ML20100R543

Amend 97 to License NPF-42,changing TS to Reflect Approval of 10CFR50,Appendix J,Option B

ML20100R543
Person / Time
Site:	Wolf Creek
Issue date:	03/01/1996
From:	Stone J NRC (Affiliation Not Assigned)
To:
Shared Package
ML20100R549	List: ML20100R543 ML20100R552
References
NUDOCS 9603120452
Download: ML20100R543 (15)

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UNITED STATES y

NUCLEAR REGULATORY COMMISSION E

WASHINGTON, D.C. - 88*1 49.....

WOLFCREEKNUCLEAROPERATINGCbRPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 License No. NPF-42 1.

The Nuclear Regulatory Commission (the Commission) 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 December 20, 1995, as supplemented by letter dated February 8,1996, complies with the standards and requirements of the Atomic Energy i

Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;

]

B.

The facility will operate in confomity with the taplication, as amended, the provisions of the Act, and the rules and regulations of the Commission; 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 Commission's regulations; D.

The issuance of this license amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satisfied.

9603120452 960301 PDR ADOCK 05000482 P

PDR

'. 2.

Accordingly, the license is amended by changes to the Technical Specifications 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 Snecification1 The Technical Specifications contained in Appendix A, as revised through Amendment No. 97, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are herehy incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

The license amendment is effective as of its date of issuance and shall be implemented prior to startup from the eighth refueling outage.

FOR THE NUCLEAR REGULATORY COMISSION

{

James C. Stone, Senior Project Manager Project Directorate IV-2 1

Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 1, 1996 i

l ATTACHMENT TO LICENSE AMENDMENT NO. 97 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 l

Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and l

contain marginal lines indicating the areas of change. The corresponding i

overleaf pages are also provided to maintain document completeness.

REMOVE INSERT j

1-2 1-2 3/4 6-1 3/4 6-1 3/4 6-4 3/4 6-4 l

3/4 6-5 3/4 6-5 3/4 6-12 2/4 6-12

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6-18 6-18 6-18a 6-18a 6-18b l

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4 A

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1.0 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications.

ACTION 1.1 ACTION shall be that part of a Technical Specification which prescribes remedial measures required under designated conditions.

ACTUATION LOGIC TEST 1.2 An ACTUATION LOGIC TEST shall be the application of various simulated input combinations in conjunction with each possible interlock logic state and verification of the required logic output.

The ACTUATION LOGIC TEST shall include a continuity check, as a minimum, of output devices.

ANALOG CHANNEL OPERATIONAL TEST 1.3 An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY of alars, interlock and/or trip functions.

The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the alarm, inter-lock and/or Trip 5etpoints such that the Setpoints are within the required range and accuracy.

AXIAL FLUX DIFFERENCE AXIALFLUXDIFFERENCEshallbethedifferenceinnormalizedfluxsihnals 1.4 between the top and bottom halves of a two section excore neutron detector.

CHANNEL CALIBRATION 1.5 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input.

The CHANNEL CALIBRATION shall encompass the. entire channel including the sensors and alare, interlock and/or trip functions and may be performed by any. series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 1

1.6 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation.

This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

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S WOLF CREEK - UNIT 1 1-1

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DEFINITIONS 1

CONTAIMENT INTEGRITY 1.7 CONTA!WENT INTEGRITY shall exist when:

a.

All penetrations required to be closed during accident conditions are either:

i 1)

Capable of being closed by an OPERABLE containment automatic isolation valve system, or j

2)

Closed by manual valves, blind flanges, or deactivated automatic valves secured in their c'osed positions, except as provided in Table 3.6-1 of Specification 3.6.3.

b.

All equipment hatches are closed and sealed, c.

Each air lock is in compliance with the requirements of Specification 3.6.1.3, d.

The sealing mechanism associated with each penetration (e.g., welds, bellows, or 0-rings) is OPERABLE, and e.

The containment leakage rates determined by Specification 4.6.1.1.c l

are within limits.

I EQt(IPOLLED LEAKAGE 1.8 CONTROLLED LEAKAGE shall be that seal water flow from the reactor coolan't pump seals.

CORE ALTERATION 1.9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.

CORE OPERATING LINITS REPORT i

1.10 The CORE OPERATING LINITS REPORT (COLR) is the unit-specific document that provides core operating limits for the current operating reload cycle.

These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.9.

Plant operation within these operating limits is addressed in individual Specifications.

WOLF CREEK - UNIT 1 1-2 Amendment No. 6h89,97

i 3/4.6 CONTAIMENT SYSTEMS 3/4.6.1 PRIMARY CONTAIMENT i

CONTAIMENT INTEGRITY i

1 LIMITING CONDITION FOR OPERATION l

3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY: MODES 1, 2, 3, and 4.

i ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within 4

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 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 /> and 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 />.

