ML111330556

License Amendment No. for Various Administrative Technical Specifications Changes

ML111330556
Person / Time
Site:	Clinton
Issue date:	05/26/2011
From:	DiFrancesco N J Plant Licensing Branch III
To:	Pacilio M J Exelon Generation Co
DiFrancesco N, NRR/DORL/LPL3-2, 415-1115
References
TAC ME4030
Download: ML111330556 (14)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 CLINTON POWER STATION, UNIT NO.1 -LICENSE AMENDMENT NO. 193 FOR VARIOUS ADMINISTRATIVE TECHNICAL SPECIFICATIONS CHANGES (TAC NO. ME 4030)

Dear Mr. Pacilio:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 193 to Facility Operating License No. NPF-62 for the Clinton Power Station (CPS) Unit No.1. The amendment is in response to your application dated June 4, 2010. The amendment removes an expired time-related item and several typographical errors from the CPS Technical Specifications.

A copy of the Safety Evaluation is also enclosed.

The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Nicholas J. DiFrancesco, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-461

Enclosures:

1. Amendment No. 193 to NPF-62 2. Safety Evaluation cc w/encls: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, O.C. 20555*0001 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-461 CLINTON POWER STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 193 License No. NPF-62 The U.S. Nuclear Regulatory Commission (the Commission) has found that: The application for amendment by Exelon Generation Company, LLC (the licensee), dated June 4,2010 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 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. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-62 is hereby amended to read as follows:

-Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No193 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jac I. Zimm man, Chief Plan Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Facility Operating License Date of Issuance:

May 26, 2011 ATTACHMENT TO LICENSE AMENDMENT NO. FACILITY OPERATING LICENSE NO. DOCKET NO. Replace the following pages of the Facility Operating License and Appendix "A" Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Remove License NPF-62 License NPF-62 Page 3 Page 3 TSs TSs 3.0-5 3.0-5 3.3-34 3.3-34 3.6-54b 3.6-54b 3.6-69 3.6-69 3.8-24b 3.8-24b Exelon Generation Company, pursuant to the Act and to 10 CFR Parts 30, 40, and 70, to receive. pO$HSS. and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup. sealed sources for reactor instrumentation and radiation monitoring equipment cal"ratlon, and as fission detectors In amounts as required: exelon Generation Company, purauant to the Act and 10 CFR Parts 301 40, and 70. to receive, possess, and use;, amounts as required any byproduct.

source or special nucl_ material without restriction to chemical or physical form. tor sam pte analysis or instrument calibration or associated with radioactive apparatus or components: Exelon GeneratIon Company. pursuant to the Act and 10 CFR Parts 30. 40. and 70. to possess, but not such byproduct and special nuclear materials as may be produced by the operation of the facility.

Mechanical disassembly of the GE'411s0tope test assembHes containing Cobalt-60 Is not considered separatlon; and Exelon Generauon Company, pursuant to the Act and 10 CFR Part 30, to intentionaBy produce. possess, receive, transfer, and use Cobalt-60. Ttis license shalt be deemed to contain a"ld is subjeel to the conditions specified In the Commission's regulations set for1h in 10 CFR Chapter' and Is subject to all appltcable provisions of the Act and to the rules. regulations and orders of the CommissIOn now or hereafter In effect; and is subject to the additional conditions specified or Incorporated below: Maxtmym P9w@r Live! Exelon Generation Company is authorfzed to operate the facility at reactor core power levels not in excess of 3473 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein. Technical SpecificationS IDd enVironmental Prptectlon PIItl The Technical SpectflcallonS contained In AppendiX A and the Environmental Protectlor1 D ..... contained In Appendix 8, as f9Ylsed through Amendment No. 193.are hereby incorporated into this license. Exelon Generation ComP.;8l1y shall operate the facility In accordance with the Technical SpecificatiOns and the Environmental Protection Plan. Amendment No..-193 SR Applicability 3.0 3.0 SR APPLICABILITY (continued)

SR 3.0.3 When the Surveillance is performed within the delay period (continued) and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered. SR Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4. This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit. 3.0-5 Amendment No. 193 ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

D.1 Only applicable if HPCS pump suction is not aligned to the suppression pool. AND Declare HPCS System inoperable.

