ML20094Q849
| ML20094Q849 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 11/22/1995 |
| From: | Thomas K NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20094Q851 | List: |
| References | |
| NUDOCS 9512040139 | |
| Download: ML20094Q849 (10) | |
Text
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UNITED STATES
[
S NUCLEAR REGULATORY COMMISSION D
WASHINGTON, D.C. 30006 4 001
\\...../
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UNION ELECTRIC COMPANY CALLAWAY PLANT. UNIT NO. 1 DOCKET NO. 50-483 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.104 License No. NPF-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Callaway Plant, Unit I (the facility) Facility Operating License No. NPF-30 filed by the Union Electric Company (the licensee), dated January 13, 1995, 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, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance:
(1) 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 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 Commission's regulations and all applicable requirements have been satisfied.
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4 9512040139 951122 PDR ADOCK 05000483 P
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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-30 is hereby l
amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised
}
through Amendment No.104, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. UE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance to be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION QM rCl~omh Kristine M. Thomas Project Manager i
Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical
}
Specifications Date of Issuance:
November 22, 1995 i
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ATTACHMENT TO LICENSE AMENDMENT NO.104 FACILITY OPERATING LICENSE NO. NPF-30 DOCKET NO. 50-481 1
Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
3 REMOVE INSERT Y
v l
3/4 3-1 3/4 3-1 3/4 3-7 3/4 3-7 2
3/4 3-8 3/4 3-13 3/4 3-13 3/4 3-14*
3/4 3-14*
3/4 3-29 3/4 3-29 3/4 3-30 4
3/4 3-31 J
3/4 3-32 4
3/4 3-32(a)
B 3/4 3-2(a)
B 3/4 3-2(a) d i
l j
1
- Denotes overleaf page
1 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION E8SE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE..................................
3/4 2-1 DELETED 3/4 2-3 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - F,(Z)...................
3/4 2-4 DELETED 3/4 2-5 3/4.2.3 NUCLEARENTHALPYRISEHOTCHANNELFACTOR-F5........
3/4 2-8 3/4.2.4 QUADRANT POWER TILT RATI0..............................
3/4 2-10 i
3/4.2.5 DNB PARAMETERS.........................................
3/4 2-13 TABLE 3.2-1 DNB PARAMETERS.........................................
3/4 2-14 3/4.3 INSTRUMENTATION i
3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION....................
3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION....................
3/4 3-2 TABLE 3.3-2 DELETED l
TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................................
3/4 3-9 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.......................................
3/4 3-13 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.....................................
3/4 3-14 1
TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETP0lNTS.......................
3/4 3-22 TABLE 3.3-5 DELETED 1
TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS............
3/4 3-33 CALLAWAY - UNIT 1 V
Amendment No. 28 68,104 i
7
3;.
E 3/4.3 INSTRUMENTATION 3/4.3.k REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE.
l APPLICABILITY: As shown in Table 3.3-1.
ACTION:
As shown in Table 3.3-1.
SURVEILLANCE REQUIREMENTS L
4.3.1.1 Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic shall be demonstrated OPERABLE by the performance of i
the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 4.3.1.
4.3.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function shall be demonstrated to be within its limit at least once per 18 months.
Neutron detectors are exempt from response time testing.
Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels re tested at least once every N times 18 months where N is the total number of redundant channels in a specific Reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.
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4 CALLAWAY - UNIT 1 3/4 3-1 Amendment No.104 l
c THIS PAGE INTENTIONALLY BLANK e
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4 CALLAWAY -' UNIT I' 3/4 3-7 Amendment No. M,104 (Next page_is 3/4 3-9)
INSTRUMENTATION l
3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION j>
LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their Trip -
l Setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4.
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APPLICABILITY: As shown in Table 3.3-3.
i ACTION:
j With an ESFAS Instrumentation or Interlock Trip Setpoint less a.
conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 3.3-4 adjust the Setpoint consistent with the Trip Setpoint value.
b.
With an ESFAS Instrumentation or Interlock Trip Setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, either:
1.
