ML20083Q271
| ML20083Q271 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/23/1995 |
| From: | Mckee P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20083Q274 | List: |
| References | |
| NUDOCS 9505250231 | |
| Download: ML20083Q271 (8) | |
Text
'
acn p '-
~ *4 UNITED STATES g
j NUCLEAR REGULATORY COMMISSION o
t WASHINGTON, D.C. 20066 4001 Y+9..
,o NORTHEAST NUCLEAR ENERGY' COMPANY. ET AL.
DOCKET NO. 50-421 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.114 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 January 24, 1995, as supplemented March 22 and 29, 1995, and April 25, 1995, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rule: 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 rults and regulations of the Commission; 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 Lccordance with 10 CFR Part 51 of the Commission's regulatinns and all applicable requirements have been satisfied.
i 9505260231 950523 PDR ADOCK 05000423 P
.. 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-I l
(2)
Technical Soecifications The T'echnical Specifications contained in Appendix A, as revised through Amendment No. 114
, 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 i
Specifications and the Environmental Protection Plan.
l 3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
Phill11p. 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:
May 23, 1995
ATTACHMENT TO LICENSE AMENDMENT NO.114 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 Insert 2-5 2-5 2-6 2-6 2-10 2-10 2-12 2-12 3/4 2-19 3/4 2-19 i
p 3
L i
i'
-.w w
e-,
y r
_c
TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUENTATION TRIP SETPOINTS a=
TOTAL SENSOR IE ALLOWANCE ERROR h
FUNCTIONAL UNIT fTA)
I fSi TRIP SETPOINT ALLOWABLE VALUE E
m 1.
Manual Reactor Trip N.A.
N.A.
N.A.
M.A.
N.A.
g 2.
Power Range, Neutron Flux
[
a.
High Setpoint
- 1) Four Loops Operating 7.5 4.56 0
< 1095 of RTP**
s 111.1% of RTP**
- 2) Three Loops Operating 7.5 4.56 0
1 80% of RTP**
1 82.1% of RTP**
b.
Low Setpoint 8.3 4.56 0
s 25% of RTP**
1 27.1% of RTP**
3.
Power Range, Neutron Flux, 1.6 0.5 0'
s 5% of RTP** with 1 6.3% of RTP** with High Positive Rate a time constant a time constant 1 2 seconds 1 2 seconds 4,
4.
Power Range, Neutron Flux, 1.6 0.5 0
s 5% of RTP** with 5 6.3% of RTP** with High Negative Rate a time constant a time constant 1 2 seconds 1 2 seconds 5.
Intermediate Range, 17.0 8.41 0
s 25% of RTP**
5 30.9% of RTP**
Neutron Flux 6.
Source Range, Neutron Flux 17.0 10.01 0
s 10** cps s 1.4 x 10+' cps g
7.
Overtemperature AT a.
Four Loops Operating E
- 1) Channels I, II 10.0 8.14 1.61 + 1.33 See Note 1 See Note 2 g:
(Temp + Press)
- 2) Channels III, IV 10.0 7.17 1.61 + 2.60 See Note 1 See Note 2 ya (Temp + Press)
R
- RTP = RATED THERMAL POWER I
Ij
TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS o
E r-0; TOTAL SENSOR ALLOWANCE ERROR k
FUNCTIONAL UNIT (TA)
I (S)
TRIP SETPOINT ALLOWABLE VALUE b.
Three Loops Operating
- 1) Channels I, II 10.0 6.80 1.71 + 1.33 See Note 1 See Note 2 w
(Temp + Press)
- 2) Channels III, IV 10.0 5.83 1.71 + 2.60 See Note 1 See Note 2 (Temp + Press) 8.
Overpower AT (Four Loops Operating) 4.8 1.28 1.61 See Note 3 See Note 4 l
9.
Pressurizer Pressure-Low 5.0 1.77 3.3 1 1900 psia 1 1890 psia
- 10. Pressurizer Pressure-High 5.0 1.77 3.3 1 2385 psia 1 2395 psia
- 11. Pressurizer Water level-High 8.0 5.13 2.7 s 89% of instrument 190.7% of instnment span span a
- 12. Reactor Coolant Flow-Low 2.5 1.52 0.78 190% of loop 189.1% of loop design flow
- design flow *
- 13. Steam Generator Water 18.10 16.64 1.50 118.10% of narrow 117.11% of narrow -
Level Low-tow range instrument range instrument span span k
s
- 14. General Warning Alam N.A.
