ML20134C166
| ML20134C166 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 01/29/1997 |
| From: | Skay D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20134C169 | List: |
| References | |
| NUDOCS 9701310273 | |
| Download: ML20134C166 (19) | |
Text
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An nar ug p
i UNITED STATES g
j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 30e064001 f
COM)NWEALTH EDISON COMPANY DOCKET NO. 50-373 LASALLE COUNTY STATION. UNIT 1 MENDMENT TO FACILITY OPERATING LICENSE Amendment No. 117 License No. NPF-11 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment filed by the Comonwealth Edison Company (the licensee), dated October 31, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 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 ba conducted in compliance 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 i
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.
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:
9701310273 970129 PDR ADOCK 05000373 P
l-r.
t (2)
Technical Soecifications and Environmental Protection Plan l
The Technical Specifications contained in Appendix A, as revised through Amendment No. 117, and the Environmental Protection Plan l
contained in Appendix B, are hereby incorporated in the license.
l The licensee shall operate the facility in accordance with the l
Technical Specifications and the Environmental Protection Plan.
The license is also amended by adding paragraph 2.C.(36)* to read as l
follows:
(36) Relocated Technical Soecifications Commonwealth Edison Company shall relocate certain technical specification requirements to licensee-controlled documents as described below. The location of these requirements shall be retained by the licensee.
a.
This license condition approves the relocation of certain technical specification requirements to licensee-controlled documents (UFSAR), as described in the licensee's application dated October 31, 1996. The approval is documented in the staff's safety evaluation dated January 29, 1997. This license condition is effective as of its date of issuance by Amendment No.117 and shall be implemented within 90 days from the date of issuance.
Implementation shall include the relocation of technical specifications requirements to the appropriate licensee-controlled document as identified in the licensee's appilcation dated October 31, 1996.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 90 days.
FOR THE NUCLEAR REGULATORY COMMISSION 7,
/(Q.w 7M Donna M. Skay, Project anager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Attachments:
1.
License pages 16a, 16b and 17 2.
Changes to the Technical Specifications Date of Issuance:
January 29, 1997
- License pages 16a,16b and 17 are attached, for convenience, for the composite license to reflect this change.
O
- 16a -
2.C.(34) Deleted.
2.C.(35)
Surveillance Interval Extension The performance interval for those surveillance requirements identified in the licensee's request for surveillance interval extension dated April 11, 1995, shall be extended to April 5,1996, to coincide with the Unit I seventh refueling outage schedule. The extended interval shall not exceed a total of 25.1 months for 18 month surveillances.
2.C.(36) Relocated Technical Soecifications j
Commonwealth Edison Company shall relocate certain technical specification requirements to licensee-controlled documents as described below.
The location of these requirements shall be retained by the licensee.
a.
This license condition approves the relocation of certain technical specification requirements to licensee-controlled documents (UFSAR), as described in the licensee's application dated October 31, 1996.
The approval is documented in the staff's safety evaluation dated January 29, 1997.
This license condition is effective as of its date of issuance by Amendment No.117 and shall be implemented within 90 days from the date of issuance.
Implementation shall include the relocation of technical specifications requirements to the appropriate licensee-controlled document as identified in the licensee's application dated October 31, 1996.
D.
The facility requires exemptions from certain requirements of 10 CFR Part 50, 10 CFR Part 70, and 10 CFR Part 73.
These include:
(a)
Exemptions from certain requirements of Appendices G, H and J and 10 CFR Part 73 are described in the Safety Evaluation Report and Supplement No.1, No. 2 and No. 3 to the Safety Evaluation Report.
(b)
An exemption was requested until the completion of the first refueling from the requirements of 10 CFR 70.24.
(c)
An exemption from 10 CFR Part 50, Appendix E from performing a full scale exercise within one year before issuance of an operating license, both exemptions (b) and (c) are described in Supplement No. 2 of the Safety Evaluation Report.
Amendment No.195, JJE,117
- 16b -
(d)
An exemption was requested from the requirements of 10 CFR 50.44 until either the required 100 percent rated thermal power trip startup test has been completed or the reactor has operated for 120 effective full power days as specified by the Technical Specifications. Exemption (d) is described in the safety evaluation of License Amendment No. 12.
(e)
An exemption from the requirement of paragraph III.D of Appendix J to conduct the third Type A test of each ten-year service period when the plant is shutdown for the 10-year plant inservice inspections.
Exemptfon (e) is described in the safety evaluation accompanying Arwdment No.102 to this license.
