ML20072A967
| ML20072A967 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 08/04/1994 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20072A971 | List: |
| References | |
| ULNRC-3050, NUDOCS 9408150328 | |
| Download: ML20072A967 (22) | |
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1901 Chouteau Avt>nue
- n. ', Post O!!iw Box 149 Si touh, Missowi fi3166 .
314 554-2650 n
u Donald F. Schnell Etscruic Senior Viw President ne, y@] August 4, 1994 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, D.C. 20555 Gentlemen: ULNRC-3050 DOCKET NUMBER 50-483 CALLAWAY PLANT CONTAINMENT SPRAY ADDITIVE SYSTEM RETIREMENT
Reference:
ULNRC-3023 dated May 20, 1994 Union Electric Company herewith transmits an application for amendment to Facility Operating License No. NPF-30 for the Callaway Plant.
This amendment application replaces Technical Specification 3/4.6.2.2, Spray Additive System, with a new Specification 3/4.6.2.2 entitled Recirculation Fluid pH Control (RFPC) System. The current Spray Additive System will be retired, pending approval of this amendment request, and replaced with the passive RFPC System consisting of stainless steel baskets containing trisodium phosphate dodecahydrate (TSP-C).
-One such basket will be located within the confines of each. containment recirculation sump and will contain sufficient TSP-C to ensure a minimum equilibrium eump pH of 7.1. The new LCO will ensure that the amount of TSP-C contained in the baskets is greater than this minimum amount yet less than the basket design capacity. Mode Applicability and the Action Statement for the new specification are unchanged from the current specification while the Surveillance -)
Requirements have been revised to correspond to the passive nature of the RFPC System. The Bases for 3/4.6.2.2.have been revised accordingly as have the Bases for 3/4.5.5, RWST. A similar change will be needed for Attachment 6 of the referenced submittal; draft FSAR Section 16.1.2.1.2, taken from current Bases page B 3/4 1-3, will be revised to refer to a minimum equilibrium sump pH of 7.1 on page 16.1-2.
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U.S. Nuclear Regulatory Commission Page 2 The Callaway Plant Onsite Review Committee and the Nuclear Safety Review Board have reviewed this amendment application. Attachments 1 through 5 provide the Safety Evaluation, Significant Hazards Evaluation, Environmental Consideration, proposed Technical Specification revisions, and FSAR mark-ups, respectively, in support of this request. It has been determined that this amendment application does not involve an unreviewed safety question as determined per 10CFR50.59 nor a significant hazard consideration as determined per 10CFR50.92. Pursuant to 10CFR51. 22 (b) ,
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
Implementation of this modification is currently scheduled for Refuel 7 beginning in March 1995. Review and approval of this amendment application is requested by March 1, 1995 to support that schedule. If you have any questions on the attachments, please contact us.
Ver' truly your ,
t 1 Donald F. Schnell GGY/plr Attachments: 1 - Safety Evaluation 2 - Significant Hazards Evaluation 3 - Environmental Consideration .
4 - Proposed Technical Specification Revisions 5 - FSAR Mark-ups
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STATE OF MISSOURI )
) SS ,
CITY OF ST. LOUIS )
Donald F. Schnell, of lawful age, being first duly sworn upon oath says that he is Senior Vice President-Nuclear and an officer of Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts thercin stated are true and. correct to the best of his knowledge, information and belief.
By
. Donald F.'Schnell Senior Vice President Nuclear
>l SUBSCRIBED and sworn to before me this V [A' day of' /[ltar d , 1994.
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/~ g 16 BARBARA J. PFAFE NOTARY PUBUC-STATE OF MISSOURI My COMMISSION EXPIRES APRll 22,1$J SL LOUIS COUNTX
cc: T. A. Baxter, Esq.
Shaw, Pittman, Potts & Trowbridge 2300 N. Street, N.W.
Washington, D.C. 20037 M. H. Fletcher Professional Nuclear Consulting, Inc.
18225-A Flower Hill Way Gaithersburg, MD 20879-5334 L. Robert Greger Chief, Reactor Project Branch 1 U.S. Nuclear Regulatory Commission Region III 801 Warrenville Road Lisle, IL 60532-4351 Bruce Bartlett Callaway Resident Office U.S. Regulatory Commission RR#1 Steedman, MO 65077 L. R. Wharton (2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 White Flint, North, Mail Stop 13E21 11555 Rockville Pike Rockville, MD 20852 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102 Ron Kucera Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102 4
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- ULNRC-3050 ATTACHMENT ONE SAFETY EVALUATION I
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Attachment 1 Page 1 of 10 SAFETY EVALUATION INTRODUCTION This amendment application replaces Technical Specification 3/4.6.2.2, Spray Additive System, with a new Specification 3/4.6.2.2 entitled Recirculation Fluid pH Control (RFPC)
System. The current Spray Additive System will be retired, pending approval of this amendment request, and replaced with the passive RFPC System consisting of stainless steel baskets containing trisodium phosphate dodecahydrate (TSP-C). One such basket will be located within the confines of each containment recirculation sump and will contain sufficient TSP-C to ensure a minimum equilibrium sump pH of 7.1. The new LCO will ensure that the amount of TSP-C contained in the baskets is greater than this minimum amount yet less than the basket design capacity. Mode Applicability and the Action Statement for the new specification are unchanged from the current specification while the Surveillance Requirements have been revised to correspond to the passive nature of the RFPC System. The Bases for 3/4.6.2.2 have been revised accordingly as have the Bases for 3/4.5.5, RWST. Refer to Attachment 5 for selected FSAR mark-ups describing pertinent details of the proposed modification.
DES _IGN CONSIDERATIONS The Callaway design utilizes the Containment Spray System to reduce radiciodine concentrations in the containment atmosphere following a design basis large break loss of coolant accident (LOCA). The current design includes a sodium hydroxide (NaOH) solution additive. This would raise the pH of the spray droplets to high levels during the injection phase (e.g., 9.3 to 11.0). At the time this system was designed it was believed that a high pH level, maintained in the spray through the use of the sodium hydroxide additive, was required to effectively remove elemental iodine from the containment atmosphere and retain it in the sumps. However, the results of recent studies (SRP 6.5.2 Revision 2 and NUREG/CR-4697) on the behavior of iodine in the post-LOCA containment environment have demonstrated that iodine removal during the injection phase can be effectively performed by boric acid sprays, without using an NaOH additive, and that long-term iodine retention in the sumps is assured as long as the equilibrium sump pH level is maintained above 7.0. This would allow the retirement of the Spray Additive System and associated spray additive tank, controls, and instrumentation. The advantages of retiring the Spray Additive System include:
reduced safety-related component testing, maintenance and surveillance; eliminating personnel safety concerns with
Attachment 1 l Page 2 of 10 respect to concentrated NaOH spills; and elimination of the potential for expensive caustic cleanup of containment in ;
the event of an inadvertent containment spray actuation. '
l However, the equilibrium pH of the containment recirculation sump water should still be maintained above 7.0 in order to retain iodine in the sump solution and to minimize chloride-induced stress corrosion cracking of austenitic stainless steels in the Emergency Core Cooling System (ECCS). Since the initial pH of the RWST spray fluid is greater than or equal to 4.0 but less than 7.0, a chemical additive is needed to raise the pH.
To provide this pH control, UE intends to install a passive system utilizing TSP-C stored in two wire-mesh baskets located within the confines of the recirculation sumps.
One seismically designed TSP-C basket will be constructed within the confines of each of the two containment recirculation sumps. Each basket is designed to contain a maximum of 6720 lbm of TSP-C (basis for the maximum depth of 36.8" in the proposed Technical Specification) whereas a minimum depth of 19", corresponding to 2500 lbm, must be contained in each basket to ensure an equilibrium sump pH of at least 7.1. The baskets will be located at an elevation that will ensure dissolution by the sump fluids. The baskets will have a stainless steel frame with walls constructed of stainless steel grating and lined with #100 wire mesh stainless steel screening. Inside dimensions of each basket will be 80" x 56" x 38".
The calculation of the minimum and maximum depths of TSP-C includes conservative allowances for compaction, spillage through the wire mesh, density variations, and the limited transformation of TSP-C into disodium triphosphate which is a weaker base (expected to have a small impact in the outer surface layer). The minimum equilibrium sump pH of 7.1 corresponds to a minimum of 5000 lbm of TSP-C in the baskets and a maximum sump boron concentration of 2500 ppm. If the maximum of 13,440 lbm of TSP-C were contained in the baskets at the end of cycle life such that a minimum sump boron concentration of 2007 ppm would occur, the maximum equilibrium sump pH would be less than 9.0.
Four floor mounted plates will be anchored (using Hilti Kwik Bolt II anchors) within each sump to support carbon steel beams which will support the baskets. Piping, valves, and flow instrumentation from the spray additive eductors to the common line from the spray additive tank will be removed and the lines will be capped. The spray additive tank will be retired in place and its level and pressure instrumentation will be removed. These changes are shown on the mark-up of FSAR Figure 6.2.2-1 in Attachment 5. The instrumentation,
Attachment 1 Page 3 of 10 including all annunciators and associated wiring, will be removed from the system and from the main control board.
EFFECT ON OFFSITE AND CONTROL ROOM RADIOLOGICAL CONSEOUENCES The offsite and control room doses currently discussed in FSAR Section 15.6.5 were calculated using an elemental iodine spray removal rate of 10hr-1 and a particulate iodine spray removal rate of 0.45 hr-1 The current dose calculation uses these spray removal coefficients until a decontamination factor (DF) of 100 is attained for both species. The DF, defined as the ratio of the initial iodine concentration in the containment atmosphere to the equilibrium iodine concentration in the containment atmosphere, for elemental iodine is a function of the equilibrium iodine partition coefficient, H, which in turn is based on the pH of the sump fluid as discussed in SRP 6.5.2 Revision 2 and FSAR Section 6.5A.2 (Equation 6.5A-15).
The equilibrium iodine partition coefficient is defined as the ratio of the iodine concentration in the liquid phase (i.e., in the sump fluid) to the iodine concentration in the vapor phase (i.e., in the containment atmosphere) at equilibrium. As such, the offsite and control room doses were reanalyzed to support this modification.
With the replacement of the Spray Additive System with TSP-C baskets in the containment recirculation sumps, the minimum equilibrium sump fluid pH is reduced to 7.1. This reduced pH results in a reduction in the equilibrium iodine partition coefficient from 5000 to 1100 per NUREG/CR-4697,
" Chemistry and Transport of Iodine in Containment," October 1986. As discussed in Standard Review Plan Section 6.5.2, Revision 2, " Containment Spray as a Fission Product Cleanup System," December 1988, the effectiveness of the spray during the injection phase against elemental iodine vapor is chiefly determined by the rate at which fresh solution surface area is introduced into the containment atmosphere.
The rate of solution created per unit gas volume in the containment atmosphere may be estimated as (6F/VD), where F is the spray volumetric flow rate, V is the volume of the sprayed region, and D is the mean diameter of the spray drops. The first-order spray removal constant for elemental iodine, Ag , may be taken to be:
As = Ek TF where k g is the gas phase mass transfer coefficient and T is the drop fall time (or drop exposure time), which may be estimated by the ratio of the average fall height to the terminal velocity of the average drop. The above expression represents a first-order approximation if a well-mixed droplet model is used for spray absorption efficiency. This
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Attachment 1 Page 4 of 10 expression is valid for A s values equal to or greater than 10 per hour but less than 20 per hour. Using this expression and the values contained in the FSAR Table 6.5-2, a value of 37 hr-1 is calculated (refer to new FSAR Section 6.5A.3 contained in Attachment 5). However, a value of 10 per hour was used in this reanalysis of offsite and control room doses.
Spray removal of elemental iodine continues until the DF of Equation 6.5A-15 is reached. The value for the partition coefficient, H-1100, in Equation 6.5A-15 was taken from Figure 6 of NUREG/CR-4697 using the 323 K plot at 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> (representative of the average conditions during a LOCA).
The value of 1100 used is considered to be conservative since the sump fluid temperature at 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> would be greater than 323 K per FSAR Figure 6.2.1-17 and Figure 6 of NUREG/CR-4697 shows that higher temperatures would be associated with higher partition coefficients. The resulting_DF is calculated to be 28.7.
Per SRP 6.5.2 Revision 2, the particulate iodine spray removal rate, calculated using Equation 6.5A-1 in FSAR Section 6.5A.1, can conservatively be based on an assumed E/D (ratio of the dimensionless collection efficiency term to the mean drop diameter) of 10 per meter initially, changing to 1 per meter after a DF of 50. After the particulate iodine spray removal rate is reduced, there is no DF limit imposed by SRP 6.5.2. However, for. simplicity and conservatism, removal was assumed to stop after a DF of 50 was reached in this reanalysis of offsite and control room doses.
Therefore, this reanalysis used the current spray removal coefficients (i.e., 10 hr-1 and 0.45 hr-1) until a DF of 28.7 was reached for elemental species and a DF of 50 was reached for particulate species. No plateout removal lambda was used in this reanalysis, consistent with the current FSAR Section 15.6.5 dose calculations, since credit was-taken for the instantaneous plateout of half of the iodines released to the containment atmosphere (i.e., 25% of the core iodines). These reduced DF values mean that more iodine is available for leakage from the containment atmosphere.
The current control room doses discussed in FSAR Section 15.6.5 are based on a 90% efficiency for the control building pressurization and control room filtration ESF filter assemblies. Consistent with our position on RG 1.52 in FSAR Table 9.4-2, this reanalysis used a 95% filter efficiency for these ESF filters.
ECCS and RWST leakage doses were not recalculated as the change in spray chemistry will have no impact on these dose l
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Attachment 1 Page 5 of 10 pathways. Since 50% of the core iodines are assumed to be immediately deposited in the sumps, these leakage doses are not mechanistically tied to the airborne iodine activity.
The doses currently reported in FSAR Table 15.6-8 contain a minimum of 14% of margin, arbitrarily assigned and available for design flexibility, over and above a 5.5% margin assigned to accommodate capacity factor variations from an assumed 95%. If the available margin were to be subtracted from the containment leakage portions of the reported EAB and LPZ doses, then this offsite and control room dose reanalysis would show a 1% and 2.4% increase, respectively, in these portions of the total dose. However, given the minimum of 14% of available margin, there is no impact on the EAB and LPZ doses reported in FSAR Table 15.6-8. The containment leakage portion of the control room dose in FSAR Table 15.6-8 is lower in this reanalysis than the previously calculated results, even with the available margin subtracted and lower DF values, due to the increased ESF filter efficiency assumption.
Therefore, the doses currently reported in FSAR Table 15.6-8 are not increased and the regulatory limits of 10CFR100, SRP 15.6.5 II, and SRP 6.4.II continue to be met.
EFFECT ON EOUIPMENT OUALIFICATION DOSES FSAR Section 3.11(B).1.2.2 discusses the decontamination factors (DFs) of 200 and 10,000 for elemental and particulate iodines, respectively, which were used in the EQ dose calculations and were taken from NUREG-0588, Revision
- 1. The spray removal rate for elemental iodine was calculated in FSAR Section 6.5A.2 to be 25.7 hr-1 This spray removal rate plus the calculated plateout removal rate (25.7 hr-1 + 1.58 hr-1) were assumed to be effective in the sprayed region until an elemental iodine DF of 200 was reached in the EQ dose calculations. Only the plateout removal rate was assumed to be effective in the unsprayed region until an elemental iodine DF of 2 was reached in the EQ dose calculations. The spray removal rate for particulate iodine was calculated to be 0.73 hr-1 in FSAR Section 6.5A.1 and was assumed to be effective in the sprayed region until a particulate iodine DF of 10,000 was reached in the EQ dose calculations.
With consideration given to the reduced DF values for elemental and particulate iodines of 28.7 and 50 discussed above, airborne gamma doses listed in FSAR Table 3.11(B)-4 have been estimated to increase by 3% as a result of this design change. Further, the doses in penetration rooms 1409-1412 and 1506-1509 in FSAR Table 3.11(B)-2 have been estimated to increase by 8% due to the harder spectrum of gamma energies associated with the iodines. The margins available between the affected equipment's qualified (EQ
Attachment 1 Page 6 of 10 test) doses and the currently required doses are sufficient to accommodate these increases. The location-specific doses for the MCCs were recalculated based on a 1% cesium release fraction in order to avoid exceeding their available margin.
