ML20155E307
| ML20155E307 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 04/11/1986 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20155E310 | List: |
| References | |
| NUDOCS 8604170560 | |
| Download: ML20155E307 (14) | |
Text
_ _ _ - _ _ - _ _ _
je UNITED STATES g
NUCLEAR REGULATORY COMMISSION o
(
WASHINGTON. D. C. 20555
\\
/
COMMONWEALTH EDISON COMPANY 00CV.ET NO. 50-373 LA SALLE COUNTY STATT3N, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 38 License No. NPF-11 1.
The Nuclear Reaulatory Connission (the Commission or the NRC) having found that:
A.
The application for amendment filed by the Commonwealth Edison Comoany 1
(the licensee), dated February 7,1986, as supplemented by letter dated March 5,1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's reculations set forth in 10 CFR Chapter I; l
R.
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 endanaering the health and safety of the public, and (ii) that such activities will be conducted in comoliance with the Commission's regulations set forth in 10 CFR Chapter I; 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 reculations and all applicable requirements have been satisfied.
2.
Accordinaly, the license is amended by changes to the Technical Specifica-tions as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facilitf 0oeratina License No. NPF-11 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 38, and the Environmental Protection Plan contained in Appendix R, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Techriical Specifications and the Environmental Protection Plan.
8604170560 860411 PDR ADOCK 05000373 P
2 3.
This amendment is effective as of date of issuance.
FOR THE NUCLEAR REGULATORY COMISSION f
Elinor G. Adensam, Director BWR Project Directorate No. 3 Division of BWR Licensing
Enclosure:
Changes to the Technical Specifications Date of Issuance: A/R : ; y i
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1 T
s
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ENCLOS!!RE TO LICENSE AMENDMENT NO. 38 FACILITY OPERATING LICENSE NO. NPF-11 DOCKET NO. 50-373 t
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised paces are identified by Amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT i
V V
3/4 3-74 3/4 3-74 83/4 3-5 B3/4 3-5 3/4 7-5 3/4 7-5 e
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IEDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION....................
3/4 3-1 3/4.3.2 ISO LATION ACTUATION INSTRUMENTATION..........................
3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION......
3/4 3-23 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS Recirculation Pump Trip System Instrumentation..........
3/4 3-35 End-of-Cycle Recirculation Pump Trip System Instrumentation............................................
3/4 3-39 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION............................................
3/4 3-45 i
3/4.3.6 CONTROL R0D WITHDRAWAL BLOCK INSTRUMENTATION.................
3/4 350 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation.........................
3/4 3-56 Seismic Monitoring Instrumentation...........................
3/4 3-60 Meteorological Monitoring Instrumentation...................
3/4 3-63 Remote Shutdown Monitoring Instrumentation...................
3/4 3-66 Accident Monitoring Instrumentation..........................
3/4 3-69 Source Range Monitors........................................
3/4 3-72 Traversing In-core Probe System..............................
3/4 3-73 Ammonia Detection System.....................................
3/4 3-74 l Fire Detection Instrumentation...............................
3/4 3-75 Radioactive Liquid Effluent Monitoring Instrumentation.......
3/4 381 Radioactive Gaseous Effluent Monitoring Instrumentation......
3/4 386 Loose-Part Detection System..................................
3/4 3-91 3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION.............................................
3/4 3-92 LA SALLE - UNIT 1 V
Amendment No. 38
}
INSTRUMENTATION AMMONIA DETECTION SYSTEM l
LIMITING CONDITION FOR OPERATION 3.3.7.8 Two independent ammonia detection system subsystems shall be OPERABLE,*
each with two ammonia detectors, with their alarm / trip setpoints adjusted to actuate at an ammonia concentration of less than or equal to 25 ppm.
APPLICABILITY: All OPERATIONAL CONDITIONS.
ACTION:
With one ammonia detector in either detection subsystem inoperable, l
a.
restore the inoperable detector (s) to OPERABLE status within 7 days or, within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, initiate and maintain operation of at least one control room charcoal filter system train in the recircu-lation mode of operation.
b.
With both ammonia detection subsystems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of at least one control room charcoal j
filter system train in the recirculation mode of operation.
The provisions of Specification 3.0.4 are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.3.7.8 Each of the above required ammonia detection system subsystems shall l
be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months, f
- The normal or emergency power source may be inoperable in OPERATIONAL CONDITION 4 or 5.
