ML060740214

License Amendment 221 Regarding Revised Rod Worth Minmizer Bypass Allowances

ML060740214
Person / Time
Site:	Pilgrim
Issue date:	04/13/2006
From:	James Shea Plant Licensing Branch III-2
To:	Kansler M Entergy Nuclear Operations
SHea J, 415-1388, NRR/DLPM
References
TAC MC7055
Download: ML060740214 (10)

Text

April 13, 2006 Mr. Michael Kansler President Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601

SUBJECT:

PILGRIM NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE: REVISED ROD WORTH MINIMIZER BYPASS ALLOWANCES (TAC NO. MC7055)

Dear Mr. Kansler:

The Commission has issued the enclosed Amendment No. 221 to Facility Operating License No. DPR-35 for the Pilgrim Nuclear Power Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated May 24, 2005, as supplemented by letter dated December 6, 2005. Specifically, this amendment revises the TSs allowances for bypassing the rod worth minimizer.

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,

/RA/

James J. Shea, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293

Enclosures:

1. Amendment No. 221 to License No. DPR-35

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

April 13, 2006 Mr. Michael Kansler President Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601

SUBJECT:

PILGRIM NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE: REVISED ROD WORTH MINIMIZER BYPASS ALLOWANCES (TAC NO. MC7055)

Dear Mr. Kansler:

The Commission has issued the enclosed Amendment No. 221 to Facility Operating License No. DPR-35 for the Pilgrim Nuclear Power Station. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated May 24, 2005, as supplemented by letter dated December 6, 2005. Specifically, this amendment revises the TSs allowances for bypassing the rod worth minimizer.

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,

/RA/

James J. Shea, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293

Enclosures:

1. Amendment No. 221 to License No. DPR-35

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

PUBLIC RidsRgn1MailCenter VKlein LPL1-1 Reading RidsNrrLASLittle FAkstulewicz RiddsNrrDORL RidsAcrsMailCenter GHill (2)

RiddsNrrDORLLpla RidsEDOMailCenter RidsNrrJShea RidsOgcMail Center Accession Number: ML60740214

• See SE dated 12/28/05 OFFICE LPL1-1/PM LPL1-1/LA SNPB/BC OGC LPL1-1/BC NAME JShea SLittle FAkstulewicz* SHamrick RLaufer DATE 03/15/06 3/28/06 12/28/05 4/07/06 4/13/06 OFFICIAL RECORD COPY

ENTERGY NUCLEAR GENERATION COMPANY ENTERGY NUCLEAR OPERATIONS, INC.

DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 221 License No. DPR-35

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

A. The application for amendment filed by Entergy Nuclear Operations, Inc. (the licensee) dated May 24, 2005, as supplemented by letter dated December 6, 2005, 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 Chapter1; 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 3.B of Facility Operating License No. DPR-35 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 221, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Richard J. Laufer, Chief Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 13, 2006

ATTACHMENT TO LICENSE AMENDMENT NO. 221 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET NO. 50-293 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 iii iii 3/4.3-11 3/4.3-11 3/4.14-3 3/4.14-3 3/4.14-4 3/4.14-4

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 221 TO FACILITY OPERATING LICENSE NO. DPR-35 ENTERGY NUCLEAR GENERATION COMPANY ENTERGY NUCLEAR OPERATIONS, INC.

PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293

1.0 INTRODUCTION

By letter dated May 24, 2005, as supplemented by letter dated December 6, 2005, Agencywide Documents Access and Management System (Accession Nos. ML051520474 and ML053480192), Entergy Nuclear Operations, Inc. (the licensee) submitted a request for changes to the Pilgrim Nuclear Power Station (Pilgrim) Technical Specifications (TSs). The requested changes would revise the TSs allowances for bypassing the rod worth minimizer consistent with NUREG-1433, Standard Technical Specifications - General Electric Plants, BWR/4, Revision 3 (NUREG-1433).

