Text

Issuance of Amendment No. 227, Request to Adopt Technical Specification Task Force (TSTF)-477, Revision 3, Adding an Action Statement for Two Inoperable Control Room Air Conditioning Subsystem
	ML14010A030
Person / Time
Site:	Columbia
Issue date:	02/11/2014
From:	Lyon C; Plant Licensing Branch IV
To:	Reddeman M; Energy Northwest
	Lyon C
References
	TAC MF2528
	Download: ML14010A030 (12)
	v • d • e

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 11, 2014 Mr. Mark E. Reddemann Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023)

Richland, WA 99352-0968

SUBJECT:

COLUMBIA GENERATING STATION -ISSUANCE OF AMENDMENT RE:

ADOPT TSTF-477, ADD ACTION STATEMENT FOR TWO INOPERABLE CONTROL ROOM AIR CONDITIONING SUBSYSTEMS (TAG NO. MF2528)

Dear Mr. Reddemann:

The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 227 to Renewed Facility Operating License No. NPF-21 for the Columbia Generating Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated July 25, 2013.

The amendment changes the TS 3.7.4, "Control Room Air Conditioning (AC) System,"

requirements by revising the Required Action and associated Completion Time for two inoperable control room air conditioning subsystems. The proposed changes are consistent with NRC-approved TS Task Force (TSTF) change traveler TSTF-477, Revision 3. The availability of this TS improvement was announced in the Federal Register on March 26, 2007 (72 FR 14143), as part of the consolidated line item improvement process.

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

Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397

Enclosures:

1. Amendment No. 227 to NPF-21

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

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENERGY NORTHWEST DOCKET NO. 50-397 COLUMBIA GENERATING STATION AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 227 License No. NPF-21

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

A. The application for amendment by Energy Northwest (licensee), dated July 25, 2013, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's 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.

Enclosure 1

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 Renewed Facility Operating License No. NPF-21 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. 227 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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

FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License No. NPF-21 and Technical Specifications Date of Issuance: February 11, 2014

ATTACHMENT TO LICENSE AMENDMENT NO. 227 RENEWED FACILITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the following pages of the Renewed Facility Operating License No. NPF-21 and Appendix A, Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Facility Operating License REMOVE INSERT Technical Specification REMOVE INSERT 3.7.4-1 3.7.4-1 3.7.4-2 3.7.4-2

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 227 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

a. For Surveillance Requirements (SRs) not previously performed by existing SRs or other plant tests, the requirement will be considered met on the implementation date and the next required test will be at the interval specified in the Technical Specifications as revised in Amendment No. 149.

(3) Deleted.

(4) Deleted.

(5) Deleted.

(6) Deleted.

(7) Deleted.

(8) Deleted.

(9) Deleted.

(10) Deleted.

(11) Shield Wall Deferral (Section 12.3.2, SSER #4, License Amendment #7)

The licensee shall complete construction of the deferred shield walls and window as identified in Attachment 3, as amended by this license amendment.

( 12) Deleted.

(13) Deleted.

The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

Renewed License No. NPF-21 Amendment No. 227

Control Room AC System 3.7.4 3.7 PLANT SYSTEMS 3.7 .4 Control Room Air Conditioning (AC) System LCO 3.7.4 Two control room AC subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2. and 3, During operations whh a potentlal for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One control room AC A.1 Restore control room AC 30days subsystem Inoperable. subsystem to OPERABLE status.

B. Two control room AC B.1 Verify control room area Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months subsystems inoperable. temperature < gooF.

AND B.2 Restore one control room 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AC subsystem to OPERABLE status.

c. Required Action and C.1 Be In MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, or3. C.2 Be in MODE4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. Required Action and 0.1 Place OPERABLE control Immediately associated Completion room AC subsystem in Time of Condition A not operation.

met during OPORVs.

QB.

0.2 Initiate action to suspend Immediately OPORVs.

Columbia Generating Station 3.7.4-1 Amendment No. 4-69,499 225 227

Control Room AC System 3.7.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Initiate action to suspend Immediately associated Completion OPDRVs.

Time of Condition B not met during OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify each control room AC subsystem has the 24 months capability to remove the assumed heat load.

Columbia Generating Station 3.7.4-2 Amendment No. 489,4Q9 ~ 227

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 227 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-21 ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NO. 50-397

1.0 INTRODUCTION

By application dated July 25, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13247A659), Energy Northwest (the licensee) requested changes to the Technical Specifications (TSs; Appendix A to Renewed Facility Operating License No. NPF-21) for the Columbia Generating Station (CGS). The requested change would change the CGS TS 3.7.4, "Control Room Air Conditioning (AC) System," requirements by revising the Required Action and associated Completion Time for two inoperable control room air conditioning subsystems. The proposed changes are consistent with U.S. Nuclear Regulatory Commission (NRC)-approved TS Task Force (TSTF) change traveler TSTF-477, Revision 3.

The availability of this TS improvement was announced in the Federal Register on March 26, 2007 (72 FR 14143), as part of the consolidated line item improvement process (CUI P).

TSTF-477, Revision 3, revised Standard Technical Specification 3.7.5, "Control Room Air Conditioning (AC) System," by adding the following TS Actions Condition:

CONDITION REQUIRED ACTION COMPLETION TIME B. Two [control room AC] 8.1 Verify control room area Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months subsystems inoperable Temperature< 90°F.

AND 8.2 Restore one [control room AC] 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem to OPERABLE status The licensee did not propose changes or variations from the TS changes described in TSTF-477, Revision 3.

