ML20236P491
| ML20236P491 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 08/07/1987 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236P494 | List: |
| References | |
| NUDOCS 8708120387 | |
| Download: ML20236P491 (17) | |
Text
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UNITED STATES J'
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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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, 29 i
License No. NPF-35 1.
The Nuclear Regulatory Comission (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., (licensees dated June 10, 1987, as supplemented June 11 and 16, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, j
as amended (the Act) and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, es amended, 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 Comission's rules and regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; 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.
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 and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
29, and the Environmental Protection Plan G708120337 870807 DR ADOcK 0500 0
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contained in Appendix B botn of which are attached hereto, are hereby incorporated into this 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 S.J. Youngbicod, Director Project Directorate II-3 Division of Reactor Projects I/II
Attachment:
Technical Specification Changes l
Date of Issuance:
August 7, 1987 I
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PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 i
AMENDMENT TO FACILITY OPERATING LICENSE I
Amendment No. 20 j
License No. NPF-52 j
1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 2 i
(the f0cility) Facility Operating License No. NPF-52 filed by the Duke Power Company acting for itself, North Carolina Municipal Power Agency No I and Piedmont Municipal Power Agency (licensees) dated June 10, 1987, as supplemented June 11 and 16, 1987, 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 confonnity with the application, as amended, the provisions of the Act, and the rules and regulations of 4
the Commission; C.
There is reasonable assurance: (1)thattheactivitiesauthorizedby 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 rules and regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requireraents have I
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-52 is hereby amended to read as follows:
l (2) Technical Specifications and Environmental Protection Plan l
The Technical Specifications contained in Appendix A, as revised through Amendment No. 20, and the Environmental Protection Plan I
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contained in Appendix B, both of which are attached hereto, are f
hereby incorporated into this license.
Duke Power Company shall j
operate the facility in accordance with the Technical Specifications 1
and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
b B.J. Youngblood, Director Project Directorate II-3 Division of Reactor Projects I/II 1
Attachment:
1 Technical Specification Changes i
Date of Issuance: August 7, 1987 s
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ATTACHMENT TO LICENSE AMENDMENT NO. 29 1
FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND TO LICENSE AMENDMENT NO. 20 FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Spec'ifications with the enclosed pages.
The revised pages are identified by' Amendment number and contain vertical lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Amended Overleaf Page Page 3/4 3-1 3/4 3-14 3/4 3-13 1
3/4 3-45 3/4 3-46 1
3/4 3-50 3/4 3-49 I
3/4 6-54 3/4 6-53 l
3/4 7-5 3/4'7-6 1
3/4 8-5 l
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~ /4.3 INSTRUMENTATION 3
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 as shown in Table 3.3-2.
APPLICABILITY:
As shown in Taule 3.3-1.
ACTION:
As shown in Table 3.3-1.
SURVEILLANCE REQUIREMENTS 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.*
l 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.
CThis surveillance need not be performed for the primary RTO response time testing portion of items 7 and 8 from Table 3.3-2 for Unit 2 until prior to entering STARTUP following the Unit 2 first refueling.
CATAWBA - UNITS 1 & 2 3/4 3-1 Amendment No. 29 (Unit 1)
Amendment No. 20 (Unit 2)
w INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation j
channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their Trip Setpoints set consistent with the values shown in the Trip Setpoint l
column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.
APPLICABILITY:
As shown in Table 3.3-3 ACTION:
a.
With an ESFAS Instrumentation or Interlock Trip Setpoint trip less j
conservative than the value shown in the Trip Setpoint column but i
more conservative than the value shown in the Allowable Value rolumn of Table 3.3-4, adjust the Setpoint consistent with the Trip 5etpoint value.
J b.
With an ESFAS Instrumentation or Interlock Trip Setpoint less conservative than the value shown in the Allowable Values Column of j
Table 3.3-4, either:
1.
Adjust the Setpoint consistent with the Trip Setpoint value of Table 3.3-4, and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Equation 2.2-1 l
was satisfied for the affected channel, or 1
2.
