ML18227D849
| ML18227D849 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  (DPR-031, DPR-041) |
| Issue date: | 10/27/1976 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18227D849 (15) | |
Text
0 P
P
~
~
~
~
~
~
~
~
~
~
g j
~
~
~
~
~Ill
~
~
~
~
~
0 RR
~
e
~
I
~
I 0
R g
e s
s R
il a ~
~
~
~
~
FL 33101
~gM IÃr Q
FLORIDAPOWER 8 LIGHT COMPANY October 27, 1976 L-76-372 Director of Nuclear Reactor Regulation Attention:
Mr. Victor Stello, Directo ~
g p Division of operating Rea.
ors g y f,"Il U. R. Nuclear Regulatory commissionOl
<<es>>
~Nims<
Washington, D.
C.
- 20555,
Dear Mr. Stello:
Re:
Turkey Point Units 3 and 4
Q
>'>0<is
"'ocket Nos.
50-250 'and 50-251 ql Proposed Amendment to Facility X 'v
~0 eratin Licenses DPR-31 and DPR-4 ~~
Xn accordance with 10 CFR 50.30, Florida Power 6 Light Company submits herewith three (3) signed originals and forty (40) copies of a request to amend Appendix A of Facility Operating Licenses DPR-31 and DPR-41.
This proposal is being submitted in response to a September 8,
1976 letter from your staff which contained model technical specifica-tions on steam generator tube leakage and steam generator tube surveillance requirements.
The proposed changes are described below and shown on the accompanying Technical Specification pages bearing the date of this letter in the lower right. hand corner.
Pa e 3.1-1 Specification 3.1.l.b is revised to incorporate limiting conditions for operation regarding primary-to-secondary leakage through steam generator tubes.
~acae B3.l-l The Basis for Specification 3.1.1 is revised to include a discussion of steam generator tube integrity.
The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee and the Florida Power 6 Light Company Nuclear Review Board.
They have concluded that. it does not involve a significant hazards consideration and should not require prenoticing pursuant to 10 CFR 2.105.
PEOPLE... SERVING PEOPLE
0 IfII ff
' 'I g f JC L '1%'>TV'L 1 I~ftg ff-'~$ '5
Director of Nuclear Reactor Regulation Attention:
Mr. Victor Stello, Director Division of Operating Reactors Page Two The proposed amendment does not include new technical specifications on the surveillance of steam generator
- tubes, because we have not completed our review of that portion of the NRC model technical specifications.
The model specifications represent a significant addition to the Turkey Point Technical Specifications, therefore, they need to be carefully considered to ensure their proper adaptation to the Turkey Point format.
We intend to complete our review of the model technical specifications by December 20, 1976, at which time we will report the results of the review.
Very tr y
- ours, Robert E. Uhrig Vice President REU/MAS/cpc Attachment cc:
Mr. Norman C. Moseley
'ack R.
Newman, Esquire
t
]I
3.0 LIMITING CONDITIONS FOR OPERATION t
3.1 REACTOR C60LANT SX System.
~0b 'ective:
To specify those limiting conditions for operation of the Reactor. Coolant System which must be met to assure safe reactor operation.
a.
Reactor Coolant Pum s l.
A minimum of ONE pump shall be in operation when the reactor is in power operation, except during low power physic's tests.
2.
A minimum of ONE pump, or ONE Residual Heat Removal Pump, shall be in operation during reactor coolant boron concentration reduction.
3.
Reactor power shall not exceed 10% of rated power unless at least TWO reactor coolant pumps are in operation.
4.
Reactor power shall not exceed 45% of rated power with only two pumps in operation unless the overtemperature AT trip setpoint, Kl, for two loop operation, has been set at 0.88.
b.
A minimum of TWO steam generators shall be operable when the average coolant temperature is above 350'.
2.
During hot shutdown and power operation, except as allowed by Specification 3,l.l.b.3, the primary-to-secondary leak rate through the steam generator tubes shall not exceed 1 gallon per minute total for all 3 steam generators or
'0.35 gallon per minute for each steam generator.
3.
With any steam generator tube leak rate greater than the limits in Specification 3.l.l.b.2, the leak rate shall be reduced to within the limits within four hours or the unit shall be in cold shutdown within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
c.
Pressurizer Safet Valves 1.
ONE valve shall be operable whenever the head is on the reactor vessel except during hydrostatic tests.
2.
THREE valves shall be operable when the reactor coolant average temperature is above 350' or the reactor is critical.
3 ~ 1 1 10/27/76
B3.1 BASES FOR LIMITING CONDITIONS FOR OPERATXON, REACTOR COOLANT SYSTEH 1.
0 erational Com onents The specification requires that a sufficient number of reactor coolant pumps be operating to provide coast down core cooling in the event that a loss of flow occurs.
The flow provided will keep DNBR well above 1.30.
When the boron concentration of the Reactor Coolant System is to be reduced the process must be uniform to prevent sudden reactivity changes in the reactor.
EHxing of the reactor coolant will be sufficient to maintain a uniform boron concentration if at least one reactor coolant pump or one residual heat removal pump is running while the change is taking place.
The residual heat removal pump will circulate the reactor coolant system volume in approximately one half hour.
Each of the pressurizer safety valves is designed to relieve 293,330 lbs. per hr. of saturated steam at the valve set point.~
~
Below 350 F and 450 psig in the Reactor Coolant System, the Residual Heat Removal System can remove decay heat and thereby control system temperature and pressure.
Xf no residual heat were removed by any of the means available the amount of steam which could be generated at safety valve lifting pressure would be less than the capacity of. a single valve.
Also, two safety valves have capacity greater than the maximum surge rate resulting from complete loss of load.~2~
The extent of stress corrosion cracking caused by localized corrosion can be limited by limiting steam generator tube leakage between the primary coolant system and the secondary coolant system.
