ML20155E649
| ML20155E649 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 04/07/1986 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20155E653 | List: |
| References | |
| NUDOCS 8604180013 | |
| Download: ML20155E649 (15) | |
Text
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WASHtNGTON, D. C. 20555
%.....j DUKE POWER COMPANY DOCKET N0. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
54 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Comission) 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 (the licensee) dated July 22, 1985, and supplemented September 11, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comis-sion's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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 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.
1 8604180013 860407 PDR ADOCK 05000369 P
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. 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.54, are hereby incorpcrated into the license.
The licensee shall operate the facility in accordar e with the 4
Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k' *h L
j'g B. J. Youngblood, Director PWR Project Directorate #4 i
Division of PWR Licensing-A
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Attachment:
Technical Specification i
Changes i
Date of Issuance: April 7, 1986 i
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1.
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.54, are hereby incorporated into 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 its date of issuance ~.*
FOR THE NUCLEAR REGULATORY C0FNISSION c\\
B. J. Youngblood, Director PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
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Technical Specification 1
Changes Date of Issuance: April 7, 1986 i
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DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 35 License No. NPF-17 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by the Duke Power Company (the licensee) dated July 22, 1985, as supplemented September 11, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commis-sion's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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 set forth in 10 CFR Chapter I; e
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.
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in' Appendix A, as revised through Amendment No.35, are hereby incorporated into 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 1
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B. J. Youngblood, Director 4t j
PWR Project Directorate #4
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Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: April 7, 1986 i
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Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, i
and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.35, are hereby incorporated into 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 its date of issuance.
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FOR THE NUCLEAR REGULATORY COMMISSION i
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B. J. Youngblood, Director j
PWR Project Directorate #4 Division of PWR Licensing-A 4
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Attachment:
Technical Specification i
Changes 4
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ATTACHMENT TO LICENSE AMENDMENT N0. 54 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND f
TO LICENSE AMENDMENT NO. 35 FACILITY OPERATING LICENSE N0. NPF-17 DOCKET NO. 50-370 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. The corresponding over-leaf pages are also provided to maintain document completeness.
Amended Overleaf Page Page 3/4 3-3 l
+
3/4 3-4 3/4 3-6 3/4 3-5 3/4 3-7 8 3/4 3-1 B 3/4 3-2 B 3/4 3-la (new page) i e
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_._.m TABLE 3.3-1 (Continued)
?
REACTOR TRIP SYSTEM INSTRUMENTATION E
MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE
.E FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 8.
Overpower WT w
Four Loop Operation 4
2 3
1, 2 6
Three Loop Operation
(**)
(**)
(**)
(**)
(**)
M 9.
Pressurizer Pressure-Low 4
2 3
1 6
(***)
l 10.
Pressurizer Pressure--High 4
2 3
1, 2 6
l
(***)
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11.
Pressurizer Water Level--High 3
2 2
1 6
l l
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a 12.
Low Reactor Coolant Flow a.
Single Loop (Above P-8) 3/ loop 2/ loop in 2/ loop in 1
6, l
l any oper-each oper-ating loop ating loop b.
Two Loops (Above P-7 and 3/ loop 2/ loop in 2/ loop 1
6 below P-8) two oper-each oper-ating loops ating loop N3a kk 1
13.
Steam Generator Water 4/stm. gen.
2/stm. gen.
3/stm. gen.
1, 2 6
Level--Low-Low in any oper-each oper-(***)l
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gg ating stm.
ating stm.
22 gen.
gen.
08 xA EE l
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TABLE 3.3-1 (Continued)
?g REACTOR TRIP SYSTEM INSTRUMENTATION m
MINIMUM TOTAL NO.
CHANNELS' CHANNELS APPLICABLE g
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 1
m e
14.
Undervoltage-Reactor Coolant Pumps (above P-7) 4-1/ bus 2
3 1
6, w
1 E
15.
Underfrequency-Reactor Coolant 6,
Pumps (above P-7) 4-1/ bus 2
3 1
m
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16.
