ML17340B003

Tech Spec 3.8 for Steam & Power Conversions & B3.8 Re Bases for Limiting Conditions for Operation

ML17340B003
Person / Time
Site:	Turkey Point
Issue date:	04/13/1981
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17340B000	List: ML17340A998 ML17340B003
References
NUDOCS 8104210211
Download: ML17340B003 (6)

Text

3.8 STEAM AND POWER CONVERSION SYSTEMS P

conversion systems.

Objective: To define conditions of the steam-relieving capacity and auxiliary feedwater system.

h 350'F the following conditions must be met:

a. TWELVE (12) of its steam generator safety valves shall be operable (except for testing).

b. System piping, interlocks and valves directly associated with the related components shall be operable.

c. Its condensate storage tank shall contain a minimum gallons of water. of'85,000

d. Its main steam stop valves shall be operable and capable of closing in 5 seconds or less.

2. The iodine-131 activity on the secondary side of a steam generator shall not exceed 0.67 Ci/cc.

3. During power operation, if any of the conditions of 3.8.1 or 3.8.2 cannot be met withi n 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be shut down and the reactor coolant temperature reduced below 350'F.

4. The following number of independent steam generator auxiliary feedwater pumps and associated flow path shall be operable when the reactor coolant is heated above 350'F:

a. Sin le Nuclear Unit 0 eration Two auxiliary feedwater pumps capable of being powered from an operable steam supply.

b. Dual Nuclear Unit 0 eration Three auxiliary feedwater pumps capable of being powered from an operable steam supply.

5. During power operation, if any of the conditions of 3.8.4 cannot be met, the reactor shall be shut down and the reactor coolant temperature reduced below 350'F, unless one of the following conditions can be met;

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a. For single unit operation with one of the two required auxi 1 i a ry feedwater pumps i noperabl e, r estore the inoperable pump to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or the reactor shall be shut down and the reactor coolant temper ature reduced below 350'F within the next 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> s.

b. For dual unit oper ation with one of the three required auxiliary feedwater pumps inoperable, restore the inoperable pump to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or a reactor shall be shut down and its reactor coolant temperature reduced below 350 F within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3.8-2

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B3.8 BASES FOR LIf"IITING CONDITIONS FOR OPERATION, STEAH AND POWER CONVERSION SYSTEMS In the unlikely event of complete loss of electrical power to the nuclear units, decay heat removal will be assured by the availability of the steam-driven auxiliary feedwater pumps and steam discharge to the atmosphere via the steam generator safety valves and power relief valves.(l) The operability of the auxiliary feedwater system ensures that the Reactor Coolant System can be cooled down to less than 350'F from normal operating conditions in the event of a total loss of off-site power. Each steam driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 600 gpm to the entrance of the steam generators. This capacity is sufficient to ensure that adequate feedAater flow is availiable to remove decay heat and reduce the Reactor Coolant System temperature to less than 350' when the Residual Heat Removal System may be placed into operation. The minimum amount of water in the condensate storage tanks is established from FSAR Figure 9.11-.1, and meets safe shutdown requirements, (2)

The limit on secondary coolant iodine-131 specific activity is based on a postulated release of secondary coolant equivalent to the contents of three steam generators to the atmosphere due to a net load rejection.

The limiting dose for this case would result from radioactive iodine in the secondary coolant. I-131 is the dominant isotope because of its low MPC in air and because the other shorter lived iodine isotopes cannot build up to significant concentrations in the secondary coolant under the limits of primary system leak rate and activity. One tenth of the iodine i'n the secondary coolant is assumed to reach the site boundary making allowance for plate-out and retention in water droplets.

The inhalation thyroid dose at the site boundary is'hen:

Dose (Rem) = C; ~

V ~ B - DCF . X/g ~ 0.1 Where: (C = secondary coolant I-131 specific acti vity

= 1. 34 curies/m3 (iiCi/cc) or 0.67 Ci/m3, each unit V = equivalent secondary coolant volume released = 214 m3 B = Breathing rate = 3.47x10 4 m3/sec.

X/g .= atmospheric dispersion parameter = 1.54x10 'ec/m 0.1 = equivalent fraction of activity released DCF = Dose conversion factor, Rem/Ci The resultant thyroid dose in less than 1.5 Rem.

References

1) FSAR - Section 10.3

2) FSAR Section 14.2.5 B3. 8-1

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