The original EQ dose calculations were based on a 50% cesium release; however, RG 1.7 and RG 1.89 discuss only a 1%
cesium release (i.e., as part of the release of "1% of the remaining fission product solids"). Therefore, the difference is considered to be available margin.
HYDROGEN GENERATION ASSESSMENT An assessment of this modification on the generation of hydrogen was performed. The hydrogen generation due to the corrosion of metals and paints by solutions used for containment spray is dependent on solution pH. The assessment concluded that the generation of hydrogen due to the corrosion of aluminum at a lower equilibrium sump pH of 7.1 would be less severe and would be bounded by the current analysis which assumed a constant recirculation sump pH of 9.5. The generation of hydrogen due to the corrosion of zinc above a temperature of 170 F would also be bounded by the present analysis. The generation of hydrogen due to the corrosion of zinc below a temperature of 170 F would be greater at the lower pH value; however, this effect would be offset by the decrease in the aluminum corrosion rates.
Since aluminum is the dominant source of hydrogen from corrosion at Callaway, the use of TSP-C in baskets will not adversely impact the results of the current, post-LOCA hydrogen generation calculation.
DETERMINATION OF NO UNREVIEWED SAFETY OUESTION The proposed changes to the Technical Specifications do not involve an unreviewed safety question because operation of Callaway Plant with these proposed changes would not:
(1) Involve an increase in the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR. Overall protection system performance will remain within the bounds of the accident analyses documented in FSAR Chapter 15, WCAP-10961-P, and WCAP-11883.
The accidents evaluated in the FSAR that could be ;
affected by this proposed change are those involving .
the pressurization of the containment and associated j flooding of the containment and recirculation of this '
fluid within the ECCS or the Containment Spray System (i.e., large break LOCA, main steam line break inside containment, and feedwater line break inside containment). The TSP-C will dissolve in the
attachment 1 Page 7 of 10 containment sump fluid resulting from these accidents raising the pH of the fluid, which would initially be greater than or equal to 4.0 but less than 7.0 during the injection phase of containment spray operation.
The equilibrium spray pH during the recirculation phase resulting from this change will be greater than or equal to 7.1. The pH range for the spray will be bounded by the range of 4.0 to 11.0 in the current FSAR Section 3.11(B) for the postulated spray solution environment. Since the resulting pH level will be closer to neutral using the TSP-C instead of NaOH, post-LOCA corrosion of containment components will not be increased. The results of the current, post-LOCA hydrogen generation calculation will remain bounding.
There will not be an adverse radiation dose effect on any safety-related equipment. Thus, the potential for failures of the ECCS or safety-related equipment following a LOCA will not be increased as a result of the proposed change.
This modification affects the Containment Spray System which is intended to respond to and mitigate the effects of a LOCA. The TSP-C baskets serve a passive function to provide TSP-C to neutralize the sump solution. Failure of a basket would not initiate an accident. The Containment Spray System will continue to function in a manner consistent with the plant design basis. There will be no degradation in the performance of nor an increase in the number of challenges to equipment assumed to function during an accident situation.
As such, these Technical Specification revisions do not affect the probability of any event initiators.
There will be no change to normal plant operating parameters, ESF actuation setpoints, or accident mitigation capabilities.
The proposed change substitutes a passive Recirculation Fluid pH Control System for the active Spray Additive System currently used to mitigate the consequences of an accident. By substituting a passive system for an active system, the' probability of occurrence of a malfunction of equipment associated with the Spray Additive System would be reduced since the number of active components subject to malfunction is reduced. The items currently listed in the single failure analysis in FSAR Table 6.5-4 for the Spray Additive System will be eliminated as a result of this modification. This modification will maintain the equilibrium sump pH at greater than or equal to 7.1 to minimize chloride-induced stress corrosion cracking in austenitic stainless components important to safety located inside containment. Therefore, the proposed l
Attachment 1 Page 8 of 10 changes will not increase the probability of an accident or malfunction of equipment important to safety previously evaluated in the FSAR.
The radiological consequences of changing from NaOH to TSP-C were reanalyzed using the current NRC methodology presented in Revision 2 of the Standard Review Plan (NUREG-0800) Section 6.5.2. This reanalysis indicates that the proposed change would result in reduced control room doses. Offsite doses would remain less than those currently reported in FSAR Table 15.6-8. The offsite and control room doses will continue to meet the requirements of 10 CFR 100, 10 CFR 50 Appendix A GDC 19, SRP 15.6.5.II, and SRP 6.4.II. The dose reanalysis, combined with knowledge gained from recent studies on the behavior of iodine in the post-LOCA environment, demonstrates that the deletion of the Spray Additive System and replacement with a sump pH control system using TSP-C will not increase the reported radiological consequences of a postulated LOCA. The proposed new pH control system will provide satisfactory retention of iodine in the sump water, as well as provide adequate pH control to minimize the potential of chloride-induced stress corrosion cracking of austenitic stainless steel components.
The baskets which will contain the trisodium phosphate are seismically designed and located in the sump area to ensure mixing with the recirculating fluid. The consequences of a malfunction of any piece of equipment associated with the Containment Spray System would not be affected by the change from an active l Spray Additive System to a passive system. The l consequences of a failure in the active Spray Additive :
System are eliminated by this passive system. ,
Therefore, the proposed changes will not increase the ;
consequences of an accident or malfunction of j equipment important to safety previously evaluated in i the FSAR. 1 (2) Create the possibility for an accident or malfunction of a different type than any previously evaluated in -l the FSAR.
The new Recirculation Fluid pH Control System is a passive system, i.e., no operator or automatic action is required to actuate the system. There are no active components being added whose failure could prevent the new system from functioning. The only new components being added are the TSP-C storage baskets.
Seismic requirements have been included in the design I to ensure the structural integrity of the baskets will be maintained during a seismic event.
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Attachment 1 Page 9 of 10 No new accident scenarios, transient precursors, failure mechanisms, or limiting single failures are introduced as a result of these changes. There will be no adverse effect or challenges imposed on any safety-related system as a result of these changes.
The use of dry sodium phosphates is allowed for adjustment of the post-LOCA sump solution pH as discussed in SRP G.1.1. Trisodium phosphate has a dissolution rate of 0.7 lbm/f t 2 -min in water at 160 F (given in WCAP-12477, based on trisodium phosphate in the form of a solid block with no agitation of the solution). The quantity of trisodium phosphate chosen will provide a minimum equilibrium sump pH of 7.1 following dissolution and mixing. Therefore, the i possibility of a new or different type of accident is not created. 1 There are no changes which would cause the malfunction of safety-related equipment, assumed to be operable in j the accident analyses, as a result of the proposed i Technical Specification changes. No new equipment performance burdens are imposed; however, there is the potential for an unlikely, but possible, event in which an initially concentrated solution of TSP-C occupies the stagnant volume of an inoperable sump.
This situation would not last for long since, as the recirculated sump fluid is cooled in the RHR heat exchangers, sufficient buoyancy-driven circulation within containment will result to displace the stagnant solution and eventually yield a uniform, equilibrium solution. Therefore, the possibility of a i new or different malfunction of safety-related equipment is not created.
- 3. Involve a reduction in the margin of safety as defined in the bases for any Technical Specification.
The only function of the NaOH spray additive solution is to provide pH control of the post-accident containment recirculation sump water, since the borated water from the Refueling Water Storage Tank (RWST) used as the containment spray pump suction source during injection is sufficient to remove iodine from the containment atmosphere following a LOCA. The net effect on the pH control function of replacing NaOH with TSP-C is that the equilibrium sump pH will be lowered to a minimum of 7.1. There will be no change to the current acceptance limits on RSWT volume and boron concentration. The resulting equilibrium sump pH level from this change will be closer to neutral; therefore, the post-LOCA corrosion of containment components will not be increased. The
Attachment 1 Page 10 of 10 results of the current, post-LOCA hydrogen generation calculation will remain bounding.
The radiological analysis performed for this proposed change, as discussed above, shows that there would be no impact on the doses reported in FSAR Table 15.6-8.
There will be no change to the DNBR Correlation Limit, the design DNBR limits, or the safety analysis DNBR limits discussed in Bases Section 2.1.1. There will be no effect on the manner in which safety limits or limiting safety system settings are determined nor will there be any effect on those plant systems necessary to assure the accomplishment of protection functions. There will be no impact on DNBR limits, Fg, F-delta-H, LOCA PCT, peak local power density, or any other margin of safety. Therefore, the proposed change would not result in a reduction in the margin of safety defined in any Technical Specification Bases.
Based on the information presented above, the proposed amendment does not involve an unreviewed safety question and will not adversely affect or endanger the health or safety of the general public.
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ULNRC-3050 s
ATTACHMENT TWO SIGNIFICANT HAZARDS EVALUATION I
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Attachment 2 Page 1 of 4 SIGNIFIC_ ANT HAZARDS EVALUATII)E This amendment application replaces Technical Specification 3/4.6.2.2, Spray Additive System, with a new Specification 3/4.6.2.2 entitled Recirculation Fluid pH Control (RFPC)
System. The current Spray Additive System will be retired, pending approval of this amendment request, and replaced with the passive RFPC System consisting of stainless steel baskets containing trisodium phosphate dodecahydrate (TSP-C). One such basket will be located within the confines of each containment recirculation sump and will contain sufficient TSP-C to ensure a minimum equilibrium sump pH of 7.1. The new LCO will ensure that the amount of TSP-C contained in the baskets is greater than this minimum amount yet less than the basket design capacity. Mode Applicability and the Action Statement for the new specification are unchanged from the current specification while the Surveillance Requirements have been revised to correspond to the passive nature of the RFPC System. The Bases for 3/4.6.2.2 have been revised accordingly as have the Bases for 3/4.5.5, RWST.
The proposed changes to the Technical Specifications do not involve a significant hazards consideration because operation of Callaway Plant in accordance with these changes would not:
(1) Involve a significant increase in the probability or consequences of an accident previously evaluated.
Overall protection system performance will remain within the bounds of the accident analyses documented in FSAR Chapter 15, WCAP-10961-P, and WCAP-11883.
The accidents evaluated in the FSAR that could be affected by this proposed change are those involving the pressurization of the containment and associated flooding of the containment and recirculation of this fluid within the ECCS or the Containment Spray System (i.e., large break LOCA, main steam line break inside containment, and feedwater line break inside containment). The TSP-C will dissolve in the containment sump fluid resulting from these accidents raising the pH of the fluid, which would initially be greater than or equal to 4.0 but less than 7.0 during the injection phase of containment spray operation.
The equilibrium spray pH during the recirculation phase resulting from this change will be greater than or equal to 7.1. The pH range for the spray will be i bounded by the range of 4.0 to 11.0 in the current FSAR l Section 3.11(B) for the postulated spray solution l environment. Since the resulting pH level will be ,
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Attachment 2 Page 2 of 4 closer to neutral using the TSP-C instead of NaOH, post-LOCA corrosion of containment components will not be increased. The results of the current, post-LOCA hydrogen generation calculation will remain bounding.
There will not be an adverse radiation dose effect on any safety-related equipment. Thus, the potential for failures of the ECCS or safety-related equipment following a LOCA will not be increased as a result of the proposed change.
The radiological consequences of changing from NaOH to TSP-C were reanalyzed using the current NRC methodology presented in Revision 2 of the Standard Review Plan (NUREG-0800) Section 6.5.2. This reanalysis indicates that the proposed change would result in reduced control room doses. Offsite doses would remain less than those currently reported in FSAR Table 15.6-8.
The offsite and control room doses will continue to meet the requirements of 10 CFR 100, 10 CFR 50 Appendix A GDC 19, SRP 15.6.5.II, and SRP 6.4.II. The dose reanalysis, combined with knowledge gained from recent studies on the behavior of iodine in the post-LOCA environment, demonstrates that the deletion of the Spray Additive System and replacement with a sump pH control system using TSP-C will not increase the reported radiological consequences of a postulated LOCA. The proposed new pH control system will provide satisfactory retention of iodine in the sump water, as well as provide adequate pH control to minimize the potential of chloride-induced stress corrosion cracking of austenitic stainless steel components.
The Containment Spray System will continue to function in a manner consistent with the plant design basis.
There will be no degradation in the performance of nor an increase in the number of challenges to equipment assumed to function during an accident situation.
These Technical Specification revisions do not affect the probability of any event initiators. There will be no change to normal plant operating parameters, ESF actuation setpoints, or accident mitigation capabilities. Therefore, these changes will not involve a significant increase in the probability or consequences of an accident previously evaluated.
(2) . Create the possibility of a new or different kind of accident from any previously evaluated.
The new Recirculation Fluid pH Control System is a passive system, i.e., no operator or automatic action is required to actuate the system. There are no active components being added whose failure could prevent the new system from functioning. The only new components i
Attachment 2 Page 3 of 4 being added are the TSP-C storage baskets. Seismic requirements have been included in the design to ensure the structural integrity of the baskets will be maintained during a seismic event.
No new accident scenarios, transient precursors, failure mechanisms, or limiting single failures are introduced as a result of these changes. There will be no adverse effect or challenges imposed on any safety-related system as a result of these changes. The use of dry sodium phosphates is allowed for adjustment of the post-LOCA sump solution pH as discussed in SRP 6.1.1. Trisodium phosphate has a dissolution rate of 0.7 lbm/ft2-min in water at 160 F (given in WCAP-12477, based on trisodium phosphate in the form of a solid block with no agitation of the solution). The quantity of trisodium phosphate chosen will provide a minimum equilibrium sump pH of 7.1 following dissolution and mixing. No new equipment performance burdens are imposed; however, there is the potential for an unlikely, but possible, event in which an initially concentrated solution of TSP-C occupies the stagnant volume of an inoperable sump. This situation would not last for long since, as the recirculated sump fluid is cooled in the RHR heat exchangers, sufficient buoyancy-driven circulation within containment will result to displace the stagnant solution and eventually yield a uniform, equilibrium solution. Therefore, the possibility of a new or different type of accident is not created.
(3) Involve a significant reduction in a margin of safety.
The radiological analysis performed for this proposed change, as discussed above, shows.that there would be no impact on the doses reported in FSAR Table 15.6-8.
There will be no change to the DNBR Correlation Limit, the design DNBR limits, or the safety analysis DNBR limits discussed in Bases Section 2.1.1.
There will be no effect on the manner in which safety limits or limiting safety system settings are determined nor will there be any effect on those plant systems necessary to assure the accomplishment of protection functions. There vill be no impact on DNBR limits, Fg, F-delta-H, LOCA PCT, peak local power density, or any other margin of safety.
Based upon the preceding information, it has been determined that the proposed changes to the Technical Specifications do not involve a significant increase in the probability or consequences of an accident previously evaluated, create the
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Page 4 of 4 possibility of a new or different kind of accident from any accident previously evaluated, or involve a significant reduction in a margin of safety. Therefore, it is concluded that the proposed changes meet the requirements of 10CFRSO . 92 (c) and do not involve a significant hazards consideration, t
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ULNRC-3050 ATTACHMENT THREE ENVIRONMENTAL CONSIDERATION
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Page 1 of 1 ElWIRONMENTAL CONSIDERATION This amendment application replaces Technical Specification 3/4.6.2.2, Spray Additive System, with a new Specification 3/4.6.2.2 entitled Recirculation Fluid pH Control (RFPC)
System. The current Spray Additive System will be retired, pending approval of this amendment request, and replaced with the passive RFPC System consisting of stainless steel baskets containing trisodium phosphate dodecahydrate (TSP-C) . One such basket will be located within the confines of each containment recirculation sump and will contain sufficient TSP-C to ensure a minimum equilibrium sump pH of 7.1. The new LCO will ensure that the amount of TSP-C contained in the baskets is greater than this minimum amount yet less than the basket design capacity. Mode Applicability and the Action Statement for the new specification are unchanged from the current specification while the Surveillance Requirements have been revised to correspond to the passive nature of the RFPC System. The Bases for 3/4.6.2.2 have been revised accordingly as have the Bases for 3/4.5.5, RWST.