D.2.1 Place channel in trip. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of HPCS initiation capability 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> D.2.2 Align the HPCS pump suction to the suppression pool. 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> (continued)

CLINTON 3.3-34 Amendment No. 193 Drywell 3.6.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR Verify bypass leakage is less than or equal to the bypass leakage limit. However, during the first unit startup following bypass leakage testing performed in accordance with this SR, the acceptance criterion is 10% of the drywell bypass leakage limit. FREQUENCY 24 months following 2 consecutive tests with bypass leakage greater than the bypass leakage limit until 2 consecutive tests are less than or equal to the bypass leakage limit AND 48 months following a test with bypass leakage greater than the bypass leakage limit AND SR 3.0.2 is not applicable for extensions

> 12 months. In accordance with the Surveillance Frequency Control Program (continued) 3.6-54b Amendment N0.193 Drywell Post-LOCA Vacuum Relief System 3.6.5.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Two or more drywell post-LOCA vacuum relief subsystems inoperable for reasons other than Condition A. C.1 Restore drywell post LOCA vacuum relief subsystems to OPERABLE status. 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> D. Required Action and associated Completion Time of Condition A not met. D.1 Be in MODE 3. AND D.2 Be in MODE 4. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> E. Action and associated Completion Time of Condition B or C not met. -LCO 3.0.4.a is not applicable when entering MODE 3. E.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> CLINTON 3.6 69 Amendment No.193 3.8.4 DC Sources-Operating This page intentionally left blank. CLINTON 3.8 24b Amendment No.

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 193 TO FACILITY OPERATING LICENSE NO. NPF-62 EXELON GENERATION COMPANY. LLC CLINTON POWER STATION, UNIT NO.1 DOCKET NO. 50-461

1.0 INTRODUCTION

By letter to the U.S. Nuclear Regulatory Commission (NRC, the Commission) dated June 4, 2010, (Agencywide Document Access and Management System Accession (ADAMS) No. ML 101550500)

Exelon Generation Company, LLC (EGC, the licensee) requested an amendment to Technical Specifications (TSs) for the Clinton Power Station (CPS), Unit No.1. The proposed amendment would remove an expired time-related item and several typographical errors from the TSs.

2.0 REGULATORY EVALUATION

Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The NRC regulatory requirements related to the content of the TSs are contained in Title 10, Code of Federal Regulations (10 CFR), Part 50, Section 50.36, 'Technical Specifications." The TS requirements in 10 CFR 50.36 include the following categories:

(1) safety limits, limiting safety systems settings and control settings, (2) limiting conditions for operation, (3) surveillance requirements (SRs), (4) design features, (5) administrative controls, (6) decommissioning, (7) initial notification, and (8) written reports. 3.0 TECHNICAL EVALUATION 3.1 Proposed change to TS 3.0, "SR Applicability" The licensee is proposing to remove the single line and parenthetical

"(continued)" at the bottom of TS page 3.0-5, and insert a double line to indicate the end of the section. This error was introduced into the TS during the implementation of Amendment 163 (Reference 1). The NRC staff has determined that the proposed change corrects an editorial issue related to the format of TS page 3.0-5 and is administrative.

3.2 Proposed change to TS 3.3.5.1, "ECCS Instrumentation" The licensee is proposing to correct an administrative issue in TS 3.3.5.1, "ECCS Instrumentation" by changing the position of the Logical Connector "OR" between TS 3.3.5.1, Required Actions 0.2.1 and 0.2.2. The logical "OR" connector will be placed in alignment with the Required Action wording. The NRC staff has concluded that this change will provide clarity, will not change the current TS requirement, and is consistent with NUREG 1434, "Standard Technical Specifications General Electric Plants, BWR [Boiling Water Reactor]/6" (Reference 2). This error was introduced into the CPS TS in Amendment 95 (Reference 3), which converted the CPS TS to the Improved Technical Specifications format. 3.3 Proposed Change to TS 3.6.5.1! "Drywell" The licensee is proposing to delete Note 1 in Surveillance Requirement (SR) 3.6.5.1.3.

