ML022950065

License Amendment, Adding Two Footnotes to TSs Table 3.3.8.1-1, Functions 1.e & 2.e, & Makes Editorial Change to Heading of TS Table 3.3.8.1-1

ML022950065
Person / Time
Site:	LaSalle
Issue date:	11/12/2002
From:	Macon W NRC/NRR/DLPM/LPD3
To:	Skolds J Exelon Generation Co, Exelon Nuclear
Macon W, NRR/DLPM/LPDIII-02, 415-3965
References
TAC MB5556, TAC MB5557
Download: ML022950065 (14)

Text

November 12, 2002 Mr. John L. Skolds, President Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

LASALLE COUNTY STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS (TAC NOS. MB5556 AND MB5557)

Dear Mr. Skolds:

The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 155 to Facility Operating License No. NPF-11 and Amendment No. 141 to Facility Operating License No. NPF-18 for the LaSalle County Station, Units 1 and 2, respectively. The amendments are in response to your application dated July 8, 2002.

The amendments add two footnotes to Technical Specifications (TS) Table 3.3.8.1-1, "Loss of Power Instrumentation," Functions 1.e and 2.e, "Degraded Voltage - Time Delay, LOCA," and makes an editorial change to the heading of TS Table 3.3.8.1-1.

A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions biweekly Federal Register notice.

Sincerely,

/RA/

William A. Macon, Jr., Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-373, 50-374

Enclosures:

1. Amendment No. 155 to NPF-11

2. Amendment No. 141 to NPF-18

3. Safety Evaluation cc w/encls: See next page

LaSalle County Station Units 1 and 2 cc:

Site Vice President - LaSalle Regional Administrator Exelon Generation Company, LLC U.S. NRC, Region III 2601 North 21st Road 801 Warrenville Road Marseilles, IL 61341-9757 Lisle, IL 60532-4351 LaSalle County Station Plant Manager Illinois Department of Nuclear Safety Exelon Generation Company, LLC Office of Nuclear Facility Safety 2601 North 21st Road 1035 Outer Park Drive Marseilles, IL 61341-9757 Springfield, IL 62704 Regulatory Assurance Manager - LaSalle Document Control Desk-Licensing Exelon Generation Company, LLC Exelon Generation Company, LLC 2601 North 21st Road 4300 Winfield Road Marseilles, IL 61341-9757 Warrenville, IL 60555 U.S. Nuclear Regulatory Commission Senior Vice President - Nuclear Services LaSalle Resident Inspectors Office Exelon Generation Company, LLC 2605 North 21st Road 4300 Winfield Road Marseilles, IL 61341-9756 Warrenville, IL 60555 Phillip P. Steptoe, Esquire Vice President Sidley and Austin Mid-West Operations Support One First National Plaza Exelon Generation Company, LLC Chicago, IL 60603 4300 Winfield Road Warrenville, IL 60555 Assistant Attorney General 100 W. Randolph St. Suite 12 Senior Vice President Chicago, IL 60601 Mid-West Regional Operating Group Exelon Generation Company, LLC Chairman 4300 Winfield Road LaSalle County Board Warrenville, IL 60555 707 Etna Road Ottawa, IL 61350 Vice President - Licensing and Regulatory Affairs Attorney General Exelon Generation Company, LLC 500 S. Second Street 4300 Winfield Road Springfield, IL 62701 Warrenville, IL 60555 Chairman Illinois Commerce Commission 527 E. Capitol Avenue, Leland Building Springfield, IL 62706 Robert Cushing, Chief, Public Utilities Division Illinois Attorney Generals Office 100 W. Randolph Street Chicago, IL 60601

LaSalle County Station Units 1 and 2 Director - Licensing Mid-West Regional Operating Group Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Senior Counsel, Nuclear Mid-West Regional Operating Group Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Manager - Licensing -Clinton and LaSalle Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

November 12, 2002 Mr. John L. Skolds, President Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

LASALLE COUNTY STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS (TAC NOS. MB5556 AND MB5557)

Dear Mr. Skolds:

The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 155 to Facility Operating License No. NPF-11 and Amendment No. 141 to Facility Operating License No. NPF-18 for the LaSalle County Station, Units 1 and 2, respectively. The amendments are in response to your application dated July 8, 2002.

