ML16148A442
| ML16148A442 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/13/1981 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML16148A441 | List: |
| References | |
| NUDOCS 8111170376 | |
| Download: ML16148A442 (24) | |
Text
ATTACHMENT 1 DUKE POWER COMPANY OCONEE NUCLEAR STATION Proposed Technical Specification Revision Oconee 2, Cycle 6 Pages 2.1-3b 3.5-19a 2.1-8 3.5-19b 2.1-11 3.5-19c 2.3-9 3.5-19d 3.2-2 3.5-19e 3.5-9 3.5-22 3.5-10 3.5-22a 3.5-16 3.5-22b 3.5-16a 3.5-25 3.5-16b 3.5-25a 3.5-19 3.5-25b
- 1. The 1.30 DNBR limit produced by the combination 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 20.15 kw/ft for Unit 2.
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 for Curves 1, 2, and 3 of Figure 2.1-2B correspond to.the expected minimum flow rates with four pumps, three pumps, and one pump in each loop, respectively.
The curve of Figure 2.1-1B is the most restrictive of all possible reactor coolant pump-maximum thermal power combinations shown in Figure 2.1-3B.
The magnitude of the rod bow penalty applied to each fuel cycle is equal to or greater than the necessary burnup independent DNBR rod bow penalty for the applicable cycle minus a credit of 1% for the flow area reduction factor used in the hot channel analysis.
All plant operating limits are presently based on an original method of calculating rod bow penalties that are more conservative than those that would be obtained with new approved procedures. For Cycle 6 operation, this subrogation results in a 10% DNBR margin, which is partially used to offset the reduction in DNBR due to fuel rod bowing.
The maximum thermal power for three-pump operation is 90.606 percent due to a power level trip produced by the flux-flow ratio 74.7 percent flow x 1.08 =
80.68 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 1.30 or a local quality at the point of minimum DNBR less than 22 percent for that particular reactor coolant pump situation. The 1.30 DNBR curve for four-pump operation is more restrictive than any other reactor coolant pump situation because any pressure/temperature point above and to the left of the four-pump curve will be above and to the left of the other curves.
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) Oconee 2, Cycle 5 - Reload Report - BAW-1565.
2.1-3b
THERMAL POWER LEVEL, % FP UNACCEPTABLE 120 OPERA TI ON
(-41.0,112.0)
-42. 0, 107. 3) * -E- - -. .. (42. 0,112. 0) 4 PUMP OPERATION 100
(-42.0,85.906)1 (-41.0,90.1606) (59.0,93.3) 1-- L0. .0.) (42.0,90.606) j ACCEPTABLE 3 & 4 PUMP UNACCEPTABLE OPERATION 80 OPERATION
-41. ,63.50) A? n Ai 10) (59. 0, 71. 9086
(-4 2.0,58 .45 ) PTABLE50 8(4CCE 2,3 & 4 PUMP OPERATION If (59.0,44.45) 1 40 11 1 lI* I1 I~ 20 1 1,1 1 I
-60 .40 -20 0 0 +20 20+40 +60 Reactor Power Imoalance, CORE UNIT PROTECTION
- 2. SAFETY
~5 ~wJOCONEE NUCLEARSrro LIMITS 1FIGURE OF~
RE 2.-28g.8ARSTATION~
. .. .2....8
2400 ACCEPTABLE '
OPERATION 2200 2000
- /
1 2 3 o 1800 1600 560 580 600 620 640 Reactor Coolant Outlet Temperature, F CURVE COOLANT FLOW, GPM POWER, % PUMPS OPERATING TYPE OF LIMIT 1 374,880 (100%) 112 4 DNBR 2 280,035 (74.7%) 90.606 3 ONBR 3 183,690 (49.0%) 63.150 1 PER LOOP QUALITY CORE PROTECTION SAFETY LIMITS UNIT 2 OCONEE NUCLEAR STATION FIGURE 2.1-38 2.1-11
THERMAL POWER LEVEL, a" FP (17,108.0)
(-17,108.0) 1= +1.0 ACCEPTABLE 2= 1 4 PUMP 100 UNACCEPTABLE
(-28,97.0) OPERATIONOPERATION I I OEATO I I UNACCEPTABLE I(-17,80.6) 80 (17,80.6) (42,83.0)
OPERATION ACCEPTABLE I3g4 PUMP
(-28,69.6) 10PERATION I
II-1(-17,52.9)1 8 (17,52. 9) (42,55.6)
ACCEPTABLE 2,3&4
(-28,41.9) 1PUMP
.9) OPERATION- 40 (42,27.9)
II 20' +
14In in
-40 -20 0 +20 +40 Reactor Power Imoalance, %
PROTECTIVE SYSTEM MAXIMUM ALLOWABLE SETPOINTS UNIT 2 onm OCONEE NUCLEAR STATION FIGURE 2.3-28 2.3-9
Bases The high pressure injection system and chemical addition system provide con trol of the reactor coolant system boron concentration.(1) This is normally accomplished by using any of the three high pressure injection pumps in series with a boric acid pump associated with either the boric acid mix tank or the concentrated boric acid storage tank. An alternate method of boration will be the use of the high pressure injection pumps taking suction.directly from the borated water storage tank.(2)