Turbine Trip a.
Low Fluid Oil Pressure 3
2 2
1 6
l 4
1 1
11#
b.
Turbine Stop Valve Closure 4
17.
Safety Injection Input w
from ESF 2
1 2
1, 2 9
s I
w 18.
Reactor Trip System Interlocks
)
a.
Intermediate Range Neutron Flux, P-6 2
1 2
2,,
8 b.
Low Power Reactor l
Trips Block, P-7 P-10 Input 4
2 3
1 8
or' l
$i P-13 Input 2
1 2
1 8
a I
0' $
c.
Power Range Neutron 8E Flux, P-8 4
2 3
1 8
4 n "
s
?E d.
Low Setpoint Power i
Range Neutron Flux, P-10 4
2 3
1, 2 8
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Turbine Impulse Chamber yy Pressure, P-13
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2 1
8 2?
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REACTOR TRIP SYSTEM INSTRUMENTATION 5
A MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT '
0F CHANNELS TO TRIP OPERABLE MODES ACTION eg d
19.
Reactor Trip Breakers 2
1 2
1 2 9
A 2
1 2
3, 4*, 5*
10 i
k
- 20. Automatic Trip and Interlock 2
1 2
1 2 9
Logic 2
1 2
3, 4*, 5*
10 A
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e 9
1 4
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TABLE 3.3-1 (Continued)
TABLE NOTATION With the Reactor Trip System breakers in the closed position, the Control Rod Drive System capable of rod withdrawal.
Values left blank pending NRC approval of three loop operation.
Comply with the provisions of Specification 3.3.2 for any portion of the channel required to be OPERABLE by Specification 3.3.2.
- The provisions of Specification 3.0.4 are not applicable.
2
- Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
- Below the P-10 (Low Setpoint' Power Range Neutron Flux Interlock) Setpoint.
ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 2 - With the number of OPERABLE channels one less than the Total l
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 />, l
b.
The Minimum Channels OPERABLE 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 /> l
for surveillance testing of other channels per Specification 4.3.1.1, and i
c.
Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2.
1 MCGUIRE - UNITS 1 & 2 3/4 3-6 Amendment NoS4(Unit 1)
Amendment Noa3(Unit 2) i
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:
i 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 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 1
l Channels OPERABLE requirement suspend all operations involving' positive reactivity changes.
l 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.
ACTION 6 - With the number of OPERAB8.E channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
The inoperable channel is placed in the tripped condition a.
within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, ana b.
The Minimum Channels OPERABLE 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 />
'l for surveillance testing of other channels per Specification 4.3.1.1 and Specification 4.3.2.1.
ACTION 7-Delete 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 i
MCGUIRE - UNITS 1 & 2 3/4 3-7 Amendment NoE4(Unit 2)
Amendment No35(Unit 1)
3/4.3 INSTRUMENTATION BASES
?
3/4.3.1 and 3/4.3.2 REACTOR TRIP AND ENGINEERED SAFETY FEATURES ACTUATION l
SYSTEM INSTRUMENTATION The OPERABILITY of the Reactor Trip and Engineered Safety Features Actuation System instrumentation and interlocks ensure that:
(1) the associated ACTION and/or Reactor trip will be initiated when the parameter 4
monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic and sufficient redundancy is maintained to permit a channel to be out-of service for testing or maintenance consistent with maintaining an appropriate level of reliability of the Reactor Protection and Engineered Safety Features Instrumentation and (3) sufficient system functions capability is available from diverse parameters.
The OPERABILITY of these systems is required to provide the overall reliability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions.
The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.
The Surveillance Requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original des.ign standards.
The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.
Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with WCAP-10271, " Evaluation of Sur-veillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System," and supplements to that report.
Surveillance inter-vals and out of service times were determined based on maintaining an appro-t priate level of reliability of the Reactor Protection System and Engineered Safety Features instrumentation.