The proposed amendment involves changes with respect to the use of facility components located within the restricted area, as defined in 10CFR20, and changes surveillance requirements. Union Electric has determined that the proposed amendment does not involve:
- 1) A significant hazards consideration, as discussed in ALtachment 2 of this amendment application;
- 2) A significant change in the types or significant increase in the amounts of any effluents that may be released offsite;
- 3) A significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed ame:idment meets the eligibility criteria for categorical excit- 'on set forth in 10CFR51. 22 (c) (9 ) . Pursuant to 10CFR51.22 (b) , no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
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- ULNRC-3050 ATTACHMENT FOUR PROPOSED TECHNICAL SPECIFICATION REVISIONS l
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.- SPR ADDITIVE SYSTEM LIMITI 1 CONDITION FOR OPERATION
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3.6.2.2 T e Spray Additive System shall- be OPERABLE with:
- a. A s ray additive tank containing a volume of between 4 40 and 454 gallons of between 31% and 34% by weight NaOH s ution, j and .
- b. Two spr additive eductors each capable of addi Na0H solution from the hemical additive tank to a Containme Spray System pump flow.
APPLICABILITY: MODES 2, 3, and 4.
ACTION:
With the Spray Additive Sys em inoperable, res re the system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT ANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; ;
restore the Spray Additive Sy +em to OPERAB status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within e followin 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
,- ) SURVEILLANCE REQUIREMENTS x -
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4 ~. 6. 2. 2 The Spray Additive Syste, sha 1 be demonstrated OPERABLE:
- a. At least once per 31 ays by v rifying that each valve (manual, power-operated, or utomatic) i the flow path that is not locked, sealed, or otherw e secured in sition, is in its correct position;-
- b. At least once r 6 months by:
- 1) Verify g the contained solution olume in the tank, and
- 2) Ver' ying the concentration of the a0H solution by chemical an ysis.
- c. At 1 st once per 18 months during shutdown, by verifying that each au matic valve in the flow path actuates to ts correct position o a Containment Pressure-High-3 (CSAS) test gnal; and
- d. At least once per 5 years by verifying
- 1) Each eductor flow rate is greater than or equ 1 to 52 gpm using the RWST as the test source throttled to 17 ps1 at the eductor ;
iniet, and j 2) The lines between the spray additive tank and the ductors are not blocked by verifying flow.
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CALLAWAY - UNIT 1 3/4 6-14 Amendment No. 44 Corrected
t CONTAINMENT SYSTEMS s
RECIRCULATION FLUID pH CONTROL (RFPC) SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.2 The RFPC System shall be OPERABLE with each of the two storage baskets (one within the confines of each of the two containment recirculation sumps) containing a minimum of 19", but not to exceed 36.8" (uniform depth), of granular trisodium phosphate dodecahydrate (TSP-C).
APPLICABILITY: MODES 1,2,3, and 4 ACTION:
With the RFPC System inoperable, restore the system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the RFPC System to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REOUIREMENTS 4.6.2.2 The RFPC System shall be demonstrated OPERABLE at least once per 18 months by verifying that.
(a) One TSP-C storage basket is in place in the confines of each containment recirculation sump, and ;
i (b) Both baskets show no evidence of structural distress or abnormal corrosion, and (c) Each basket contains between 19" and 36.8" (uniform depth) of granular TSP-C. l 4
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BASES REFUELING WATER STORAGE TANK (Continued)
The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
The limits on contained water volume and boron concentration of the RWST also ensure a p" ;;la: of bct;cca C. ;nd 11.0 for the solution recirculated within conta nment af ter a LOCA. This pH _..; minimizes the evolution of iodine and minimiz s the effect of chloride and caus it stress corrosion on mechanical j systems an components, '
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The 36-inch containment purge supply and exhaust isolation valves are required to be closed and blank flanged during plant operations since these valves have not been demonstrated capable of closing during a LOCA or steam line break accident. Maintaining these valves closed and blank flanged during plant operation ensures that excessive quant.ities of radioactive material will not be released via the Containment Purge System. To provide assurance that the 36-inch containment valves cannot be inadvertently opened, the valves are blank flanged.
The use of the containment mini-purge lines is restricted to the 18-inch purge supply and exhaust isolation valves since, unlike the 36-inch valves, the 18-inch valves are capable of closing during a LOCA or steam line break accident.
Therefore, the SITE BOUNDARY dose guideline values of 10 CFR Part 100 would not be exceeded in the event of an accident during containment purging operation.
Operation will be limited to 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> during a calendar year. The total time the Containment Purge (vent) System isolation values may be open during MODES 1, 2, 3, and 4 in a calendar year is a function of anticipated need and operating -
experience. Only safety-related reasons; e.g., containment pressure control or
- the reduction of airborne radioactivity to f acilitate personnel access for '
- survelliance and maintenance activities, should be used to support additional Lime requests. Only safety related reasons should be used to justify the opening of these isolation valves during MODES 1, 2, 3,. and 4 in any calendar year regardless of the allowable hours.
Leakage integrity tests with a maximum allowable leakage rate for
%y containment purge supply and exhaust supply valves will provide early indica-tion of resilient material seal degradation and will allow opportunity for repair before gross leakage failures could develop. The 0.60 L leakage limit of Specif.ication 3.6.1.2b. shall not be exceeded when the leakade rates deter-mined by the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.
3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1- CONTAINMENT SPRAY SYSTEM The OPERABilllY of the Containment Spray System ensures that containment
<'.aturization and cooling capability will be available in the event of a t00A r *ceam line break. The pressure reduction and resultant lower contain-wt c u 'e rate are consistent with the asrumptions used in the safety m r.e ,
The CW ainment Spray System and the Containment Cooling System are
- u % nt each other in providing post-accident cooling of the Containment atmospha e. However, the Containment Spray System also provides a mechanism for removing iodine from the containment atmosphere and therefore the time requirements for restoring an inoperable spray system to OPERABLE status have been maintained consistent with that assigned other inoperable ESF equipment.
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3/4.6.2.3 CONTAINMENT COOLING SYSTEM 1 The OPERABILITY of the Containment. Cooling System ensures that: (1) the containment air temperature will be maintained within limits during normal 1 operation, and (2) adequate heat removal capacity is available when operated in l conjunction with the Containment Spray Systems during post-LOCA conditions.
The Containment Cooling System and the Containment Spray System are redundant to each other in providing post-accident cooling of the Containment -
atmosphere. As a result of this redundancy in cooling capability, the allowable .. 1 out-of-service time requirements for the Containment Cooling System have been l appropriately adjusted. However, the allowable out-of-service time require-
- ments for the Containment Spray System have been maintained consistent with that assigned other inoperable ESF equipment since the Containment Spray l
System also provides a mechanism for removing iodine from the containment atmosphere. e .
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3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with the requirements of GDC 54 thru S7 of Appendix A to 10 CFR Part 50. Containment isolation within the time limits specified for those isolation valves designed to close auto-matically ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses f>:r a LOCA.
1/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to m.nintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions. Either recombiner unit (or the Purge System) is capable of controlling the expected hydrogen generation associated with: (1) zirconium-water reactions, (2) radiolytic decomposition of water, and (3) corrosion of metals within containment. The Hydrogen Purge Subsystem discharges directly to the Emergency Exhaust System. Operation of the Emergency lxhaust System with the heaters operating for at least 10 continuous hours in a 31-day. period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concentrations in Containment Following a loss-of-Coolant Accidert," Revision 2, November 1978. .,,
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3/4.6.2.2 RECIRCULATION FLUID pH CONTROL (RFPC) SYSTEM l The operability of the RFPC System ensures that there exists adequate TSP-C in the containment such that a post-LOCA equilibrium sump pH of greater i than or equal to 7.1 is maintained during the recirculation phase. The minimum depth of 19" inches ensures that 5000 lbm of TSP-C is available for dissolution to yield a minimum equilibrium sump pH of 7.1. This pH level minimizes the evolution ofiodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components. The upper limit of 36.8" corresponds to the basket design capacity.
CONTAINMENT SYSTEMS RECIRCULATION FLUID nH CONTROL (RFPC) SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.2 The RFPC System shall be OPERABLE with each of the two storage baskets (one within the confines of each of the two containment recirculation sumps) containing a minimum of 19", but not to exceed 36.8" (uniform depth), of granular trisodium phosphate dodecahydrate (TSP-C).
APPLICABILITY: MODES 1, 2, 3, and 4 ACTION:
With the RFPC System inoperabir restore the system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY ain the next 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />s: restore the RFPC System to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.2 The RFPC System shall be demonstrated OPERABLE at least once per 18 months by verifying that:
(a) One TSP-C storage basket is in place in the confines of each containment recirculation sump, and (b) Both baskets show no evidence of structural distress or abnormal corrosion, and (c) Each basket contains between 19" and 36.8" (uniform depth) of granular TSP-C.
CALLAWAY - UNIT 1 3/4 6-14 Amendment No. 44 Corrected
EMERQENCY CORE COOLING SYSTEMS l BASES REFUELING WATER STORAGE TANK (Continued)
The contained water volume limit includes an allowance for water not usable because ,
of tank discharge line location or other physical characteristics.
P The limits on contained water volume and boron concentration of the RWST also ensure a minimum equilibrium sump pH of 7.1 for the solution recirculated within containment after a LOCA. This pH level minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components. 1 CALLAWAY - UNIT 1 B 3/4 5 - 4 Amendment No. 42,68
CONTAINMENT SYSTEMS BASES 3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM The 36-inch containment purge supply and exhaust isolation valves are required to be closed and blank flanged during plant operations since these valves have not been demonstrated capable of closing during a LOCA or steam line break accident. Maintaining these valves closed and blank flanged during plant operation ensures that excessive quantities of radioactive material will not be released via the Containment Purge System.
To provide assurance that the 36-inch containment purge valves cannot be inadvertently opened, the valves are blank flanged.
The use of the containment mini-purge lines is restricted to the 18-inch purge supply and exhaust isolation valves since, unlike the 36-inch valves, the 18-inch valves are capable of closing during a LOCA or steam line break accident. Therefore, the SITE BOUNDARY dose guideline values of 10 CFR Part 100 would not be exceeded in the event of an accident during containment purging operation. Operation will be limited to 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> during a calendar year. The total time the Containment Purge (vei.t) System isolation valves may be open during MODES 1,2,3, and 4 in a calendar year is a function of anticipated need and operating experience. Only safety-related reasons; e.g., containment pressure control or the reduction of airborne radioactivity to facilitate personnel access for surveillance and maintenance activities, should be used to support additional time requests. Only safety-related reasons should be used to justify the opening of these isolation valves during MODES 1,2,3, and 4 in any calendar year regardless of the allowable hours.
Leakage integrity tests with a maximum allowable leakage rate for containment purge supply and exhaust isolation valves will provide early indication of resilient material seal !
degradation and will allow opportunity for repair before gross leakage failures could l develop. The 0.60 L leakage limit of Specification 3.6.1.2b. shall not be exceeded when the leakage rates determined by the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.
_3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the Containment Spray System ensures that containment depressurization and cooling capability will be available in the event of a LOCA or steam line break. The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the safety analyses.
The Containment Spray System and the Containment Cooling System are redundant to each other in providing post-accident cooling of the Containment atmosphere. However, the Containment Spray System also provides a mechanism for removing iodine from the containment atmosphere and therefore the time requirements for restoring an inoperable spray system to OPERABLE status have been maintained consistent with that assigned other inoperable ESF equipment.
3/4.6.2.2 RECIRCULATION FLUID DH CONTROL (RFPC) SYSTEM The operability of the RFPC System ensures that there exists adequate TSP-C in the containment such that a post-LOCA equilibrium sump pH of greater than or equal to 7.1 is CALLAWAY - UNIT 1 B 3/4 6 - 3
CONTAINMENT SYSTEMS BASES 3/4.6.2.2 RECIRCULATION FLUID oH CONTROL (RFPC) SYSTEM (Continued) maintained during the recirculation phase. The minimum depth of 19" ensures that 5000 lbm of TSP-C is available for dissolution to yield a minimum equilibrium sump pH ,
of 7.1. This pH level minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components. The upper limit of 3G.8" corresponds to the basket design capacity.
3/4.6.2.3 CONTAINMENT COOLING SYSTEM The OPERABILITY of the Containment Cooling System ensures that: (1) the containment air temperature will be maintained within limits during normal operation, and (2) adequate heat removal capacity is available when operated in conjunction with the Containment Spray System during post LOCA conditions.
The Containment Cooling System and the Containment Spray System are redundant to each other in providing post-accident cooling of the Containment atmosphere. As a result of this redundancy in cooling capability, the allowable out-of-service time requirements for the Containment Cooling System have been appropriately adjusted. However, the allowable out-of-service time requirements for the Containment Spray System have been maintained consistent with that assigned other inoperable ESF equipment since the Containment Spray System also provides a mechanism for removing iodine from the containment atmosphere.
3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated froin the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with the requirements of GDC 54 thru 57 of Appendix A to 10 CFR Part
- 50. Containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions. Either recombiner unit (or the Purge System) is capable of controlling the expected hydrogen generation associated with: (1) zirconium-water reactions, (2) radiolytic decomposition of water, and (3) corrosion of metals within containment. The Hydrogen Purge Subsystem discharges directly to the Emergency Exhaust System.
Operation of the Emergency Exhaust Systern with the heaters operating for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident," Revision 2, November 1978.
CALLAWAY - UNIT 1 B 3/4 6 - 4
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The post-accident parameters onditions is described below.
used in the equipment review are provided in summary form in Table 3.11(B)-2 and as used in the review, in Figures 3.11(B)-1 through 84. }-f a ay,.f,,.n a m dn.a, we,.a jne,.gasad' f fnad};}
"h0lAerion!/s 3'/ s e coun+ +Ae rey /aeemen}- A No aeft Radiattor> J rny addifive tyr/em wi e j>attive syb dMe o's in e con}sinmen-} escirca/a/ien swyr con}sinina -f>-irodian, p/w,>la}e, Using he dance of NUREG-0588, post-LOCK radiatiort' environ-ments ere determined in all areas of the containment. The origir al fission product release data used in this analysis l were cbtained from Westinghouse. The isotopic inventory provic ed by Westinghouse was for an equilibrium cycle Callaway
; core. The data were calculated at the end of cycle life and, therefore, represent maximums suitable for post-accident evalua tions. This source term is referred to as the licensing basis EQ source term, applicable to the initial core load.
Subsecuent cycles have seen changes in fuel type (from STD/LOPAR to OFA to VANTAGE 5), power level (from 3425 MWt to 3579 P Wt), and burnup (up to 60,000 mwd /MTU as discussed in Sectio 4.2.1). The doses reported in Table 3.11(B)-4 have been increased by 5% to account for these effects.t The following discussion refers to the initial calculations performed with the licensing basis EQ source term and a 50% cesium release fraction. The accident scenario assumed that a LOCA event occurred - causing core damage. The entire source of 100 percent noble gas inventory, 50 percent of the core halogen inventory, 50 percent of the cesium, and 1 percent of the other solids was released to the containment. This release was conservatively assumed to occur at time zero. For the liquid source, 50 per-cent of the halogens, 50 percent of the cesium, and 1 percent of the remaining fission product solids were assumed to go directly to the sump and were diluted by the volume of the refueling water storage tank (RWST) and the liquid volume of the reactor coolant system. For the airborne source, 100 percent of the noble gases and 50 percent of core halogens were assumed to be released to the free volume of the containment. The 3 simultaneous release of 50 percent of the halogens to the
) atmosphere and to the sump introduced additional conservatism. ;
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Credit was taken for mechanistic remaval of the airborne iodine : via containment spray and plateout. The spray removal lambdas ) for elemental and particulate iodineywere taken from E;; tion -//e cm/ca/m/4/ ! The plate-out removal lambda n o d;tuc.ined using method V4/ust
-fr-J .
ology outlined in NUREG/CR-0009. he surface area available ////*/ In for plateout was assumed to be eq ivalent to the heat sink area W /8 used in the containment pressure analysis given in Table 6.2.1-4. [.#-2, In addition, two of the four hy ogen mixing fans were assumed to be operating, at 42,500 cfm .ach, to provide mixing between g the sprayed (86 percent) and u sprayed (14 percent) regions of
) the containment. These remov 1 processes were assumed to
- persist until the elemental nd particulate iodine in the (I.sr A;') wu ca/cuMed Rev. OL-6 3.11(B)-5 6/92 ;
CALLAWAY - SP sprayed region were reduced by factors of 200 and 10,000, respectively. S NTE M '/ To determine the gamma dose rate inside the containment, the multigroup, three-dimensional, point kernal code QAD-CG was used to take credit for all major internal structures. The containment was divided into regions, and the maximum dose rate within each region as a function of time was determined. These dose rates were assumed to apply to all equipment within that t Rev. OL-6 3.ll(B)-Sa l 6/92
i INSERT 1 These decontamination factors (DFs) were taken from Reference 22. The spray removal rate for elemental iodine was calculated in Section 6.5A.2 to be 25.7 hrl. This spray removal rate plus the plateout removal rate (25.7 hrl
+ 1.58 hrl) were assumed to be effective in the sprayed region until an elemental iodine decontamination factor (DF) of 200 was reached in the EQ dose calculations. Only the plateout removal rate was assumed to be effective in the unsprayed region until an elemental iodine DF of 2 was reached in the EQ dose calculations. The spray removal rate for particulate iodine was calculated to be 0.73 hrl in Section 6.5A.1 and was assumed to be effective in the sprayed region until a particulate iodine DF of 10,000 was reached in the EQ dose calculations.