The quantity of boric acid in storage in the concentrated boric acid storage tank or the borated water storage tank is sufficient to borate the reactor coolant system to a 1% Ak/k subcritical margin at cold conditions (700 F) with the maximum worth stuck rod and no credit for xenon at the worst time in core life. The current cycles for each unit, Oconee 1, Cycle 7, Oconee 2, Cycle 6, and Oconee 3, Cycle 6 were analyzed with the most limiting case selected as the basis for all three units. Since only the present cycles were analyzed, the specifications will be re-evaluated with each reload. A minimum of 1020 ft3 of 8,700 ppm boric acid in the concentrated boric acid storage tank, or a minimum of 350,000 gallons of 1835 ppm boric acid in the borated water storage tank (3) will satisfy the requirements. The volume requirements include a 10%
margin and, in addition, allow for a deviation of 10 EFPD in the cycle length.
The specification assures that two supplies are available whenever the reactor is critical so that a single failure will not prevent boration to a cold con dition. The required amount of boric acid can be added in several ways. Using only one 10 gpm boric acid pump taking suction from the concentrated boric acid storage tank would require approximately 12.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> to inject the required boron. An alternate method of addition is to inject boric acid from the borated water storage tank using the makeup pumps. The required boric acid can be injected in less than six hours using only one of the makeup pumps.
The concentration of boron in the concentrated boric acid storage tank may be higher than the concentration which would crystallize at ambient conditions.
For this reason, and to assure a flow of boric acid is available when needed, these tanks and their associated piping will be kept at least 10aF above the crystallization temperature for the concentration present. The boric acid concentration of 8,700 ppm in the concentrated boric acid storage tank cor responds to a crystallization temperature of 770 F and therefore a temperature requirement of 870 F. Once in the high pressure injection system, the concea trate is sufficiently well mixed and diluted so that normal system temperatures assure boric acid solubility.
REFERENCES (1) FSAR, Section 9.1; 9.2 (2) FSAR, Figure 6.2 (3) Technical Specification 3.3 3.2-2
- f. If the maximum positive quadrant power tilt exceeds the Maximum Limit of Table 3.5-1, the reactor shall be shut down within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Subsequent reactor operation is permitted for the purpose of measurement, testing, and corrective action provided the ther mal power and the Nuclear Overpower Trip Setpoints allowable for the reactor coolant pump combination are restricted by a reduction of 2% of thermal power for each 1% tilt for the maximum tilt observed prior to shutdown.
- g. Quadrant power tilt shall be monitored on a minimum frequency of once every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during power operation above 15% full power.
3.5.2.5 Control Rod Positions
- a. Technical Specification 3.1.3.5 does not prohibit the exercising of individual safety rods as required by Table 4.1-2 or apply to inoperable safety rod limits in Technical Specification 3.5.2.2.
- b. Except for physics tests, operating rod group overlap shall be 25% + 5% between two sequential groups. If this limit is ex ceeded, corrective measures shall be taken immediately to achieve an acceptable overlap. Acceptable overlap shall be attained within two hours or the reactor shall be placed in a hot shutdown condition within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- c. Position limits are specified for regulating and axial power shaping control rods. Except for physics tests or exercising control rods, the regulating.control rod insertion/withdrawal limits are specified on figures 3.5.2-lAl, 3.5.2-LA2, and 3.5.2-LA3 (Unit 1); 3.5.2-131, 3.5.2-132, and 3.5.2-133 (Unit 2); 3.5.2-101, 3.5.2-1C2 and 3.5.2-1C3 (Unit 3) for four pump operation, on figures 3.5.2-2A1, 3.5.2-2A2, and 3.5.2-2A3 (Unit 1); 3.5.2-2B1, 3.5.2-232, and 3.5.2-233 (Unit 2) for three pump operation, on figures 3.5.2-2A4, 3.5.2-2A5, and 3.5.2-2A6 (Unit 1); 3.5.2-234, 3.5.2-235, and 3.5.2-2B6 (Unit 2) for two pump operation, and on figures 3.5.2-2C1, 3.5.2-2C2 and 3.5.2-2C3 (Unit 3) for two or three pump operation. Also, excepting physics tests or exercising control rods, the axial power shaping control rod insertion/
withdrawal limits are specified on figures 3.5.2-4Al, 3.5.2-4A2, and 3.5.2-4A3 (Unit 1); 3.5.2-431, and 3.5.2-4B2, and 3.5.2-4B.3, (Unit 2); 3.5.2-401, 3.5.2-4C2, and 3.5.2-403 (Unit 3).
