ML080840339

License Amendments 286 and 263 Modification of Technical Specification Definitions

ML080840339
Person / Time
Site:	Calvert Cliffs
Issue date:	04/23/2008
From:	Pickett D NRC/NRR/ADRO/DORL/LPLI-1
To:	Spina J Calvert Cliffs
Pickett D, NRR/DORL, 415-1364
Shared Package
ML080840357	List: ML080840339
References
TAC MD7315, TAC MD7316
Download: ML080840339 (13)

Text

April 23, 2008 Mr. James A. Spina, Vice President Calvert Cliffs Nuclear Power Plant, Inc.

Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702

SUBJECT:

CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -

AMENDMENT RE: MODIFICATION OF TECHNICAL SPECIFICATION DEFINITIONS (TAC NOS. MD7315 AND MD7316)

Dear Mr. Spina:

The Commission has issued the enclosed Amendment No. 286 to Renewed Facility Operating License No. DPR-53 and Amendment No. 263 to Renewed Facility Operating License No. DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2. These amendments consist of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated November 8, 2007, as supplemented on March 11, 2008.

These amendments modify TS 1.1, Definitions, to clarify the definitions of Channel Calibration and Channel Functional Test. The amendments incorporate TS Task Force (TSTF) Standard TS Change Traveler TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, Revision 3, dated July 31, 2003.

A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission=s next regular biweekly Federal Register notice.

Sincerely,

/RA/

Douglas V. Pickett, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318

Enclosures:

1. Amendment No. 286 to DPR-53

2. Amendment No. 263 to DPR-69

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

April 23, 2008 Mr. James A. Spina, Vice President Calvert Cliffs Nuclear Power Plant, Inc.

Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702

SUBJECT:

CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -

AMENDMENT RE: MODIFICATION OF TECHNICAL SPECIFICATION DEFINITIONS (TAC NOS. MD7315 AND MD7316)

Dear Mr. Spina:

The Commission has issued the enclosed Amendment No. 286 to Renewed Facility Operating License No. DPR-53 and Amendment No. 263 to Renewed Facility Operating License No. DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2. These amendments consist of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated November 8, 2007, as supplemented on March 11, 2008.

These amendments modify TS 1.1, Definitions, to clarify the definitions of Channel Calibration and Channel Functional Test. The amendments incorporate TS Task Force (TSTF) Standard TS Change Traveler TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, Revision 3, dated July 31, 2003.

A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission=s next regular biweekly Federal Register notice.

Sincerely,

/RA/

Douglas V. Pickett, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318

Enclosures:

1. Amendment No. 286 To DPR-53

2. Amendment No. 263 To DPR-69

3. Safety Evaluation cc w/encls: See next page Package No.: ML080840357, Amendment No.: ML080840339, Tech Spec No.: ML NRR-058 OFFICE PM/LPL1-1 LA/LPL1-1 BC/ITSB OGC BC/LPL1-1 NAME DPickett:sp SLittle GWaig CChandler MKowal DATE 4/04/ 08 4/03/ 08 4/08/ 08 4/17/ 08 4/23/ 08 OFFICIAL RECORD COPY

DATED: April 23, 2008 AMENDMENT NO. 286 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 CALVERT CLIFFS UNIT 1 AMENDMENT NO. 263 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 CALVERT CLIFFS UNIT 2 PUBLIC LPLI-1 R/F RidsNrrDorlLpi-1 RidsNrrLASLittle RidsNrrPMDPickett G. Hill (4) Hard Copy RidsOgcMailCenter RidsAcrsAcnw&mMailCenter RidsNrrDirsItsb RidsRgn1Mailcenter (G. Dentel)

CSchulten

Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 cc:

Mr. Michael J. Wallace, President Ms. Kristen A. Burger, Esquire Constellation Energy Nuclear Group, LLC Maryland People's Counsel 750 East Pratt Street, 18th Floor 6 St. Paul Centre Baltimore, MD 21202 Suite 2102 Baltimore, MD 21202-1631 Mr. John M. Heffley, Senior Vice President and Chief Nuclear Officer Ms. Patricia T. Birnie, Esquire Constellation Energy Nuclear Generation Co-Director Group Maryland Safe Energy Coalition 111 Market Place P.O. Box 33111 Baltimore, MD 21202 Baltimore, MD 21218 President Mr. Roy Hickok Calvert County Board of NRC Technical Training Center Commissioners 5700 Brainerd Road 175 Main Street Chattanooga, TN 37411-4017 Prince Frederick, MD 20678 Mr. Louis S. Larragoite Mr. Carey Fleming, Esquire Manager - Nuclear Licensing Sr. Counsel - Nuclear Generation Constellation Energy Nuclear Generation Constellation Energy Nuclear Group, LLC Group 750 East Pratt Street, 17th floor 111 Market Place, 2nd Floor Baltimore, MD 21202 Baltimore, MD 21202 Mr. Jay S. Gaines Director, Licensing Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 287 St. Leonard, MD 20685 Ms. Susan T. Gray, Program Manager Power Plant Assessment Program Maryland Department of Natural Resources Tawes State Office Building B-3 580 Taylor Avenue Annapolis, MD 21401 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406

CALVERT CLIFFS NUCLEAR POWER PLANT, INC.

DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 286 Renewed License No. DPR-53

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

A. The application for amendment by Calvert Cliffs Nuclear Power Plant, Inc. (the licensee) dated November 8, 2007, as supplemented by letter dated March 11, 2008, 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 the Act, and the rules and 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; 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 attachment to this license amendment, and paragraph 2.C.2. of Renewed Facility Operating License No. DPR-53 is hereby amended to read as follows:

2. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 286, are hereby incorporated into the license. The licensee 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 be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Mark G. Kowal, Chief Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License and Technical Specifications Date of Issuance: April 23, 2008

CALVERT CLIFFS NUCLEAR POWER PLANT, INC.

DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 263 Renewed License No. DPR-69

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

A. The application for amendment by Calvert Cliffs Nuclear Power Plant, Inc. (the licensee) dated November 8, 2007, as supplemented by letter dated March 11, 2008, 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 the Act, and the rules and 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; 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 attachment to this license amendment, and paragraph 2.C.2. of Renewed Facility Operating License No. DPR-69 is hereby amended to read as follows:

2. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 263, are hereby incorporated in the license. The licensee 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 be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Mark G. Kowal, Chief Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License and Technical Specifications Date of Issuance: April 23, 2008

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 286 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO. 263 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NOS. 50-317 AND 50-318 Replace the following pages of the Facility Operating License with the attached revised pages.

The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages 3 3 3 3 Replace the following pages of the 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 Pages Insert Pages 1.1-1 1.1-1 1.1-2 1.1-2 1.1-3 1.1-3 1.1-4 1.1-4 1.1-5 1.1-5 1.1-6 1.1-6

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 286 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 AND AMENDMENT NO. 263 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 CALVERT CLIFFS NUCLEAR POWER PLANT, INC.

CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-317 AND 50-318

1.0 INTRODUCTION

By application dated November 8, 2007 (Agencywide Documents Access and Management Systems (ADAMS) Accession No. ML073170180), as supplemented by letter dated March 11, 2008 (ADAMS Accession No. ML080740049), Calvert Cliffs Nuclear Power Plant, Inc. (the licensee) submitted a request for changes to the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Technical Specifications (TSs). The proposed changes would revise selected TS definitions in accordance with TS Task Force (TSTF) Improved Standard TS Change Traveler TSTF-205-A, "Revision of Channel Calibration, Channel Functional Test, and Related Definitions," Revision 3, dated July 31, 2003. The application proposes changes to the definitions of Channel Calibration and Channel Functional Test to ensure that testing performed in accordance with the TS defined terms includes all instrument loop components required to establish channel operability.

The letter dated March 11, 2008, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination as published in the FEDERAL REGISTER.

2.0 REGULATORY EVALUATION

In Title 10 of the Code of Federal Regulations (10 CFR) 50.36, the Commission established its regulatory requirements related to the content of the TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to plant operation:

(1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls. The rule does not, however, specify the particular requirements to be included in a plant=s TS.

In 1992, the NRC issued the improved standard TSs (STS) to clarify the content and form of requirements necessary to ensure safe operation of nuclear power plants in accordance with 10 CFR 50.36. Major revisions to the STS were published in April 2001 and June 2004. Total adoption of the improved STS will substantially improve the efficiency of the regulatory process, and ensure that licensee and NRC resources are applied to significant safety matters.

As use of the STS matured, necessary improvements were identified. The process to initiate changes to the STS involves the industry-sponsored TSTF submitting proposed changes (called a traveler) to the NRC for review, approval, and subsequent incorporation into the next revision of the STS. The NRC staff did not, prior to 2002, prepare a formal safety evaluation describing its safety basis for accepting the associated changes to the STS. The generic acceptability of the model specifications in the STS, however, is documented in the much expanded and improved Bases for the STS.

In general, the licensee cannot justify TS changes solely on the basis of adopting the model STS or industry TSTF travelers. Changes that result in relaxation (less restrictive conditions) of TS requirements require detailed justification. When requirements have been shown to give little or no safety benefit, their relaxation or removal from the TSs may be appropriate. Other changes made to adopt the model STS are new, more conservative than corresponding requirements in the current TS, or have additional restrictions that are not in the current TSs but are in the STS.