It is noted that the offsite and control room doses discussed in Section 15.6.5 were calculated using an elemental iodine spray removal rate of 10 hel and a particulate iodine spray removal rate of 0.45 hrl, until a DF of 28.7 was reached for elemental species and a DF of 50 was reached for particulate species. No plateout removal lambda was used in the Section 15.6.5 dose calculations since credit was taken for the instantaneous plateout of half of the iodines released to the containment atmosphere (i.e. 25% of the core iodines). With the replacement of the spray additive system with trisodium phosphate baskets in the containment recirculation sumps, the minimum equilibrium sump fluid pH is reduced to 7.1. This reduced pH results in a reduced spray partition coefficient (H, from Equation 6.5A-15 on page 6.5A-7) of 1100 per Reference 23. Using Equation 6.5A-15, the resulting elemental iodine DF was calculated to be 28.7 for the analysis of offsite and control room doses discussed in Section 15.6.5. Per Reference 24, the particulate iodine spray removal rate, calculated using Equation 6.5A-1 on page 6.5A-2, can conservatively be based on an assumed E/D of 10 per meter initially, changing to 1 per meter after a DF of 50. After the particulate iodine spray removal rate is reduced, there is no DF limit. However, for simplicity and conservatism, removal was assumed to stop after a DF of 50 was reached in the analysis of offsite and control room doses. With consideration given to these reduced DF values for elemental and particulate iodines, airborne gamma doses listed in Table 3.11(8)-4 have been estimated to increase by 3% as a result of the use of the trisodium phosphate baskets.
CALLAWAY - SP region. Each dose rate was numerically integrated to obtain
) the 180-day integrated dose for each region. The beta dose rate as a function of time was obtained assuming a semi-infinite cloud model. These dose rate values were also numerically integrated to obtain the 180-day beta doses for each region.
The gamma plate-out was modeled using a cylinder with a height and radius equal to that of the containment. The dose rate was obtained at the center of the cylinder without taking credit for air attenuation. Beta dose rate contributions due to plate-out were obtained assuming a contact dose rate. The resulting containment integrated dose curves are provided as Figures 3.11(B)-50 through 3.11(B)-84. Per the commitments to Regulatory Guides 1.7 and 1.89 in Appendix 3A, a 1% cesium source term is sufficient for Callaway. However, the radiation levels reported in Table 3.11(B)-4, obtained using a 50% cesium source term, were utilized during the NUREG-0588 review. Due to the extreme conservatism in the equipment specifications, most components were qualified to this radiation level. For the isolated cases where the 50% cesium source term radiation proved too severe (i.e. electrical specifications J-301, J-481, J-1030, J<'^a ESE-3A and mechanical specifi ations ESE-21, ESE-48A), t.he equipment was evaluated against < 1% cesium source term. Pressure, Temperature, and Humidity 20/// Callaway unique containment pressure-temperature profiles were utilized for the current equipment evaluation to NUREG-0588. The temperature and pressure conditions were evaluated for both LOCA and MSLB accidents. The resulting containment temperature and pressure profiles are provided in Figures 3.11(B)-1 through 6. The maximum containment temperatures are 308.6 F and 384.9 F for LOCA and MSLB conditions, respectively. The maximum containment pressure utilized for evaluating both accidents is 63 psi a. For the evaluation of equipment located inside containment, _ pressure-temperature enveloping profiles for Callaway have
'. been generated. These environments were generated for a spectrum of MSLBs and LOCAs. For LOCAs, full and partial double-ended breaks and split breaks in the pump suction line were evaluated. Full double-ended hot and cold leg breaks were also analyzed. For the main steam lines, a spectrum of break sizes (split and double-ended) at various power levels wit + minimum entrainment were evaluated. For these p aluations, loss of offsite power and a worst single failure were assumed. Pressure and temperature mitigation from the operation of safety-related containment sprays, air coolers, and heat transfer to structures was considered.
3 All methode applied in the determination of environments are in j accordance with Sections 1.1 and 1.2 of NUREG-0588, Revision 1 for Category I plants. The evaluation of mass and energy Rev. OL-6 3.11(B)-6 6/92
CALLAWAY - SP S a. The peak qualification temperature envelopes the peak J- uprating temperature with significant margin (384.9 F vs. 352*F).
- b. The total heat transferred into the equipment is greater for the previous EQ profile (Fig. 3.11(B)-3) than for the uprating profile, particularly at 45 seconds. This is possible since the EQ pressure at 45 seconds is higher -
than the uprating pressure (55 psia vs. 45 psia) and the condensing heat transfer coefficient is orders of magnitude greater than convective heat transfer coefficient.
- c. The equipments' thermal lag makes small deviations from an accident profile insignificant in comparison to the
} overall profile.
Therefore, there was no impact on equipment qualification as a result of the plant uprating to 3579 MWt. Containment Spray The Callaway design utilizes two redundant trains to supply containment spray for temperature and pressure reduction - and fission product removal from the containment atmosphere. Table 3.ll(B)-5 identifies the containment spray requirements. The Standard Review Plan indicates that single failures should ' 1 be evaluated to determine the worst case chemical concentrations.
.) The worst case concentrationsg"reculting frer e cingle failure,
' are pH = 4.0 and pH = 11.0, as discussed in Section 6.5.2.3. :
#f// de A caustic spray with an upper limit of pH = 11.0 4ebbsed in 44we d32 s I
review $,Peucver, it ic rcccgniced that thic cycnt aill cnly I cccur for chcrt period.- A boron concentration of 2050 ppm. was used in the EQ reviews. The Cycle 4 change to an RWST boron concentration of 2350-2500 ppm has a negligible effect on peak pH, therefore the corrosive effects of the containment spray are not increased. As such, there is no adverse EQ impact arising from this change in RWST boron concentration.
-s 3.11(B).1.2.3 Accident Environments - Outside Containment
) Radiation Using the guidance of NUREG-0588 and NUREG-0737, post-LOCA dose rates and doses were determined in those areas of the auxiliary building where safety-related equipment qualification would be reviewed. The fission product release data used in this analysis were the same as discussed in Section 6.2.1. The analysis for the auxiliary building yielded a conservative upper bound estimate for the doses to all safety-related electrical equipment as required by NUREG-0588. See Section 3.11(B).1.2.2 regarding source term changes since the initial
% core load. The following discussion refers to the initial
) .calculatio s performed with the licensing basis EQ source term and a 50% esium release fraction.
.TNIER7 :2. Rev. OL-6 3.11(B)-Ba 6/92
s i INSERT 2 With the replacement of the spray additive system with trisodium phosphate baskets in the containment recirculation sumps, the doses in penetration rooms 1409-1412 and 1506-1509 in Table 3.11(B)-2 have been estimated to increase by 8% due to the harder spectrum of gamma energies associated with the iodines.
'k
+
t f f i p r l
~
CALLAWAY - SP
~~
)
- 17. SLNRC 83-054, " Instrumentation and Control Systems Branch g Review," October 27, 1983.
- 18. WCAP-9230, Rev. O, " Report on the Consequences of a Postulated Main Feedline Rupture, Proprietary."
- 20. ULNRC-1471 "Callaway Plant Uprating Submittal", March 31, 1987.
- 21. ULNRC-1618 " Responses to Questions on Callaway Uprating",
September 18, 1987. 1~N TEX 7~ 3' s, I l
)
l l 1 Rev. OL-3 3.11(B)-32 6/89 l
INSERT 3
- 22. NUREG-0588, Revision 1, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," Part II, Appendix D, page IID-4, July 1981.
- 23. E. C. Beahm, W. E. Shockley, C. F. Weber, S. J. Wisbey, and Y. M.
Wang, " Chemistry and Transport ofIodine in Containment," NUREG/CR-4697, October 1986.
- 24. NUREG-0800, Standard Review Plan Section 6.5.2, Revision 2,
" Containment Spray as a Fission Product Cleanup System," December 1988.
I i l l l
CA!1ANAY - SP TABLE 3.11t B)-2 IShoot 31 i l DBA DBA D8A DBA Environmental Pressure Temp. RH % Dose ph Max. F IO N 'I Area Max. IpsiglI 'I Nax . I O I! ' I 1 Rad 1 II0I DBA
- fRoom No.
uniliary Building I II'I Auxiliary feedpump Atmospheric 104 70 7.26 x 10 i 1325 ' imotor1 room II'I I Auxiliary f eedpump Atmospheric 104 70 6.66 x 10 1326 (motor) room 1327 Feedwater pump valve Atmospheric 104 70 8.79 x 10 2 ccapartment No. 2 Feedwater pump valve Atmospheric 104 70 8.79 x 10 1328 compartment No. 3 Vestibule 1.0 110 73 8.79 x 10 2 1329 1330 Feedwater pump valve Atmospheric 104 70 8.79 x 10 compartment No. 4 I 1331 Auxiliary feedpump Atmospheric 142 100 8.85 x 10 (turbine) room 116) CCH pump room 1.0 106 71 4.48 x 10 1401 1402 Corridor No. 1, 1.0 106 71 1.55 x 10 2 El. 2026' E 1406 II'I CCH pump room 1.0 106 71 4.85 x 10 Corridor 1.0 106 71 7.88 x 10 1408 1409 Electrical pene- 1.0 106 71 + rte =x 10' c tration room /,27 1410 Electrical pene- 1.0 106 71 .4. & x 10' tration room /,% t18) 100 W x lo' Main feedwater room 6.7 324 No. 1 /, /[p
,y )14111412 Main feedwater room No. 2 6.7 324' 100 &,49 x 10
/,/f Auxiliary shutdown 1.0 106 71 1.10 x 10 1413 panel room 1501 Control room a/c Atmospheric 104 71 7.14 x lo equip room 1502 CCW surge tank area 1.0 106 71 8.92 x 10 l (B)
I CCH surge tank area 1.0 106 71 9.58 x 10 1503 (A) 2 Ctat purge exhaust 1.0 106 71 3.97 x 10 1504
% and mech equip.
) room (B)
Same as room 1504 conditions .3.,4e=x 10 5 1506 Ctmt. purge supply air handling unit 7, 73 room iA1 4,44- x 10 0 1507 Personnel hatch 1.0 106 71 aren El. 2047'-6" /,gg
.J J
s Rev. OL-4 6/90
CALLANAY - SP~ TABLE 3.111B 1-2 (Sheet 4 9 DBA DBA DBA DBA Environmental
~"
Pressure Temp. RH % Dose ph Room No. Area Max. IPsign II Max. F IO M 'I Max.I8II'I (Rad)II*I _ DB.
-l Auxiliary Building 1508 Main ateam/ main 6.7 3248' 100 4,9P x 10' feedwater isolar,3 /, /f tion valve room 1509 Main steam / main 6.7 324 II8I 100 W x 10' feedwater isolup9, /, /f tion valve room E
1512 Control room a/c Atmospherie 104 71 3.13 x 10 equip. room 1513 Control b1dg a/c 1.0 106 71 3.13'x 102 equip. room Control Buildir.g ) 3101 Pipe space tank area Atmospheric 120 95 <2.5 El. 1974' 3105 Control building Atmospheric 120 95 <2.5 cable chase 3106 Control building Atmospheric 120 95 <2.5 cable chase 3222 Health physicists Atmospheric 120 95 <2.5 office, El. 1984' 3224 Vestibule No. 2 Atmospheric 120 95 <2.5 El. 1984* 3229 Control building Atmospheric 120 95 <2.5 cable chase 3230 Control building Atmospheric 120 95 <2.5 ,N cable chase IIII Atmospheric 90 70 <2.5 _/ 3301 ESF switchgear room II7I Atmospheric 90 70 3302 ESF switchgear room (2.5 3404 II7I Switchboard room Atmospheric 90 70 <0,0005 ( No. 4 ) 3405 IIII Battery room Atmospheric 90 70 <2.5 3407 117) Battery room Atmospheric 90 70 <2.5 IIII Switchboard room Atmospheric 90 70 <0.0005 3408 ( No. 1 ) 3410 II73 Switchboard room Atmospheric 90 70 <0.0005 (No. 2) 's 3411 II I Battery room Atmospheric 90 70 <2.5 ) 3413
' Battery room Atmospheric 90 70 <2.5 3414'I ' Switchboard room Atmospherie 90 70 <0.0005 (No. 31 Rev. OL-3 6/89
CALLAWAY - SP TABLE 3.11 (B) -4 CONTAINMENT WORST CASE RADIATION LEVELS (MRADs) UPPER ABOVE SUBMERGED SOURCE CTMT. SUMP IN SUMP Gamma f PD 3. /b Airborne Source ST + 0 4,49 + 0 Negl. Liquid Source 1.52 + 1 6.32 + 1 1.26 + 2
.-) Plateout Source 9.24 - 2 1.39 - 1 Negl.
Total 42-34 + 1 -6 4+ + 1 1.26 + 2
.:2.4/ g. 4 f' Beta Airborne Source 1.46 + 2 1.46 + 2 0 Liquid Source 0 0 1.55 + 1 Plateout Source 1.40 + 1 2.08 + 1 0 Total 1.60 + 2 1.67 + 2 1.55 + 1 Total 1.84 +2 2.33 +2 1.42 +2
)
s
-3 Rev. OL-6 6/92
, , CALTAWAY - SP TABLE 3.11(B)-5 CONTAINMENT SPRAY REQUIREMENTS Sprayed Fluid Injection Phase Aqueous Solution, pH ' r= . , } - 41.C 80"Z4 Boric Acid, ppm boron (max./ min.) 2,500/2,350 Sprayed Fluid- Recirculation Phase
itr centinued "20!: :.ddit i:n' Aqueous Solution, pH 'rs. . ) M 7. / ~ //.O Boric Acid, ppm boron (max./ min.) 2,500/1,0Ot l
.::?,de7 Oprayed Fluid necirculntien Pharc _
?qdcouc Sclution, p!I I.C 10.0
'-m: /~d- T 2,500/_,000 Ocric 7.cid, ppr beren l Finalg Sump Fluid Aqueous Solution, pH C " ' ^ " 7. /~ I. O
, Boric Acid, ppm boron (max./ min.) 2,500/0,07 Og ed /-
gfusj,,jonum i Rev. OL-7 I 5/94 1
P
* ' " * '~
g j 7 } 6 k ( 0 ) l ON Md-H l CONTAINMENI SPRAY PUMP
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8
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g.s.. ,- ) m.;= u cam, ts .. CALLAWAY PLANT 7 . . . ,, .. . , SPRAY N )?/L F_ ri BCM7J FIGURE 612-1 CON 7amuENT SPRAY SYSTEM A (U-22EN01(0) 2t e . DWD3zb e o _ i.t -i . . . _ ._._.._ _ .l_ _ _ .
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- t, - - - P -4 w'II' O.
L .O. . ff S 38. 1CBS
- m 3-g c ,, ,
SPRAY ADDITIVE EDUCTOR
~
04 GLS 3' 10 at=cs
# y 3*
e 3+ *(V *- f W .*M [1 29 *(D.. a
- O 33-3 *_ 4 jD h 1 Fvo24 5, _,, jgt C.
ise f 46 6- . * *CD- 3* O
- .,4,. -->4.
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" ?o i'ses T%D i SPRAY
" * ~ ' '
ADDITIVE 's a 'as< l _ TANK U O' _.: 1.- P_ R I a if ,, e . .