Declare the channel inoperable and apply the applicable ACTION statement requirements of Table 3.3.3 until the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.
l Equation 2.2-1 Z + R + S 5 TA Where:Z = The value from Column Z of Table 3.3-4 for the affected channel, R = Tne..:.asured" value (in percent span) of rack error for the affected channel, S = Either the "as measured" value (in percent span) of the sensor error, or the value from Column 5 (Sensor Error) of Table 3.3-4 for the affected channel, and TA = The value from Column TA (Total Allowance) of Table 3.3-4 for the affected channel.
c.
With an ESFAS instrumentation channel or interlock inoperable, take l
the ACTION shown in Table 3.3-3.
l CATAWBA - UNITS 1 & 2 3/4 3-13
e MSTRUMENTATION SURVEILLANCE REQUIREMENTS j
4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic
_ actuation logic and relays shall be demonstrated OPERABLE by performance of
?.he Engineered Safety Features Actuation System Instrumentation Surveillance Requirements specified in Table 4.3-2.
4.3.2.2 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months.*
l 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 per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 3.3-3.
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QThis surveillance need not be performed for items 7.a, 7.b, and 8 from Table 3.3-5 on Unit 2 until prior to entering HOT SHUTDOWN following the Unit 2 first refueling.
i CATAWBA - UNITS 1 & 2 3/4 3-14 Amendment No.29 (Unit 1) 4 Amendment No.20 (Unit 2) l
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3 TABLE 3.6-3
' DIVIDER BARRIER SEAL ACCEPTABLE PHYSICAL PROPERTIES TENSILE MATERIAL STRENGTH l
Membrane Type' Seals Mk 10 39.7 lbs Mk 11 39.7 lbs O
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CATAWBA - UNITS 1 & 2 3/4 6-53 d
_m_o.--__-________
CONTAINMENT SYSTEMS CONTAINMENT VALVE INJECTION WATER SYSTEM LIMITING CONDITION FOR OPERATION l
l 3.6.6 Both trains of the Containment Valve Injection Water System shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
I ACTION:
With one train of the Containment Valve Injection Water System inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least 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 /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.6.1 Each train of the Containment Valve Injection Water System shall be demonstrated OPERABLE at least once per 31 days by verifying that the system is pressurized to greater than or equal to 1.10 Pa (16.2 psig) and has ade-j quate capacity to maintain system pressure for at least 30 days.
4.6.6.2 Each train of the Containment Valve Injection Water System shall be j
demonstrated OPERABLE at least once per 18 months by verifying that the valve seal injection flow rate is less than 1.7 gpm (Unit 1), 1.6 gpm (Unit 2) for Train A and 1.4 gpm (Unit 1), 1.5 gpm (Unit 2) for Train B with a tank pressure greater than or equal to 45 psig and each automatic valve in the flow path actuates to its correct position on a Containment Pressure-High or a Containment Pressure-High-High test signal.**
I I
I l
Q*This surveillant which assures that "...the valve seal injection flow rate is less than.. 1.6 gpm (Unit 2) for Train A and.. 1.5 gpm (Unit 2) for Train B with a tank pressure greater than or equal to 45 psig" need not be per-formed on Unit 2 until prior to entering HOT SHUTDOWN following the Unit 2 first refueling.
CATAWBA - UNITS 1 & 2 3/4 6-54 Amendment No.29 (Unit 1)
Amendment No.29(Unit 2) 4 e
1 a
V PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) j 3)
Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position; 4)
Verifying that each automatic valve in the flow path _is in the-1 fully open position whenever the Auxiliary Fesdwater System is a
placed in automatic control or when above 10% RATED THERMAL POWER; and 5)
Verifying that the isolation valves in the auxiliary feedwater pump suction lines are open and that power is removed from i
the valve operators on Valves CA-2, CA-7A, CA-98, and CA-11A and that the respective circuit breakers are padlocked.
b.
