ML083360783

Issuance of Amendment Steam Line Isolation Function Applicability (Tac No. MD8544)

ML083360783
Person / Time
Site:	Kewaunee
Issue date:	01/09/2009
From:	Tam P Plant Licensing Branch III
To:	Christian D Dominion Energy Kewaunee
Tam P
References
TAC MD8544
Download: ML083360783 (10)

Text

UN!TED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 12, 2009 Mr. David A. Christian President and Chief Nuclear Officer Dominion Energy 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

KEWAUNEE POWER STATION -ISSUANCE OF AMENDMENT RE: STEAM LINE ISOLATION FUNCTION APPLICABILITY (TAC NO. MD8544)

Dear Mr. Christian:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 202 to Facility Operating License No. DPR-43 for the Kewaunee Power Station. This amendment revises the Technical Specifications (TS) in response to your application dated April 14, 2008, as supplemented by letter dated October 17, 2008.

The amendment adds a new footnote to Kewaunee TS Table 3.5-4, "Instrument Operating Conditions for Isolation Functions." The new footnote allows the main steam line isolation circuitry to be inoperable when both main steam isolation valvesare closed and deactivated.

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

Sincerely,

~~S'~

Pe~ ~~~, enior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305

Enclosures:

1. Amendment No. 202 to License No. DPR-43

2. Safety Evaluation cc w/encls: Distribution via ListServ

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 DOMINION ENERGY KEWAUNEE. INC.

DOCKET NO. 50-305 KEWAUNEE POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 202 License No. DPR-43

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

A. The application for amendment by Dominion Energy Kewaunee. Inc., dated April 4, 2008, as supplemented by letter dated October 17, 2008, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-43 is hereby amended to read as follows:

-2 (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 202, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

~0 ("(*c'Y'<,--"--:J Lois M. James, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License and Technical Specifications Date of Issuance: January 12, 2009

ATTACHMENT TO LICENSE AMENDMENT NO. 202 FACILITY OPERATING LICENSE NO. DPR-43 DOCKET NO. 50-305 Replace the following page of the Facility Operating License No. DPR-43 with the attached revised page. The changed area is identified by a marginal line.

REMOVE INSERT Page 3 Page 3 Replace the following page of Appendix A, Technical Specifications, with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

REMOVE INSERT Table TS 3.5-4, Page 1 Table TS 3.5-4, Page 1

C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR, Chapter I: (1) Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70, (2) is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect, and (3) is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 1772 megawatts (thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 202, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Fire Protection The licensee shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the licensee's Fire Plan, and as referenced in the Updated Safety Analysis Report, and as approved in the Safety Evaluation Reports, dated November 25, 1977, and December 12, 1978 (and supplement dated February 13, 1981) subject to the following provision:

The licensee may make changes to the approved Fire Protection Program without prior approval of the Commission, only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

(4) Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Nuclear Management Company Kewaunee Nuclear Power Plant Physical Security Plan (Revision 0)" submitted by letter dated October 18, as supplemented by letter dated October 21, 2004, July 26, 2005, and May 15, 2006.

(5) Deleted Amendment No. ~ 202 Revised by letter dated May 7, 200B, August 22, 200B 3

TABLE TS 3.5-4 INSTRUMENT OPERATING CONDITIONS FOR ISOLATION FUNCTIONS I I I 1 I 2 I 3 I 4 I 5 I 6 I OPERATOR ACTION NO. OF MINIMUM MINIMUM PERMISSIBLE IF CONDITIONS OF NO. OF CHANNELS OPERABLE DEGREE OF BYPASS COLUMN30R4 NO. FUNCTIONAL UNIT CHANNELS TO TRIP CHANNELS REDUNDANCY CONDITIONS CANNOT BE MET 1 Containment Isolation

a. Safety Injection Refer to Item NO.1 of Table TS 3.5-3 HOT SHUTDOWN(l)

b. Manual 2 1 1 - HOT SHUTDOWN 2 Steam Line Isolation

a. Hi-Hi Steam Flow with 1(3) 2/loop 1 - HOT SHUTDOWN(l)

Safety Injection

b. Hi Steam Flow and 2 .

1 1(3) - HOT SHUTDOWN!l) of 4 t.o-Lo T avg with 2/loop Safety Injection

c. Hi-Hi Containment 2(3) 3 2 - HOT SHUTDOWN(1)

Pressure

d. Manual 1/loop 1/loop 1/loop(3) - HOT SHUTDOWN (1) If minimum conditions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. steps shall be taken to place the plant in a COLD SHUTDOWN condition.

(3) Steam Line Isolation channels are not required to be operable when both main steam isolation valves are closed and deactivated.

Amendment No. 4-e2 202 Page 1 of 2

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHiNGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO AMENDMENT NO. 202 TO FACILITY OPERATING LICENSE NO. DPR-43 DOMINION ENERGY KEWAUNEE, INC.

KEWAUNEE POWER STATION DOCKET NO. 50-305

1.0 INTRODUCTION

By letter dated April 14, 2008 (Agencywide Document Access and Management System (ADAMS) Accession No. ML081060476), as supplemented by letter dated October 17, 2008 (Accession No. ML082950112) Dominion Energy Kewaunee, Inc. requested an amendment to Facility Operating License Number DPR-43 for Kewaunee Power Station. The proposed changes would add a new footnote to Kewaunee Technical Specifications (TS) Table 3.5-4, "Instrument Operating Conditions for Isolation Functions." The new footnote would allow the main steam line isolation circuitry to be inoperable when both main steam isolation valves (MSIVs) are closed and deactivated.

