ML060460089

Amendment Steam Generator Tube Integrity (TAC Nos. MC8067 and MC8068)

ML060460089
Person / Time
Site:	Calvert Cliffs
Issue date:	03/09/2006
From:	Milano P Plant Licensing Branch III-2
To:	Spina J Calvert Cliffs
Milano P, NRR/DLPM ,415-1457
References
TAC MC8067, TAC MC8068
Download: ML060460089 (14)

Text

March 9, 2006Mr. James A. Spina, Vice PresidentCalvert Cliffs Nuclear Power Plant, Inc.

Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs ParkwayLusby, MD 20657-4702

SUBJECT:

CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -AMENDMENT RE: STEAM GENERATOR TUBE INTEGRITY (TAC NOS. MC8067 AND MC8068)

Dear Mr. Spina:

The Commission has issued the enclosed Amendment No. 278 to Renewed Facility OperatingLicense No. DPR-53 and Amendment No. 255 to Renewed Facility Operating LicenseNo. 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 July 13, 2005, as supplemented on November 29, 2005, andJanuary 20 and February 13, 2006.These amendments revise TS 1.1, "Definitions," TS 3.4.13, "RCS [reactor cool ant system]Operational Leakage," TS 5.5.9, "Steam Generator Tube Surveillance Program," and TS 5.6.9,"Steam Generator Tube Inspection Report," and add a new specification (TS 3.4.18) for SteamGenerator (SG) Tube Integrity. The changes implement the guidance for the industry initiative on Nuclear Energy Institute 97-06, "Steam Generator Program Guidelines." The changes are also consistent with TS Task Force (TSTF) Change TSTF- 449, Revision 4, "Steam GeneratorTube Integrity."A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in theCommission's next regular biweekly Federal Register notice.Sincerely,/RA/Patrick D. Milano, Senior Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-317 and 50-318

Enclosures:

1. Amendment No. 278 to DPR-53 2. Amendment No. 255 to DPR-69 3. Safety Evaluationcc w/encls: See next page March 9, 2006Mr. James A. Spina, Vice PresidentCalvert Cliffs Nuclear Power Plant, Inc.

Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs ParkwayLusby, MD 20657-4702

SUBJECT:

CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -AMENDMENT RE: STEAM GENERATOR TUBE INTEGRITY (TAC NOS. MC8067 AND MC8068)

Dear Mr. Spina:

The Commission has issued the enclosed Amendment No. 278 to Renewed Facility OperatingLicense No. DPR-53 and Amendment No. 255 to Renewed Facility Operating LicenseNo. 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 July 13, 2005, as supplemented on November 29, 2005, andJanuary 20 and February 13, 2006.These amendments revise TS 1.1, "Definitions," TS 3.4.13, "RCS [reactor cool ant system]Operational Leakage," TS 5.5.9, "Steam Generator Tube Surveillance Program," and TS 5.6.9,"Steam Generator Tube Inspection Report," and add a new specification (TS 3.4.18) for SteamGenerator (SG) Tube Integrity. The changes implement the guidance for the industry initiative on Nuclear Energy Institute 97-06, "Steam Generator Program Guidelines." The changes are also consistent with TS Task Force (TSTF) Change TSTF- 449, Revision 4, "Steam GeneratorTube Integrity."A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in theCommission's next regular biweekly Federal Register notice.Sincerely,/RA/Patrick D. Milano, Senior Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-317 and 50-318

Enclosures:

1. Amendment No. 278 to DPR-53

2. Amendment No. 255 to DPR-69 3. Safety Evaluationcc w/encls: See next pageAccession Number: ML060460089OFFICELPLI-1/PMLPLI-1/LACSGB/(A)BCITSB/BCOGCLPLI-1/BCNAMEPMilanoSLittleEMurphyTBoyceJBonannoRLaufer DATE02/16/0602/16/0602/16/0602/17/0603/01/0602/07/06OFFICIAL RECORD COPY DATED: March 9, 2006AMENDMENT NO. 278 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53CALVERT CLIFFS UNIT 1AMENDMENT NO. 255 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69CALVERT CLIFFS UNIT 2DISTRIBUTION:PUBLICLPLI-1 R/F R. LauferRidsNrrDorlLpla S. LittleRidsNrrLASLittle P. MilanoRidsNrrPMPMilano T. BoyceRidsNrrDirsItsb E. MurphyRidsNrrDciCsgb L. Miller E. Murphy K. Karwoski G. Hill (2)

