ML20096E524
| ML20096E524 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 05/07/1992 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20096E529 | List: |
| References | |
| NUDOCS 9205190223 | |
| Download: ML20096E524 (10) | |
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' UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20556
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.. h DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION. UNIT-1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.131 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Commission) has found that:.
A.
-The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility), Facility Operating License No. NPF-9 filed by the Duke Power Company (licensee) dated May 9,1988, as supplemented -
-August 1, 1988, and January 5, 1989, complies with the-standards and requirements-of-the. Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations as-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 Comission; 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 Comission's regulations set-forth in-10 CFR Chapter I;
-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 requ'rements. have r
been satisfied.
l?
$$"%85$!o!OSh9
, 2.
Accordingly, the license is hereby amended by page 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-9 is hereby amended to read as follows:
Technical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.10t, are hereby incorporated into this license.
The licenses shall operate the facility in accordance with 53 the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f'
f
'466)
David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
May 7, 1992
SQCICO l
- q UNITED STATES n
I E
,i NUCLEAR REGULATORY COMMISSION -
WASHINGTON, D C. 20655 s
/
o QUEf. POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATitLQ_11[IliSE Amendment No.113 License No. NPF-17 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Statien, Unit 1 (the facility), Facility Operating License No. NPF-17 filed by the Duke Power Company (licensee) dated May 9, 1988, as supplemented August 1, 1988, and January 5, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amendec
- he Act),
and the Comission's rules and regulations as 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 conoucted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issu:nce of this amendment will not be inimical to the common defense i.nd security or to the health and safety of the public; and E.
The is:uance of this amendment is in accordance with 10 CFR Part 51 of the Cottnission's regulations and all applicable requirements have been satisfied.
l
. 2.
Accordingly, the license is hereby amended by page changas to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to rad as follows:
In hnical Specificaligni The Technical Specifications contained in Appendix A, as revised through Amendment No. 113, are hereby incorporated iri this 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 1
David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuancc:
May 7, 1992 1
AITACHMENT T0 llCENSE AMENDMENT N0.131 g
FACILITY OPERATING llCENSE NO. NPF-9 DOCKET NO. M AE TO LICENSE AMENDMENT N0. 113 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following pages of the typendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas cf change.
J Bemove Paael insert Paoes 2-8 2-8 2-10 2-10 3/4 3-7 3/4 3-7 3/4 3-11 3/4 3-11 3/4 3-14a 3/4 3-14a
mxw m m _
1 li I
TABLE 2.2-1 (Continued) r
?>
5.
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 2
NOTATION
!E 5 NOTE 1:
DVERTEMPERATURE AT 1+T5 1
4 I
2 (1 + rs5)[T(1 + rs5)-T'] + K (P-P') - f (AI)
)
E (AT/AT ) (f 7
) (1 + r35) $ K1
~E 3
y g
m Measured AT by Loop Narrow Range RID Where:
AT
=
AT, Indicated AT at RATED THERMAL POWER,
=
1 Lead-lag compensator on measured AT,
=
= Time constants utilized in the lead-lag controller for 7
11, 12 AT, 12 3 8 sec., 12 5 3 sec.,
1 Lag compensator on measured AT,
=
y Time constants utilized in the lag compensator for AT, 13 $ 2 sec.*
=
13 l
yy K
5 1.1958, 1
ea hh K
0.03143
=
2 8
1 + T45 The function generated by the lead-lag controller for T dyn mic compensation,
=
avg
..E 1+15 E
5 Time constants utilized in the lead-lag controller for Ty9, C Bf 14 15
=
1 28 sec, 15 5 4 sec.,
14 EE Average temperature, F,
T
=
pp OU l
L g compensator on measured Tavg'
=
1 + tsS i.