(f)
An exemption was granted to remove the Main Steam Isolation Valves (MSIVs) from the acceptance criteria for the combined local leak rate test (Type B and C), as defined in the regulations of 10 CFR Part 50, Appendix J, Option B, Paragraph III.B.
Exemption (f) is described in the safety evaluation accompanying Amendment No. 112 to this License.
These exemptions are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest. Therefore, these exemptions are hereby granted.
The facility will operate, to the extent authorized herein, in conformity with the application, as amended, and the rules and regulations of the Commission (except as hereinafter exempted therefrom), and the provisions of the Act.
E.
This license is subject to the following additional condition for the protection of the environment:
Before engaging in additional construction or operational activities which may result in a significant adverse environmental impact that was not evaluated or that is significantly greater than that evaluated in the Final Environmental Statement and its Addendum, the licensee shall provide a written notification to the Director of the Office of Nuclear Reactor Regulation and receive written approval from that office before proceeding with such activities.
F.
Reporting to the Commission:
(a)
The licensee shall report any violations of the requirements contained in Section 2, Items C(1), C(3) through (33), and E of this license within twenty-four (24) hours by telephone l
l Amendment No. J, JE, JPE, JJE, 117
J -
1 and confirmed by telegram, mailgram, or facsimile 4
i transmission to the NRC Regional Administrator, Region III, or designee, not later than the first working day following i
the violation, with a written followup report within j
fourteen (14) working days.
1 (b)
The licensee shall notify the Commission, as soon as possible but not later than one hour, of any accident at this facility which could result in an unplanned release of quantities of fission products in excess of allowable limits for normal operation established by the Commission.
G.
The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
j l
H.
This license is effective as of the date of iss.v.nce and shall expire April 17, 2022.
FOR THE NUCLEAR REGULATORY COMMISSION 1
original signed by:
Harold R. Denton, Director Office of Nuclear Reactor Regulation
Attachment:
i
- 1.
2.
Appendix A - Technical Specifications (NUREG-0861) 3.
Appendix B - Environmental Protection Plan Date of Issuance: April 17, 1982 4
Amendment No. 117 j
. ~ _ _ -_- _.. _.. -
ATTACHMENT TO LICENSE AMENDMENT NO. 117 FACILITY OPERATING LICENSE NO. NPF-ll t
DOCKET NO. 50-373 l
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and l
contain a vertical line indicating the area of change.
l REMOVE INSERT v
v XII XII XXI XXI 3/4 3-60 3/4 3-60 3/4 3-61 3/4 3-62 B 3/4 3-4a B 3/4 3-4a l
l
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION Pf_qE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMEh.....'................
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 3-39 I
3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION........................................
3/4 3-45 3/4.3.6 CONTROL R0D WITHDRAWAL BLOCK INSTRUMENTATION.............
3/4 3-50 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation.....................
3/4 3-56 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 Deleted..................................................
3/4 3-73 Deleted.......................................,..........
3/4 3-74 Fire Detection Instrumentation...........................
3/4 3-75 Deleted..................................................
3/4 3-81 Explosive Gas Monitoring Instrumentation.................
3/4 3-82 Loose-Part Detection System..............................
3/4 3-85 3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION........................................
3/4 3-86 LA SALLE - UNIT 1 V
Amendment No. 117
INDEX BASES SECTION PAG 1 A
3/4.0 APPLICABILITY................................................
B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN...................................
B 3/4 1-1 3/4.1.2 REACTIVITY AN0MALIES..............................
B 3/4 1-1 3/4.1.3 CONTROL R0DS......................................
B 3/4 1-2 3/4.1.4 CONTROL R0D PROGRAM CONTR0LS......................
B 3/4 1-4 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM.....................
B 3/4 1-5 3/4.1.6 ECONOMIC GENERATION CONTROL SYSTEM................
B 3/4 1-6 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE........
B 3/4 2-1 3/4.2.2 DELETED...........................................
B 3/4 2-3 3/4.2.3 MINIMUM CRITICAL POWER RATI0......................
B 3/4 2-3 3/4.2.4 LINEAR HEAT GENERATION RATE.......................
B 3/4 2-5 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYUEM INSTRUMENTATION.........
B 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION...............
B 3/4 3-2 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION...................................
B 3/4 3-2a 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION.
B 3/4 3-3 i
3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION...................................
B 3/4 3-4 3/4.3.6 CONTROL R0D WITHDRAWAL BLOCK INSTRUMENTATION......
B 3/4 3-4 3/4.3.7 MONITORING INSTRUMENTATION i
Radiation Monitoring Instrumentation..............
