ML20216A867
| ML20216A867 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/23/1987 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20216A872 | List: |
| References | |
| NPF-68-A-001 NUDOCS 8706260400 | |
| Download: ML20216A867 (7) | |
Text
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o UNITED STATES g
NUCLEAR REGULATORY COMMISSION o
- ,E WASHINGTON, D. C. 20555
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4 GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA, 3
i CITY OF DALTON, GEORGIA DOCKET NO. 50-424 i
V0GTLE ELECTRIC GENERATING PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 1 i
License No. NPF-68 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the facility) Facility Operating License No. NPF-68 filed by i
the Georgia Power Company acting for itself, Oglethorpe Power Corporation, 1
Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensees) dated March 30, 1987, 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 confonnity with the application, as amended, 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license 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 Comission'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 attachments to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-68 is hereby amended to read as follows:
8706260400 870623 PDR ADOCK 05000424 P
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. l (2) Technical Specifications and Environmental Protection Plan -
i The Technical Specifications contained in Appendix A, as revised through Amendment No. 1, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. GPC 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.
FOR THE NUCLEAR REGULATORY COMMISSION B. J. Youngblood,. Director Project Directorate II-3 I
Division of Reactor Projects
Attachment:
l Technical Specification Changes Date of Issuance: June 23, 1987 I
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SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 REACTOR C0RE................................................
2-1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE.............................
2-1 FIGURE 2.1-1 REACTOR CORE SAFETY LIMIT............................
2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETP0INTS...............
2-3 e
TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS....
2-4
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BASES J
SECTION PAGE.
2.1 SAFETY LIMITS 2.1.1 REACTOR C0RE................................................
B 2 2.1.2 REACTOR COOLANT SYSTEM PRESSURE.............................
B 2-2 2.2 LIMITING 5AFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETP0INTS...............
. B 2-3
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V0GTLE - UNIT 1 III
I j
s INDEX j
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i
SECTION PAGE 3/4.0 APPLICABILITY...............................................
3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS l
3/4.1.1 B0 RATION CONTROL Shutdown Margin - MODES 1 and 2..........................
3/4 1-1 Shutdown Margin - MODES 3, 4 and 5.......................
3/4 1-3 l
FIGURE 3.1-1 REQUIRED SHUTDOWN MARGIN FOR MODES 3 AND 4 t
(MODE 4 WITH AT LEAST ONE REACTOR COOLANT PUMP RUNNING)..
3/4 1-3a FIGURE 3.1-2 REQUIRED SHUTDOWN MARGIN FOR MODE 5 (MODE 4 WITH NO RCPs RUNNING).........................................
3/4 1-3b i
ModeratorTeheratureCoefficient........................
3/4 1-4 Minimum Temperature for Criticality......................
3/4 1-6 3/4.1.2 B0 RATION SYSTEMS 1
i F l ow P a t h - S h utd own.....................................
3/4 1-7
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Flow Paths - Operating...................................
3/4 1-8 Charging Pump - Shutdown.................................
3/4 1-9 Charging Pumps - Operating...............................
3/4 1-10 Borated Water Source - Shutdown..........................
3/4 1-11 Borated Water Sources - 0perating........................
3/4 1-12 3/4.1.3 MOVABLE CONTROL ASSEMBLIES I
j Group Height.............................................
3/4 1-14 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE 4
EVENT OF AN INOPERABLE CONTROL OR SHUTDOWN ROD...........
3/4 1-16 j
Position Indication Systems - Operating..................
3/4 1-17 l
Position Indication System - Shutdown....................
3/4 1-18 Rod Drop Time............................................
3/4 1-19 Shutdown Rod Insertion Limit.............................
3/4 1-20 Control Rod Insertion Limits.............................
3/4 1-21
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FIGURE 3.1-3 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER.......
3/4 1-22 i
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i V0GTLE - UNIT 1 IV Amendment No. 1 i
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l V0GTLE - UNIT 1 3/4 1-3b Amendment No.
1 l
REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION i
3.1.1.3 The moderator temperature coefficient (MTC) shall be:
Less positive than 0 Ak/k/ F for the all rods withdrawn, beginning a.
of cycle life (BOL), hot zero THERMAL POWER condition; and b.
Less negative than - 4.0 x 10 4 Ak/k/*F for the all rods withdrawn, end of cycle life (EOL), RATED THERMAL POWER condition.
i APPLICABILITY:
Specification 3.1.1.3a. - MODES I and 2* only**.
Specification 3.1.'1.3b. - MODES 1, 2, and 3 only**.
ACTION:
With the MTC' more positive than the limit of Specification 3,1,1.3a.
a.
above,'oper~ tion in MODES 1 and 2 may proceed provided:
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a 1.
Control rod withdrawal limits are established and maintained sufficient to restore the MTC to less positive than 0 Ak/k/ F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
These withdrawal limits shall be in addition to the insertion
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limits of Specification 3.1.3.6; 2.
The control rods are maintained within the withdrawal limits o
established above until a subsequent calculation verifies that the i4TC has been restored to within its limit for the all rods j
witndrawn condition; and i
3.
A Special Report is prepared and submitted to the Commission, pursuant to Specification 6.8.2, within 10 days, describing the value of the measured MTC, the interim control rod withdrawal j
limits, and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.
b.
With the MTC more negative than the limit of Specification 3.1.1.3b.
above, be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i
- With K,ff greater than or equal to 1.
- See Special Test Exceptions Specification 3.10.3.
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V0GTLE - UNIT 1 3/4 1-4
i ATTACHMENT TO LICENSE AMENDMENT NO. 1 FACILITY OPERATING LICENSE NO. NPF-68 l
DOCKET NO. 50-424 I
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
Amended Overleaf Page Page IV III 3/4 1-3b 3/4 1-4
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