If the control rod position limits are exceeded, corrective measures shall be taken immediately to achieve an acceptable control rod position. An acceptable control rod position shall then be attained within two hours. The minimum shutdown margin required by Specification 3.5.2.1 shall be maintained at all times.
3.5-9
3.5.2.6 Xenon Reactivity Except for physics tests, reactor power shall not be increased above the power level-cutoff shown in Figures 3.5.2-lAl, 3.5.2-1A2, and 3.5.2-LA3 for Unit 1; Figures 3.5.2-131, 3.5.2-132, and 3.5.2-1B3, for Unit 2; and Figures 3.5.2-1C1, 3.5.2-lC2, and 3.5.2-1C3 for Unit 3 unless one of the following conditions is satisfied:
- 1. Xenon reactivity did not deviate more than 10 percent from the equilibrium value for operation at steady state power.
- 2. Xenon reactivity deviated more than 10 percent but is now within 10 percent of the equilibrium value for operation at steady state rated power and has passed its final maximum or minimum peak during its approach to its equilibrium value for operation at the power level cutoff.
- 3. Except for xenon free startup (when 2. applies), the reactor has operated within a range of 87 to 92 percent of rated thermal power for a period exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
3.5.2.7 Reactor power imbalance shall be monitored on a frequency not to exceed two hours during power operation above 40 percent rated power.
Except for physics tests, imbalance shall be maintained within the envelope defined by Figures 3.5.2-3A1, 3.5.2-3A2, 3.5.2-3A3, .3.5.3-3B1, 3.5.3-3B2, 3.5.2-3B3., 3.5.2-3C1, 3.5.2-3C2, and 3.5.2-3C3. If the imbalance is not within the envelope defined by these figures, cor rective measures shall be taken to achieve an.acceptable imbalance.
If an acceptable imbalance is not achieved within two hours, reactor power shall be reduced until imbalance limits are met.
3.5.2.8 The control rod drive patch panels shall be locked at all times with limited access to be authorized by the manager or his designated alternate.
3.5.2.9 The operational limit curves of Technical Specifications 3.5.2.5.c and 3.5.2.7 are valid for a nominal design cycle length, as defined in the Safety Evaluation Report for the appropriate unit and cycle.
Operational beyond the nominal design cycle length is permitted pro vided that an evaluation is performed to verify that the operational limit curves are valid for extended operation. If the operational limit curves are not valid for the extended period of the operation, appropriate limits will be established and the Technical Specification curves will be modified as required.
3.5-10
(1) g SHUTOOWN MARGIN LIMIT 1001 0 (117.102) (281,102) POWER OPERATION IN THIS LEVEL REGION NOT ALLOWED (277.5,92) CUTOFF = 100V F 80 RESTRICTED (284.5,80) a OPERATION KWFT LIMIT CN 60 (58,50) (200,50) 40 PERMISSIBLE OPERATING 20 (REGION (0,2.5) 0 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 0 25 50 75 100 Rod Index, % Witndrawn Group 5 0 25 50 75 100 Group 6 0 25 50 75 100 Group 7 ROD POSITION LIMITS FOR FOUR PUMP OPERATION FROM 0 to 50 (+10, -0) EFPD UNIT 2 noPws OCONEE NUCLEAR STATION FIGURE 3.5.2-181 3.5-16
100 (184,102) (274, 102) POWER (271,92) LEVEL SHUTDOWN CUTOFF = 10O FP MARGIN LIMIT 80 (258,80)
OPERATION IN THIS RESTRICTED KW/FT REGION NOT ALLOWED OPERATION LIMIT
- - 60 (118,50) (200,50) 40 .
