ML15112B114
| ML15112B114 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/03/1983 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duke Power Co |
| Shared Package | |
| ML15112B115 | List: |
| References | |
| DPR-38-A-122, DPR-47-A-122, DPR-55-A-119 NUDOCS 8308290013 | |
| Download: ML15112B114 (26) | |
Text
0 UNITED STATES AR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO.
50-269 OCONEE NUCLEAR STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.1 22 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 May 19, 1983, as supplemented July 13, 1983, 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 Chaoter I; B. The facility will operate in conformity with the application, the pro visions 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;
- 0. 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 satis fied.
- 2. Accordingly, the license is amended by changes to the Technicil-Specifications as indicated in the attachment to this license amendment and paragraph 3.8 of Facility Operating License No. DPR-38 is hereby amended to read as follows:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 122 are hereby incorporated in the license. The licensee shall operate the facility in accordance:
with the Technical Specifications.
8308290013 8306039 PDR ADOCK 05000269 PDR I
-2
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h F. Stolz, Chief Ope ating Reactors Bra 4
ision of Licensing
Attachment:
Changes to. the Technical Specifications Date of Issuance: August 3, 1983
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0. C. 20555 DUKE POWER COMPANY DOCKET NO.
50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 122 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 May 19, 1983, as supplemented July 13, 1983, 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 pro visions 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 satis fied.
- 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. OPR-47 is hereby amended to read as follows:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 122 are 1hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION n *F.
Stolz, Chief)
(Opratino Reactors Btanch i-Ovision of Licensing
Attachment:
Changes to the Technical Specifications.
Date of Issuance: August 3, 1983
- EGUNITED STATES o)
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. 119 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 May 19, 1983, as supplemented July 13, 1983, 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 Cha.pter I; B. The facility will operate in conformity with the application, the pro visions 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 an.d all applicable requirements have been satis fied.
- 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:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.119 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 Jo n F. Stolz, Chi 0 eratina Reactors qranch ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 3, 1983
ATTACHMENTS TO LICENSE AMENDMENTS AMENDMENT NO. 122 TO DPR-38 AMENDMENT NO. 122TO OPR-47 AMENDMENT NO. 119TO 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 2.1-2 2.1-2 2.1-3 2.1-3 2.1-7 2.1-7 2.3-8 2.3-8 3.5-15 3.5-15 3.5-15a 3.5-15a 3.5-15b 3.5-15b 3.5-18 3.5-18 3.5-18a 3.5-18a 3.5-18b 3.5-18b 3.5-18c 3.5-18c..
3.5-18d 3.5-18d 3.5-18e 3.5-18e 3.5-21 3.5-21 3.5-21a 3.5-21a 3.5-21b 3.5-21b 3.5-24 3.5-24 3.5-24a 3.5-24a 3.5-24b 3.5-24b
can be related to DNB through the use of the BAW-2 corelation (1).
The BAW-2 correlation has 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. A DNBR of 1.30 corresponds to a 95 percentprobability 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 jtrip setpoints to correspond to the elevated location where the pressure is actually measured.
The curve presented in Figure 2.1-1A represents the conditions at which a minimum DNBR of 1.30 is predicted for the maximum possible thermal power (112 percent) when four reactor coolant pumps are operating (minimum reactor coolant flow is 106.5 percent of 131.3 x 106 lbs/hr).
This curve is based on the combination of nuclear power peaking factors, with potential effects of fuel densification and rod bowing, which result in a more conservative DNBR than any other shape that exists during normal operation.
The curves of Figure 2.1-2A are based on the more restrictive of two thermal limits and include the effedts of potential fuel densification and rod bowing:
- 1.
The 1.30 DNBR limit produced by thecombination of the radial peak, axial peak and position of the axial peak that yields no less than a 1.30 DNBR.
- 2.
The combination of radial and axial peak that causes central fuel melting at the hot spot. The limit is 20.5 kw/ft for 8C, 9 and 1OC Batches-of fuel and 17.6 kw/ft for the IA, lOB gadolinia fuel, Batch for Unit. 1.
Power peaking is not a directly observable quantity and therefore lim'itr have been established on the bases of the reactor power imbalance produced by -the power peaking.
The specified flow rates of Figure 2.1-3A correspond to.the expected mi-ifimnuzm flow rates with four pumps, three pumps, and one pump in each loop, respectively.
The curve of Figure 2.1-1A is the most restrictive of all possible reactor coolant pump-maximum thermal power combinations shown i-n Figure 2.1-3A.
