ML033450435

License Amendment, Issuance of Amendment, Relocation of Technical Specifications Parameters to the Core Operating Limits Report

ML033450435
Person / Time
Site:	Millstone
Issue date:	03/09/2004
From:	Nerses V NRC/NRR/DLPM/LPD1
To:	Christian D Dominion Nuclear Connecticut
Nerses V, NRR/DLPM, 415-1484
Shared Package
ML033450436	List: ML033450435
References
TAC MB8387
Download: ML033450435 (15)

Text

March 9, 2004 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: RELOCATION OF TECHNICAL SPECIFICATION PARAMETERS TO THE CORE OPERATING LIMITS REPORT (TAC NO. MB8387)

Dear Mr. Christian:

The Commission has issued the enclosed Amendment No. 218 to Facility Operating License No. NPF-49 for Millstone Power Station, Unit No. 3, in response to your application dated April 7, 2003 and its supplement dated September 18, 2003.

The amendment proposes Technical Specification (TS) changes requested by Dominion Nuclear Connecticut, Inc. for Millstone Power Station, Unit No. 3. The proposed TS changes will affect cycle-specific parameters that will be relocated to the Core Operating Limits Report.

A copy of the related 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, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-423

Enclosures:

1. Amendment No. 218 to NPF-49

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

Millstone Power Station, Unit No. 3 cc:

Lillilan M. Cuoco, Esquire Senior Resident Inspector Senior Counsel Millstone Power Station Dominion Resources Services, Inc. c/o U.S. Nuclear Regulatory Commission Rope Ferry Road P. O. Box 513 Waterford, CT 06385 Niantic, CT 06357 Edward L. Wilds, Jr., Ph.D. Mr. G. D. Hicks Director, Division of Radiation Director - Nuclear Station Safety Department of Environmental Protection and Licensing 79 Elm Street Dominion Nuclear Connecticut, Inc.

Hartford, CT 06106-5127 Rope Ferry Road Waterford, CT 06385 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Ms. Nancy Burton 475 Allendale Road 147 Cross Highway King of Prussia, PA 19406 Redding Ridge, CT 00870 First Selectmen Mr. William D. Meinert Town of Waterford Nuclear Engineer 15 Rope Ferry Road Massachusetts Municipal Wholesale Waterford, CT 06385 Electric Company Moody Street Mr. P. J. Parulis P.O. Box 426 Manager - Nuclear Oversight Ludlow, MA 01056 Dominion Nuclear Connecticut, Inc.

Rope Ferry Road Mr. J. Alan Price Waterford, CT 06385 Site Vice President Dominion Nuclear Connecticut, Inc.

Mr. W. R. Matthews Rope Ferry Road Senior Vice President - Nuclear Operations Waterford, CT 06385 Dominion Nuclear Connecticut, Inc.

Rope Ferry Road Mr. Chris Funderburk Waterford, CT 06385 Director, Nuclear Licensing and Operations Support Mr. John Markowicz Dominion Resources Services, Inc.

Co-Chair 5000 Dominion Boulevard Nuclear Energy Advisory Council Glen Allen, VA 23060-6711 9 Susan Terrace Waterford, CT 06385 Mr. David W. Dodson Licensing Supervisor Mr. Evan W. Woollacott Dominion Nuclear Connecticut, Inc.

Co-Chair Rope Ferry Road Nuclear Energy Advisory Council Waterford, CT 06385 128 Terrys Plain Road Simsbury, CT 06070

Millstone Power Station, Unit No. 3 cc:

Mr. S. E. Scace Assistant to the Site Vice President Dominion Nuclear Connecticut, Inc.

Rope Ferry Road Waterford, CT 06385 Mr. M. J. Wilson Manager - Nuclear Training Dominion Nuclear Connecticut, Inc.

Rope Ferry Road Waterford, CT 06385 Mr. A. J. Jordan, Jr.

Director - Nuclear Engineering Dominion Nuclear Connecticut, Inc.

Rope Ferry Road Waterford, CT 06385 Mr. S. P. Sarver Director - Nuclear Station Operations and Maintenance Dominion Nuclear Connecticut, Inc.

Rope Ferry Road Waterford, CT 06385

March 9, 2004 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: RELOCATION OF TECHNICAL SPECIFICATION PARAMETERS TO THE CORE OPERATING LIMITS REPORT (TAC NO. MB8387)

Dear Mr. Christian:

The Commission has issued the enclosed Amendment No. 218 to Facility Operating License No. NPF-49 for Millstone Power Station, Unit No. 3, in response to your application dated April 7, 2003 and its supplement dated September 18, 2003.