} .. e em m
*c45 ra n ,
.083
- P ggn u e- = P 3
o+* 3- b
., a f
"3 m We g i
.J /
SPRAY ADDITIVE EDUCTOR LSEM lEJ
,, 3 s0*?.
T LELw_ULI '4 Esl~>3 ,
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- 'cg s, ;
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=
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- SPRAY PUMP o. a -s- D u Y
P-]i. g --.; j i- ,
%'::!="s-hg..l; g'---g ---
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I I - - a91n=,,p-- hDP .
. , . , - . = , .
o ,,
. - CALLAWAY - SP Radiciodine in its various forms is the fission product of primary concern in the evaluation of a LOCA. It is absorbed by the containment spray from the containment atmosphere. To enhance this iodine absorption capacity of the spray, the spray solution is adjusted to an alkaline pH which promotes iodine hydrolysis, in which iodine is converted to nonvolatile forms tending to plate out on containment structures or to be retained in the containment recirculation sumps. The physical characteristics of the. CSS are discussed in Section 6.2.2.1. Discussed herein I+<- the cpray additive portien of *ha cy 'e- -nd the containment spray system's fission product removal capability following a LOCA. 6.5.2.1 Design Baces 6.5.2.1.1 Safety Design Bases SAFETY DESIGN BASIS ONE - The CSS is designed to provide an_T~N S 6 6 Y cpray celutier 'hile the cpray additive porticr of the cyctem is in operation in thc pH rang: of 0.3 to 11.0 and a final l eer.tcinment recirculation cump colution with p" of at 1ccat _n e u.a. SAFETY DESIGN BASIS TWO - The CSS is capable of reducing the iodine and particulate fission product inventorics in the con-tainment atmosphere such that the offsite radiation exposures resulting from a design basis LOCA are within the plant siting . dose guidelines of 10 CFR 100. l Additional safety design bases are included in Section 6.2.2.1, in wnich the capability of the spray system to remove heat from the containment atmosphere is discussed. 6.5.2.1.2 Power Generation Design Basis The CSS has no power generation design basis. 6.5.2.2 System Design 6.5.2.2.1 General Description The centainmcat-epray additivc portion of the CSS providec for eductier of 31 20 veight perccat codium hydronidc inte the l cprny injectier cclution Thic yic dc cpray r.irture ri tF a
-pH cf f rom 9. 3 tc 11.0 during the injecticn phace, her l
- redi ci edir e in beinc rcreved frcr the
-/ank / or Se en redired In f */e e contei r enteroded and a.r.n atmcepher^Nve
/Inar l laen cayek at The spray additiveVcubryci - - of the CSS, shown schematically in Figure 6 . 2 . 2 - 1, -een c i c t e of one cpra y addi t "^ trab, t'z'e
-eductor", "civer, nd co necting piping. Th^ cyctw urer thm
-containment cprcy pumpe and opray headerc, cc dcccribcd ;r CCCtion C.2.2.1, to dcl:vcr nd distribut: th^ Cprc; add 5ti":
Rev. OL-4 6.5-4 6/90
INSERT 4 1 I equilibrium sump solution pH of greater than or equal to 7.1 following the complete dissolution of the trisodium phosphate stored in baskets within the confmes of the containment recirculation sumps. l l l I l 1 j l l 1 I
1 l I
. - CALLAWAY - SP l
-eelutier te the cent 2inment atrecpherec Initially, water from l the refueling water storage tank (RWST) is used for containment i
} spraying followed by water from the containment recirculation sumps. Sodium hydrexide in educted f:cr the cpray cdditiv
-tan' inte th: vatcr frcr the P4CT and centcinment rccirculation
=cump: 2nd pumped te the cpr2y ring henderc nnd ne:21cc l candninman+.Qorng flutd.r Those parts of the system in contact withV bernte_ atcr cr the 1
-codiur hydroxide cprny 2dditi"e, er mixturec of the tre,- are {
stainless steel or an e stant mate ial Jar} eft chv}rae}t) in /e.rr ha uAde) E ,',"
-/>i.rodium,i TheVctn
= leg cc nij/ua-/e cteel cprey (7Tf.-C)quivalent 2dditive tark corrosion-contain [ sufficient es 7T/?-C or'uge fr ,
31 30 ccight percent rediur hydroxide cprey edditive relutien l to bring the sump fluid to a minimum pH of 4-6 upon mixing with ~5} , the borated ater from the refueling water sto age tank, 44Hr her:r inj ec :d e- t:r', the accumulators, and r actor coolant. This assur_s continued iodine retention effec iveness of the sump wate du 7. / eguo,ri[ng,
/i rium the recirculation phase.
4tc tec cprey 2dditive educterc 2re 2-incP mining educterc The unito drcu the 32 31 veight pcreent codiur hydrenide cprcy l edditivc colution into thcir cuction by ucing bcrated unter, diccFcrged by the containment cpray pumpc, 20 their motive fler. l The spray header design, including the number of nozzles per header, nozzle spacing, and nozzle orientation, is provided in Section 6.2.2.1 and shown in Figures 6.2.2-2 and 6.2._2-4. Each
' spray header layout is oriented to provide more than 90-percent area coverage at the operating deck of the reactor building.
Total containment free volume, unsprayed containment free volume, specific unsprayed regions and volumes, and post-accident ventilation between sprayed and unsprayed volumes are provided in Table 6.5-2. Operability of dampers, ductwork, etc., for which credit is taken post-accident is discussed in Section 6.2.2.2. 6.5.2.2.2 Component Description -~~. The mechanical ec=ponente of the oprcy additive cubcyctcm crc
} deceribed ir thic cectier other compenente in the contain ment cprcy cyctcm crc dcccribcd in Ecction 5.'.2.1 SprOy cdditiv: cubcyctem comp ncnt dccigr pcremeterr Orc giver ir
__ u , _ -.e e
. ~ .
ja a,,,, g4na ),d,
+ica in p al c e .
The containment spray additive tank, located at El. ,000 feet in the auxiliary building, is a stainless steel tank ith 2 nitregen gec blanhet decigned tc centcin 21 21 percent by weight- l codiur hydronide celution The capacity of the tar ic giver in Tsbic S.5 2, ? Iccal ccmple co-nectie- el'eur ped ^A4"
-t Rev. OL-4 6.5-5 6/90
. l i CALLAWAY - SP l 1 1 r wicc: enclycic of thc contente, cnd fill and drain connectic:-- 1 pro de for initial fill, concentration adjustments, and mainte nce. A manway is also provided for tank internal
.nspecti .
Tank level, pressure indication, and alarm s-3
- rumentatio are provided. l l
1 An interlock is ovided from the tank level tra preclude closure o the discharge valves befor sufficient itters to l l laOH has been added the spray solution t comply with the sump pH criterion. { Hea tracing of the s ay additive tank and associated piping con ning 31-34 eight percent NaOH is not required since the auxil ry bu ing rooms (areas [ containing this tank and the a- _ated piping) are heated to 4 l maintain temperatures at no le an 60 F. The containment 3 pray additive tank is provi ud wit verpressure protection and vacuum relief. Setpo ts of the r ief devices are provided in Table 6.5- l i kdium hydroxide added to the spray liquid a liquid jet 2ductor, a devi which uses kinetic energy of a ressurized Liquid to en ain another liquid, mix the two, and scharge bhe mixtur against a counter pressure. The pressurio d liquid this case is the spray pump discharge which i sed to e ain the sodium hydroxide solution and discharge the ni 'ure into the suction of the spray pumps. The eductors a
.ccigned te accurc c minimum pII of 0.3 for th^ aprc; minture. l l
Component descriptions of the nozzles are provided in Section 6.2.2.1. Special tests performed on the spray nozzlesinclude } capacity and droplet size distribution. l Fi gu re s 6. 5 -i , 6.5-2, l and 6.5-3 provide the test results for the spray nozzles (Ref. 1). I i The spray nozzle was flow tested at a range of inlet pressures l from 3 to 100 psig to determine that the actual flow at 40 psi l differential across the nozzle was in accordance with the design value of 15.2 gpm, as depicted in Figure 6.5-1. Droplet-size distribution measurements were performed at the l design pressure differential of 40 psi and the design flowrate l o f 15 . 2 gpm . At these conditions, the spray distribution was l obtained by measuring the spray volume distribution in two perpendicular planes over a timed interval (Ref. 1). For the droplet size distribution measurement, a television camera and light source were mounted on a flat beam. A pro-tective covering was constructed with a slot which allowed ; spray droplets to fall between the camera and light source. l Measurements of drop count in each micron increment were re- ' corded at 4-inch increments from the outer edge of the spray cone to the spray axis. l Rev. OL-4 6.5-6 6/90 l
I CALLAWAY - SP l At the design pressure, the droplet size distribution was re-
. corded by high speed photographic methods. The droplet images were measured, and droplets with a diameter in the micron in-crement being counted.were registered. Figure 6.5-2 shows the relative frequency for each droplet size. The results of testing performed on the spray nozzle are provided in Table 6.5-2. The containment spray envelope reduction factor as a function of post-LOCA containment saturation temperature is provided in Figure 6. 5-4. This envelope reduction factor was '
applied to the throw distance and elliptic coverage values presented in Table 6.5-2. 6.5.2.2.3 System Operation
)
Summary of the design basis LOCA and MSLB chronology for the l CSS is presented in Table 6.2.2-3. ' The spray system is actuated either manually from the control room or on coincidence of two-out-of-four CSAS containment pressure signals. Either of these actuation mechanisms starts the containment spray pumpsg opens the discharge valves to the spray headers, and opone the apray
'dditive tank. tb(_ v and a lve c - a c c c c i a t-ed ci tF recirculnlsd.
On actuation, app oximately 5 percent of each spray pump's I discharge flow is.divcrted thrcugh each cprcy additive eductor i I tc drcw ccdium hydronid; from the spray cdditive t a r': The l
-!!ur hydrenide c e lu ti c:. mince ei th the liquid entering the-cuctier line cf the pumpc te give a colution cuitable for removal of iodanc frc the contairment atmerp kcre.
When the refueling water storage tank has reached its specified low-low-2 tlated. level limit, recirculation spray flow is manually ini-The operator can remotely initiate recirculation flow by use of either or both of the spray pumps. Sections' 6.2.2.1.5 ! and 6.5.2.5 address the instrumentation and information displays ; available to the operator, in order for manual switchover of the CSS to take place. 4 System flow rates and the duration of operational modes are presented in Section 6.2.2.1.2.3. Design operation of the CSS 2nd the contairment rpray cdditi"e c"keyc'a- is such that LOCA iodine removal requirements are fulfilled during the injection phase and the amount of 14eOH ~7'I'/2.C grov//e/ 2docd-is sufficient to ensure long-term iodine retention. Op
+ ration of the containment opray additi;c cubayctcm is rcmetc manaclly terminatcd fcllowing thc cduction of the pr::cribed qu .tity of "nOF which accurec minimu: leng-terr cump pF cf et lenct 9.5 ^utomatic icc10tien of the' containment cpray additive cubcynter occurc uper receipt of 2 ~ '- 2 01 le"el rigrnl frc- *he cpray additive t a r ic"cl ir-t:rmentc. The 3
Eontainment iodine removal credit assumed in the calculation of offsite doses following a LOCA is provided in g^aptcr lE.C. 95}le /S.S~S. JCAU'EA7' pey, on_o
'I 6.5-7 6/86 l
. . .l
1 l
. I l
l INSERT 5 l l Following a large break LOCA, the containment spray during the injection phase will be a boric acid solution having a pH of about 4.5. The desired pH level is greater than 7.0 to assure iodine retention in the sumps, to limit ; corrosion and the associated production of hydrogen, and to limit chloride induced stress-corrosion cracking of austenit:c stainless steels. To adjust the sump solution pH into the desired range, a mir.imum of 5000 pounds of trisodium phosphate dodecahydrate (Na3 PO4 + 12 H2 0 1/4 NaOH)is stored in two baskets, one within the confines of each containment recirculation sump, which will be submerged after a LOCA. This amount of trisodium phosphate is sufficient to assure that the equilibrium sump solution pH will be greater than or equal to 7.1. I l l l l l l
c - CALIaWAY - SP 6.5.2.3 Safety Evaluation The safety evaluations are numbered to correspond to the safety design bases.
. ( .rar-fa c e are A SAFETY EVALUATION ONE - The system's capability to reduce the airborne fission product inventory is based on the v pH- of the spray solution for removal during injection and for retention during recirculation, and on the system's capab lity to provide spray for essentially all regions of the conta nment, considering post-accident conditions. o n ,r u n y ro /u fh J
. .w a ,,w ,,e
-, ,,m,_... .-y..
, __n , n , _.,.m.._
n_,w .. m a_ ~_. 4. . .c,,,.
,,, 4 m. 4 ,.m. . . . . ,y _. . -.-, . . . . . , . . ..y..
_g-e -n . n. . , ..w s_ _, . +.. w .,y,,.... - w ,. _4. . ..~ - . . . ,,m..,.-4,,.,,m. ., ,,, , c ,s w e_ ,. n_ ,
. ~m - - . . . - . . - . - - - _
a 4. .e,_em ,e
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- ,a _ ._. : e .a m,.~
. ~ ~
m, m .. m - . m , m .m. ._, 9_ _4 ,s A 4 ,, o-.
- t. . ,, _- . . . - k~ .,~m.., .- m ~ _ m ..k. m .mm. , , . . ~
.~.. .~ _ ..
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m r..,- - _ . .
-phace-. The 1 a3 < i.. minimum sump pH of G:-5 A assures iodine retent on in the recirculate spra '/, /
XNMCT~g egui/;y j,.ru liquid,,,,
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- m. m.~ e,.,._,,
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A
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n- - am- . 5 m.,. - c. c -~-
-. ~.- .e . e., .
. e gj Q The system is designed to provide a . ray solution 4r the CSS--
during the recirculation phase, with a r.:xi~.= e pH offlocc "^ thar 11. O
, - . . .- _-*#^_
' ^- 'A"
- a. . , - m.~a ,
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+. - " . ~ ..~..'.y-
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- ~_r., - in e -
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-:.w .. u. . _g...,.
j n ,_ . . .:
.. w. . . v .e - . . .
bmleveI Rev. OL-7 6.5-8 5/94
INSERT 6 During injection, the effectiveness of the spray against elemental iodine vapor is chiefly determined by the rate at which fresh solution surface area is ' introduced into the containment atmosphere, as discussed in Reference 3. The first-order spray removal coefficient calculated per Reference 3, as discussed in Section 6.5A.3, is 37 hr-l. Thus, the elemental iodine removal coefficient of 10 hr-1 used in Section 15.6.5 is conservative. 9 L 1 P
- r. .w. ._-w--, , , ,-.,- . -, - - - ._m
CALLAWAY - SP i ./f e i,
- e darb
-fe M ?!,.r.ec-Hm.e , % 7.j l*s.r*nAa,, MMY Se j"Y"! N 'n k *["*l
~w 0.2 and 21.0 during the injcction phasc and bctwccn 0.0 and 10.0 l
) -dering t'c re irculatic." phace - The worst case concentra tioner-rcculting f rc: a =ing1; f ailurc, arc p" - ^ . 0 and pi: 11.0. Thc cclue a cingic failure of one of the ofpF-'h.0recultefrc-containment op 1 n id i ' ' -- t h asciation valvcc. If onc of
-- thc s c two valyc; fails to epcn,0 water from the refueling water storage tank -{p" - 2.0)-is sprayed directly to the containment.
.:- +u rr~.s-> w : ., ..:su,,+ un w- ,AA-> > c
~"
,, ~ -c onh'aktheseva5vebtoopeSNteisAn~un5ike[yevent. Prior t$
fuel lo a jumper is installed around the thermal overloa to ensure t power to open the valves is not interru d.
