ML20056E306
| ML20056E306 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/04/1993 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056E307 | List: |
| References | |
| NUDOCS 9308230162 | |
| Download: ML20056E306 (15) | |
Text
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NUCLEAR REGULATORY COMMISSION g
5 o C WASPINGT ON, D. C. 20555 s
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WOLF CREEK NUCLEAR OPERATING CORPORATION
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WOLF CREEK GENERATING STATION DOCKET NO. 50-481 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. NPF-42
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated June 1, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
9308230162 930804 i
PDR ADOCK 05000482 i
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Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-42 is hereby amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised I
through Amendment No. 65, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
4 3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION M
Suzanne Black, Director Project Directorate IV-2 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical j
Specifications Date of Issuance:
August 4, 1993 l
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I ATTACHMENT T0 tICENSE AMENDMENT NO. 65 f
FACILITY OPERATING LICENSE NO NPF-42 DOCKET NO. 50-482 i
Revise Appendix A Technical Specifications by removing the pages identified i
below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
l The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT l
1 XXI XXI 1-4 1-4 3/4 11-1 3/4 11-1 3/4 11-3 3/4 11-3 B 3/4 8-1 B 3/4 8-1 i
6-20 6-20 6-25 6-25 1
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4 ADMINISTRATIVE CONTROLS SECTION PAGE t
6.5.2 NUCLEAR SAFETY REVIEW COMMITTEE (NSRC)
Function....................................................
6-9 Composition.................................................
6-10
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Alternates..................................................
6-10 C o n s u l t a n t s.......................................... -.......
6-10
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Meeting Frequency...........................................
6-10 i
Quorum......................................................
6-10 i
Review......................................................
6-11 Audits......................................................
6-11 l
Records.....................................................
6-12 6.6 REPORTABLE EVENT ACTI0N.......................................
6-13 6.7 SAFETY LIMIT VIOLATION........................................
6-13 6.8 PROCEDURES AND PR0 GRAMS.......................................
6-13 6.9 REPORTING RE0VIREMENTS j
6.9.1 ROUTINE REP 0RTS.............................................
6-17 i
Startup Report..............................................
6-17 j
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Annual Reports..............................................
6-17 t
j Annual Radiological Environmental Operating Report..........
6-18 j
Annual Radioactive Effluent Release Report..................
6-19 l
l Monthly Operating Report....................................
6-20 l
Core Operating Limits Report...............................
6-21 6.9.2 SPECIAL REP 0RTS.............................................
6-21a 6.10 RECORD RETENTION.............................................
6-21a i
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k WOLF CREEK - UNIT 1 XXI Amendment No. 4e,64,65
I ADMINISTRATIVE CONTROLS SECTION PAGE S.11 RADIATION PROTECTION PROGRAM..........................,............
6-23 6.12 HIGH RADIATION AREA...............................................
6-23
_6.13 P R O C E S S CO NT R O L P ROG RAM ( PCP )....................
6-24 6.14 0FFSITE DOSE CALCULATION MANUAL(0DCM)............................
6-24 6.15 DELETED i
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4 WOLF CREEK - UNIT 1 XXII Amendment No. 42
t DEFINITIONS DOSE EOUIVALENT I-131 1.11 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie /
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gram) which alone waald produce the same thyroid dose as the' quantity and iso-topic mixture of I 431, 1-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."
I - AVERAGE DISINTEGRATION ENERGY 1.12 E shall be the average (weighted in proportion to the concentration of l
i each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half-lives greater than 15 minutes, making up at least 95% of the total noniodine activity in the coolant.
ENGINEERED SAFETY FEATURES RESPONSE TIME 1.13 The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be that time l
interval from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel sensor until the ESF equiprent is capable of performing its safety function (i.e., the valves travel to their required positions, pump i
discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.
i FRE0VENCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance l
Requirements shall correspond to the intervals defined in Table 1.1.
IDENTIFIED LEAKAGE I
1.15 IDENTIFIED LEAKAGE shall be:
j Leakage (except CONTROLLED LEAKAGE) into closed systems, such as a.
pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or b.
