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, 2007 Mr. David A. Christian Sr. 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 AMENDMENT RE: CYCLE-SPECIFIC PARAMETERS TECHNICAL SPECIFICATION CHANGE (TAC NO. MC2634)

Dear Mr. Christian:

The Commission has issued the enclosed Amendment No. 236 to Facility Operating License No. 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 the Commissions 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 Regulation Docket No. 50-423

Enclosures:

1. Amendment No. 236 to NPF-49

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

March 14, 2007 Mr. David A. Christian Sr. 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 AMENDMENT RE: CYCLE-SPECIFIC PARAMETERS TECHNICAL SPECIFICATION CHANGE (TAC NO. MC2634)

Dear Mr. Christian:

The Commission has issued the enclosed Amendment No. 236 to Facility Operating License No. 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 the Commissions 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 Regulation Docket No. 50-423

Enclosures:

1. Amendment No. 236 to NPF-49

2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:

PUBLIC LPL1-2 R/F RidsNrrPMVNerses RidsNrrLACRaynor RidsNrrDorlLpl1-2 RidsNrrDorl RidsOgcRp RidsAcrsAcnwMailCenter PKrohn, Rgn 1 TKobetz GHill(2)

Package Accession No.: ML063540109 Amendment Accession No.: ML063540114 TS(s) Accession No.: ML070780688 OFFICE LPLI-2/PM LPL1-2/LA SPWB/BC ITSB/BC OGC LPLI-2/BC NAME VNerses CRaynor JNakoski TKobetz MBarkman HChernoff (NLO w/edits)

DATE 1/12/07 1/12/07 11/22/06 1/18/07 2/14/07 3/14/07 OFFICIAL RECORD COPY

Millstone Power Station, Unit No. 3 cc:

Lillilan M. Cuoco, Esquire Mr. Joseph Roy, Senior Counsel Director of Operations Dominion Resources Services, Inc. Massachusetts Municipal Wholesale Building 475, 5th Floor Electric Company Rope Ferry Road Moody Street Waterford, CT 06385 P.O. Box 426 Ludlow, MA 01056 Edward L. Wilds, Jr., Ph.D.

Director, Division of Radiation Mr. J. Alan Price Department of Environmental Protection Site Vice President 79 Elm Street Dominion Nuclear Connecticut, Inc.

Hartford, CT 06106-5127 Building 475, 5th Floor Rope Ferry Road Regional Administrator, Region I Waterford, CT 06385 U.S. Nuclear Regulatory Commission 475 Allendale Road Mr. Chris Funderburk King of Prussia, PA 19406 Director, Nuclear Licensing and Operations Support First Selectmen Dominion Resources Services, Inc.

Town of Waterford 5000 Dominion Boulevard 15 Rope Ferry Road Glen Allen, VA 23060-6711 Waterford, CT 06385 Mr. David W. Dodson Mr. J. W. "Bill" Sheehan Licensing Supervisor Co-Chair NEAC Dominion Nuclear Connecticut, Inc.

19 Laurel Crest Drive Building 475, 5th Floor Waterford, CT 06385 Rope Ferry Road Waterford, CT 06385 Mr. Evan W. Woollacott Co-Chair Nuclear Energy Advisory Council 128 Terry's Plain Road Simsbury, CT 06070 Senior Resident Inspector Millstone Power Station c/o U.S. Nuclear Regulatory Commission P. O. Box 513 Niantic, CT 06357 Ms. Nancy Burton 147 Cross Highway Redding Ridge, CT 00870

DOMINION NUCLEAR CONNECTICUT, INC DOCKET NO. 50-423 MILLSTONE POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 236 License No. NPF-49

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

A. The application for amendment filed by Dominion Nuclear Connecticut, Inc. (the licensee) dated July 19, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 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 Commissions regulations set forth in 10 CFR Chapter I; 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 Commissions 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 Facility Operating License No. NPF-49 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment 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 implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/ra/

Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: March 14, 2007

ATTACHMENT TO LICENSE AMENDMENT NO. 236 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following page of Facility Operating License No. NPF-49 with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.

