RA-08-091, Submittal of Revised Bases Page - Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR)

Submittal of Revised Bases Page - Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR)

ML082740103
Person / Time
Site:	Oyster Creek
Issue date:	09/29/2008
From:	Cowan P AmerGen Energy Co, Exelon Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-08-091
Download: ML082740103 (4)

Text

10 CFR 50.90 RA-08-091 September 29, 2008 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Oyster Creek Nuclear Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219

Subject:

Submittal of Revised Bases Page - Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR)

References:

1) Letter from P. B. Cowan (AmerGen Energy Company, LLC) to U.S. Nuclear Regulatory Commission, "Technical Specification Change Request No. 348-Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR)," dated March 10,2008

2) Letter from P. B. Cowan (AmerGen Energy Company, LLC) to U.S. Nuclear Regulatory Commission, "Response to Request for Additional Information Concerning Technical Specification Change Request No. 348 - Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR)," dated June 30, 2008 In the Reference 1 letter, AmerGen Energy Company, LLC (AmerGen) requested a change to the Technical Specifications. The proposed change modifies Technical Specifications (TS)

Section 1.0 ("Definitions"), Limiting Conditions for Operation Section 3.3 ("Reactor Coolant"),

Surveillance Requirement 4.3 ("Reactor Coolanf'), and 6.0 ("Administrative Controls") to delete reference to the pressure and temperature curves, and include reference to the Pressure and Temperature Limits Report (PTLR).

As a result of additional discussions with the U.S. Nuclear Regulatory Commission (U.S. NRC) on September 25, 2008, Bases page 3.3-8a is being resubmitted. This page has been revised to include the date of SIR-05-044-A, "Pressure-Temperature Limits Report Methodology for Boiling Water Reactors," which was issued in April 2007. Attachment 1 contains this revised Bases page.

There are no commitments contained in this letter.

If any additional information is needed, please contact Tom Loomis at (610) 765-5510.

Submittal of Revised Bases Page -

Relocation of P-T Curves to PTLR September 29, 2008 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 29th of September, 2008.

Respectfully, Pamela B. Cbwan Director - Licensing & Regulatory Affairs AmerGen Energy Company, LLC

Attachment:

Revised Bases Page 3.3-8a cc: S. J. Collins, Administrator, USNRC Region I G. E. Miller, USNRC Project Manager, Oyster Creek M. S. Ferdas, USNRC Senior Resident Inspector, Oyster Creek Director, Bureau of Nuclear Engineering, New Jersey Department of Environmental Protection

ATTACHMENT REVISED BASES PAGE 3.3-8a

References:

1. FDSAR, Volume 1, Section IV-2

2. Letter to NRC dated May 19, 1979, "Transient of May 2, 1979"

3. General Electric Co. Letter G-EN-9-55, "Revised Natural Circulation Flow Calculation", dated May 29,1979

4. Licensing Application Amendment 16, Design Requirements Section

5. (Deleted)

6. FDSAR, Volume I, Section IV-2.3.3 and Volume II, Appendix H

7. FDSAR, Volume I, Table IV-2-1

8. Licensing Application Amendment 34, Question 14

9. Licensing Application Amendment 28, Item ill-B-2

10. Licensing Application Amendment 32, Question IS

11. (Deleted)

12. (Deleted)

13. Licensing Application Amendment 16, Page 1

14. (Deleted)

IS. SIR-05-044-A, "Pressure-Temperature Limits Report Methodology for Boiling Water Reactors,"

April 2007

16. (Deleted)

17. GPUN Safety Evaluation, SE-00022I-004, "Reactor Vessel Thermal Cycles"

18. 50.59 Evaluation, OC-2006-E-00 I, Revised Method For The Determination of Fatigue Cumulative Usage Factor for ECR 06-00046 OYSTER CREEK 3.3-8a Corrected Letter dated 8/7/2000 Amendment No: 135, 140, 151, 188,203,212, ECR OC 0600046,