ML070250523

License Amendment, Modified Technical Specification Regarding Containment Airlock Surveillance Frequency (Technical Specification Change No. 84)

ML070250523
Person / Time
Site:	Three Mile Island
Issue date:	02/07/2007
From:	Kristina Banovac NRC/FSME/DWMEP/DURLD
To:	Leidich G FirstEnergy Nuclear Operating Co
bANOVAC k (415-5114)
References
Download: ML070250523 (10)

Text

February 7, 2007 Mr. Gary Leidich President & Chief Nuclear Officer First Energy Nuclear Operating Corp.

76 South Main Street Akron, OH 44308

SUBJECT:

THREE MILE ISLAND NUCLEAR STATION, UNIT 2 - ISSUANCE OF LICENSE AMENDMENT MODIFYING TECHNICAL SPECIFICATION REGARDING CONTAINMENT AIRLOCK SURVEILLANCE FREQUENCY (TECHNICAL SPECIFICATION CHANGE NO. 84)

Dear Mr. Leidich:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 61 to Facility Possession-Only License No. DPR-73 for the Three Mile Island Nuclear Station, Unit 2.

This amendment is in response to your application dated October 10, 2006.

This amendment approves your proposed revision to the Technical Specification Surveillance Requirement 4.1.1.3 to extend the containment airlock surveillance frequency from once per year to once every five years.

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

Sincerely,

/RA/

Kristina L. Banovac, Project Manager Reactor Decommissioning Branch Decommissioning & Uranium Recovery Licensing Directorate Division of Waste Management and Environmental Protection Office of Federal and State Materials and Environmental Management Programs Docket No.: 50-320 License No.: DPR-73

Enclosures:

1. Amendment No. 61 to DPR-73

2. Safety Evaluation Report cc: See next page

February 7, 2007 Mr. Gary Leidich President & Chief Nuclear Officer First Energy Nuclear Operating Corp.

76 South Main Street Akron, OH 44308

SUBJECT:

THREE MILE ISLAND NUCLEAR STATION, UNIT 2 - ISSUANCE OF LICENSE AMENDMENT MODIFYING TECHNICAL SPECIFICATION REGARDING CONTAINMENT AIRLOCK SURVEILLANCE FREQUENCY (TECHNICAL SPECIFICATION CHANGE NO. 84)

Dear Mr. Leidich:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 61 to Facility Possession-Only License No. DPR-73 for the Three Mile Island Nuclear Station, Unit 2. This amendment is in response to your application dated October 10, 2006.

This amendment approves your proposed revision to the Technical Specification Surveillance Requirement 4.1.1.3 to extend the containment airlock surveillance frequency from once per year to once every five years.

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

Sincerely,

/RA/

Kristina L. Banovac, Project Manager Reactor Decommissioning Branch Decommissioning & Uranium Recovery Licensing Directorate Division of Waste Management and Environmental Protection Office of Federal and State Materials and Environmental Management Programs Docket No.: 50-320 License No.: DPR-73

Enclosures:

1. Amendment No. 61 to DPR-73

2. Safety Evaluation Report cc: See next page DISTRIBUTION:

DURLD r/f RidsRgn1MailCenter DOrlando QGan ML070250523 OFFICE DWMEP:PM DWMEP:LA DWMEP:BC OGC DWMEP:DD NAME KBanovac TMixon CCraig EWilliamson KMcConnell for FCameron DATE 01/29/07 01/29/07 01/29/07 01/31/07 02 /07/07 OFFICIAL RECORD COPY

cc.: Three Mile Island Service List Mr. Eric Epstein Mr. David W. Jenkins, Esq.

EFMR Monitoring Group First Energy Legal Department 4100 Hillsdale Road 76 South Main St.