LA SALLE - UNIT 1 3/4 3-74 Amendment No. 38
\\
INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 4
- ~
3/4.3.7.5 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess important variables following an accident.- This capability is con-sistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."
l 3/4.3.7.6 SOURCE RANGE MONITORS The source range monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup and shutdown.
At these power levels, reactivity additions should not be made without this flux level information available to the operator. When the inter-mediate range monitors are on scale adequate information is available without the SRMs and they can be retracted.
]
3/4.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM The OPERABILITY of the traversing in-core probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribu-tion of the reactor core.
3/4.3.7.8 AMMONIA DETECTION SYSTEM The OPERABILITY of the ammonia detection system ensures that an accidental
- l ammonia release will be detected promptly and the necessary protective actions will be automatically initiated to provide protection for~ control room person-nel.
Upon detection of a high concentration of ammonia,.the control room l
i emergency ventilation system will automatically be placed in the recirculation mode of operation to provide the required protection. The detection systems e
required by this specification are consistent with the recommendations of Regulatory Guide 1.78 " Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release."
3/4.3.7.9 FIRE DETECTION INSTRUMENTATION i
OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires.
This 4
capability-is required in order to detect and locate fires in their early j
stages.
Prompt detection of fires will reduce the potential for damage'to safety-related equipment and is an integral element in the overall facility fire protection program.
i LA SALLE UNIT - 1 B 3/4 3-5 Amendment No. 38
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
N b.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the train by:
1.
Verifying that the train satisfies the in place testing acceptance criteria and uses the test procedures of Regulatory Positions C.S.a C.5.c and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the train flow rate is 4000 cfm t 10L 2.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.
3.
Verifying a train flow rate of 4000 cfm + 10% during subsystem operation when tested in accordance with ANSI N510-1975.
After every 720** hours of charcoal adsorber operation by verifying c.
within 31 days af ter removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Positon C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.
d.
At least once per 18 months by:
1.
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 8 inches Water Gauge while operating the train at a flow rate of 4000 cfm 10L 2.
Verifying that on a simulated ammonia signal, the recirculating l
charcoal filter automatically switches to the recirculation mode of operation and the isolation dampers close within 6 seconds.
1
- This surveillance shall include the recirculating charcoal filter, " odor eater,"
in the normal control room supply filter train using ANSI N510-1975 as a guide to verify _ > 70% efficiency in removing freon test gas.
- Except that recirculating charcoal filter samples shall be removed and analyzed at least once per 18 months.
LA SALLE - UNIT 1 3/4 7-5 Amendment No. 38
([
'o UNITED STATES
~,t NUCLEAR REGULATORY COMMISSION s t WASHINGTON, D. C. 20555 s'o COMMONWEALTP EDISON COMPANY DOCKET NO. 50-374 LA SALLE COUNTY STATION, UNIT 2 AMENDMENT TO FACILITY ODERATING LICENSE Amendment No. 20 License No. NPF-18 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The apolication for amendment filed by the Commonwealth Edison Company (the licensee), dated February 7, 1986, as supplemented by letter dated March 5,1986, 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 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 forth in 10 CFR Chaoter I; 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 reculations and all applicable requirements have been satisfied.
2.
Accordinaly, the license is amended by changes to the Technical Specifica-tions 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:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 20, 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.
I 4
i 2
3.
This amendment is effective upon date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Director BWR Project Directorate No. 3 Division of BWR Licensing
Enclosure:
Changes to the Technical Specifications Date of Issuance: !.f L,-,gj i
f i
e 5
1
ENCLOSURE TO LICENSE AMENDMENT NO. 20 FACILITY OPERATING LICENSE NO. NPF-18 DOCKET NO. 50-374 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.
1 REMOVE INSERT V
V 3/4 3-74 3/4 3-74 B3/4 3-5 B3/4 3-5 3/4 7-5 3/4 7-5 3
t r
f i
o
.l i
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION....................
3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION..........................
3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION......
3/4 3-23 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS Recirculation Pump Trip System Instrumentation..........
3/4 3-35 End-of-Cycle Recirculation Pump Trip System Instrumentation............................................
3/4 3 '9 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION............................................
3/4 3-45 3/4.3.6 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION.................
3/4 3-50 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation.........................
3/4 3-57 Seismic Monitoring Instrumentation...........................
3/4 3-60 Meteorological Monitoring Instrumentation....................
3/4 3-63 Remote Shutdown Monitoring Instrumentation...................
3/4 3-66 Accident Monitoring Instrumentation..........................
3/4 3-69 Source Range Monitors........................................
3/4 3-72 Traversing In-core Probe System..............................
