ML14183A119
| ML14183A119 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 06/20/1988 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14183A120 | List: |
| References | |
| DPR-23-A-119 NUDOCS 8806300355 | |
| Download: ML14183A119 (10) | |
Text
UNITED STATES 0
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 119 License No. OPR-23
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Carolina Power & Light Company (the licensee), dated May 7, 1988, as supplemented May 16, and May 20, 1988, 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;
- 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 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-23 is hereby amended to read as follows:
'8806'300355 880620 PDR ADOCK 05000261 P
-2 (B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 119, are hereby incorporated in the license. Carolina Power & & Light Company 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 Elinor G. Adensam, Director Project Directorate II-1 Division of Reactor Projects I/lI
Attachment:
Changes to the Technical Specifications Date of Issuance: June 20, 1988 OFC
- LA:
PR:PM:PD21:DRP :
G9/
O:D 21: RPR NAME : P
- R E
Wdsam DATE 6/h/8 8 6/i(/88 6/ /88
- 61,0/88 OFFICIAL RECORD COPY
ATTACHMENT TO LICENSE AMENDMENT NO.
119 FACILITY OPERATING LICENSE NO. OPR-23 DOCKET NO. 50-261 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
Remove Pages Insert Pages 3.3-2 3.3-2 3.3-3 3.3-3 3.10-2 3.10-2 3.10-2a 3.10-3 3.10-3 3.10-3a 3.10-4 3.10-4 3.10-4a 3.10-5 3.10-5 3.10-5a 3.10-22 3.10-22
(HBR-50)
- b.
Each accumulator is pressurized to at least 600 psig and contains at least 825 ft3 and no more than 841 ft3 of water with a boron concentration of at least 1950 ppm. No accumulator may be isolated.
- c. Two safety injections pumps are operable, each capable of automatic initiation from a separate emergency bus.
- d.
Two residual heat removal pumps are operable.
- e.
Two residual heat exchangers are operable.
- f. All essential features including valves, interlocks, and piping associated with the above components are operable.
- g.
During conditions of operation with reactor coolant pressure in excess of 1000 psig the A.C. control power shall be removed from the following motor operated valves with the valve in the specified position:
Valves Position MOV 862 A&B Open MOV 864 A&B Open MOV 865 A,B,&C Open MOV 878 A&B Open NOV 863 A&B Closed MOV 866 A&B Closed
- h.
During conditions of operation with reactor coolant pressure in excess of 1000 psig, the air supply to air operated valves 605 and 758 shall be shut off with valves in the closed position.
3.3-2 Amendment No.97, 7J0, 119
(HBR-50)
- i.
Power operation with less than three loops in service is prohibited.
3.3.1.2 During power operation, the requirements of 3.3.1.1 may be modified to allow any one of the following components to be inoperable.
If the system is not restored to meet the requirements of 3.3.1.1 within the time period specified, the reactor shall be placed in the hot shutdown condition utilizing normal operating procedures.
If the requirements of 3.3.1.1 are not satisfied within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in the cold shutdown condition utilizing normal operating procedures.
- a.
One accumulator may be isolated for a period not to exceed four hours.
- b.
If one safety injection pump becomes inoperable during normal reactor operation, the reactor may remain in operation for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, provided the remaining safety injection pump is demonstrated to be operable prior to initiating repairs.
- c.
If one residual heat removal pump becomes inoperable during normal reactor operation, the reactor may remain in operation for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, provided the other residual heat removal pump is demonstrated to be operable prior to initiating repairs.
3.3-3 Amendment No. 07, Y10, 119
(HBR-50) 3.10.1.5 Except for physics tests, if a full length control rod is withdrawn as follows:
at positions > 200 steps and is > 15 inches out of alignment with its bank position, or at positions < 200 steps and is > 7.5 inches out of alignment with the average of its bank position then within two hours, perform the following:
- a. Correct the situation, or
- b. Determine by measurement the hot channel factors and apply Specification 3.10.2.1, or
- c. Limit power to 70 percent of rated power 3.10.1.6 Insertion limits do not apply during physics tests or during period exercise of individual rods.
However, the shutdown margin indicated in Figure 3.10-2 must be maintained, except during the low power physics test to measure control rod worth and shutdown margin. For this test, the reactor may be critical with all but one full length control rod inserted.
3.10.2 Power Distribution Limits 3.10.2.1 At all times except during low power physics tests, the hot channel factors, FQ(Z) and FAH, defined in the basis, must meet the following limits:
F (Z) < (2.32/P) x K(Z) for P > 0.5 F Q(Z) < 4.64 x K(Z) for P < 0.5 FAH < 1.65 (1 + 0.2(1-P) )
3.10-2 Amendment No. 07, X15, 119
(HBR-50) where P is the fraction of rated power (2300 Mwt) at which the core is operating. FQ(Z) is the measured FQ(Z) including the measurement uncertainty factor FN = 1.05 and the engineering factor FE = 1.03.
u Q
FAH is the measured FAH including a 1.04 measurement uncertainty factor. K(Z) is based on the function given in Figure 3.10-3, and Z is the axial location of FQ.