Enclosure 2

2.0 REGULATORY EVALUATION

Section 182a of the Atomic Energy Act (the "Act") requires applicants for nuclear power plant operating licenses to include TS as part of the license application. The TS must be sufficient enable the Commission to find that the utilization of special nuclear material will be in accord with the common defense and security and will provide adequate protection to the health and safety of the public. The Commission's regulatory requirements related to the content of the TS are contained in Section 50.36(c} of Title 10 of the Code of Federal Regulations (10 CFR}. That regulation requires that the TS include, among other things, items in the following categories:

(1} safety limits, limiting safety systems settings, and limiting control settings (50.36(c)(1 )}; (2}

limiting conditions for operation (50.36(c)(2)); (3) surveillance requirements (50.36(c)(3; (4) design features (50.36(c}(4}); and (5) administrative controls (50.36(c}(5}). Pursuant to 10 CFR 50.92(a), in determining whether an amendment to a license will be issued to the applicant, the Commission will be guided by the considerations which govern the issuance of initial licenses to the extent applicable and appropriate. In determining the acceptability of revising Control Room Air Conditioning (AC) System TS, the NRC staff used the accumulation of generically approved guidance in NUREG-1433, "Standard Technical Specifications, Revision 4, General Electric Plants, BWR/4," dated April 2012 (BWR/4 STS}. CGS is classified as a boiling water reactor 5 (BWR/5) plant. While CGS TS 3.7.4 is based on NUREG-1434, "Standard Technical Specifications General Electric Plants, BWR/6," the proposed changes by the licensee are modeled after changes made to STS 3.7.5 for BWR/4 in TSTF-477. Because TSTF-477 provides technical justification for the addition of an allowed outage time of 72 hours, versus 7 days as provided for the BWR/6 plants, this is a more conservative adoption of the TSTF-477 change. The proposed changes are consistent with the plant design, and are therefore acceptable. Licensees may request to revise their TS to adopt current STS format and content by fully describing the changes desired, and following as far as applicable, the form prescribed for original applications. To issue the amendment, the Commission must find, to the extent applicable and appropriate, that the facility will operate in conformity with the application as amended, the provisions of the Act, and the rules and regulations of the Commission, there is reasonable assurance that the activities authorized by the operating license can be conducted without endangering the health and safety of the public, and there is reasonable assurance that such activities will be conducted in compliance with the regulations in this chapter; and the issuance of the amended license will not be inimical to the common defense and security or to the health and safety of the public

3.0 TECHNICAL EVALUATION

The Control Room AC System provides temperature control for the control room following isolation of the control room. The Control Room AC System consists of two independent, redundant subsystems that provide cooling and heating of recirculated control room air. Each subsystem consists of heating coils, cooling coils, fans, chillers, compressors, ductwork, dampers, and instrumentation and controls to provide for control room temperature control. The Control Room AC System is designed to provide a controlled environment under both normal and accident conditions. The design basis of the Control Room AC System is to maintain the control room temperature for a 30 day continuous occupancy. During emergency operation, the

Control Room AC System maintains a habitable environment and ensures the OPERABILITY of components in the control room. Prior to TSTF-477, the required content of the BWR/4 STS for the Control Room AC system did not contain an Action Condition for two inoperable subsystems. During the TS conversion of the BWR/6 Plants, the BWR/6 Plants adopted Action Conditions for the ventilation and AC systems that contained Condition descriptions and Requirements for two inoperable subsystems similar to those proposed in TSTF-477. This is consistent with numerous other safety-related systems in the STS which also contain Action Conditions for two inoperable subsystems. TSTF-477 proposed to add a new Action Condition for two inoperable Control Room AC subsystems to the BWR/4 STS in order to be consistent with the BWR/6 STS. The licensee proposes to implement TSTF-477, Revision 3, by revising the Actions of TS 3.7.4, "Control Room Air Conditioning (AC) System," to provide a new Action when both Control Room AC subsystems are inoperable. The new Action allows 72 hours to restore one Control Room AC subsystem to operable status and requires verification that control room temperature is maintained less than(<) 90 degrees Fahrenheit (°F) once every 4 hours. 3.1 Actions Condition for Two Inoperable Control Room Ventilation Subsystems The proposed boiling-water reactor Condition, Required Action, and Completion Time allows 72 hours to restore one subsystem to the operable status for the TS condition of two inoperable subsystems. During the 72-hour completion time, the control room area temperature is verified < 90 oF every 4 hours. If one control room ventilation subsystem cannot be restored to operable status or the control room area temperature cannot be maintained< 90 °F, then the unit must be placed in at least MODE 3 within 12 hours and MODE 4 within 36 hours. Maintaining the control room area temperature < 90 oF 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 concludes that the proposed changes in TSTF-477 are acceptable for CGS, because TSTF-477 changes 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 Washington 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 the installation or 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 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

published in the Federal Register on October 29, 2013 (78 FR 64544). 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 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) there is reasonable assurance that 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: M. Hamm, NRR/DSS/STSB Date: February 11, 2014

ML14010A030 *via email **Memo dated OFFICE NRR/DORLILPL4-1/PM NRR/DORLILPL4-1/LA* NRR/DSS/STSB/BC**

NAME FLyon JBurkhardt REIIiott DATE 1/13/14 1/10/14 1/13/14 OFFICE OGC- NLO NRR/DORLILPL4-1/BC NRR/DORLILPL4-1/PM NAME DRoth MMarkley Flyon DATE 2/10/14 2/11/14 2/11/14}}

v t e Letter Sequence Approval
TAC:MF2528, Add Action for Two Inoperable Control Room AC Subsystems (Approved, Closed)
Initiation Request Acceptance Administration Questions Answers Results Approval Other:
MONTHYEAR2013-09-23 [Table View]

ML14010A030