ML17340B198
| ML17340B198 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 05/06/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17340B199 | List: |
| References | |
| NUDOCS 8105150408 | |
| Download: ML17340B198 (11) | |
Text
C UNITED STATES NUCLEAR REGULATORY COMMISS1ON WASHINGTON, O. C. 20555
'FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT PLANT UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
65 License No. DPR-31 The Nuclear Regulatory Commission {the Commission) has found that:
A.
The application for amendment by Florida Power and Light Company (the licensee) dated February 27, 1980 {L-80-62), 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
'he 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 i>ith 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.
c Ci
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility'Operating License No. DPR-3l is hereby amended to read as follows:
(B)
Technical S ecifications
'he Technical Specifications contained in Appendices A and B, as revised through Amendment No.
65
, are hereby incorporated in the license.
The licensee shall operate the facility i'n accordance with the Technical Specifications.
~.
3.
This license amendment is'effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION z EL teven A.
arg Ch Operating Reactors anch 81
. Division of Licens
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 6, 1981
~Ps llaCI c+
"**<<+
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER AND LIGHT CO/1PANY DOCKET NO. 50-251 TURKEY POINT PLANT UNIT NO.
4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.'7 License No. DPR-41 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power and.Light Company (the licensee) dated February 27, 1980 (L-80-62), compli.es 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 facil'ity will operate in conformity with the application, the provisions of the Act, and the, rules and regulations of the Commission; C. 'here 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
>cith 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 ha ve been sat isfied.
2.
Accordi'ngly,.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-41 is hereby amended to read as follows:
(B)
Technical S ecifications The Technical, Specifications contained in Appendices A and B, as revised through Amendment No. 57, are hereby 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 RE ULATORY COMMISSION St I
ven A.
V ga, Chi f
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 6, 1981 Operating Reactors B
a ch 41 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT'MENDMENT NO. 65 TO FACILITY OPERATING LICENSE NO.
DPR-31 AMENDM NT NO.
TO F CILITY OPERATING LICENSE NO.
DPR-1 DOCKET NOS. 50-250 AND 50-251 Revise'ppendix A as follows:
Remove Pa es Insert Pa es
- 3. 2-2 3.2-3 Table 4. 1-1, Sheet 1
- 3. 2-2 302-3 Table 4.1-1 Sheet 1
f.
Except for low power physics tests, the shutdown margin with allowance for a stuck control rod shall exceed the applicable value shown on Figure 3.2-2 under all steady-state operating conditions from zero to full power, including effects of axial power distribution.
The shutdown margin as used here is defined as the amount by which the reactor core would be subcritical at hot'hutdown conditions (540'F) if all control rods were tripped, assuming that the highest worth control rod remained fully withdrawn, and assuming,no changes in xenon, boron con-centration or part-length rod position.
g.
During physics tests and control rod exercises, the insertion limits need not be met, but the required shutdown margin, Figure 3.2-2 must be maintained or exceeded 2.
MISALIGNED CONTROL ROD If a part length* or full length control rod is more than 12 steps out of alignment with its bank, and is not corrected within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> power shall be reduced so as not to exceed 75/ of interim power for 3 loop or 45%
of interim power for two loop operation, unless the hot channel factors are shown to be no greater than allowed by Section 6a of Specification 3.2.
3.
ROD DROP TIME The drop time of each control rod shall be no greater than 1.8 seconds at full flow and operating temperature from the beginning of rod motion to dashpot entry.
4.
No more than one inoperable control rod shall be permitted during sustained power operation, except
'I it shall not be permitted if the rod has a potential
~Any reference to part-length rods no longer applies after the part-1 tnqth rods are removed from the reactor.
Amendments 65 5 57
- 3. 2-2
reactivity insertion upon ejection greater than 0.3X k/k at rated power.
Inoperable rod worth shall be determined within 4-weeks.
5.
6.
b.
A control rod shall be considered inoperable if (a) the rod cannot be moved by the GRDM, or (b) the rod is misaligned from its bank by more than 12 steps, or (c) the rod drop time is not met.
- c. If a control rod cannot be moved by the drive mechanism, shutdown margin shall be increased by boron addition to compensate for the withdrawn worth of the inoperable rod.
CONTROL ROD POSITION INDICATION If either the power range channel deviation alarm or the rod deviation monitor alarm are not operable; rod positions shall be logged once per shift and after a load change greater than 1OX of rated power. If both alarms are inoperable for two hours or more, the nuclear overpower trip shall be reset to 93K of. rated power.
POWER DISTRIBUTION LIMITS a.'ot channel factors:
'ith steam generator tube plugging
<25%, the hot channel factors (defined in the basis) must meet the following limits at all times except during low power physics tests'.
F (Z)
< (1.93/P)xK(Z), for P.
>.5 P
(Z)
< (3.86)xK(Z), for P c
.5 8
< 1.55[1.+0.2 (1-P)]
Where P is the fraction of rated power at which the core is operating; K(Z) is the function given in Figure 3.2-3; Z is the core height location of F
! If F
', as predicted by approved physic: calculation.;,
q exceeds 1..93, the'ower will be limited to the rated power multiplied by the ratio of 1.93 divided by the predicted F
, or augmented surveillance of q'ot channel factors shall be implemented.
Amendments 65,5 57 3.2-3
TABLE 4.1.1 MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TEST OF INSTRUHENT CHANNELS Channel Descri tion 1.
Nuclear Power Range (Check, Calibrate and Test only applicable above 100K of rated power.)
2.
Nuclear Intermediate Range 3.
Nuclear Source Pange 4.
Reactor Cool ant Temperature 5.
Reactor CooTant Flow 6.
.Pressurizer Water Level 7.
Pressurizer.
pressure 8.
4 kv Voltage
& Frequency Analog'Rod Position Check S (1)
M"(4)
S (l)i.
S (1)
Si-,
N.A.
Calibrate D (2) o*(4)
N.A.
N.A..
Test li (3) p (2)
P (2)
B/W (1)i.-
(2)t Remarks
- 1) Load v.s. flux curve
- 2) Thermal oower calculation
- 3) Signal to bT; bistable action (permissive, rod.
stop, trips)
- 4) Upper
& lower detectors for symmetric offset (+5 to -5%)
- 1) Once/s hift up to 50K R.P.
- 2) Log level; bistable action (permissive, rod stop, trip);
- 1) Once/shift when in service
- 2) Bistahle action (alarm, trip)
- 1) Overtemperature-hT
- 2) Overpower-bT Reactor protection circuits only 1),
With step counters P)
Cal ib) ate indicated nosition to Qi'thin'12 steps of actual position.
Arendments 65 & 57