Cracks having a primary-to-secondary leakage less than the Technical Specification limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents.
Operating plants have demonstrated that primary-to-secondary leakage can be detected by radiation monitoring of the steam generator blowdown.
Leakage in excess of the Technical Specification limit may require plant shutdown and unscheduled steam generator tube inspections if the leakage cannot be reduced below the limit within a specified length of time.
Leaking tubes will be located and plugged during the shutdown.
2.
Heatu and Cooldown E
All components in the Reactor. Coolant System are designed to withstand the effects of cyclic loads due to reactor system temperature and pressure changes.
These cyclic loads are introduced by normal unit load transients, reactor trips, and tartup and shutdown operation.
The number of thermal and loading cycles used for design purposes are shown in Table 4.1-8 of the FSAR.
During unit startup and shutdown, the rates of temperature and pressure changes are limited.
The maximum specified heatup and cooldown rates are consistent with the design number of cycles and satisfy stress limits for cyclic operation.
10/27/76 B3.1-1
3.0 LIHITING CONDI S
FOR OPERATION e
I 3.'1 REACTOR COOLANT SYSTEM System.
~Ob ective:
To specify those limiting conditions for operation of the Reactor Coolant System which must be met to assure safe reactor operation.
a.
Reactor Coolant Pum s 1.
A minimum of ONE pump shall be in operation when the reactor is in power operation, except during low power physics tests.
2.
A minimum of ONE pump, or ONE Residual Heat Removal Pump, shall be in operation during reactor coolant boron concentration reduction.
3.
Reactor power shall not exceed 10% of rated power unless at least TWO reactor coolant pumps are in operation.
4.
Reactor power shall not exceed 45% of rated power with only two pumps in operation unless the overtemperature AT trip setpoint, Kl, for two loop operation, has been set at 0.88.
b.
A minimum of TWO steam generators shall be operable when the average coolant temperature is above 350'.
2.
During hot shutdown and power operation, except as allowed by Specification 3.l.l.b.3, the primary-to-secondary leak rate through the steam generator tubes shall not exceed 1 gallon per minute total for all 3 steam generators or 0.35 gallon per minute for each steam generator.
3.
With any steam generator tube leak rate greater than the limits in Specification 3.1.l.b.2, the leak rate shall be reduced to within the limits within four hours or the unit shall be in cold shutdown within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
c.
Pressurizer Safet Valves l.
ONE valve shall be operable whenever the head is on the reactor vessel except during hydrostatic tests.
2.
THREE valves shall be operable when the reactor coolant average temperature is above 350' or the reactor is critical.
3.1-1 10/27/76
0
0 B3.1 BASES FOR LIMITING CONDITIONS FOR OPERATION, REACTOR'OOLANT SYSTEM l.
0 erational Com onents The specification requires that a sufficient number of reactor coolant pumps be operating to provide coast down core cooling in the event that a loss of flow occurs.
The flow provided will keep DNBR well above 1.30.
When the boron concentration of the Reactor Coolant System is to be reduced the process must be uniform to prevent sudden reactivity changes in the reactor.
Mixing of the reactor coolant will be sufficient to maintain a uniform boron concentration if at least one reactor coolant pump or one residual heat removal pump is running while the change is taking place.
The residual heat removal pump will circulate the reactor coolant'system volume in approximately one half hour.
Each of the pressurizer safety valves is designed to re3,ieve 293,330 lbs. per hr. of saturated steam at the valve set point.<1~
Below 350 F and 450 psig in the Reactor Coolant System, the Residual Heat Removal System can remove decay heat and thereby control system temperature and pressure.
If no residual heat were removed by any of the means available the amount of steam which could be generated at safety valve lifting pressure would be less than the capacity of a single valve.
Also, two safety valves have capacity greater than the maximum surge rate resulting from complete loss of load.~
The extent of stress corrosion cracking caused by localized corrosion can be limited by limiting steam generator tube leakage between the primary coolant system and the secondary coolant system.
Cracks having a primary-to-secondary leakage less than the Technical Specification limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents.
Operating plants have demonstrated that primary-to-secondary leakage can be detected by radiation monitoring of the steam generator blowdown.
Leakage in excess of the Technical Specification limit may require plant shutdown and unscheduled steam generator tube inspections if the leakage cannot be reduced below the limit within a specified length of time.
Leaking tubes will be located and plugged during the shutdown.
2.
Heatu and Cooldown All c'omponents in the Reactor Coolant System are designed to withstand the effects of cyclic loads due to reactor system temperature and pressure changes.
These cyclic loads are introduced by normal unit load transients, reactor trips, and startup and shutdown operation.
The number of thermal and loading cycles used for design purposes are shown in Table 4.1-8 of the FSAR.
During unit startup and shutdown, the rates of temperature and pressure changes are limited.
The maximum specified heatup and cooldown rates are consistent with the design number of cycles and satisfy stress limits for cyclic operation.
10/27/76 B3. 1-1
~-
P
STATE OF FLORIDA
)
,)
- COUNTY OF DADE
)
~
E. A. Adomat
, being first duly sworn, deposes and says:
That he is Executive Vice President Light Company, the Licensee herein; of Florida Power That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee E. A. A omat Subscribed and sworn to before me this day of IgQ".U~NY PUBLIC, in and for the County of Dade, St'a'ke of Florida TARY PU8UC STATE Of APORIA AT EAR MYCOMMISSfON EXPIRES NOV 30 IP79
'~My'ommission expires:
'~<>>>>U.+i>>Rii ws. uNotRw
~
~
( ~
>>> I>>
~
(>>
I
(
>> Ip >> ~,
'('>>