PERMISSIBLE OPERATING REGION 20 (0,8.1) (57,15) 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 0 25 50 75 100 Rod Index, % Witndrawn I I II Group 5 0 25 50 75 100 Group 6 0 25 50 75 100 Group 7 ROD POSITION LIMITS FOR FOUR PUMP OPERATION FROM 50 (+10, -0) to 225 +10 EFPD UNIT 2 OCONEE NUCLEAR STATION FIGURE 3.5.2-1B2 3.5-16a
120 1o - (243,102) (274.102)
POWER LEVEL SHUTDOWN (264.5,92) CUTOFF = 100% F MARGIN LIMIT 80 - OPERATION IN THIS REGION NOT ALLOWED 255,80)
KW/FT LIMIT 60 (176,50) (200,50) 40 PERMISSIBLE OPERATING 20 REGION (101,15)
O _(0,5.4) 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 0 25 50 75 100 Rod Index, % Witndrawn Group 5 0 25 50 75 100 I
Group 6 0 25 50 75 100 I I I Group 7 ROD POSITION LIMITS FOR FOUR PUMP OPERATION AFTER 225 +10 EFPD IPWER ~& NEE NUCLEAR STATION FIGURE 3.5.2-183 3.5-16b
100 80 -(17, 77)
SHUTDO WN -77)( (-- 258,77)
MARGIN LIMIT RESTRICTED OPERATION 60 OPERATION IN KW/FT THIS REGION NOT LIMIT o ALLOWED (200r50) 40 (58,38) 20 PERMISSIBLE OPERATING REGION (0,1
.98)(90,15)
(0,2.
0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 Rod Index, % Witnorawn 0 25 50 75 100 Group 5 0 25 50 75 100 I I .1 Group 6 0 25 50 75 100 Group 7 ROD POSITION LIMITS FOR THREE PUMP OPERATION FROM 0 to 50 (+10, -0) EFPO UNIT 2 DEuw OCONEE NUCLEAR STATION FIGURE 3.5.2-21 3.5-19
100 80 (184,77) (252,77) 60 SHUTDOWN RESTRICTED LIMIT OPERATION IN MARGIN OPERATION THIS REGION LIMIT NOT ALLOWED (200,50) 40 (118, 38) 20 PERMISSIBLE OPERATING REGl0N (57,11.75)
,6..6) 0 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 0 25 50 75 100 Rod Index, 5 Witndrawn Group 5 0 25 50 75 100 Group 6 0 25 50 75 100 Group 7 ROD POSITION LIMITS FOR THREE PUMP OPERATION FROM 50 (+10, -0) to 225 +10 EFPD UNIT 2 DEOw OCONEE NUCLEAR STATION FIGURE 3.5.2-292 3.5-19a
100 80 (243.77)
SHUTDOWN MARGIN (250, 77)
LIMIT KWFT 60 OIRESTRICTED LIMIT OPERATION IN THIS OPERATION REGION NOT ALLOWED (200,50)
(176,38) 20 PERMISSIBLE OPERATING REGION (0,4.5) (101,11.75) 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 0' 25 50 75 100 Roa Index, % Witndrawn Group 5 0 25 50 75 100 Group 6 0 25 50 75 100 Group 7 ROD POSITION LIMITS FOR THREE PUMP OPERATION AFTER 225 +10 EFPO UNIT 2 oUKEPoEsOCONEE NUCLEAR STATION FIGURE 3.5.2-2B3 3.5-19b
- 0 100 80 SHUTDOWN MARGIN 60 - (204,52)
OPERATION IN THIS REGION NOT (
ALLOWED (200,50) 40 RESTRCTEDKW/FT LIMIT OPERATION 20 (0,8.65 (58,26) PERMISSIBLE OPERATING REGION 0,2. (90,15) 0 20 40 60 80 100 120 140 160 1.80 200 220 240 260 280 300 O 25 50 75 100 Rod Index, 1 Witnrawn Group 5 0 25 50 75 100 Group 6 0 25 50 75 100 Group 7 ROD POSITION LIMITS FOR TWO PUMP OPERATION FROM 0 to 50 (+10, -0) EFPD UNIT 2 UOWEJ OCONEE NUCLEAR STATION FIGURE 3.5.2-284 3.5-19c
100 80 RESTRICTED 60 OPERATION OPERATION IN THIS (204,52)
