=__. =c_
_ _ _ _ _ _ _ - _._. .__ _.,_ _. _ __=;.__ p. r r
._=_a_
_ _ .-_- __.
. _J~.~ __ b_- = , 1- _
?= --
._'._._?__.
_
.__.._4=L.,_.._-
_ ' - -
==& __ . .- _ _ _ .
_y - .._.,_:- . = - : __ ._
=x=t_ _ --- m- -
-
=& - --
.-- r __.n a _q_w _ . ._ A-
.
E - . _:= rr . . .g___+_ _m a = _
~ _ _a
- .+
.
s _._ _ % . e
._
== t- = =- t-=_ _ . ; - q._gh
,_._.__p__ .. _
g_- ==._.m__._t=_.__.
==- r._ _- u= . ._-
_ .
. g==-
-
*--
g . ._ g ____
'
-
_.~H __t _.L ,_ __ _ _ . _ _ . _ . _ _ . _ , _ _ , . g_ _ _ . _. _._ .;.___ - -. ._ . __ ___ cE:7zg._~ -__ -.
-
_ . _ _
'
__. _ _r i--* t = _-ic. Q ,-~~'~I"=n_~,_-_ .,u .. i . __ . . _.tr =-
~C p=. . k"EC~ _r._ _ _ . .
s
- _- .% - -=. =___=4 y=_ =_ =t _ - ~ }
'._.__w.':>'._.__
-
- -
= =::-4_ :=_=,_ g_ = _._ t=r - ". _u= =%=tz.-- .\ = t==_- -.; -. - _i ;=_: r=_.x=s==-__g__.__. :- q=_=_= r._ _ -t.
._. _%,_
_ . 5____
3
,_ -
r_.__ _
.__g., _ .
__ ,___ _ .__ 4.___ .. n
-
._4
_ _ V.r- g _._t__
,,
n_e.,-6m..e_ _, _.g4--- . _ --+4._e._b_ -__L. ._._.l_4 _.-_p --4.._ {_ _. . . . . r : t ' .: - - l=. ~ - ~ =a Qi.' 1- $=
^ -----
-
C----" - ---- -' ! - . :. .='
.
a ___"t=_=1* __m,-_.. __g t .; -_ _ =. . _ _ ~ _ _ ' . . - 'I~' L__ __ _
* .
_;.__ ,__4____._._.__
~
.{. , c_
.._ "---* *~ _ .f~ ~* ~ i= 2._hL'
._ C _ _t_._ . ; . r--i .__ _ .=\: =: t- =- {=r
--.2=--
._____-----t--
-* : :-- ::= t.
- - - - - - - -
.
. . =~ -? W _ _ - .. : .-
-- -
==y - -- _- __ . . _ _ _ jag --
,
6 _ _ _ -
= XT' A -- - - - - -
-----
-
m
- -- -- r " :'I=r=
-
_._._._:=:.__- L =--- r \ i _ _ - - - - -
._...'?*t = \Q- _ _- _J _ r-- r---3 __ r=-. t:=.- - , - 3: t- . ;j- =_ g=%" k =_: "._ - 6
_- i r-- - _ _ . _ . . i. p g ,-- - 3 f_ _,.__ _ ___m__. . ._s.-___._._. . g __ ___
= N g=_. _7. ,__:- .W_-
- _ _M (- _r .@._._._..___2[_. . . . . _ . _ _ m+_4._ __.:t . :rrt-- _n=b __ = u. - g . t --- t _ _ __ _
- - - -
_ .
, _ _ _ .
f
= p==d
.c T
=r-- g2=
-
r= _ _j _ ; .__ _ _ r= . : _._.--t r = = t- 7 r: 4 _. _
-
T-- _;. 2 2=.
.__:-y M_ =_.M[__m_.g_n= -
_ _rncr - =nt cnr% %r- . _ _ _ e
- --x_g= .p ,.
- ut
=_ t __. i .t .=nd.
=_. . . . 1. =
t=- --.__,__~_n.____L
. ==tu-
-t.___= t=
'2
= 1\ _:=d==-~-l=--_ = _
w A L==___=_.1_= =r.
=-~f=h=;t---
= == _ _ --
, _ _ _ _
3I ;ng..._.w-Wr==r . __ __.t=.~_2= l = _ ,. .... _. s
.- - - . _ _ _ - ,____.p___.. -t
.p.t=g r =-t-_- --g C _ r- . :- 2 2. _._ ,_-- : .._.____rr=g'._____ -
r; _..m. .
. _._. ,
r.- _ w . _---- ;
- =:--+ - : - ~ - ~
-
g - -* - - y-_. =. t Lk. = =R = rt =. _=_ = .=. _. . . .t- r=- rt = h- = rn r m=_ 2_ =_ .
- t=
L__.=. = (==:tt x=t r---- =:T-- -: -- 4. tc==
.g=-'- f ====:- -
==w : __ _ .1 __ _ ____
~-~3- = N h'_5 5-h- dN._~i-N~- N E[. [ NMN-*2.- Shi~5{_~5 c 's N-N_k
, sy
--
- . 4 =_= c _..,_=_ _=.%= == \======s =____ _=-
t
._== r-- r: __ m==\==2r._.=_ - = =_ . cm,=a =_ a._= - _ .= --- . _ =._ , = _ _ . - _ _ . _
_ g .___ _ _ _ q__ ; __ ;__=....___ g .._.__;;.__._ . - . .,.
.c_ _ _ =~;-4.______.--12=t----t--::=__==_=_I._.=y_.,_.,_.._..__,....=t f=__4- _ __ _ _. _:_. .
