ML20206B106
| ML20206B106 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 04/03/1987 |
| From: | Oconnor P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206B110 | List: |
| References | |
| NUDOCS 8704080336 | |
| Download: ML20206B106 (8) | |
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UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 DOCKET N0. 50-483 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 19 I
License No. NPF-30 1.
The Nuclear Regulator, Comission (the Comission) has found that:
A.
The application for amendment to the Callaway Plant, Unit 1 (the facility) Facility Operating License No. NPF-30 filed by Union Electric Company (the licensee) dated January 9,1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as afnended (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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 19, and the Environmental Protection Plan 8704000336 870403 PDR ADOCK 05000483 p
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- contained in Appendix B both of which are attached hereto, are hereby incorporated into the license. -Union Electric shall operate the facility in accordance with the Technical Specifications and-the Environmental Protection Plan..
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION M\\
Paul O'Connor, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance:
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ATTACHMENT TO LICENSE AMENDMENT NO. 19 OPERATING LICENSE NO. NPF-30 DOCKET NO. 50-483 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Amended Page 3/4 3-4 l
3/4 3-6a (new page) 3/4 3-9 3/4 3-12 3/4 3-12a F
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e' TABLE 3.3-1 (Continued)
"I.
h REACTOR TRIP SYSTEM INSTRUMENTATION E
E MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 5Z
- 18. Reactor Trip System Interlocks a.
Intermediate Range Neutron Flux, P-6 2
1 2
2M 8
b.
Low Power Reactor Trips Block, P-7 P-10 Input 4
2 3
1 8
or P-13 Input 2
1 2
1 8
R c.
Power Range Neutron Flux, P-8 4
2 3
1 8
4 d.
Power Range Neutron Flux, P-9 4
2 3
1 8
e.
Power Range 1, 2 8
Neutron Flux, P-10 4
2 3
f.
Turbine Impulse Chamber Pressure, P-13 2
1 2
1 8
19.
Reactor Trip Breakers 2
1 2
1, 2 9,32 l
g 2
1 2
3*, 4*, 5*
10
- 20. Automat'ic Trip and Interlock logic 2
1 2
1; 2 9
g 2
1 2
3, 4 *, 5*
10 e
1 1
TABLE 3.3-1 (Continu?d)
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ACTION STATEMENTS (Continued)
ACTION 12 - With one of the diverse trip features (Undervoltage or Shunt Trip Attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the affected breaker inoperable and apply ACTION 9.
The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.
s CALLAWAY - UNIT 1 3/4 3-6a Amendment No.19
TABLE 4.3-1 n
REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS E
f TRIP ANALOG ACTUATING MODES FCR CHANNEL DEVICE WHICH E
CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE G
FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED w
, N.A.
R(16)
N.A.
1, 2, 38, 4*,5*0 1.
Manual Reactor Trip N.A.
N.A.
2.
Power Range, Neutron Flux a.
High Setpoint S
D(2, 4),
Q(14)
N.A.
N.A.
1, 2 M(3, 4),
Q(4, 6),
R(4,5) b.
Low Setpoint S
R(4)
S/U(1)
N.A.
N.A.
1###, 2 R
3..
Power Range, heutron Flux, N.A.
R(4)
Q(14)
N.A.
N.A.
1, 2
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High Positive Rate 4.
Power Range, Neutron Flux, N.A.
R(4)
Q(14)
N.A.
N. A.
1, 2 High Negative Rate 5.
Intermediate Range, S
R(4, 5)
S/U(1)
N.A.
N.A.
1###, 2 Neutron Flux 6.
Source Range, Neutron Flux S
R(4, 5, 12)
S/U(1),Q(9,14)
N.A.
N.A.
2##, 3, 4, 5 7.
Overtemperature AT S
R(13)
Q(14)
N.A.
N.A.
1, 2
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Overpower AT S
R Q(14)
N.A.
N.A.
1, 2 9.
Pressurizer Pressure-Low S
R Q(14)
N.A.
N.A.
1 10.
Pressurizer Pressure-High S
R Q(14)
N.A.
N.A.
1, 2 11.
Pressurizer Water Level-High S
R Q(14)
N.A.
N. A.
1 12.
Reactor Coolant Flow-Low S
R Q(14)
N.A.
N.A.
1 A
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- h TABLE 4.3-1 (Continued)
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TABLE NOTATIONS
- 0nly if the Reactor Trip System breakers happen to be closed and the Con-trol Rod Drive System is capable of rod withdrawal.
- The.specified 18 month frequency may be waived for Cycle I provided the surveillance is performed prior to restart following the first refueling outage or June 1,1986, whichever occurs first. The provisions of Specification 4.0.2 are reset from performance of this surveillance.
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- Below P-6 (Intermediate Range Neutron Flux interlock) Setpoint.
- Below P-10 (Low Setpoint Power Range Neutron Flux interlock) Setpoint.
(1) If not performed in previous 31 days.
(2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER. Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%. The provisions of Specification-4.0.4 are not applicable for entry into MODE 2 or 1.
(3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15%
of RATED THERMAL POWER.
Recalibrate if the absolute difference is greater than or equal to 3%.
The provisions of Specification 4.0.4 are not appli-4 cable for entry into MODE 2 or 1.
(4) Neutron detectgrs may be excluded from CHANNEL CALIBRATION.
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(5) Detector plateau curves shall be obtained, evaluat'ed and compared to manu-facturer's data.
For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
i (6) Incore - Excore Calibration, above 75% of RATED THERMAL POWER. The provi-sions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
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('7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.
4 The TRIP ACTUATING DEVICE OPERATIONAL TEST shall' independently verify the OPERABILITY of the Undervoltage and Shunt Trip Attachments of the Reactors Trip Breakers.
(8) Deleted (9) Quarterly surveillance in MODES 3*, 4*, and 5* shall also include verification that permissives P-6 and-P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window. Quarterly surveillance shall include verification of the Boron Dilution Alarm Setpoint
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of less than or equal to an increase of twice the count rate within a 10-minute period.
l (10) Setpoint verification is not required.
(11) Following maintenance or adjustment of the Reactor trip breakers, the l
TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent veri-fication of the Undervoltage and Shunt trips.
(12) At least once per 18 months during shutdown, verify that on a simulated
' Boron Dilution Doubling test signal the normal CVCS discharge valves will close and the centrifugal charging pumps suction valves from the RWST will open within 30 seconds.
1 CALLAWAY - UNIT 1 3/4 3-12 Amendment No.19 4
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TABLE NOTATIONS (13) CHANNEL CALIBRATION shall include the RTD bypass loops flow rate.
(14) Each channel shall be tested at least every 92 days on a STAGGERED TEST BASIS.
(15) The surveillance frequency and/or MODES specified for these channels in Table 4.3-2 are more restrictive and, therefore, applicable.
(16) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the Undervoltage and Shunt Trip circuits for the Manual Reactor Trip function.
The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit.
j CALLAWAY - UNIT 1 3/4 3-12a Amendment No.
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