ML080070540

Issuance of Amendment Two Control Room Ventilation Subsystem Inoperable Per TSTF-477

ML080070540
Person / Time
Site:	Monticello
Issue date:	01/23/2008
From:	Tam P NRC/NRR/ADRO/DORL/LPLIII-1
To:	O'Connor T Nuclear Management Co
Peter Tam, NRR/DORL 415-1451
Shared Package
ML080240068	List: ML080070540 ML080240085
References
TAC MD6770
Download: ML080070540 (10)

Text

January 23, 2008 Timothy J. O=Connor Site Vice President Monticello Nuclear Generating Plant Nuclear Management Company, LLC 2807 West County Road 75 Monticello, MN 55362-9637

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT - ISSUANCE OF AMENDMENT RE: TWO INOPERABLE CONTROL ROOM VENTILATION SUBSYSTEMS USING THE GUIDANCE OF TSTF-447 (TAC NO. MD6770)

Dear Mr. O=Connor:

The Commission has issued the enclosed Amendment No. 154 to Renewed Facility Operating License No. DPR-22 for Monticello Nuclear Generating Plant (MNGP), in response to your application dated September 17, 2007.

The amendment revised Technical Specifications Section 3.7.5 to specify the conditions and required actions associated with two control room ventilation subsystems inoperable. The revised Section 3.7.5 follows Technical Specifications Task Force (TSTF) Change Traveler TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems.

A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.

Sincerely,

/RA/

Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263

Enclosures:

1. Amendment No. 154 to DPR-22

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

Timothy J. O=Connor Site Vice President Monticello Nuclear Generating Plant Nuclear Management Company, LLC 2807 West County Road 75 Monticello, MN 55362-9637

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT - ISSUANCE OF AMENDMENT RE: TWO INOPERABLE CONTROL ROOM VENTILATION SUBSYSTEMS USING THE GUIDANCE OF TSTF-447 (TAC NO. MD6770)

Dear Mr. O=Connor:

The Commission has issued the enclosed Amendment No. 154 to Renewed Facility Operating License No. DPR-22 for Monticello Nuclear Generating Plant (MNGP), in response to your application dated September 17, 2007.

The amendment revised Technical Specifications Section 3.7.5 to specify the conditions and required actions associated with two control room ventilation subsystems inoperable. The revised Section 3.7.5 follows Technical Specifications Task Force (TSTF) Change Traveler TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems.

A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.

Sincerely,

/RA/

Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263

Enclosures:

1. Amendment No. 154 to DPR-22

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

PUBLIC LPL3-1 r/f RidsNrrDorlLpl3-1 RidsNrrPMPTam RidsNrrLATHarris RidsOGCRp RidsAcrsAcnwMailCenter RidsNrrDirsltsb G. Hill, OIS A. Lising, NRR RidsRgn3MailCenter RidsNrrDorlDpr Package Accession No.: ML080240068 Amendment Accession No.: ML080070540 TS Pages Accession No.: ML080240085 OFFICE LPL3-1/PM LPL-1/LA TSB/BC OGC/NLO w/comments LPL3-1/(A)BC NAME PTam THarris TKobetz* MSmith PMilano DATE 1/15/08 1/15/08 11/15/07* 1/18/08 1/ 23/08

• SE transmitted by memo of 11/15/07.

OFFICIAL RECORD COPY

NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No.154 License No. DPR-22

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

A. The application for amendment by Nuclear Management Company, LLC (the licensee), dated September 17, 2007, 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-22 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 154 are hereby incorporated in the license. NMC 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 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Patrick D. Milano, Acting Chief Plant Licensing Branch III-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 23, 2008

ATTACHMENT TO OPERATING LICENSE AMENDMENT NO. 154 RENEWED FACILITY OPERATING LICENSE NO. DPR-22 DOCKET NO. 50-263 Replace the following page of Renewed Facility Operating License DPR-22 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 Page 3 Page 3 Replace the following pages of Appendix A (Technical Specifications): The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

