ML20128N571
| ML20128N571 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/17/1993 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp |
| Shared Package | |
| ML20128N577 | List: |
| References | |
| DPR-50-A-170 NUDOCS 9302230301 | |
| Download: ML20128N571 (8) | |
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1 UNITED STATES
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NUCLEAR REGULATORY COMMISSION g
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WASHINGTON, D, C. 20555 '
METROPOLITAN EDIS0N COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO.-50-289 I E E MILE ISLAND NUCLEAR STATION. UNIT N0. 1 AM_fSDMENT TO FACILITY OPERATING LICENSE Amendment No.170 1.icense No. OPR-50 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(the licensee) dated August 25, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as wended (the Act), and 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.
9302230301 930217 PDR ADOCK 05000289 P
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-Accordingly..the license is' amended.by; changes to the Technical.
Specifications as indicated inithe' attachment to.this license, amendment, and paragraph 2.c.(2) of facility 0perating License _No.
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DPR-50 is hereby. amended-to read as follows:
(2) Iechnical Specificationi
-The Technical; Specifications contained;in~ Appendix A,-as1 _
- revised through Amendment No. :170, are hereby-incorporated in the license.
GPU Nuclear Corporation shall operate the facilityLin accordance with.the Technical Specifications.;
3.
This license amendment is effective as of its date of issuance, to.be implemented within 60_daysiof issuancou -
FOR THE NUCLEAR REGULATORY COMMISSION
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/Jo 'P.' Stolz, Direct' r 1 Pr ject Directorate LDivision of: Reactor Projects - I/II:
Office of Nuclear Reactor Regulation
Attachment:
n Changes to the Technical
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Specifications Date of Issuance: February 17, 1993 L
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ATTACHMENT TO LICENSE AMENDMENT N0.170 FACILITY OPERATING LICENSE NO. OPR-50 DOCKET NO. 50-289 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 Insert 5-4 5-4
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5-6
.,,E-6 5-7
' 5-7 5-7a 5-7a 5-7b O
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i 5.3 REACTOR Aeolicability Applies to the design features of the reactor core and reactor coolant system.
Obiective To define the significant design features of the reactor core and reactor coolant system.
Soecification 5.3.1 REACTOR CORE 5.3.1.1 The reactor core is composed of slightly enriched uranium dioxide pellets contained in fuel rods. A fuel assembly normally contains 208 fuel rods arranged in a 15 by 15 lattice.
The details of the fuel assembly design are described in THI-1 UFSAR Chapter 3.
5.3.1.2 The reactor core shall approximate a right circular cylinder with an equivalent diameter of 128.9_ inches. The active fuel height is defined in TMI-1 UFSAR Chapter 3.
5.3.1.3 The core average and individual batch enrichments for the present cycle are described in THI-1 UFSAR Chapter 3.
5.3.1.4 The control rod assemblies (CRA) and axial power shaping rod assemblies (APSRA) are distributed in the reactor core as shown in THI-1 FSAR Chapter 3.
The CRA and APSRA design data are also-described in the UFSAR.
5.3.1.5 The TMI-1 core may contain burnable poison rod assemblies (BPRA) as described in TMI-1 UFSAR-Chapter 3.
5.3.1.6 Reload fuel assemblies and rods shall conform to design and evaluation data described in the UFSAR. fnrichment shall not exceed-a nominal 5.0 weight percent of U 5.3.2 REACTOR COOLANT SYSTEM 5.3.2.1 Th' mactor coolant system shall ba designed and constructed in accordance with code requirements.
(Refer to UFSAR Chapter 4 for details of design and operation.)
5.3.2.2 The reactor coolant system and any connected auxiliary systems' exposed to the reactor coolant conditions of temperature and pressure, shall be designed for a pressure of 2,500 psig and a temperature of 650*F.
The pressurizer and pressurizer surge line shall be designed for a temperature of 670*F.
5-4 Amendment No. Up,19, J59,157,170
1 5.4 NEW AND SPENT FUEL STORAGE FACILITIES Aeolicability l
Applies to storage facilities for new and spent fuel assamblies.
Ob.iecti1g hot'h new and spent fuel assemblies will be stored in such a To assure th manner that an inadvertent criticality could not occur.
Soecification 5.4.1 NEW FUEL STORAGE a.
New fuel will normally be stored in the new fud storage vault or spent fuel pools.
