ML17341A800
| ML17341A800 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/24/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17341A801 | List: |
| References | |
| NUDOCS 8201150080 | |
| Download: ML17341A800 (10) | |
Text
l UNITEDSTATES t
NUCLEAR REGULATORY COMMISSION WASHING/ON, D. C. 20555 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT PLANT UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 75 License No.
DPR-31 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
The application for amendment by Florida Power and Light Company (the licensee) dated April 13, 1981, 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 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.
820ii50080 8ii224 PDR ADOCK 05000250
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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-31 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. 75, 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.
~ Operating Reactors r
Division of Licensin nch No.
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ULATORY COMMISSION j, '(g~(
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Attachment:
Changes to the Technical Specifications Date of Issuance:
December 24, 1981
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER AND LIGHT COMPANY DOCKET NO.
50-251 TURKEY POINT PLANT UNIT NO.
4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 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 April 13, 1981, 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; 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; 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-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. 69, 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.
OR THE NUCLE R REGULATORY COMMISSION teven"n-. )arga, C 'ef Operating Reactors anch No.
1 Division of Licensi
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 24, 1981
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 75 TO FACILITY OPERATING LICENSE NO.
DPR-31 AMENDMENT NO. 69 TO FACILITY OPERATING LICENSE NO.
DPR-41 DOCKET NOS.
50-250 AND 50-251 Revise Appendix A as follows:
Remove Pa es
- 3. 8-1 B3.8-1 Insert Pa es 3.8-1 3.8-2 B3.8-1
3.8 STEAH AND POWER CONVERSION SYSTEMS Objective:
conversion systems.
To define conditions of the steam-relieving capacity and auxiliary feedwater system.
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 di rectly associated with the related components shall be operable.
- c. Its condensate storage tank shall contain a minimum of 185,000 gallons of ~ater.
- d. Its main steam stop valves shall be operable and capable of closi ng 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 within 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 bei'ng 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.
k 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; Amendment Nos.
75 5 69
- a. For single unit operation with one of the two required auxi 1 i a ry feedwa ter pumps i nope rab 1 e, 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 the reactor shall be shut down and the 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 />.
- b. For dual unit operation 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 snut down and its reactor coolant temperature reduced below 350'F withi'n the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Amendment Nos.
75 8 69 3.8-2
- 83. 8 BASFS FOR Llf1ITING CONDITIONS FOR OPERATION, STEAH AND PO~lER CONVERSION SYSTEi6 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' 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 feedwater flow is avai liable 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 radioacti ve iodine in the secondary coolant.
I-131 is the dominant isotope because of its low HPC 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 in 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 then:
Dose (Rem)
= C.
~
V
~
8
~
DCF X/Q
. O.l Where:
C = secondary coo>ant I-131 specific activity
= 1.34 curies/m3 (Ci/cc) or 0.67 Ci/m3, each unit V = equivalent secondary coolant volume released
= 214 m3 B
= Breathing rate
= 3.47xlO 4 m3/sec.
X/Q = atmospheric dispersion parameter
= 1.54xlO sec/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 Amendment Nos.
75 8 69 B3.8-1