ML20236U704
| ML20236U704 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/24/1987 |
| From: | Crocker L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236U706 | List: |
| References | |
| NUDOCS 8712030304 | |
| Download: ML20236U704 (9) | |
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'o 1 a UNITED STATES E '~ Y
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NUCLEAR IWGULATORY COMMISSION r
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'DUV,E POWER COMPANY b
NORTH CAROLINA ELECTRIC hh,3.8..E.R.. SHIP CORPORATION SALUDA RIVER ELECTRIC AMOPERATIVE, INC.
o DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 a(.
' AMENDMENT TO FACILITY OPERAlING UCENSE o
Amendment No. 34 N
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o License No. NPF-35 1.
The Nu(.let.r Regulatory Comissics (the Comission) has found that:
l A.
The application for amendant to the Catawba Nuclear Station, Unit 1 I
(the facility) Facility Operatfr.g License No. NPF-35 filed by the Duke I
Power Company acting for itself, North Carolina Electric Membership),
Corporation and Saluda River Electric Ceoperat',ve, Inc., (licensees dated July 31, 1985, and supplemented November 8 and December 26, 1985, March 7, 1986, and July 1, 1987, complies vith the standards and reactrements' of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and reguladons as set forth in 10 CFR Chapter I;
- j. The facility w m bperate in conformity with the application, as-amended, the provisions of the Act, and the rules and regulations of i
the Commission;
.I C.
There is reasonable assurance: (1) that t};e activities authorized by this ' amer.dment can be conducted without erpangering the health and safety of the public, and (ii) that such k tivities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I;-
0 The issuancLct this license amendment will not be inimical to the f..;e>
J comon defense a'ra security or to the health and safety of the public; n
m f
E.
The ishuance of this amendment is in accordence with 10 CFR Part 51 of the Comisstfs regulations and all appMcable requirements have
,been satisfied.
,a t
( 2.
Acd.vdjngly, the license is hereby amended by pMchanges to the Technical l
Specifications as indicated"in the attachments,to this license amendment and
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Pathgraph 2.C.(2) of Facility Operating License No. NPF-35 is hereby amended
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to read as follows:
i' l
!('2) Technical Specifications and Environmental Protection Plan
~h The' Technical Specifications contained in Appendix 4, as revised
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q through Amendment No. 34, and the Environmental Protection Plan 8732030304 871124 PDR ADO (K 05000413 ck l
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-2
. u contained in Appendix B, both of which are attached hereto, are 7
hereby incorporated into this license.
Duke Power Company shall operate the facility in accordance with the Technical Specifications e
and the Environmental Protection Plan.
3.
This 1: cense ansndment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Lawrence P. Crocker, Acting Director Project Directorate II-3 Div1M on o. N ctor Projects I/II
Attachment:
Technical Specification Changes
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Date of IsstJance: November 24, 1987 I
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- SEE PREVIOUS CONCURRENCE wL
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Acting Director 02/4/87 02/4/87 11/i
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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY N0. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 25 License No. NPF 1.
The Nuclear Regulatory Comission (the Commission) has 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 Munici No. I and Piedmont Municipal Power Agency. (licensees) pal Power Agency dated July 31, 1985, and supplemented November 8 and December 26, 1985, March 7, 1986, and July 1,1987, complies with the standards and requirements 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 conformity with the application, as amended,'the provisions of the Act, and the rules and regulations of the Comission; j
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 Comission's regulations set forth in 10 CFR l
Chapter I;
{
l D.
The issuance of this license amendment will not be inimical to the 1
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 4
Paragraph 2.C.(2) of Facility Operating License No. NPF-52 is hereby amended 1
to read as follows:
(2) Technical Specifications and Environmental Protection Plan -
a The Technical. Specifications contained in Appendix A, as revised l
through Amendment No.
25, and the Environmental Protection Plan i
__A
contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.- Duke Power Company shall.
operate the.. facility in accordates 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-Lawrence P. Crocker, Acting Director
. Project Directorate II Division'of Reactor Projects I/II
Attachment:
Technical Specification Changes Date of Issuance:
November 24, 1987 l
l l
l l
l 1
II A
- SEE PREVIOUS CONCURRENCE PWR#yDfWR-A PWR# /DPWR-A 0L PD I-3/DRPI/II-
- MDuncan:mac
- KJabbour gm Acting //87 Director-02/4/87 02/4/87.
11/lo /87 11//
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I ATTACHMENT TO LICENSE AMENDMENT NO. 34
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FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 i
AND i
l TO LICENSE AMENDMENT N0. 25
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FACILITY OPERATING LICENSE N0. NPF-52 DOCKET NO. 50-414 i
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendmer,t number and l
contain vertical lines indicating the areas of change. -The corresponding overleaf page is also provided to sr.aintain document repleteness.
l Amended-Overleaf Page Pag 3/4 2-9 l
3/4 2-10 3/4 2-11 3/4 2-12 l
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POWER DISTRIBUTION LIMITS 3/4.2.3 REACTOR COOLANT SYSTEM FLOW RATE AND NUCLEAR ENTHALPY RISE HOT i
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 regior, of allowable operation shown on Figure 3.2-3 for four loop operation.
Where:
N FAH R = 1.49 [1.0 + 0.3 (1.0 - P)]
a.