"he valves are wered from safety-related power so ces that have multiple sour (including the diesel gene tors). If one of these two valve should fail to open e to a loss of
_s}. power, it is probable tha- " e rest of t affected train would also not have power to operate. The . ore, no spray would be
- .ntroduced from that train. In t unlikely event that one of these valves did fail to oper - and rest of the affected train did function, this e ition would immediately identified
- .n the control room on le ESF status panel. f one of these
" alves does not op (and no resulting operator a " on is taken),
the resulting dition will be one train providing s y at pH = 4.0 w ' e the other train provides spray at pH 210. . Since t spray header is redundant the components being spra vil eceive spray from both headers. The resultant:p" at the
., c zpenent cheuld b^ approni..ctcly '.0. ^dditienc113 'Zhe Tj injection phase is the only time thatthispH=4.Ohcondition
_jr could exist. The injection phase is short (1 hour) relative to the entire spray duration (approximately 24 hours). During the grem7 recirculation phasejtheApH range is ^0 . 10.0. This spray is l ] directed through the s me spray he ders and, therefore, should j rinse all of the prev'ously spray components (for a period of l approximately 23' ho rs) . /ilra.um 7, / - 7,0, I e.gur
- normal spray p:: dur;ng the 2njection phasc is 0.5 to 10.5. _
1
?he . er value occurs early during the injection phase.
the leve the spray additive tank decreases, the he on the npray additive uctors decreases; accordingly, t p level 1 -s decreases in the s - c v. It is possible durin u e beginning of the recirculation phase ' still be addi sodium hydroxide via the eductor (s). During thio e ort . od ($1 minute), it is possible to have an elevated pH 1.0. Assuming a single failure in the spray syste his per' could last up to
- 0 minutes. For the r .ainder of the rec ulation phase (22 to'23.5 hours), ti spray pH = 8.0-10.0. Sin failure analysis {
for the sprar - ditive subsystem is given in Table 5-4. The cump pH s a function of time, is provided in Figure .<-5. The ,cle 4 changes have an insignificant impact on' Figure U.L 5, thus it ic prcVidcd for informction only - j
-Sk j
- CALCSALET 6AMPf Y EVALUATION TWO The spray- iodine removal analysis is based on the assumptions that:
.)
- a. Only one out of two spray pumps is operating
- b. The ECCS-is operating at its maximum capacity Rev. OL-4 j 6.5-9 6/90 i
-- -_______-_a
INSERT 7 i The minimum equilibrium sump pH of 7.1 is based on the Technical Specification minimum of 5000 lbm of TSP-C in the baskets and the maximum sump solution bo ic acid concentration of 2500 ppm boron. With the Technical Specification maximum of 13,440 lbm of TSP-C in the baskets and the minimum sump solution boric acid concentration of 2007 ppm boron, the maximum equilibrium sump pH would be less than 9.0. The previously evaluated upper boun:' for containment spray pH of 11.0 will continue to be cited, consistent with Section 3.11(B).l.2.2, for the purpose of performing EQ reviews. Another issue that has been reviewed is the unlikely, but possible, event in which an initially concentrated solution of TSP-C occupies the stagnant volume of an inoperable sump. This situation would not last for long since, as ; the recirculated sump fluid is cooled in the RHR heat exchangers, suflicient buoyancy-driven circulation within containment will result to displace the ; stagnant solution and eventually yield a unifonn, equilibrium solution.
+
CALLAWAY - SP The spray system is assumed to spray approximately 85 percent of the total containment net free volume. This volume consists of those areas directly sprayed plus those volumes which have good communication with the directly sprayed volumes. The remaining 15 percent of the containment free volume has res-tricted communication with the sprayed volumes and is assumed to be unsprayed. A description of the unsprayed volumes is presented in Table 6.5-2. The centeinmen+ epray 2dditive cubryrte- i- ured te maintnir ' the cpray celution at : minimur pH cf 9.2 during MaOF l injection te encure efficient rnd rapid r^-^""1 cf th^ icdir^ frc the centairment atr^cpb^re. The performance of the spray system was evaluated at the containment post-LOCA calculated saturation temperature cor-responding to the calculated peak pressures and containment design pressure provided in Table 6.2.1-2. The net spray flow rate of 3,131 gpm (see Table 6.5-2) per train was used in the calculations described in Appendix 6.5A. Based on Regulatory Guide 1.4, three species of airborne iodine are postulated to exist in the containment atmosphere following a LOCA. These are elemental, particulpte, and organic species. en/ It has been assumed in these eva:.uations of spray removal ef-fectiveness that organic iodine 'orms are not removed by the can/whimen1b
-^diur hydicnide-spray. A limited credit for the removal of airborne particulates sentainingi' elemental iodine has been }
taken assuming that the spray rsmoval rate is 10 hr 2 deco amination factor (DF) of +9& is attaine ,&VTheas assump- until a _jg,,g/,,,nyL/ 7, 73, , ti s underestimate the actua amounts of io ne removed and us result in calculated ac dent doses hi er than could realistically be expected. 29,7 p.%h.~ dan}il
- t/ econ}emindisn in 'Ihe effri}e and con /rs/ m }We ea/ ula/4 Sec & af 9 O e N'InsY er Utilizing the dose analysis inpub parameters in Table 6.5-2, and in Appendix 15A, the dose indicated analysisabove, of ger//cu/e/Ar anal V4ef-Chaptc. 15.0 demonstrates that offsite radiation exposures J4e #p rey resulting dose guide fr m a design basis LOCA are within the plant siting reag e,7 nes of 10 CFR 100. re/w /r Sec}4n /T,4.S Appendix 6.5A provides the model used to calculate the iodine removal coefficients provided in Table 6.5-2.
6.5.2.4 Tests and Inspections
^11 2ctive componente ir the spray 2dditive cubeyeter are tcctcd both by performance tectc in the anufncturer'c chop rnd by in placc tccting after inctallatier Prcoperational testing is dcocribcd in Chapter 1-i.0. During thc initial prccpcrational tectc of the cycte=, the perferrence of the eductor in chcched by rt :ning %c ^cnta.irmert cpray Rev. OL-4 6.5-30 6/90
CALLAWAY - SP T,pc with the spray additivc tank filled witF water. Cali r$"Eh ion curves, which correlate water flow with 30 weight- '7') perce NaOH flow, are provided by the manufacturer, bas on ahop te . In addition, during the initial preopera 'onal
- ests, cal ation curves are generated for water w, under
-:he condition of periodic plant tests when the ray pump will be operating at utoff head (miniflow only).
Routine periodic testi of the spray a itive system compo-aents and all necessary port synt at power is planned. Encluded is a periodic samp go he NaOH in the spray additive tank through the loca ampling connection.
) The spray eductors are te ed singl
- he spray pump miniflo ines to the R y opening the valves in and the valve.in the 3ductor suction lin rom the RWST and ru ing the respective pump. The opera- observes the eductor suc 'on flow and auction pressu .
The spra additive tank isolation valves can be open pe-ly for testing. The contents of the tank are p j ciodi ci cally sampled to determine that the required solution s N f l
-_intained. i
^dditional- CSS tests and inspections are discussed in Section 6.2.2.1.4, including spray nozzle tests and inspections.
.c 6.5.2.5 Instrumentation Requirements strumentaticn and asacciated analog and Icgic charnels l i
emp ed for the initiation of spray additive system operat tre di ussed in Section 7.3.8. The fol'lowin describes the instrumentation which g employed for monitoring spray additive subsystem dur normal plant operation and duri post-accident operatio All alarms are snnunciated in the co rol room. i 1
- a. Spray Additive. Tan ress l A locally mounted i ca r on the spray additive tank provides means t monitor t tank pressure while adding nitro and during per dic inspections.
- b. Spray itive Flow low element is located in each discharg ine from the spray additive tank to.the eductors. Rea ut is local and on the main control board to provide i indication during flow testing.
s Rev. OL-0 6.5-11 6/86
CALLAWAY - SP
- q. Spray ^_dditi"e Tr"h Le"el s
- 1. Redundant level instruments are provided to ala
- imminent depletion of the spray additive ank
)
and provide automatic closure of the . ay additi tank discharge line valves.
- 2. Redundant lev instruments ar < so provided to annunciate at th ime that afficient ad-ditive -
has been educted fro th ank to meet the pH criteria of the syste . These level instruments are interlocked w the s y additive tank discharge line alves to prec e premature closure of ose valves. D i d . Spray Ad ive Eductor Suction Pressure A cally mounted indicator on the eductor suctio ine provides eductor suction pressure during flow testing. ww Containment spray instrumentation is 4444* discussed in Section 6.2.2.1.5. 6.5.2.6 Materials Thc containment spray additive subcycter ic conctruct-ed primarily of ccrrecier-recictant auc;cnitic ctcinlecc cteel. Th" cpray cdditive tank, in which the.Nc0!! ic stored, ir conctr cted of -} auctonitic stainico; stccl. Conctruction material: for the
-cpray.cdditive cubeyctcm are provided ir Tchic 5.5-?
The chemical compositions-cf thc Naci! ctered in the cpray cdditi.c t;nkgfthe containment spray fluid entering the spray header during the injection phase of containment sprayg Pand the containment spray fluid in the system during the recirculation phase of containment spray (containment recirculation sump solution) are provided in Table 6.5-5. None of the materials used is subject to decomposition by the ^ radiation or thermal environment. 7.11 opecificaticr- require I thet the ;..atcrials bc unaffcctcd whcn :npcccd to the cquipncnt-dccign temperature and total integrated radictier decc; 1 The corrosion of materials in the NSSS and the containment I building, resulting from the spray solution used for iodine ! absorption, has been tested by the Reactor Division at ORNL i (Ref. 2). The spray solutions provided in Table 6.5-5 result I I in negligible corrosion, based on these studies.
~7~Jf-C Indiu- hydrc, M d,oes not undergo radiolytic decomposition in the post-LOCA environment. Sodium has a low neutron absorption cross section and will not undergo significant activation.
l I Rev. OL-0 l 6.5-12 6/86 l
I 1 CALLAWAY - SP
-With respect to the potential for -pyrclytic- decomposition, .NaOH~73'8-C is stable to at least it mclting pcint tcmpcrcturc cf C00 P. /57#/C It = y convert to codium cxidc 'M O) u en removal of the
,at; , alsve /5W may, eeruff in +At fstr of kg $mn +{e 7~h-C$ erMu Q'
Avi// m/
- AAe cf ik caus/fcfnyede.t .
6.5.3 FISSION PRODUCT CONTROL SYSTEM j 1 6.5.3.1 Primary Containment The containment consists of a prestressed post-tensioned, reinforced concrete structure with cylindrical walls, hemispherical dome, and base slab lined with a welded quarter-inch carbon steel liner plate, which forms a ' continuous, leaktight membrane. Details of the containment structural design are discussed in Section 3.8. Layout drawings of the containment structure and the related items are given in the general arrangement drawings of Section 1.2. The containment walls, liner plate, penetrations, and isolation valves function to limit the release of radioactive materials, subsequent to postulated accidents, such that the resulting offsite doses are less than the guideline values of 10 CFR 100. Containment parameters affecting fission product release accident analyses are given in Appendix 15A. Long-term containment pressure response to the design basis LOCA is shown in Figure 6.2.1-1. Relative to this time period, the CSS is operated to reduce iodine concentrations and containment atmospheric temperature and pressure commencing with system initiation, at approximately 60 seconds, as shown in Table 6.2.2-3 and ending when containment pressure has - returned to normal. For the purpose of post-LOCA dose calculations discussed in Chapter 15.0, two dose models have been assumed, the 0-2 hour case and the 0-30 day case, as shown in Appendix 15A. The containment minipurge system may be operated for personnel access to the containment when the reactor is at power, as discussed in Section 9.4.6. Redundant, safety-related hydrogen recombiners are provided in the containment as the primary means of controlling postaccident hydrogen concentrations. A hydrogen purge system is provided for backup hydrogen control. See Section 6.2.5.3 (Safety Evaluation Eight) . Containment combustible gas control systems are discussed in detail in Section 6.2.5. Rev. OL-7 6.5-13 5/94
+J CALLAWAY - SP 6.5.3.2 Secondary Containment .,
1 This section is not applicable to SNUPPS. 6.5.4 ICE CONDENSER AS A FISSION PRODUCT CLEANUP SYSTEM This section is not applicable to SNUPPS. 6.
5.5 REFERENCES
- 1. Spraying Systems Company Topical Report No. SSCO-15215-1C-304SS-6.3-NP, April 1977, " Containment Spray Nozzles for Nuclear Power Plants"
-s
- 2. " Design Considerations of Reactor Containment Spray Systems, The Corrosion of Materials in Spray Solutions," ORNL-TM-2412 Part III, December 1969 3 NMAGG-0PDO, f-fandao-) Aeview J /an fe c-/%n 6. .C 2, levi.rion 1, "Csn-Mnman+ spry a.e a Re.,isn /%Ac+ C /e an up J y.,Ja,n, "
becamlae /9tr.
)
i I i i Rev. OL-0 6.5-14 6/86
CALLAWAY - SP TABLE 6.5-1 ESF FILTRATION SYSTEMS INPUT PARAMETERS TO CHAPTER 15.0 ACCIDENT ANALYSIS Emergency exhaust 90 filter adsorber unit efficiencies (percent) Emergency exhaust 9,000 system flowrate (SCFM) Control room filter HFP 96' adsorber unit efficiency (percent) Control room air conditioning system flowrate (SCFM) per train Filtered intake from 540 l control building Filtered recirculation 1,440 l from control room I J l s 6 Rev. OL-4 6/90
CALLAWAY - SP TABLE 6.5-2 INPUT PARAMETERS AND RESULTS OF SPRAY IODINE REMOVAL ANALYSIS Core power rating 3,565 MWt Total containment free volume 2.50 x 10' ft'
.Unsprayed containment free volume <15.0 percent Area coverage at the operating deck
-design Calculated >90 percent
>93 percent Mixing rate between sprayed and !
unsprayed volumes 85,000 cfm Dose model One region Minimum vertical distance to operating deck from lowest spray header 118 feet - 2 in. Net spray flow rate per train, - injection phase 3,131 gpm Occign "cO:: flow rctc pcr cductor- 'i '2 . 0 gp-Number of spray pumps operating 1 Spray solution pH 9.2 to 11.0 Elemental iodine absorption co-
+o-zo i,p c-u;l 6.c.)
efficient, is, 2 7. / re cieeu a /en calculations usedLDing)2ccident-o(fri-je a s{ Orrfrtl d Tur/,da/,,re, C) n 10 hr~2 40 rMrh d6te Enpceted Ca leufahis l 25.7 hr~2' * (2) 2*7 />c', Particulate iodine absorption coefficient, m M A - - '- Ap, used in /.g c/] o ((.rth and C8drW/ '"*** calculations e 0.45 hr-2 *- (3) Calculated 1p 0.73 hr-1 "(f) Spray drop size, design See Figure 6.5-2 Rev. OL-4 6/90
CALLAWAY - SP TABLE 6.5-2 (Sheet 2) f
' Schmidt number (fee f e e4~,n t.ro.2) 11.58 Gas diffusivity (tee [ee4'en 4.rA.2) 0.064ce[#8c 5,000 Partitioncoefficient(fee $*Cb5n$'#b'#
m coe S&c re,4 (fee fee.fron j,gg,g) 9,S.pj' ;,, Car pl ate inau +mula, 79s (4/ min Termin./ man-mean d'n,a ve/ sci-/y (see fee +&n C.SA B)
//bb far-lfbbn co elAcien-l- (Je e fe c-}fsn d',CA.3) l Used D"; cf up te 100
~
Ao chlculetcd from ?.ppendiy 6.53 (O (/nfil b f = 2 P. ~7. .fe ch*on i.CA.D *ndusedin~fAe
) (*) 2.7 of Q C.7 hr~' was co / cola-led inS eefan 2. //(f). /.D.2. % of 37/,~'
Ea close es/c~/*hhnt c/rseustej in wu ca /c uMed in fee %n J.rA.S ded /b Anwase used in + o fh,% and con +n/ room dose 5 gs (S.) (4fil b f= S0 J.rA./ and useot 7,, -fle Ep of 6.73 /r*' war e n /ca /ahd in fe chon (1) }due ealcd -Inn,.
CALLAWAY - SP TABLE 6.5-3 SPRAY ADDITIVE SUBSYSTEM-DESIGN PARAMETERS E_ductors Quantity 2 Eductor in et (motive) Operat ng fluid Borate water Operati g temperature Ambie t Eductor Sucti n Fluid NaOH conc tration, wt percent 31- 4 Specific g avity ~
.35 Viscosity ( esign), cp 0 Operating te erature mbient Material Stainless steel Spray Additive Tank Number 1 Total volume, usable gal ons 4,700 NaOH concentration, wt pe cent 31-34 Design temperature, F l 200 External design pressure, p ig 3 Internal design pressure, ps g 10 Operating temperature, F Ambient Operating pressure, psig ~1*
Material 'g , Stainless steel - High pressure relief valve t point, psig 5 Vacuum relief valves setp int, in, g 2 Spray Additive System Pipin ! Material Stainless steel '
*During normal conditi s, there is a 1 to 2 sig nitrogen gas blanket. During ccident injection, the t k pressure will f all below atmo >pheric pressure; redundant vacuum breakers are provided in or r to assure that tank extern design pressure is not e eeded relative to the tank int nal vacuum.
