ML071100237

Oyster Creek Nuclear Generating Station, License Amendment, Issuance of Amendment Request to Change Technical Specification Definition of Channel Calibration, Channel Check, and Channel Test

ML071100237
Person / Time
Site:	Oyster Creek
Issue date:	07/27/2007
From:	Miller G E NRC/NRR/ADRO/DORL/LPLI-2
To:	Crane C M AmerGen Energy Co
Miller G, NRR/DORL, 415-2481
Shared Package
ML071100242	List: ML071100237
References
TAC MD3133
Download: ML071100237 (11)

Text

July 27, 2007Mr. Christopher M. CranePresident and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

OYSTER CREEK NUCLEAR GENERATING STATION - ISSUANCE OF AMENDMENT RE: REQUEST TO CHANGE TECHNICAL SPECIFICATION DEFINITION OF CHANNEL CALIBRATION, CHANNEL CHECK, AND CHANNEL TEST (TAC NO. MD3133)

Dear Mr. Crane:

The Commission has issued the enclosed Amendment No. 263 to Facility Operating LicenseNo. DPR-16 for the Oyster Creek Nuclear Generating Station (Oyster Creek), in response to your application dated September 28, 2006. The amendment revises the Oyster Creek Technical Specification definition of ChannelCalibration, Channel Check, and Channel Test consistent with NUREG-1433, Revision 3.0, "Standard Technical Specifications General Electric Plants, BWR/4 Specifications," dated June2004. A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included inthe Commission's biweekly Federal Register notice. Sincerely,/ra/G. Edward Miller, Project ManagerPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-219

Enclosure:

1. Amendment No. 263 to DPR-16

2. Safety Evaluationcc w/encls: See next page July 27, 2007Mr. Christopher M. Crane President and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

OYSTER CREEK NUCLEAR GENERATING STATION - ISSUANCE OF AMENDMENT RE: REQUEST TO CHANGE TECHNICAL SPECIFICATION DEFINITION OF CHANNEL CALIBRATION, CHANNEL CHECK, AND CHANNEL TEST (TAC NO. MD3133)

Dear Mr. Crane:

The Commission has issued the enclosed Amendment No. 263 to Facility Operating LicenseNo. DPR-16 for the Oyster Creek Nuclear Generating Station (Oyster Creek), in response to your application dated September 28, 2006. The amendment revises the Oyster Creek Technical Specification definition of ChannelCalibration, Channel Check, and Channel Test consistent with NUREG-1433, Revision 3.0, "Standard Technical Specifications General Electric Plants, BWR/4 Specifications," dated June2004. A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included inthe Commission's biweekly Federal Register notice. Sincerely,/ra/G. Edward Miller, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-219

Enclosure:

1. Amendment No. 263 to DPR-16

2. Safety Evaluationcc w/encls: See next page DISTRIBUTION

PUBLICRidsOgcRpRidsNrrDorlDpr LPLI-2 R/FRidsNrrDorlLpl1-2(HChernoff)GHill (2)

TKobetzRidsNrrPMGMillerRidsNrrLAMOBrien RidsAcrsAcnwMailCenterMHamm, NRR CSchulten, NRRRidsRgn1MailCenter(GMatakas)Package Accession Number: ML0711002472Amendment Accession Number: ML0711002397TS(s) Accession Number: ML072130293OFFICELPLI-2/PMLPLI-2/LADIRS/ITSB/BCOGCLPLI-2/BCNAMEGEMillerMO'BrienTKobetzMYoungHChernoff(w/comments)DATE5/10/075/3/076/5/077/16/077/27/07OFFICIAL RECORD COPY

AMERGEN ENERGY COMPANY, LLC DOCKET NO. 50-219OYSTER CREEK NUCLEAR GENERATING STATIONAMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 263License No. DPR-161.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by AmerGen Energy Company, LLC, (thelicensee), dated September 28, 2006, 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;B.The facility will operate in conformity with the application, the provisions of theAct, and the rules and regulations of the Commission;C.There is reasonable assurance: (i) that the activities authorized by thisamendment 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;D.The issuance of this amendment will not be inimical to the common defense andsecurity 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 theCommission's regulations and all applicable requirements have been satisfied. 2.Accordingly, the Facility Operating License is amended by changes to the TechnicalSpecifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-16 is hereby amended to read as follows.(2)Technical SpecificationsThe Technical Specifications contained in Appendices A and B, as revisedthrough Amendment No. 263, are hereby incorporated in the license. AmerGen Energy Company, LLC, shall operate the facility in accordance with the Technical Specifications. 3.This license amendment is effective as of the date of its issuance and shall beimplemented within 60 days of the date of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/ra/Harold K. Chernoff, ChiefPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License and Technical SpecificationsDate of Issuance: July 27, 2007 ATTACHMENT TO LICENSE AMENDMENT NO. 263 FACILITY OPERATING LICENSE NO. DPR-16DOCKET NO. 50-219Replace page 3 of Facility Operating License No. DPR-16 with the attached revised page 3. The revised page is identified by amendment number and contains a marginal line indicatingthe area of change.Replace the following pages of the Technical Specifications with the attached pages. Therevised pages are identified by amendment number and contain marginal lines indicating theareas of change. RemoveInsert1.0-41.0-43.1-193.1-19 4.1-94.1-9 4.3-24.3-2 4.4-14.4-1 4.12-14.12-1 4.12-24.12-2 4.13-14.13-1 4.13-24.13-2 4.15-24.15-2 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 263TO FACILITY OPERATING LICENSE NO. DPR-16AMERGEN ENERGY COMPANY, LCCOYSTER CREEK NUCLEAR GENERATING STATIONDOCKET NO. 50-21

