ML063540114

License Amendment, Issuance of Amendment Cycle Specific Parameters Technical Specification Change

ML063540114
Person / Time
Site:	Millstone
Issue date:	03/14/2007
From:	Nerses V NRC/NRR/ADRO/DORL/LPLI-2
To:	Christian D Dominion Nuclear Connecticut
Nerses V
Shared Package
ML063540109	List: ML063540114
References
TAC MC2634
Download: ML063540114 (12)

Text

March 14, 2007Mr. David A. ChristianSr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.

Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

MILLSTONE POWER STATION, UNIT NO. 3 - ISSUANCE OF AMENDMENTRE: CYCLE-SPECIFIC PARAMETERS TECHNICAL SPECIFICATION CHANGE (TAC NO. MC2634)

Dear Mr. Christian:

The Commission has issued the enclosed Amendment No. 236 to Facility Operating LicenseNo. NPF-49 for the Millstone Power Station, Unit No. 3 (MPS3). This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated July 19,2006. The amendment revises the reactor core safety limits TS and relocates the reactor core safety limit figure to the Core Operating Limits Report in the MPS3 Technical Requirements Manual.A copy of our Safety Evaluation is also enclosed. Notice of Issuance will be included in theCommission's biweekly Federal Register notice. Sincerely,/ra/Victor Nerses, Senior Project ManagerPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-423

Enclosures:

1. Amendment No. 236 to NPF-49

2. Safety Evaluationcc w/encls: See next page March 14, 2007Mr. David A. ChristianSr. Vice President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.

Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

MILLSTONE POWER STATION, UNIT NO. 3 - ISSUANCE OF AMENDMENTRE: CYCLE-SPECIFIC PARAMETERS TECHNICAL SPECIFICATION CHANGE (TAC NO. MC2634)

Dear Mr. Christian:

The Commission has issued the enclosed Amendment No. 236 to Facility Operating LicenseNo. NPF-49 for the Millstone Power Station, Unit No. 3 (MPS3). This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated July 19,2006. The amendment revises the reactor core safety limits TS and relocates the reactor core safety limit figure to the Core Operating Limits Report in the MPS3 Technical Requirements Manual.A copy of our Safety Evaluation is also enclosed. Notice of Issuance will be included in theCommission's biweekly Federal Register notice. Sincerely,/ra/Victor Nerses, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-423

Enclosures:

1. Amendment No. 236 to NPF-49

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

PUBLICLPL1-2 R/FRidsNrrPMVNersesRidsNrrLACRaynor RidsNrrDorlLpl1-2RidsNrrDorlRidsOgcRpRidsAcrsAcnwMailCenter PKrohn, Rgn 1TKobetzGHill(2)Package Accession No.: ML063540109Amendment Accession No.: ML063540114 TS(s) Accession No.: ML070780688 OFFICELPLI-2/PMLPL1-2/LASPWB/BCITSB/BCOGCLPLI-2/BCNAMEVNersesCRaynorJNakoski TKobetzMBarkman(NLO w/edits)HChernoffDATE1/12/071/12/0711/22/061/18/072/14/073/14/07OFFICIAL RECORD COPY Millstone Power Station, Unit No. 3 cc:

Lillilan M. Cuoco, EsquireSenior Counsel Dominion Resources Services, Inc.

Building 475, 5 th FloorRope Ferry Road Waterford, CT 06385Edward L. Wilds, Jr., Ph.D.Director, Division of Radiation Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127Regional Administrator, Region IU.S. Nuclear Regulatory Commission

475 Allendale Road King of Prussia, PA 19406First SelectmenTown of Waterford 15 Rope Ferry Road Waterford, CT 06385Mr. J. W. "Bill" Sheehan Co-Chair NEAC 19 Laurel Crest Drive Waterford, CT 06385Mr. Evan W. WoollacottCo-Chair Nuclear Energy Advisory Council 128 Terry's Plain Road Simsbury, CT 06070Senior Resident InspectorMillstone Power Station c/o U.S. Nuclear Regulatory Commission P. O. Box 513 Niantic, CT 06357Ms. Nancy Burton147 Cross Highway Redding Ridge, CT 00870Mr. Joseph Roy, Director of Operations Massachusetts Municipal Wholesale Electric Company Moody Street P.O. Box 426 Ludlow, MA 01056Mr. J. Alan PriceSite Vice President Dominion Nuclear Connecticut, Inc.