THERMAL POWER and b*
P
= RATED THERMAL POWER c.
F H = Measured values of F obtained by using the movable incore g
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:
With the combination of Reactor Coolant System total flow rate and R within a.
the region of acceptable operation with the flow rate less than 396100 gpm, i
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 outside the region of acceptable operation shown on Figure 3.2-3:
1.
Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either-a)
Restore the combination of Reactor Coolant System total flow rate and R to within the above limits, or b)
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER l
and reduce the Power Range Neutron Flux - High Trip Setpoint 4
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 outside the above limits, verify l
through incore flux mapping and Reactor Coolant System total flow rate comparison that the combination of R and Reactor Coolant System total flow rate are restored to within the above limits, or 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.34 (Unit 1)
Amendment No.25 (Unit 2)
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POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continued)
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3.
Identify and correct the cause of the out-of-limit condition prior l
to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION a.2, and/or b., above; subsequent POWER OPERA-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 region of acceptable operation shown on Figure 3.2-3 prior to exceeding the following THERMAL POWER levels:
a)
A nominal 50%'of. RATED THERMAL POWER, l
b)
A nominal 75% of RATED THERMAL POWER, and l.
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%
l 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 region of acceptable operation of Figure 3.2-3:
Prior to operation above 75% of RATED THERMAL POWER after each fuel a.
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 region of acceptable operation of Figure 3.2-3 at least once
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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 Specifica-tion 4.2.3.2, is assumed to exist.
4.2.3.4 The Reactor Coolant System total flow rate indicators shall be subjected to a CHANNEL CALIBRATION at least once per 18 months.
The measurement instrumentation shall be calibrated within 7 days prior to the performance of 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.
i CATAWBA - UNITS 1 & 2 3/4 2-10 Amendment No.34 (Unit 1)
Amendment No. 25 (Unit 2)
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FOULING AND MEASUREMENT UNCERTAINTIES OF 2.1% FOR 4
s i'
f'.
FLOW AND 4.0% FOR INCORE MEASUREMENT OF F$g ARE lj-INCLUDED IN THIS FIGURE.
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i 6 ACCEPTABLE' UNACCEPTABLE I
i itiItii t 1 ifI ii iittieiIIi aiieiaiii441 66I 6I iei6i6i '
OPERATION.
OPERATION
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REGION
. REGION i
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o-o (1.000,39.610) g j.
O 39.5 - 22[ ACCEPTABLE FOR i
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I e e i i e i i I t-1 t 6 6 4 i eii4 6 4 & 4 I-i
(([ P0kTR 5 98% RTP r
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ACCEPTABLE FOR I
g eit t ti eiiIt
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a 39*0"
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POWER 5 96%' RTP 7'
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E i e i l it i i 4 4 i I
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ACCEPTABLE FOR I'
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t t I i i t iIt i 1 1
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"'~~-' POkTR'194% RTP I
e 1 66 i i !iil 4 4 4
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4, 38.5 =
'it t i t t t i i tti t J
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(0.982,38.422) l u
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g ACCEPTABLE FOR I
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6 i i eiiieiiti r
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i POWER 1 92% RTP I
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38.0 ;
-~ (0.977,38.026) ii i 16ei6646iit J
t ACCEPTABLE FOR, i J
't it it eiit i
a eiiie1 61 4 6 1
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POWER 190% RTP i.
IIIittItItI ri ei6 I II IeI i r j (0.971,37.630.)
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37.5 =
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a a
0.95 0.96 0.97 0.98 0.99 1.00 1.01 1.02 n. r;,n.a n..m.m 4
FIGURE 3.2-3 REACTOR COOLANT SYSTEM TOTAL FLOW RATE VERSUS R - FOUR L CATAWBA - UNITS 1 & 2 3/4 2-11 Amendment No. 34 (Unit 1)
Amendment No. 25 (Unit 2)
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POWER DISTRIBUTION LIMITS
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3/4.2.4 QUADRANT POWER TILT RATIO LIMITING CONDITION FOR OPERATION 3.2.4 The QUADRANT POWER TILT RATIO shall not exceed 1.02 above 50% of RATED THERMAL POWER.
APPLICABILITY:
MODE 1.*
ACTION:
With the QUADRANT POWER TILT RATIO determined to exceed 1.02 but a.
less than or equal to 1.09:
1.
Calculate the QUADRANT POWER TILT RATIO at least once per hour until either:
a)
The QUADRANT POWER TILT RATIO is reduced to within its limit, or b)
THERMAL POWER is reduced to less than 50% of RATED THERMAL POWER.
2.
Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either-
)
a)
Reduce the QUADRANT POWER TILT RATIO to within its limit, or b)
Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for each 1% of indicated QUADRANT POWER TILT RATIO in excess of I and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
3.
Verify that the QUADRANT PDWER TILT RATIO is within its limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding the limit or reduce THERMAL POWER to less than 50% 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 /> and reduce the Power Range Neutron Flux-High Trip Setpoints 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 />; and 4.
Identify and correct the cause of the out of-limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified acceptable at 95%
or greater RATED THERMAL POWER.
- See Special Test Exceptions Specification 3.10.2.
CATAWBA - UNITS 1 & 2 3/4 2-12
. _ _ _ _ _ _ _.. _. _ _ _. _ _.