ML20217K820
| ML20217K820 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 04/27/1998 |
| From: | Skay D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217K825 | List: |
| References | |
| NUDOCS 9805040145 | |
| Download: ML20217K820 (23) | |
Text
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UNITED STATES
,j NUCLEAR RESULATORY COMMISSION WASHINGTON, D.C. 20666-0001
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-373 LASALLE COUNTY STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.125 License No. NPF-11 j
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated September 26,1997, as supplemented on April 7,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can b.e 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 set forth in 10 CFR Chapter ll D.
The issuance of this 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-11 is hereby amended to read as follows:
l 9805040145 980427 DR ADOCK 05000373 PDR l
l
4
't I (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.125, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented prior to restart of LaSalle, Unit 2, from the current outage.
j FOR THE NUCLEAR REGULATORY COMMISSION p sd 1
Donna M. Skay, Project ager Project Directorate 111-2 i
l Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technic,al Specifications l
Date of issuance: April 27, 1998 1
' s, t
ATTACHMENT TO LICENSE AMENDMENT NO. 125 FACILITY OPERATING LICENSE NO. NPF-11 l
DOCKET NO. 50-373 l
l Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT XVill XVill 3/4 6-15 3/4 6-15 3/4 6-41 3/4 6-41 i
3/4 6-42 3/4 6-42 B 3/4 6-2 B 3/4 6-2 l
6-20a 6-20a 6-20b l
l l
l l
l
3, g
i INDEX ADMINISTRATIVE CONTROLS i
SECTION PAGE 6.1 OR G A N IZATI O N......................................................................................
6-1 j
i l
6.1.1 High Radiation Area s........................................................................
6-15 J
6.2 PLANT OPERATING PROCEDURES AND PROGRAMS........................... 6-16 6.3 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE EVENT I N PLANT OPE RATION......................................................
6-20b 6.4 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED... 6-21 6.5 PLANT OPERATING RECORDS..................................................... 6-21 6.6 R E PORTI NG R EQ UI R EM E NTS............................................................. 6-22 6.7 PROCESS CONTROL PROGRAM........................................................ 6-26 6.8 OFFSITE DOSE CALCULATION MANUAL................................................. 6-27 6.9 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS.... 6-27
)
i l
i LA SALLE-UNIT 1 XVill Amendment No.125
i
- 1 CONTAINMENT SYSTEMS DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.8 The drywell and suppression chamber purge system may be in operation with the drywell i
or suppression chamber purge supply and exhaust butterfly isolation valves open for inerting, de-1 inerting and pressure control. Purging through the Standby Gas Treatment System shall be restricted to less than or equal to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per 365 days.
APPLICABILITY: OPERATIONAL CONDITIONS 1,2 AND 3 ACTION:
With any drywell or suppression chamber purge supply or exhaust butterfly isolation valve open l
for other than inerting, de-inerting or pressure control, close the butterfly valve (s) within one hour or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN withir. the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I SURVEILLANCE REQUIREMENTS 4.6.1.8.1 The cumulative time that the drywell and suppression chamber purge system has been in operation purging through the Standby Gas Treatment System shall be verified to be less than or equal to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per 365 days prior to use in this mode of operation.
LA SALLE - UNIT 1 3/4 6-15 Amendment No.125 t
l
)
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
Perform required standby gas treatment filter testing in accordance with, and at the frequency specified by, the Ventilation Filter Testing Program.
c.
Deleted.
d.
At least once per18 months by:
1.
Deleted.
2.
Verifying that the filter train starts and isolation dampers open on each of the following test signals:
a.
Reactor Building exhaust plenum radiation - high, b.
Drywell pressure - high, c.
Reactor vessel water level - low low, level 2, and d.
Fuel pool vent exhaust radiation - high.
3.
Deleted.
1 LA SALLE - UNIT 1 3/4 6-41 Amendment No.125
i CONTAINMENT SYSTEMS
- 1 SURVEILLANCE REQUIREMENTS (Continued) e.
Deleted.
f.