The amendments add two footnotes to Technical Specifications (TS) Table 3.3.8.1-1, "Loss of Power Instrumentation," Functions 1.e and 2.e, "Degraded Voltage - Time Delay, LOCA," and makes an editorial change to the heading of TS Table 3.3.8.1-1.

A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions biweekly Federal Register notice.

Sincerely,

/RA/

William A. Macon, Jr., Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-373, 50-374

Enclosures:

1. Amendment No. 155 to NPF-11

2. Amendment No. 141 to NPF-18

3. Safety Evaluation cc w/encls: See next page DISTRIBUTION:

Public AMendiola WMacon, Jr.

PD3-2 r/f OGC, O15B18 JKnox GHill (4), T5C3 RDennig (DRIP/RORP) CRosenberg ACRS, T2E26 BBurgess, RIII ADAMS Accession Number: ML022950065 OFFICE PM:LPD3-2 LA:LPD3-2 OGC SC:LPD3-2 NAME WMacon, Jr. CRosenberg RWeisman LRaghavan for AMendiola DATE 10/23/02 10/22/02 11/01/02 11/05/02 OFFICIAL RECORD COPY

EXELON GENERATION COMPANY, LLC DOCKET NO. 50-373 LASALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.155 License No. NPF-11

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment filed by the Exelon Generation Company, LLC (the licensee), dated July 8, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 Commissions 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 Commissions 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:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 155, 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 within 30 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA by L. Raghavan for/

Anthony J. Mendiola, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: November 12, 2002

EXELON GENERATION COMPANY, LLC DOCKET NO. 50-374 LASALLE COUNTY STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 141 License No. NPF-18

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment filed by the Exelon Generation Company, LLC (the licensee), dated July 8, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 Commissions 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 Commissions 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:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 141, 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 within 30 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA by L. Raghavan for/

Anthony J. Mendiola, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: November 12, 2002

ATTACHMENT TO LICENSE AMENDMENT NO. 155 AND 141 FACILITY OPERATING LICENSE NO. NPF-11 AND NPF-18 DOCKET NOS. 50-373 AND 50-374 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by amendment number and contains marginal lines indicating the area of change.

Remove Page Insert Page 3.3.8.1-3 3.3.8.1-3

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 155 TO FACILITY OPERATING LICENSE NO. NPF-11 AND AMENDMENT NO. 141 TO FACILITY OPERATING LICENSE NO. NPF-18 EXELON GENERATION COMPANY, LLC LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374

1.0 INTRODUCTION

By application dated July 8, 2002, Exelon Generation Company, LLC (the licensee), requested changes to the Technical Specifications for the LaSalle County Station, Units 1 and 2. The proposed amendments would change Appendix A, Technical Specifications (TS), of Facility Operating License Nos. NPF-11 and NPF-18. Specifically, the proposed change would add two footnotes to TS Table 3.3.8.1-1, "Loss of Power Instrumentation," Functions 1.e and 2.e, "Degraded Voltage - Time Delay, LOCA," and would make an editorial change to the heading of TS Table 3.3.8.1-1. The Degraded Voltage - Time Delay, LOCA, function is currently required to be OPERABLE during plant configurations when the emergency core cooling system (ECCS) instrumentation that generates the loss-of-coolant accident (LOCA) signal is not required to be OPERABLE. The proposed changes correct this inconsistency by adding two new footnotes to TS Table 3.3.8.1-i that modify the required OPERABILITY of the Degraded Voltage - Time Delay, LOCA, function.

1.1 Background Successful operation of the required safety functions of the ECCS is dependent upon the availability of adequate power sources for energizing the various components such as pump motors, motor operated valves, and the associated control components. The loss of power (LOP) instrumentation monitors the 4.16 kilovolt (kV) emergency buses. If the instrumentation determines that insufficient voltage is available, the buses are automatically disconnected from the offsite power sources and connected to the onsite diesel generator (DG) power sources.

