ML19325D477
| ML19325D477 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/17/1989 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19325D478 | List: |
| References | |
| NUDOCS 8910240233 | |
| Download: ML19325D477 (6) | |
Text
77 4
i
[
. /p" " %,'o, i
UNITED STATES p 3 L.
I[ > r, 'i.
NUCLEAR REGULATORY COMMISSION
. ~n -
2 WASHINGTON. D. C. 20555 c,
t 1
i; g'%.
j lC FLORIDA POWER CCRPORATION CITY OF ALACHUA CITY OF BUSHNELL CTTY OF GAINE5VILLE j
CITY OF KISSIMMEE EITT OF LEE 55UEG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION, CITY OF NEW SMYRNA BEACH l
CITY OF OLALA ORLANDO UTILITIES COMMIs5 ION AND CITY OF ORLANDO SE5 RING UTILITIES COMMISSION e
SEMINOLE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHA55,EE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.124 License No. OPR-72
-1.
The Nuclect Regulatory Commission (the Commission) has found that:
1 A.
The application for amendment by Florica Power Corpuration, et al.
(the licensees) dated July 26, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission'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 anendment will not be inimical to the comon defense and security or to tha 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 requiren,ents have.
been satisfied.
8910240233 891017 DR ADOCK 0500 if,_
h 2
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and pardgraph 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 Anendment No.124, are hereby incorporated in the license.
Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
3, This license amendnient is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
,[g' er ert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications Cate of Issuance: October 17, 1989 1
i l
l l
l 1
L>
F Y
ATTACHMENT TO LICENSE AMENDMENT NO.124 4
FAClllTY OPERATING LICENSE NO. DPR-72 L-00CKET NO. 50-302
?
I Replace the following peges of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and cchtain vertical lines indicating the area of change.
L Remove Insert 3/4 3-37 3/4 3-37 3 /4 3-38 3/4 3-38 3/4 3-39 3/4 3-39 h
e l
l-t l
l l
l l
l
i i
'i
..s INS'IIDEDfMTICH i
POST-ACCIIENT IN!mDEWD.TICH I
LIMITING CI24DITIW Ft2 OPERATICN 3.3.3.6
'1he post-socident monitoriruj instrumentation channels shown in Table 3.3-10 shall be OPERABIE with Imaccats on all channels in th2 control recun. Recorders on instruments 1 thrurA 10 shall be OPERABIE.
APPLICABILITY: M3CES.32, and 3.
LEGti:
a.
With the number of OPERABIE post-accident monitoring channels less than required by Table 3.3-10 (except for Reactor Vessel Inval Instrumentation, itans 21 and 22), either restors the inoperable chanrnal to OPGABLE status within 30 days, or be in HOT SHUIDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
With the number of OPERABIE channels of Reactor Vessel Hot Lag Inval or Reactor Vessel Head Isvel 1 less than recpired by Table 3.3-10, either restore the inoperable channel to OPERABLE status within 7 days or sutanit a report to the Courtission within the next 30 days outlining the cause of the inoperability and the plans and schedule for Instoring the caannel to OPERABIE status.
c.
With the number of OPERABLE channels of Reactor Vessel Hot lag Imvel or Reactor Vessel Head Inval 2 less than required by Table 3.3-10, either restore at least 1 channel to CPGABLE status within 7 days, or be in HOT SHUID3WN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, d.
'Ibe provisions of Specification 3.0.4 are not applicable.
SURWTUANCE REQUIRDENIS 4.3.3.6 Each post-accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL GECK and GANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.
l l
CRYSTAL RIVER UNIT 3 3/4 3-37 Amminent No. f?.I24
e
>y -
? y; ;
' ' " ~
TAINE 3.3-10 IUF-ACCIIEfr MONITORIPC IfMI11MNTATION g
MINIMM 4
g MEY3UREMNP OWNEIS ItBIMMFITP HANGE ORRABLE 1.
Ibwer Range f.'uclear Flux 0-125%
2
!d 2.
Reactor Buildirg Pressum 0-70 psia 2
0-280 psig 2
W 3.
Source Range Nuclear Flux 10-1 to 106@
2 4.
Reactor (bolant Outlet Tenprature 520*F - 620*F 2 per loop 5.
Reactor Coolant Total Flow 0-160 x 106 lb./hr.
1 6.
RC Icop Pmssure 0-2500 psig 2
0-600 psig 1
1700-2500 psig 2
7.
Pressurizer level 0-320 inches 2
8.
Steam Generator Outlet Pmssurn 0-1200 psig 2/st-generator 9.
Steam Generator Operating Range level 0-100%
2/steaum generator Y
10.
Dorated Water Storage Tank level 0-50 feet 2
u" 11.
Startup Feedwater Flow 0-1.5x106 lb./hr.
2 12.
Reactor Coolant System Subcooling Margin Monitor
-658
- F to +658
- F 1
13.
LOIN Position Indicator (Primary Detector)
N/A 1
14.
EDRV Itcition Indicator (Backup Detector)
N/A N/A 15.
IDRV Block Valve Ibsition Indicator N/A N/A 16.
Safety Valve Ibsition Indicator (Primary Detector)
N/A 1/ valve 2~
17.
Safety Valve Ibsition Indicator (Backup Detector)
N/A N/A 18.
Emergency Feedwater Flow 0-850 get 2/st m aior
~
_ st 19.
Reactor Building Flood Level 0-10 feet 2
%f 20.
Core Exit 'Iherinoccuples 0-2500*F 2/qtama<= A.
sa 21.
Rehr Vessel Hot Leg level 0-100%
2 E
22.
Reactor Vessel liead level 0-100%
2
.e e
w m---
m-w e -
T-a-a- - - - -
- ~ - - = ^
-'f1 ;
s v.
I
[^
'h y
9 TABLE 4.3-7..
~
a,,
e INAOCIDENP MONFIORINGCIMDENPATION SURVEIIIANT REQUIREDENTS c: g .r' 01ANNEL QUNEEL ItsrIRIMFNP OIECK OLIIRATI@ 1. Ibwer Range itaclear Flux M-Q* 2. Reactor 111ilding Itessure M ~ R 3d 3. Source Range texlear Flux M R* 6 4. Reactor Coolant Outlet Tenperature M R k 5. Reactor Coolant 'Ibtal Flow Rate M R u 6. RC Icop Pressure M R l 7. Pressurizer Level M R 8. Steam Generator Outlet Pressure M R 9. Steam Generator level M R 10. Borated Water Storage Tank Level M R 11. Startup Feedwater Flow Rate M R 1 12. Reactor Coolant System Subcooling Margin Monitor M R 1 { 13. IOIN Ibsition Indicator (Primary Detector) M R 14. ICIN Ibsition Indicator (Backup Detector) M R 15. IOIN Block Valve Position Indicator M R 16. Safety Valve Position Indicator (Primary Detector) _M R 17. Safety Valve Position ' Indicator (Backup Detector) M R 18. Dnergency Feedwater Flow M R j 19. Reactor Building Flood Ievel M R ~ 20. Core Exit 'Iherinoccuples M R h 21. Reactor Vessel Hot leg level NA R brt 22. Reactor Vessel liead level NA R 4 l .g %D
- Neutrus detectors may be excluded frun GIAltfEL CALIIRATION
~" .,.,,,,.a a,.,, , -}}