ML050900299

Replacement Pages Associated with the Application for Technical Specification Change Regarding Mode Change Limitations

ML050900299
Person / Time
Site:	Ginna
Issue date:	03/25/2005
From:	Korsnick M Constellation Energy Group
To:	Skay D Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MB9123
Download: ML050900299 (5)

Text

Maria Korsnick 1503 Lake Road Vice President Ontario, New York 14519-9364 585.771.3494 585.771.3943 Fax maria.korsnick@ constellation.com Constellation Energy R.E. Ginna Nuclear Power Plant March 25, 2005 Ms. Donna M. Skay Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Replacement Pages Associated with the Application For Technical Specification Change Regarding Mode Change Limitations R.E. Ginna Nuclear Power Plant Docket No. 50-244

Reference:

(a) Letter from Robert C. Mecredy (RG&E) to Robert L. Clark (NRC), "Application For Technical Specification Change Regarding Mode Change Limitations", dated March 1, 2004.

(b) Letter from Donna M. Skay (NRC) to Mary G. Korsnick (Ginna LLC), "R. E.

Ginna Nuclear Power plant - Amendment Re: Modification of the CREATS and Change to Dose Calculation Methodology to Alternate Source Terrn (TAC No.

MB9123)", dated February 25, 2005.

Dear Ms. Skay:

In Reference (a), Rochester Gas & Electric (RG&E) submitted a proposed change to the Improved Technical Specifications associated with mode change limitations. Subsequent to the submittal, as the result of Amendment No. 87 to the R.E. Ginna Nuclear Power Plant Facility Operating Report (Reference (b)), the proposed revised Improved Technical Specification pages of Enclosure 3 of Reference (a) have been amended. Attached are the replacement pages for of Reference (a).

Any questions concerning this submittal should be directed to Thomas Harding, Nuclear Safety and Licensing at (585) 771-3384.

V ry truly rsk/

Mary . Korsnick 1.7--7

Revised Enclosure 3. Revised Technical Specification Pages xc: Ms. Donna M. Skay (Mail Stop 0-8-C2)

Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector Mr. Peter R. Smith New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Paul D. Eddy Electric Division NYS Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223

Enclosure 3 R.E. Ginna Nuclear Power Plant Revised Technical Specification Pages

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 The specific activity of the reactor coolant shall be within limits.

APPLICABILITY: MODES 1 and 2, MODE 3 with RCS average temperature (Tavg) 2 500 0F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT -------

1- activity 1-131 specific 1 seciic ctiitynot-not NOTE LCO 3.0.4.c is -applicable.

l within limit. ----------------

A.1 Verify DOSE EQUIVALENT Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1-131 < 60 pCi/gm.

AND A.2 Restore DOSE 7 days EQUIVALENT 1-131 to within limit.

B. Required Action and B.1 Be in MODE 3 with Tavg 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> associated Completion < 5000F.

Time of Condition A not met.

OR DOSE EQUIVALENT 1-131 specific activity> 60 pCilgm.

C. Gross specific activity not C.1 Be in MODE 3 with Tavg 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> within limit. < 5000F.

R.E. Ginna Nuclear Power Plant 3.4.16-1 Amendment

RCS Specific Activity 3.4.16 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify reactor coolant gross specific activity < 100/E 7 days pCi/gm.

SR 3.4.16.2 -NOTE-Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 1-131 14 days specific activity < 1.0 pCi/gm.

AND Between 2 and 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> after a THERMAL POWER change of 2 15%

RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period SR 3.4.16.3 ---- -NOTE-Only required to be performed in MODE 1.

Determine E from a reactor coolant sample. Once within 31 days after a minimum of 2 effective full power days and 20 days of MODE I operation have elapsed since the reactor was last subcritical for 2 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

AND Every 184 days thereafter R.E. Ginna Nuclear Power Plant 3.4.1 6-2 Amendment