ML17329A444
| ML17329A444 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/12/1992 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17329A445 | List: |
| References | |
| NUDOCS 9204130176 | |
| Download: ML17329A444 (15) | |
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UNITED STATES NUCLEAR REGULATORY.COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
163 License No. DPR-58 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated February 15, 1991, as supplemented October 8, 1991, and January 14, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (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.
D.
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; 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.
9204130176 920312 PDR ADOCN 050003i5 PDR
2 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 Faci lity Operating License No.
DPR-74 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 163
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
March I2
] 992
$ov L
B. Mar, Director Project Directorate III-I Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
ATTACHt'IENT TO LICENSE AMENDMENT NO.
163 TO FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
REMOVE XVI 5-5 5-5a 5-6 5-6a 5-7 5-8 5-9 5-10 5-11 5-12 INSERT XVI 5-5 5-6 5-7 5-8 5-9 5-10 5-11 5-12
INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE Exclusion Area Low Population Zone Site Boundary for Gaseous and Liquid Effluents 5.2 CONTAINMENT Configuration Design Pressure and Temperature Penetrations 5.3 REACTOR CORE Fuel Assemblies Control Rod Assemblies 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature Volume 5.5 EMERGENCY CORE COOLING SYSTEMS 5.6 FUEL STORAGE Criticality Drainage Capacity 5.7 SEISMIC CLASSIFICATION 5.8 METEOROLOGICAL TOWER LOCATION 5.9 COMPONENT CYCLIC OR TRANSIENT LIMIT 5-1 5-1 5-1 5-1 5-4 5-4 5-4 5-4 5-4 5-5 5-5 5-5 5-7 5-7 5-7 5-7 5-7 COOK NUCLEAR PLANT - UNIT 1 q
XVI AMENDMENT NO. Py,
- ygP, 163
DESIGN FEATURES a.
In accordance with the code requirements specified in Section 4.1.6 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and 0
c.
For a temperature of 650 F, except for the pressurizer which is 680 F.
VOLUME 5.4.2 The total contained volume of the reactor coolant system is 12,612
+ 100 cubic feet at a nominal T of 70 F.
avg 5.5 EMERGENCY CORE COOLING SYSTEMS 5.5.1 The emergency core cooling systems are designed and shall be main-tained in accordance with the original design provisions contained in Section 6.2 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.6 FUEL STORAGE CRITICALITY -
SPENT FUEL 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
'a.
A k f equivalent to less than 0.95 when flooded with unborated eff
- water, b.
A nominal 10.5 inch center-to-center distance between fuel assemblies placed in the storage racks.
1.
A separate region within the spent fuel storage racks (defined as Region 1) shall be established for storage of Westinghouse fuel types of enrichments greater than 3.95 weight percent U-235 and burnup less than 5,550 MWD/MTU in a checkerboard pattern configuration alternating Category 1 and Category 2 fuel as shown in Figure 5.6-1.
Westinghouse Category 1 and Category 2 fuel definitions are given in Figure 5.6-2.
COOK NUCLEAR PLANT - UNIT 1 5-5 AMENDMENT NO. gg,
- gpss, gpss 163
DESIGN FEATURES cont'd 5.6 FUEL STORAGE CRITICALITY -
SPENT FUEL cont'd A separate region within the spent fuel storage
- racks, defined as Region 2, shall be established for storage of Westinghouse fuel of an enrichment less than or equal to 3.95 weight percent U-235 or an enrichment greater than 3.95 weight percent U-235 but with a burnup greater than or equal to 5,550 MWD/MTU, and Exxon/ANF fuel of an enrichment less than or equal to 4.23 weight percent U-235 for a 17 x 17 assembly or less than or equal to 3.50 weight percent U-235 for a 15 x 15 assembly.
3.
The boundary between the Regions 1 and 2 mentioned above shall be such that the checkerboard pattern storage requirement of Region 1 shall be carried into Region 2 by at least one row as shown in Figure 5.6-1.
5.6.1.2 Fuel stored in the spent fuel storage racks shall have a maximum nominal fuel assembly enrichment as follows:
Descri tion Maximum Nominal Fuel Assembly Enrichment Wt.
s 235 1)
Westinghouse 15 x 15 STD 15 x 15 OFA 2)
Exxon/ANF 15 x 15 4.95 3.50 3)
Westinghouse 17 x 17 STD 17 x 17 OFA 17 x 17 V5 4.95 4)
Exxon/ANF 17 x 17 4.23 CRITICALITY-NEWFUEL 5.6.2.1 The new fuel pit storage racks are designed and shall be maintained with a nominal 21 inch center-to-center distance between new fuel assemblies such that K ff will not exceed 0.98 when fuel assemblies are placed in the pit and aqueous foam moderation is assumed.