(Implementation of quarterly testing of RTS is being postponed until after approval of a similar testing interval for ESFAS.)
The NRC Safety Evaluation Report for WCAP-10271 was provided in a letter dated February 21, 1985 from C. O. Thomas (NRC) to J. J. Sheppard (WOG-CP&L).
The meas'urement of response time at the specified frequencies provides assurance that the Reactor trip and the Engineered Safety Feature actuation 1
associated with each channel is completed within the time limit assumed in the accident analyses.
No credit was taken in the analyses for those channels with response times indicated as not applicable.
Response time may be demonstrated by any series of sequential, overlapping, or total channel test measurements provided that such tests demonstrate the total channel response time as defined.
Sensor response time verification may be demonstrated by either:
(1) in place, onsite, or offsite test measurements, or (2) utilizing replacement, sensors with certified response times.
The Engineered Safety Features Actuation System senses selected plant parameters and determines whether or not predetermined limits are being exceeded.
If they are, the signals are combined into logic matrices sensitive to combinations indicative of various accidents, events, and transients.
Once the required logic combination is completed, the system sends actuation signals to those Engineered Safety Features components whose aggregate function best serves the requirements of the condition.
As an example, the McGUIRE - UNITS 1 and 2 B 3/4 3-1 Amendment NoS4(Unit 1)
Amendment No35(Unit 2)
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INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued) following actions may be initiated by the Engineered Safety Features Actuation System to mitigate the consequences of a steam line break or loss-of-coolant accident:
(1) Safety Injection pumps start and automatic valves position, (2) Reactor trip, (3) feedwater isolation, (4) startup of the emergency diesel generators, (5) containment spray pumps start and automatic valves position, (6) containment isolation, (7) steam line isolation, (8) Turbine trip, (9) auxiliary feedwater pumps start and automatic valves position, and t
(10) nuclear service water pumps start and automatic valves position.
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McGUIRE - UNITS 1 and 2 B 3/4 3-la Amendment No.5t(Unit 1) i Amendment okn3f Unit 2)
INSTRUMENTATION
)
BASES REACTOR PROTECTION SYSTEM AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)
The Engineered Safety Features Actuation System interlocks perform the following functions:
P-4 Reactor tripped - Actuates Turbine trip, closes main feedwater valves on T,yg below Setpoint, prevents the opening of the main feedwater valves which were closed by a Safety Injection or High s
Steam Generator Water Level signal, allows Safety Injection block so that components can be reset or tripped.
Reactor not tripped prevents manual block of Safety Injection.
P-11 Defeats the manual block of Safety Injection actuation on low pressurizer pressure and low steamline pressure and defeats steam-line isolation on negative steamline pressure rate.
Defeats the manual block of the motor-driven auxiliary feedwater pumps on trip of main feedwater pumps and low-low steam generator water level.
P-12 On increasing reactor coolant loop temperature, P-12 automatically provides an arming signal to the steam dump system.
On decreasing reactor coolant loop temperature, P-12 automatically removes the arming signal from the steam dump system.
- ]Y' P-14 On increasing steam generator level, P-14 automatically trips all feed-water isolation valves and inhibits feedwater control valve modulation.
3/4.3.3 MONITORING INSTRUMENTAlION 3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS The OPERABILITY of the radiation monitoring instrumentation for plant operations ensures that:
(1) the associated action will be initiated when the radiation level monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained, and (3) suffi-cient redundancy is maintained to permit a channel to be out-of service for testing or maintenance.
The radiation monitors for plant operations senses radiation levels in selected plant systems and locations and determines whether or not predetermined limits are being exceeded.
If they are, the signals are combined into logic matrices sensitive to combinations indicative of various i
accidents and abnormal conditions. Once the required logic combination is completed, the system sends actuation signals to intiate alarms or automatic isolation action and actuation of Emergency Exhaust or Ventilation Systems.
3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the Jnovable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution s
i McGUIRE - UNITS 1 and 2 B 3/4 3-2 l