Building 475, 5 th FloorRope Ferry Road Waterford, CT 06385Mr. Chris FunderburkDirector, Nuclear Licensing and Operations Support Dominion Resources Services, Inc.

5000 Dominion Boulevard Glen Allen, VA 23060-6711Mr. David W. DodsonLicensing Supervisor Dominion Nuclear Connecticut, Inc.

Building 475, 5 th FloorRope Ferry Road Waterford, CT 06385 DOMINION NUCLEAR CONNECTICUT, INCDOCKET NO. 50-423MILLSTONE POWER STATION, UNIT NO. 3AMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 236License No. NPF-491.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment filed by Dominion Nuclear Connecticut, Inc. (thelicensee) dated July 19, 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 Title 10 of the Code of Federal Regulations(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 set forth in 10 CFR Chapter I;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 as indicatedin the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-49 is hereby amended to read as follows:(2)Technical Specifications and Environmental Protection PlanThe Technical Specifications contained in Appendix A, as revised throughAmendment No. , and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. Dominion Nuclear Connecticut, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3.This license amendment is effective as of its date of issuance and shall be implementedwithin 60 days 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 Technical SpecificationsDate of Issuance: March 14, 2007 ATTACHMENT TO LICENSE AMENDMENT NO. 236 FACILITY OPERATING LICENSE NO. NPF-49DOCKET NO. 50-423Replace the following page of Facility Operating License No. NPF-49 with the attached revisedpage. The revised page is identified by amendment number and contains a marginal line indicating the area of change.RemoveInsert 44Replace the following pages of the Appendix A, Technical Specifications with the attachedrevised pages as indicated. The revised pages are identified by amendment number and contains marginal lines indicating the areas of change.RemoveInsertiiiiii2-12-1 2-22-2 3/4 2-193/4 2-19 3/4 2-203/4 2-20 6-19a6-19a 6-206-20 6-20a6-20a SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 236 TO FACILITY OPERATINGLICENSE NO. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION, UNIT NO. 3 DOCKET NO. 50-423

1.0INTRODUCTION

By letter dated July 19, 2006 (Reference 1), Dominion Nuclear Connecticut, Inc. (Dominion),the licensee for operation of Millstone Power Station, Unit No.3 (MPS3) submitted a license amendment request (LAR) to revise reactor core safety limit (RCSL) Technical Specifications (TSs) and relocate the RCSL figure to the Core Operating Limits Report (COLR) in the MPS3 Technical Requirements Manual. The proposed amendment also adds safety limits relating to departure from nucleate boiling ratio (DNBR) and peak fuel centerline temperature and moves the reactor coolant system (RCS) total flow rate limit to the COLR (while retaining the minimum RCS total flow rate in the TSs). The TSs affected by the change are:*TS 2.1.1 - "Safety Limits - Reactor Core"*Figure 2.1 "Reactor Core Safety Limit"

• TSs 6.8.1.6.a and b - "Administrative Controls - Core Operating Limits Report"

• TS LCO (limiting condition of operation) 3/4.2.3.1 - "RCS Flow Rate and NuclearEnthalpy Rise Hot Channel Factor"This license amendment incorporates Technical Specification Task Force (TSTF) ChangeTraveler TSTF-339 and is consistent with NUREG-1431, Revision 3.1, "Standard Technical Specifications for Westinghouse Plants."

2.0REGULATORY EVALUATION

Guidance on the relocation of cycle-specific TS parameters to the COLR was developed by theNuclear Regulatory Commission (NRC or the Commission) staff and published in Generic Letter (GL) 88-16, "Removal of Cycle-Specific Parameter Limits from Technical Specifications,"