OGC RidsOgcMailCenter ACRSRidsAcrsAcnwMailCenter J. Trapp, RIcc: Plant Service list Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 cc:

PresidentCalvert County Board of Commissioners 175 Main Street Prince Frederick, MD 20678Mr. Carey Fleming, EsquireSr. Counsel - Nuclear Generation Constellation Generation Group, LLC 750 East Pratt Street, 17 th floorBaltimore, MD 21202Mr. Louis LarragoiteCalvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs ParkwayLusby, MD 20657-4702Resident InspectorU.S. Nuclear Regulatory Commission

P.O. Box 287 St. Leonard, MD 20685Mr. R. I. McLean, ManagerNuclear Programs Power Plant Research Program Maryland Department of Natural Resources 580 Taylor Avenue (B wing, 3rd floor)

Tawes State Office Building Annapolis, MD 21401Regional Administrator, Region IU.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406Ms. Kristen A. Burger, EsquireMaryland People's Counsel 6 St. Paul Centre Suite 2102 Baltimore, MD 21202-1631Ms. Patricia T. Birnie, EsquireCo-Director Maryland Safe Energy Coalition P.O. Box 33111 Baltimore, MD 21218Mr. Roy HickokNRC Technical Training Center 5700 Brainerd Road Chattanooga, TN 37411-4017 CALVERT CLIFFS NUCLEAR POWER PLANT, INC.DOCKET NO. 50-317CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 1AMENDMENT TO RENEWED FACILITY OPERATING LICENSEAmendment No. 278 Renewed License No. DPR-531.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by Calvert Cliffs Nuclear Power Plant, Inc. (thelicensee) dated July 13, 2005, as supplemented on November 29, 2005, and January 20 and February 13, 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 theCommission'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; andE.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 license is amended by changes to the Technical Specifications asindicated 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 SpecificationsThe Technical Specifications contained in Appendices A and B, as revisedthrough Amendment No. 278, are hereby incorporated into the license. The licensee shall operate the facility in accordance with the TechnicalSpecifications.3.This license amendment is effective as of the date of its issuance and shall beimplemented within 60 days.FOR THE NUCLEAR REGULATORY COMMISSION/RA/Richard J. Laufer, ChiefPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical SpecificationsDate of Issuance: March 9, 2006 CALVERT CLIFFS NUCLEAR POWER PLANT, INC.DOCKET NO. 50-318CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 2AMENDMENT TO RENEWED FACILITY OPERATING LICENSEAmendment No. 255 Renewed License No. DPR-691.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by Calvert Cliffs Nuclear Power Plant, Inc. (thelicensee) dated July 13, 2005, as supplemented on November 29, 2005, and January 20 and February 13, 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 theCommission'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; andE.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 license is amended by changes to the Technical Specifications asindicated 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 SpecificationsThe Technical Specifications contained in Appendices A and B, as revisedthrough Amendment No. 255, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the TechnicalSpecifications.3.This license amendment is effective as of the date of its issuance and shall beimplemented within 60 days.FOR THE NUCLEAR REGULATORY COMMISSION/RA/Richard J. Laufer, ChiefPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical SpecificationsDate of Issuance: March 9, 2006 ATTACHMENT TO LICENSE AMENDMENTSAMENDMENT NO. 278 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53AMENDMENT NO. 255 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69DOCKET NOS. 50-317 AND 50-318Replace the following pages of the Appendix A Technical Specifications with the attachedrevised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.Remove PagesInsert Pagesiiiiiiiiii iviv vv 1.1-41.1-4 1.1-51.1-5 3.4.13-13.4.13-1 3.4.13-23.4.13-2

