ML17228B511
| ML17228B511 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 05/30/1996 |
| From: | Hebdon F NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17228B512 | List: |
| References | |
| NUDOCS 9606050198 | |
| Download: ML17228B511 (12) | |
Text
gI,S R50I Wp, O~
Cy O
l
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER
& LIGHT COMPANY DOCKET NO. 50-335 ST.
LUCIE PLANT UNIT NQ.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
4 License No.
DPR-67 The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
E.
The application for amendment by Florida Power
& Light Company, et al. (the licensee),
dated January 4,
- 1996, 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.
9b0b050i98 9b0530 PDR ADQCK 05000335 P
2.
Accordingly, Facility Operating License No.
DPR-67 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 2.C.(2) to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No.
- 143, 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 its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
"...~S.c; ~z+
Frederick J.
He&don, Director Project Directorate II-3 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 3O, 1gg6
I'
ATTACHMENT TO LICENSE AMENDMENT NO.
143 TO FACILITY OPERATING LICENSE NO.
DPR-67 DOCKET NO. 50-335 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document comoleteness.
Remove Pa es 3/4 5-7 B 3/4 5-1 Insert Pa es 3/4 5-7 B 3/4 5-1
3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:
a.
In MODES 3* and 4", one ECCS subsystem composed of one OPERABLE high pressure safety injection pump and one OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection actuation signal and automatically transferring suction to the containment sump on a sump recirculation actuation signal
~
b.
Prior to decreasing the reactor coolant system temperature below 270'F a maximum of only one high pressure safety injection pump shall be OPERABLE with its associated header stop valve open.
c.
Prior to decreasing the reactor coolant system temperature below 236'F all high pressure safety injection pumps shall be disabled and their associated header stop valves closed except as allowed by Specifications 3.1.2.1 and 3.1.2.3.
MODES 3* and 4.
MODES 5 and 6 when the Pressurizer manway cover is in place and the reactor vessel head is on.
hQItQH:
a.
With no ECCS subsystems OPERABLE in MODES 3* and 4', immediately restore one ECCS subsystem to OPERABLE status or be in COLD SHUTDOWN within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
b.
With RCS temperature below 270'F and with more than the allowed high pressure safety injection pump OPERABLE or injection valves and header isolation valves open, immediately disable the high pressure safety injection pump(s) or close the header isolation valves.
c.
In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.
4.5.3.1 4.5.3.2 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.
The high pressure safety injection pumps shall be verified inoperable and the associated header stop valves closed prior to decreasing below the above specified Reactor Coolant System temperature and once per month when the Reactor Coolant System is at refueling temperatures.
With pressurizer pressure <1750 psia.
¹ REACTOR COOLANT SYSTEM cold leg temperature above 250'F.
ST. LUCIE - UNIT 1 3/4 5-7 Amendment No. 96, 66, &+
~, 143
The OPERABILITYof each of the RCS safety injection tanks ensures that a sufficient volume of borated water willbe immediately forced into the reactor core through each of the cold legs in the event the RCS pressure falls below the pressure of the safety injection tanks. This initial surge of water into the core provides the initial cooling mechanism during large RCS pipe ruptures.
The limits on safety injection tank volume, boron concentration and pressure ensure that the assumptions used for safety injection tank injection in the accident analysis are met.
The limitof one hour for operation with an inoperable safety injection tank minimizes the time exposure of the plant to a LOCA event occurring concurrent with failure of an additional safety injection tank which may result in unacceptable peak cladding temperatures.
The OPERABILITYof two separate and independent ECCS subsystems ensures that sufficient emergency core cooling capability willbe available in the'event of a LOCA assuming the loss of one subsystem through any single failure consideration.
Either subsystem operating in conjunction with the safety injection tanks is capable of supplying sufficient core cooling to limit the peak cladding temperatures within acceptable limits for all postulated break sizes ranging from the double ended break of the largest RCS cold leg pipe downward.
In addition, each ECCS subsystem provides long term core cooling capability in the recirculation mode during the accident recovery period.
The Surveillance Requirements provided to ensure OPERABILITYof each component ensure that at a minimum, the assumptions used in the accident analyses are met and that subsystem OPERABILITYis maintained.