Deleted.
l l
l 1.A SALLE - UNIT 1 3/4 6-42 Amendment No.125 L
I*
- 1 CONTAINMENT SYSTEMS
' BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.14 DELETED 3/4.6.1,5 DELETED 3/4.6.1,6 DRYWELL AND SUPPRESSION CHAMBER INTERNAL PRESSURE The limitation on drywell and suppression chamber intomal pressure ensure that the containment peak pressure of 3g.6 psig does not exceed the design pressure of 45 psig during LOCA conditions or that the extemal pressure diMerential does not exceed the design maximum extemal pressure diMerential of 5 psid. The limit of 2.0 psig for initial positive primary containment pressure will limit the total pressure to 3g.6 psig which is less than the design pressure and is consistent with the accident analysis.
3/4.6.1.7 DRYWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that the containment peak air temperature does not exceed the design temperature of 340*F during LOCA conditions and is consistent with the accident analysis.
3/4.6.1.8 DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM The drywell and suppression chamber purge supply and exhaust isolation valves are required to be closed during plant operation except as required for inerting, de-inerting and pressure control. During operations involving inerting, de-inerting and pressure control, only the drywell or suppression chamber purge supply and exhaust isolation valves may be open to prevent the creation of a bypass path between the drywell and suppression chamber. Creation of a bypass path between the drywell and the suppression chamber air space through the vent and purge lines would allow steam and gases from a LOCA to bypass the downcomers to the suppression poolin excess of design bypass leakage. These valves have been demonstrated capable of closing during a LOCA or steamline break accident from the full open position.
LA SALLE - UNIT 1 B 3/4 6-2 Amendment No.125
l 3
1 ADMINISTRATIVE CONTROLS PLANT OPERATING PROCEDURES AND PROGRAMS (Continued) 7.
Primary Conta!nment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the primary containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as n odified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Testing Program," dated September 1995.
The peak calculated primary containment intemal pressure for the design basis loss of coolant accident, P, is 39.6 psig.
The maximum allowable primary containment leakage rate, L, at P., is 0.635% of primary containment air weight per day.
Leakage rate acceptance criteria are:
a.
Primary containment overall leakage rate acceptance criterion is s1.0 L,. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are s 0.60 L, for the combined Type B and Type C tests, and s 0.75 L, for Type A tests.
b.
Air lock testing acceptance criteria are:
1)
Overall air lock leakage rate is s0.05 L, when tested at 2 P.
2)
For each door, the seal leakage rate is s 5 scf per hour when the gap between the door seals is pressurized to 210 psig.
The provisions of specification 4.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.
The provisions of specification 4.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.
B.
Ventilation Filter Testing Program (VFTP)
A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in Regulatory Guide 1.52, Revision 2, dated March 1978, and in accordance with ASME N510-1989.
The provisions of Specifications 4.0.2 and 4.0.3 are applicable to the VFTP test frequencies.
a.
Demonstrate for each of the ESF systems that an inplace test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass
<0.05% when tested in accordance with ASME N510-1989, at the system flowrate specified below-ESF Ventilation Flowrate (cfm)
System SBGT System 23600 and s 4400 4
l LA SALLE - UNIT 1 6-20s Amendment No. 125 l
l 1
ABMINisTRATIVE CONTROLS 3LANT OPERATING PROCEDURES AND PROGRAMS (Continued) b.
Demonstrate for each of the ESF system filter units that an inplace test of the charcoal adsorber shows a penetration and system bypass less than the value specified below, when tested in accordance with ASME N510-1989, at the system flowrate specified below:
j ESF Ventilation Penetration and Flowrate (cfm) l System System Bypass l
l SBGT System 0.05 %
2 3600 and s 4400 c.
Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2, shows the methyliodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of 30'C, a relative humidity of 70 % and a face velocity as specified below.
ESF Ventilation Penetration Face System
. Velocity (fpm) l SBGT System 0.5 %
40 d.
Demonstrate for each of the ESF systems that the pressure drop across the combined moisture separator, heater, profilter, HEPA filters and the charcoal adsorbers is less than the value specified below when tested at the system flowrate specified below:
l ESF Ventilation Delta P Flowrate (cfm)
System (inches wg)
SBGT System 8
2 3600 and s 4400 e.