3.10.2.1.1 Following initial loading, or upon achieving equilibrium conditions after exceeding by 10% or more of rated power, the power FQ(Z) was last determined, and at least once per effective full power month, power distribution maps using the movable detector system, shall be made to confirm that the hot channel factor limits of Specification 3.10.2.1 are satisfied and to establish the target axial flux difference as a function of power level (called the target flux difference).*
If either ieasured hot channel factor exceeds the specified limit, the reactor power shall be reduced so as not to exceed a fraction equal to the ratio of the FQ{Z) or FAH limit to the measured value, whichever is less, and the high neutron flux trip setpoint shall be reduced by the same ratio.
If subsequent incore mapping cannot, within a 24-hour period, demonstrate that the hot channel factors are met, the overpower AT and overtemperature AT trip setpoints shall be similarly reduced.
3.10.2.2 FQ(Z) shall.be determined to be within the limit given in 3.10.2.1 by satisfying the following relationship for the middle axial 80%
of the core at the time of the target flux determination:
F (Z) < ( 232 [K(Z)] for P > 0.5 Q
~
)
P
>0.5 FQ(2) < 4.64
[K(Z)] for P < 0.5
- During power escalation at the beginning of each cycle, the design target may be used until a power level for extended operation has been achieved.
3.10-3 Amendment No. $1, 7 119
(HBR-50) where V(Z) is defined in Figure 3.10-4 which corresponds to the target band and P > 0.5.
3.10.2.2.1 If the relationship specified in 3.10.2.2 cannot be satisfied, one of the following actions shall be taken:
a) Place the core in an equilibrium condition where the limit in 3.10.2.2 is satisfied and re-establish the target axial flux difference b) Reduce the reactor power by the maximum percent calculated with the following expression for the middle axial 80% of the core:
F (Z) x V(Z)
(max.
over Z of 2.3
] -1 x 100%
x 3
K(2) c) Comply-with the requirements of Specification 3.10.2.2.2.
3.10.2.2.2 The Allowable Power Level above which initiation of the Axial Power Distribution Monitoring System (APDMS) is required is given by the relation:
APL = minimum over Z of 2.32 x K(Z) x 100%
F Q(Z) x V(Z) where FQ(Z) is the measured F(Z, including the engineering factor F = 1.03 and the measurement uncertainty factor Fu 1.05 at the time of target flux determination from a power distribution map using the movable incore detectors. V(Z) is the variation function defined in Figure 3.10-4 which corresponds to the target band. K(Z) is the function defined in Figure 3.10-3.
The above limit is not applicable in the following core plane regions.
- 1) Lower core region 0% to 10% inclusive.
- 2) Upper core region 90% to 100% inclusive.
3.10-4 Amendment No. 07, 1l5, 119
(HBR-50)
At power levels in excess of APL of rated power, the APDMS will be employed to monitor FQ(Z).
The limiting value is expressed as:
(F.(Z) S(z)]
2.103/P R i (1 + a.)
j J
where:
- a. P is the fraction of rated power (2300 Mwt) at which the core is operating (P < 1.0).
- b. R for thimble j, is determined from core power maps and is by definition:
6 F
-. 1 j6.[F(Z).j.
S(Z)] max F
is the value obtained from a full core map including S(Z),
but without the measurement uncertainty factor FN or the u
engineering uncertainty factor, F. The quantity F(Z)ij S(Z) is the measured value without inclusion of the instrument uncertainty factors Fa.
Those uncertainty factors, FN = 1.05, Fa = 1.02, as well as the engineering factor FE = 1.03, have Q
-Q been included in the limiting value of 2.103/P.
- c. a is the standard deviation associated with the determination of R j
- d. S(Z) is the inverse of the K(Z) function given in Figure 3.10-3.
This limit is not applicable during physics tests and excore detector calibrations.
3.10.2.2.3 With successive measurements indicating the enthalpy rise hot channel factor, F N, to be increasing with exposure, the total peaking factor, F Q(Z), shall be further increased by two percent over that specified in Specifications 3.10.2.2, 3.10.2.2.1, and 3.10-5 Amendment No. 87, 7 119
I I
0 l
(6.0,1.0)
U (100.,94) z
(
O o
z I w (12.0,.647) 0 I"Z 0
x N
m om m0
- 3 0
Vt
.o I
IIII
'0 2
4 6
9 10 12 ELEVATION IN CORE (FEET)
FIGURE 3.10-3 NORMALIZED AXIAL DEPENDENCE FACTOR FOR Fq VERSUS ELEVATION (PEAK Fq = 2.32)