ML040330814
| ML040330814 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/29/2004 |
| From: | Tam P NRC/NRR/DLPM/LPD1 |
| To: | |
| References | |
| TAC MC0331 | |
| Download: ML040330814 (3) | |
Text
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RCS P/T Limits 3.4.11 0,
C)
E 0
E to U)Q 4-3 C,n a) a.CL C)
U) 0 0
a)
A:
1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0
0 50 100 150 200 250 Downcomer Water Temperature (F) 300 350 Figure 3.4.11-1 (Page 1 of 1)
Non-Nuclear System Leakage and Hydrostatic Testing Curve NMP2 3.4.11-6 Amendment 04, 110 Corrected by letter of 1/29/t4
RCS P/T Limits 3.4.11 1400 1300 1200 1100
_I.F CL 1000 G
E DX 900 E
.a 800 U) ax 3
700 XL 600 z
o 500 a.a 300 200 100 0
(1740 F, 1395 psig)
I I I
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4 4
4-4-4 4
I 4t't 4
I 4
4 4-4-4 4
4 4
4-4-4 4
4 4
4-4-4 4
(70°F, 312 psig)1 L
(1740 F, 312 psig)
I I
0 50 100 150 200 250 Downcomer Water Temperature (F) 300 350 Figure 3.4.11-2 (Page 1 of 1)
Non-Nuclear Heatup Curve NMP2 3.4.11-7 Amendment 94, 11n
'Corrected by letter of 1/29/04
RCS P/T Limits 3.4.11 M
._5 Co E00 E
a a)
C',
0 I..
a)
IoCo a,
I-0 a
cc 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0
I~~~~~~~_%
(1350F, 1253 psig)
(1350F, 312 psig)
(70'F, 312 psig)
~~~I I
________ I i I I
0 50 100 150 200 250 Downcomer Water Temperature (F) 300 350 Figure 3.4.11-3 (Page 1 of 1)
Non-Nuclear Cooldown Curve NMP2 3.4.11-8 Amendment 4, 110 Corrected by letter of 1/29/04
RCS P/T Limits 3.4.11 0)
C-Q 0
0 D
- a am Cn CD (n
C) a)
I-U, U,a)
(n I-a:
1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0
(214TF, 1395 psig)
(1 27IF, 312 psig)
(75pF, 312 psig)t (214F, 312 psig) 0 50 100 150 200 250 300 Downcomer Water Temperature. (F) 350 Figure 3.4.11-4 (Page 1 of 1)
Nuclear Heatup Curve NMP2 3.4.11-9 Amendment 110 I
Can-ecte. by letter of 1/29/C4
RCS P/T Limits 3.4.11 1400 1300 1200 t
I I I I I I
(1750 F, 1253 psig)
=
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cm
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(n 0
a-.
0cc 1100 1000 900 800 700 600 500 400 300 200 100 0
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tt1 4-4 (75IF, 312 psig)I
\\^*1 (175IF, 312 psig)
(960F, 312 psig)
_ I 0
50 100 150 200 250 300 Downcomer Water Temperature (OF) 350 Figure 3.4.11-5 (Page 1 of 1)
Nuclear Cooldown Curve NMP2 3.4.11-10 Amendment 94, 110 QT ted by letter of 1/29/0 I
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 RELATED TO AMENDMENT NO. jjp: TO FACILITY OPERATING LICENSE NO. NPF-69 NINE MILE POINT NUCLEAR STATION. LLC NINE MILE POINT NUCLEAR STATION. UNIT NO. 2 DOCKET NO. 50-410
1.0 INTRODUCTION
By letter dated August 15, 2003, Nine Mile Point Nuclear Station, LLC (NMPNS, the licensee) for the Nine Mile Point Nuclear Station, Unit No. 2 (NMP2), submitted changes related to the reactor pressure vessel (RPV) pressure-temperature (P-T) limits in the NMP2 Technical Specifications (TSs). The licensee proposed to revise P-T limits which would be effective through 22 effective full-power years (EFPYs) of facility operation. The proposed changes to the P-T limits were based, in part, on the use of American Society of Mechanical Engineers (ASME) Code Case N-640.
To support the proposed amendment, the licensee submitted additional information by a letter dated September 15, 2003. This letter provided clarifying information that did not change the scope of the proposed amendment as described in the original notice of proposed action published in the Federal Register, and did not change the initial proposed no significant hazards consideration determination.
2.0 REGULATORY EVALUATION
The Nuclear Regulatory Commission (NRC) has established requirements in Title 10 of the Code of Federal Regulations (10 CFR) Part 50 to protect the integrity of the reactor coolant pressure boundary in nuclear power plants. The NRC staff evaluates P-T limit curves based on the following NRC regulations and guidance: Appendix G to 10 CFR Part 50; General Design Criteria (GDC) 14, 30, and 31 of Appendix A of 10 CFR Part 50; Generic Letter (GL) 88-11; Regulatory Guide (RG) 1.99, Revision 2; RG 1.190; GL 92-01, Revision 1; GL 92-01, Revision 1, Supplement 1; and Standard Review Plan (SRP) Section 5.3.2. Appendix G to 10 CFR Part 50 requires that P-T limit curves for the RPV be at least as conservative as those obtained by applying the methodology of Appendix G to Section Xi of the ASME Boiler and Pressure Vessel Code (ASME Code). GL 88-11 advised licensees that the NRC staff would use RG 1.99, Revision 2 to review P-T limit curves. RG 1.99, Revision 2, contains methodologies for determining the increase in transition temperature and the decrease in upper-shelf energy (USE) in RPV material resulting from neutron irradiation. GL 92-01, Revision 1, requested that licensees submit RPV data for review. GL 92-01, Revision 1, Supplement 1 requested that licensees provide and assess data from other licensees that could affect their RPV integrity evaluations. These data are used by the NRC as the basis for the review of P-T limit curves. SRP Section 5.3.2 provides an acceptable method of determining the P-T limit curves for ferritic materials in the beltline of the RPV based on the linear elastic fracture mechanics (LEFM) methodology of Appendix G to Section XI of the ASME Code.
Qrrecteld by letter of 1/29/C4