ML20059B548
| ML20059B548 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/25/1993 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO) |
| Shared Package | |
| ML20059B550 | List: |
| References | |
| NPF-49-A-085 NUDOCS 9310280289 | |
| Download: ML20059B548 (7) | |
Text
--
. pa atog?
l
'#i 3
UNITED STATES li litf NUCLEAR REGULATORY COMMISSION
/
b WASHINGTON, D.C. 20555-0001 gr g
NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 i
MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 85 License No. NPF-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated September 14, 1993, 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.
i 9310280289 931025 i
PDR ADOCK 05000423 P
PDR 9 --
r
,y,.,
-r
i 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-49 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 85
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto 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.
FOR THE NUCLEAR REGULATORY COMMISSION 3
r Edis/
A30 n F. Stolz, Dir tor oject Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 25, 1993 I
f I
f l
3 ATTACHMENT TO LICENSE AMENDMENT NO. 85 j
FACILITY OPERATING LICENSE NO. NPF-49 i
DOCKET NO. 50-423 i
i i
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 2-7 2-7 2-8 2-8 2-12 2-12 B 2-8 8 2-8' t
0 i
e 9
l
-i
+
TABLE 2.2-1 (Continued)-
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS TOTAL SENSOR l
ALLOWANCE ERROR FUNCTIONAL UNIT (TA)
Z (S)
TRIP SETPOINT ALLOWABLE VALUE 3
16.
Turbine Trip a.
Low Fluid Oil Pressure N.A.
N.A.
N.A.
2 500 psig 2 450 psig i
l b.
Turbine Stop Valve N.A.
N.A.
N.A.
2 1% open
? 1% open Closure
- 17. Safety Injection Input N.A.
N.A.
N.A.
N.A.
N.A.
from ESF i
18.
Reactor Trip System Interlocks 3
a.
Intermediate Range N.A.
N.A.
N.A.
2 1 x 10 amp 2 6 x 10'" amp 4
Neutron Flux, P-6 b.
Low Power Reactor Trips Block, P-7 1)
P-10 input (Note 5)
N.A.
N.A.
N.A.
1 11% of RTP**
1 12.1% of RTP**
2)
P-13 input N.A.
N.A.
N.A.
1 10% RTP** Turbine 1 12.1% RTP** Turbine Impulse Pressure Impulse Pressure Equivalent Equivalent c.
Power Range Neutron Flux, P-8 4
1)
Four Loops Operating N.A.
N.A.
N.A.
5 37.5% of RTP**
s-39.6% of RTP**-
- 2) Three-Loops Operating N.A.
N.A.
N.A.
s 37.5% of RTP**
s 39.6% of RTP**
4
- RTP - RATED THERMAL POWER 1
4 NILLSTONE - UNIT 3 2-7' Amendment No. pp,--
ote"
- 85 4
5 w
1--
.,e m
4 r-
,,y
- n w,
t---m-re.---ene.
y e
y
-.., =. -
e-
,w.
.m w.
c#w.
e
.~%
.-v..
.v,.
.c
..s-e
TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS TOTAL SENSOR ALLOWANCE ERROR FUNCTIONAL UNIT (TA)
Z (S)
TRIP SETPOINT ALLOWABLE VALUE d.
Power Range Neutron N.A.
N.A.
N.A.
1 51% of RTP**
1 53.1% of RTP**
Flux, P-9 e.
Power Range Neutron N.A.
N.A.
N.A 2 9% of RTP**
1 7.9% of RIP **
Flux, P-10 (Note 6) 19.
Reactor Trip Breakers N.A.
N.A.
N.A N.A.
N.A.
- 20. Automatic Trip and Interlock N.A.
N.A.
N.A.
N.A.
N.A.
Logic
- 21. Three Loop Operation N.A.
N.A.
N.A.
N.A.
N.A Bypass Circuitry
- RTP - RATED THERMAL POWER I
MILLSTONE - UNIT 3 2-8 Amendment No. Jg.
0198
a Table 2.2-1 (Continued)
TABLE NOTATIONS (Continued)
NOTE 3:
(Continued) 0.00180/*F for T > T" and K6 = 0 for T 1 T",
K 6
As defined in Note 1, T
at RATED THERMAL POWER (Calibration temperature for AT Indicated T,yg T"
=
instrumentation, 5 587.l*F),
As defined in Note 1, and S
O for all AI.
f (AI) 2 NOTE 4:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 2.7% AT span.
NOTE 5:
Setpoint is for increasing power.
NOTE 6:
Setpoint is for decreasing power.
MILLSTONE - UNIT 3 2-12 Amendment No. 77,85 0169 I
LIMITING SAFETY SYSTEM SETTINGS BASES Reactor Trio System Interlocks (Continued)
P-8 On increasing power, P-8 automatically enables Reactor trips on low flow in one or more reactor coolant loops. On decreasing power, the l
P-8 automatically blocks the above listed trips.
i P-9 On increasing power, P-9 automatically' enables Reactor trip on Turbine trip. On decreasing power, P-9 automatically blocks Reactor trip on Turbine trip.
P-10 On increasing power, P-10 provides input to P-7 to ensure that Reactor Trips on low flow in more than one reactor coolant loop, reactor coolant. pump low shaft speed, pressurizer low pressure and pressurizer high level are active when power reaches 11%.
It also allows the manual block of the Intermediate Range trip and the Low Setpoint Power Range trip; and automatically blocks the Source Range trip and deenergizes the Source Range high voltage power.
On decreasing power, P-10 resets to automatically reactivate the Intermediate Range trip and the Low Setpoint Power Range trip before power drops below 9%.
It also provides input to reset P-7.
P-13 Provides input to P-7.
Three Loon Operation Bvoass Circuitry The Three Loop Operation Bypass Circuitry reactor trip ensures that' a suf-1 ficient number and the correct combination of trip circuits remain available to provide necessary protection and mitigation capability during three loop operation. Should more than two channels in one train or two dissimilar channels in two trains be bypassed, a reactor trip will occur.
In this manner, it is 3
ensured that sufficient protective features remain to mitigate the consequences of analyzed transients.
MILLSTONE - UNIT 3 8 2-8 Amendment No. 85 0170
_ _ _ _ _ _ _ _ _ _ _ _. _ _. _. - - - _ _