ML19322B385
| ML19322B385 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/24/1975 |
| From: | Purple R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19322B377 | List: |
| References | |
| NUDOCS 7912020233 | |
| Download: ML19322B385 (7) | |
Text
. _ _ _ _
i UNITED STATES NUCLEA R REGULATORY COMMISSION r
WASHINGTON, D.
C.
20555 i
DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment"No.12 License No. DPR-55 1.
The Nuclear Regulatory Commission (the Commission) has found that:-
A.
The application for amendment by Duke Power Company (the licensco) dated November 10, 1975, 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 1; 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 reasonabic assurance (i) that the activitics 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; and 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.
2.
Accordingly, the license is amended by a change to the Tc'chnical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Facility License No.DPR-55 is hereby amended to read as follows:
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. "B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised, are hereby incorporated in the license. The licensee shal1 operate the facility in accordance with the Technical Specifications, as revised by issued changes thereto through ChangcPNo.12 "
3.
This license amendment is effective as of the date of its issuance.
9 FOR TiiE NUCLEAR REGULATORY C0!B1ISSION 3
TT)OLSYM f0kC I Robert A. Purple, Chief Operating Reactors Branch #1 Division of Reactor Licensing
Attachment:
Change No. 12 to the Technical Specifications Date of Issuance:
NOV 2 41975 s
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A'ITACIBENT TO LICENSE AMENDMENTS AMENDMENT NO.1 g TO FACILITY LICENSE NO. DPR-38 CHANGE. NO. A D TO TECilNICAL SPECIFICATIONS; AMENDMENT NO.1 g TO FACILITY LTCENSE NO. DPR-47 CilANGE NO.E D TO TECHNICAL SPECIFICATIONS; AMENDMENT NO.12 TO FACILITY LICENSE NO. DPR-55 CilANGE NO. l' TO TECHNICAL SPECIFICATIONS 4
h DOCKET NOS. 50-269, 50-270, AND 50-287 Revise Appendix A as follows:
itemove pages 3.5-13 and 3.5-21, and insert revised pages 3.5-13 and 3.5-21.
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g.
If within one (1) hour of determination of an inoperable rod, it is not determined that a 1%Ak/k hot shutdown margin exists combining the worth of the inoperable rod with each of'the other rods, the reactor shall be brought to the hot. standby condition until this margin is established.
h.
Following the determination of an inoperable rod, all rods shall be exercised within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and ex'ercised weekly until 'the rod problem is solved.
- i. If a control rod in the regulating or safety rod groups is declared inoperable, power shall be reduced to 60 percent of the thermal power allowable for the reactpr coolant pump com-bination.
2 j.
If a control rod in the regulating or axial power shaping groups is declated inoperable, operation above 60 percent of rated power may continue provided the rods in the group are positioned such that the rod that was declared inoperable is maintained within allowable group average position limits of Specification 3.5.2.2.a and the withdrawal limits of Specification 3.5.2.5.c.
5.2.3 The worths of single inserted control rods during criticality are limited by the rest.rictions'of Specification 3.1.3.5 and the 25/20/12 control rod position limits defined in Specification 3.5.2.5.
5.2.4 Quadrant Power Tilt a.
Whenever the quadrant power tilt exceeds 4 percent, except for physics tests, the quadrant tilt shall be reduced to less than 4 percent within two hours or the following actions shall be taken:
(1) If four reactor coolant pumps are in operation, the allowable' thermal power shall be reduced by"2 percent of full power for each 1 percent tilt in excess of 4 percent below the power level cutoff (see Figures 3.5.2-1A1, 3.5.2-1A2, 3.5.2-1B1, l25/20/12 3.5.2-1B2, 3.5.2-1B3, 3.5.2-Ici, 3.5.2-1c2, and 3.5.2-1c3).
(2) If less than four reactor coolant pumps are in operation, the allowable thermal power shall be reduced by 2 percent of full power for each I percent tilt b.elow the power allowable for the reactor coolant pump combination as defined by Specification 2.3.
(3) Except as provided in 3.5.2.4.b, the reactor shall be brought to the hot shutdown condition within four hours if the quadrant' tilt is not reduced to less than 4 percent after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- b. If the quadrant tilt exceeds 4 percent and there is simultaneous indication of a misaligned control rod per Specification 3.5.2.2, reactor operation may continue provided power is reduced to 60 percent of the thermal power allowable for the reactor, coolant 3.5-7 a
10V 2 41975
., pump comb,ination.