COOK NUCLEAR PLANT - UNIT 1 5-6 AMENDMENT NO.
DESIGN FEATURES cont'd 5.6.2.2 Fuel stored in the new fuel storage racks shall have a maximum nominal fuel assembly enrichment as follows:
Maximum Nominal Fuel Assembly Enrichment Wt.
a 235 1)
Westinghouse 15 x 15 STD 15 x 15 OFA 2)
Exxon/ANF 15 x 15 4.55 3.50 3)
Westinghouse 17 x 17 STD 17 x 17 OFA 17 x 17 V5 4.55 4)
Exxon/ANF 17 x 17 4.23 DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 629'".
CAPACITY 5.6 '
The fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 2050 fuel assemblies.
5.7 SEISMIC CLASSIFICATION 5.7.1 Those structures, systems and components identified as Category I items in the FSAR shall be designed and maintained to the original design provisions contained in the FSAR with allowance for normal degradation pursuant to the applicant Surveillance Requirements.
5.8 METEOROLOGICAL TOWER LOCATION 5.8.1 The meteorological tower shall be located as shown in Figure 5.1.1.
5.9 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.9.1 The components identified in Table 5.9-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.9-1.
COOK NUCLEAR PLANT - UNIT 1 5-7 AMENDMENT NO. ?63
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Region 1 to 2 Boundary Regfon 1
Region 2 REGION 1, CATEGORY 2
FUEL REGION 1
g CATEGORY 1 FUEL FIGURE 5.6-1 DONALD C.
COOK NUCLEAR PLANT SCHEMATIC FOR SFP INTERFACE BOUNDARY BETWEEN REGIONS 1 AND 2 COOK NUCLEAR PLANT - UNIT 1 5-8 AMENDMENT NO.
163
l Region 1 Storage Requirements Burnup vs. Initial Enrichment Fuel Assembly Burnup (GWD/MTU) 32
( 4.9 54 30. 4 5) 28 24 ACCEPTABLE FOR STORAGE AS CATEGORY 1 FUEL 20 16-12 (3.95. 5.55)
(4.95. 5.55) 0 2.2 (2.3I 0.0)
REQUIRED TO BE STORED AS CATEGORY 2 FUEL 2.6 3
3.8 4.2 4.6 initial Westinghouse Fuel Enrichment w/o I
Category 1 - Region above and including line through 2.3 w/o Category 2 - Region in lower right box I
FIGURE 5.6-2 DONALD C.
COOK NUCLEAR PLANT SFP REGION 1 BURNED FUEL ASSEMBLY MINIMUMBURNUP VS. INITIALU-235 ENRICHMENT CURVE COOK NUCLEAR PLANT - UNIT 1 5-9 AMENDMENT NO Il9 727i 163
TABLE 5.9-1 COMPONENT CYCLIC OR TRANSIENT LIMITS COMPONENT CYCLIC OR TRANSIENT LIMIT DESIGN CYCLE OR TRANSIENT Reactor Coolant System 200 heatup cycles at less than or equal to 100 F/hr and 200 cooldown cycles at less than or equal to 0
100 F/hr (pressurizer cooldown at less than or equal to 200 F/hr).
80 loss of load cycles.
Heatup cycle
- T from less than or equal to 550 F to greater than or equal to 547 F.
0 Cooldown cycle - T from greater than or equar to 547 F
avr.
0 to less than or equal to 200 F.
0 Without immediate turbine or reactor trip.
40 cycles of loss of offsite A.C.
electrical power.
Loss of offsite A.C. electrical power source supplying the onsite Class 1E distribution system.
80 cycles of loss of flow in one reactor coolant loop.
Loss of only one reactor coolant pump.
400 reactor trip cycles.
100% to 0% of RATED THERMAL POWER.
200 large step decreases in load.
100% to 5% of RATED THERMAL POWER with steam dump.
COOK NUCLEAR PLANT - UNIT 1 5-10 AMENDMENT NO.]63
TABLE 5.9-1 COMPONENT CYCLIC OR TRANSIENT LIMITS COMPONENT CYCLIC OR TRANSIENT LIMIT DESIGN CYCLE OR TRANSIENT Reactor Coolant System 1 main reactor coolant pipe break.
Break in a reactor coolant pipe greater than 6 inches equivalent diameter.
Operating Basis Earthquakes 400 cycles
- 20 earthquakes of 20 cycles each.
Secondary System 50 leak tests.
5 hydrostatic pressure tests 1 steam line break Pressurized to 2500 psia.
Pressurized to 3107 psig.
Break in a steam line greater than 5.5 inches equivalent diameter.
5 hydrostatic pressure tests Pressurized to 1356 psig.
COOK NUCLEAR PLANT - UNIT 1 5-11 AMENDMENT N0.163
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