Each 4.16 kV emergency bus has its own independent LOP instrumentation and associated trip logic. The voltage for the Division 1, 2, and 3 buses is monitored at two levels, which can be considered as two different undervoltage functions: loss of voltage and degraded voltage.

For Division 1, 2 and 3, each degraded voltage function is monitored by two instruments per bus whose output trip contacts are arranged in a two-out-of-two logic configuration per bus.

The degraded voltage signal is generated when a degraded voltage occurs for a specified time interval; the time interval is dependent upon whether a LOCA signal is present. A degraded voltage signal results in the start of the associated DG, the trip of the normal and alternate

offsite power supply breakers to the associated 4.16 kV emergency bus, and, for Divisions 1 and 2 only, the shedding of the appropriate 4.16 kV bus loads.

The Degraded Voltage Time Delay circuitry is composed of two time delay components. Upon detection of a degraded voltage condition, the Degraded Voltage - Time Delay, LOCA, function timer is initiated with a TS Allowable Value of $ 9.4 seconds and # 10.9 seconds. If a coincident LOCA signal is present after the time delay setting of the Degraded Voltage - Time Delay LOCA, the Loss of Power trip logic is initiated. If no LOCA signal is present, the Degraded Voltage - Time Delay LOCA function is bypassed while the Degraded Voltage time Delay, NO LOCA timer is initiated with a TS Allowable Value of $ 270.1 seconds and # 329.9 seconds. The Time Delay Allowable Values are long enough to provide time for the offsite power supply to recover to normal voltages, but short enough to ensure that sufficient power is available to the required equipment. The shorter time delay associated with a coincident LOCA signal is required to ensure that the ECCS injection assumptions of the LOCA analyses are met.

Currently, the Degraded Voltage - Time Delay, LOCA, function is required to be OPERABLE in MODES 1, 2, 3, 4, and 5, and during movement of irradiated fuel assemblies in the secondary containment in accordance with the APPLICABILITY of TS 3.3.8.1.

TS 3.3.8.1, Loss of Power (LOP) Instrumentation, requires the LOP instrumentation for each function in Table 3.3.8.1-1 to be OPERABLE in MODES 1, 2, and 3, and when the associated DG is required to be OPERABLE by LCO 3.8.2, AC Sources - Shutdown.

TS 3.8.2 is applicable in MODES 4 and 5, and during movement of irradiated fuel assemblies in the secondary containment. TS 3.8.2 requires one DG to be OPERABLE which is capable of supplying one division of the Division 1 or 2 onsite Class 1E alternating current (AC) electrical power distribution subsystem(s) required by the limiting condition for operation (LCO) of TS 3.8.8, Distribution System - Shutdown. Additionally, TS 3.8.2 requires the Division 3 DG to be OPERABLE when the Division 3 onsite Class 1E AC electrical power distribution subsystem is required by the LCO of TS 3.8.8.

TS 3.8.8 is applicable in MODES 4 and 5, and during movement of irradiated fuel assemblies in the secondary containment. TS 3.8.8 requires the necessary portions of the Division 1, Division 2, opposite unit Division 2 and Division 3 AC, and direct current (DC) electrical power distribution subsystems to be OPERABLE to support equipment required to be OPERABLE.

Thus, the Degraded Voltage - Time Delay, LOCA, function is currently required to be OPERABLE in MODES 1, 2, 3, 4, and 5, and during movement of irradiated fuel assemblies in the secondary containment.

The Degraded Voltage - Time Delay, LOCA, function relies on ECCS instrumentation that is required to be OPERABLE in accordance with TS 3.3.5.1, Emergency Core Cooling System (ECCS) Instrumentation. The LOCA signal for the Division 1 and 2 buses is generated by either the Reactor Vessel Water Level - Low Low Low, Level 1, or Drywell Pressure - High, ECCS instrumentation. The LOCA signal for the Division 3 buses is generated by either Reactor Vessel Water Level - Low Low, Level 2, or Drywell Pressure - High, ECCS instrumentation. TS 3.3.5.1, Emergency Core Cooling System (ECCS) Instrumentation,

requires the ECCS instrumentation for each function listed in TS Table 3.3.5.1-1 to be OPERABLE in the MODE(s) specified in TS Table 3.3.5.1-1.