REMOVE INSERT 3.7.5-1 3.7.5-1 3.7.5-2 3.7.5-2

2. Pursuant to the Act and 10 CFR Part 70, NMC to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operations, as described in the Final Safety Analysis Report, as supplemented and amended, and the licensee=s filings dated August 16, 1974 (those portions dealing with handling of reactor fuel) and August 17, 1977 (those portions dealing with fuel assembly storage capacity);

3. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NMC to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;

4. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NMC to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and

5. Pursuant to the Act and 10 CFR Parts 30 and 70, NMC to possess, but not separate, such byproduct and special nuclear material as may be produced by operation of the facility.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission=s regulations in 10 CFR Chapter I and 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 is subject to the additional conditions specified or incorporated below:

1. Maximum Power Level NMC is authorized to operate the facility at steady state reactor core power levels not in excess of 1775 megawatts (thermal).

2. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 154, are hereby incorporated in the license. NMC shall operate the facility in accordance with the Technical Specifications.

3. Physical Protection NMC shall implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Renewed License No. DPR-22 Amendment No. 1 thru 154

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 154 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-22 NUCLEAR MANAGEMENT COMPANY, LLC MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263

1.0 INTRODUCTION

By letter dated September 17, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML070460545), Nuclear Management Company, LLC (the licensee) submitted an application for amendment regarding Monticello Nuclear Generating Plant (MNGP)

Technical Specifications (TS). The proposed amendment would adopt Technical Specifications Task Force (TSTF) Change Traveler TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems, which was proposed by the TSTF by letter on September 8, 2006 (Agencywide Document Access and Management System (ADAMS) Accession No. ML062510321). TSTF-477 revised Standard Technical Specification (STS) 3.7.4 Control Room Air Conditioning (AC) System by adding the following TS Action Requirements:

CONDITION REQUIRED ACTION COMPLETION TIME B.1 Verify control room area Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B. Two [control room AC] Temperature, <90F.

subsystems inoperable AND B.2 Restore one [control room AC] 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> subsystem to OPERABLE status The Nuclear Regulatory Commission (NRC) announced the availability of TSTF-477, Revision 3, in the Federal Register on March 26, 2007 (72 FR 14143) as part of its consolidated line item improvement process (CLIIP).

MNGP proposed the following variations from the TS changes described in TSTF-477, Revision 3. TSTF-477, Revision 3, refers to the control room air conditioning (AC) system and the control room AC subsystems. The corresponding nomenclature at MNGP are the control room ventilation system and the control room ventilation subsystems. These variations in

terminology have no impact on the NRC staffs regulatory evaluation or technical evaluation published in the model safety evaluation (SE) dated December 18, 2006 (71 FR 75774), and are, therefore, acceptable differences.

The following two sections, Regulatory Evaluation and Technical Evaluation, are substantially reproduced from the NRC staffs model SE (71 FR 75775, dated December 18, 2006), with minor word changes to match MNGPs nomenclature and specific conditions.

2.0 REGULATORY EVALUATION

Section 182(a) of the Atomic Energy Act (the Act) requires applicants for nuclear power plant operating licenses to include TS as part of the license. The TS ensures the operational capability of structures, systems, and components that are required to protect the health and safety of the public. The Commissions regulatory requirements related to the content of the TS are contained in 10 CFR Section 50.36. That regulation requires that the TS include items in the following specific categories: (1) safety limits, limiting safety systems settings, and limiting control settings (50.36(d)(1)); (2) Limiting Conditions for Operation (50.36(d)(2));

(3) Surveillance Requirements (50.36(d)(3)); (4) design features (50.36(d)(4)); and (5) administrative controls (50.36(d)(5)).

In general, there are two classes of changes to the TS: (1) changes needed to reflect modifications to the design basis (TS are derived from the design basis), and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content and preferred format of TS over time. This amendment deals with the second class of changes.

In determining the acceptability of revising control room ventilation subsystem TS, the NRC staff used the accumulation of generically approved guidance in NUREG-1433, Standard Technical Specifications, Revision 3, General Electric Plants, BWR/4, dated June, 2004 (BWR/4 STS).