Harrisburg, PA 17112 Akron, OH 44308 Mr. David J. McGoff Chairperson Office of LWR Safety and Technology Dauphin County Board of Commissioners NE-23 Dauphin County Courthouse U.S. Department of Energy Front and Market Streets Washington, DC 20545 Harrisburg, PA 17120 Mr. Wythe Keever Mr. Ad Crable The Patriot Lancaster New Era 812 Market Street 8 West King Street Harrisburg, PA 17105 Lancaster, PA 17601 U.S. Environmental Protection Agency Director Region III Office Bureau of Radiation Protection ATTN: Mr. B. Hoffman Department of Environmental Protection EIS Coordinator 13th Floor, Rachel Carson State Office 3ES30 Bldg. P. O. Box 8469 1650 Arch Street Harrisburg, PA 17105-8469 Philadelphia, PA 17103 Senior Resident Inspector (TMI-1)

Ms. Jane Lee U.S. Nuclear Regulatory Commission 183 Valley Road P.O. Box 311 Etters, PA 17319 Middletown, PA 17057 Mr. Walter W. Cohen, Consumer Dr. Judith H. Johnsrud Advocate Environmental Coalition on Nuclear Power Department of Justice 433 Orlando Avenue Strawberry Square, 14th Floor State College, PA 16803-3477 Harrisburg, PA 17127 Mr. Craig W. Smith Mr. Donald E. Smith AmerGen Energy Co. LLC AmerGen Energy Co. LLC P. O. Box 480 P.O. Box 480 Middletown, PA 17057 Middletown, PA 17057 David J. Petro Mr. Robert Borsum Senior Consultant B&W Nuclear Technologies FirstEnergy Nuclear Operating Company Suite 525 76 South Main Street 1700 Rockville Pike Akron, OH 44308 Rockville, MD 20852 Ellen P. Anderson Mr. Bruce Williams Fleet RP Manager AmerGen Energy Co. LLC FirstEnergy Nuclear Operating Company P.O. Box 480 76 South Main Street Middletown, PA 17057 Akron, OH 44308

GPU NUCLEAR, INC.

THREE MILE ISLAND NUCLEAR STATION, UNIT 2 DOCKET NO. 50-320 AMENDMENT TO FACILITY POSSESSION-ONLY LICENSE Amendment No. 61 License No. DPR-73

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

A. The application for amendment by GPU Nuclear, Inc. (the licensee) dated October 10, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 Commissions 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 Commissions 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.(1) of Facility Possession-Only License No. DPR-73 is hereby amended to read as follows:

C.(1) Technical Specifications The Technical Specifications, as revised through Amendment No. 61 are hereby incorporated into this license. The licensee shall maintain the facility in accordance with the Technical Specifications and all Commission Orders issued subsequent to the date of the possession-only license.

Enclosure 1

3. The license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Keith I. McConnell, Deputy Director Decommissioning & Uranium Recovery Licensing Directorate Division of Waste Management and Environmental Protection Office of Federal and State Materials and Environmental Management Programs

Attachment:

Changes to the Technical Specifications Date of Issuance: February 7 , 2007

ATTACHMENT TO LICENSE AMENDMENT NO. 61 FACILITY POSSESSION-ONLY LICENSE NO. DPR-73 DOCKET NO. 50-320 Replace the following page of Appendix A, Technical Specifications, with the attached revised page. The revised page is identified by the amendment number and contains marginal lines indicating the areas of change.

Remove Insert 3/4.1-4 3/4.1-4 Attachment

CONTAINMENT AIR LOCKS SURVEILLANCE REQUIREMENTS 3.1.1.3 Each Containment Air Lock shall be OPERABLE with at least one door closed except when the air lock is being used for transit entry and exit in accordance with site-approved procedures.

APPLICABILITY: PDMS ACTION:

With no Containment Air Lock door OPERABLE, restore at least one door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.1.1.3 Each Containment Air Lock shall be demonstrated OPERABLE every five (5) years by performing a mechanical operability check of each Air Lock Door, including a visual inspection of the components and lubrication if necessary and by visually inspecting the door seals for significant degradation. When both Containment Air Lock doors are opened simultaneously, verify the following conditions:

a. The capability exists to expeditiously close at least one Air Lock door;

b. The Air Lock doors and Containment Purge are configured to restrict the outflow of air in accordance with site-approved procedures; and

c. The Air Lock doors are cycled to ensure mechanical operability within seven days prior to opening both doors.