---3.4.13-3

---3.4.18-1

---3.4.18-2 5.5-75.5-7 5.5-85.5-8 5.5-95.5-9 5.5-105.5-10 5.5-115.5-11 5.5-125.5-12 5.5-135.5-13 5.5-145.5-14 5.5-155.5-15 5.5-165.5-16 5.5-175.5-17 5.5-185.5-18 5.6-95.6-9 5.6-105.6-10 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 278 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53AND AMENDMENT NO. 255 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69CALVERT CLIFFS NUCLEAR POWER PLANT, INC.CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2DOCKET NOS. 50-317 AND 50-31

81.0 INTRODUCTION

By letter dated July 13, 2005, as supplemented on November 29, 2005, and January 20 andFebruary 13, 2006 (Agencywide Documents Access and Management System Accession Nos.

ML051990345, ML053390082, ML060240111 and ML060530037, respectively), the 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 (CCNPP), Technical Specifications (TSs). Therequested changes would revise the existing steam generator (SG) tube surveillance programto be consistent with TS Task Force (TSTF) Change TSTF-449, "Steam Generator Tube Integrity," Revision 4, and the model safety evaluation prepared by the Nuclear RegulatoryCommission (NRC) and published in the Federal Register notice on March 2, 2005 (70 FR10298). In this regard, the scope of the application includes changes to the definition of leakage, changes to the primary-to-secondary leakage requirements, changes to the SG tube surveillance program (SG tube integrity), changes to the SG reporting requirements, and associated changes to the TS Bases.The November 29, 2005, and January 20 and February 13, 2006, letters provided additionalinformation that clarified the application, did not expand the scope of the application asoriginally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register on December 6, 2005 (70 FR 72669).

2.0 REGULATORY EVALUATION

The background, description, and applicability of the proposed changes associated with theSG tube integrity issue and the applicable regulatory requirements were included in the NRCstaff's model safety evaluation (SE) published in the Federal Register on March 2, 2005(70 FR 10298). The "Notice of Availability of Model Application Concerning TechnicalSpecification; Improvement To Modify Requirements Regarding Steam Generator Tube Integrity; Using the Consolidated Line Item Improvement Process" was published in theFederal Register on May 6, 2005 (70 FR 24126), which made the model SE available tolicensees for use.

3.0 TECHNICAL EVALUATION

In its July 13, 2005, application, the licensee proposed changes to the TSs that are consistent,with one exception, with the proposed changes approved in TSTF-449. The NRC model SEprovides a detailed evaluation of the proposed changes that are requested by the licensee in itsapplication. Consistent with TSTF-449, the proposed TS changes included: (1) a reviseddefinition of LEAKAGE in TS 1.1, (2) a revised TS 3.4.13, "RCS [Reactor Coolant System]

Operational Leakage," (3) a new TS 3.4.18, "Steam Generator (SG) Tube Integrity," (4) arevised TS 5.5.9, "Steam Generator Tube Surveillance Program," (5) a revised TS 5.6.9,"Steam Generator Tube Inspection Report," and (6) revised Table of Content pages to reflect the proposed changes. However, as discussed below, the licensee took an exception to TSTF-449, Revision 4, regarding the current primary-to-secondary operational leakage limit.The NRC staff reviewed the licensee's application for consistency with TSTF-449. The staffmade the following observation as a result of its review.In TSTF-449, the TS limit on normal operating primary-to-secondary leakage rate through anyone SG is significantly less than accident induced primary-to-secondary leakage assumed in the licensing basis accident analyses. For CCNPP, the TS operating primary-to-secondaryleakage limit and the accident induced primary-to-secondary leakage assumed in the accident analyses are identical in value. Given this situation, the NRC staff evaluated the acceptability ofthe TS limit and licensing basis assumption presented in the licensee's application as compared to the difference between leakage limits presented in TSTF-449. Since the leakage rate observed during operation may increase during a design-basis accident (DBA), it may be necessary to keep the actually observed operating leak rate well below the operational TS leak rate limit to ensure that the accident induced leakage rate that is assumed in the accidentanalysis is not exceeded. The accident induced leakage rate can increase as a result of either:

(1) the higher differential pressure between the primary and secondary coolant systemsassociated with a DBA causing the leak rate from flaws leaking during normal operation to leak at higher rates; or (2) the higher loadings associated with a DBA causing a flaw that was not leaking during normal operation to leak during the accident.As a result of this issue, the licensee agreed to modify its plant procedures to ensure that theaccident-induced leak rate limit (i.e., the value of leakage rate assumed in the accident analyses) will not be exceeded during a DBA. The licensee stated that it would place anadministrative limit on the observed operational leakage to 50 gpd per SG to provide assurance that the accident-induced leakage would not exceed the TS limit on accident induced leakage of100 gpd per SG. The administrative limit, which is to ensure that the accident-induced leakage analysis assumption is not exceeded, depends on several factors, which can change from cycleto cycle. The NRC staff did not review the adequacy of the administrative operating leakage limitselected by the licensee. Rather, the staff reviewed the adequacy of the proposed TS limits foroperating and accident-induced leakage. However, the staff recognized that adoption of the 50gpd administrative limit on normal operating leakage provided added confidence that the accident-induced leakage limit assumed in the accident analyses would not be exceeded. TheTS limits on operating and accident induced leakage (100 gpd per SG) were consistent with the licensee's final safety analysis report and lower than the value approved in the generic TSTF-449. With respect to the remainder of the licensee's application, the NRC staff finds it isgenerally consistent with TSTF-449 and is bounded by the generic SE. Therefore, the stafffinds the proposed changes are acceptable. ConclusionThe proposed TS changes establish a programmatic, largely performance-based regulatoryframework for ensuring SG tube integrity is maintained. The NRC staff finds that it addresseskey shortcomings of the current framework by ensuring that SG programs are focused on accomplishing the overall objective of maintaining tube integrity. It incorporates performance criteria for evaluating tube integrity that the NRC staff finds consistent with the structuralmargins and the degree of leak tightness assumed in the current plant licensing basis. The NRC staff finds that maintaining these performance criteria provides reasonable assurance thatthe SGs can be operated safely without increase in risk.The revised TSs will contain limited specific details concerning how the SG Tube SurveillanceProgram is to achieve the required objective of maintaining tube integrity; the intent being thatthe licensee will have the flexibility to determine the specific strategy for meeting this objective.

However, the NRC staff finds that the revised TSs include sufficient regulatory constraints onthe establishment and implementation of the SG Tube Surveillance Program such as to providereasonable assurance that tube integrity will be maintai ned.Failure to meet the performance criteria will be reportable pursuant to the requirements in10 CFR Parts 50.72 and 50.73. The NRC reactor oversight process provides a process bywhich the NRC staff can verify that the licensee has identified any SG Tube SurveillanceProgram deficiencies that may have contributed to such an occurrence and that appropriate corrective actions have been implemented.In conclusion, the NRC staff finds that the TS changes proposed by the licensee in itsJuly 13, 2005, application conform to the requirements of 10 CFR 50.36 and establish a TSframework that will provide reasonable assurance that SG tube integrity is maintained withoutundue risk to public health and safety.

4.0 STATE CONSULTATION

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

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to installation or use of a facilitycomponent located within the restricted area as defined in 10 CFR Part 20. The NRC staff hasdetermined that the amendments involve no significant increase in the amounts, and nosignificant change in the types, of any effluents that may be released offsite, and that there isno 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(70 FR 72669). Accordingly, the amendments meet the eligibility criteria for categoricalexclusion 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 isreasonable assurance that the health and safety of the public will not be endangered byoperation in the proposed manner, (2) such activities will be conducted in compliance with theCommission's regulations, and (3) the issuance of the amendments will not be inimical to thecommon defense and security or to the health and safety of the public.

7.0 REFERENCES

A complete list of references used to complete this review can be found in the NRC's model SEpublished in the Federal Register on March 2, 2005 (70 FR 10298).Principal Contributor: L. Miller Date: March 9, 2006