N.A.
M.A.
M.A.
N.A.
k
=
- 15. Low Shaft Speed - Reactor 3.8 0.5 0
1 95.8% of rated 1 92.5% of rated Coolant Pumps speed speed E.
M.
D
- Minimum Measured Flow Per Loop = 1/4 of the RCS Flow Rate Limit as listed in Section 3.2.3.1.a (Four Loops Operating);
1/3 of the RCS Flow Rate Limit as listed in Section 3.2.3.2.a (Three Loops Operating)
?
"w a
y5,-
~
g TABLE 2.2-1 (Continued) k TABLE NOTATIONS (Continued) i NOTE 1:
(Continued) g E
w
- 587.l*F (Nominal T at RATED THERMAL POWER):
T' avg 0.001311/ psi; K
3 i
Pressurizer pressure, psia; P
4 2250 psia (Nominal RCS operating pressure);
P' Laplace transform operator, s ';
S and f (AI) is a function of the indicated difference between top and bottom detectors of the 3
7 power-range neutron ion chambers; with gains to be selected based on measured instrument response 5
during plant startup tests such that:
- qb tween -26% ad + M, f,(AI) - 0, dere q 9b are percent RATED THERMAL POWER (1)
For qk top and bottom halves of the core respectively,t *nd qt + 9 in th a
is total THERMAL POWER in b
percent of RATED THERMAL POWER; (2) For each percent that the magnitude of q, - q, exceeds -26%, the AT Trip Setpoint shall be automatically reduced by 3.55% of its value aY RATED THERMAL POWER; and (3) For each percent that the magnitude of qlue at RATED THERMAL POWER. exceeds +3%, the AT Trip Setpoint sha
- qs automatically reduced by 1.98% of its va
)
k s
g NOTE 2:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 1.4%
l i
AT span (Four Loop Operation); 2.7% AT span (Three Loop Operation).
s*
u
9 j!!
F:
TABLE 2.2-1 (Continued)
M Ej TABLE NOTATIONS (Continued)
E
- 3 NOTE 3: (Continued) w 0.00180/*F for T > T" and K6 - 0 for T 1 T",
K 6
As defined in Note 1, T
Indicated T,yg at RATED THERMAL POWER (Calibration temperature for AT T'
instrumentation, s 587.1*F),
As defined in Note 1, and S
O for all AI.
f (AI) 2 7
E3 NOTE 4:
The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than i
2.7% AT span. (Four Loop Operation) l NOTE 5:
Setpoint is for increasing power.
NOTE 6:
Setpoint is for decreasing power.
a Ea E
M.
a
POWER DISTRIBUTION LIM]TS
.1/4.2.3 RC5 FLOW RATE AM NUCLEAR ENTHALPY RISE H0T CHANNEL FACTOR k
FOUR LOOPS OPERATIM LIMITIM COMITION FOR OPERATION 3.f.3.1 The indicated Reactor Coolant System (RCS) total flow rate and FE shall be,saintained as follows:
a.
RCS total flow rate 2 371,920 gpm, and b.
FL 1 Fm" [1.0 + PF, (1.0 - P)]
Where:
THERMAL POWER 3y p,
RATED THERMAL POWER, 2)
FE -
Measured values of FE obtained by using the movable incore detectors to obtain a power distribution map.
The measured value of FE should be used since Specification 3.2.3.lb.
takes into consideration a measurement uncertainty of 4% for incore measurement, 3)
Fm" - The FE limit at RATED THERMAL POWER in the CORE OPERATING LIMITS REPORT (COLR),
4)
PFm - The power factor multiplier for FE provided in the COLR, and 5)
The measured value of RCS total flow rate shall be used since uncertainties of 2.4% for flow measurement have been included in Specification 3.2.3.la.
APPLICABILITY: MODE 1.
ACTION:
With the RCS total flow rate or FE outside the region of acceptable operation:
a.
Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either:
1.
Restore the RCS total flow rate and FE to within the above limits, or 2.
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High Trip Set soint to less than or equal to 55% of RATED THERMAL POWER wit 11n the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
(
MILLSTONE - UNIT 3 3/4 2-19 Amendment No. J7, 77, 77 114 0181
.. _