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SURVEILLANCE REOUIREMENTS l

4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

l a.

At least once per 31 days by verifying that all penetrations

• not i

capable of being closed by OPERABLE containment automatic j

isolation valves and required to be closed during accident i

conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.3;

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b.

By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3; i

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c.

By performing containment leakage rate testing in accordance with 9

j the Containment Leakage Rate Testing Program of Specification j

j 6.8.4.i; and 3

d.

By verifying containment structural integrity in accordance with l

j the Containment Tendon Surveillance Program of Specification j

6.8.5.c.

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• Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured

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in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.

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WOLF CREEK - UNIT 1 3/4 6-1 Amendment No. 89,97 (Next page is 3/4 6-4)

CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with both doors closed except when the air lock is being used for normal transit and exits through the containment, then at least one air lock door shall be closed.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a.

With one containment air lock door inoperable:

1.

Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door

closed, 2.

Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days, 3.

Otherwise, 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 /> and 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 />, and 4.

The provisions of Specification 3.0.4 are not applicable.

b.

With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 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 /> and 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 />.

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l WOLF CREEK - UNIT 1 3/4 6-4 Amendment No. 97 l

1 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

4 I

a.

By verifying leakage rates in accordance with the Containment Leakage Rate Testing Program of Specification 6.8.41; and b.

At least once per 6 months by verifying that only one door in each air lock can be opened at a time.

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WOLF CREEK - UNIT 1 3/4 6-5 Amendment No. 97 f-

J CONTAINMENT SYSTEMS INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION 3.6.1.4 Primary containment internal pressure shall be maintained between

+1.5 and -0.3 psig.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With the containment internal pressure outside of the limits above, restore the internal pressure to within the limits within I hour 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 /> and 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 4.6.1.4 The primary containment internal pressure shall be determined to be within the limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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e WOLF CREEK - UNIT 1 3/4 6-6 i

b CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.7 Each containment purge supply and exhaust isolation valves shall be OPERABLE and:

Each 36-inch containment shutdown purge supply and exhaust isolation a.

valve shall be closed and blank flanged, and b.

The 18-inch containment mini purge supply and exhaust isolation valve (s) may be open for up to 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> during a calendar year.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With a 36-inch containment purge supply and/or exh'aust isolation a.

valve open or not blank flanged, close and/or blank flange that valve or isolate the penetration (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, otherwise 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 /> and 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 />.

b.

With the 18-inch containment mini purge supply and/or exhaust isolation valve (s) open for more than 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> during a calendar year, close the open 18-inch valve (s) or isolate the penetration (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, otherwise 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 />, and 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 />.

With a containment purge supply and/or exhaust isolation valve (s) c.

having a measured leakage rate in excess of the limits of j

Specifications 4.6.1.7.2 and/or 4.6.1.7.4, restore the inoperable' i

valve (s) to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, otherwise 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 />, and 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 />.

t WOLF CREEK - UNIT 1 3/4 6-11

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.1.7.1 Each 36-inch containment shutdown purge supply and exhaust isolation valve (s)* shall be verified blank flanged and closed at least once per,31 days.

4.6.1.7.2 Each 36-inch containment shutdown purge supply and exhaust isolation valve and its associated blank flange shall be leak tested at least once per 24 months and following each reinsta11ation of the blank flange when pressurized to P, 48 psig, and verifying that when the measured leakage rate for these valves and flanges, including stem leakage, is added to the leakage rates determined pursuant to Specification 4.6.1.lc., for all other Type B and l

C penetrations, the combined leakage rate is less than 0.60 L,.

4.6.1.7.3 The cumulative time that all 18-inch containment mini-purge supply and/or exhaust isolation valves have been open during a calendar year shall be determined at least once per 7 days.

4.6.1.7.4 At least once per 3 months each 18-inch containment mini-purge supply and exhaust isolation valve with resilient material seals shall be demonstrated OPERABLE by verifying that the measured leakage rate is less than 0.05 L, when pressurized to P,.

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• Except valves and flanges which are located inside containment. These valves i

.shall be verified to be closed with their blank flanges installed prior to entry into MODE 4 following each COLD SHUTDOWN.

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WOLF CREEK - UNIT 1 3/4 6-12 Amendment No. a@,97

I ADMINISTRATIVE CONTROLS

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PROCEDURES AND PROGRAMS (Continued) i

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e.