TS Table 3.3.5.1-1 requires the Drywell Pressure - High instrumentation to be OPERABLE in MODES 1, 2 and 3. The Reactor Vessel Water Level - Low Low Low, Level 1 and the Reactor Vessel Water Level - Low Low, Level 2 ECCS instrumentation is required to be OPERABLE in MODES 1, 2, and 3, and in MODES 4 and 5 when associated ECCS subsystems are required to be OPERABLE per LCO 3.5.2, ECCS - Shutdown.

TS 3.5.2 requires the ECCS subsystems to be OPERABLE in MODE 4, and MODE 5 except with the spent fuel storage pool gates removed and the water level > 22 feet over the top of the reactor pressure vessel flange.

As such, the ECCS instrumentation that is required to be OPERABLE to support the Degraded Voltage - Time Delay, LOCA, function is required to be OPERABLE in MODES 1, 2 and 3, and in MODES 4 and 5, when associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2. The ECCS instrumentation is not required to be OPERABLE when the plant is in a configuration that is not a defined MODE (i.e., no fuel in the vessel).

Therefore, the Degraded Voltage - Time Delay, LOCA, function is currently required to be OPERABLE during plant configurations when the ECCS instrumentation that generates the LOCA signal is not required to be OPERABLE. The proposed changes correct this inconsistency by adding two new footnotes to TS Table 3.3.8.1-1 that modify the required OPERABILITY of the Degraded Voltage - Time Delay, LOCA, Function.

2.0 REGULATORY EVALUATION

The staff has reviewed the licensees regulatory requirements analysis in support of its proposed license amendment which is described in Section 4 of Attachment 2 to the licensees submittal. The regulatory requirements on which the staff based its review are set forth in 10 CFR 50.36, "Technical Specifications," which provides the regulatory requirements for the content required in a licensee's TS.

3.0 TECHNICAL EVALUATION

The staff has reviewed the licensees regulatory and technical analyses in support of its proposed license amendment which are described in Sections 5 and 6 of Attachment 2 to the licensees submittal. The detailed evaluation below will support the conclusion that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

3.1 Proposed change to TS Table 3.3.8.1-1 The proposed change adds two new footnotes to TS Table 3.3.8.1-1 that modify the required OPERABILITY of the Degraded Voltage -- Time Delay, LOCA, Functions 1.e and 2.e. The proposed footnotes are as follows:

(a) In MODES 4 and 5, when associated ECCS subsystems(s) are required to be OPERABLE per LCO 3.5.2, ECCS -- Shutdown.

(b) With no fuel in the vessel, not required to be OPERABLE.

The proposed change modifies the loss of power instrumentation TS (i.e., TS Table 3.3.8.1-1) so that the OPERABILITY of the Degraded Voltage - Time Delay, LOCA, function is consistent with the OPERABILITY of the ECCS instrumentation that generates the LOCA signal.

Proposed footnote (a) is consistent with OPERABILITY requirements for ECCS instrumentation.

Proposed footnote (b) removes the OPERABILITY requirement of the Degraded Voltage - Time Delay, LOCA, function when the ECCS instrumentation that generates the LOCA signal is not required to be operable.

The proposed change corrects an identified inconsistency between loss of power and ECCS instrumentation TS OPERABILITY requirements. The proposed changes modify the OPERABILITY requirement of the Degraded Voltage - Time Delay, LOCA, function so that it is consistent with the OPERABILITY requirement of the ECCS instrumentation that generates the LOCA signal. Thus, the proposed changes are consistent with the ECCS injection assumptions of the LOCA analyses and are considered acceptable.

3.2 Proposed change to TS Table 3.3.8.1-1 Function column heading The TS Table 3.3.8.1-1 Function column heading is editorially changed to add the reference to the Opposite Unit Division 2. It was always the intent and practice of LaSalle County Station to apply TS requirements from this column to the opposite unit Division 2 4.16 kV emergency bus.

The proposed change is editorial and is therefore considered acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Illinois State official was notified of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (67 FR 53986). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: J. Knox Date: November 5, 2002