ML13197A350

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Correction to Amendment Approving the Use of Alternate Control and Shutdown Rod Position Monitoring System
ML13197A350
Person / Time
Site: Ginna Constellation icon.png
Issue date: 07/18/2013
From: Thadani M
Plant Licensing Branch 1
To: Joseph Pacher
Ginna
Thadani M
References
TAC ME8514
Download: ML13197A350 (10)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555"()001 July 18, 2013 Mr. Joseph E. Pacher Vice President RE. Ginna Nuclear Power Plant RE. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519

SUBJECT:

RE. GINNA NUCLEAR POWER PLANT - RE: CORRECTION TO AMENDMENT APPROVING THE USE OF ALTERNATE CONTROL AND SHUTDOWN ROD POSITION MONITORING SYSTEM (TAC NO. ME8514)

Dear Mr. Pacher:

By letter dated April 20. 2012, RE. Ginna Nuclear Power Plant, LLC, (licensee) submitted to U.S. Nuclear Regulatory Commission (NRC) a license amendment request to the RE. Ginna Nuclear Power Plant (Ginna) Renewed Facility Operating License No. DPR-18. On June 25, 2013. the NRC staff issued Amendment No. 114 to Renewed Facility Operating License No.

DPR-18, for Ginna.

The Amendment revised Technical Specification (TS) 3.1.7 to approve the use of an alternative method, other than the current method using the movable incore detectors system, to monitor the position of control rod or shutdown rod. in the event of a malfunction of the microprocessor rod position indication system. The use of this alternative method would reduce the required frequency of flux mapping using the movable incore detector system to determine the position of the control or shutdown rod position that is not being indicated. This will reduce the wear on the movable incore detector system that is also used to complete other required TS surveillances.

The licensee's staff subsequently informed the NRC that the amended TS pages included footers that incorrectly referenced the previous version of those TS pages. The licensee also reported that the amended page 3 of the operating license was missing from Amendment No. 114. As a result, the licensee is unable to implement the Amendment within 30 days from the date of the Amendment, as required. includes revised Amendment No. 114 to Renewed Facility Operating License No.

DPR-18 that reflects an implementation period of 60 days. Enclosure 2 includes page 3 of the operating license and the corrected TS pages.

J. Pacher -2 If you have any questions, please contact me at (301) 415-1476 or email Mohan.Thadani@nrc.gov .

Sincerely, Mohan C. Thadani, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244

Enclosures:

1. Revised Amendment No. 114 to Renewed License No. DPR-18
2. Corrected TS Pages cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 RE. GINNA NUCLEAR POWER PLANT, LLC DOCKET NO. 50-244 RE. GINNA NUCLEAR POWER PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 114 Renewed License No. DPR-18

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

A. The application for amendment filed by the R E. Ginna Nuclear Power Plant, LLC (the licensee) dated April 20, 2012, 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. 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. DPR-18 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 114, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

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

FOR THE NUCLEAR REGULATORY COMMISSION Robert Beall, Acting 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: July 18, 2013

-3 (b) Pursuant to the Act and 10 CFR Part 70, to possess and use four (4) mixed oxide fuel assemblies in accordance with the RG&E's application dated December 14, 1979 (transmitted by letter dated December 20, 1979), as supplemented February 20, 1980 and March S, 1980; (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (S) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections SO.S4 and SO.S9 of Part SO, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

(1) Maximum Power Level Ginna LLC is authorized to operate the facility at steady-state power levels up to a maximum of 177S megawatts (thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.114, are hereby incorporated in the renewed license.

The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Fire Protection (a) The licensee shall implement and maintain in effect all fire protection features described in the licensee's submittals referenced in and as approved or modified by the NRC's Fire Protection Safety Evaluation (SE) dated February 14, 1979, and Amendment No. 114

Rod Position Indication 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Rod Position Indication LCO 3.1.7 The Microprocessor Rod Position Indication (MRPI) System and the Demand Position Indication System shall be OPERABLE.

APPLICABILITY: MODE 1, MODE 2 with Keft ~ 1.0.

ACTIONS

- NOTE-Separate Condition entry is allowed for each inoperable MRPI per group and each demand position indicator per bank.

CONDITION REQUIRED ACTION  ! COMPLETION TIME A. One MRPI per group A.1 Verify the position of the Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable for one or rods with inoperable more groups. position indicators by using movable incore detectors.

A.2 Reduce THERMAL PO\I'\ER 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to:;;. 50% RTP.

R.E. Ginna Nuclear Power Plant 3.1.7-1 Amendment 114

Rod Position Indication 3.1.7 CONDITION REQLJIRED ACTION I COMPLETION TIME

- NOTE-Rod position monitoring by Actions A.3.1 and A.3.2 may be applied to only one inoperable rod position indicator and shall only be allowed until an entry into MODE 5 A.3.1 Verify the position of the 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> non-indicating rod indirectly by using movable incore AND detectors.

Once within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of rod control system indication of potential rod movement AND Once per 31 days thereafter AND A.3.2 Review the parameters of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> the rod control system for indications of rod movement AND for the rod with an inoperable position Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> indicator. thereafter B. One or more rods with B.1 Verify the position of the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> inoperable position rods with inoperable indicators have been position indicators by using moved> 24 steps in one movable incore detectors.

direction since the last determination of the rod's OR position.

B.2 Reduce THERMAL POV\.ER 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to s 50% RTP.

R.E. Ginna Nuclear Power Plant 3.1.7-2 Amendment 114 I

Rod Position Indication 3.1.7 CONDITION REQUIRED ACTION COMPLETION TIME C. One demand position C.1.1 Verify by administrative Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> indicator per bank means all MRPls for the inoperable for one or affected banks are more banks. OPERABLE.

AND C.1.2 Verify the most withdrawn Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> rod and the least withdrawn rod of the affected banks are s 12 steps from the OPERABLE demand position indicator for that bank.

OR C.2 Reduce THERMAL POVVER 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to s 50% RTP.

D. Required Action and 0.1 Be in MODE 2 with Keff 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion < 1.0.

Time of Condition A, Condition B or Condition C not met.

E. More than one MRPI per E.1 Enter LCO 3.0.3. Immediately group inoperable for one or more groups.

OR More than one demand position indicator per bank inoperable for one or more banks.

R.E. Ginna Nuclear Power Plant 3.1.7-3 Amendment 114

Rod Position Indication 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify each MRPI agrees within 12 steps of the group Prior to reactor demand position for the full indicated range of rod criticality after each travel. Iremoval of the reactor head R.E. Ginna Nuclear Power Plant 3.1.7-4 Amendment 114

ML13197A350 OFFICE LPL1-1/PM LPL 1-1/LA LPL1-1/Acting BC NAME MThadani KGoldstein RBeali (DPickett for)

DATE 7/18/13 07/18/13 07/18/13

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