The amendment proposes Technical Specification (TS) changes requested by Dominion Nuclear Connecticut, Inc. for Millstone Power Station, Unit No. 3. The proposed TS changes will affect cycle-specific parameters that will be relocated to the Core Operating Limits Report.

A copy of the related 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, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-423

Enclosures:

1. Amendment No. 218 to NPF-49

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

PUBLIC OGC PDI-2 R/F ACRS CHolden CRaynor BMcDermott, RI Tech Branch GHill (2) WBeckner DRoberts VNerses ADAMS Accession Numbers: Letter: ML033450435; TS(s): ML  ;

Package: ML033450436 *See previous concurrence.

OFFICE PDI-2/PM PDI-2/LA DSSA/SRXB OGC PDI-2/SC(A)

NAME VNerses CRaynor JUhle* RWeisman* DRoberts DATE 03/01/04 03/01/04 1/14/04 2/25/04 03/08/04 OFFICIAL RECORD COPY

DOMINION NUCLEAR CONNECTICUT, INC., ET AL.

DOCKET NO. 50-423 MILLSTONE POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 218 License No. NPF-49

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

A. The application for amendment by the applicant dated April 7, 2003, and its supplement dated September 18, 2003, 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 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; 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 The Technical Specifications contained in Appendix A, as revised through Amendment No. 218, 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 the date of issuance, and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Darrell Roberts, Acting Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: March 9, 2004

ATTACHMENT TO LICENSE AMENDMENT NO. 218 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 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 Insert iv iv v v 2-9 2-9 2-10 2-10 2-11 2-11 3/4 1-1 3/4 1-1 3/4 1-3 3/4 1-3 3/4 1-4 3/4 1-4 3/4 1-6 3/4 1-6 3/4 1-7 3/4 1-7 3/4 1-8 3/4 1-8 3/4 1-9 3/4 1-9 3/4 2-27 3/4 2-27 3/4 2-28 3/4 2-28 3/4 3-82 3/4 3-82 3/4 9-1 3/4 9-1 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. 218 TO FACILITY OPERATING LICENSE NO. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

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

1.0 INTRODUCTION

In letters dated April 7, 2003, and September 18, 2003 (References 1 and 2), Dominion Nuclear Connecticut, Inc. (the licensee) requested a license amendment to relocate the values of certain cycle-specific parameters from Technical Specifications (TSs) to a Core Operating Limits Report (COLR) for Millstone Power Station, Unit No. 3 (MP3). The proposed TS changes will affect the TSs which have cycle-specific parameters. These TSs are: (1) TS 2.2, Limiting Safety System Settings, Table 2.2-1; (2) TS 3/4.1.1.1.1, Reactivity Control Systems, Boration Control, Shutdown Margin - Modes 1 and 2; (3) TS 3/4.1.1.1.2, Reactivity Control Systems, Boration Control, Shutdown Margin - Modes 3, 4 and 5 Loops Filled; (4) TS 3/4.1.1.2, Reactivity Control Systems, Shutdown Margin - Modes 3, 4 and 5 Loops Not Filled; (5) TS 3/4.2.5, Power Distribution Limits, DNB Parameters; (6) TS 3/4.3.5, Instrumentation, Shutdown Margin Monitor; (7) TS 3/4.9.1.1, Refueling Operations, Boron Concentration; (8) TS Section 6.9.1.6.a, Core Operating Limits Report, Core Operating Limits; and (9) TS Section 6.9.1.6.b, Core Operating Limits Report, The Analytical Methods Used To Determine The Core Operating Limits. The licensee will revise these TSs and relocate the values of these cycle-specific parameters to the COLR based on the Nuclear Regulatory Commission (NRC or the Commission) Generic Letter (GL) 88-16, Removal of Cycle-Specific Parameter Limits From Technical Specifications, (Reference 3) and the NRC-approved topical report, WCAP-14483-A, Generic Methodology For Expanded Core Operating Limits Report (Reference 4). The COLR process reduces the burden on licensees and the NRC from processing changes to cycle-specific parameter limits in TSs for each fuel cycle, provided the limits are developed using an NRC-approved methodology. The September 18, 2003 letter provided clarifying information that did not change the scope of the amendment as described in the original Federal Register notice dated May 27, 2003 (68 FR 28849), and did not change the staffs initial proposed no significant hazards consideration determination.