The magnitude of the rod bow penalty applied to each fuel cycle is equal to or greater than the necessary burnup dependent DNBR rod bow penalty for the ap plicable cycle minus a credit of 1% for the flow area reduction factor used in the hot channel analysis.
All plant operating limits are based on a minimum DNBR criteria of 1.30:plus the amount necessary to offset the reduction in DNBR due to fuel rod bow.
(3) 2.1-2 Amendmenvt los. 122, 122 & 11
The maximum thermal power for three-pump opertion is 8V.899 percent due to a power level trip produced by the flux-flow ratio 74.7 percent flow x 1.07 =
79.929 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 2.1-3A a pressure-temperature point above and to the left of the curve would result in a DNBR greater than 1.30 or a local quality at the point of minimum DNBR less than 22 percent for that particular reactor coolant pump situation. The curve of Figure 2.1-1A is the most restrictive of all possible reactor coolant pump-maximum thermal power combinations shown in Figure 2.1-3A.
References (1) Correlation of Critical Heat Flux in a Bundle Cooled by Pressurized Water, BAW-10000, March, 1970.
(2) Oconee 1, Cycle 4 -
Reload Report -
BAW-1447, March, 1977.
(3) Oconee 1, Cycle 8 -
Reload Report -
BAW-1774, February, 1983.
2.1-3 Amendment NaI. 122, 122 & 119
Thermal Power Level, %
120
= 1. 571
(-41.0,112.0)
(33.0,112)
ACCEPTABLE 110 1
2 = -1.100
(-48.0,101.0) '
4 PUMP I
OPERATION 100 (48.0. 95.5)
(-41.0,89.899).
(33.0,89.899)
ACCEPTABLE 4&3 PUMP
(-48.0,78.899) 1 80 OPERATION (48.0,73.399)
.70
(-41. 0, 62. 73)
(33.0,62.73)
ACCEPUTABLEN ASO (48. 0, 51. 73) 4,3&2 PUMP an 50 OPERATION O (48.0,46.23)
I.
so Co so 7 -
20 "W
UNACCEPTABLE I
nUNACCEPTABLE OPERATION
.10 IfOPERATION
-60
-40
-20 0
20 40 60 Reactor Power Imoalance, S CURVE RC FLOW (GPM) 1 374,880 2
280,035 3
183,690 CORE PROTECTION SAFETY LIMITS UNIT 1 suUmaU OCONEE NUCLEAR STATION Figure 2.1-2A 2.1-7 Amendment Nos. 122, 122 & 119
Tnermal Power Level, %
--120
(-1.7. 0, 107. 0)
.110 (17. 0,107.0)
M1 = 1.0625 ACEPABE 100 M2 =-1..3750 ACCEPTA8LE 4 PUMP
(-33. 0, 90.0)
OPERATION g
9 (17,
- 79. 92)
(17, 79.92)
(33. 0. 85.0)
UNACCEPTABLE UNACCEPTABLE OPERATION ACCEPTABLE OPERATION
- 4,3 PUMP
(-33.0,62.92)
OPERATION 1(-17,52. 43)
(17 (2.
- 43)
ACCEPTABLE
- 4.
4 4,3,2 PUMP (33. 0, 3 5. 43)0 OPERATION (33. 0,
- 30. 43)
II ALLOWABLEL SETPINT
-20 ~
NI 1
-60
-40,
-20 0
20 40 6
Reactor Power Imoalance,%
PROTECTIVE SYSTEM MAXIMUM ALLOWABLE SETPOINTS u OCONEE NUCLEAR STATION Figure 2.3-2A 2.3-8 Amendment Nos. 122, 122 & 119
OPERATION (204.102)
(280,102) 100*
NOT ALLOWED SHUTDOWN (300,102) POWER LEVEL MARGIN (275,92)
CUTOFF 100% FP LIMIT o80 (273,80)
C6 OPERATION RESTRICTED 60
- (139,50)
.(200,50)
S40 OPERATION ACCEPTABLE 20*
0 100 200 300 Roo Inoex. % Witnarawn GR 5' 0
75 100 GR 6 0
25 75 100 GR 7I 0
25 100 ROD POSITION LIMITS FOR FOUR-PUMP OPERATION, o to 26 +10/-0 EFPO, OCONEE 1, CYCLE 8 ounw OCONEE NUCLEAR STATION Figure 3.5.2-1A1 3.5-15 Amendment los. 122, 122 & 119
POWER LEVEL CUTOFF 100% FP (275, 102)(300,102)
(238.102).
