ML20093E104
| ML20093E104 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 09/24/1984 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20093E110 | List: |
| References | |
| TAC-53531, TAC-53532, TAC-57316, TAC-57317, NUDOCS 8410110540 | |
| Download: ML20093E104 (10) | |
Text
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DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 35 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to.the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company (licensee) dated February 17, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth,in 10 CFR Chapter I; B.
The. facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; 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
2.
Accordingly, the license is hereby amended by page changes to the Technical l
Specifications as. indicated in the att'achaents to this li. cense amendment and oaragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
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2-(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amen ~dnent No. 35, are-hereby incorporated into this license.
The licensee shall operate the facility in accordance with,the Tech-nical Specifications and the Environmental Protection Plan.
3.
This license amendment is~ effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Technical Specification Changes Date of Issuance: SepteEber 24, 1984 9
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NUCLEAR REGULATORY COMMISSION -
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N DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 a
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 16 License No. NPF-17 1.
The Nuclea~r Regulatory Comission (the Commission) has found that:
A.
The application for amendment to,the McGuire Nuclear Station, Unit 2 (the facility)-Facility Operating License No. NPF-17 filed by the Duke Power Company (licensee) dated February 17, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The, facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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 Comission's regulations set forth in 10 CFR Chapter I-D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health.and safety of the public; E.
The issuance of this amendment is in accordance'with I0 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as. indicated in the att'achments to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 16, are hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Tech-nical Specifications and the Environmental Protection Plan.'
3.
This license amendment is effective as of its date or issuance.
'FOR THE NUCLEAR REGULATORY COMMISSION hy l$'<W Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Technical Specificatic,n Changes Date of Issuance: September 24, 1984 e
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ATTAChi*.ENT TO LICENSE AMENDMEliT N0. 35 FACILITY OPERATING LICINSE 110. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT NO. 16
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FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
The corresponding over-leaf pages are also provided to maintain document completeness.
Amended dverleaf Page Page
'5-7 5-8 5-7a 3/4 9-16 3/4 9-17 O
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a.
DESIGN FEATURES
-o 5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE
,5.4.1 The React'or Coolant System is designed and shall be maintained:
a.
In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and c.
For a temperature of 650 F, except for the pressurizer which is
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680*F.
VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 12,040 + 100 cubic feet at a nominal T f 525 F.
avg.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY 5.6.1 The new and spent fuel storage racks are designed and shall be maintained with:
a.
Ak equivalent to less than or equal to 0.95 when flooded with unb8f$ted water, which includes a conservative allowance for uncertainties as described in Section 9.1.2.3.1 of the FSAR, and -
b.
A nominal 21-inch center-to-center distance between fuel assemblies placed in the new fuel storage vault racks, and c.
'A nominal 10.4-inch and 9.125-inch center-to-center distance:between fuel assemblies placed in Region 1 and Region 2 storage racks, respectively, in the spent fuel storage pool.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintaided to prevent inadvertent draining of the pool below elevation 745 ft. 7 in.
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1463 fuel assemblies (286 spaces in Region 1 and 1177 spaces _ in Region 2) having an initial enrichment less than or equal to 4.0 weight percent U-235.
d u!T,E'- UNIT 5 1 ano 2 5-7
. Amendment No.16 (Unit 2)
Amendment No 35 UhnJLA)
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DESIGN FEATURES 5.7 COMPONENT'CVCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
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McGUIRE - Uti!TS 1 and 2 5-7a Amendment No.16 (Unit 2)
Agendent flo. 35 (Unit __l)
TABLE 5.7-1 II g
COMPONENT CYCLIC OR TRANSIENT LIMITS E
n CYCLIC OR DESIGN CYCLE cj COMPONENT TRANSIENT LIMIT OR TRANSIENT l
I El Reactor Coolant Syste.a 200 heatup cycles at 5 100 F/hr Heatup cycle - T,yg from m
and 200 cooldown cycles at
< 200*F to > 551*F.
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g 5 100 F/hr (pressurizer cooldown Cooldown cycTe - T from
- c' at < 200 F/hr for 200*F avg
$ T pressurizer 5 650*F).
> 551*F to < 200 F.
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'N 80 loss of load cycles.
Without immediate Turbine or Reactor trip.
i 40 cycles of loss-of-offsite Loss-of-offsite A.C. electrical A.C. electrical power.
power source supplying the Onsite Class lE Distribution l[
System.
t 80 cycles of loss of flow in Loss of only one reactor l
one reactor coolant loop.
coolant pump.
400 Reactor trip cycles.
100% to 0% of RATED THERMAL POWER.
200 large step decreases in load.
100% to 0% of RATED THERMAL POWER with steam dump.
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E,EFUELING GPERATIONS 3/4.9.12 FUEL STORAGE - SPENT FUEL STORAGE' POOL LIMITING CONDITION FOR OPERATION 3.9.12 Fuel.is to be stored in the spent fuel storage pool with:
g, a.
Storage in Region 2 restricted to the following:
j 1)
Fuel which has been qualified in accordance with Figure 3.9-2 or unqualified fuel stored in a checkerboard configuration.
In the event checkerboard storage is used, one row between normal storage locations and checkerboard storage locations will be vacant; and 2)
Irradiated fuel which has decayed at least 16 days; and b.
The boron concentration in the spent fuel pool maintained at greater than or equal to 2000 ppm.
APPLICABILITY:
During storage of fuel in the spent fuel pool.
ACTION:
Suspend all actions involving the movement of fuel in the spent a.
fuel pool if it is determined a fuel assembly has been placed in the incorrect Region until such time as.the correct storage location is de'termined.
Move the assembly to its correct location before -
resumption of any other fuel movement.
b.
Suspend all actions involving the movement of fuel in the spent fuel pool if it is determined the pool boron concentration is less than 2000 ppm, until such time as the boron concentration is increased to 2000 ppm or greater.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
c.
SURVEILLANCE REOUIREMENTS 4.9.12a.
Verify all fuel assemblies to be placed in Region 2 of the spent fuel pool are within the enrichment and burnup limits of Figure 3.9-2 I
by checking the assemblies' design and burnup documentation.
b.
Verify at least once per 31 days that the spent fuel pool boron concentration is greater than 2000 ppm.
Amendment No.16 (Unit 2)
M:C'a"E - U"ITS 1 and 2 3/4 9-16 Amencment No. 35 (Unit 1)
1 REFUELING OPERATIONS.
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.40 36 32 ACCEPTABLE 28
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'm UNACCEPTABLE a
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1.0 2.0
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INITIAL ENRICHMENT (W/O U-235)
Figure 3.9-2 Minimum Burnup vs. Initial Enrichment for Region 2 Storage l
l Amendment No.16 (Unit 2) l McGUIRE - UNITS 1 and 2 3/4 9-17 AmendT.ent No. D (Unit 1).