ML20209F773
| ML20209F773 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/08/1986 |
| From: | Jabbour K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20209F778 | List: |
| References | |
| NUDOCS 8609120255 | |
| Download: ML20209F773 (11) | |
Text
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UNITED STATES
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I DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 9 License No. NPF-35 1.
The Nuclear Regulatory Connission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company acting for itself, North Carolina Electric Membership Corporation, and Saluda River Electric Cooperative, Inc., (the licensee)datedJuly 22, 1985, and supplemented September 11, 1985 and June 12, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comis-ston's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the regulations of the Comiss,1on; 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 (11) that such activities will be conducted in compliance with the Connission'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 Commission's regulations and all applicable requirements have been satisfied.
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-2 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-35 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 9, and the Environmental Protection Plan con-tained in Appendix B, both of which are attached hereto, are hereby incorporated into the license. Duke Power Company shall operate the facility in accordance with the Technical Spccifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION W\\
Kahtan N. Jabbour, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: September 8, 1986 i
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
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- ....,E DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
2 License No. NPF-52 1.
The Nuclear Regulatory Connission (the Connission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Facility Operating License No. NFP-52 filed by the Duke Power Company, acting for itself, North Carolina Electric Membership Corporation, and Piedmont Municipal Power Agency, (the licensee) dated July 22, 1985, and supplemented September 11, 1985, March 7, 1986 and June 12, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Connission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the regulations of the Connission; 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 Connission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the connon 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 I
of the Connission's regulations and all applicable requirements have been satisfied.
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-2 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-35 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 2, and the Environmental Protection Plan con-tained in Appendix B, both of which are attached hereto, are hereby incorporated into the license. Duke Power Company 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
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Kahtan N. Jabbour, Project Manager PWR Project Directorate #4 Division of Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: September 8, 1986 d
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ATTACHMENT TO LICENSE AMENDMENT NO. 9 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND TO LICENSE AMENDMENT NO. 2 FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414~
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 3-2 3/4 3-1 3/4 3-3 3/4 3-4 2
3/4 3-5 3/4 3-6 l
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3/4.3 INSTRUMENTATION
}
3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION -
LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES Table 3.3-2.
APPLICABILITY: As shown in Table 3.3-1.
ACTION:
As shown in Table 3.3-1.
SURVEILLANCE REQUIREMENTS 1
4.3.1.1 Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic shall be demonstrated OPERABLE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in' Table 4.3-1.
4.3.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function shall be demonstrated to be within its limit at least once per 18 months.
i Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the
" Total No. of Channels" column of Table 3.3-1.
t 1
CATAWBA - UNITS 1 & 2 3/4 3-1
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TABLE 3.3-1 k
REACTOR TRIP SYSTEM INSTRUMENTATION E$
MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE e
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MDDES ACTION 5d 1.
1 2
1, 2 1
~
2 1
2 3*, 4*, 5*
10 e-m 2.
Power Range, Neutron Flux a.
High Setpoint 4
2 3
1, 2 2#
b.
Low Setpoint 4
2 3
1#M, 2 2#
3.
Power Range, Neutron Flux 4
2 3
1, 2 2#
High Positive Rate 4.
Power Range, Neutron Flux, 4
2 5 3 1, 2 2#
R High Negative Rate s
"'4 Intermediate Range, Neutron Flux 2
1 2
1#M, 2 3
5.
6.
Source Range, Neutron Flux a.
Startup 2
1 2
2M 4
b.
Shutdown 2
1 2
3,4,5 5
7.
Overtemperature AT Four Loop Operation 4
2 3
1, 2 6#
8.
Overpower AT Four Loop Operation 4
2 3
1, 2 6#
EE*
9.
Pressurizer Pressure-Low 4
2 3
1 6#**
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TABLE 3.3-1 (Continued) hk REACTOR TRIP SYSTEM INSTRUMENTATION E
E MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE e
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 5
Dl 10.
Pressurizer Pressure-High 4
2 3
1, 2 6#**
l 11.
Pressurizer Water Level-High 3
2 2
1 6#
l ro 12.
Reactor Coolant Flow-Low a.