I 1 i b ELE ~TEb Rev. OL- I 6/90
4 0 CALLAWAY - SP TABLE 6.5-4 SPRAY ADDITIVF SUBSYSTEM - SINGLE FAILURE ANALYSIS Comment and Componen Malfunction Conse ences Fails to open Two rovided in Automatica y pa allel. Operation operated sp y o one required. additive tan outlet isolati n valve Fails to close Potential exists I for losing one train. Operation of only one train required. Spray additive Fails to ope Two provided. tank vacuum Operation of one required. breaker l l 1 I l l l l l l
~
hswrsb Rev. OL-O 6/86
CALLAWAY - SP d
%!.rdskm llsrfla-h2 bde ca ly rw4e ('7~rt*--C)
[Mg /44 /.2 4 0 *//p A/,4//) TABLE 6.5-5 CONTAINMENT SPRAY SYSTEM FLUID CHEMISTRY I. Containment Spray Additive
~
y Cediur hydroxide, ecight percent 21 2 '. - $#o //m m,k/ mum Temperature range, 'F 40 104 So-/.no II. Sprayed Fluid - Injection Phase
- so Aqueous solution, pH 4.0(11.O Chloride, ppm, max 100 Fluoride, ppm, max 100 Boric acid, ppm boron, max / min 2,500/2,350
-Ecdi r hydroxide, ppr -0 7,330 -
Temperature range, F 37-120 III. Sprayed Fluid - Recirculation Phase Aqueous solution, pH -E.0 11.0- % /-//,0 Boric acid, ppm boron, max / min 2 , 5 0 0 /1, 0 O C- 2,o47
-E cdir, hydr-cxide , ppra, - --- -'" '^^
Temperature range, *F 120-255 E Finalqui/rJetum IV. Recirculation Sump Fluid Aqueous solution, pH J E 10 0- 7. /~ 7 4 ' Boric acid, ppm boron, max / min 2,500/1,070 2j # 7
-Ecdi =,hydroxidc, ppn, rax - -5,000 Temperature range, F 120-255 Rev. OL-7 5/94
SUMP TEMP. = 200F 9.0 - CONTAINMENT N NAL FLOW SPRAY RECIRC. OF BO EDUCTORS b
- 8. G - m 8.4 MINIMUM REO.*
$ l 58.2-
- NOMINAL FLOW OF ONE EDUCTOR 7.8 -
REV. OL-7 5/94 OTAL ECCS CALLA %(AY PLANT RHR FIGUR .5-5 7.4 - REC . CONTAINMENT SUMP PH NOMINAL EDUCTOR FLOW FOR ONE ED OR AND TWO EDUCTOR OPERATIO 7.0 , , , , , , , 3 6 9 12 15 30 45 60 TIME (MINUTES)
- At end of injection phase; long-term minimum is 8.5.
CALLAWAY - SP 6.5A.1 PARTICULATE IODINE MODEL The spray washout model for aerosol particles is represented in equation form as follows: AP = (6.5A-1) 2dV Where: AP = spray removal constant for particles h = drop fall height E = total collection efficiency for a single drop F = spray volumetric flow rate l d = mean drop diameter V = volume of sprayed region The capture of particles by falling drops results from Brownian diffusion, diffusiophoresis, interception, and impaction. Early in the injection phase, particles are removed mainly by impaction. Following injection, when the larger particles have already been removed, the removal rate is controlled by diffusiophoresis, which is the collection of particulates by steam condensing on the spray drops. The single drop collection efficiency, E, is taken as 0.0015, the minimum value observed in experimental tests (Ref. 1). The minimum collection efficiency, 0.0015, was only attained after the major fraction of airborne particles was removed. For early time periods, the removal rates were much higher than the minimum values ultimately reached. JA//6A'7~ 7 The spray removal constant (AP) for particulate iodine has been calculated to be 0.73/hr, based on equation 6.5A-1, and' utv/ /n Sec/fon 3 /l(8)./. 3.:1 7 , f a e.jfs n / S.j, C , A limited and conservative credit for spray .omoval of airborne particulates containing iodine has been taken assuming the spray removal constant is 0.45/hr for the O to 2 hour period following the postulated LOCA (s a Table 6. -2
,Mdi/ a e ced) .omine/4, & c-/s,. o-$ l Particle spray removal constants considerably larger and of /c reac ad y longer duration than those conservatively chosen above have been reported from the Battelle Northwest Containment Systems Experiment (Ref. 2) and by the Oak Ridge National Laboratories Nuclear Safety Pilot Plant (Ref. 4).
l 6.5A.2 ELEMENTAL IODINE MODEL F34 E& bofs cALCut.A neNr The spray system, by virtue of the large surface area provided between the droplets and the containment atmosphere, will afford an excellent means of absorbing elemental radioactive Rev. OL-7 6.5A-2 5/94
I INSERT 8 Per Reference 11, it is conservative to assume that E/D is 10 per meter initially (i.e.,-l% efficiency for spray drops of one millimeter in diameter), changing abruptly to one per meter after the aerosol mass has been depleted by a DF of 50 (i.e.,98% of the particulate mass is ten times more readily removed than the remaining 2%). Using the 831 micron mean drop diameter ide'ntified in Table 6.5-2 and the minimum collection efficiency of 0.0015 - from Reference 1, E/D would be 1.8 per meter which is consistent with the value from Reference 11. after a DF of 50 is attained. 4 i 4
._ - . ~ - _ _ . . , . _ . _ _ - . _,
1 CALLAWAY - SP ' iodine released as a consequence of a LOCA. Sodium hydrox4ds
- will be added to t4e-sprey fluid to inercace the celubility of
-iedsnc in the-spray to thc point wherc"The rate of absorption is largely dependent on the concentration of radiciodine in the l air surrounding the drops. I
_ -,>- 1 CO4U29fT~ The basic model of r.he containment atmosphere and spray system l
$P is given by Parsley (Ref. 4). The containment atmosphere is viewed as a " black box" having a sprayed volume, V, and containing iodine at some uniform concentration Cg. Liquid enters at a flow of F volumes per unit time, containing iodine at a concentration of CL1, and leaves at the same flow, at concentration CL2. A material balance for the containment vessel as a function of time is given by:
-VdCg = F(CL2 - CL1)dt (6.5A-2)
Where: CL1 = the iodine concentration in the liquid entering the dispersed phase, gm/cm 3 CL2 = the iodine concentration in the liquid leaving the dispersed phase, gm/cm 3 V = sprayed volume of containment, cm3 Cg = the iodine concentration in the containment atmosphere, gm/cm 3 F = the spray volumetric flow rate, cm 3 /sec t = spray time, sec A drop absorption efficiency, E, which may be described as the fraction of saturation, is defined as: E = (CL2 - CL1) / (CL* - CL1) (6.5A-3) In addition, the equilibrium distribution of iodine between the vapor and liquid phases is given by: H = CL*/Cg (6.5A-4) Where: H = the iodine partition coefficient (gm/ liter of liquids)/(gm/ liter of gas) CL* = the equilibrium concentration in the liquid, gm/cm 3 Rev. OL-7 6.5A-3 5/94
INSERT 9 The following discussion is based on the pH dependent correlation for the elemental iodine spray removal constant discussed in Reference 12 and used in the EQ dose calculations of Section 3.11(B).l.2.2 (see Equations 6.5A-9 and 6.5A-17). Section 6.5A.3 discusses the surface area dependent correlation for the elemental iodine spray removal constant discussed in
. Reference 11 and used in the offsite and control room dose calculations of Section 15.6.5. Both of these correlations are applicable for the injection phase only.
CALLAWAY - SP Substitution of equation 6.5A-4 into equation 6.5A-3 yields E= (CL2 - CL1) / (hcg - CL1) (6.5A-5) Solving equation 6.5A-5 for (CL2 - CL1) and inserting the result into equation 6.5A-2 gives ^
- (V) dCg = EF (hcg - CL1) dt (6.5A-6)
During the injection ph&se, CL1 = 0, so that
- (V) dCg = (EFHCg) dt (6.5A-7)
Equation 6.5A-7 can be integrated to solve for Cg. The concentration of iodine in the containment atmosphere during injection as a function of time is given by: Cg = Cgo exp [-EHFt / V] (6.5A-8) Where: Cgo = the initial iodine concentration in the containment atmosphere, gm/cm 3 Equation 6.5A-8 is applicable up to the time the spray solution is recirculated and is based on the following assumptions:
- a. Cg is uniform throughout the containment
- b. There are no iodine sources after the initial release
- c. The concentration of iodine in the spray solution entering the containment is zero From equation 6.5A-8, the spray removal constant, Ls,is given by A As= EHF (6.5A-9)
^ V The above equation for A is independent of the models on which the numerical evaluation of the drop absorption efficiency, E, and the iodine partition coefficient, H, may be based.
Absorption efficiency for elemental iodine may be calculated from the time-dependent diffusion equation for a rigid sphere, with the gas film mass transfer resistance as a boundary condition. This mass transfer model was suggested by L. F. Rev. OL-7 6.5A-4 5/94
CALLAWAY - SP interface, is in equilibrium with the iodine concentration in the gas phase outside the drop. The expression in this reference model is:
' 6kt' ge E = 1 - exp -
(6.5A-14) s dH s The absorption efficiency is a function of the drop diameter, the gas phase mass transfer coefficient, diffusivity of iodine in the liquid drop, the partition coefficient, and the drop exposure time. Eggleton's equation (Ref. 8) for the equilibrium elemental iodine de. contamination factors, DF, is given by: DF = 1 + H (VL) / (VG) (6.5A-15) Where: E - equilibrium iodine partition coefficient i ,,, .}.;, / concen}rn+1sn DF = ratio of the actcl-Viodine Vin the n .1 lip id-and containment atmos here to t'at thea containment atmasphere = C3 Cy egul//Lrium iodine corean}nl Ton in ~/A e VG = net free containment volume minus VL VL = volume of liquid in the containment sumps plus overflow from the sumps, which may be used for calculation of the partition coef fi cient, H, for a g ff, given value of the DF. "cr:; r, uation 6.5A-15 was c a /e u /o-/iene not used in thekprccent analysis, instead, a numerical g.,, yffg ;n value of 5,000 for H, the minimum found from Containment Systems Experiment (CSE) tests (Refs. 9 [cc7b.en K//(M/2 %,and 10) for sodium hydroxide spray, was used in the evaluation of 1. MJ'M /d Since the spray does not consist of a uniform droplet size, a spectrum of drop sizes and their corresponding volume percentage (for the specific nozzle design) were used to determine the individual spray removal constant for each droplet size. The total spray removal constant is equal to the sum of the individual spray removal constants, i.e.: n n m A = [A j= [ [A j (6.5A-16) i=1 i=1t=1 i Since the drop exposure time, t e , is dependent on distance from l the spray header to the operating deck, and each spray header consists of ring headers (f ) located at various levels, A 5 was calculated for each spray ring header (l ) , utilizing the appropriate drop distance for each header. Rev. OL-7 6.5A-7 5/94
. . . . - - - - . - _ _ _ _ . ~ _ - . ..
v INSERT 10 While a value of 5000 for H was used to calculate the elemental iodine spray removal constant of 25.7 hrl used in the EQ dose calculations, it is noted that Section 6.5A.3 calculates an elemental iodine spray removal constant of 37 hrl. In any event, for dose calculations the spray remcval constant is not as important as the DF in detennining EQ doses. 6 l
)
i l
)
~* CALLAWAY - SP Therefore, Ei# HFi # (6.5A-17) 2<f - -r- V Where: Ej = collection efficiency for a single drop of micron increment i for ring header i Fi - spray flow rate for micron increment i for header t and, Fi - (Fj / nozzle) - (Ng ) (6.5A-18) Where: F;/norde = (15.2 n gpm)(N;)-(V;) N iV; [1 18: Ng = number of nozzles on ring header i N; = number frequency for micron increment i (Figure 6.5-2) V; = volume of a drop in micron increment i As the spray solution enters the high-temperature containment atmosphere, steam will condense on the spray drops. The amount of condensation is easily calculated by a mass balance of the drop: mh + mc hg= nf h f where: m and m' = the mass of the drop before and after condensation, lbs m = the mass of condensate, lbs i h = the initial enthalpy of the drop, Btu /lb ! hgand h p = The saturation enthalpy of water vapor and j liquid, Btu /lb Rev. OL-7 6.5A-8 5/94
CALLAWAY - SP The increase in each drop diameter in the distribution, therefore, is given by: r r dis3 ' y hg- h> sd/ _ sgv h 9 Where: vf = the specific volume of liquid at saturation, R 3 /lb v = the specific volume of the drop before condensation, 3 R /lb h = the latent heat of evaporation, Btu /lb h = the enthalpy of steam at saturation, Btu /lb d and d' = the drop diameter before and af ter condensation, cm Postma and Pasedag (Ref. 6) conclude that condensation will tend to increase the iodine washout rate due to the increased volume of the spray. Their effect has been conservatively ignored. The drop exposure time calculated is based on the assumption that the drops were sprayed in such a manner that the initial downward velocity of the drops at the spray ring header elevation was zero. The drops fall under the effect of gravity from the spray ring header to the operating deck. The minimum height is given in Table 6.5-2. As the drop size increases, the average exposure time decreases from about 20 co 5 seconds. l Incorporating the above parameters into equation 6.5A-16 with the sprayed containment volume, V, and assuming a single spray header flow rate, the value of the spray removal coefficient calculatedg is presented in Table 6.5-2. (2S147 0 mA The resulting elemental iodine spray removal constant is greater than 10/hr. Cr.1 2 uua l' conservative removal constant of 10/hr is assumed and used in the design basis LOCA evaluations presented in Section 15.6.5. SN rEKT"// 4 l 6 . 5 A . REFERENCES
+
- 1. Hilliard, R. K., Coleman L. F., " Natural Transport Effects of Fission Product Behavior in the Containment System Experiment," BNWL-1457, Battelle Pacific Northwest Laboratories, Richland, Washington, December 1970.
Rev. OL-7 6.5A-9 5/94
INSERT 11 6.5A.3 ELEMENTAL IODINE MODEL FOR OFFSITE AND CONTROL ROOM DOSE CALCULATIONS As discussed in Reference 11, the effectiveness of the spray during the injection phee against elemental iodine vapor is chiefly determined by the rate at which fresh solution surface area is introduced into the containment atmosphere. The rate of solution created per unit gas volume in the containment atmosphere may be estimated as (6F/VD), where F is the spray volumetric flow rate, V is the volun:e of the sprayed region, and D is the mean diameter of the spray drops. The first-order spray removal constant for elementaliodine, As, may be taken to be: As = 6k T._E g VD where kgis the gas phase mass transfer coefficient and T is the drop fall time (or drop exposure time), which may be estimated by the ratio of the average fall height to the tenninal velocity of the average drop. The above expression represents a first-order approximation if a well-mixed droplet model is used for spray absorption efficiency. This expression is valid for As values equal to or greater than 10 per hour but less than 20 per hour. Using this expression and the values contained in Table 6.5-2 a value of 37 hrl is calculated. A value of 10 per hour will continue to be used in the dose calculations of ) Section 15.6.5. I Spray removal of elemental iodine continues until the DF of Equation 6.5A-15 is reached. Although the VL tenn in Equation 6.5A-15 represents the volume of the sumps plus any overflow from the sumps, it is conservative to just use the volume of the sumps for VL since a lower DF will result. The ; value for the partition coeflicient, H, in Equation 6.5A-15 was taken from Figure 6 of Reference 13 using the 323 K plot at 14 hours (representative of the average conditions during a LOCA). The value of 1100 used is considered l to be conservative since the sump fluid temperature at 14 hours would be greater than 323 K per Figure 6.2.1-17 and Figure 6 of Reference 13 shows ~ that higher temperatures would be associated with higher partition coefficients. The resulting DF is calculated to be 28.7. i 1 i
CALLAWAY - SP
- 2. Hilliard, R. K., et al, " Removal of Iodine and Particu-lates from containment Atmospheres by Sprays - Containment I Systems Experiment Interim Report," BNWL-1244, 1970.