The NRC staff evaluates the additional restrictions on plant operation to ensure that they enhance safety. Additionally, non-technical (administrative) TS changes incorporate human factor principles for the preferred format into the form and structure of the TSs so that plant operations personnel can use them more easily. These changes are editorial in nature or involve the reorganization or reformatting of current TS requirements without affecting technical content or operational restrictions. In order to ensure consistency, the NRC staff use STS as guidance to reformat and make other administrative changes.

Consequently, licensees applying to incorporate a TSTF into the TSs require plant-specific justification acceptable to the NRC staff. Therefore, the NRC staff made use of applicable regulatory guidance which includes the following:

(1) Model TSs contained in the improved STS NUREG-1432, "Standard Technical Specifications Combustion Engineering Plants," Revision 3.0, dated June 2004, and (2) Industry/TSTF Standard Technical Specifications Change Traveler TSTF-205-A, Revision 3, "Revision of Channel Calibration, Channel Functional Test, and Related Definitions."

3.0 TECHNICAL EVALUATION

TSTF-205-A, Revision 3, revised definitions for Channel Calibration and Channel Functional Test in the improved STS to remove potential ambiguity in what constitutes an acceptable test.

TS Section 1.1 includes definitions for instrumentation testing requirements. In accordance with 10 CFR 50.36(c)(3), "Surveillance requirements," SRs are requirements related to test, calibration, or inspection needed to assure that the necessary quality of systems and components is maintained, facility operation is within limits, and that the TS LCO is met. The definitions of Channel Calibration and Channel Functional Test establish requirements for conducting testing including what the test involves, the scope of components that the test encompasses, and instructions on how the test is to be performed. The terms defined in Section 1.1 are referenced throughout instrumentation TS SRs to help assure consistent performance of SRs.

3.1 TSTF-205-A, Revision 3 In its application, the licensee proposed to adopt TSTF-205-A, Revision 3, TS changes to the definitions of the Channel Calibration and Channel Functional Test to eliminate current ambiguity and possible misinterpretations of testing requirements. In addition, conforming Bases changes were made to provide an appropriate basis for these revised terms.

The current TS definitions for instrumentation Channel Calibration and Channel Functional Test use the phrases "sensor and alarm and/or trip functions, and "alarm and/or trip functions, respectively, to describe those instrument channel devices required to be included for specified tests. There is ambiguity as to whether the list is inclusive of all devices that must be tested or whether the list is representative of devices to be tested. Thus, the licensee adopted proposed changes from TSTF-205-A, Revision 3, which replace the string of required instrument channel devices in the definitions discussed above with "all devices in the channel required for channel OPERABILITY." These changes make clear that the components that are required to be tested or calibrated are only those that are necessary for the channel to perform its safety functions.

The current TS definition for Channel Calibration specifies that testing may be "performed by means of any series of sequential, overlapping or total channel steps so that the entire channel is calibrated." The proposed TS change deletes the phrase "so that the entire channel is calibrated" from the definition of Channel Calibration to eliminate a verbatim conflict between the definition and the TSTF-205-A, Revision 3, Bases, which state a successful test to be the verification of the change of state of a single contact of the relay.

The licensee proposes to add the following sentence to the TS definition for Channel Functional Test:

The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps.

The addition of the above sentence clarifies how the Channel Functional Test is to be performed, eliminates any conflicts between the definition and the TSTF-205-A, Revision 3, Bases, and is consistent with NUREG-1432.

Finally, the revised Channel Functional Test definition does not address the method for conducting testing of all required channel devices. The NRC staff position is that a successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable channel functional test of a relay. This is acceptable because all of the other required contacts of the relay are verified by other TS and non-TS tests at least once per refueling interval with applicable extensions. This NRC staff position is incorporated into the TSTF-205-A, Revision 3, Bases for channel functional tests. The licensee chose to adopt the approved TSTF-205-A, Revision 3, Bases to clarify testing requirements by modifying the Bases of applicable surveillances to provide acceptable methods of testing.

The NRC staff reviewed all of the administrative changes proposed by the licensee and finds them acceptable because they are compatible with the STS, do not result in any substantive change in operating requirements, and are consistent with the Commission's regulations. These changes will provide for a consistent application of the definitions, tests, and calibrations.

4.0 STATE CONSULTATION

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

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves 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 amendment involves no significant hazards consideration, and there has been no public comment on such finding (72 FR 71705). 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.

6.0 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 amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: C. Schulten Date: April 23, 2008