i TABLE 2.2-1 (Continued) f x
l REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOIN.,
i
'o NOTATION (Continued)
C NOTE 2:
OVERPOWER AT (AT/AT ) (y
)(y 1 5) I 4
- 5) (1 + 1s5) T -K [T(1
,cg)- T"] - f (AI)
~K5 (1 6
2 g
13 7
5 As defined in Note 1, Where:
AT
=
m As defined in Note 1, l
l ST
=
g b
1 Ij
= As defined in Note 1 7
= As defined in Note 1 13, T2 l
N 1
As defined in Note 1,
=
k; 1+T3 5 K
5 1.0809, 4
0.02/ F for increasing average temperature and 0 for decreasing average K
=
5 temperature, EE T 5 7
The function generated by the rate-lag controller for T,yg dynamic
=
gg y
T3 7
compensation, Time constant utilized in the rate-lag controller for Tavg, 1 7 > 5 sec,
=
17 IE 1
As defined in Note 1,
=
~'
1 + ts5 05 As defined in Note 1,
=
Tc mm EE 0.001239/ F for T > T" and K6 = 0 for T 5 T",
K
=
n ;"
6 UC
TABLE 3.3-1 (Continued)
ACTION STATEMENTS (Continued)
' ACTION 3 -With~the number of-channels OPERABLE-one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:
a.
Below the P-6-(Intermediate Range Neutron Flux Interlock)
Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint, and-b.
Above~the P-6 (Intermediate Range Neutron Flux Interlock)
Setpoint but below 10% of RATED THERMAL POWER, restore the i
inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10%-of RATED THERMAL POWER.
-ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement suspend all operations involving positive' reactivity changes.
ACTION 5
-With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.-2, as applicable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at'least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.
LACTION 62-With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
a.
The' inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and--
b.- The Minimum Channels 0PERABLE-requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing'of other channels per Specification 4.3.1.1 and Specification 4.3.2.1.
ACTION'7-Deleted l
ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply
~ Specification 3.0.3.
i:
McGUIRE - UNITS 1 & 2 3/4 3-7 Amendment No.131 (Unit 1)
Amendment No.113 (Unit %)
I i
l TABLE 4.3-1 N
O REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS
-T TRIP ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH
, CHANNEL Cf 1NEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLAt:CE g
FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST fOGIC TEST IS REQUIRFP g
k 1.
Manual Reacter Trip N.A.
N.A.
N.A.
R (1])
N.A.
1, 2, 3 *, 4 *, 5*
2.
Power Range, Neutron Flux High Setpoint S
D(2, 4),
M N.A.
N.A.
1, 2 M(3,4),
j Q(4, 6),
R(4, 5) gg, Low Setpoint S
R(4)
M N.A.
N. A.
1
,2 1
3.
Power Range, Neutron Flux, N.A.
R(4)
M N.A.
N.A.
1, 2 y
High Positive Rate 4.
Intermediate Range, S
R(4, 5)
S/U(1),M N.A.
N.A.
1
,2 Neutron Flux 5.
Source Range, Neutron Flux 5
R(4, 5)
S/U(1),M(9)
N.A.
N.A.
2, 3, 4, 5 y
6.
Overtemperature AT S
R(15)
M N.A.
N.A.
1, 2 l
h h 7.
Overpower AT S
R(15)
M N.A.
N.A.
1, 2 l
m :a 55 8.
Pressurizer Pressure--Low S
R H
N.A.
N.A.
1 zz PP 9.
Pressurizer Pressure--High S
R H
N.A.
N.A.
1, 2 10.
Pressurizer Water Level--High S
R H
N.A.
N.A.
I mm
((
11.
Low Reactor Coolant Flow 5
R H
N.A.
N.A.
I ee L
TABLE 4.3-1 (Continued)
TABLE NOTATION
((}
(11) -
The TRIP ACTUATING DEVICE OPERATIONAL TEST shall in.iependently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function.
(12) -
The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.
(13) -
Prior to placing breaker in service, a local manual shunt trip shall be performed.
(14) -
The automative undervoltage trip capability shall be verified operable.
(15) -
Overtemperature setpoint, overpower setpoint, and T channels re-avg quire an 18 month channel cainbration.
Calioration of the AT channels is required at the beginning of each cycle upon completion of the precision heat balance of Surveillance 4.2.3.5.
RCS loop AT values shall be determined by precision heat balance measurements at the beginning of each cycle in connection with Surveillance 4.2.3.5.
i McGUIRE - UNITS 1 and 2 3/4 3-14a Amendment No. 131 (Unit 1)
Amendment No. ',3 (Unit 2)
_ _ _ _ _ _ _ _ _ _