ML20214V610
| ML20214V610 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  (DPR-72-A-100) |
| Issue date: | 05/28/1987 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214V613 | List: |
| References | |
| NUDOCS 8706120190 | |
| Download: ML20214V610 (7) | |
Text
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o, UNITED STATES 8
7.
NUCLEAR REGULATORY COMMISSION g
p WASHINGTON, D. C. 20555 l
FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINE5VILLE 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 SEMINOLE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 100 License No. DPR-72 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Florida Power Corporation, et al.
(the licensees) dated January 24, 1985, as supplemented February 17, 1987, 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) 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 Comission's regulations and all applicable requirements have
)
been satisfied.
8706120190 870528 DR ADOCK 05000302 PDR
l I
{' 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.100, are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION e e m tester S. Rubenstein, 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: May 28, 1987
ATTACHMENT TO LICENSE AMENDMENT NO.100 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 l
3/4 3-13 3/4 3-13 3/4 3-16a 3/4 3-16a
~
TABLE 3.3-3 (Cont'd) n M
d ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION y
MINIMUM t-TOTAL NO.
CHANNELS CHANNELS APPLICABLE it!<
FUNCTIONAL UNIT OF CHANNELS TO TRIP _
OPERABLE MODES _
ACTION rn M
5.
REACTOR BLDG. ISOLATION C3 a.
Manual initiation 2
1 2
1, 2, 3, 4 13
-4 b.
Reactor Bldg. Pressure 3
2 2
1, 2, 3 9#
High w
c.
Automatic Actuation Logic 2
1 2
1, 2, 3, 4 10 l
~
Y d.
Deleted C
e.
RCS Pressure Low 3
2 2
1, 2, 3
- 13 (HPI Isolation) f.
Automatic Actuation Logic 2
1 2
1, 2, 3, 4 10 (HPI Isolation) i E
a 4
.O L
8 i
e TABLE 3.3-3 (Continued)
TABLE NOTATION
- Trip function may be bypassed in this MODE with RCS pressure below 1700 psig. Sypass shall be automatically removed when RCS pressure exceeds 1700 psig.
" Trip function may be bypassed in this MODE with RCS pressure below 900 psig. Bypass shall be automatically removed when RCS pressure exceeds 900 psig.
- o* Trip function may be bypassed in this MODE with steam generator pressure below 750 psig.
Bypass shall be automatically removed when steam generator pressure exceeds 750 psig.
4
- Tne provisions of Specification 3.0.4 are not applicable.
- Trip automatically b passed below 20 pe'rcent of RATED THERMAL POWER.
3
- Trip function may be bypassed below 10 percent of RATED THERMAL POWER.
- Manual trip fenetion occurs if two channels in the same train are actuated.
ACTION STATEMENTS ACTIOD 9 With the number of OPERABLE Channels one less t.han the Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placec m the tripped condition within I hour.
ACTION 10 -
With the number of OPERABLE channels one less than the Total Number of Channels, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to I hour for Surveillance testing per Specification 4.3.2.1.1.
ACTION 11 -
With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge and exhaust valves are maintained closed.
ACTION 12 -
With the number of OPERABLE Channels one less than the Total Number of Channels, opera: ion"ma;. practed provided ;he incpercble chawei is placed m the bypassed condition and the minimum channels OPERABLE required is demonstrated within I hour; one additional channel may be bypassed for up l
to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for Surveillance testing per Specification 4.3.2.1.1.
ACTION 13 -
With the number of OPERABLE Channels one less than the Total Number of Channeis, restore the inoperable channe! to OPERABLE status within 45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ACTION 14 -
With the number of OPERABLE Channels one less than the Tota! Number of I
Channels, operation may proceed provided the inoperable channel is placed in the tripped cond tiva widun a hour, une meditional cnannel may be bypassec for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for Surveillance testing per Specification 4.3.2.1.1.
l 3/c 3-14 Amendment flo. 38,78
-. CRYSTAL RIVER UNIT 3
e.
TABLE 3.3 4 (Continued) gn d
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM _ INSTRUMENTATION TRIP SETPOINTS s'rz FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
~2 Q
3.
REACTOR BLDG. ISOLATION c
a.
ES Actuation "A" and "B" 3
[
1.
Manual Initiation Not Applicable Not Applicable 2.
Reactor Bldg. Pressure High 6 4 psig f 4 psig 3.
Automatic Actuation Logle Not Applicable Not Applicable 4.
Deleted R.
I P
3.
RCS Pressure Low
{
(HPI Isolation) 21500 psig 21300 psig I
6.
Automatic Actuation Logic (HPI Isolation)
Not Applicable Not Applicable E
i a
.E
=
i 8
1
TABLE 3.3-5 ENGINEERED SAFETY PEATURES RESPONSE TIMES INITTATING SICNAL AND PUNCTION RESPONSE TIME IN SECONDS *
)
1.
Manual a.
High Prenure Injection Not App!! cable b.
Low Pressure Injection Not Applicable c.
Reactor Building Cooling Not Applicable d.
Reactor Building Isolation Not Applicable Reactor Building Spray Not Applicable e.
f.
Reactor Building Purge Isolation Not Applicable g.
MPW and M5L 1 solation l
1.
Emergency Peedwater Actuation Not Applicable 2.
Feedwater Isolation Not Applicable 3.
5 team Line Isolation Not Applicable h.
Emergency Peedwater Actua-lon Not Applicable l
2.
Reactor Bu!! dine Pressure-High High Pressure injection 23*
a.
b.
Low Pressure injection 23*
c.
Reactor Building Cooling 25*
d.
Reactor Building Isolation 60*
)
3.
Resetor Bu!! dint Pressure Hirh-High fwlth HP! sirnal) a.
Reactor Building 5 pray 36*
4.
RCS Pressure Low a.
High Pressure Injection 73 +
b.
HPIIsolation 60+
J.
RCS Pressure Low-Lew i
a.
High Pressure Injection 25' b.
Low Pressare Injection 25' i
6.
Low 5 team Generater Pressure i
i m.
Pecdwater Isolation 34 l
h.
Steam Line Isolation -
J 1
c.
Emergency Peedwater Actuation Not Applicable l
l l
CR,Y5TAL RIVER - UNIT 3 3/4 3-17
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