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE BOUNDARY LEAKAGE, or Reactor Coolant System leakage through a steam generator to the c.
Secondary Coolant System.
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j WOLF CREEK - UNIT 1 1-3 Amendment No. 61
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DEFINITIONS
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MASTER RELAY TEST 1.16 A MASTER RELAY TEST shall be the energization of each master relay and verification of OPERABILITY of each relay.
The MASTER RELAY TEST shall include a continuity check of each assor.iated slave relay.
MEMBER (S) 0F THE PUBLIC 1.17 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
OFFSITE DOSE CALCULATION MANUAL 1.18 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from i
radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program.
The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by l
Specifications 6.9.1.6 and 6.9.1.7.
j OPERABLE - OPERABILITY 1.19 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),
and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).
OPERATIONAL MODE - MODE t
l.20 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.
PHYSICS TESTS f
1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the core and related instrumentation: (1) described in Chapter 14.0 of the FSAP., or (2) authorized under the provisions of i
10 CFR 50.59, or (3) otherwise approved by the Commission.
WOLF CREEK - UNIT 1 1-4 Amendment No. 64, 65 m
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i 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIOUID EFFLUENTS L10VID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 1
3.11.1.4 The quantity of radioactive material contained in each of the following unprotected outdoor tanks shall be limited to less than or equal to 150 Curies, excluding tritium and dissolved or entrained noble gases.
a.
Reactor Makeup Water Storage Tank,
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b.
Refueling Water Storage Tank, j
c.
Condensate Storage Tank, and d.
Outside temporary tanks, excluding demineralizer vessels and liners being used to solidify radioactive wastes.
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APPLICABILITY: At all times.
ACTION:
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With the quantity of radioactive material in any of the above listed i
j tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank i
contents to within the limit, and describe the events leading to this 1
condition in the next Annual Radioactive Effluent Release Report, l
pursuant to Specification 6.9.1.7.
l b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
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l SURVEILLANCE REQUIREMENTS l
4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a l
representative sample of the tank's contents at least once per 7 days when j
radioactive materials are being added and within 7 days following any addition of s
radioactive material to the tank.
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WOLF CREEK - UNIT 1 3/4 11-1 Amendment No. 43, 65
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RADI0 ACTIVE EFFLUENTS J
3/4.11.2 GASEOUS EFFLUENTS j
EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the WASTE GAS HOLDUP SYSTEM shall be limited to less than or equal to 3% by volume whenever the hydrogen concentration exceeds 4% by volume.
APPLICABIllTY:
At all times.
ACTION:
I With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM 1
a.
i greater than 3% by volume but less than or equal to 4% by volume, J
re:uce the oxygen concentration to the above limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
With the contentration of oxygen in the WASTE GA5 HOLDUP SYSTEM b.
greater than 41 by volume and the hydrogen concentration greater than 41 by volume, immeciately suspend all additions of waste gases l
to the system and reduce the concentration of oxygen to less than er l
equal to 4% by volume, then take ACTION a. above.
c.
t The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
j SURVEILLANCE REOUIREMENTS 4.11.2.5 The concentrations of hydrogen and oxygen in the WASTE GAS HOLDUP SYSTEM shall be determined to be within the above limits by continuously monitoring the waste gases in the WASTE GAS HOLDUP SYSTEM with the hydrogen and oxygen conitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.11.
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v WOLF CREEK - UNIT I 3/4 11-2 Amendment No. 42 t0F E ! $31
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l RADI0 ACTIVE EFFLUENTS 1
GAS STORAGE TANKS i
l LIMITING CONDITION FOR OPERATION l
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3.11.2.6 The quantity of radioactivity contgined in each gas storage tank shall be limited to less than or equal to 2.5 x 10 Curies of noble gases (considered as t
Xe-133 equivalent).
j APPLICABILITY: At all times.
ACTION:
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With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of i
radioactive material to the tank, and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the tank 4
contents to within the limit, and describe the events leading to this J
condition in the next Annual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.