dated October 3, 1988 (Reference 2). In the GL, the NRC states that license amendments are generally required each fuel cycle to update the values of cycle-specific parameter limits in the TSs. Because the methodology for determining the parameter limits is documented in an NRC-approved Topical Report or in a plant-specific submittal, the review of such proposed changes is primarily limited to the confirmation that the updated limits are calculated using an NRC-approved methodology and consistent with all applicable limits of the safety analysis. Given the redundant and frequent nature of the reviews, processing these changes presented an unnecessary burden on both the licensee and NRC resources. As a result, the COLR wasestablished. The COLR is a formal report that includes the values of cycle-specific parameter limits that have been established using NRC-approved methodologies and consistent with all applicable limits of the safety analysis. GL 88-16 allows licensees to remove cycle-dependent variables from the TSs as long as the values are included in a COLR and are determined with an NRC-approved methodology that is referenced in the TSs. This avoids frequent TS revisions to change the value of certain parameter limits that cannot be reasonably bound across multiple operating cycles without significant loss of operating flexibility. In January of 1999, the NRC approved Westinghouse Owner's Group (WOG) topical reportWCAP-14483-A (Reference 3), "Generic Methodology for Expanded Core Operating Limits Report," that provides methodology to support the removal of RCS-related cycle-specific parameter limits from the TSs to the COLR. The NRC staff's evaluation approving WCAP-14483-A as an acceptable method to relocate these TS requirements to the COLR consistent with GL 88-16 is provided in Reference 4.TSTF-339 was approved by the NRC on July 27, 1999. Revision 2 to TSTF-339 approvedchanges to NUREG-1431, including the revision of TS 3.4.1, "RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits," to relocate the pressurizer pressure, RCS average temperature (T-avg), and RCS total flow rate values to the COLR. The minimum limit for total RCS flow based on the value used in the safety analysis was required to be retained in the TSs. The TSTF also revised TS 2.1, "Safety Limits," and the associated bases to relocate Figure 2.1.1-1 to the COLR and replace it with more specific requirements regarding the safety limits (fuel DNB design basis and the fuel centerline melt design basis). As with all other similarTS changes, the NRC-approved methodology used to derive the parameters in the figure must be referenced in the Reporting Requirements section of the TSs. Further references to TSTF-339 in this Safety Evaluation (SE) refer to Revision 2 of the TSTF.

3.0TECHNICAL EVALUATION

3.1Relocation of Figure 2.1-1 to the COLRThe licensee proposed relocating Figure 2.2-1 to the COLR and replacing it with more specificsafety limits for DNBR and peak fuel centerline temperature to better align MPS3 TSs with the WOG standard TS, NUREG-1431. TSTF-339, based on WCAP 14483-A, was incorporated into Revision 3.1 of NUREG-1431. Reference 4 describes the NRC staff's basis for allowing the relocation of the RCSL figure:The current TS figure presents core limits on RCS temperature conditions (T-avg) as afunction of pressurizer pressure and fractional rated thermal power. This figure was originally included in the Westinghouse TS to satisfy the requirements of 10 CFR [Title 10 of the Code of Federal Regulations] 50.36 which states that "safety limits for nuclearreactors are limits upon important process variables that are found to be necessary to reasonably protect the integrity of certain physical barriers that guard against the uncontrolled release of radioactivity." However, the figure is not a complete presentation of reactor core safety limits but is intended to provide the relationship between the process variables that are available to the operator (i.e., T-avg, pressurizer pressure, and thermal power) and the DNB design basis safety limit. To ensure that the requirements of 10 CFR 50.36 are met, i.e. limits upon importantprocess variables, the WOG has proposed to retain the requirement for a Reactor Core Limits figure in the Safety Limits TS, but relocate the actual figure to the COLR and replace it with the DNB design basis limit and the fuel centerline melt limit. Both of these limits are criteria that must be satisfied for normal operation and for AOOs