At least once per 18 months during shutdown by:
J 1)
Verifying that each automatic valve in the flow path actua:es to its correct position upon receipt of an Auxiliary Feedwater Actuation test signal, 2)
Verifying that each motor-driven auxiliary feedwater pump starts as designed automatically upon receipt of an Auxiliary Feedwater Actuation test signal, 3)
Verifying that the turbine-driven auxiliary feedwater pump steam supply valves open upon receipt of an Auxiliary Feedwater Actua-tion test signal,** and l
)
4)
Verifying that the valve in the suctior. line of each auxiliary feedwater pump from the Nuclear Service Water System automatically actuates to its full open position within less than or equal to 15 seconds
- on a Loss-of-Suction test signal.
4.7.1.2.2 An auxiliary feedwater flow path to each steam generator shall be demonstrated OPERABLE following each COLD SHUTDOWN of greater than 30 days prior to entering MODE 2 by verifying normal flow to each steam generator, j
- Includet 5 second time delay.
i
- This surveillance need not be performed on Unit 2 until prior to entering HOT STANDBY following the Unit 2 first refueling.
CATAWBA - UNITS 1 & 2 3/4 7-5 Amendment No.29 (Unit 1)
Amendment No.20 (Unit 2)
4 PLANT SYSTEMS SPECI(ICACTIVITY f
l LIjjl]INGCONDITIONFOROPERATION f
3.7.1.3 The specific activity of the Secondary Coolant System shall be less than or' equal to 0.1 microcurie / gram DOSE EQUIVALENT I-131.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With the specific activity of the Secondary Coolant System greater than 0.1 microcurie / gram DOSE EQUIVALENT I-131, be in at least HOT STANDBY within 6 o
hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.-
1 SURVEILLANCE REQUIREMENTS 4.7.1.3 The specific activity of the Secondary Coolant System shall be determined to be within the limit by performance of the sampling and analysis program of Table 4.7-1.
CATAWBA - UNITS 1 & 2 3/4 7-6
-. - ~.
_.m._
1 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l f.
At least once every 31 days by obtaining a sample of fuel oil in accordance with ASTM-D2276-78, and verifying that total particulate contamination is less than 10 mg/ liter when checked in accordance i
with ASTM-D2276-78, Method A; f
g.
At least once per 18 months by:
l 1)
Subjecting the diesel to an inspection, during shutdown, in f
accordance with procedures prepared in conjunction with its j
manufarWrer's recommendations for this class of standby service;***
l 2)
Verifying the generator capability to reject a load of greater than or equal to 825 kW while maintaining voltage at 4160 + 42.0 volts and frequency at 60 1 1.2 Hz; 3)
Verifying the generator capability to reject a load of greater than or equal to 5600 kW but less than or equal to 5750 kW without tripping.
The generator speed shall not exceed 500 rpm during and following the load rejection; 4)
Simulating a loss-of-offsite power by itself,** during shutdown, and:
a)
Verifying aeenergization of the emergency busses and load shedding from the emergency busses, and b)
Verifying the diesel starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 11 seconds, energizes the auto-connected emergency (accident) loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads.
After ener-gization, the steady-state voltage and frequency of the emergency busses shall be maintained
' 4160 1 420 volts l
and 60 1 1.2 Hz during this test.
5)
Verifying that on an ESF Actuation test signal, without loss-of-offsite power, the diesel generator starts on the auto-start signal and operates on standby for greater than or equal to 5 minutes.
The generator voltage and frequency shall be at 4160
- 420 volts and 60 1 1.2 Hz within 11 seconds after the auto-start signal; the steady-state generator voltage and frequency snall be maintained within these limits during this test; 6)
Simulating a loss-of-offsite power in conjunction with an ESF Actuation test signal, during shutdown, and a)
Verifying deenergization of the emergency husses and load shedding from the emergency busses;*
- his surveillance need not be performed until prior to entering HOT SHUTDOWN following the Unit 1 first refueling.
- This surveillance need not be performed on Unit 2 until prior to entering HOT SHUTDOWN following the Unit 2 first refueling.
CATAWBA - UNITS 1 & 2 3/4 8-5 Amendment No. 29(Unit 1)
Amendment No. 2aunit 2)
.