ML093360443

License Amendment 241 Revision of High Radiation Area Controls

ML093360443
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	01/04/2010
From:	James Kim Plant Licensing Branch 1
To:	Entergy Nuclear Operations
kim j
References
TAC ME2187
Download: ML093360443 (13)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001

.Januarv 4, 2010 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: REVISION OF HIGH RADIATION AREA CONTROLS (TAC NO. ME2187)

Dear Sir or Madam:

The Commission has issued the enclosed Amendment No. 241 to Facility Operating License DPR-28 for the Vermont Yankee Nuclear Power Station, in response to your application dated August 26, 2009.

The amendment would revise the Technical Specification (TS) Section 6.5 that governs administrative controls of High Radiation Areas (HRA) to incorporate the HRA administrative controls contained within the Standard Technical Specifications, NUREG-1433, Revision 3.

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, 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. 241to License 1\\10. 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.241 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 August 26, 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.

- 2

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. 241, 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

~x:~

Nancy L. Salgado, Chief 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: January 4, 2010

ATTACHMENT TO LICENSE AMENDMENT NO. 241 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 257 257 257a 257b 258 258

- 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 No. 241 are hereby incorporated in the license. Entergy Nuclear Operations, Inc. shall 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 1\\10.226.

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.--200, 200, 22e,~,~, 2J..:t,~, 233, 234, 235,240,241

VYNPS 6.2 ORGANIZATION (Cont'd)

C.

Unit Staff Qualifications Each member of the unit staff shall meet or exceed the minimum qualifications of the American National Standards Institute N-18.1-1971, "Selection and Training of Personnel fo?Nuclear Power Plants," except for the radiation protection manager who shall meet the qualifications of Regulatory Guide 1.8, Revision 1 (September 1975) and the shift engineer, who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.

6.3 ACTION TO BE TAKEN IF A SAFETY LIMIT IS EXCEEDED Applies to administrative action to be followed in the event a safety limit is exceeded.

If a safety limit is exceeded, the reactor shall be shutdown immediately.

6.4 PROCEDURES Written procedures shall be established, implemented, and maintained covering the following activities:

A.

Normal startup, operation and shutdown of systems and components of the facility.

B.

Refueling operations.

C.

Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, suspected Primary System leaks and abnormal reactivity changes.

D.

Emergency conditions involving potential or actual release of radioactivity.

E.

Preventive and corrective maintenance operations which could have an effect on the safety of the reactor.

F.

Surveillance and testing requirements.

G.

Fire protection program implementation.

H.

Process Control Program in-plant implementation.

I.

Off-Site Dose Calculation Manual implementation.

6.5 HIGH RADIATION AREA As provided in paragraph 20.160l(c) of 10 CFR 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraphs 20.160l(a) and 20.1601(b) of 10 CFR 20:

A.

High Radiation Areas with dose rates greater than 0.1 rem/hour at 30 centimeters, but not exceeding 1.0 rem/hour at 30 centimeters from the' radiation source or from any surface penetrated by the radiation:

Amendment No. ~, ~, 43, ~ H-l, ~ -3:-++,.~ ~,241 257

VYNPS

1.

Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. *Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

2.

Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

3.

Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in.such areas.

4.

Each individual or group entering such an area shall possess:

a.

A radiation monitoring device that continuously displays radiation dose rates in the area, or

b.

A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or

c.

A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel r~diation exposure within the area, or

d.

A self-reading dosimeter (e.g., pocket ionization

.chamber or electronic dosimeter) and,

1.

Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or

2.

Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.

5.

Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted. personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does* not requiie ~

documentation prior to initial entry.

Amendment No. 241 257a

VYNPS B.

High Radiation Areas with dose rates greater than 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation, but less than 500 rads/hour at 1 meter from the radiation source or from any surface penetrated by the radiation:

1.

Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:

a.

All such door and gate keys shall be maintained under the administrative control of the shift supervisor, and/or radiation protection manager, or his or her designee.

b.

Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.

2.

Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

3.

Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

4.

Each individual or group entering such an area shall possess one of the following:

a.

A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or

b.

A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or

c.

A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and,

1.

Be under the surveillance, as specified ~n the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or Amendment No. 241 257b

VYNPS

2.

Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.

d.

In those cases where option Ib) and (cl, above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Acihievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.

5.

Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre~job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

6.

Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and.where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.

6.6 REPORTING REQUIREMENTS The following reports shall be submitted in accordance with 10 CFR 50.4.

A.

