ML20148F992
| ML20148F992 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/21/1988 |
| From: | Crocker L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20148F996 | List: |
| References | |
| NUDOCS 8803280359 | |
| Download: ML20148F992 (10) | |
Text
. _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _
sMsc oq'o UNITED STATES
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NUCLEAR REGULATORY COMMISSION g
- j WASHINGTON. D. C. 20555
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Ol'KE POWER COMPANY NORTH CAROLINA ELECTR!C MEMBERSHIP CORPORATION SAltinA RIVER ELECTRIC COOPERATIVE, INC.
CATAWRA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 42 License No. NPF-35 1.
The Nuclear Pegulatory 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 Duke Power Comnany acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc., M icensees) dated February 10, 1988, complies with the standards and reouirements of the Atomic Energy Act of 1954, 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 conformiiy with the application, as amended, the provisions of the Act, and the rules and reaulations of the Comission; C.
There is reasonable assurance (i) th6t the activities authorized by this amendment can be conducted without endangerina 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 CFP Chapter I; D.
The issuance of this anendment 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 of the Comission's regulations and all applicable reauirements 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 ?.C.(21 of Facility Operating License No. NPF-35 is hereby amended to read as follows:
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. (2) Te_chnical Specifications The Technical Specifications contained in Appendix A, as revised through Arnendment No. 42, and the Environmental Protection Plan contained 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 Original signed by:
Lawrence P. Crocker, Acting Director Droject Directorate 11-3 Division of Reactor Projects I/II
Attachment:
Technical Specification Changes Date of Issuance: March 21, 1988 h
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NUCLEAR REGULATORY COMMISSION
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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO.50-41a CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Arerdment No. 35 License No.
NPF-57 1.
The Nuclear Regulatory Comission (the Comission) har found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) 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 (licensee) dated February 10, 1988 complies with the standards and requirements of the Atomic Eneroy 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, as amended, 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 reaulations set forth in 10 CFR l
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 regulat:ons 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, l
and Pargraph 2.C. (2) of Facility Operating License No. NPF-52 is hereby l
charged to read as follows-i l
1 1
. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 35, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incoroorated 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 issuar.ce.
FOR THE NUCLEAR REGULATORY COMMISSION Original signed by:
Lawrence P. Crocker, Acting Director Project Directorate II-3 Division of Reactor Projects I/II
Attachment:
Technical Specification Changes Date of Issuance:
Marbh 21, 1988 PDI3/CRPI/II PDI 3 PI/II SFXB4 0G0
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ATTACHMENT TO LTCENSE AMENDMENT NO. 42 FACILITY OPEPATING L! CENSE NO. NPF-35 DOCKET NO. 50 d13 AND TO LICENSE AMENDPENT NO. 35 FACILITY OPERATING LTCENSE 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.
Amended Overleaf Page Page 24 2-3 3/4 ?-9 3/4 2-10 3/4 2-11
o SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS 2.2.1 The Reactor Trip System Instrumentation and Interlocks Setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2-1.
APPLICABILITY:
As shown for each channel in Table 3.3-1.
ACTION:
With a Reactor Trip System Instrumentation or Interlock Setpoint a.
.less conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value Column of Table 2.2-1, adjust the Setpoint consistent with the Trip Setpoint value.
b.
With the Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Allowable Values column of Table 2.2-1, either:
1.
Adjust the Setpoint consistent with the Trip Setpoint value of Table 2.2-1 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 was satisfied for the affected channel, or 2.
Declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1 until the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.
Equation 2.2-1 Z + R + 5 < TA Where:
Z=
The value from Column Z of Table 2.2-1 for the affected channel, R=
The "as measured" 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 S (Sensor Error) of Table 2.2-1 for the affected channel, and TA = The value from Column TA (Total Allowance) of Table 2.2-1 for the affected channel.
l i
CATAWBA - UNITS 1 & 2 2-3 l
k TABLE 2.2.-1 g
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS E
TOTAL SENSOR ALLOWANCE ERROR cz FUNCTIONAL UNIT (TA)
Z (S)
TRIP SETPOINT ALLOWABLE VALUE N
1.
Manual Reactor Trip N.A.
N.A.
N.A.
N.A.
N.A.
[
2.
Power Range, Neutron Flux a.
High Setpoint 7.5 4.56 9
$109% of RTP*
$111.1% of RTP*
m b.
Low Setpoint 8.3 4.56 0
125% of RTP*
$27.1% of RTP*
3.
Power Range, Neutron Flux, 1.6 0.5 0
<S% of RTP* with
<6.3% of RTP* with High Positive Rate i time constant a time constant 1 2 seconds 3 2 seconds 4.
Power Range, Neutron Flux,
- 1. 6
- 0. 5 0
55% of RTP* with 16.3% of RTP* with High Negative Rate a time constant a time constant 22 seconds 22 seconds m
A S.
Intermediate Range, 17.0 8.4 0
125% of RTP*
<31% of RTP*
Neutron Flux 6.
Source Range, Neutron Flux 17.0 10 0
$105 cps
$1.4 x 10 cps 5
7.
Overtemperature AT 7.2(8.9 )
4.47(5.41 )
2.03(2.65 ) See Note 1 See Note 2 8.
Overpower AT 4.3(4.9 )
1.3(1.24 )
1.2(1.7 )
See Note 3 See Note 4 gg 9.
