ML20205M700
| ML20205M700 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 03/28/1987 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205M705 | List: |
| References | |
| NUDOCS 8704020471 | |
| Download: ML20205M700 (10) | |
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 r,,
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GULF STATES UTILITIES COMPANY DOCKET NO. 50-458 RIVER BEND STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 3 License No. NPF-47 1.
The Nuclear Regulatory Commission (the Comission or the NRC) has found that:
A.
The application for amendment filed by Gulf States Utilities Company, dated August 29, 1986 as supplemented on February 19, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's 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 regulations of the Comission; 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 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 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-47 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 3 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. GSU shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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This license amendment is effective as of'its date of issuance.
FOR-THE NUCLEAR REGULATORY COMMISSION' Walter:R. Butler, Directori BWR Project Directorate No. 4' Division of BWR Licensing
Attachment:
- Changes to the Technical Specifications Date of Issuance: March 28, 1987 i
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'This litense amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 28, 1987 i
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ATTACHMENT TO LICENSE AMENffENT NO. 3 FACILITY OPERATING LICENSE NO. NPF-47 DOCKET N0. 50-458 Replace the following page of the Appendix "A" Technical Specifications with the enclosed pace. The revised page is identified by Amendment number and contains a vertical line indicating the area of change. Overleaf page provided to maintain document completeness.*
REMOVE INSERT 3/4 3-7 3/4 3-7 3/4 3-8 3/4 3-8*
3/4 3-9 3/4 3-9 3/4 3-10 3/4 3-10*
3/4 3-63 3/4 3-63 3/4 3-64 3/4 3-64 i
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TABLE 4.3.1.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS m
CHANNEL OPERATIONAL E
CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH 7
FUNCTIONAL UNIT CHECK TEST CALIBRATION (a)
SURVEILLANCE REQUIRED E
1.
a.
Neutron Flux - High S/U,$,(b)
S/U(c),W R
2 Z
s S
W R
3,4,5 b.
Inoperative NA W
NA 2,3,4,5 2.
Average Power Range Monitor:(I) a.
Neutron Flux - High, S/U S,(b)
S/U(c),W SA 2
Setdown S
W SA 3,4,5 b.
Flow Biased Simulated y
Thermal Power - High S,D(h)
S/U(c),y g(d)(e), SA("), RII) 1 c.
Neutron Flux - High S
S/U(c),y g(d), SA 1
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d.
Inoperative NA W
NA 1,2,3,4,5 3.
Reactor Vessel Steam Dome Pressure - High S
M R(9) 1,2(3) 4.
Low, Level 3 S
M R(9) 1, 2 5.
3 High, Level 8 5
M R(g) 1 a
6.
Main Steam Line Isolation R
Valve - Closure NA M
R 1
7.
Main Steam Line Radiation -
-.6 High S
M' R
1,2(3) f9) 1,2(I) 8.
Drywell Pressure - High S
M R
4
TABLE 4.3.1.1-1 (Ccntinued) h REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS "a'
CHANNEL OPERATIONAL ao SE CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH C'
FUNCTIONAL UNIT CHECK TEST CALIBRATION SURVEILLANCE REQUIRED b
9.
Scram Discharge Volume Water Level - High IU) 1, 2, 5(k) a.
Level Transmitter S
M R
-d w
I) b.
Float Switch NA Q
R 1, 2, S f
IU)(")
M ")
R S ")
I 1
- 10. Turbine Stop Valve - Closure 11.
Turbine control Valve Fast Closure, Trip Oil I
IU)I")
M ")
R S ")
I 1
Pressure - Low 12.
Reactor Mode Switch u,);
Shutdown Position NA R
NA 1,2,3,4,5 4*
13.
Manual Scram NA M
NA 1,2,3,4,5 on (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.
(b) The IRM and SRM channels shall be determined to overlap for at least 1/2 decade during each startup after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for at least 1/2 decade during each controlled shutdown, if not performed within the previous 7 days.
(c) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous 7 days.
(d) This calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER >25% of RATED THERMAL POWER. Adjust the APRM channel if the absolute difference is greater than 2% of RATED THERMAL POWER. Any APRM channel gain adjustment made in compliance with Specification 3.2.2 shall not be included in determining the absolute. difference.
(e) This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a calibrated flow signal.
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TABLE 4.3.1.1-1 (Continued) h REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS
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(f) The LPRMs shall be calibrated at least once per 1000 effective full power hours (EFPH) using the TIP system.