Demonstrate that the heaters for each of the ESF systems dissipate the electrical power specified below when tested in accordance with ASME N510-1989. These readings shallinclude appropriate corrections for variations from 480 Volts at the bus.
ESF Ventilation Wattage (kw)
System l
SBGT System 2 21 and s 25 6.3 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE EVENT IN PLANT OPERATION The following actions shall be taken for REPORTABLE EVENTS:
l a.
The Commission shall be notified and a Licensee Event Report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the Onsite Review and Investigative Function.
l LA SALLE - UNIT 1 6-20b Amendment No.125
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1 UNITED STATES g
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NUCLEAR RECULATORY COMMISSION WASHINGTON, D.C. 20666 4001 COMMONWEALTH EDISON COMPANY J
DOCKET NO. 50-374 LASALLE COUNTY STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE.
Amendment No. 110 License No. NPF-18 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated September 26,1997, as supplemented on April 7,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I;
i B.
The facility will operate in conformity with the application, the provisions of the Act, and the 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 set imih in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical m the common defense and i
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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is hereby amended to read as follows:
l
3
, (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 110, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented prior to startup of LaSalle, Unit 1, from the current outage.
FOR NUCLEAR REGUI.ATORY COMMISSION L.m-A' &
Donna M. Skay, Project nager Project Directorate 111-2 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
April 27, 1998
ATTACHMENT TO LICENSE AMENDMENT NO.110 FACILITY OPERATING LICENSE NO NPF-18 1
DOCKET NO. 50-374 l
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain a verticalline indicating the area of change. Pages indicated by an asterisk (*) are overleaf pages and are provided for convenience only.
REMOVE INSERT j
1 XVill XVill i
'3/4 6-17
'3/4 6-17 3/4 6-18 3/4 6-18
- 3/4 6-43
- 3/4 6-43 3/4 6-44 3/4 6-44 3/4 6-45 3/4 6-45 B 3/4 6-2a B 3/4 6-2a 6-20a 6-20a 6-20b l
I INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 ORGANIZATION............
6-1 6.1.1 High Radiation Areas 6-15 6.2 PLANT OPERATING PROCEDURES AND PROGRAMS 6-16 6.3 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE EVENT IN PLANT OPERATION 6 20b 6.4 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED..
6-21 6.5 PLANT OPERATING RECORDS 6-21 6.6 REPORTING REQUIREMENTS.
6-22 6.7 PROCESS CONTROL PROGRAM 6-26 6.8 0FFSITE DOSE CALCULATION MANUAL 6-27 6.9 MAJOR CHANGES TO RADIDACTIVE WASTE TREATMENT SYSTEMS 6-27 1
LA SALLE - UNIT 2 XVill Amendment No. 110
1 CONTAINMENT SYSTEMS l
l DRYWELL AVERAGE AIR TEMPERATURE l
LIMITING CONDITION FOR OPERATION 3.6.1.7 Drywell average air temperature shall not exceed 135'F.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
With the drywell average air temperature greater than 135'F, reduce the average air temperature to within the limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN.within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l SURVEILLANCE REQUIREMENTS l
i l
4.6.1.7 The drywell average air temperature shall be the average temperature l
of the operating return air plenum upstream of the primary containment ventila-tion heat exchanger coil and cabinet at the following locations and shall be l
determined to be within the limit at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
Elevation Azimuth a.
740'0" 248' b.
740'0" 76*
1 i
t I
t I
l-l LA SALLE - UNIT 2 3/4 6-17
- s CONTAINMENT SYSTEMS DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.8 The drywell and suppression chamber purge system may be in operation with the drywell or suppression chamber purge supply and exhaust butterfly isolation valves open for inerting, deinerting, and pressure control. Purging through the Standby Gas Treatment System shall be restricted to less than or equal to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per 365 days.
APPLICABILITY: OPERATIONAL CONDITIONS 1,2, and 3.