The supplement dated October 17, 2008, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination as published in the Federal Register on June 17, 2008 (73 FR 34340).

2.0 REGULATORY EVALUATION

The NRC staff considered the following regulatory requirements and guidance in reviewing the licensee's application:

Title 10 of the Code of Federal Regulations (10 CFR, Part 50), "Domestic Licensing of Production and Utilization Facilities," establishes the fundamental regulatory requirements with respect to the domestic licensing of nuclear production and utilization facilities. Specifically, Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 provides. in part, the necessary design, fabrication, construction, testing, and performance requirements for structures, systems, and components important to safety.

General Design Criterion (GDC)-13, "Instrumentation and Control," requires that instrumentation shall be provided to monitor variables and systems over their anticipated ranges for normal operation. for anticipated operational occurrences, and for accident conditions as appropriate to assure adequate safety, inclUding those variables and systems that can affect the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the Enclosure

-2 containment and its associated systems. Appropriate controls shall be provided to maintain these variables and systems within prescribed operating ranges.

GDC-20, "Protective System Functions," requires the protection system be designed (1) to initiate automatically the operation of appropriate systems includinq the reactivity control systems, to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences, and (2) to sense accident conditions and to initiate the operation of systems and components important to safety.

3.0 TECHNICAL EVALUATION

The engineered safety feature actuation system initiates necessary safety systems, based on the values of selected unit parameters, to protect against violating core design limits, to protect against violating the Reactor Coolant System pressure boundary, and to mitigate accidents.

Steam line isolation (SLI) instrumentation provides a signal to close the MSIVs, which provide protection in the event of a steam line break (SLB) inside or outside containment. Rapid isolation of the steam lines will limit the consequences of an SLB accident. For an SLB upstream of the MSIVs, inside or outside of containment, closure of the MSIVs limits the accident to only the blowdown from the affected steam generator. For an SLB downstream of the MSIVs, closure of the MSIVs terminates the accident as soon as the steam lines depressurize.

The licensee's proposed amendment to change the TS requirements associated with the SLI function would add footnote 3 to TS Table 3.5-4, "Instrument Operating Conditions for Isolation Functions". The footnote states:

Steam Line Isolation channels are not required to be operable when both main steam isolation valves are closed and de-activated.

The footnote would be added to the following functional units, under column 3, "Minimum Operable Channels":

a. Hi-Hi Steam Flow with Safety Injection

b. Hi Steam Flow and 2 of 4 Lo-Lo T avg with Safety Injection

c. Hi-Hi Containment Pressure

d. Manual When the MSIVs are closed and de-activated, their intended safety function is fulfilled and the SLI instrumentation has accomplished its function. Since the safety function has already been accomplished and no signal will be sent to open the MSIVs, further actuation of the SLI instrumentation is not required. Allowing the SLI channels to be inoperable when both MSIVs are closed and de-activated would not affect or limit the safety function of the SLI system.

The proposed amendment would not change any setpoint values, allowable values, or surveillance requirements associated with SLI. No physical change, modification or removal would be made to existing equipment, and no new equipment would be installed. The proposed amendment would not change the methods used to respond to accident conditions.

-3 The NRC staff has reviewed the licensee's proposed TS changes for SLI applicability. The NRC staff finds that the proposed changes to the TS as set forth above meet the requirements of 10 CFR Part 50 GDC-13 and GDC-20. Therefore, the proposed changes are acceptable.

4.0 STATE CONSULTATION

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

5.0 ENVIRONMENTAL CONSIDERATION

This amendment changes a requirement with respect to use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent 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 this amendment involves no significant hazards consideration and there has been no public comment on such finding (73 FR 34340). Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors: Samir Darbali, NRR Barry Marcus, NRR Date: January 12, 2009

January 12, 2009 Mr. David A. Christian President and Chief Nuclear Officer Dominion Energy 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

KEWAUNEE POWER STATION - ISSUANCE OF AMENDMENT RE: STEAM LINE ISOLATION FUNCTION APPLICABILITY (TAC NO. MD8544)

Dear Mr. Christian:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 202 to Facility Operating License No. DPR-43 for the Kewaunee Power Station. This amendment revises the Technical Specifications (TS) in response to your application dated April 14, 2008, as supplemented by letter dated October 17, 2008.

The amendment adds a new footnote to Kewaunee TS Table 3.5-4, "Instrument Operating Conditions for Isolation Functions." The new footnote allows the main steam line isolation circuitry to be inoperable when both main steam isolation valves are closed and deactivated.

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

Sincerely, IRAJ Peter S. Tam, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305

Enclosures:

1. Amendment No. 202 to License No. DPR-43

2. Safety Evaluation cc w/encls: Distribution via ListServ DISTRIBUTION:

PUBLIC RidsAcrsAcnw MailCTR Resource LPL3-1 rlf RidsNrrDirsltsb Resource RidsNrrDorlDpr Resource RidsOgcRp Resource RidsNrrDorlLpl3-1 Resource RidsNrrPMKewaunee Resource S. Darbali, NRR RidsNrrLABTully Resource RidsRgn3MailCenter Resource B. Marcus, NRR RidsNrrDeEicb Resource Accession No. ML083360783 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/EICB/BC OGC NRR/LPL3-1/BC NAME PTam BTuily WKemper* MSimon LJames DATE 12/19/08 12/16/08 11/20108 117/09 1/12/09

• SE transmitted by memo of 11/20108.

OFFICIAL RECORD COPY