91.0INTRODUCTION

By application dated September 28, 2006, AmerGen Energy Company, LLC (AmerGen or thelicensee) requested changes to the Facility Operating License for the Oyster Creek Nuclear Generating Station (Oyster Creek). The proposed amendment would revise the Oyster Creek Technical Specification (TS) definition for Channel Calibration, Channel Check, and ChannelTest consistent with NUREG-1433, Revision 3.0, "Standard Technical Specifications General Electric Plants, BWR/4 Specifications," June 2004. The proposed changes to the current definitions of Channel Calibration, Channel Check, andChannel Test in Section 1.19 of the Oyster Creek TSs will apply to all instrument functions in the TSs, including Reactor Protection System (RPS) instruments. The proposed changes would allow for overlapping or sequential testing of all instrumentation channels. Among other things, this manner of testing would minimize the time the RPS would be in a half-scram condition during surveillance testing, thereby minimizing the chance of a full scram due to spurious half scram signals from the opposite channel.

2.0REGULATORY EVALUATION

The licensee identified the applicable regulatory requirements in Section 5.2 of Attachment 1 ofits submittal. The criteria against which the Nuclear Regulatory Commission (NRC) staff evaluated the proposed change are Title 10 of the Code of Federal Regulations (10 CFR), Part50, Appendix A, General Design Criterion (GDC) 21, "Protection System Reliability and Testability," and 10 CFR 50.55a(h), "Protection and safety systems." GDC 21 states as follows: The protection system shall be designed for high functional reliability andinservice testability commensurate with the safety functions to be performed. Redundancy and independence designed into the protection system shall besufficient to assure that (1) no single failure results in loss of the protection function and (2) removal from service of any component or channel does not result in loss of the required minimum redundancy unless the acceptable reliability of operation of the protection system can be otherwise demonstrated.

The protection system shall be designed to permit periodic testing of its functioning when the reactor is in operation, including a capability to test channels independently to determine failures and losses of redundance that may have occurred. Since Oyster Creek was designed, built, and began operation prior to the codification of theGDCs, they were not a part of the original design basis for the plant. However, the Updated Final Safety Analysis Report (UFSAR) was subsequently revised to describe conformance with the GDC, including GDC 21. Further, 10 CFR 50.55a(h) lists the codes and standards that licensees must adhere to withregard to protection and safety systems. Currently, this regulation endorses Institute of Electrical and Electronics Engineers (IEEE) Standard 603, 1991 edition, including the correctionsheet dated January 30, 1995. For those nuclear power plants whose construction permits were issued after January 1, 1971, but before May 13, 1999, the regulation requires that plant protection systems must meet either IEEE Standard 279 or IEEE 603, 1991 edition, including the correction sheet dated January 30, 1995. For nuclear power plants with construction permits issued before January 1, 1971, protection systems must be consistent with their licensing bases. Although the Oyster Creek construction permit was issued prior to January 1, 1971, and theissuance of IEEE 279, the licensing basis as described in the Oyster Creek UFSAR has since been updated to reflect IEEE 279 as the design basis for Oyster Creek.

3.0TECHNICAL EVALUATION

3.1Description of Proposed Change 3.1.1Channel Check The proposed change would revise the definition of Channel Check from: A qualitative determination of acceptable operability by observation of channelbehavior during operation. This determination shall include, where possible, comparison of the channel with other independent channels measuring the same variableto: A CHANNEL CHECK shall be the qualitative assessment, by observation, ofchannel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications orstatus derived from independent instrument channels measuring the same parameter. 3.1.2Channel TestThe proposed change would rename a Channel Test as a Channel Functional Test and revisethe definition from: Injection of a simulated signal into the channel to verify its proper responseincluding where applicable, alarm and/or trip initiating action.to: A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actualsignal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY.

The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps. 3.1.3Channel Calibration The proposed change would revise the definition of Channel Calibration from: Adjustment of channel output such that it responds, with acceptable range andaccuracy to known values or the parameter which the channel measures.