SR 3.6.5.1.3 Note 1 states, "The next required performance of this SR may be delayed to November 23, 2008." EGC is requesting deletion of Note 1 from SR 3.6.5.1.3, as the allowance provided by this Note which was added in TS Amendment 160 (Reference

4) has expired. The NRC staff has concluded that this SR is being met and no longer needs to be modified by this Note. 3.4 Proposed change to TS 3.6.5.6, "Drywell Post-LOCA Vacuum Relief System" The licensee is requesting the addition of the words "not met" at the end of Condition D. These words were erroneously omitted from the markups of the TS pages that were submitted in the request that led to Amendment 187 (Reference 5). The NRC staff has concluded that this change corrects an editorial error and is administrative.

3.5 Proposed change to TS 3.8.4, "DC Sources-Operating" The licensee is requesting the insertion of a new TS Page 3.8.24b. The new TS page 3.8.24b is intentionally left blank. Since the CPS TS are double-sided, an additional blank page should have accompanied Page 3.8-24a during the implementation of Amendment 187. The NRC staff has determined that the purpose of the blank page is to maintain the pagination on the pages subsequent to the newly inserted TS page. 3.6 Summary of Changes The proposed changes in 3.1 through 3.5 are nontechnical, administrative changes that are editorial in nature or involve the reorganization or reformatting of requirements without affecting technical content or operational requirements.

The NRC staff finds that the proposed changes are acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Illinois State official was notified of the proposed issuance of the amendment.

The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION 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

-3 involve no significant hazards consideration, and there has been no public comment on such finding (September 7, 2010, 75 FR 54395;). 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 Commission's 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.

5.0 REFERENCES

License Amendment 163, "Clinton Power Station, Unit 1 -Issuance of Amendment Re: Increased Flexibility in Mode Restraints (TAC NOS. MC3024)," ADAMS Accession No. ML05061 0297 NUREG-1434, Revision 3.0, "Standard Technical Specifications General Electric Plants, BWRl6," ADAMS Accession No. ML041910204 License Amendment 95, "Notice of issuance of Amend 95 to License NPF-62 re changes made to TS to replace existing TS wrrs based on NUREG-1434, "Improved BWR-6 TS" dated Sept 1992," ADAMS Legacy Accession No. 9412150114 License Amendment 160, "Clinton Power Station, Unit 1 -Issuance of Amendment (TAC NO. MB 7675)," ADAMS Accession No. ML033360470 License Amendment 187, "Clinton Power Station, Unit 1 -Issuance of Amendment Re: Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidate Line Item Improvement Process (TAC NO. MD5859)," ADAMS Accession No. ML090710332 Principal Contributor:

Kristi Bucholtz Date of issuance:

May 26,2011 May 26,2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 CLINTON POWER STATION, UNIT NO.1 -LICENSE AMENDMENT NO. 193 FOR VARIOUS ADMINISTRATIVE TECHNICAL SPECIFICATIONS CHANGES (TAC NO. ME 4030)

Dear Mr. Pacilio:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 193 to Facility Operating License No. NPF-62 for the Clinton Power Station (CPS) Unit No.1. The amendment is in response to your application dated June 4, 2010. The amendment removes an expired time-related item and several typographical errors from the CPS Technical Specifications.

A copy of the Safety Evaluation is also enclosed.

The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice. Sincerely.

IRA! Nicholas J. DiFrancesco.

Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-461

Enclosures:

1. Amendment No. 193 to NPF-62 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:

PUBLIC LPL3-2 RIF RidsOgcRp Resource RidsNrrLASRohrer Resource RidsNrrDirsltsb Resource RidsNrrPMClinton Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl3-2 Resource RidsNrrDorlDpr Resource RidsNrrRgn3MailCenter Resource Amendment:

ML 111330556

• SE Memo Date NRR-058 OFFICE LPL3-2/PM ATBC LPL3-2/PM LPL3-2/LA DIRSIITSB*

OGC NLO LPL3-2/BC NAME CNorton ABiliochcolon NDiFrancesco SRohrer RElliot RH JZimmerman DATE 5/16/11 5/26/11 1 11/18/10 5125111 5/26/11 OFFICIAL RECORD