Pressurizer Pressure-Low 4.0 2.21
- 1. 5 21945 psig 11938 psig***
10.
Pressurizer Pressure-High 7.5 4.96 0.5
-<2385 psig
-<2399 psig gg 11.
Pressurizer Water Level-High S.0 2.18 1.S
$92% of instrument <93.8% of instrument eo span span ff 12.
Reactor Coolant Flow-Low 2.5 1.77(1.41 )
0.6 190% of loop 389.2% (88.8% ) of loop:
minimum measured minimum measured flow **~
UE flow **
22 as37
- RTP = RATED THERMAL POWER
- Loop minimum measured flow = 96,900 gpm m-
~
- Time constants utilized in the lead-lag controller for Pressurizer Pressure-Low are 2 seconds for lead and 1 second for lag. Channel calibration shall ensure that these time constants are adjusted to these values.
- Applicable upon deletion of RTO Bypass System.
POWER DISTRIBUTION LIMITS 3/4.2.3 REACTOR COOLANT SYSTEM FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LIMITING CONDITION FOR OPERATION 3.2.3 The combination of indicated Reactor Coolant System total flow rate and R shall be maintained within the region of permissible operation shown on Figure
{
3.2-3 for four loop operation.
Where:
F"H a
R = l.49 [1.0 + 0.3 (1.0 - P)]
a' b*
P _
THERMAL POWER and RATED THERMAL POWER
=MeasuredvaluesofFhobtainedbyusingthemovableincore c.
F H
detectors to obtain a power distribution map.
The measured values of F shall be used to calculate R since Figure 3.2-3 H
includes penalties for undetected feedwater venturi fouling of 0.1% and for measurement uncertainties of 2.1% for flow and 4%
for incore measurement of F H'
APPLICABILITY:
MODE 1.
ACTION:
a.
With the combination of Reactor Coolant System total flow rate and R within the region of restricted operation (flow rate less than 387,600 gpm),
l within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> reduce the Power Range Neutron Flux-High Trip Setpoint to below the nominal setpoint by the same amount (% RTP) as the power reduction required by Figure 3.2-3.
b.
With the combination of Reactor Coolant System total flow rate and R within the region of prohibited operation shown on Figure 3.2-3:
i 1.
Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either:
1 l
a)
Restore the combination of Reactor Coolant System total flow rate and R to within the region of permissible operation, or l
b)
Restore the combination of Reactor Coolant System total flow I
rate and R to within the region of restricted operation and comply with action a.
sbove, or c)
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and reduce the Power Rango Neutron Flux - High Trip Setpoint to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
2.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of initially being within the region of prohibited l
operation shown on Figure 3.2-3, verify through incore flux mapping and Reactor Coolant System total flow rate comparison that the com-bination of R and Reactor Coolant System total flow rate are restored l
to within the regions of restricted or permissible operation, or l
l reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
CATAWBA - UNITS 1 & 2 3/4 2-9 Amendment No. 42 (Unit 1)
Amendment No. 35 (Unit 2)
POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION _{ Continued) 3.
.'dentify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION b.1.c) and/or b.2.,
above; subsequent LOWER OPERA-l TION may proceed provided that the combination of R and indicated Reactor Coolant System total flow rate are demonstrated, through incore flux mapping and Reactor Coolant System total flow rate comparison, to be within the regions of restricted or permissible l
operation shown on Figure 3.2-3 prior to exceeding the following THERMAL POWER levels:
a)
A nominal 50% of RATED THERMAL POWER, b)
A nominal 75% of RATED THERMAL POWER, and c)
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining greater than or equal to 95%
of RATED THERMAL POWER.
SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.
4.2.3.2 The combination of. indicated Reactor Coolant System total flow rate determined by process computer readings or digital voltmeter measurement and R shall be determined to be within the regions of restricted or permissible l
operation of Figure 3.2-3:
a.
Prior to operation above 75% of RATED THERMAL POWER after each fuel loading, and b.
At least once per 31 Effective Full Power Days.
4.2.3.3 The indicated Reactor Coolant System total flow rate shall be verified to be within the regions of restricted or permissible operation of Figure 3.2-3 l
at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the most recently obtained value of R, obtained per Specification 4.2.3.2, is assumed to exist.
4.2.3.4 The Reactor Coolant System total flow rate indicators shall be subjected i
to a CHANNEL CALIBRATION at least once per 18 months.
The measurement instrumentation shall be calibrated within 7 days prior to the performance of l
the calorimetric flow measurement.
4.2.3.5 The Reactor Coolant System total flow rate shall be determined by precision heat balance measurement at least once per 18 months.
l l
1 l
l CATAWBA - UNITS 1 & 2 3/4 2-10 Amendment No. 42(Unit 1)
Amendment No. 35(Unit 2) l
PENAL.T115 0F O.1% FOR UNDETICTED FEEDWATER VENTURI FOUUNG AND MEASUREMENT UNCERTAINTIES OF 2.1% FOR FLOW AND 4.0% FOR INCORE MEASUREMENT OF F ARE INCLUDED IN THis FIGURL
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,i POWER < 92% RTP,i..
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FIGURE 3.2-3 REACTOR CCOLANT SYSTEM TOTAL Flow RATE VER$US R - 800R LOOPS IN OPERATION Amendment No. 42 (Unit 1)
Amendment No. 35 (Unit 2)
CATA14A - UNIT 31 & 2 3/4 2-11
- - -