Calibration shall encompass the entire channel, including equipment actuation, alarm or trip. to: A CHANNEL CALIBRATION shall be the adjustment as necessary, of thechannel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps. 3.2.1Evaluation of Proposed Definition Changes In its application, AmerGen stated that the Oyster Creek TSs were reviewed for all sectionsreferencing and/or using the instrument terms check, test, functional test, and calibrate/calibration in the context of using the proposed definitions of Channel Check, Channel Calibration, and Channel Functional Test. Further, AmerGen stated that the differences resulting from the proposed definitions were consistent with the existing TS definitions for checking, testing, and calibrating instrument channels while allowing for alternate and improved testing methodologies and maintaining the performance requirements of the instrumentation and associated surveillance frequencies. The NRC staff reviewed the impact of the proposed definition revisions to confirm the licensee'sassertion that the proposed revision will allow flexibility in testing methodologies, while continuing to verify the operability of the instrument channels. The NRC staff finds that the proposed changes will allow for performing overlapping or sequential testing that will continue to test the entire channel, consistent with IEEE 279. Further, the proposed amendment does not modify the time intervals for Surveillance Requirements (SRs), required action times for failure to meet Limiting Conditions for Operation, or Limiting Safety System Settings.

Therefore, the proposed change will continue to meet the design-basis standard of IEEE 279 for Oyster Creek . Additionally, AmerGen stated that complying with the current Oyster Creek TS definitions ofChannel Calibration, Channel Check, and Channel Test for the RPS requires placing the RPSin a half-scram condition during some SR testing. This situation creates a condition where a full-scram would occur while the reactor is at power and within operating limits if the opposite channel of the RPS received a spurious scram signal. By implementing the proposed definitions, overlapping or sequential testing of the RPS channels would be permissible, thus minimizing the time a half-scram condition exists during testing. Minimizing this time reduces the likelihood of a spurious scram at power, improving the reliability of the RPS. Given that the proposed changes will continue to meet the design-basis standard of IEEE 279,while improving the reliability of the RPS, the NRC staff finds the proposed change acceptable. 3.2.2Update of Wording in Associated Specifications Revising the definitions of Channel Check, Channel calibration, and Channel functional Testalso necessitates updating those sections of the TSs that reference the terms. The NRC staff reviewed the current Oyster Creek TSs and the proposed revisions and finds that the licensee appropriately identified those areas in the TSs needing revision and has proposed changes to these areas consistent with the definition changes discussed above. Therefore, the NRC staff finds the proposed revisions to be acceptable.

4.0STATE CONSULTATION

In accordance with the Commission's regulations, the New Jersey State official was notified ofthe proposed issuance of the amendment. The State official had no comments.

5.0ENVIRONMENTAL CONSIDERATION

This amendment changes a requirement with respect to installation or use of a facilitycomponent located within the restricted area as defined in 10 CFR Part 20 and changes SRs.

The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent 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 amendment involves no significant hazards consideration and there has been no public comment on such finding (71 FR 67392). Accordingly, the amendment meets 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 amendment.

6.0CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) thereis 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. Principal Contributors: M. Hamm, G. E. Miller Date: July 27, 2007 Oyster Creek Nuclear Generating StationSite Vice President - Oyster Creek Nuclear Generating Station AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731Senior Vice President of Operations AmerGen Energy Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348Kathryn M. Sutton, EsquireMorgan, Lewis, & Bockius LLP 1111 Pennsylvania Avenue, NW Washington, DC 20004Kent Tosch, ChiefNew Jersey Department of Environmental Protection Bureau of Nuclear Engineering

CN 415 Trenton, NJ 08625Vice President - Licensing and Regulatory Affairs AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555Regional Administrator, Region IU.S. Nuclear Regulatory Commission

475 Allendale Road King of Prussia, PA 19406-1415Mayor of Lacey Township818 West Lacey Road Forked River, NJ 08731Senior Resident InspectorU.S. Nuclear Regulatory Commission P.O. Box 445 Forked River, NJ 08731Director - Licensing and Regulatory AffairsAmerGen Energy Company, LLC Correspondence Control P.O. Box 160 Kennett Square, PA 19348Manager Licensing - Oyster CreekExelon Generation Company, LLC Correspondence Control P.O. Box 160 Kennett Square, PA 19348Regulatory Assurance Manager Oyster Creek AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731Assistant General CounselAmerGen Energy Company, LLC 200 Exelon Way Kennett Square, PA 19348Ron Bellamy, Region IU.S. Nuclear Regulatory Commission

475 Allendale Road King of Prussia, PA 19406-1415Correspondence Control DeskAmerGen Energy Company, LLC 200 Exelon Way, KSA 1--1 Kennett Square, PA 19348Oyster Creek Nuclear Generating StationPlant Manager AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731