The limitations on HPSI pump operability when the RCS temperature is ~270'F and ~236'F, and the associated Surveillance Requirements provide additional administrative assurance that the pressure/temperature limits (Figures 3.4-2a and 3.4-2b) willnot be exceeded during a mass addition transient mitigated by a single PORV. A limiton the maximum number of operable HPSI pumps is not necessary when the pressurizer manway cover or the reactor vessel head is removed.
ST. LUCIE - UNIT 1 8 3/4 5-1 Amendment No. B6, e+,~
~
~ >>
gI>,g AEQUI
~C+
Wp.0 Cy A,0O 4~
~O
+>>*<<+
UNITED STATES NUCLEAR REGULATORY COMMISSlON WASHINGTON> D.C. 2055&0001 FLORIDA POWER
& LIGHT COMPANY ORLANDO UTILITIES COMMISSION OF THE CITY OF ORLANDO FLORIDA AND FLORIDA MUNICIPAL POWER AGENCY DOCKET NO. 50-389 ST.
LUCIE PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
83 License No.
NPF-16 The Nuclear Regulatory Commission (the Commission) has found that:
A.
8.
C.
D.
E.
The application for amendment by Florida Power
& Light Company, et al. (the licensee),
dated January 4,
- 1996, 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 Comtlllsslon; 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'pplicable requirements have been satisfied.
2.
Accordingly, Facility Operating License No.
NPF-16 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 2.C.2 to read as follows:
2.
Technical S ecifications 3.
The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 83
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Project Directorate II-3 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
ATTACHMENT TO LICENSE AMENDMENT NO.
83 TO FACILITY OPERATING LICENSE NO.
NPF-16 DOCKET NO. 50-389 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove Pa es 3/4 5-7 8 3/4 5-2 Insert Pa es 3/4 5-7 8 3/4 5-2
3.5.3 AQIIQH
As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:
a.
One OPERABLE.high-pressure safety injection pump, and An OPERABLE flow path capable of taking suction from the refueling water tank on a Safety Injection Actuation Signal and automatically transferring suction to the containment sump on a Sump Recirculation Actuation Signal.
MODES 3 and 4".
Footnote ¹ shall remain applicable in MODES 5 and 6 when the Pressurizer manway cover is in place and the reactor vessel head is on.
a.
With no ECCS subsystem OPERABLE, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
b.
In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.
The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.
4.5.3 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.
With pressurizer pressure less than 1750 psia.
¹ One HPSI shall be rendered inoperable prior to entering MODE 5.
ST. LUCIE - UNIT2 3/4 5-7 Amendment No. Wi83
o I
In Mode 3 with RCS pressure <1750 psia and in Mode 4, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.
The trisodium phosphate dodecahydrate (TSP) stored in dissolving baskets located in the containment basement is provided to minimize the possibility of corrosion cracking of certain metal components during operation of the ECCS following a LOCA. The TSP provided this protection by dissolving in the sump water and causing its final pH to be raised to greater than or equal to 7.0.,
The requirement for one high pressure safety injection pump to be rendered inoperable prior to entering MODE 5, although the analysis supports actuation of safety injection in a water solid RCS with pressurizer heaters energized, provides additional administrative assurance that a mass addition pressure transient can be relieved by the operation of a single PORV or SDCRV.
A limiton the maximum number of operable HPSI pumps is not necessary when the pressurizer manway cover or the reactor vessel head is removed.
The Surveillance Requirements provided to ensure OPERABILITYof each component ensure that at a minimum, the assumptions used in the accident analyses are met and that subsystem OPERABILITYis maintained.
Surveillance Requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows willbe maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration, (2) provide the, proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.
The requirement to dissolve a representative sample of TSP in a sample of RWT water provides assurance that the stored TSP willdissolve in borated water at the postulated post-LOCA temperatures.
The OPERABILITYof the Refueling Water Tank (RWT) as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA.
The limits on RWT minimum volume and boron concentration ensure that (1) sufficient water is available within containment to permit recirculation cooling flow to the core, and (2) the reactor will remain subcritical in the cold condition following mixing of the RWT and the RCS water volumes with all control rods inserted except for the most reactive control assembly.
These assumptions are consistent with the LOCA analyses.
ST. LUCIE - UNIT2 B 3/4 5-2 Amendment No. +e, &>>83