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b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
i SURVEitlANCE REQUIREMENTS i
i 4.11.2.6 The quantity of radioactive material contained in each gas storage tank j
shall be determined to be within the above limit at least once per 7 days when i
radioactive materials are being added and within 7 days following any addition of radioactive material to the tank.
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WOLF CREEK - UNIT 1 3/4 11-3 Amendment No. 42,65
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Se 3/4.8 ELECTRICAL POWER SYSTEMS BASES 3 /4.8.1. 3/4.8.2. and 3/4.8.3 A.C. SOURCES. D.C. SOURCES. AND ONSITE POWER DISTRIBUTION The OPERABILITY of the A.C. and D.C power sources and associated distri-bution systems during operation ensures that sufficient power will be avail-able to supply the safety-related equipment required for:
(1) the safe shut-down of the facility, and (2) the mitigation and control of accident condi-tions within the facility. The minimum specified independent and redundant A.C. and D.C. power sources and distribution systems satisfy the requirements of General Design Criterion 17 of Appendix A to 10 CFR Part 50.
The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commen-surate with the level of degradation. The OPERABILITY of the power sources are consistent with the initial condition assumptions of the safety analyses and are based upon maintaining at least one redundant set of onsite A.C. and D.C. power sources and associated distribution systems OPERABLE during acci-dent conditions coincident with an assumed loss-of-offsite power and single failure of the other onsite A.C. source. The A.C. source aid D.C. source allowable out-of-service times are based en Regulatory Guide 1.93,
" Availability of Electrical Power Sources", December 1974. When one diesel generator is inoperable, there is an additional ACTION requirement to verify that all required systems, subsystems, trains, components and devices, that depend on the remaining OPERABLE diesel generator as a source of emergency power, are also OPERABLE, and that the steam-driven auxiliary feedwater pump is OPERABLE. This requirement is intended to provide assurance that a loss-of-offsite power event will not result in a complete loss of safety function of critical systems during the period one of the diesel generators is inoperable.
The term verify as used in this context means to administratively check by examining logs or other information to determine if certain components are out-of-service for maintenance or other reasons.
It does not mean to perform the Surveillance Requirements needed to demonstrate the OPERABILITY of the component.
The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that:
(I) the facility can be maintained in the shutdown or refueling condition for extended time periods, and (2) sufficient instrumentation and control capability are available for monitoring and maintaining the unit status.
The Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators are in accordance with the recommendations of Regulatory Guides 1.9, " Selection of Diesel Generator Set Capacity for Standby Power Sup-plies," Revision 1, November 1978, 1.108, " Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," Revision 1, August 1977 as modified by Amendment No. 8 issued on May 29, 1987, and 1.137, " Fuel-011 Systems for Standby Diesel Generators,"
Revision 1, October 1979.
WOLF CREEK - UNIT I B 3/4 8-1 Amendment No. 8,59, 65 l
ELECTRIC POWER SYSTEMS BASES A.C. SOURCES. D.C. SOURCES. AND ONSITE POWER DISTRIBUTION (Continued)
Each diesel generator (DG) is provided with an engine overspeed trip to prevent damage to the engine.
Recovery from the transient caused by the loss of a large load could cause diesel engine overspeed, which, if excessive, might result in a trip of the engine. The DG load response characteristics and capability to reject the largest single load without exceeding predetemined voltage and frequency are demonstrated while maintaining a specified margin to the overspeed trip as required by Regulatory Guide 1.9, Position C.4.
For meeting Surveillance Requirements, the largest single load is defined as a load equivalent to the ESW pump motor while under the full post-LOCA mode of operation.
The Surveillance Requirement for demonstrating the OPERABILITY of the Station batteries are based on the recomendations of Regulatory Guide 1.129,
" Maintenance Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants," February 1978, and IEEE Std 450-1980, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Bat-teries for Generating Stations and Substations."
Verifying average electrolyte temperature above the minimum for which the battery was sized, total battery terminal voltage on float charge, connection resistance values and the perfomance of battery service and discharge tests ensures the effectiveness of the charging system, the ability to handle high discharge rates and compares the battery capacity at that time with the rated l
capacity.