2.0 REGULATORY EVALUATION

The Commissions regulatory requirements related to the contents of TSs are set forth in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, which requires that TS limiting conditions for operation (LCOs) be established for process variables, design features, and operating restrictions for which a value is assumed as an initial condition of a design-basis accident in the licensees safety analyses. In accordance with 10 CFR 50.36, the staff and the Nuclear Steam Supply System Owners groups developed Improved Standard Technical Specifications (ISTSs) to meet 10 CFR 50.36(c)(2)(ii) and 10 CFR 50.36(c)(3) requirements.

The licensee is using the guidance from the NUREG-1431, Revision 2, Standard Technical Specifications Westinghouse Plants (Reference 5), and WCAP-14483-A, Generic Methodology For Expanded Core Operating Limits Report. The licensee conforms to the guidance in NRC GL 88-16, Removal of Cycle-Specific Parameters Limits From Technical Specifications, and the staff-approved Technical Specification Task Force (TSTF) Travelers, TSTF-9, Revision 1, TSTF-339, Revision 2, and TSTF-363 (References 6, 7 and 8), which the staff approved for incorporation into the ISTSs. The licensee will be required to comply with 10 CFR 50.59 for any future changes to the COLR parameters after relocation.

3.0 TECHNICAL EVALUATION

NRC GL 88-16 sets forth a method for licensees to relocate cycle-specific values of operating parameters from TSs to the COLR, provided that the values are determined using an NRC-approved methodology which is referenced in TS Section 6.9. Examples of the values of such parameters that may be relocated to the COLR in accordance with GL 88-10 include moderator temperature coefficient, shutdown bank insertion limits, control bank insertion limits, axial flux difference limits, nuclear heat flux hot channel factor limit, nuclear enthalpy rise hot channel factor limit, refueling boron concentration limit, and shutdown margin. The staff has also approved WCAP-14483-A, which provides justification to relocate the departure from nucleate boiling (DNB) parameters of reactor coolant system (RCS) average temperature, RCS flow rate, and pressurizer pressure, as well as the overtemperature T (OT T) and overpower T (OP T) reactor trip setpoints values to the COLR for Westinghouse plants. The only condition stated in the staffs Safety Evaluation Report approving WCAP-14483-A is that minimum limits on RCS flow rate remain in the TSs. MP3 is a Westinghouse plant and the TSs retain a requirement for minimum RCS flow rate in TS 3/4.2.3. Accordingly, MP3 meets the conditions for applying WCAP-14483-A, and the analysis in it applies to the requested amendments.

Furthermore, the staff approved the TSTF Travelers, TSTF-9, Revision 1, TSTF- 339, Revision 2, and TSTF-363 for incorporation into the ISTSs, and the proposed TS changes are consistent with these TSTF travelers. Based on this information, the licensee proposed the following TS changes:

1. TS 2.2, Limiting Safety System Settings, Table 2.2-1."

The values of the OT T and OP T setpoint parameters are deleted from Note 1 and Note 3 of Table 2.2-1 and replaced with [*]. A note is added in the TS stating: The values denoted with [*] are specified in the COLR. This approach would allow these setpoints to be based on cycle-specific values of core design parameters, which are verified on a cycle-specific basis. The applicable NRC-approved setpoint methodology, WCAP-8745-P-A, Design basis for the Thermal Overpower T and Thermal Overtemperature T trip functions, September 1986, is referenced in TS Section 6.9.1.6 b. The requested change conforms to WCAP-14483-A and, therefore, the staff finds this TS change acceptable.

2. All SHUTDOWN MARGIN-related TS changes are discussed in this section to eliminate repetition.

A. S 3/4.1.1.1.1, Reactivity Control Systems, Boration Control, SHUTDOWN MARGIN-Modes 1 and 2.

The LCO Action Statement and Surveillance Requirements (SRs) would be modified to identify that the value of the Shutdown Margin required by TS is relocated and specified in the COLR.

B. TS 3/4.1.1.1.2, Reactivity Control Systems, Boration Control, SHUTDOWN MARGIN Modes 3, 4 and 5 Loops Filled.

The LCO and SR 4.1.1.1.2.1 would be modified to identify that the value of the Shutdown Margin required by TS is specified in the COLR. The cycle-specific values of Shutdown Margin requirements for this TS and Figures 3.1-1, 3.1-2, 3.1-3 and 3.1-4 are relocated to the COLR.

C. TS 3/4.1.1.2, Reactivity Control Systems, SHUTDOWN MARGIN-Cold Shutdown-Loops Not Filled.

This LCO would be modified by removing Figures 3.1-4 and 3.1-5 and relocating them to the COLR. SR 4.1.1.2.1 would be modified to identify that the value of the Shutdown Margin required by TS is specified in the COLR.