Radioactive Effluent Controls Procram

{

A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as' low as reasonably i

achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial i

t actions to be taken whenever the program limits are exceeded. The j

program shall include the following elements:

1 1)

Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and i

setpoint determination in accordance with methodology in the

ODCM, 2)

Lititstions on the concentrations cf rcdioactive material re Nased

.in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Fart 20, Appendix E, Table II, Column 2, 1

3) l'onitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM, 4)

Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid i

effluents released to UNRESTRICTED AREAS conforming to Appendix I l

to 10 CFR Part 50, 5)

Determination o'f cumulative and projected dose contributions j

from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 33 days, 6)

Limitations on the operability an; use of the liquid and gase,ws effluent treatment systems to ensure that the appropriate portions 1

of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of j

the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, i

7)

Limitations of the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix

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B, Table II, Column 1, WOLF CREEK - UNIT 1 6-17 Amendment No. 42 1

ADMINISTRATIVE CONTROLS

, PROCEDURES AND PROGRAMS (Continued) 8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9)

Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,

10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

f.

Radioloaical Environmental Monitorina Proaram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) veritication of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1)

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM.

2)

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and the modifications to the monitoring program are made if required by the results of this census, and 3)

Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

g.

Reserved l

h.

Reserved l

1.

Containment Leakaae Rate Testina Procram A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.

The peak calculated containment internal pressure for the design basis loss of coolant accident, P,, is 48 psig.

WOLF CREEK - UNIT 1 6-18 Amendment No. 4h89,97

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_ MINISTRATIVE CONTROLS AD

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j PROCEDURES AND PROGRAMS (Continued)

The maximum allowable containment leakage rate, L, at P,, shall be 1

0.20% of containment air weight per day.

Leakage rate acceptance criteria are:

a.

Containment leakage rate acceptance criterion is s 1.0 L Duringthefirstunitstartupfollowingtestinginaccor8ance with this program, the leakage rate acceptance criteria are 5 0.60 L, for the Type B and C tests and s 0.75 L, for Type A tests; b.

Air lock testing acceptance criteria are:

i 1)

Overall air lock leakage rate is s 0.05 L, when tested at i

1 P,;

4 2)

For each door, leakage rate is s 0.005 L, when pressurized I

to 2 10 psig.

The provisions of Technical Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

The provisions of Technical Specification 4.0.3 are applicable to the Containment Leakage Rate Testing Program.

j 6.8.5 a.

Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the WASTE GAS HOLDUP SYSTEM, the quantity of radioactivity contained in gas storage tanks, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.

The program shall include:

1.

The limits for concentrations of hydrogen and oxygen in the WASTE GAS HOLDUP SYSTEM and a serve 111ance program to ensure the limits are maintained.

2.

A surveillance program to ensure that the quantity of radioactivity contained in each gas storage tank is less than the amount that would result in a whole body exposure of 20.5 rem to any individual in an UNRESTRICTED AREA in the event of an uncontrolled release of the tanks' contents,. consistent with Branch Technical Position ETSB 11-5, " Postulated Radioactive Releases due to Waste Gas System Leak or Failure."

WOLF CREEK - UNIT 1 6-18a Amendment No. 89,97

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) i 3.

A surveillance program to ensure that the quantity of i

radioactivity contained in following outdoor liquid radwaste tanks that are not surrounded by liners, dikes, i

or walls capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste system is less than the e

amount that would result in concentrations less than the limits of 10 CFR 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA, in the event of an uncontrolled release of the tank's contents.

a.

Reactor Makeup Water Storage Tank, b.

Refueling Water Storage Tank, c.

Condensate Storage Tank, and d.

Outside Temporary tanks, excluding demineralizer vessels and the liner being used to solidify radioactive waste.

The provisions of Specifications 4.0.2 and 4.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.

b.

Reactor Coolant Pump Flywheel Inspection Program Each reactor coolant pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory i

Guide 1.14, Revision 1, dated August 1975.

I c.

Containment Tendon Surveillance Program This program provides controls for monitoring tendon i

perfo.,4ance, including the effectiveness of the tendon corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial plant operation as well as periodic testing i

thereafter. The Containment Tendon Surveillance Program, and i

its inspection frequencies and acceptance criteria, shall be in accordance with Wolf Creek Generating Station position on draft

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Revision 3 of. Regulatory Guide 1.35 dated April 1989.

The provisions of Specifications 4.0.2 and 4.0.3 are applicable to the Containment Tendon Surveillance Program inspection frequencies.

6.9 REPORTING REOUIREMENTS j

ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the NRC Regional Office unless otherwise noted.

WOLF CREEK - UNIT 1 6-18b Amendment No. 89,97

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