ML091610224

Issuance of Amendment Testing and Inspection of Suppression Chamber-To-Drywell Vacuum Breakers

ML091610224
Person / Time
Site:	Vermont Yankee
Issue date:	07/06/2009
From:	James Kim Plant Licensing Branch 1
To:	Entergy Nuclear Operations
kim j
References
TAC ME0767
Download: ML091610224 (11)

Text

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• • • • i' Site Vice President Entergy Nuclear Operations, Inc.

Vermont Yankee Nuclear Power Station P.O. Box 250 Governor Hunt Road Vernon, VT 05354 SUB,IECT: VERMONT YANKEE NUCLEAR POWER STATION -ISSUANCE OF AMENDMENT RE: TESTING AND INSPECTION OF SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS (TAC NO. ME0767)

Dear Sir or Madam:

The Commission has issued the enclosed Amendment No. 238 to Facility Operating License DPR-28 for the Vermont Yankee Nuclear Power Station, in response to your application dated February 24, 2009.

The amendment would revise the Technical Specification (TS) Surveillance Requirement (SR) that governs operability testing of the pressure suppression chamber-drywell vacuum breakers to incorporate the SR contained within the Standard Technical Specifications (STS), NUREG 1433 and delete the SR that requires inspection of the pressure suppression chamber-drywell vacuum breakers. This requirement is replaced with the STS SR 3.6.1.8.2 to perform operability testing within 12hours after the discharge of steam into the suppression chamber from the safety/relief valves or following operation that causes any of the vacuum breakers to open.

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

Sincerely,

/~~

f.' !

James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-271

Enclosures:

1. Amendment No.238 to License No. DPR-28

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

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENTERGY NUCLEAR VERMONT YANKEE, LLC AND ENTERGY NUCLEAR OPERATIONS, INC.

DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.23R License No. DPR-28

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

A. The application for amendment filed by Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. (the licensee) dated February 24,2009, 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.

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-28 is hereby amended to read as follows:

(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.238 ,are hereby incorporated in the license. Entergy Nuclear Operations, Inc. 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.

FOR THE NUCLEAR REGULATORY COMMISSION

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Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License and Technical Specifications Date of Issuance: July 6, 2009

ATTACHMENT TO LICENSE AMENDMENT NO. 238 FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-271 Replace the following page of the Facility Operating License with the attached revised page.

The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Insert 3 3 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 149 149 150 150

-3 E. Entergy Nuclear Operations, Inc., pursuant to the Act and 10 CFR Parts .30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility. .

3. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20. Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; 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 below:

A. Maximum Power Level Entergy Nuclear Operations, Inc. is authorized to operate the facility at reactor core power levels not to exceed 1912 megawatts thermal in accordance with the Technical Specifications (Appendix A) appended hereto.

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment N0238 are hereby incorporated in the license. Entergy Nuclear Operations, Inc. snail operate the facility in accordance with the Technical Specifications.

C. Reports Entergy Nuclear Operations, Inc. shall make reports in accordance with the requirements of the Technical Specifications.

D. This paragraph deleted by Amendment No. 226.

E. Environmental Conditions Pursuant to the Initial Decision of the presiding Atomic Safety and Licensing Board issued February 27, 1973, the following conditions for the protection of the environment are incorporated herein:

Amendment No,~, aos. aas, ~, aso, ~, ~, 233, 234, 235,23R

VYNPS 3.7 LIMITING CONDITIONS FOR 4.7 SURVEILLANCE REQUIREMENTS OPERATION line is verified to be closed and conditions required by 3.7.0.2 are met.

6. Pressure Suppression 6. Pressure Suppression Chamber - Drywell Vacuum Chamber - Drywell Vacuum Breakers Breakers

a. When primary a. Periodic Operability containment is Tests required, all suppression chamber Operability testing

- drywell vacuum of the* vacuum breakers shall be breakers shall be in operable except accordance with during testing and Specification 4.6.E as stated in and within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Specifications after any discharge

. 3.7.A.6.b and c, of steam to the below. Suppression suppression chamber chamber - drywell from the vacuum breakers safety/relief valves shall be considered and within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> operable if: following an operation that (1) The valve is causes any of the demonstrated vacuum breakers to to open fully open. Operability with the of the corresponding applied force position switches at all valve and position posi tions not in,dicators and exceeding alarms shall be that verified monthly and equivalent to following any 0.5 psi maintenance.

acting on the suppression b. Refuel~ng Outage chamber face Tests of the valve disk. (1) All suppression (2) The valve can chamber be closed by drywell gravity, when vacuum released breaker a f t e r ' being position opened by indication remote or and alarm manual means, systems shall to within not be calibrated greater than and the functionally equivalent of tested.

0.05 inch at all points. (2) Deleted along the seal surface of the disk.

Amendmen t No. ~; 238 149

VYNPS 3.7 'LIMITING CONDITIONS FOR 4.7 SURVEILLANCE REQUIREMENTS OPERATION (3) The position alarm system will annunciate in the control room if the valve opening exceeds the equivalent of 0.05 inch at all points along the seal surface of the disk.

b. Up to two (2) of the ( 3) A drywell to ten (10) suppression suppression chamber - drywell chamber leak vacuum breakers may rate test be determined to be shall inoperable provided demonstrate that they are' that ,with' an secured, or known to initial be, in the closed differential position. pressure of not less than

c. Reactor operation 1.0 psi, the may continue for differential fifteen (15) dayi pressure decay provided that at rate shall not' least one position exceed the alarm circuit for equivalent of each vacuum breaker the leakage is operable and each rate through a suppression chamber 1-inch

- drywell vacuum orifice.

breaker is physically verified to be closed immediately and daily thereafter.