D. TS 3/4.3.5, Instrumentation, SHUTDOWN MARGIN Monitor.

The LCO references Figures 3.1-1, 3.1-2, 3.1-3, 3.1-4 and 3.1-5 which would be relocated to the COLR, as discussed in TS 3/4.1.1.1.2 and TS 3/4.1.1.2. Shutdown Margin is a cycle-specific variable similar to Moderator Temperature Coefficient, Rod Insertion Limits, Axial Flux Difference, Heat Flux Hot Channel Factor, and Nuclear Enthalpy Rise Hot Channel Factor, which are currently contained in the COLR.

The NRC-approved methodology for calculating Shutdown Margin is provided in WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, which is referenced in TS Section 6.9.1.6. Specifically, the values of these parameters must be calculated with the NRC-approved methodologies set forth in TS 6.9.1.6.b, and must be identified in the COLR. Furthermore, the licensee will comply with 10 CFR 50.59 for any future changes of the Shutdown Margin requirements to the extent that they are reflected in the UFSAR after they are relocated to the COLR.

These shutdown margin related TSs conform to WCAP-14483-A, and the staff finds them acceptable. This change will provide core design and operational flexibility that can be used for improved fuel management and to solve cycle-specific issues.

3. TS 3/4.2.5, Power Distribution Limits, DNB Parameters This LCO and SR 4.2.5 would be modified so that the DNB-related parameters which are listed in Table 3.2.1 would be relocated and specified in the COLR.

The DNB parameters (RCS average temperature and pressurizer pressure) are cycle-specific and the changes are consistent with the staff-approved WCAP-14483-A and TSTF-339-Revision 2. The RCS flow rate is a separate TS and will remain in TS 3/4.2.3. The proposed TS changes conform to WCAP-14483-A and, therefore, the staff finds them acceptable. The benefit of relocating these parameter limit values to the COLR is that it would allow licensees the flexibility to utilize available margins to increase cycle operating margins and/or improve core reload designs. This margin could also be used to offset any DNB penalties and address licensing issues, without the requirement of cycle-specific license amendments. The relocation of these selected TS limit values to the COLR will also result in a more complete COLR containing not only cycle-specific core reload related parameters, but also cycle-specific operating condition parameters.

4. TS 3/4.9.1.1, Refueling Operations, Boron Concentration.

The limit of 2600 ppm for the refueling boron concentration stated in the LCO and the Action Statement would both be relocated to the COLR.

The current TS 3/4.9.1.1 specifies an effective multiplication factor (Keff) shutdown margin limit of 0.95 and a boron concentration limit of 2600 ppm. The reload cycle analysis for each cycle includes the calculation of the minimum boron concentration corresponding to a Keff shutdown margin limit of 0.95. This value is a function of fuel burn-up, reactivity parameters and other cycle design conditions that will vary from cycle to cycle. The limit for the refueling boron concentration is calculated using an NRC-approved methodology which is described in WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology. This WCAP has been approved by the staff and is currently referenced in TS Section 6.9.1.6.b. The staff finds this acceptable because the boron concentration must be specified in the COLR, and the TS will require the continued use of the methodology in WCAP-9272-P-A to calculate refueling boron concentration.

5. TS Section 6.9.1.6.a, Core Operating Limits Report, Core Operating Limit.

TS Section 6.9.1.6.a would be updated to reflect the proposed TS changes. The proposed TS changes would add the OT T and OP T setpoint parameters, SHUTDOWN MARGIN, DNB parameters, and boron concentration to this TS to reflect the relocation of cycle-specific values to the COLR. These changes conform to the guidance in GL 88-16 and conforms to WCAP-14483-A. Accordingly, we find these changes acceptable.

6. TS Section 6.9.1.6.b, Core Operating Limits Report, The Analytical Methods Used to Determine the Core Operating Limits.

The proposed changes to this TS Section are to remove the revision number and date from the title of the WCAPs and add the following three new references:

WCAP-8301, LOCTA-IV Program: Loss-of-Coolant Transient Analysis.

WCAP-10054-P-A, Addendum 2, Addendum to the Westinghouse Small Break ECCS

[emergency core cooling system] Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop COSI Condensation Model.

WCAP-8745-P-A, Design Bases for the Thermal Overpower T and Thermal Overtemperature T Trip Functions, (Westinghouse Proprietary Class 2)

(Methodology for Specification 2.2.1).

Removal of the revision number and date from the title of topical reports would allow the licensee to use current topical reports to support limits in the COLR without having to submit an amendment to the facility operating license every time the topical report is revised. The licensee has stated that the COLR would provide specific information identifying the particular approved topical reports used to determine the core limits for a particular cycle.

