ML15113A153
| ML15113A153 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/18/1985 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duke Power Co |
| Shared Package | |
| ML15113A154 | List: |
| References | |
| DPR-38-A-137, DPR-47-A-137, DPR-55-A-134 NUDOCS 8505010629 | |
| Download: ML15113A153 (14) | |
Text
0,R REGjj NIE CUNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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K 0'
DUKE POWER COMPANY DOCKET NO.
50-269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 137 License No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated December 19, 1984, as supplemented on March 8, 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 set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, 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 Commission's regulations; 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 Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-38 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 137 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8505010629 850418 PDR ADOCK 05000269
-P RPDR
)
-2
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 6ohn )F. Stolz, Chief 6peating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 18, 1985
- ~REGU NIE UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 137 License No. DPR-47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated December 19, 1984, as supplemented on March 8, 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 set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, 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 Commission's regulations; 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 Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-47 is hereby amended to read as follows:
3.8 Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.137 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
-2
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h F. Stolz, Chief rating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 18, 1985
- ~
k REGj UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 134 License No. DPR-55
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated December 19, 1984, as supplemented on March 8, 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 set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, 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 Commission's regulations; 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 Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-55 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 134 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 2
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION oh F. Stolz, Chief rating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 18, 1985
ATTACHMENTS TO LICENSE AMENDMENTS AMENDMENT NO.137 TO DPR-38 AMENDMENT NO. 137 TO DPR-47 AMENDMENT NO.134 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Replace the following-pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment numbers and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 2.1-3a 2.1-3a 2.1-3b 2.1-3b 3.5-16 (3 pages) 3.5-16 (1 page) 3.5-19 (3 pages) 3.5-19 (1 page) 3.5-22 (3 pages) 3.5-22 (1 page) 3.5-25 (2 pages) 3.5-25 (1 page) 3.5-28 (1 page) 3.5-28 (1 page)
Bases -
Unit 2 The safety limits presented for Oconee Unit 2 hav been generated using the BAW-2 and BWC critical heat flux correlations 1'3 and the Reactor Coolant System flow rate of 106.5 percent of the design flow (design flow is 352,000 gpm for four-pump operation).
TIe)flow rate utilized is conservative compared to the actual measured flow rate To maintain the integrity of the fuel cladding and to prevent fission product release, it is necessary to prevent overheating of the cladding under normal operating conditions.
This is accomplished by operating within the nucleate boiling regime of heat transfer, wherein the heat transfer coefficient is large enough so that the clad surface temperature is only slightly greater than the coolant temperature. The upper boundary of the nucleate boiling regime is termed "departure from nucleate boiling" (DNB). At this point, there is a sharp reduction of the heat transfer coefficient, which would result in high cladding temperatures and the possibility of cladding fail ure. Although DNB is not an observable parameter during reactor operation, the observable parameters of neutron power, reactor coolant flow, temperat re,,
and pressure can be related to DNB through the use of the CHF correlations 1' 3.
The BAW-2 and BWC correlations have been developed to predict DNB and the location of DNB for axially uniform and non-uniform heat flux distributions.
The local DNB ratio (DNBR), defined as the ratio of the heat flux that would cause DNB at a particular core location to the actual heat flux, is indicative of the margin to DNB. The minimum value of the DNBR, during steady-state operation, normal operational transients, and anticipated transients is limited to 1.30 (BAW-2) or 1.18 (BWC).. A DNBR of 1.30 (BAW-2) or 1.18 (BWC) corresponds to a 95 percent probability at a 95 percent confidence level that DNB will not occur; this is considered a conservative margin to DNB for all operating conditions.
The difference between the actual core outlet pressure and the indicated reactor coolant system pressure has been considered in determining the core protection safety limits.
The difference in these two pressures is nominally 45 psi; however, only a 30 psi drop was assumed in reducing the pressure trip setpoints to correspond to the elevated location where the pressure is actually measured.
The curve presented in Figure 2.1-1B represents the conditions at which a minimum allowable DNBR is predicted for the maximum possible thermal power (112 percent) when four reactor coolant pumps are operating (minimum reactor coolant flow is 374,880 gpm).
This curve is based on the following nuclear power peaking factors with potential fuel densification and fuel rod bowing effects:
N N(3 N
F
= 2.565; F
= 1.71 3 ) F N = 1.50 q
AHz The design peaking combination results in a more conservative DNBR than any other power shape that exists during normal operation.
The curves of Figure 2.1-2B are based on the more restrictive of two thermal limits and include the effects of potential fuel densification and fuel rod bowing:
Amendments Nos. 137
, 137
, & 134 2.1-3a
- 1.
The combination of the radial peak, axial peak and position of the axial peak that yields no less than the CHF correlation limit.
- 2.
The combination of radial and axial peak that causes central fuel melting at the hot spot. The limit is 20.15 kw/ft for fuel rod burnup less than or equal to 1,000 MWD/MTU and 21.2 kw/ft after 1,000 MWD/MTU.
Power peaking is not a directly observable quantity, and, therefore, limits have been established on the basis of the reactor power imbalance produced by the power peaking.