[anticipated operational occurrences] to prevent overheating of the fuel cladding and possible cladding perforation which could result in the release of fission products to the RCS and are, therefore, the true safety limits...The NRC staff finds that the changes proposed by the licensee are consistent with theapproved changes identified in WCAP-14483-A for relocating TS Figure 2.1-1 to the COLR, and the above reasoning applies to the requested change. The licensee stated in its LAR that the RCSLs in Figure 2.1-1 are derived from NRC-approved methodologies. These methodologies are contained in WCAP-8745-P-A (Reference 5), "Design Bases for Thermal Overpower Delta T and Thermal Overtemperature Delta T Trip Functions." This report has been approved by the NRC staff and is currently in the list of NRC-approved analytical methods located in TS 6.9.1.6.b. Consequently, TS 6.9.1.6.b.18. (WCAP-8745-P-A) will be updated per the proposed amendment to include reference to Specification 2.1.1. The licensee's proposal also includes the addition of the figure's reference, "1. Reactor Core Safety Limit for Specification 2.1.1," to TS 6.9.1.6.a. Additionally, the proposed change renumbers subsequent items in TS 6.9.1.6.a due to the addition of Item 1, and adds a notation to the index to indicate the deletion of Figure 2.2-1. These items are purely editorial in nature and are acceptable to NRC staff.3.2Revision of TS 2.1.1The proposed changes to TS 2.1.1 include modifying the specification to include a reference tothe COLR for thermal power, RCS highest loop average temperature, and pressurizer pressure limits as well as including specific safety limits for DNBR and peak fuel centerline temperature, added as TS 2.1.1.1 and 2.1.1.2, respectively. The licensee states that the safety limit is similar to the existing one with the exception of (1) referencing the COLR to reflect the relocation of and requirement to operate within the limits of the RCSL figure, and (2) the addition of DNBR and peak fuel centerline temperature limits. The NRC staff finds that these changes are consistent with the approved changes identified inWCAP-14483-A for relocating these parameter values to the COLR as indicated by the following statement in Reference 4:The TS limits on the DNB parameters assure that pressurizer pressure, RCS flow, andthe RCS T-avg will be maintained within the limits of steady-state operation assumed in the accident analyses. These limits must be consistent with the initial full power conditions considered in the FSAR [final safety analysis report] safety analysis for normal operation and anticipated operational occurrences (AOOs) in which precluding DNB is the primary criterion. The DNB parameter limits are also based on initial conditions assumed for accidents in which precluding DNB is not a criterion. The licensee stated in its LAR that proposed TS 2.1.1.1, which requires that DNBR bemaintained greater than or equal to 1.17 for the WRB-1/WRB-2 DNB correlations, and proposed TS 2.1.1.2, which requires peak fuel centerline temperature to be maintained less than 5080 F, decreasing by 58 F per 10,000 MWD/MTU of burnup, are both based on NRC-approved methodologies. These methodologies are contained in WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology" (Reference 6). WCAP-9272-P-A has been approved by the NRC staff and is currently in the list of NRC-approved analytical methods located in TS 6.9.1.6.b. Consequently, TS 6.9.1.6.b.1. (WCAP-9272-P-A) will be updated per the proposed amendment to include reference to Specifications 2.1.1.1 and 2.1.1.2.The licensee also proposed modification of the ACTION associated with TS 2.1.1 to agree withchanges in TS 2.1.1. The proposed action requires the licensee to restore compliance and be in HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in the event that the RCSL is violated. This proposed action is consistent with Revision 3.1 to NUREG-1431 and assures compliance with the criteria set forth in the COLR and the safety limits and is, therefore, acceptable to the NRC staff.3.3Relocation of the RCS Total Flow Rate Requirement to the COLRThe licensee proposed relocation of the RCS total flow rate requirement from the TSs to theCOLR as a means of providing operating and analysis flexibility from cycle to cycle consistent with WCAP-14483-A. In conjunction with this change, the licensee's proposal also includes the addition of the "RCS total flow rate" to TS 6.9.1.6.a to identify it as an item included in the COLR. The RCS total flow rate minimum value, however, will remain in the TS (TS 3/4.2.3.1) in order to assure that an RCS total flow rate is not lower than that approved by the NRC.

