ML20086G638
| ML20086G638 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/11/1995 |
| From: | Mckee P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20086G641 | List: |
| References | |
| NUDOCS 9507170032 | |
| Download: ML20086G638 (7) | |
Text
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4 UNITED STATES e
E NUCLEAR REGULATORY COMMISSION r
If WASHINGTON, D.C. 20068 4001
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NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.116 License No. NPF-49 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated January 10, 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, 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 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 Commission's regulations and all applicable requirements have been satisfied.
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PDR ADOCK 05000423 P
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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-49 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 116, and the Environmental Protection-Plan contained in Appendix B, both of which are attached hereto i
are hereby incorporated in the license. The licensee 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, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
-./
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Phillip F. McKee, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 11, 1995 Y
I
ATTACHMENT TO LICENSE AMENDMENT NO. 116 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove J.Ditrl 2-5 2-5 B 2-4 B 2-4 3/4 3-2 3/4 3-2 3/4 3-10 3/4 3-10 I
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TABLE 2.2-1
- 'E.
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS TOTAL SENSOR
]p ALLOWANCE ERROR G
FUNCTIONAL UNIT (TA) 1 (S)
TRIP SETPOINT ALLOWABLE VALUE
-4 l
1.
Manual Reactor Trip N.A.
N.A.
N.A.
N.A.
M.A.-
h 2.
Power Range, Neutron Flux E
a.
High Setpoints w
I
- 1) Four Loops Operating 7.5 4.56 0
< 109% of RTP**
1 111.1% of RTP**
- 2) Three Loops Operating 7.5 4.56 0
$ 80% of RTP**
I 82.1% of RTP**
b.
Low Setpoint 8.3 4.56 0
s 25% of RTP**
s 27.1%.of RTP**
3.
Power Range, Neutron Flux, 1.6 0.5 0
5 5% of RTP** with 5 6.3% of RTP** with High Positive Rate a time constant a time constant 2 2 seconds 1 2 seconds 4.
Deleted 5.
Intermediate Range, 17.0 8.41 0
s 2bs of RTP**
i 30.9% of RTP**
Neutron Flux 6.
Source Range, Neutron Flux 17.0 10.01 0
s 10+' cps 1 1.4 x 10** cps 7.
Overtemperature AT k
a.
Four Loops Operating
- 1) Channels I, II 10.0 8.14 1.61 + 1.33 See Note 1 See Note 2 a
(Temp + Press) p
- 2) Channels III, IV 10.0 7.17 1.61 + 2.60 See Note 1 See Note 2 (Temp + Press)
D.
3
- RTP - RATED THERMAL POWER
=
cn
LIMITING SAFETY SYSTEM SETTINGS BASES REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS (Continued)
The various Reactor trip circuits automatically open the Reactor trip breakers whenever a condition monitored by the Reactor Trip System reaches a preset or calculated level.
In addition to redundant channels and trains, the design approach provides a Reactor Trip System which monitors numerous system variables, therefore providing Trip System functional diversity. The functional capability at the specified trip setting is required for those anticipatory or diverse Reactor trips for which no direct credit was assumed in the safety analysis to enhance the overall reliability of the Reactor Trip System. The Reactor Trip System initiates a Turbine trip signal whenever Reactor trip is initiated. This prevents the reactivity insertion that would otherwise result from excessive Reactor Coolant System cooldown and thus avoids unnecessary actuation of the Engineered Safety Features Actuation System.
Manual Reactor Trio The Reactor Trip System includes manual Reactor trip capability.
Power Ranoe. Neutron Flux In each of the Power Range Neutron Flux channels there are two independent bistables, each with its own trip setting used for a High and Low Range trip power operations to mitigate the consequences of a power excursio,tical and low setting. The Low Setpoint trip provides protection during subcri n beginning from low power, and the High Setpoint trip provides protection during power operations to mitigate the consequences of a reactivity excursion from all power levels.
The High Setpoint trip is reduced during three loop operation to a value consistent with the safety analysis.
The Low Setpoint trip may be manually blocked above P-10 (a power level of approximately 10% of RATED THERMAL POWER) and is automatically reinstated below the P-10 Setpoint.
Power Ranae. Neutron Flux. Hiah Positive Rate l
The Power Range Positive Rate trip provides protection against rapid flux increases whith are characteristic of a rupture of a control rod drive housing.
Specifically, this trip complements the Power Range Neutron Flux High and Low l
trips to ensure that the criteria are met for all rod ejection accidents, f
MILLSTONE - UNIT 3 B 2-4 Amendment No.116 0208
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TABLE 3.3-1 f',
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REACTOR TRIP SYSTEN INSTRUMENTATION N
NININUN E
TOTAL NO.
CHANNELS CHANNELS APPLICABLE 7
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE N00ES ACTION E
1.
Manual Reactor' Trip 2
1 2
1, 2 I
w 2
1 2
3*, 4*, 5*
11 l
~
2.
Power Range, Neutron Flux a.
High Setpoint 4
2 3
1, 2 2
b.
Low Setpoint 4
2 3
Ifff, 2 2
3.
Power Range, Neutron Flux 4
2 3
1, 2 2
High Positive Rate 4.
Deleted 5.
Intermediate Range, Neutron Flux 2
1 2
l###, 2 3
,s*
6.
Source Range, Neutron Flux a.
Startup 2
1 2
2ff 4
b.
Shutdown 2
1 2
3*, 4*, 5*
11 7.
Overtemperature AT a.
Four Loop Operation 4
2 3
1, 2 6
b.
Three Loop Operation 3
2 2
1, 2 6
8.
Overpower AT a.
Four Loop Operation 4
2 3
1, 2 6
b.
Three Loop Operation 3
2 2
1, 2 6
9.
Pressurizer Pressure--Low 4
2 3
1**
6 (1) 10.
Pressurizer Pressure--High 4
2 3
1, 2 6 (1) g:
- 11. Pressurizer Water Level--High 3
2 2
1**
6 4
w
,..m g5 TABLE 4.3-1
.p-5 REACTOR TRIP SYSTEN INSTRUNENTATION SURVEILLANCE REQUIRENENTS E
m TRIP ANALOG ACTUATING
.N00ES FOR E
CHANNEL DEVICE WHICH 8
CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE-4 FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST..IS REOUIRED 1.
Manual Reactor Trip N.A.
N.A.
N.A.
R(14)
N.A.
g 2, 3*, 4*,
2.
Power Range, Neutron Flux a.
High Setpoint S
Dj, 4?,
Q N.A.
N.A.
1, 2 N4
, 4.l, b.
Lcw Setpoint S
R(4,5?
S/U(1)
N.A.
N.A.
1***,
2 3.
Power Range, Neutron Flux, N.A.
R(4,5)
Q N.A.
N.A.
1, 2 g
High Positive Rate h
4.
' Deleted l
5 5.
Intemediate Range S
R(4,5)
S/U(1)
N.A.
N.A.
1***,
2 6.
Source Range, Neutron Flux S
R(4,5) 1),
M.A.
N.A.
g**,3,4,-
I 7.
Overtemperature AT S
R Q
N.A.
N.A.
1, 2
- s" 8.
Overpower AT S
R Q
N.A.
N.A.
1, 2 E
9.
Pressurizer Pressure--Low S
R Q(18)
N.A.
N.A.
I w
?*
10.
Pressurizer Pressure--High S
R Q(18)
N.A.
N.A.
1, 2 y
11.
Pressurizer Water Level--High S R
Q N.A.
N.A 1
q
- 12. Reactor Coolant Flow--Low S
R Q
N.A.
N.A.
I w
=,
o
.