The specified flow rates of Figure 2.1-3B correspond to the expected minimum flow rates with four pumps, three pumps, and one pump in each loop, respectively.
The curve of Figure 2.1-lB is the most restrictive of all possible reactor coolant pump-maximum thermal power combinations shown in Figure 2.1-3B.
A B&W topical report discussing the Te5 hanisms and resulting effects of fuel rod bow has been approved by the NRC 4.
The report concludes that the DNBR penalty due to rod bow is insignificant and unnecessary, because the power production capability of the fuel decreases with irradiation. Therefore, no rod bow DNBR penalty needs to be considered for thermal-hydraulic analyses.
The maximum thermal power for three-pump operation is 88.07 percent due to a power level trip produced by the flux-flow ratio 74.7 percent flow x 1.07 =
79.92 percent power plus the maximum calibration and instrument error. The maximum thermal power for other coolant pump conditions is produced in a similar manner.
For each curve of Figure 2.1-3B, a pressure-temperature point above and to the left of the curve would result in a DNBR greater than the CKF correlation limit or a local quality at the point of minimum DNBR less than the CHF correla tion quality limit for that particular reactor coolant pump situation. The curve of Figure 2.1-1B is the most restrictive of all possible reactor coolant pump-maximum thermal power combinations shown in Figure 2.1-3B.
References (1) Correlation of Critical Heat Flux in a Bundle Cooled by Pressurized Water, BAW-10000, March 1970.
(2) Oconee 2, Cycle 4 - Reload Report, BAW-1491, August 1978.
(3) Correlation of 15 x 15 Geometry Zircaloy Grid Rod Bundle CHF.Data with the BWC Correlation, BAW-10143P, Part 2, Babcock & Wilcox, Lynchburg, Virginia, August 1981.
(4) Fuel Rod Bowing in Babcock & Wilcox Designs, BAW-10147P-A, Rev. 1, Babcock & Wilcox, May 1983.
Amendments Nos. 137
, 137
, & 134 2.1-3b
POWER LEVEL CUTOFF=100% FP 100-(220,102)
(300,102)
RESTRICTED (260,90)
OPERATION 80 (240,80)
UNACCEPTABLE OPERATION 60
.0 O
(160,50)
(200,50)
C, U 40 SHUTDOWN MARGIN ACCEPTABLE LIMIT OPERATION 20 (90,15)
(0,5) 0, 0
50 i5 200 250 300 ROD INDEX.%WD 0
25 50 75 100 BANK 5 0
25 50 75 100 BANK 6 25 50 75 100 BANK 7 ROD POSITION LIMITS FOR FOUR PUMP OPERATION FROM 0 EFPD TO EOC UNIT 2 OCONEE NUCLEAR STATION Amendments Nos. 1 3 7,
- 137, 134 Figure 3.5.2-2 3.5-16(1 of 1)
100 RESTRICTED OPERATION 80 (210,77)
(236.77)
(300,77)
LL 0
UNACCEPTABLE (160,50)
(200,50)
C OPERATION 40 SHUTDOWNACCEPTABLE MARGIN ACPAL LIMIT
-OPERATION 20 (90,15)
(0,5) 0 0
50 100 150 100 250 300 ROD INDEX,%WD 0
25 50 75 100 BANK5 0
25 50 75 100 BANK 6 0
25 50 75 100 BANK 7 ROD POSITION LIMITS FOR THREE PUMP OPERATION FROM 0 EFPD TO EOC UNIT 2 Amendments os 137 137 134ouPow OCONEE NUCLEAR STATION 3.5-19 Figure 3.5.2-5 (1 of 1)
100 80 U.
960 RESTRICTED c
OPERATION LLU CL(170,52)
(2 35 )(3(X),52 UNACCEPTABLE 0
OPERATION (200,50)
- 2) 0 40 0
0100 150 200 250 300 MARGNROD INDEXAWC 0
100 11 ROIIDXW BANK 5 0
25 50 75 100 BANK 6 0
25 50 75 10 BANK7 ROD POSITION LIMITS FOR TWO PUMP OPERATION FROM 0 EFPD TO EOC UNIT 2
[PowE OCONEE NUCLEAR STATION Amendments Nos.
137, 137., & 134 3.5-22 Figure 3.5.2-8 (1 of 1)
REACTOR POWER,%FP
(-20.0,102.0) 100 (30.0,102.0) 100 (00120 ACCEP ABLE
(-30.0,90.0)
APERPTION OPER kTION
- 80
- 60 RESTRICTED OPERATION RESTRICTED OPERATION
- 40 20
-100
-80
-60
-40
-20 0
20 40 60 80 100 IMBALANCE,%
-OPERATIONAL POWER IMBALANCE ENVELOPE FROM 0 EFPD TO EOC UNIT 2 m~EPUI OCONEE NUCLEAR STATION Amendments Nos.
137,
137, & 134 3.5-25 Figure 3O E.AR T
I Figure 3.5.2-11 (1 of 1)
Figure 3.5.2-14 (Deleted)
[Note that no rod position limits exist for Unit 2 axial power shaping rods.]
Amendments Nos.
137, 137
, & 134 3.5-28