Deleted Amendment No. ~ ~, ~ ~ ~,241 258

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AME!\\IDMENT NO. 2bl 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 August 26, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092440704), Entergy Nuclear Operations, Inc. (the licensee) submitted a request to amend the Vermont Yankee Nuclear Power Station (Vermont Yankee) Technical Specification (TS) Section 6.5 to incorporate the standard high radiation area administrative controls specified in NUREG-1433, Revision 3, "Standard Technical Specifications General Electric Plants, BWR/4."

2.0 REGULATORY EVALUATION

Title 10 of the Code of Federal Regulations (10 CFR) Part 20.1601 (c) establishes a regulatory provision whereby licensees may apply to the Nuclear Regulatory Commission (NRC) for approval of alternate methods of controlling access to high radiation areas. NUREG-1433, Revision 3, "Standard Technical Specifications General Electric Plants, BWR/4" provides Standard Technical Specifications (STS) that are acceptable to the NRC. In Section 5.0, "Administrative Controls," an alternate method is provided for controlling high radiation areas that is acceptable to the NRC.

The proposed license amendment would allow the licensee to adopt these NUREG-1433 high radiation area controls with two minor changes for the purpose of clarification, and two spelling corrections. These proposed changes to the STS are evaluated below. The proposed changes do not alter the intent or the level of controls specified in the NUREG-1433, Revision 3, and are, therefore, acceptable.

3.0 TECHNICAL EVALUATION

The !\\IRC staff has evaluated the proposed license amendment as compared to the STS provided in NUREG-1433, Revision 3, Section 5.7, "High Radiation Area."

- 2 The requested modifications to the approved STS are as follows:

1. A modification to the title/heading of the licensee's TS in Administrative Control 6.5.A to clarify the lower bounding dose rates for a high radiation area. The modification would thus retain similar wording in the licensee's current TS that defines the lower bounds to the dose rates in a high radiation area. Although these additional words are redundant to the definition of a high radiation area, retaining this wording for the lower bounding dose rates for a high radiation area provides consistency with the licensee's current TS.

Specifically, the licensee proposes to clarify the heading in its TS Section 6.5.A by adding the following underlined text: "High Radiation Areas with dose rates greater than 0.1 rem/hour at 30 centimeters, but not exceeding 1.0 rem/hour at 30 centimeters from the radiation source or from any surface penetrated by the radiation." This revised wording is consistent with the definition of a High Radiation Area in 10 CFR 20 and does not change the intent of the administrative control specified in the STS.

2. The licensee's request also includes modifying Administrative Control 6.5.B.1.a to read "All such door and gate keys shall be maintained under the administrative control of the shift supervisor, and/or radiation protection manger, or his or her designee." The addition of the phrase "and/or" is a clarification that either, or both, the shift supervisor and the radiation protection manager are authorized to have administrative control of the keys for locked high radiation areas. This modification is consistent with the intent of the existing STS.

3. The licensee also requested a correction to the misspelling of the word "dose" in NUREG-1433 Section 5.7.1.d.4.(i) and 5.7.2.b.

4. In addition to the licensee requested changes, an administrative change/correction is being made by the NRC to the Standard Technical Specifications to incorporate the missing word "dose" in NUREG-1433 Section 5.7.2.d.1. Therefore, Administrative Control 6.5.B.4.a is provided such that the corrected text is "A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or"...

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 relates to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(1 0). 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.

- 3

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: Steve Garry Date: January 4, 2010

January 4,2010 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: REVISION OF HIGH RADIATION AREA CONTROLS (TAC NO. ME2187)

Dear Sir or Madam:

The Commission has issued the enclosed Amendment No. 241 to Facility Operating License DPR-28 for the Vermont Yankee Nuclear Power Station, in response to your application dated August 26,2009.

The amendment would revise the Technical Specification (TS) Section 6.5 that governs administrative controls of High Radiation Areas (HRA) to incorporate the HRA administrative controls contained within the Standard Technical Specifications, NUREG-1433, Revision 3.

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. 241 to License No. DPR-28

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

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• See memo dated November 16, 2009 OFFICE LPL1-1/PM LPL 1-1/LA IPAB/BC OGC LPL1-1/BC NAME JKim SLittie UShoop*

LSubin NSalgado DATE 12/09/09 12/09/09 11/16/2009 12/14/09 1/04/2010 OFFICIAL RECORD COpy