Licensees may revise the TS to adopt current improved STS (iSTS) format and content provided that plant-specific review supports a finding of continued adequate safety because: (1)

The change is editorial, administrative or provides clarification (i.e., no requirements are materially altered), (2) the change is more restrictive than the licensees current requirement, or (3) the change is less restrictive than the licensees current requirement, but nonetheless still affords adequate assurance of safety when judged against current regulatory standards. The detailed application of this general framework, and additional specialized guidance, are discussed in Section 3.0 below in the context of the licensees specific proposed changes.

3.0 TECHNICAL EVALUATION

The BWR STS for the Control Room Air Conditioning AC System do not contain an action statement for two inoperable subsystems. During the TS conversion of the BWR/6 plants, the BWR/6 plants adopted action statements for the ventilation and AC systems that contained action statements for 2 inoperable subsystems similar to the proposed action statements in TSTF-477. The STS for numerous safety-related systems also contain action statements for two inoperable subsystems. The TSTF proposed to add an Action Condition for 2 inoperable control room AC subsystems to the BWR STS in order to be consistent with the BWR/6 current iSTS. Furthermore, the consistency of the BWR STS will be enhanced since most safety-related systems currently have action statements in the STS to address two inoperable subsystems.

3.1 Action Requirements for 2 Inoperable Control Room Ventilation Subsystems The licensees proposed Condition, Required Action, and Completion Time would allow 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore 1 subsystem to the operable status for the TS condition of 2 inoperable subsystems. During the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time the control room area temperature is verified to be <90 degrees every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. If 1 control room ventilation subsystem can not be restored to operable status or the control room area temperature can not be maintained to be <90 degrees, then the unit must be placed in at least Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Mode 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Maintaining the control room area temperature <90 degrees assures that the safety-related equipment in the control room area will remain within the original licensed design operating temperature, because the maximum allowable control room area temperature is unchanged by TSTF-477. The NRC staff finds that the proposed changes in TSTF-477 are acceptable for MNGP because the changes per TSTF-477 provide TS requirements that the control room area temperature will be maintained within the original licensed design operating temperature of the control room area equipment or the plant will be placed in the Cold Shutdown Mode (Mode 4, Safe Shutdown Condition).

4.0 STATE CONSULTATION

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

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes the requirements with respect to use of facility components located within the restricted area as defined in 10 CFR Part 20, and changes the associated 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 increase in individual or cumulative occupational radiation exposure. The NRC staff has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (72 FR 62689). Accordingly, the 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 the amendment.

6.0 CONCLUSION

The NRC staff 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 the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: A. J. Lising, NRR Date: January 23, 2008

Monticello Nuclear Generating Plant cc:

Jonathan Rogoff, Esquire Commissioner Vice President, Counsel & Secretary Minnesota Department of Commerce Nuclear Management Company, LLC 85 7th Place East, Suite 500 700 First Street St. Paul, MN 55101-2198 Hudson, WI 54016 Manager - Environmental Protection U.S. Nuclear Regulatory Commission Division Resident Inspector's Office Minnesota Attorney General=s Office 2807 W. County Road 75 445 Minnesota St., Suite 900 Monticello, MN 55362 St. Paul, MN 55101-2127 Manager, Nuclear Safety Assessment Michael B. Sellman Monticello Nuclear Generating Plant President and Chief Executive Officer Nuclear Management Company, LLC Nuclear Management Company, LLC 2807 West County Road 75 700 First Street Monticello, MN 55362-9637 Hudson, MI 54016 Commissioner Nuclear Asset Manager Minnesota Pollution Control Agency Xcel Energy, Inc.

520 Lafayette Road 414 Nicollet Mall, R.S. 8 St. Paul, MN 55155-4194 Minneapolis, MN 55401 Commissioner Dennis L. Koehl Minnesota Department of Health Chief Nuclear Officer 717 Delaware Street, S. E. Nuclear Management Company, LLC Minneapolis, MN 55440 700 First Street Hudson, WI 54016 Douglas M. Gruber, Auditor/Treasurer Wright County Government Center 10 NW Second Street Buffalo, MN 55313