Table 4.8-2 specifies the normal limits for each designated pilot cell and each connected cell for electrolyte level, float voltage and specific gravity. The limits for the designated pilot cells float voltage and specific gravity, greater than 2.13 volts and 0.015 below the manufacturer's full charge specific gravity or a battery charger current that had stabilized at a 1
low value, is characteristic of a charged cell with adequate capacity. The l
nomal limits for each connected cell for float voltage and specific gravity, l
greater than 2.13 volts and not more than 0.020 below the manufacturer's full charge specific gravity with an average specific gravity of all the connected cells not more than 0.010 below the manufacturer's full charge specific gravity, ensures the OPERABILITY and capability of the battery.
Operation with a battery cell's parameter outside the normal limit but within the allowable value specified in Table 4.8-2 is permitted for up to 7 days. During this 7-day period:
(1) the allowable values for electrolyte level ensures no physical damage to the plates with an adequate electron transfer capability; (2) the allowable value for the average specific gravity of all the cells, not more than 0.020 below the manufacturer's recommended full charge specific gravity, ensures that the decrease in rating will be less than the safety margin provided in sizing; (3) the allowable value for an individual cell's specific gravity, ensures that an individual cell's specific gravity will not be more than 0.040 below the manufacturer's full charge
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specific gravity and that the overall capability of the battery will be maintained within an acceptable limit; and (4) the allowable value for an individual cell's float voltage, greater than 2.07 volts, ensures the battery's capability to perfom its design function.
WOLF CREEK - UNIT 1 B 3/4 8-2 Amendment No. 59
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ADMINISTRATIVE CONTROLS STARTUP REPORT i
6.9.1.1 A summary report of plant startup and power escalation' testing shall be submitted following-(1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
6.9.1.2 The Startup Report shall address each of the tests identified in the Final Safety Analysis Report FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.
Any corrective ACTIONS that were required to obtain satisfactory operation shall also be described.
Any additional specific details required i
in license conditions based on other commitments shall be included in this report.
- 6. 9. L 3 Startup Reports snall be submitteo within:
(1) 90 days following completien of the Startup Test Program, (2) 90 days following resumption of connencerent o' commercial power operation, or (3) 9 months following initial 1
criticslity, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption o-commencement of commercial operation) supplementary reports shall be submitted at least every 2 months until all three events have been completed.
ANNUAL REPORT _5 Ar ual Reports.overing the acti ities of the Unit as described below 6.9.1.4 v
for the previous caler. der year shall be submitted prior to March I of each year.
The initial report snol' be submitted prior to March I of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include:
a.
Tabulation on an annual basis cf the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrems/yr and their associated man rem exposure according to work and job functions,* e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.
The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources should be assigned to specific major work functions; and This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.
WOLF CREEK UNIT 1 6-19 Amendment No. 42 R-1 e ! 231
7 ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) b.
Documentation of all challenges to the PORVs or safe,ty valves.
The results of specific activity analysis in which the primary coolant c.
exceeded the limits of Specification 3.4.8.
The following information shall be included:
(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit.
Each result should include date and time of sampling and the radiciodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific acti t ty of the primary coolant exceeded the radiciodine limit.
i ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.
The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.
The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix 1 to 10 CFR Part 50.
ANNUAL RAD 10sCTIVE EFFLUJNT RELEASE REPORT l
6.9.1.7 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.
The report snall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.
The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix 1 to 10 CFR Part 50.
MONTHLY OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience shalf te submitted on a monthly basis to the Director, Office of Resource Management, U.S.
Nuclear Regulatory Commission, Washington, D.C.
20555, with a copy to the NRC Regional Office, no later than the 15th of each month following the calendar month covered by the report.
WOLF CREEK - UNIT 1 6-20 Amendment No. 42, 65
i ADMINISTRATIVE CONTROLS OFFSITE DOSE CALCULATION MANUAL (ODCM) c.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the l
t report in which any change to the ODCM was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
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WOLF CREEK - UNIT 1 6-25 Amendment No. 44-55
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