ACTION:
With any drywell or suppression chamber purge supply or exhaust butterfly isolation valve open for other than inerting, deinerting, or pressure control, close the butterfly valve (s) within 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 SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hoors.
SURVEILLANCE REQUIREMENTS 4.6.1.8.1 The cumulative time that the drywell and suppression chamber purge system has been in operation purging through the Standby Gas Treatment System shall be verified to be less than or equal to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per 365 days prior to use in this mode of operation.
LA SALLE - UNIT 2 3/4 6-18 Amendment No.110
u
.. y..,
CONTAINMENT SYSTEMS I
STANDBY GAS TREATMENT SYSTEM l
l LIMITING CONDITION FOR OPERATION 3.6.5.3 Two independent standby gas treatment subsystems shall be OPERABLE.#
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, 3, and
- ACTION:
a.
With one standby gas treatment subsystem inoperable, restore the inoperable subsystem to OPERABLE status withf n 7 days, or:
i 1.
In OPERABLE CONDITION 1, 2, or 3, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHilTDOWN sithin the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
In OPERATIONAL CONDITION *, suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS and opera-tions with a potential for draining the reactor vessel.
The i
provisions of Specification 3.0.3 are not applicable.
b.
With both standby gas treatment subsystems inoperable in OPERATIONAL
' 4 CONDITION *, suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS and operations with a potential for j
draining the reactor vessel.
The provisions of Specification 3.0.3 l
are not applicable.
SURVEILLANCE REQUIREMENTS 4.6.5.3 Each standby gas trc tment subsystem shall be demonstrated OPERABLE:
a.
At least once per 31 days by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the subsystem operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters OPERABLE.
t l
l "When irradiated fuel is being handled in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
- The normal or emergency power source may be inoperable in OPERATIONAL CONDITION *.
LA SALLE - UNIT 2 3/4 6-43
CONTAINMENT SYSTEMS y,,
SURVEILIANCE REQUIREMENTS (Continued) b.
Perform required standby gas treatment filter testing in accordance with, and at the frequency specified by, the Ventilation Filter Testing Program.
c.
Deleted.
l d.
At least once per 18 months by:
1.
Deleted.
l 2.
Verifying that the filter train starts and isolation dampers open on each of the following test signs!r a.
Reactor Building te u r.enum radiation - high, b.
Drywell pressure - high, I
c.
Reactor vessel water level - low low, level 2, and d.
Fuel pool vent exhaust radiation - high.
3.
Deleted.
1 i
l l
LA SALLE - UNIT 2 3/4 6-44 Amendment No.110
CONTAINMENT SYSTEMS
.? 3*?
SURVEILLANCE REQUIREMENTS (Continued) e.
Deleted.
f.
Deleted.
l l
l LA SALLE - UNIT 2 3/4 6-45 Amendment No. 110
- o 2'a 1
CONTAINMENT SYSTEMS BASES i
1 3/4.6.1 PRIMARY CONTAINMENT l
3/4.6.15 DELETED 3/4.6.1.6 DRYWELL AND SUPPRESSION CHAMBER INTERNAL PRESSURg i
The limitation on drywell and suppression chamber intemal pressure ensure that the containment peak pressure of 39.6 psig does not exceed the design pressure of 45 psig during LOCA conditions or that the extemal pressure differential does not exceed the design maximum extemal pressure differential of 5 psid, The limit of 2.0 psig for initial positive primary containment pressure will limit the total pressure to 39.6 psig which is less than the design pressure and is consistent with the accident analysis.
i 3/4.6.1.7 DRYWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that the containment peak air temperature does not exceed the design temperature of 340'F during LOCA conditions and is consistent with the accident analysis.
3/4.6.1.8 DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM The drywell and suppression chamber purge supply and exhaust isolation valves are required to be closed during plant operation except as required for inerting, de-inerting and pressure control. During operations involving inerting, de-inerting and pressure control, only the drywell or suppression chamber purge supply and exhaust isolation valves may be open to prevent the creation of a bypass path between the drywell and suppression chamber. Creation of a bypass path between the drywell and the suppression chamber air space through the vent and purge lines would allow steam and gases from a LOCA to bypass the downcomers to the suppression poolin excess of design bypass leakage. These valves have been demonstrated capable of closing during a LOCA or steamline break accident from the full open position.
i l
l l
LA SALLE - UNIT 2 B 3/4 6-2a Amendment No.110 l
l
ADMINISTRATIVE CONTROLS 7
PLANT OPERATING PROCEDURES AND PROGRAMS (Continuid) the Initial Structural Integrity Tests were not within 2 years of each other.