Adjust the Setpoint consistent with the Trip Setpoint value of Table 3.3-4 and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Equation 2.2-1 4
was satisfied for the affected channel, or l
2.
Declare the channel inoperable and apply the applicable ACTION statement requirements of Table 3.3.3 until the channel is 1
restored to OPERABLE status within its Setpoint adjusted consistent with the Trip Setpoint value.
Equation 2.2-1 Z + R + S s TA Where:
I Z - The value from Column Z of Table 3.3-4 for the affected
- channel, l
R - The "as measured" value (in percent span) of rack error for the affected channel, S - Either the "as measured" value (in percent span) of the sensor error, or the value from Column S (Sensor Error) of Table 3.3-4 for the affected channel, and j
TA - The value from Column TA (Total Allowance) of Table 3.3-4 for the affected channel.
c.
With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-3.
SURVEILLANCE REQUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic l
actuation logic and relays shall be demonstrated OPERABLE by the performance i
of the ESFAS Instrumentation Surveillance Requirements specified in Table 4.3-2.
4.3.2.2 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function i
shall be demonstrated to be within the limit at least once per 18 months.
Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 3.3-3.
CALLAWAY - UNIT 1 3/4 3-13 Amendment No.104
TABLE 3.3-3
_n ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION N
[
MINIMUM
(
TOTAL NO.
CHANNELS CHANNELS APPLICABLE 7
FUNCTIONAL UNIT OF CHANNELS TO TRIP
- OPERABLE M00ES '
- ACTION E
- 1. Safety Injection (Reactor Trip, 4
Phase "A" Isolation, Feedwater Isolation Component Cooling Water Turbine Trip. Auxiliary l
Feedwater-Motor-Driven Pump, l
Emergency Diesel Generator Operation, Containment Cool-ing, and Essential Service l
Water Operation) j-a.
Manual Initiation 2
1 2
1,2,3,4 18 i
i b.
Automatic Actuation Logic and Actuation w
-y Relays (SSPS) 2 1
2
- 1,2,3,4 14 c.
Containment l
Pressure-High-1 3
2 2
1,2,3 33*
=l l
d.
Pressurizer Pressure - Low 4
2 3
1, 2, 3#
33*
l' e.
Steam Line Pressure-F Low 3/ steam line-2/ steam line 2/ steam line 1, 2, 3# _
.33*
l j
{
any steam g
line n
[
- 2. Containment Spray a.
Manual Initiation 2 pair
- 1 pair 2 pair 1, 2, 3, 4 18 g
operated simultaneously j
b.
Automatic Actuation 2
1 2
1,2,3,4 14 Logic and Actuation Relays (SSPS) c.
Containment Pressure-4 2
3 1,2,3
-16 High-3
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~CALLAWAY - UNIT 1 3/4 3-29 Amendment No. 48 42,104 1
(Next page is 3/4 3-33)
1 INSTRUMENTATION BASES REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued) l The Engineered Safety Features Actuation System senses selected plant parameters and determines whether or not predetermined limits are being exceeded.
If they are, the signals are combined into logic matrices sensitive to combinations indicative of various accidents, events, and transients. Once the required logic combination is completed, the system sends actuation signals to those Engineered Safety Features components whose aggregate function best serves the requirements of the condition. As an example, the following actions may be initiated by the Engineered Safety Features Actuation System to mitigate the consequences of a steam line break or loss-of-coolant accident:
(1) Safety Injection pumps start and automatic valves position, (2) Reactor trips, (3) Feedwater System isolates, (4) the emergency diesel generators start, (5) containment spray pumps start and automatic valves position, (6) contain-ment isolates, (7) steam lines isolate, (8) Turbine trips, (9) auxiliary feedwater pumps start and automatic valves position, (10) containment cooling fans start and automatic valves position, (11) essential service water pumps start and automatic valves position, and (12) isolate normal control room ventilation and start Emergency Ventilation System.
1 s.
4 CALLAWAY - UNIT 1 B 3/4 3-2(a)
Amendment No.17,22,S',104
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