ML20237D784
| ML20237D784 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/14/1987 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20237D786 | List: |
| References | |
| NUDOCS 8712240183 | |
| Download: ML20237D784 (7) | |
Text
-
4 8
o
' UNITED STATES
! ", c ( [',i NUCLEAR REGULATORY COMMISSION
' g
/ j WA$HINGTON. D. C. 20555 k..... o 8
FLORIDA POWER CORPORATION I
CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE
-CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEBRING UTILITIES COMMISSION SEMIN0LE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSE,E DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.101 License No. DPR-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power Corporation, et al.
(the licensees) dated April 15, 1987, 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; and 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.
h22QQ h 2
P l
L,.
2..
Accordingly, the license is amended by changes to the Technical
-Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-72 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.101, are hereby incorporated in the license.
Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
J.
This' license amendment is effective as of its date of issuance.
~5 FOR THE NUCLEAR REGULATORY COMMISSION erbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to,the Technical Specifications Date'of Issuance: December 14, 1987
)
1
4 ATTACHMENT TO LICENSE AMENDMENT N0.101 i
FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace the following pages of the Appendix "A" Technical Specifications with the attached 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 Insert 3/4 5-2 3/4 5-2 B3/4 5-1 B3/4 5-1 0
i
EMERGENCY CORE COOLING SYSTEMS
.e SURVEILLANCE REQUIREMENTS (Continued) ll b.
At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of each solution volume increase of > 80 gallons by verifying the boron concentration of the tank solution.
1
.c.
At least once per 31 days by verifying that power to the isolation valve operator is removed by locking the breaker in the open position.
d.
At least once per 18 months by performing a CHANNEL CALIBRATION i
of each core flooding tank isolation valve closed alarm.
l i
i
\\
l 1
'\\l
- (
i CRYSTAL RIVER - UNIT 3 3/4 5-2 Amendment No.101 1
- - _ _= -__ = __
4 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
CORE FLOODING TANKS LIMITING CONDITION FOR OPERATION Each reactor coolant system core flooding tank shall be OPERABLE 3.5.1 with:
a.
The isolation valve open, A contained borated water volume between 7555 and 8005 b.
gallons of borated water, Between 2270 and 3500 ppm of boron, and c.
d.
A nitrogen cover-pressure of between 575 and 625 psig.
APPLICABILITY: MODES 1, 2 and 3*.
ACTION:
With one core flooding tank inoperable, except as a result of a closed isolation valve, restore the inoperable tank to OPERABLE a.
status within one hour or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
With any core flooding tank inoperable due to the isolation b.
valve being closed, either immediately open the isolation valve or be in HOT STANDBY within one hour and be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS Each core flooding tank shall be demonstrated OPERABLE:
4.5.1 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:
a.
1.
Verifying the contained borated water volume and nitrogen cover-pressure in the tanks, and 2.
Verifying that each tank isolation valve is open.
- With Reactor Coolant pressure >750 psig.
CRYSTAL RIVER - UNIT '3 3/4 5-1 I
i
s N
P ik 1
-t l:
E.
p, 3/4.5 EMERGENCY CORE COOLING SYST2LS, (ECCS)
R
'L q
" lie S 1 CORE FLOODING TANKS i-The OPERABILITY of each core flooding tank ensures that a sufficient volume of e
borated water will be immediately forced into the reactor vessel in the event the RCS pressure falls below the pressure of the tanks.
This initial surge of l
7..
water into the vessel provides the. initial cooling mechanism during large RCS
.I pipe ruptures.
{
1 I
Thet4. Nits in f volume,D, boron concentrc. tion and. pressure ensure that the assuunhons ud for ccrie ficoding tank injection in the safety analysis are i
net.
l Tine limits for operation with a core flooding tank inoperable for any reason
' except en isolation valve closed minimizes the time exposure of the plant ~ to a LO:A. event occurring concurrmt with the failure of an additional tank which say. restle in unacceptable pak cladding temperatures.
If a closed isolation valve cannot be immediately opefed, the. f ull capability of one tank is net availablej and prompt action is required to place the reactor in a mode where this capeJility is not rectired, t
The Cc R Flooding Tank Isolation Valve Closed Alarm provides a warning to operato$ whenever any Core Flooding Tank Isolation Valve is not fully open and 1
the Ectutor Coolant System pressure exceeds 750 psig.
l l
t t,
{
)
1 1
1 3-
~,
s 7
3 w
3l,.js i
I i
e t
I t -
.h,
I
/
(;
g f )l 4
r y
t 4'
b
)
./ I 1
(f-c 1
i j
4
')
i
\\
.t
\\
+.
l
<k-I l-N 1 CR'tSTAL RIVtv - M7;,3 B 3/4 5-1 Mendment flo.101 t
')
i f
I. '
sw
.V m.
A D _ _ _ _ _ _ _ _
y
EMERGENCY CORE-COOLING SYSTEMS BASES 3/4 ~.5.2 and 3/4.5.3 ECCS SUBSYSTEMS The OPERABILITY of-two independent ECCS subsystems with RCS average temperature p 230'F ensures that sufficient emergency core cooling.
capability dll be 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 core flooding tanks is capable of supplying sufficient core cooling to maintain the peak cladding tempera-tures 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.
With' the RCS temperature below 280*F, one OPERABLE ECCS subsyster-is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.
The Surveillance Requirements provided to ensure OPERABILITY of each component ensures, that, at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained.
The decay heat renoval system leak rate surveillance requirements aswre that the leakage' rates. assumed for the system during the recirculation.
phase of the low pressure irdection will not be exceeded.
The purpose of these surveillance requirements is to provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Main.
tenance 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.
3/4.5.4 BORATED WATER STORAGE TANK The OPERABILITY of the borated water storage tank (BWST) as part of the ECCS ensures that a sufficient supply of berated water is available for injection by the ECCS in the event of a LOCA. The limits on BWST sinimtsn 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 suberitical in the cold condi-tion following mixing of the BWST 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.
CRYSTAL RIVER - UNIT 3 8 3/4 5-2 Amendment No.17
)
JM d B79
-