.
. _ _
_
.
_ F =---r um:- tm
%,
. ___ _ s. _r_.--_,- .. . , .. -1 =_.=_i
- p. _z__._j.__.-1__y.__N_.____._g___..__.
- ..__ . _-
_ p ---- - -
- n-? - :1. __ . _-t --- tu r- =t __.2 __ . . == . __--C.----+._----
d 11- ---n _ g.= rgc-- u ]n , -xtt_ _-_ .t: ._.:.x - n. _=:===t..___ .- r--- i = =._. . _ =- ,.---t 3, .:.. _ _ ;;m _ . =_ - , __ __a .._-~ m y r___i.- .. ._ =_
.
_ _ . .., ___nn Tr _ _.-
-f .
g ~ - -
-. E 4_ .-A... _+--_._.-___4--g
- z: .W
.
_.
.' _= . h~.' ' $1 5 . 5 i = = - ' W..~b1
,
.t5_% 5$5.~-5 ' ' ' "-'hE._~_h:---_ ? _ -._^:- f.-f _ Y 'i. ~
~
-
2 y ..n_ _ _. .g._.g = r_- =_ _ _..._yr.;_..___._.
-
- 2
! ;
_. .. __ p_ _. ___m _ . .
._ _ . p _ 4_ .. _4-- y _._.___ --
.
, __y_~ . _.g _M_.. . - -.
_ ; -- _.-. _~~-__-- --._--_,---*~_- g , .,,- F- _ - _ - + - ___..___-C**.7t-3.._..__.__ -
,_,7._;___t...__.
---+---4.___.'-*"T- L. _ ___._._5.__._.; f.
=
v- r--~ =. ,
- -
_ _, q__ - - __; _
--- .;-
- t. ._._ m . = .=3_ ,:__ ._._ .. -
-_
=- .: =g~_ _ __ p_
-
,. _.___.._____p_..__.
= .. =A _ t__ ___
__
+._. .__ j . _ p . . _ . gr . . r_ --+ _,
_ _ . _
.;_j___ _ .
-.-r---- - - -
r
'
__ w-a--- -; a _=t-
-
-
"-- _ a,_- =2_. = r -_. __a = =. _____L____,
v -~_ &.---'O ; _i ;T: -- 4-C:i_-."=.- ,_ _ - l
- _ _ { - CC.}.: -= - '- '--[*= .::==__IMR- . 22.;: 'a.; --==.g=== '- - ~
- r-- ' - * - -----*'.22---"." _ ' _ -
r= _ --
- -
t __ r _
.z=_ __t.== w __ t = =,_ .
.'..3.__._g.---g_ , _ _ _ .
, _ _ _ _ . ._ .. _
. =. . -L._=. =___=_2.
.
__. _ __ _.._.3__:_._.__.,_._,u_.t.------~--g n . .- -- _: .h.
._-- - :. . L. .. s,r=. =_ 3 . .:- .2_=.~s__...__._ -
__
~
__U ;--_':'T-'"-- : : :=.I.-'- .-- .' T_ 2- ~ - -- Tan = :h-. ;.r*t ri ~~ _'r' .:...._-_4 a j , ------ '
--- d= . "r:-t C .7 -~~ '
.* r =;= = _ --1 == :t _ . ___n n-4: cr _1- . : J 4 U. {nc. ::' WT:_Y c==t= : r
- _ _ __L..::: _ =r N _ _N1 --
t i
._ -- . . c u r-L _-- % _ a :: p- :=/ _Q - - -- - t-. -m . ._ . -Q .~.':.. ~ +T:___._ . Q := _Vt= lr z = V Q u= _::: {----.=- G o =. =~ =.rro tur - = Q ===r==~: -- ** :=~. ==: l
-- --
1
-.-- y- --- E A -^ ^'+kr_:==- Q =-* =_ ==l =: . . :qn=r n=. q=. =* tq=* .3==. =. t _.7._7 .nr
. . =
=-*I t.ntvr'. =. t == q %== = =t:=: t.7 .V. *h * =-'.y=;=r . 43 =rd:: (47 =r N
-
, .. . . ': i. _
; : =. r _ .. ___t __. __ . nc H--~~' r ; = - nr=* *"
! _ _. . . L-~' *:! - n f . J .' T =- -- 1 _ 2=_. . j . : T- . . ~-_ f - -- ; -'I- t'-'_=, r ~=t .=. . , . *. T ' ~ 4 - N -~ I-' -" : _b= ~ T~4~=.! -- i * =a n= = T c . .:~, u ==- Tu-i - : '**'"-~~$---*~~C-?
-t . ' .:
~
b [ v . . ,=_ .Y. _Tdd. _ . __$5i..:5. . - .&.
'~
..
__ _ .n _ ._ _ _ .} . _ _[_- -. =_2_.W* ~5. -~_~_~ (C. . .Y.. f_ $. _$_0_.Y. _$._ _:f. . f.0 0 . .. ..,
=_=l._.
. _ . . _ .
- - ..
. . . . _ . _
.
- - - r = 'i ;r==_r.=4
-
=2=t === f =_ =:n tr _-=-t - - - 3. . ===. 7.t-. =.=" =' : .= .= u(- .- -:_ 3:,
h_ .-- .. . f . s ==1 u ::- _ntr t=== utxl w== u----=__ E=c_=: -.- q =r ===G==:;=_=~ : := != u : 1: - - __c*- 1 i ._, . _ _ _ _ _ _ . _ _ . - _ __ .__ _ .___. . _ _ - , , _ _ _ _ __ _ _ _ _ . . _ _ .}}