ML17341A808: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
Line 22: Line 22:
: 8. The spent  fuel cask shall not be moved over spent fuel, and only one spent fuel assembly will be handled at one time over the reactor or the spent fuel pit.
: 8. The spent  fuel cask shall not be moved over spent fuel, and only one spent fuel assembly will be handled at one time over the reactor or the spent fuel pit.
9.,  Fuel which has been discharged from a reactor will not be moved outside the containment in fewer than 100 hours after shutdown If any  one  of the specified'imiting conditions for refuel-ing is not met, refueling shall cease until specified limits are met, and there shall be no operations which may increase reactivity.
9.,  Fuel which has been discharged from a reactor will not be moved outside the containment in fewer than 100 hours after shutdown If any  one  of the specified'imiting conditions for refuel-ing is not met, refueling shall cease until specified limits are met, and there shall be no operations which may increase reactivity.
,
           'goi
           'goi
   .Sooiioooi~osooo>>o                      3.10-2                          1-13-82
   .Sooiioooi~osooo>>o                      3.10-2                          1-13-82

Latest revision as of 22:54, 3 February 2020

Proposed Tech Specs B3.10-1 & 3.10-2 Re Bases for Limiting Conditions of Operation,Refueling.Safety Evaluation Encl
ML17341A808
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 01/13/1982
From:
FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17341A807 List:
References
NUDOCS 8201180512
Download: ML17341A808 (8)


Text

5. At least ONE residual heat removal pump shall be in operation, unless Tavg is less than 160F.

6. When the reactor vessel head is removed and fuel is in the vessel, the minimum boron concentration of 1950 ppm or higher., sufficient to maintain the reactor subcritical by 1056 k/gin the cold condi-tion with all rods inserted shall be maintained in the reactor coolant system and the concentration shall be verified daily.
7. Direct communication between the control room and the refueling cavity manipulator crane shall be available during refueling operation.
8. The spent fuel cask shall not be moved over spent fuel, and only one spent fuel assembly will be handled at one time over the reactor or the spent fuel pit.

9., Fuel which has been discharged from a reactor will not be moved outside the containment in fewer than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown If any one of the specified'imiting conditions for refuel-ing is not met, refueling shall cease until specified limits are met, and there shall be no operations which may increase reactivity.

'goi

.Sooiioooi~osooo>>o 3.10-2 1-13-82

~po> AOOC~ PDR P J

r i

E

  • Ih

~ )

J 2

TABLE 1 RCS BORON CONCENTRATIONS CYCLE 8 (1ST CYCLE) (UNIT 3)

Refueling Shutdown; Rods in (k = .90) 1950 2000 2200 (k = .95) 1520 1700 Shutdown (k = .99) with Rods Inserted, Clean,. Cold 780 1180 1350 Shutdown (k = .99) with Rods Inserted, Clean,. Hot. 510 750 1080 Shutdown (k = .99) with No Rods Inserted, Clean, Cold 1250 1570 1720 Shutdown (k = .99) with No Rods Inserted, Clean, Hot 1210 1610 1890 NOIK

  • Cycle 8 for Turkey Point Unit 3 is designed with gn alternate Positive Moderator Temperature Coefficient (+ RlC) core.

1-1'3-82

li t r'i

Turkey Point Units 3 6 4 pocket Nos.. 50-250 and 50-251 Proposed .License Amendment Raising the Required Refueling Boron Concentration from 1950 ppm SAFETY EVALUATION In the design of the earlier cores, the refuel'ing boron concentration of 1950 ppm provided a 10% subcriticality with all rods inserted in cold, condition (reference Table 3.2.1-1 of FSAR). Also, the reactor .stayed subcritical with all rods out in the cold condition.

Current cores, such as the Unit 3 Cycle 8 redesign core, are designed for longer (18 month). operation and have more initial reactivity than the earlier cores. .A higher boron concentration than 1950 ppm may be required, to keep the core subcritical by 10%

in cold condition with all rods inserted and will also keep the core subcritical with all rods. out (reference 'Table -1).

The required refueling -boron concentration must be calculated for each core deign and for. each nuclear unit., but shall not be less. than 1950 ppm.

Since the refueling boron concentration will keep the core 10%

subcritical, plant safety will not be compromised.

I

I I

l

STATE OF FLORIDA )

) ss COUNTY OF DADE )

Robert E. Uhri being first duly sworn, deposes and says:

4 That he is Vice President of Florida Power Light Company, the herein; 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 Robert E. Uhrig Subscribed and sworn to before me this j- '~S'. ay of

~LI

~ g;fl NOTARY'PUBLIC, n and for the County of Dade,

>'.Stat;e of Florida Rorida at Largo Notary Public, Stato of October 30, 1983 commission expires: Mv mmhsion commmion epr Expires

I

~ ~

'