7. Oxygen Concentration 7. Oxygen 'Concentration'

a. The primary The primary containment containment oxygen concentration shall atmosphere shall be be measured and recorded reduced to less on a weekly basis.

than 4 percent oxygen by volume with nitrogen gas while in the RUN MODE during 'the time period:

i. From 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after thermal power is greater than 15% rated thermal power following startup, to Amendment No. 1-9-, H-8-, ~,238 150

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.238 TO FACILITY OPERATING LICENSE NO. DPR-28 ENTERGY NUCLEAR VERMONT YANKEE, LLC AND ENTERGY NUCLEAR OPERATIONS, INC.

VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

1.0 INTRODUCTION

By application dated February 24, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090620391), Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. (the licensee) submitted a request to amend the Vermont Yankee Nuclear Power Station (Vermont Yankee or VY) Technical Specifications (TSs). The proposed change would modify the Vermont Yankee TSs Surveillance Requirements (SR) that govern testing of the pressure suppression chamber-to-drywell vacuum breakers. The proposed changes (1) incorporate the SR included in the boiling-water reactor (BWR) Standard Technical Specifications (STS) concerning testing of the vacuum breakers following any release of energy to the suppression pool, and (2) delete a requirement to inspect at least two suppression chamber-to-drywell vacuum breakers during each refueling outage.

2.0 REGULATORY EVALUATION

Vermont Yankee Principal Design Criterion 11 states:

It shall be possible to test primary containment integrity and leak tightness on a periodic basis.

The purpose of the suppression chamber-to-drywell vacuum breakers is to ensure structural integrity of the primary containment by limiting the pressure difference between the suppression chamber and the drywell.

Vermont Yankee has ten suppression chamber-to-drywell vacuum breakers. Operation may continue with two of these inoperable provided that they are secured or known to be in the closed position (Vermont Yankee TS 3.7.6.b).

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3.0 TECHNICAL EVALUATION

Vermont Yankee SR 4.7.A.6.a requires operability testing of the vacuum breakers "and following any release of energy to the suppression chamber." Since some releases of steam to the suppression chamber do not cause actuation of the vacuum breakers, this requirement is overly conservative. The licensee proposes to replace this requirement with the STS SR 3.6.1.8.2 to perform operability testing within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the discharge of steam into the suppression chamber from the safety/relief valves (SRVs) or following operation that causes any of the vacuum breakers to open. This change is acceptable since it requires testing for any event which causes the vacuum breakers to open or an event (opening of SRVs) which has a reasonable likelihood to result in opening the suppression chamber-to-drywell vacuum breakers.

Reducing unnecessary testing reduces vacuum breaker wear.

The licensee's justification for this change states:

Operability testing of the suppression chamber-to-drywell vacuum breakers will continue to be performed on a quarterly basis in accordance with the VY Inservice Testing Program. Operability testing of the corresponding position switches and position indicators in accordance with SR 4.7.A.6.a will continue to be required on a monthly basis and following any maintenance. [... ]

For these reasons, the Nuclear Regulatory Commission (NRC) staff finds the proposed change to the STS requirements to be acceptable. .

SR 4.7.A.6.b.(2) requires at least two suppression chamber-to-drywell vacuum breakers to be inspected each refueling outage. The licensee proposes to delete this requirement based on a review of inspections performed since 1996 that revealed no significant deficiencies that required entry into the Vermont Yankee Corrective Action Program. This periodic disassembly results in worker radiation dose and wear on vacuum breaker components. This requirement is not included in the BWR/4 STS. Therefore, the NRC staff finds this deletion to be acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Vermont 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 surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in 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 (74 FR 15770). 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.

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

Principal Contributor: Richard Lobel Date: July 6, 2009

July 6,2009 Site Vice President Entergy Nuclear Operations, Inc.

Vermont Yankee Nuclear Power Station P.O. Box 250 Governor Hunt Road Vernon, VT 05354

SUBJECT:

VERMONT YANKEE NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE: TESTING AND INSPECTION OF SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS (TAC NO. ME0767)

Dear Sir or Madam:

The Commission has issued the enclosed Amendment No. 238 to Facility Operating License DPR-28 for the Vermont Yankee Nuclear Power Station, in response to your application dated February 24, 2009.

The amendment would revise the Technical Specification (TS) Surveillance Requirement (SR) that governs operability testing of the pressure suppression chamber-drywell vacuum breakers to incorporate the SR contained within the Standard Technical Specifications (STS), NUREG 1433 and delete the SR that requires inspection of the pressure suppression chamber-drywell vacuum breakers. This requirement is replaced with the STS SR 3.6.1.8.2 to perform operability testing within 12hours after the discharge of steam into the suppression chamber from the safety/relief valves or following operation that causes any of the vacuum breakers to open.

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

Sincerely, IRA!

James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-271

Enclosures:

1. Amendment No. 238 to License No. DPR-28

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

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