The supplement dated December 6, 2005, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination.

2.0 REGULATORY EVALUATION

Section 182a of the Atomic Energy Act of 1954, as amended (the Act) requires applicants for nuclear power plant operating licenses to include TSs as a part of the license. The TSs ensure the operational capability of structures, systems, and components that are required to protect the health and safety of the public. The NRCs regulatory requirements that are related to the content of the TSs are contained in Title 10 of the Code of Federal Regulations (10 CFR)

Section 50.36 Technical specifications. 10 CFR 50.36 requires that the TSs include items in the following specific categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls.

Pursuant to 10 CFR 50.90 Application for amendment of license or construction permit, a licensee may apply for an amendment to its license including the TSs incorporated into the license. In determining the acceptability of the proposed changes, the Nuclear Regulatory Commission (NRC) staff interprets the requirements of the current version of 10 CFR 50.36.

Within this general framework licensees may revise their current TSs provided that a plant-specific review supports a finding of continued adequate safety such that: (1) the change is

editorial, administrative, or a 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 continues to afford adequate assurance of safety when judged against current regulatory standards.

Control rod patterns during startup conditions are controlled by the operator and the rod worth minimizer (RWM) "Control Rod Block Instrumentation", so that only specified control rod sequences and relative positions are allowed over the operating range of all control rods withdrawn to 10 percent of reactor thermal power. The sequences limit the potential amount of reactivity addition that could occur in the event of a control rod drop accident (CRDA). CRDA analyses assume that the reactor operator follows prescribed withdrawal sequences. These sequences define the potential initial conditions for the CRDA analysis. The RWM provides backup to operator control of the withdrawal sequences to ensure that the initial conditions of the CRDA analysis are not violated. Rod pattern control during reactor startup satisfies Criterion 3 of 10 CFR 50.36(c)(2)(ii). With the RWM inoperable during a reactor startup, the operator is still capable of enforcing the prescribed control rod sequence. However, the overall reliability is reduced because a single operator error can result in violating the control rod sequence.

3.0 TECHNICAL EVALUATION

If the RWM is inoperable during reactor startup, the licensees TSs require that the licensee either (1) immediately suspend control rod movement (except by scram), or (2) they can verify movement of control rods by a second licensed operator or other qualified member of the technical staff during control rod movement. The second option is restricted only to instances when startup with the RWM inoperable has not been performed in the last 12 months.

The licensee proposed to modify the conditions of the second option which would allow the movement of the control rods if the RWM is inoperable during startup as long as (1) a second licensed operator or other qualified member of the technical staff is verifying control rod movements, and (2) the RWM inoperable has not been performed in the last calendar year or if twelve or more control rods are already withdrawn. This is essentially the same as the original TS except if there were a startup with the RWM inoperable in the last calendar year (not 12 months), the licensee could still move the control rods (with verification from another operator or staff member) as long as 12 rods are already withdrawn.

In response to NRC staff inquiries, the licensee explained that the option to continue startup under these conditions provides operational flexibility without a reduction in safety margin should the RWM suddenly become inoperable during the startup. Verifying that $ 12 control rods are withdrawn prior to continuing startup should the RWM become inoperable is intended to demonstrate that the RWM was operable when startup began and is still maintaining the philosophy of keeping the RWM operable as much as possible. The staff agrees with the licensees statement that the use of the proposed option is acceptable, improves operational flexibility and unit availability, reduces undue restrictions on startup activities and does not reduce safety.

The other licensee proposed TS change would re-define the condition of the RWM being operable during startup for 12 months to the RWM being operable for the last calendar year.