- 3. Perkins, J. F., " Decay of U235 Fission Products," Physical Science Laboratory, RR-TR-63-11, U.S. Army Missile Command Redstone Arsenal, Alabama, July 25, 1963.
- 4. Parsley, Jr., L. F., " Design Considerations of Reactor Containment Spray Systems - Part VII," ORNL TM 2412, Part 7, 1970.
- 5. Ranz, W.E., and Marshall, Jr., W.R., " Evaporation from Drops," Chemical Engineering Progress 48, 141-46, 173-80, '.'
1952.,
- 6. Postma, A. K., and Pasedag, W. F., "A Review of Mathematical Models for Predicting Spray Removal of Fission Products in Reactor Containment Vessels," WASH-1329, U.S. Atomic Energy Commission, June 1974.
- 7. Griffiths, V., "The Removal of Iodine from the Atmosphere by Sprays," Report No. AHSB(S)R45, United Kingdom Atomic Energy Authority, London, 1963.
- 8. Eggleton, A. E. J., "A Theoretical Examination of Iodine-Water Partition Coefficient," AERE (R)-4887, 1967. T
)
- 9. Postma, A. K., Coleman, L. F., and Hilliard, R. K.,
" Iodine Removal from Containment Atmospheres by Boric Acid Spray," BNP-100, Battelle-Northwest, Richland, Washington, 1970.
- 10. Coleman, L. F., " Iodine Gas-Liquid Partition," Nuclear Safety Quarterly Report, February, March, April 1970, BNWL-1315-2, Battelle-Northwest, Richland, Washington,
- p. 2.12-2.19, 1970.
.rN.rcM /3.
Rev. OL-0 6.5A-10 6/86
INSERT 12
- 11. NUREG-0800, Standard Review Plan Section 6.5.2, Revision 2,
" Containment Spray as a Fission Product Cleanup System," December 1988.
- 12. ANSI /ANS-56.5-1979, "PWR and BWR Containment Spray System Design Criteria."
- 13. E. C. Beahm, W. E. Shockley, C. F. Weber, S. J. Wisbey, and Y. M.
Wang, " Chemistry and Transport ofIodine in Containment," NUREG/CR-4697, October 1986. l 1 l l l
CALLAWAY - SP l
-s assumed to plateout onto the internal surfaces of the contain-The remaining iodine ment or adhere to internal components.
s and the noble gas activity are assumed to be immediately available for leakage from the containment. l Once the gaseous fission product activity is released to the i J containment atmosphere, it is subject to various mechanisms of removal which operate simultaneously to reduce the amount of activity in the containment. The removal mechanisms include radioactive decay, containment sprays, and containment leakage. For the noble gas fission products, the only removal processes considered in the containment are radioactive decay and con-tainment leakage.
- a. Radioactive Decay - Credit for radioactive decay for ,
fission product concentrations located within the l containment is assumed throughout the course of the accident. Once the activity is released to the environment, no credit for radioactive decay or deposition is taken. Containment Sprays ( rt}ed'en
- The containment spray system is b.
designed to abnorb airborne iodine fission products within the containment atmosphere. To enhance the iodine :::: ca-Wcapability of the containment sprays,'fe/ed/e' urn Me : di= hydronid:- is added to the spray solutio The
^,,7- ef spray effectiveness for the r rn ar of iodine ~ Vfd Id/MMr i dinc cherie:1 f n dependent onAth 'orH in A c '*'y'.
a M ru,, H.yada % 7.s. Geh.nlisn mi,JantI7c.lohontainmend,[eakage-Thecontainmentleaksatarate of 0.2 volume percent / day as incorporated as a Technical Specification requirement at peak calculated internal containment pressure for the first 24 hours and at 50 percent of this leak rate for the remaining duration of the accident. The containment leakage is assumed to be directly to the environment. ASSUMPTIONS AND CONDITIONS - The major assumptions and param-g eters assumed in the/Inanalysis 15.6-6 di,rearre J ac} fenare itemized in Tables 15A-1 and d.SA.3.
) ,sf and In the evaluation of a LOCA, all the fission product release assumptions of Regulatory Guide 1.4 have been followed. The following specific assdmptions were used in the analysis.
Table 15.6-7 provides a comparison of the analysis to the requirements of Regulatory Guide 1.4.
- a. The reactor core equilibrium noble gas and iodine inventories are based on long-term operation at a core power level of 3,636 MWt.
Rev. OL-2 15.6-27 6/88
CALLAWAY - SP
- b. One hundred percent of the core equilibrium radio-active noble. gas inventory is immediately available .I for. leakage from'the containment.
- c. Twenty-five percent of the core equilibrium radio-active iodine inventory is immediately available for leckage from the containment.'T/e 4//87 .3S#/s re /eareol -SS //a dembe/n/ Ash-/-
a d. Of th(ben intthendonesurly e iodine fission product fla}er ref. inventory released to the containment, 91 percent is in the form of ele-mental iodine, 5 percent is in the form of particulate iodine, and 4 percent is in the form of organic iodine. r:2f.~7 s,
- e. Credit for iodine removal by the containment spray 7 system is taken, starting at time zero and continuing until a decontamination factor of +99"for the ele-mental and particulatm speciesAhas been achieved.
and'50 p He par 4icul ale rjoecier
- f. The following iodine removal constants for the con-tainment spray system are assumed in the analysis:
Elemental iodine - 10.0 per hr Organic iodine - 0.0 per hr Particulate iodine - 0.45 per hr
- g. The following parameters were used.in the two-region spray model:
Fraction of containment sprayed - 0.85 Fraction of containment unsprayed - 0.15 Mixing rate (cfm) between sprayed and unsprayed regions - 85,000 Section 6.5 contains a detailed analysis of the sprayed and unsprayed volumes and includes an ex-planation of the mixing rate between the sprayed and unsprayed regions.
- h. The containment is assumed to leak at 0.2 volume '
percent / day during the first 24 hours immediately following the accident-and 0.1 volume percent / day thereafter.
- i. The containment leakage is assumed to-be direct unfiltere to tle 3 environment.
confrol buo out CondWl dern
- j. The .3iWiiFVfi ers will be 49 percent efficient in the removal of all species of iodine.
V Rev. OL-4 15.6-28 6/90
CALLAWAY - SP
~') MATHEMATICAL MODELS USED IN THE ANALYSIS - Mathematical models
) used in the analysis are described in the following sections:
- a. The mathematical models used to analyze the activity released during the course of the accident are described in Section 15A.2.
- b. The atmospheric dispersion factors used in the analysis 2 were calculated, based on the onsite meteorological measurements program described in Section 2.3 of the ,
Site Addendum, and are provided in Table 15A-2.
- c. The thyroid inhalation and total; body immersion doses to a receptor exposed at the exclusion area boundary
) and the outer boundary of the low population zone were analyzed, using the models described in Sections 15A.2.4 and 15A.2.5, respectively.
- d. Buildup of activity in the control room and the integrated doses to the control room personnel are analyzed, based on models described.in Section 15A.3.
IDENTIFICATION OF LEAKAGE PATHWAYS AND RESULTANT LEAKAGE ACTIVITY - For evaluating the radiological consequences of a postulated LOCA, the resultant activity released to the con-tainment atmosphere is assumed to leak directly to the
'y environment. "" No credit is taken for ground deposition or radioactive decay during transit to the exclusion area boundary or LPZ outer boundary.
15.6.5.4.1.2 Radioactive Releases Due to Leakage from ECCS I and Containment Spray Recirculation Lines Subsequent to the injection phase of ESF system. operation, the water in the containment recirculation sumps is recirculated by the residual heat removal, centrifugal charging and safety injection pumps, and the containment spray pumps. Due to the s operation of the ECCS and the containment spray system, most of
)
the radioiodine released from the core would be' contained in the containment sump. It is conservatively assumed that a leakage rate of 2 gpm from the ECCS and containment spray recirculation lines exists for the duration of the LOCA. This leakage would occur inside the containment as well as inside the auxiliary , building. For this analysis, all the leakage is assumed to occur inside the auxiliary building. Only trace quantities of radioiodine are expected to be airborne within the auxiliary building due to the temperature and pH level of the recirculated , water. However, 10 percent of the radiciodine in the leaked water J is assumed.to become airborne and exhausted from the unit vent to the environment through/refety grada-filters (90% efficient). No ! i T credit is taken for ho up (i.e. decay) or mixing in the auxiliary
'~
) building; however, mi. ng and holdup in the sumps are factored into the' release and decay removal constants for this pathway.
l
'lbe dukIli*y')MI/liy t @ ex & .t4*
Rev. OL-6 15.6-29 6/92
1 l CALLAWAY - SP 1 l loadings are in accordance with Regulatory Guide 1.52, which j limits the maximum loading to 2.5 mg of iodine per gram of ) l activated charcoal. The 100 percent efficiency assumption is conservative for the purpose of checking filter loading and is not to be confused with the 449f efficiency assumption used for ' radiological consequences s listed in Table 15.0-0 aud-15.A-1. 15.6.5.4.3.2 Wb Doses to a Receptor at the Exclusion Area Boundary and Low Population Zone Outer Boundary The potential radiological consequences resulting from the occurrence of the postulated LOCA have been conservatively analyzed, using assumptions and models described in previous sections. I The total-body done due to immersion and the thyroid dose due to inhalation have been analyzed for the 0-2 hour dose at the exclusion area boundary and for the duration of the accident at the LPZ outer boundary. The results, with margin, are listed in Table 15.6-8. The resultant doses are within the guideline l values of 10 CFR 100. 15.6.5.4.3.3 Doses to Control Room _ Personnel Radiation doses to control room personnel following a pos-tulated LOCA are based on the ventilation, cavity dilution, and dose model discussed in Section 15A.3.
)
Control room personnel are subject to a total-body dose due to immersion and a thyroid dose due to inhalation. These doses have been analyzed, and are provided in Table 15.6-8. The listed doses, with margin, are within the limits established by GDC-19. 15.6.6 A NUMBER OF BWR TRANSIENTS This section is not applicable to the Callaway Plant. 15.
6.7 REFERENCES
1 Burnett, T. W. T., et. al., "LOFTRAN Code Description", WCAP-7907-P-A (Proprietary), WCAP-7907-A (Non-Proprietary), April 1984,
~
- 2. Chelemer, H., Boman, L. H., Sharp, D. R., " Improved Thermal Design Procedures", WCAP-8587, July 1975.
- 3. SGTR Analysis letters SLNRC 86-01 (1-8-86), SLNRC 86-03 (2-11-86) SLNRC 86-05 (4-1-86), SLNRC 86-08 (9-4-86),
ULNBC-1442 (2-3-87), ULNRC-1518 (5-27-87), ULNRC-1849 (10-21-88), ULNRC-2145 (1-29-90), and the NRC SER dated 8-6490.
- 4. " Reactor Safety Study - An Assessment of Accident-Risk in U.S. Commercial Nuclear Power Plants," WASH-1400, NUREG-75/
034, October 1975. Rev. OL-6 15.6-32 6/92
- CALLAWAY - SP TABLE 15.6-6 PARAMETERS USED IN EVALUATING THE RADIOLOGICAL CONSEQUENCES OF A LOSS-OF-COOLANT-ACCIDENT I. Source Data
- a. Core power level, MWt 3,636
- b. Burnup, full power days 1,000
- c. Percent of core activity initially airborne in the containment
- 1. Noble gas 100 g
- 2. Iodine -es- 60
- d. Percent of core activity /Ar>'ebh/ / defel-/e/
in containment sump : 0. 4 7 ham
- 1. Noble gases 0
- 2. Iodine 50
- e. Core inventories Table 15A-3
- f. Iodine distribution, percent
- 1. Elemental 91
- 2. Organic 4
- 3. Particulate 5 II. Atmospheric Dispersion Factors See Table 15A-2 III. Activity Release Data
- a. Containment leak rate, volume percent / day
- 1. 0-24 hours 0.20
- 2. 1-30 days 0.10 l
- b. Percent of containment leakage j that is unfiltered 100 (
l
- c. Credit for containment sprays
- 1. Spray iodine removal constants (per hour)
- a. Elemental 10.0
- b. Organic 0.0 l
- c. Particulate 0.45 j
* /h/S inthn4=noix/7 7 lahr ed /**vfy >S*A immediaklyavoi/ die
./s,. /eokye fnm -He conhinned.
Rev. OL-2 6/88
. . . _ _ _ _ _ __ _ _ . . . . _ _ . _ _ _ _ . - . - _ _ . _ . ~ ., _ -.
..: 0 CALLAWAT - SP TABLE 15.6-6 (Sheet 2)
.2.. Maximum iodine decontamination factors'for the containment atmosphere
- a. Elemental -t90- M 7
- b. Organic . O
- c. Particulate -196- S o
- 3. Sprayed volume, percent 85
'4. Unsprayed volume, percent 15
- 5. Sprayed-unsprayed mixing rate,.CFM 85,000-
- 6. Containment volume, ft 3 2.5E+6
- d. ECCS recirculation leakage
- 1. Leak rate (0.47 hours-30 days), gpm 2.0
- 2. Sump volume, gal. '460,000 ,
- 3. Fraction iodine airborne 0.1 I
- 4. ESF filter efficiency, t 90.0 En,a^ryency exW
- e. RWST leakage
- 1. Leak rate (0.47 hours .-
30 days), gpm' 3.0
- 2. RWST volume, gal. 400,000
- 3. Fraction iodine airborne 0.1
, IV. Control room parameters Tables-15A-1 and 15A-2 , i l l l 1 1 I l I I Rev. OL;7 5/94 l l
- e CALLAWAY - SP TABLE 15A-1
}
PARAMETERS USED IN ACCIDENT ANALYSIS I. General
- 1. Core power level, Mwt 3636 (102% power)
- 2. Number of fuel assemblies in the core 193
- 3. Maximum radial peaking factor 1.65
- 4. Percentage of failed fuel 1.0
- 5. Steam generator tube leak, lb/hr 500
)II. Sources
- 1. Core inventories, Ci Table 15A-3
- 2. Gap inventories, Ci Table 15A-3
- 3. Primary coolant specific activities, Table 11.1-5*
pCi/gm
- 4. Primary coolant activity, technical specification limit for iodines - I-131 dose equivalent, pCi/gm 1.0
- 5. Secondary coolant activity technical specification limit for iodines - I-131 dose equivalent, pCi/gm 0.1 III. Activity Release Parameters
- 1. Free volume of containment, fta 2.5 x 10'
- 2. Containment leak rate
- i. 0-24 hours, % per day 0.2
- 11. after 24 hrs, % per day 0.1 IV. Control Room Dose Analysis (for LOCA)
- 1. Control building
- 1. Mixing volume, cf 150,000
-s 11. Filtered intake, cfm Prior to operator action (0-30 s} minutes) 900 After operator action (30 minutes - 720 hours) 450 l 111. Unfiltered"inleakage, cfm 300 iv. Filter efficiency (all forms of iodine), % 96'
- 2. Control room
- 1. Volume, cf 100,000
- 11. Filtered flow from control build-ing, cfm 540
.- *Except for SGTR events for which Table 11.I-4 is used.
Rev. OL-4 6/90
r -
*, O CALLAWAY - SP l i
TABLE 15A-1 (Sheet 2)
.)
111. Unfiltered flow from control building, cfm Prior to operator action (0-30 minutes) 540 After operator action (30 minutes - 720 hours) 0 iv. Filtered recirculation, cfm 1440 l
- v. Filter efficiency (all forms of iodine), % 44F76I V. Miscellaneous ) ;
- 1. Atmospheric dispersion factors, x/Q sec/m a Table 15A-2
- 2. Dose conversion factors
- 1. total body and beta skin, rem-meters /Ci-sec Table 15A-4
- 11. thyroid, rem /Ci Table 15A-4
- 3. Breathing rates, meter s/sec
- i. control room at all times 3.47 x 10 ~'
- 11. offsite ~
0-8 hrs 3.47 x 10 '
~
8-24 hrs 24-720 hrs 1.75 x 10 '
~
2.32 x 10 '
..)
- 4. Control room occupancy fractions 0-24 hrs 1.0 24-96 hrs 0.6 96-720 hrs 0.4 I
Rev. OL-4 6/90 L}}