3/4 3-73 Ammonia Detection System.....................................
3/4 3-74 l
Fire Detection Instrumentation...............................
3/4 3-75 j
Radioactive Liquid Effluent Monitoring Instrumentation.......
3/4 3-81 Radioactive Gaseous Effluent Monitoring Instrumentation......
3/4 3-86 Loose-Part Detection System..................................
3/4 3-91 3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION.............................................
3/4 3-92 LA SALLE - UNIT 2 V
Amendment No. 20
INSTRUMENTATION AMMONIA DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.8 Two independent ammonia detection system subsystems shall be OPERABLE,*
each with two ammonia detectors, with their alarm / trip setpoints adjusted to actuate at an ammonia concentration of less than or equal to 25 ppm.
APPLICABILITY: All OPERATIONAL CONDITIONS.
ACTION:
a.
With one ammonia detector in either detection subsystem inoperable, l
restore the inoperable detector (s) to OPERABLE status within 7 days or, within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, initiate and maintain operation of at i
least one control room charcoal filter system train in the recircula-tion mode of operation.
b.
With both ammonia detection subsystems' inoperable, within I hour I
initiate and maintain operation of at least one control room charcoal filter system train in the recirculation mode of operation.
c.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.7.8 Each of the above required ammonia detection system subsystems shall l
shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.
- The normal or emergency power source may be inoperable in OPERATIONAL CONDITION 4 or 5.
LA SALLE - UNIT 2 3/4 3-74 Amendment No. 20
INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) l 3/4.3.7.5 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess important variables following an accident.
This capability is con-sistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0578, "TMI-2 Lessons i
Learned Task Force Status Report and Short-Term Recommendations".
l 3/4.3.7.6 SOURCE RANGE MONITORS i
The source range monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup and shutdown. At these power levels, reactivity additions should not be made without this flux level information available to the operator. When the inter-mediate range monitors are on scale adequate information is available without the SRMs and they can be retracted.
3/4.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM The OPERABILITY of the traversing in-core probe system with the specified minimum complement of equipraent ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribu-tion of the reactor core.
3/4.3.7.8 AMMONIA DETECTION SYSTEM The OPERABILITY of the ammonia detection system ensures that an accia ntal
~
ammonia release will be detected promptly and the necessary protective act ins will be automatically initiated to provide protection for~ control room per-sonnel.
Upon detection of a high concentration of ammonia, the control room
[
emergency ventilation system will automatically be placed in the recirculation mode of operation to provide the required protection.
The detection systems required by this specification are consistent with the recommendations of Regula-tory Guide 1.78, "Assumptiions for Evaluating the Habitability of a Nuclear Power d
Plant Control Room During a Postulated Hazardous Chemical Release."
3/4.3.7.9 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires.
This capability _is required in order to detect and locate fires in their early stages.
Prompt detection of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program.
LA SALLE - UNIT 2 8 3/4 3-5 Amendment No. 20 y,
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
At least once per 18 months ## or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone i
communicating with the train by:
i i
1.
Verifying that the train satisfies t in place testing acceptance criteria and uses the ter procedures of Regulatory Positions. C.S.a, C.5.c and C.S.d of degulatory Guide 1.52, Revision 2, March 1978, and the train flow rate is 4000 cfm i 10L 2.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory i
Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.
i 3.
Verifying a train flow rate of 4000 cfm + 10% during subsystem j
operation when tested in accordance with ANSI N510-1975.
j c.
After every 720** hours of charcoal adsorber operation by verifying i
within 31 days after removal that a laboratory analysis of a l
representative carbon sample obtained in accordance with Regulatory Positon C.6.b of Regulatory Guic'e 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2,-March 1978.
d.
At least once per 18 months by:
1.
Verifying that the pressure drop across the combined HEPA
]
filters and charcoal adsorber banks is less than 8 inches Water Gauge while operating the train at a flow rate of 4000 cfm i 10L 2.
Verifying that on a simulated ammonia detection signal, the re-l circulating charcoal filter automatically switches to the recircu-2 -
lation mode of operation and the isolation dampers close within 6 seconds.
1 i
I j
- This surveillance shall include the recirculating charcoal filter, " odor eater,"
in the normal control room supply filter train using ANSI N510-1975 as a guide 2
to verify _ > 70% efficiency in removing freon test gas, i
- Except that recirculating charcoal filter samples shall be removed and
!l analyzed at least once per 18 months.
4 LA SALLE - UNIT 2 3/4 7-5 Amendment No. 20 i
,. - -