ML20133N697
| ML20133N697 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 12/30/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co |
| Shared Package | |
| ML20133N699 | List: |
| References | |
| NPF-85-A-080 NUDOCS 9701230378 | |
| Download: ML20133N697 (5) | |
Text
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t UNITED STATES s
j NUCLEAR REGULATORY COMMISSION l
t WASHINGTON, D.C. 206664m01 49.....,o PHILADELPHIA ELECTRIC COMPANY T
DOCKET N0. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPER.ATING LICENSE Amendment No. 80 License No. NPF-85 1
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated August 1, 1996, complies with the standards and recuirements of the Atomic Energy Act of 1954, as amended (the Act),
anc 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.
I i
s 9701230378 961230 PDR ADOCK 05000353 P
. 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 Facility Operating License No. NPF-85 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 80, are hereby incorporated into this license.
Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION 4
da{q3T's (f
J n,F.Stolz,Directpr roject Directorate 12 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 30, 1996 i
i
ATTACHMENT TO LICENSE AMENDMEKT NO. 80 FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 l
Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove
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Insert
- '3/4 4-20 3/4 4-20 B 3/4 4-5 B 3/4 4-5
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A' S B' C C'
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l A', B'. C'- CORE BELTLINE 800 INITIAL RTndt OF 40*F FOR PLATE A-SYSTEM HYDROTEST LIMIT j
WITH FUEL IN VESSEL
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B - NON-NUCLEAR HEATUP/
l600 COOLDOWN LIMIT I
C - NUCLEAR (CORE CRITICAL)
UMIT Z
VESSEL DISCONTINUITY l
LIMITS 400
- CORE BELTLINE b
CURVES A' ARE VAllD UP TO:
M
_312 P510 EFPY t SWFT 6.5 41.1*F k
8.5 48.0*F 200 10 52.7 F 00
/
CURVES B' AND C' ARE VALID
/
/
UP TO 10 EFPY OF OPERATION CURVES A. B, AND C ARE VAllD FOR 1 EFPY OF OPERATION l
O O.0 100.0 200.0 300.0 400.0 500.0 MINIMUM REACTOR VESSEL METALTEMPERATURE (*F)
MINIMUM REACTOR VESSEL METALTEMPERATURE VS. REACTOR VESSEL PRESSURE FIGURE 3.4.6.1 1 UMERICK-UNIT 2 3/4 4-20 Amendment No.
0'
l REACTOR COOLANT SYSTEM BASES l
PRESSURE / TEMPERATURE LIMITS (Continued)
The operating limit curves of Figure 3.4.6.1-1 are derived from the fracture i
4 toughness requirements of 10 CFR 50 Appendix G and ASME Code Section III,'
Appendix G.
The curves are based on the RTer and stress intensity factor information for the reactor vessel components.
Fracture toughness limits and the basis for compliance are more fully discussed in FSAR Chapter 5, Para-l graph 5.3.1.5, " Fracture Toughness."
The reactor vessel materials have been tested to determine their initial RTet. The results of these tests are shown in Table B 3/4.4.6-1.
Reactor operation and resultant fast neutron, E greater than 1 MeV, irradiation will cause an increase in the RTer. Therefore, an adjusted reference temperature, based upon the fluence, nickel content and copper content of the material in question, can be predicted using Bases Figure B 3/4.4.6-1 and the recommenda-tions of Regulatory Guide 1.99, Revision 2, " Radiation Embrittlement of Reactor Vessel Materials." The pressure / temperature limit curve, Figure 3.4.6.1-1, curves A', B' and C', includes an assumed shift in RTer for the conditions at 10 EFPY.
In addition, intermediate A' curves have been provided for 6.5 and 8.5 EFPY.
l The A, B and C limit curves are predicted to be bounding for all areas of the RPV until 1 EFPY when the beltline materials RTer will shift, due to neutron fluence, and the beltline curves will intersect the non-beltline discontinuity curves.
The actual shift in RTer of the vessel material will be established period-ically during operation by removing and evaluating, in accordance with 10 CFR Part 50, Appendix H, irradiated reactor vessel flux wire and charpy specimens installed near the inside wall of the reactor vessel in the core area. Since the neutron spectra at the charpy specimens and vessel inside radius are essentially identical, the irradiated charpy specimens can be used with con-fidence in predicting reactor vessel material transition temperature shift.
The operating limit curves of Figure 3.4.6.1-1 shall be adjusted, as required, on the basis of the flux wire and charpy specimen data and recommendations of Regulatory Guide 1.99, Revision 2.
The pressure-temperature limit lines shown in Figures 3.4.6.1-1, curves C, and C', and A and A', for reactor criticality and for inservice leak and hydrostatic testing have been provided to assure compliance with the minimum temperature requirements of Appendix G to 10 CFR Part 50 for reactor criticality and for inservice leak and hydrostatic testing.
The number of reactor vessel irradiation surveillance capsules and the frequencies for removing and testing the specimens in these capsules are pro-vided in Table 4.4.6.1.3-1 to assure compliance with the requirements of Appendix H to 10 CFR Part 50.
p4, LIMERICK - UNIT 2 B 3/4 4-5 Amendment No. 80