(g) Calibrate Rosemount trip unit setpoint at least once per 31 days.
c5 (h) Verify measured drive flow to be less than or equal to. established drive flow at the existing flow control valve position.
(i) This calibration shall-consist of verifying the simulated thermal power time constant to be.less
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than 6.6 seconds.
(j) This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification 3.10.1.
(k) With any control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
(1) This function is not required to be OPERABLE when DRYWELL INTEGRITY is not required per Specifica-tion 3.10.1 (m) Verify the Turbine Bypass Valves are closed when THERMAL POWER is greater than or equal to 40% RATED m
N THERMAL POWER.
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(n) The CHANNEL FUNCTICNAL TEST and CHANNEL CALIBRATION shall include the turbine first stage pressure' instruments.
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(o) The CHANNEL CALIBRATION shall exclude the flow reference transmitters; these transmitters shall be calibrated at least once per 18 months.
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INSTRUMENTATION 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3.
APPLICABILITY:
As shown in Table 3.3.2-1.
ACTION:
With an isolation actuation instrumentation channel trip setpoint a.
less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip sys. tem, place the inoperable channel (s) and/or that trip system in the tripped condition
- within one hour. The provisions of Specification 3.0.4 are not applicable.
With the number of OPERABLE channels less than required by the Minimum c.
OPERABLE Channels per Trip System requirement for both trip systems, i
place at least one trip system ** in the tripped condition within one hour and take the ACTION required by Table 3.3.2-1.
1
- An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.
In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.
00The trip system need not be placed in the tripped condition if this would cause the Trip Function to occur. When a trip system can be placed in the tripped condition without causing the Trip Function to occur, place the trip system with the most inoperable channels in the tripped condition; if both systems have the same number of inoperable channels, place either trip system in the tripped condition.
RIVER BEND - UNIT 1 3/4 3-10
TABLE 4.3.6-1 CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS g
CHANNEL OPERATIONAL z
CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH 7
TRIP FUNCTION CHECK TEST CALIBRATION (a)
SURVEILLANCE REQUIRED g
1.
R00 PATTERN CONTROL SYSTEM a.
Low Power Setpoint S(f)
S/
)
d)(e) i gg 1, 2 CI) b.
High Power Setpoint S
S/
c d)(e) 34 y
2.
APRM a.
Flow Biased Neutron Flux -
Upscale NA S/U(b) y 34(g) y b.
Inoperative NA S/U
,M NA 1,2,5
,x c.
Downscale NA S/U(b),N SA 1
[
d.
Neutron Flux - Upscale, Startup NA S/U
,M SA 2, 5 h
3.
SOURCE RANGE MONITORS a.
Detector not full in NA S/U(b) W NA 2, 5 b.
Upscale NA S/U
,W
'SA 2, 5 c.
Inoperative NA S/U(b),W W
NA 2, 5 d.
Downscale NA S/U SA 2, 5 4.
INTERMEDIATE RANGE MONITORS a.
Detector not full in MA S/U(b) W NA-2, 5 b.
Upscale NA S/U
,W SA 2, 5 c.
Inoperative NA S/U(b),W W
NA 2, 5 l
d.
Downscale NA S/U SA 2, 5 g
5.
SCRAM DISCHARGE VOLLME E
a.
Water Level-High NA M
R-1, 2, 5*
y 6.
REACTOR COOLANT SYSTEM RECIRCULATION FLOW a.
Upscale NA S/U(b) g 34(g) y
TABLE 4.3.6-1 (Continued)
CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTES:
a.
Neutron detectors may be excluded from CHANNEL CALIBRATION.
b.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous 7 days, c.
Within one hour prior to control rod movement, unless performed within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and as each power range above the RPCS low power setpoint is entered for the first time during any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period during power increase or decrease.
d.
At least once per 31 days while operation continues within a given power range above the RPCS low power setpoint.
e.
Includes reactor manual control multiplexing system input, f.
Verify the Turbine Bypass valves are closed when THERMAL POWER is greater than 20% RATED THERMAL POWER.
g.
The CHANNEL CALIBRATION shall exclude the flow reference transmitters; these transmitters shall be calibrated at least once per 18 months.
With any control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
Calibrate trip unit setpoint once per 31 days.
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RIVER BEND - UNIT 1 3/4 3-64 Amendment No. 3