100 (270.92)
PERATION
-4 80
- SHUTOOWN RTIEE (266,80)
MARGIN LIMIT OPERATION NOT ALLOWED 60 (173.50)
(200,50) 40 OPERATION ACCEPTABLE 20 0
I 0
100 200 300 Roa Inoex, % witnorawn GR 5I 0
75 100 GR S II 0
25 75 100 GR 7 i I
0 25 100 ROD POSITION LIMITS FOR FOUR-PUMP OPERATION, 26 +10/-0 TO 200 +/-10 EFPO OCONEE 1, CYCLE 8
'6w OCONEE NUCLEAR STATION Figure 3.5.2-1A2 3.5-15a Amendment Nos. 122, 122 & 119
(275,102) 100
-(238, 102),
(300,102) POWER LEVEL CUTOFF 100 FP (270,92)
PERATION 80 SHUTDOWN RESRICE (266,80)
MARGIN LIMIT OPERATION NOT 3
- o.
ALLOWED (173,50)
- (200,5) 40 OPERATION ACCEPTABLE
-6 20
<(0,68 0
I I
. I 0
100 200 300 Roo Inax, Witnorawn GR 5 0
75 100 GRS I
0 25 75 100 GR 7 0
25 100 ROD POSITION LIMITS FOR FOUR-PUMP OPERATION, AFTER 200 +/-10 EFPO, OCONEE 1, CYCLE 8 OCONEE NUCLEAR STATION Figure 3.5.2-1A3 3.5-1Sb Amendment Nos. 122, 122 & 119
100 ca 50 EQ 80 (204,77)
(265.7,77)
SHUTDOWN MARGIN PERATION LIMIT RESTRICTE UU OPERATION NOT ALLOWED
.(200,50) 40 (139,38) c 20 -OPERATION ACCEPTABLE 0
a- 0 OPRI ONACETAL 0
00 200 300 Rod Index, % withdrawn GR 5 0
75 100 GR s' 0
25 75 100 GR 7 L 0
25 100 ROD POSITION LIMITS FOR THREE-PUMP OPERATION, o to 26 +10/-0 EFPO, OCONEE 1, CYCLE 8 evenOCONEE NUCLEAR STATION Figure 3.5.2-2A1 3.5-18 Amendment Nos. 122, 122 & 119
100 OPERATION RESTRICTED 80 OPERATION (238.77) 259.4,77 Nor ALLOWED SHUTDOWN (300,71)
MARGIN So LIMIT
' (200, 50) 40 (173,38)
C3 OPERATION 20 ACCEPTASLE 0 (0.5.6) 00 100 200 300 Roa Inoex, S Wi tnarawn GR 5
...... I 0
75 100 GR 6' 0
25 75 100 GR 7 I
0 25 100 ROD POSITION LIMITS FOR THREE-PUMP OPERATION, 26 +10/-0 TO 200 +/-10 EFPD, OCONEE 1, CYCLE 8 OCONEE NUCLEAR STATION Figure 3.5.2-2A2 3.5-18a Amendment Nos. 122, 122 & 119
000 OPERATION RESTRICTED SO
- OPERATION (238,77) 259.4,77 NGT ALLOWED SHUTDOWN (300,77)
MARGIN 60 LIMIT Cu (200,50) 40*
(173,38)
OPERATION 20 ACCEPTABLE 0 (0.5-6) 0 100 200 300 Roa Inoex, % Witnarawn GR 5 0
75 100 GR 6 0
25 7.5 100 GR 7 0
25 100 ROD POSITION LIMITS FOR THREE-PUMP OPERATION, AFTER 200 +/-10 EFPD9 OCONEE 1, CYCLE 8 u OCONEE NUCLEAR STATION Figure 3.5.2-2A3 3.5-18b Amendment flos. 122, 122 & 119
100 80 OPERATION NOT ALLOWED 60 SHUTDOWN MARGIN (204.9.52)
(300,52)
LIMIT 40 20
,(139,26)
OPERATION ACCEPTABLE (0 4. 8 (648 )
0 0
100 200 300 Roo Inaex, % Witnerawn GR5 I
0 75 100 GR
' 0 25 75 100 GH7 I
0 25 100 ROD POSITION LIMITS FOR TWO-PUMP OPERATION, 0 to 26 +10/-0 EFPD, OCONEE 1, CYCLE 8 sure3s OCONEE NUCLEAR STATION Figure 3.5.2-2A4 3. 5-18c Amendment Na.. 122, 122 & 119
100
- 63.
