ML20149J759
| ML20149J759 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 02/17/1988 |
| From: | Perkins K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20149J762 | List: |
| References | |
| NUDOCS 8802230208 | |
| Download: ML20149J759 (6) | |
Text
.
o UNITED 8TATES
~,,
g NUCLEAR REGULATORY COMMISSION e a WASHING TON, D. C. 20H4
/
UNION ELECTRIC COMPANY CALLAWAY_ PLANT, UNIT 1 DOCKET NO. STN 50-483 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 34 License No. NPF-30 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendinent filed by Union Electric Company (the licensee)datedSeptember 10, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will o>erate in conformity with the application.
the provisions of tie Act, and the rules and regulatto.3 of l
the Comission; C.
There is reaso1able 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 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 Specifica-tions as indicated in the attachment to this license amendrent, and para-graph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to read as follows:
8802230200 800217 PDR ADOCK 05000403 P
.- b
.g.
(2) T,echnical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 34, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the license. UE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This ifcense amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION (n
p Kenneth E. Perkins, Director Project Directorate III-3 Division of Reactor Projects Attachrent:
Changes to the Technical Specifications Date of Issuance: February 17, 1988 E
I ATTACHMENT TO LICENSE AMENOMENT NO. 34 OPERA _T_ING LICENSE N0. NPF.30 00CKET 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 amensent number and contain marginal lines indicating the area of change, Corresponding overleaf paget are provided to maintain document completeness.
REMOVE INSERT 3/4 3-11 3/4 3-11 3/4 3-12*
3/4 3-12*
3/4 3-12a 3/4 3-12a Overleaf page
i j}
TABLE 4.3-1 (Continued) h REACTOR TRIP SYSTEM INSTRUNENTATION SURVEILLANCE REQUIREMENTS C
TRIP c:
ANALOG ACTUATING MODES FOR 25 CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED 18.
Reactor Trip System Interlocks (Continued) d.
Power Range Neutron Flux, P-10 N.A.
R(4).
R N.A.
N.A.
1,2 e.
Turbine Impulse Chamber Pressure, P-13 N.A.
R R
N.A.
.N.A.
I I
s s
- 19. Reactor Trip Breaker N.A.
N.A.
N.A.
M (7,11)
N.A.
1,2,3*,4*,5*
Y:'
- 20. Automatic Trip and Interlock Logic N.A.
N.A.
N.A.
N.A.
N(7) 1,2,3*,4*,5*
21.
Reactor Trip Bypass Breaker N.A.
N.A.
N.A.
H(17),R(18)
N.A.
1,2,3*,4*,5*
$it 2
I a
N Si i
i 1
TABLE 4.3-1 (Continuedl TABLE NOTATIONS
- 0nly if the Reactor Trip System breakers happen to be closed and the Control Rod Drive System is capable of rod withdrawal.
- The spet.ified 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.
- Below P-6 (Intennediate Range Neutron Flux interlock) Setpoint.
- HBelow 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 applicable for entry into MODE 2 or 1.
(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.
(5)
Detector plateau curves shall be obtained, evaluated and compared to manu-facturer's data. For the Intennediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(6)
Incore - Excore Calibration, above 75% of RATED THERMAL POWER. The provi-l sions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
Determination of the loop specific vessel AT value should be made when performing the Incore/Excore quarterly recalibration, under steady state conditions.
(7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.
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 verifica-tion 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 of less than or equal to an increase of twice the count rate within a 10-minute period.
I CALLAWAY - UNIT i 3/4 3-12 Amendment No. D 28 i
/
4 TABLE 4.3-1 LQon1,nyed) 1 TABLE NOTATIONS (10) Setpoint verification is not required.
(11) Following maintenance or adjustment of the Reactor trip breakers, the TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent veriff-cation of the Undervoltage and Shunt trips.
l (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.
'(15) CHADEL CAllBRATION 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.
(17) Local manual shunt trip prior to placing breaker in service.
l (18) Automatic Undervoltage Trip, l
k CALLAWAY - UNIT 1 3/4 3-12a Amendment No. J) #A 34
- _ _ _