Retaining the minimum flow rate in the TS will require any reduction in the flow rate below the listed value to be reviewed by the NRC in a license amendment. This change is based on reasoning presented by the NRC staff in Reference 4: Although some plants operate with lower steam generator tube plugging levels and thushigher RCS flow rates than those assumed in the safety analyses, a change in RCS flow is an indication of a physical change to the plant which should be reviewed by the NRC staff. Because of this, the staff recommended that if RCS flow rate were to be relocated to the COLR, the minimum limit for RCS total flow based on a staff approved analysis (e.g., maximum tube plugging) should be retained in the TS to assure that a lower flow rate than reviewed by the staff would not be used.The NRC staff finds that these changes are consistent with the approved changes identified inWCAP-14483-A for relocating these parameter values to the COLR. Additionally, the licenseestates that "For the MPS3 TS, the RCS flow rate is not included with pressurizer pressure andRCS average temperature (TS 3.2.5) requirements as it exists in the industry standard NUREG-1431, TS 3.4 REACTOR COOLANT SYSTEM. However, this is only an administrativedifference and the proposed change to TS 3/4.2.3 agrees with the intent of TSTF-339 forrelocating parameters to the COLR consistent with WCAP-14483." MPS3 TSs include pressurizer pressure and RCS average temperature requirements in TS 3/4.2.5, "DNBParameters," and RCS flow rate requirements in TS 3/4.2.3, "RCS Flow Rate and NuclearEnthalpy Rise Hot Channel Factor." Although this is different from the Standard TechnicalSpecifications, NRC staff agrees that this is only an administrative difference and does notdetract from the content of the specifications. The licensee also proposed two editorialchanges to TS 3.2.3.1.b to enhance readability and improve technical correctness: (1) a substitution of the acronym COLR for Core Operating Limits Report, and (2) replacement of adash with an equal sign. Both of these changes are editorial in nature and are consistent withRevision 3.1 to NUREG-1431; therefore, the NRC finds these changes acceptable.3.4Revision of TS 6.9.1.6, Core Operating Limits ReportAs discussed above, the licensee's proposal includes changes to TS 6.9.1.6, "Core OperatingLimits Report." According to GL 88-16, the removal of cycle-specific parameters from the TSs requires the maintenance of COLR reporting requirements in the Administrative Controls TSs.

TS 6.9.1.6b currently includes the appropriate NRC-approved analytical methods used to determine the core operating limits listed in TS 6.9.1.6.a. The proposed changes add the RCSL and RCS total flow rate to TS 6.9.1.6.a and Specifications 2.1.1.1and 2.1.1.2 (WCAP-9272-P-A) and Specification 2.1.1 (WCAP-8745-P-A) to TS 6.9.1.6.b. The NRC staff concludes that the approved NRC methodologies for the proposed additions to TS 6.9.1.6.a are contained in TS 6.9.1.6.b and that the proposed addition of Specifications 2.1.1 and RCS Total Flow Rate to TS 6.9.1.6.a is acceptable.4.0

SUMMARY

The NRC staff has completed its review of Dominion's LAR to revise reactor core safety limitTSs and relocate the RCSL figure to the COLR for MPS3. Based on the evaluation described in Section 3.0 of this SE, the NRC staff concluded that the proposed changes are acceptable.

5.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Connecticut State official was notified ofthe proposed issuance of the amendment. The Connecticut State official agreed with the NRC staff's conclusion as stated in Section 7.0 of this SE.

6.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to surveillance requirements. The NRCstaff 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 change in individual or cumulative occupational radiation exposure. TheCommission 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 51227). Accordingly, the amendment meets the eligibility criteria for categorical exclusion as 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.

7.0 CONCLUSION

The NRC staff concludes that: (1) there is reasonable assurance that the health and safety ofthe public will not be endangered by operation in the proposed manner, (2) such activity 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 health and safety of the

public.

8.0 REFERENCES

1.Letter from W.R. Matthews (Dominion Nuclear Connecticut, Inc.) to NRC, "Docket No.50-423, License No. NPF-49, Millstone Power Station Unit 3, License Amendment Request LBDCR 06-MP3-014, Cycle Specific Parameters Technical Specification Change," July 19, 2006.2.NRC, GL 88-16, "Removal of Cycle-Specific Parameters from Technical Specifications,"October 3, 1988. 3.WOG Topical Report WCAP-14483-A, "Generic Methodology for Expanded CoreOperating Limits Report," November 1995.4.Letter from T.H. Essig (NRC) to WOG, Acceptance for Referencing of Licensing TopicalReport WCAP-14483, "Generic Methodology for Expanded Core Operating Limits Report", January 19,1999.5.WOG Topical Report WCAP-8745-P-A, "Design Bases for the Thermal Overpower DeltaT and Thermal Overtemperature Delta T Trip Functions," (Westinghouse Proprietary Class 2), September 1986.6.WOG Topical Report WCAP-9272-P-A, "Westinghouse Reload Safety EvaluationMethodology, " (Westinghouse Proprietary Class 2), March 1978.Principal Contributor: S. CleavengerDate: March 14, 2007