ML20205M378
| ML20205M378 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/27/1987 |
| From: | Jabbour K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205M383 | List: |
| References | |
| NUDOCS 8704020370 | |
| Download: ML20205M378 (9) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION e
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WASHINGTON, D. C. 20555 DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.
DOCKET N0. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 24 l
License No. NPF-35 l
1.
The Nuclear Regulatory Commission (the Commission) 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 August 7,1985, and supplemented November 8, and December 4 and 20, 1985, 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; 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 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; l
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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page chanaes 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 Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 24, and the Environmental Protection Plan 8704020370 870327 PDR ADOCK 05000413 P
contained in Apoendix B, both 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 Kahtan Jabbour, Project Manager PWR Project Directorate No. 4 Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: March 27, 1987 4
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UNITED STATES f
NUCLEAR REGULATORY COMMISSION 8
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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDM0NT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.14 License No. NPF-52 1.
The Nuclear Regulatory Comission (the Comission) 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 Municipal Power Agency No. I and Piedmont Municipal Power Agency, (licensees) dated August 7, 1985, and supplemented November 8, and December 4 and 20,1985, 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 conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance: (1)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and safety of the oublic, 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 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-52 is hereby amended to read as follows:
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.14, and the Environmental Protection Plan i
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contained in Appendix B, both 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 N
Kahtan Jabbour, Project Manager PWR Project Directorate No. 4 Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: March 27, 1987 1
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ATTACHMENT TO LICENSE AMENDMENT NO. 24 FACILITY OPERATING LICENSE N0. NPF-35 DOCKET NO. 50-413 AND TO LICENSE AMENDMENT NO. 14' 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 overleaf pages are also provided to maintain document completeness.
/ vended Overleaf Page Page l
3/4 2-16 3/4 2-15 B 3/4 2-6 8 3/4 2-5 i
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POSER DISTRIBUTION LIMITS.
3/4.2.5 DNB PARAMETERS I
l LIMITING CONDITION FOR OPERATION 7
-3.2.5 The following DNB related parameters shall be maintained within the limits shown on Table 3.2-1:
i Reactor Coolant System T,yg, and a.
I b.
Pressurizer Pressure.
APPLICABILITY:
MODE 1.
ACTION:
With any of the above parameters exceeding its limit, restore the parameter to j
within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 5% of i
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 />.
SURVEILLANCE REQUIREMENTS i
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4.2.5 Each of the parameters of Table 3.2-1 shall be verified to be within their limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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CATAWBA - UNITS 1 & 2 3/4 2-15 j
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l TABLE 3.2-1 DNB PARAMETERS PARAMETER LIMITS Four Loops in Operation Average Temperature Meter Average
- 4 channels:
< 592*F
- 3 channels:
5592*F Computer Average
- 4 channels:
< 593*F
- 3 channels:
{593*F Pressurizer Pressure Meter Average
- 4 channels:
> 2227 psig*
- 3 channels:
1 2230 psig*
Computer Average
- 4 channels:
1 2222 psig**
- 3 channels:
> 2224 psig i
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- Limit not applicable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step in excess of 10% of RATED THERMAL POWER.
CATAWBA - UNITS 1 & 2 3/4 2-16 Amendment No. 24(Unit 1)
Amendment No.14(Unit 2)
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-POWER DISTRIBUTION LIMITS k
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BASES HEAT FLUX HOT CHANNEL FACTOR, and REACTOR COOLANT SYSTEM FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued)-
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N are measured, no additional When Reactor Coolant System flow rate.,and F3g allowances are necessary prior to comparison with the limits of Figure 3.2-3.
Measurement errors of 2.1% for Reactor Coolant System total flow rate and 4%
for F have been allowed for in determination of the design DNBR value.
H The measurement error for Reactor Coolant System total flow rate is based upon performing a precision heat balance and using the result to calibrate the Reactor Coolant System flow rate indicators.
Potential fouling of the feedwater venturi which might not be detected could bias the result from the precision heat balance in a nonconservative manner.
Therefore, a penalty of 0.1% for undetected fouling of the feedwater venturi is included in Figure 3.2-3.
Any fouling which might bias the Reactor Coolant System flow rate measurement i
greater than 0.1% can be detected by monitoring and trending various plant performance parameters.
If detected, action shall be taken before performing subsequent precision heat balance measurements, i.e., either the effect of the fouling shall be quantified and compensated for in the Reactor Coolant System flow rate measurement or the venturi shall be cleaned to eliminate the fouling.
The 12-hour periodic surveillance of indicated Reactor Coolant System flow is sufficient to detect only flow degradation which could lead to opera-tion cutside the acceptable region of operation shown on Figure 3.2-3.
3/4.2.4 QUADRANT POWER TILT RATIO The QUADRANT POWER TILT RATIO limit assures that the radial power distribu-tion satisfies the design values used in the power capability analysis.
Radial power distribution measurements are made during STARTUP testing and periodically during power operation.
The limit of 1.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x y plane power tilts.
A limit of 1.02 was selected to provide an allowance for the uncertainty associated with the indicated power tilt.
The 2-hour time allowance for operation with.a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned control rod.
In the event such action does not correct the tilt, the margin for. uncertainty on F is reinstated by reducing q
the maximum allowed power by 3% for each percent of tilt in excess of 1.
For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the moveable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the QUADRANT
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POWER TILT RATIO.
The incore detector monitoring is done with a full incore CATAWBA - UNITS 1 & 2 8 3/4 2-5
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l POWER DISTRIBUTION LIMITS i
BASES l
j' QUADRANT POWER TILT RATIO (Continued) flux map or two sets of four symmetric thimbles.
The two sets of four symmetric j
thimbles is' a unique set of eight detector locations. The' normal locations are C-8, E-5, E-11, H-3, H-13, L-5, L-11, N-8.
Alternate locations r.re available if any of the normal locations are unavailable.
3/4.2.5 DNB PARAMETERS The limits on the DNB-related parameters assure that each of the parameters are maintained within the normal steady-state envelope of operation assumed in the transient and accident analyses.
The limits are consistent with the I
initial FSAR assumptions and have been analytically demonstrated adequate to maintain a design limit DNBR throughout each analyzed transient.
The indicated T,yg value and the indicated pressurizer pressure value correspond to analytical limits of 594.8'F and 2205.3 psig respectively, with allowance for measurement uncertainty.
The 12-hour periodic surveillance of these parameters through instrument j}
readout is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient operation.
Indica-i tion instrumentation measurement uncertainties are accounted for in the limits provided in Table 3.2-1.
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CATAWBA - UNITS 1 & 2 B 3/4 2-6 Amendment No. 24 (Unit 1) j Amendment No.14 (Unit 2) o a