ML050770204

R. E. Ginna, Replacement Pages Associated with the Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process

ML050770204
Person / Time
Site:	Ginna
Issue date:	03/14/2005
From:	Korsnick M Constellation Energy Group
To:	Skay D Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML050770204 (7)

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 14, 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 Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process R.E. Ginna Nuclear Power Plant Docket No. 50-244

Reference:

(a) Letter from Mary G. Korsnick (Ginna LLC) to Robert L. Clark (NRC),

"Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process", dated August 6, 2004.

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

Ginna Nuclear Power Plant - Amendment Re: Increased Flexibility in Mode Restraints (TAC NO. MC2310)", dated March 1, 2005.

Dear Ms. Skay:

In Reference (a), R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC) submitted a proposed change to the Improved Technical Specifications associated with deleting the requirements related to hydrogen recombiners and hydrogen monitors. Subsequent to the submittal, as the result of Amendment No. 88 to the R.E. Ginna Nuclear Power Plant Facility Operating Report (Reference (b)), the proposed revised Improved Technical Specification pages of Attachment 3 of Reference (a) have been amended. Attached are the replacement pages for Attachment 3 of Reference (a).

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

VM trI yo May.Krsi ck 4 1

Revised Attachment 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. Carey W. Fleming Sr. Counsel - Nuclear Generation Constellation Generation Group, LLC 750 E. Pratt Street, 17th Floor Baltimore, MD 21202 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 Attachment 3 Revised Technical Specification Pages

PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

-NOTE-Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. A.1 Restore required channel to 30 days

--. _ _ . OPERABLE status.

-NOTE-Not applicable to Functions 3 and 4.

One or more Functions with one required channel inoperable.

B. Required Action and B.1 Initiate action to prepare Immediately associated Completion and submit a special report.

Time of Condition A not met.

C. C.1 Restore required channel to 7 days

--. _ OPERABLE

_ ___ _ status._ __

-NOTE-Only applicable to Functions 3 and 4.

One or more Functions with required channel inoperable.

R.E. Ginna Nuclear Power Plant 3.3.3-1 Amendment

PAM Instrumentation 3.3.3 CONDITION REQUIRED ACTION COMPLETION TIME D. One or more Functions D.1 Restore one channel to i days with two required OPERABLE status.

channels inoperable.

E. Required Action and E.1 Enter the Condition Immediately associated Completion referenced in Table 3.3.3-1 Time of Condition C or D for the channel.

not met.

F. As required by Required F.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action E.A and referenced in Table 3.3.3-1. AND F.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> G. As required by Required G.1 Initiate action to prepare Immediately Action E.1 and referenced and submit a special report.

in Table 3.3.3-1.

SURVEILLANCE REQUIREMENTS

-NOTE-SR 3.3.3.1 and SR 3.3.3.2 apply to each PAM instrumentation Function in Table 3.3.3-1.

SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

SR 3.3.3.2 Perform CHANNEL CALIBRATION. 24 months R.E. Ginna Nuclear Power Plant 3.3.3-2 Amendment

PAM Instrumentation 3.3.3 Table 3.3.3-1 Post Accident Monitoring Instrumentation FUNCTION REQUIRED CONDITION CHANNELS

1. Pressurizer Pressure 2 F

2. Pressurizer Level 2 F

3. Reactor Coolant System (RCS) Hot Leg Temperature 1per loop F

4. RCS Cold Leg Temperature Iper loop F

5. RCS Pressure (Wide Range) 2 F

6. RCS Subcooling Monitor 2 F

7. Reactor Vessel Water Level 2 G

8. Containment Sump B Water Level 2 F

9. Containment Pressure (Wide Range) 2 F

10. Containment Area Radiation (High Range) 2 G

11. Condensate Storage Tank Level 2 F

12. Refueling Water Storage Tank Level 2 F

13. Residual Heat Removal Flow 2 F

14. Core Exit Temperature-Quadrant 1 2(a) F

15. Core Exit Temperature-Quadrant 2 2(a) F

16. Core Exit Temperature-Quadrant 3 2(a) F

17. Core Exit Temperature-Quadrant 4 2(a) F

18. Auxiliary Feedwater(AFW) Flowto Steam Generator(SG)A 2 F

19. AFW Flow to SG B 2 F

20. SG A Water Level (Narrow Range) 2 F

21. SG B Water Level (Narrow Range) 2 F

22. SG A Water Level (Wide Range) 2 F R.E. Ginna Nuclear Power Plant 3.3.3-3 Amendment

PAM Instrumentation 3.3.3 Table 3.3.3-1 Post Accident Monitoring Instrumentation FUNCTION REQUIRED CONDITION CHANNELS

23. SG B Water Level (Wide Range) 2 F I 24. SG A Pressure 2 F

25. SG B Pressure 2 F (a) A channel consists of two core exit thermocouples (CETs).

R.E. Ginna Nuclear Power Plant 3.3.3-4 Amendment