B 3/4 3-4 i
LA SALLE - UNIT 1 XII Amendment No. 117 a
INDEX LIST OF TABLES (Continued)
TABLE PEE 3.3.4.1-2 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SETPOINTS............................
3/4 3-37 4.3.4.1-1 ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS............
3/4 3-38 3.3.4.2-1 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION......................................
3/4 3-41 3.3.4.2-2 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM SETPOINTS............................................
3/4 3-42 3.3.4.2-3 END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME........................................
3/4 3-43 4.3.4.2.I-1 END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM SURVEILLANCE REQUIREMENTS............................
3/4 3-44 3.3.5-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION......................................
3/4 3-46 i
3.3.5-2 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS............................
3/4 3-48 4.3.5.1-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS............
3/4 3-49 3.3.6-1 CONTROL R00 WITHDRAWAL BLOCK INSTRUMENTATION.........
3/4 3-51 3.3.6-2 CONTROL R0D WITHDRAWAL BLOCK INSTRUMENTATION SETPOINTS............................................
3/4 3-53 4.3.6-1 CONTROL R00 WITHDRAWAL BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................
3/4 3-54 3.3.7.1-1 RADIATION MONITORING INSTRUMENTATION.................
3/4 3-57 4.3.7.1-1 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................
3/4 3-59 I
3.3.7.3-1 METEOROLOGICAL MONITORING INSTRUMENTATION............
3/4 3-64 LA SALLE - UNIT I XXI Amendment No.117
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l INTENTIONALLY LEFT BLANK Pages 3/4 3-61 and 3/4 3-62 Deleted J
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LA SALLE - UNIT 1 3/4 3-60 Amendment No. 117 (next page is 3/4 3-63) t
mian nus 1
BASES i
3.4.3.7.2 DELETED 4
3/4.3.7.3 METEOROLOGICAL MONITORING INSTRUMENTATION i
The OPERABILITY of the meteorological monitoring instrumentation ensures i
that sufficient meteorological data is available for estimating potential i'
radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public. This instrumentation is consistent with the recommenda-i tions of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972.
i 3/4.3.7.4 REMOTE SHUTDOWN MONITORING INSTRUMENTATION The OPERABILITY of the remote shutdown monitoring instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the control room. This 4
capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
LA SALLE - UNIT 1 B 3/4 3-4a Amendment No.117
p enaro y
UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20006-0001
'+9.....,o COMONWEALTH EDISON COMPANY DOCKET NO. 50-374 LASALLE COUNTY STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. NPF-18 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated October 31, 1996, 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; 4
C.
There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health 1
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 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 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:
.~
),
4 (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised 1
through Amendment No.102, and the Environmental Protecticn Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the l
Technical Specifications and the Environmental Protection Plan.
The license is also amended by adding paragraph 2.C.(20)* to read as follows:
(20) Relocated Technical Snecifications 5
Commonwealth Edison Company shall relocate certain technical specification requirements to licensee-controlled documents as described below. The location of these requirements shall be retained by the licensee.
l a.
This license condition approves the relocation of certain technical specification requirements to licensee-controlled documents (UFSAR), as described in the licensee's application dated October 31, 1996.
The approval is i
documented in the staff's safety evaluction dated i.
January 29, 1997. This license condition is effective as of its date of issuance by Amendment No.102 and shall be
{
implemented within 90 days from the date of issuance.
Implementation shall include the relocation of technical specifications requirements to the appropriate licensee-controlled document as identified in the licensee's application dated October 31, 1996.
I 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 90 days.
FOR THE NUCLEAR REGULATORY COMMISSION
,.,- 3 l
Donna M. Skay, Proj Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Attachments:
1.
License page 9a i
2.
Changes to the Technical Specifications Date of Issuance:
January 29, 1997 l
- License page 9a is attached, for convenience, for the composite license to reflect this change.
1
- 9a -
2.C.(20)
Relocated Technical Specifications Commonwealth Edison Company shall relocate certain technical specification requirements to licensee-controlled documents as described below. The location of these requirements 1
shall be retained by the licensee.
]
a.
This license condition approves the relocation of certain technical specification requirements to licensee-controlled documents (UFSAR), as described in the licensee's application dated October 31, 1996.
The approval is documented in the staff's safety evaluation dated January 29, 1997.
This license condition is effective as of its date of issuance by Amendment No.102 and shall be implemented within 90 days from the date of issuance.
Implementation shall include the relocation of technical specifications requirements to the appropriate licensee-controlled document as identified in the licensee's application dated October 31, 1996.
Amendment No.102
=..-
]
ATTACHMENT TO LICENSE AMENDMENT NO.102 l
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.