The Onsite Review and investigative Function shall be responsible for reviewing and approving changes to the Inservice Inspection Program for Post Tensioning Tendons.
1 i
The provisions of 4.0.2 and 4.0.3 are applicable to the Tendon Surveillance Program l
inspection frequencies.
l 7.
Primarv Containment Leakaae Rate Testino Proaram l
A program shall be established to implement the leakage rate testing of the primary containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J Option B, I
as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment i
l Leak-Testing Program," dated September 1995.
The peak calculated primary containment intemal pressure for the design basis loss of coolant accident, P., is 39.6 psig.
The maximum allowable primary containment leakage rate, L, at P, is 0.635% of primary containment air weight per day.
Leakage rate acceptance criteria are:
a.
Primary containment overallleakage rate acceptance criterion is s1.0 L. During the first unit startup following testing in accordance with this program, the I
leakage rate acceptance criteria are s 0.60 L, for the combined Type B and Type C tests, and s 0.75 L, for Type A tests.
b.
Air lock testing acceptance criteria are:
- 1) Overall air lock leakage rate is s0.05 L, when tested at 2 P,.
l
- 2) For each door, the sealleakage rate is s 5 scf per hour when the gap between the door seals is pressurized to 210 psig.
The provisions of specification 4.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.
The provisions of specification 4.0.3 are app!icable to the Primary Containment Leakage Rate Testing Program.
8.
Ventilation Filter Testina Proaram NFTP)
A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in Regulatory Guide 1.52, Revision 2, dated March 1978, and in accordance with ASME N510-1989.
The provisions of Specifications 4.0.2 and 4.0.3 are applicable to the VFTP test frequencies.
LA SALLE - UNIT 2 6-20a Amendment No. 110 f
L
AIMAINISTRATIVE CONTROLS
' MLANT QPERATING PROCEDURES AND PROGRAMS (Continued)
Demonstrate for each of the ESF systems that an inplace test of the high efficiency a.
particulate air (HEPA) filters shows a penetration and system bypass < 0.05 % when tested in accordance with ASME N510-1989, at the system flowrote specified below; ESF Ventilation Flowrate (cfm)
System SBGT System 2 3600 and s 4400 b.
Demonstrate for eacn of the ESF system filter units that an inplace test of the charcoal adsorber shows a penetration and system bypass less than the value specified below, when tested in accordance with ASME N510-1989, at the system flowrate specified below:
ESF Ventilation Penetration and Flowrate (cfm)
System System Bypass SBGT System 0.05 %
2 3600 and s 4400 c.
Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsotter, when obtained as described in Regulatory Guide 1.52, Revision 2, shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of 30'C, a relative humidity of 70 % and a face velocity as specified below.
ESF Ventilation Penetration Face Velocity (fpm)
System SBGT System 0.5%
40 d.
Demonstrate for each of the ESF systems that the pressure drop across the combined moisture separator, heater, profilter, HEPA filters and the charcoal adsorbers is less than the value specified below when tested at the system flowrate specified below:
ESF Ventilation Delta P Flowrate (cfm)
System (inches wg)
SBGT System 8
2 3600 and s 4400 e.
Demonstrate that the hesters for each of the ESF systems dissipate the electrical power specified below when tested in accordance with ASME N510-1989. These i
readings shall include appropriate corrections for variations from 480 Volts at the bus.
ESF Ventilation Wattage (kw)
System SBGT System 2 21 and s 25 6.3 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE EVENT IN PLANT OPERATION The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a Licensee Event Report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the Onsite Review and Investigative Function.
LA SALLE - UNIT 2 6-20b Amendment No. 110