Single Loop (Above P-8) 3/ loop 2/ loop in 2/ loop in
)
6#
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#
l below P-8) two oper-each oper-y';
ating loops ating loop 13.
Steam Generator Water 4/stm 2/stm gen 3/sta gen 1, 2 6#**
Level--Low-Low gen in any each operating operating stm gen stm gen 14.
Undervoltage-Reactor Coolant 4-1/ bus 2
3 1
6#
Pumps (Above P-7)
BT 37 15.
Underfrequency-Reactor Coolant 4-1/ bus 2
3 1
6#
Pumps (Above P-7)
EE 16.
Turbine Trip r* **
a.1 Low Control Valve EH Pressure 4
2 3
1####
6#
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- (Unit 1)
' oio a.2 Stop Valve EH Pressure 4
2 3
1####
6#
- Low (Unit 2) es-s EF EF b.
Turbine Stop Valve Closure 4
4 1
1####
11#
c7;T' 17.
Safety Injection Input n3,a from ESF 2
1 2
1, 2 9
TABLE 3.3-1 (Continued) 3" REACTOR TRIP SYSTEM INSTRUMENTATION
>6 MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE e
FUNCTIONAL UNIT i'i OF CHANNELS TO TRIP OPERABLE MODES ACTION d
18.
Reactor Trip System' Interlocks w
a.
Intermediate Range Heutron Flux, P-6 2
1 2
2##
8 o.
ro b.
Low Power Reactor Trips Block, P-7 P-10 Input 4
2 3
1 8
or P-13 Input 2
1 2
1 8
c.
Power Range Neutron Flux, P-8 w2 4
2
'3 1
8 w
d.
Power Range Neutron 4
1 Flux, P-9 2
3 1
8 e.
Power Range Neutron Flux, P-10 4
2 3
~1 8
f.
Power Range Neutron Flux, Not P-10 4
3 4
1, 2 8
g.
Turbine Impulse Chamber Pressure, P-13 2
1 2
1 8
19.
Reactor Trip Breakers 2
1 2
1, 2 9
2 1
~2 3*, 4*, 5*
10
- 20. Automatic Trip and Interlock 2
1 2
1, 2 9
Logic 2
1 2
3*, 4*, 5*
10 f
I
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TABLE 3.3-1 (Continued)
TABLE NOTATIONS
- 0nly if the Reactor Trip System breakers happen to be in the closed position and the Control Rod Drive System is capable of rod withdrawal.
- 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.
- Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
- Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
- Above the P-9 (Reactor Trip on Turbine Trip Interlock) Setpoint.
ACTION STATEMENTS Ar. TION 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 at least HOT STANDBY within the next G hours.
ACTION 2 - 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:
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 />, 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 Either, THERMAL POWER is restricted to less than or equal c.
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 l
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.
ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:
I Below the P-6 (Intermediate Range Neutron Flux Interlock) a.
Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint; or b.
Above the P-6 (Intermediate Range Neutron Flux Interlock)
Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPEP.ABLE status prior to increasing i
THERMAL POWER above 10% of RATED THERMAL POWER.
CATAWBA - UNITS 1 & 2 3/4 3-5 Amendment No.9 (Unit 1)
Amendment No. 2 (Unit 2)
TABLE 3.3-1 (Continued)
ACTION STATEMENTS (Continued)
ACTION 4 - With the number of OPERABLE channels one less than the Minim Channels OPERABLE requirement, suspend all operations involving positive reactivity changes.
ACTION 5 - With the number of OPERABLE channels one less than the Mini 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 open the Reactor trip breakers, suspend all operations involving positive reactivity changes and verify Valves NV-231, NV-237, NV-241, and NV-244 are closed and secured in position within the next hour.
ACTION 6 - 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:
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 />, and 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.
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 status light (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.
i ACTION 9 - With the number of OPERABLE channels one less than the Minimum Ch'annels OPERABLE requirement be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one c,hannel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.
ACTION 10 - 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 open the Reactor trip breakers within the next hour.
ACTION 11 - With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the inoperable channels are 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
)
CATAWBA - UNITS 1 & 2 3/4 3-6 Amendment No. 9 Unit 1)
Amendment No. 2 ((Unit 2) l