REGION NOT (184,52)
ALLOWED (200,50) 40K/FSHTOWN 40 -MARGIN LIMIT LIMIT 20 (118,26)
(0,5.1) .PERMISSIBLE OPERATING REGION (57,8.5) 0' 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 0 25 50 75 100 Rod Index, 5 Witndrawn Group 5 0 25 50 75 100 Group 6 0 25 50 75 100 I II Group 7 ROD POSITION LIMITS FOR TWO PUMP OPERATION FROM 50 (+10, -0) to 225 +10 EFPO UNIT 2 tilPOWERJ OCONEE NUCLEAR STATION FIGURE 3.5.2-285 3.5-19d
100 80 LO 60 40 SHUTDOWN MARGIN LIMIT OPERATION IN THIS REGION 176,26) 20 NOT ALLOWED PERMISSIBLE OPERATING REGION (0,3.7) (101,8.5) 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 Rod Index, 5 Witndrawn 0 25 50 75 100 Group 5 0 25 50 75 100 Group 0 25 50 75 100 Group 7 ROD POSITION LIMITS FOR TWO PUMP OPERATION AFTER 225 +10 EFPD UNIT 2 ouEPOWE OCONEE NUCLEAR STATION FIGURE 3.5.2-2B6 3.5-19e
(-17.5, 102) (+17.5,102)
RESTRICTED 100 REGION
(-17.5,92) (+20,92)
-90
(-28,80) PERMISSIBLE 80 (+22,80)
OPERATING REGION 70 ZE I) 60 50 40 30 20 10 I __________________________
-40 -30 -20 -10 0 10 20 30 40 Axial Power Imoalance, %
OPERATIONAL POWER IMBALANCE LIMITS FOR OPERATION FROM 0 to 50 (+10, -0) EFPD UNIT 2 tiEPOWI) OCONEE NUCLEAR STATION FIGURE 3.5.2-31 3.5-22
-20, 102) (+17.5,102)
RESTRICTED 100 REGION
(-24 92) (+20,92)
(-34,80) PERMISSIBLE 80 (+22,80)
OPERATIN G REGION 70 50 40
- 30 20 10
-40 -30 -20 -101 0 10 20 30 40 Axial Power Imoalance, %
OPERATIONAL POWER IMBALANCE LIMITS FOR OPERATION FROM 50 (+10, -0) to 225 +10 EFPD UNIT 2 OCONEE NUCLEAR STATION
. FIGURE 3.5.2-382 3.5-ZZE
RESTRICTED -20, 102) (+17.5,102)
REGION 100
(-22, 92) (+20.92)
--90
-32, 80) 80 (+22,80)
PERMISSIBLE OPERATING REGION 70 60 50 40 30 20 10
-40 -30 -20 -10 0 10 20 30 40 Axial Power Imnalance, f' OPERATIONAL POWER IMBALANCE LIMITS FOR OPERATION AFTER 225 +10 EFPO UNIT 2 DoWE OCONEE NUCLEAR STATION FIGURE 3.5.2-383 3.5-22b -
(4,102) (35,102) 100 (9,92) (36,92) 80 cr 08)(42,80) RESTRICTED REGION CD (100,50) 40 3c PERMISSIBLE OPERATING REGION, 60 O (100, 50 20 0 20 40 60 80 100 APSR Position, 7/Witndrawn APSR POSITION LIMITS FOR OPERATION FROM 0 to 50 (+10, -0) EFPD UNIT 2 n6w OCONEE NUCLEAR STATION FIGURE 3.5.2-481 3.5-25
Se (9,102) (35,102) 100 (9,92) (37,92) 80 c (0,80) (44,80) RESTRICTED REGION 40 PERMISSIBLE OPERATING REGION 20 0 20 40 60 80 100 APSR Position, % Witndrawn APSR POSITION LIMITS FOR OPERATION FROM 50 (+10, -0) to 225+10 EFPD UNIT 2 NUCLEAR STATION oaon OONEE FIGURE 3.5.2-4B2 3.5-25a
(8.5,102) (33.5,102) 100 (8.5,92) (.42,92) 80 (45,80) RESTRICTED REGION 60 (100,50) 40 PERMISSIBLE OPERATING REGION 20 0 1 0 20 40 60 80 100 APSR Position, % Witnerawn APSR POSITION LIMITS FOR OPERATION AFTER 225 + 10 EFPD UNIT 2 UiEPOW OCONEE NUCLEAR STATION FIGURE 3.5.2-483 3.5-25b
ATTACHMENT 2 B&W Reload Report Oconee 2, Cycle 6