For the new fuel storage vault, the fuel assemblies are stored in racks in parallel rows, having a nominal center to center distance of 21-1/8 inches in both directions. The spacing in the new fuel less than 0.95 based on storage vault is sufficient to maintain K.,,
d water or less than storage of fuel assemblies in clean unborate 0.98 based on storage in an optimum hypothetical low density moderator (fog or foam) for fuel agemblies with a nominal enrichment of 5.0 weight percent U When fuel is being stored in the new fuel storage vault, twelve (12) storage locations (aligned in two rows of six locations each; traasverse row numbers four and eight) must be left vacant of fissile or moderating material to provide sufficient neutron' leakage to satisfy the NRC maximum allowable reactivity value under the optimum low moderator density condition.
For Spent Fuel Pool "A", the fuel assemblies are stored in racks in parallel rows, having a nominal center to center distance of 11.1 inches in both directions for the Region I racks and 9.2 inches in both directions for the Region 11 racks. The spacing in the Spent Fuel Pool "A" storage locations for both Region I and 11 is adequate to maintain K,,less than 0.95.
Region I will store fuel with a maximum 5.0 percent initial enrichment.
Region 11 will store new fuel with low enrichment. When fuel is being moved in or over the Spent Fuel Storage Pool "A" and fuel is being stored in the pool, c boron concentration of at least 600 ppmb must be maintained to meet the NRC maximum allowable reactivity value under the postulated accident condition.
For Spent Fuel Pool "B", the fuel assemblies are stored in racks in -
parallel rows, having nominal center to center distance of 13-5/8 inches in both directions. This spacing is sufficient to maintain a K,,,ichment of 4.37 weight percent Uless than 0.95 based on fuel asgmblies with enr When fuel is being moved in or over the Spent Fuel Storage Pool "B" and fuel is being stored in the pool, a boron concentration of at least 600 ppmb must be maintained to meet the NRC maximum allowable reactivity value under the postulated accident condition, b.
Deleted.
c.
New fuel may also be stored in shipping containers.
l 5-6 Amendment No. Up, 164,170
y 5.4.2
-SPENT FUEL STORAGE (Reference 1) l
- a. Irradiated fuel assemblies will be stored, prior to offsite shipment, in the stainless steel lined spent fuel pools, which are located in the fuel handling building, b.-Whenever there is fuel in the pool except for initial fuel loading, 77te' spent fuel pool is filled with water borated to the concentration used in the reactor cavity and fuel transfer canal.
- c. Deleted.
- d. The fuel assembly storage racks provided and the number of fuel elements each will store are listed by location below:
Spent Fuel Pool A Spent Fuel Pool B Dry New Fuel North End of Fuel South End of Fuel Storage Area Handling Building Handling Building Fuel Handling Buildino Fuel Assys.
846
- 496 54 Cores 4.78 2.8 0.37 Includes three spaces for accommodating failed fuel NOTE:
containers. An additional 648 storage locations can be installed to provide a total of 1494 locations or 8.44
- Cores, e.
All of the fuel assembly storage racks provided are designed to Seismic Class 1 criteria to the accelerations indicated below:
Fuel Handling Building Fuol Handling Dry New Fuel Storage Area Building Spent And Soent Fuel Pool A Fuel Pool B Horiz.
0.38 g Vertical 0.25 g The "B" pool fuel storage racks are designed using the NOTE: **
floor response spectra of the Fuel Handling Building.
- f. Fuel in the storage pool gall have a U* loading equal to or less than 66.2 grams of U per axial centimeter of fuel 1
assembly.
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- g. When spent fuel assemblies are stored in the Spent Fuel Pool "A", Region 11 storage locations, the combination of initial enrichment and cumulative burnup for spent fuel assemblies shall be within the acceptable area of Figure 5-4.
- h. When spent fuel assemblies are stored in the Spent Fuel Pool "B", storage locations, the combination of initial enrichment and cumulative burnup for spent fuel assemblies shall be within the acceptable area of Figure 5-5.
REFERENCES (1) UFSAR, Section 9.7
" Fuel Handling System" 5-7 Amendment No. JJ, J)S, J57,164,170
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3, INITIAL ENRICFt1ENT, WTs U-235 Figure 5-4 t1INIftJ1 BURNUP REQUIREPENTS FOR FLEL IN REGIONII 0F TFE POOL A -STORAGE RACI:S
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l Figure 5 5 MINIxcu meaNUF REQUIREMENTS-FOR FUEL IN.THE POOL "B" 8TORAGE RACKS i
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