I REMOVE INSERT V
V XII XII XXI XXI 3/4 3-60 3/4 3-60 3/4 3-61 3/4 3-62 B 3/4 3-4a B 3/4 3-4a i
INDEX LililllH(LLONQlIIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION E8E l
3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION.................
3/4 3-1 i
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 3-39 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION I N S T RUM E NT AT I ON........................................... 3 / 4 3 - 4 5 3/4.3.6 CONTROL R0D WITHDRAWAL BLOCK INSTRUMENTATION..............
3/4 3-50 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation......................
3/4 3-57 g
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 Deleted...................................................
3/4 3-73 Del e t ed................................................... 3 / 4 3 - 7 4 Fire Detection Instrumentation............................
3/4 3-75 De l e t ed................................................... 3 / 4 3 - 81 Explosive Gas Monitoring Instrumentation..................
3/4 3-82 Loose-Part Detection System...............................
3/4 3-85 3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION...........................................
3/4 3-86 i
LA SALLE - UNIT 2 V
Amendment No. 102
t INDEX BASES SECTION PAGE 3/4.0 APPLICABILITY................................................. B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN.................................... B 3/4 1-1 3/4.1.2 REACTIVITY AN0MALIES............................... B 3/4 1-1 3/4.1.3 CONTROL R0DS....................................... B 3/4 1-2 3/4.1.4 CONTROL R00 PROGRAM CONTR0LS.......................
B 3/4 1-4 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM...................... B 3/4 1-5 3/4.1.6 ECONOMIC GENERATION CONTROL SYSTEM................. B 3/4 1-6 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE............ B 3/4 2-1 3/4.2.2 DELETED............................................... B 3/4 2-2 3/4.2.3 MINIMUM CRITICAL POWER %4TIO.......................... B 3/4 2-2 3/4.2.4 LINEAR HEAT GENERATION RATE........................... B 3/4 2-4 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION.......... B 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION................ B 3/4 3-2 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION....................................
B 3/4 3-2a 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION.. B 3/4 3-3 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION....................................
B 3/4 3-4 3/4.3.6 CONTROL F.]D WITHDRAWAL BLOCK INSTRUMENTATION....... B 3/4 3-4 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation............... B 3/4 3-4 i
!.A SALLE - UNIT 2 XII Amendment No. 102 i
l
INDEX LIST OF TABLES (Continued) i
~
TABLE EASE 3.3.4.1-2 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SETPOINTS............................
3/4 3-37 4.3.4.1-1 ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS............
3/4 3-38 3.3.4.2-1 END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION......................................
3/4 3-41 3.3.4.2-2 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM SETPOINTS............................................
3/4 3-42 3.3.4.2-3 END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME........................................
3/4 3-43 4.3.4.2.1-1 END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM SURVEILLANCE REQUIREMENTS............................
3/4 3-44 3.3.5-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION 4
1 INSTRUMENTATION......................................
3/4 3-46 3.3.5-2 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS............................
3/4 3-48 4.3.5.1-1 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS............
3/4 3-49 3.3.6-1 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION.........
3/4 3-51 3.3.6-2 CONTROL R0D WITHDRAWAL BLOCK INSTRUMENTATION SETPOINTS............................................
3/4 3-53 4.3.6-1 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................
3/4 3-55 3.3.7.1-1 RADIATION MONITORING INSTRUMENTATION.................
3/4 3-58 4.3.7.1-1 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................
3/4 3-59 3.3.7.3-1 METEOROLOGICAL MONITORING INSTRUMENTATION............
3/4 3-64 4.3.7.3-1 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................
3/4 3-65 i
LA SALLE - UNIT 2 XXI Amendment No. 102
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INTENTIONALLY LEFT BLANK i
(Pages 3/4 3-61 and 3/4 3-62 Deleted) 4
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LASALLE - UNIT 2 3/4 3-60 Amendment No. 102 (next page is 3/4 3-63)
INSTRUMENTATION BASES 3.4.3.7.2 DELETED 3/4.3.7.3 METEOROLOGICAL MONITORING INSTRUMENTATION The OPERABILITY of the meteorological monitoring instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public. This instrumentation is consistent with the recommenda-tions of Regulatory Guide 1.23 "Onsite Meteorological Programs," February 1972.
3/4.3.7.4 REMOTE SHUTDOWN MONITORING INSTRUMENTATION The OPERABILITY of the remote shutdown monitoring instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
LA SALLE - UNIT 2 B 3/4 3-4a Amendment No.102