In a response to NRC staff inquiries, the licensee states that this could allow startups with the

RWM inoperable in two different calendar years but less than 12 months apart. A second individual verifying the rod movements provides protection against single operator error and the purpose of the calendar year restriction helps ensure the RWM is maintained operable as much as possible. The staff agrees with this position and finds that changing the 12 month condition to calendar year has little to no impact on safety. This is also consistent with the wording recommended in the improved standard technical specifications, NUREG-1433, Revision 3, LCO 3.3.2.1.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Massachusetts 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 SRs.

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 (70 FR 51380; August 30, 2005). 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 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: V. Klein Date: April 13, 2006

Pilgrim Nuclear Power Station cc:

Regional Administrator, Region I Secretary of Public Safety U. S. Nuclear Regulatory Commission Executive Office of Public Safety 475 Allendale Road One Ashburton Place King of Prussia, PA 19406-1415 Boston, MA 02108 Senior Resident Inspector Director, Massachusetts Emergency U. S. Nuclear Regulatory Commission Management Agency Pilgrim Nuclear Power Station Attn: James Muckerheide Post Office Box 867 400 Worcester Road Plymouth, MA 02360 Framingham, MA 01702-5399 Chairman, Board of Selectmen Mr. William D. Meinert 11 Lincoln Street Nuclear Engineer Plymouth, MA 02360 Massachusetts Municipal Wholesale Electric Company Chairman P.O. Box 426 Nuclear Matters Committee Ludlow, MA 01056-0426 Town Hall 11 Lincoln Street Mr. Michael A. Balduzzi Plymouth, MA 02360 Site Vice President Entergy Nuclear Operations, Inc.

Chairman, Duxbury Board of Selectmen Pilgrim Nuclear Power Station Town Hall 600 Rocky Hill Road 878 Tremont Street Plymouth, MA 02360-5508 Duxbury, MA 02332 Mr. Stephen J. Bethay Office of the Commissioner Director, Nuclear Safety Assurance Massachusetts Department of Entergy Nuclear Operations, Inc.

Environmental Protection Pilgrim Nuclear Power Station One Winter Street 600 Rocky Hill Road Boston, MA 02108 Plymouth, MA 02360-5508 Office of the Attorney General Mr. Bryan S. Ford One Ashburton Place Manager, Licensing 20th Floor Entergy Nuclear Operations, Inc.

Boston, MA 02108 Pilgrim Nuclear Power Station 600 Rocky Hill Road Director, Radiation Control Program Plymouth, MA 02360-5508 Commonwealth of Massachusetts Executive Offices of Health and Ms. Charlene D. Faison Human Services Manager, Licensing 174 Portland Street Entergy Nuclear Operations, Inc.

Boston, MA 02114 440 Hamilton Avenue White Plains, NY 10601

Pilgrim Nuclear Power Station cc:

Mr. Gary J. Taylor Chief Executive Officer Mr. Michael J. Colomb Entergy Operations Director of Oversight 1340 Echelon Parkway Entergy Nuclear Operations, Inc.

Jackson, MS 39213 440 Hamilton Avenue White Plains, NY 10601 Mr. John T. Herron Sr. VP and Chief Operating Officer Mr. Travis C. McCullough Entergy Nuclear Operations, Inc. Assistant General Counsel 440 Hamilton Avenue Entergy Nuclear Operations, Inc.

White Plains, NY 10601 440 Hamilton Avenue White Plains, NY 10601 Mr. Oscar Limpias Vice President, Engineering Ms. Stacey Lousteau Entergy Nuclear Operations, Inc. Treasury Department 440 Hamilton Avenue Entergy Services, Inc.

White Plains, NY 10601 639 Loyola Avenue New Orleans, LA 70113 Mr. Christopher Schwarz Vice President, Operations Support Mr. James Sniezek Entergy Nuclear Operations, Inc. 5486 Nithsdale Drive 440 Hamilton Avenue Salisbury, MD 21801-2490 White Plains, NY 10601 Mr. Michael D. Lyster Mr. John F. McCann 5931 Barclay Lane Director, Nuclear Safety Assurance Naples, FL 34110-7306 Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601