Except for physics tests, if quadrant tilt exceeds 9 percent, a c.
controlled shutdown shall be initiated immediately and the reactor shall be brought to the hot shutdown condition within four hours.
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d.
Whenever the reactor is brought to het shutdown pursuant to 3.5.2.4.a(3) or 3.5.2.4.c above, subsequent reactor operation is i
, permitted for the purpose of measurement, testing, and corrective action provided the thermal power and the power range high flux setpoint allowable for the reactor coolant pump combination are restricted by a reduction of 2 percent of full powe.r for each I per-cent tilt for the maximum tilt observed prior to shutdown.
Quadrant power tilt shall be monitored on a minimum frequency of e.
once every two hours during power operation above 15 percent of rated power.
3.5.2.5 Control Rod Positions
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a.
Technical Specificatica 3 1.3.5 does not prohibit the exercising of 25/20/
individual safety rods as required by Table 4.1-2 or apply to inoperable 12 I
safety rod limits in Technical Specification 3.5.2.2.
b.
Operating rod group overlap shall be 25% + 5% between two sequential groups, i
except for physics tests.
Except for physics tests or exercising control rods, the control rod witig-c.
drawal limits
- are specified on Figures 3.5.2-1A1 and 3.5.2-1A2 (Unit 1) [25/20/12:
3.5.2-1B1, 3.5.2-1B2 and 3.5.2-1B3 (Unit 2), and 3.5.2-1C1, 3.5.2-1C2, and 3.5.2-1C3 (Unit 3) for four pump operation and on Figures 3.5.2-2A (Unit 1), 3.5.2-2B (Unit 2), and 3.5.2-2C (Unit 3) for three or two pump
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operation.
If the control rod position limits are exceeded, corrective l'
measures shall be taken immediately to achieve an acceptable control rod position.
Acceptable control rod positions shall then be attained within two hours.
- d. Except for physics tests, power shall not be increased ~above the power lev 1 cutoff as shown on Figures 3.5.2-1A1 and 3.5.2-1A2 (Unit 1) [see additional 25/20 operating restrictions for Unit 1]* 3.5.2-1B1, 3.5.2-1B2, and 3.5.2-1B3
/12 (Unit 2), and 3.5.2-1C1, 3.5.2-lC2, 3.5.2-lC3 (Unit 3, unless the following requirements are met (1) The xenon reactivity shall be within 10 percent of the value for operation at steady-state rated power.
(2) The xenon reactivity shall be asymptotically approaching the value for operation at steady-state rated power.
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NOV 2 41975 i
,n he 3.5-8
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R00 POSITICN LIMITS FCR 4 PLF.P OPERATION APPLICABLE TO TE PERICO AFTER 245 1 10 EFPD, as provided for in the Commission's Order dated December 27, 1974.
OPERAil0N,IN THIS REG 10N 8 '
'b
is NOT ALLOIED as7.1,so 100 POWER LEVEL CUTCFF
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80 234,73 y
p
[STRICTED soo,ss 50 REC 10N
[%
PERillS$1BLE OPERATING REGION w
y 40 2
20 (o.5) 0 0
50 100 150 200 250 300 Rod Inder, 5 to 0
25 50 75 100 0
25 50 75 100 t
I i
1 1
I I
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t Grcup 5 Grcup 7 0
25 50 75 100 i
f I
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Grcup 6 Rod index 'is the precentage sum of the withdrawal of Groups 5,6 and 1.
UNIT 1 ROD POSITION LIMITS FOR 4 PUMP OPERATION suMi f OCONEE NUCLEAR STATION Figure 3.5.2-1A2 4- -
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3.5-13 i
P0cer, 5 of 2568 MWt 110 RESTRICTED REGION
-15.3,102 5.9,102 100
-22.1,92 l
o 80
'N 25/20/12
-27.69 60 PERMISSIBI.E
+is.I,5 OPERATING P~
REGION
.. 40 T
20 I
I I
I
-20 10 0
10 20 Core imbalance, %
UNIT 1 OPERATIONAL. POWER IMBALANCE ENVELOPE OCONEE NUCLEAR STATION Figure 3.5.2-3A L1 b
3.5-21 NOV 2 41975
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