80 OPERATION NOT ALLOWED 63 es 60.*
SoSUT0W (238. 52)
SHUTDOWN CS MARGIN Z
LIMIT 300,52 40 C3 LJ OPERATION ACCEPTABLE 20
- (173,25)
(0.4.4) 20 100 200 300 RoG Inoex, l witnarawn GR 5. a 75 100 GR 6 25 75 100 GR 7 0
25 100 ROD POSITION LIMITS FOR T140-PUMP OPERATION, 26 +10/-O TO 200 EFPO, OCONEE 1, CYCLE 8 u OCONEE NUCLEAR STATION Figure 3.5.2-2A5 3.5-18d Amendment flos. 122, 122 & 119
33 80 OPERATION NOT ALLOWED
.3 60 -
HTON(238,
- 52)
MARGIN LIMIT(300,52) 40 OPERATION ACCEPTABLE 20 (173,28)
(0,4.4),
100 200 300 Roo naex, % Witnarawn 0
75 100 GR 6 1I 0
25 75 100 GR 71 0
25 100 R00 POSITION LIMITS FOR TWO-PUMP OPERATION, AFTER 200 +/-10 EFPO, OCONEE 1, CYCLE 8 s ure OCONEE NUCLEAR STATION Figure 3.5.2-2A6
- 3. 5-18e Amendment Nlos.
122,-_T22 & 119
-. 17.4, 9 )
so(25
- 92)
(-24.8,80) f0 (30, 80)
N OPERATION 70 ACCEPTABLE a
640 02 140
.40
-30
-20
.0 20 3040 Axial Power Imcalance, POWER IMBALANCE LIMITS FOR 0 to 26 +10/-0 EFPO,
~
OCONEE 1, CYCLE 8 OUE~OCONEE NUCLEAR STATION Figure 3.5.2-3A1 3.5-~21 Amendment 11os.
- 122, 122 &..119
(20, 102)
(-3800 (35,80)
OPERATION ACCEPTABLE 50 05 C6 20 10
-40
-30
-20
-10 a
10 20 30 40 Axial Power Imcalance.
POWER IMBALANCE LIMITS, 26 +10/-0 to 200,+/-10 EFPO
( ~
OCONEE 1, CYCLE 8
\\m(9w!JOCONEE NUCLEAR STATION Figure 3.5.2-3A2 3.5-21a Amcndnient %~s,
- 122, 122 & 119
OPERATION RESTRICTED
-19,102) 20,102) 100
(-23, 92) 90
.(-31,80)
- 80 (35,80)
- 70 70 OPERATION ACCEPTABLE 60
@3 0
5 0
30 C6 20 10
-40
-30
-20
-10 0
10 20 30 0
Axial Power Imbalance, 7.
POWER IMBALANCE LIMITS AFTER 200 +/-10 EFPO OCONEE 1, CYCLE 8 u OCONEE NUCLEAR STATION Figure 3.5.2-3A3 3.5-21b Amendment os. 122, 122 & 119
110 (10,102)
(33.102) 100 (10,92)
(34,92)
((38,a80)
OPERATION RESTRICTED to 70 a
I so 50
.. 40OPERATION ACCEPTABLE (g,g0
.O 40 10.0 U
cJ 30 20 10 0
10 20 30 40 50 S0 70 80 90 100 APSR Position, % witnerawn APSR POSITION LIMITS FOR 0 to 26 +10/-0 EFPO, OCONEE 1, CYCLE 8 o~uuw OCONEE NUCLEAR STATION Figure 3.5.2-4Al 3.5-24 Amendment Nos. 122, 122 & 119
(1O. 102).
3.12 (10.9)
(3892)*OPERATION SO RESTR ICTED 70 10 C3 OPERATION ac 50ACCEPTABLE 40 40 20 a
10 20 30 40 50 60
.1.
80 90 lOO APSR Position, S litnarawn APSR POSITION LIMITS,
- 26 +10/-O TO 2Z00 i10 EP OCONEE 1~CCE8 imruOCONEE NUCLEAR STATION Figure 3.5.2-4A2 3.5-24a Amend;.,ent 'C 122, 122 & 119
(10. 102)
(34 102) 1Aft 0 (1.0.92)
.(38,92)
OPERATION 90 -
RESTRICTED 0
(08 38.5.80) 80 IB a'
4 C0 a-0 2
0 4
0 s
70 sos*c OCNEECYLE 60 O
OPERAT ION 50
- ACCEPTABLE*
CS 30