Three Mile Island - Unit 2 3/4.1-4 Amendment 51, 61

SAFETY EVALUATION BY THE OFFICE OF FEDERAL AND STATE MATERIALS AND ENVIRONMENTAL MANAGEMENT PROGRAMS RELATED TO AMENDMENT NO. 61 TO FACILITY POSSESSION-ONLY LICENSE NO. DPR-73 GPU NUCLEAR, INC.

THREE MILE ISLAND NUCLEAR STATION, UNIT 2 DOCKET NO. 50-320

1.0 INTRODUCTION

By application dated October 10, 2006, GPU Nuclear, Inc. (the licensee) submitted Technical Specification (TS) Change Request No. 84, requesting a change to the TS Surveillance Requirement 4.1.1.3 to extend the containment airlock surveillance frequency from once per year to once every five years for Three Mile Island Nuclear Station, Unit 2 (TMI-2). The purpose of this change is to reduce the personnel exposure associated with implementing the surveillance.

The staffs proposed no significant hazards consideration determination was published in the Federal Register on December 5, 2006 (71 FR 70560).

2.0 BACKGROUND

AND REGULATORY EVALUATION The TMI-2 operating license was issued on February 8, 1978. On March 28, 1979, the unit experienced an accident which resulted in severe damage to the reactor core. TMI-2 has been in a non-operating status since that time. GPU Nuclear conducted a substantial program to defuel the reactor vessel and decontaminate the facility. As a result, TMI-2 has been defueled, and the core debris removed from the reactor has been shipped off-site. The site has also been decontaminated to the extent that the plant is in a safe, inherently stable condition suitable for long-term management, and any threat to public health and safety has been minimized.

This long-term management condition is referred to as Post-Defueling Monitored Storage (PDMS).

GPU Nuclear, Inc. is licensed pursuant to Section 103 of the Atomic Energy Act and 10 CFR Part 50 to possess, but not operate, the TMI-2 facility. Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TS as part of the license.

3.0 TECHNICAL EVALUATION

The proposed amendment would revise TS Surveillance Requirement 4.1.1.3. The licensee proposed to change the containment airlock surveillance frequency from once per year to once every five years.

Enclosure 2

TMI-2 contains two airlocks, which are used during entries into the containment to ensure that radioactive materials are not unnecessarily being released to the environs. The licensee states that in reviewing the history of this surveillance since 1994, no problems with the airlock hardware or indications of seal degradation have been identified. The licensee further states that since the service demands on the airlocks are very light (typically only one entry per year),

any hardware degradation would be very gradual and would not be significant during the proposed surveillance interval. In addition, it is expected that any degradation of the door seals would also be gradual and would be detected during the surveillance inspection. The licensee also conducted an evaluation of the lubricants used in the airlock interlock system, which indicated that the lubricants would support a five-year surveillance frequency.

In the event of an inability to operate an airlock during exit from the reactor building, there is a second airlock available to personnel. In addition, as the failure mechanism of the airlock is a failure of the airlock to open, there is no potential for an additional release to the environment.

The staff reviewed the licensing basis for the containment integrity surveillance and could not identify any safety impact resulting from this change. The staffs previous safety evaluation for PDMS conditions, dated December 28, 1993, considered a variety of accident scenarios and found that for the most severe of these accidents, the dose to the maximally exposed individual at the site boundary meets the limits specified in 10 CFR Part 20 and 10 CFR Part 100. The proposed change would not alter the analysis in the previous evaluation and would not create a new potential accident scenario.

Based on the discussion above, the staff concludes that the licensees proposal to change the containment airlock surveillance frequency from once per year to once every five years is acceptable.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the official from the State of Pennsylvania was notified of the proposed issuance of the amendment. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes surveillance requirements. The proposed change does not involve a significant change in the types or significant increase in the amounts of any effluents that may be released offsite. Furthermore, the proposal does not involve a 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 (71 FR 70560). 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 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

regulations of the Commission; 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: Qi Gan Date: February 7 , 2007