Remove Insert 4 4 Replace the following pages of the Appendix A, Technical Specifications with the attached revised pages as indicated. The revised pages are identified by amendment number and contains marginal lines indicating the areas of change.

Remove Insert iii iii 2-1 2-1 2-2 2-2 3/4 2-19 3/4 2-19 3/4 2-20 3/4 2-20 6-19a 6-19a 6-20 6-20 6-20a 6-20a

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 236 TO FACILITY OPERATING LICENSE NO. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION, UNIT NO. 3 DOCKET NO. 50-423

1.0 INTRODUCTION

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 Nuclear Enthalpy Rise Hot Channel Factor This license amendment incorporates Technical Specification Task Force (TSTF) Change Traveler TSTF-339 and is consistent with NUREG-1431, Revision 3.1, Standard Technical Specifications for Westinghouse Plants.

2.0 REGULATORY EVALUATION

Guidance on the relocation of cycle-specific TS parameters to the COLR was developed by the Nuclear 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 was established. 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 Owners Group (WOG) topical report WCAP-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 staffs 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 approved changes 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 similar TS 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.

3.0 TECHNICAL EVALUATION

3.1 Relocation of Figure 2.1-1 to the COLR The licensee proposed relocating Figure 2.2-1 to the COLR and replacing it with more specific safety 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 staffs basis for allowing the relocation of the RCSL figure:

The current TS figure presents core limits on RCS temperature conditions (T-avg) as a function 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 nuclear reactors 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 important process 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 the approved 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 licensees proposal also includes the addition of the figures 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.

3.2 Revision of TS 2.1.1 The proposed changes to TS 2.1.1 include modifying the specification to include a reference to the 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 in WCAP-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, and the 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 be maintained 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 EF, decreasing by 58 EF 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 with changes 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.

3.3 Relocation of the RCS Total Flow Rate Requirement to the COLR The licensee proposed relocation of the RCS total flow rate requirement from the TSs to the COLR as a means of providing operating and analysis flexibility from cycle to cycle consistent with WCAP-14483-A. In conjunction with this change, the licensees 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 thus higher 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 in WCAP-14483-A for relocating these parameter values to the COLR. Additionally, the licensee states that For the MPS3 TS, the RCS flow rate is not included with pressurizer pressure and RCS 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 administrative difference and the proposed change to TS 3/4.2.3 agrees with the intent of TSTF-339 for relocating parameters to the COLR consistent with WCAP-14483. MPS3 TSs include pressurizer pressure and RCS average temperature requirements in TS 3/4.2.5, DNB Parameters, and RCS flow rate requirements in TS 3/4.2.3, RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor. Although this is different from the Standard Technical Specifications, NRC staff agrees that this is only an administrative difference and does not detract from the content of the specifications. The licensee also proposed two editorial changes 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 a dash with an equal sign. Both of these changes are editorial in nature and are consistent with Revision 3.1 to NUREG-1431; therefore, the NRC finds these changes acceptable.

3.4 Revision of TS 6.9.1.6, Core Operating Limits Report As discussed above, the licensees proposal includes changes to TS 6.9.1.6, Core Operating Limits 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 Dominions LAR to revise reactor core safety limit TSs 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 Commissions regulations, the Connecticut State official was notified of the proposed issuance of the amendment. The Connecticut State official agreed with the NRC staffs 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 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 change 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 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 of the public will not be endangered by operation in the proposed manner, (2) such activity will be conducted in compliance with the Commissions 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 Core Operating Limits Report, November 1995.

4. Letter from T.H. Essig (NRC) to WOG, Acceptance for Referencing of Licensing Topical Report 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 Delta T and Thermal Overtemperature Delta T Trip Functions, (Westinghouse Proprietary Class 2), September 1986.

6. WOG Topical Report WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, (Westinghouse Proprietary Class 2), March 1978.

Principal Contributor: S. Cleavenger Date: March 14, 2007