For LOCA methodology WCAPs, removal of the revision number and date from the title of topical reports needs clarification. Different report numbers, titles, revision numbers, supplements, amendments, dates and other designations for LOCA methodologies identify specifically different LOCA methodologies. For LOCA codes, 10 CFR 50.46(a)(1) governs methods of calculating emergency core cooling system performance. The NRC staff reviews each revision, supplement, or amendment to these LOCA code topical reports in accordance with 10 CFR 50.46. If a new version of such a report is acceptable, the staff generically approves it for use at power reactors at which the conditions under which the report would be applied are within the ranges of the conditions for which the report is approved. These approved ranges of conditions, as understood at the time of review, are set forth in the reports and the associated NRC Safety Evaluations.

With regard to the LOCA methodologies listed above, the staff finds the specific relocations requested acceptable because relocation of the specific identifying information for these methodologies, which have been approved for MP3 without changing the identifying designations, will preserve the specific identifications of the methodologies and will not introduce unreviewed or unapproved methodologies. The specific identifying information for methodologies employed at MP3 is maintained in the COLR. The licensee has stated that changes to the COLR are controlled by their 10 CFR 50.59 program. Therefore, the staff finds that there is reasonable assurance that the licensee will employ only approved methodologies that the licensee determines apply to MP3, in that MP3 meets any conditions that the staff has imposed on those methodologies.

WCAP-8301 does not have separate approval by the staff; however, the staff reviewed WCAP-8301 in its review of WCAP-8471-P-A and accepted it. WCAP-8301 is also listed in NUREG-1031 (Reference 9) and was accepted for use at MP3. WCAP-10054-P-A, Addendum 2, is an approved topical report and, together with WCAP-8301, describes the most recent small-break LOCA analysis methodology. WCAP-8745-P-A accounts for a new DNB correlation, new fuel design and a new plant operating procedure at MP3 and generated the revised reactor trip setpoints. These three reports are included in TS Section 6.9.1.6.b of the COLR.

The proposed changes meet GL 88-16 and TSTF-363 guidelines.

The licensee revised the appropriate TS Bases to reflect these TS changes, and the staff does not object to these Bases changes.

The NRC staff has reviewed the proposed TS revisions for COLR implementation at MP3 and finds that these TS changes conform to GL 88-16 guidelines and conform to the generic changes analyzed in WCAP-14483-A. The values of parameters controlled by these changes are calculated by approved methodologies identified in the COLR, which are the same methodologies that would be used if these parameter values remained in the TSs. The licensee has no discretion to change these methodologies and may change how it determines whether or not revisions of them apply at MP3 only in accordance with 10 CFR 50.59.

Therefore, the NRC staff finds that the proposed changes follow and implement NRC-approved methodologies and these changes will not affect the availability or operation of the equipment used to mitigate design basis accidents. In addition, there will be no adverse effect on plant operation. Therefore, the NRC staff concludes that the proposed changes are acceptable.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the Connecticut 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 SRs.

The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any 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 (68 FR 28849). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). In addition, the amendment changes administrative procedures or requirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). 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 Commissions 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.

7.0 REFERENCES

1. Letter from William Matthews, Dominion Nuclear Connecticut, Inc., to the Nuclear Regulatory Commission, License Amendment Request to relocate some TS parameters to the COLR and Updating the Description of Analytical Methods Used to Determine Core Operating Limits, April 7, 2003.

2. Letter from J. Alan Price, Dominion Nuclear Connecticut, Inc., to the Nuclear Regulatory Commission, Response to Request for Additional Information for License Amendment to Relocate Some TS Parameters to the COLR, dated September 18, 2003.

3. US NRC Generic Letter 88-16. Removal of Cycle-Specific Parameter Limits from Technical Specifications, October 4, 1988.

4. WCAP-14483-A, Generic Methodology for Expanded Core Operating Limits Report, January 19, 2001.

5. NUREG-1431, Rev. 2, Standard Technical Specifications, Westinghouse Plants, June 2001.

6. Industry/TSTP Standard Technical Specification Change Traveler, TSTF-9, Rev. 1, Relocate Value for Shutdown Margin to COLR, January 1996.

7. TSTF-339, Rev. 2, Relocate TS Parameters to the COLR Consistent with WCAP-14483, March 1999.

8. TSTF-363, Revise Topical Report References in ITS 5.6.5, COLR, February 2000.

9. NUREG-1031, Safety Evaluation Report Related to the Operation of Millstone Nuclear Power Station, Unit 3, July 1984.

Principal Contributor: K. Desai Date: March 9, 2004