ML20077L958
| ML20077L958 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/25/1983 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Florida Power Corp, City of Alachua, FL, City of Bushnell, FL, City of Gainesville, FL, City of Kissimmee, FL, City of Leesburg, FL, City of New Smyrna Beach, FL, Utilities Commission, City of New Smyrna Beach, FL, City of Ocala, FL, City of Orlando, FL, Orlando Utilities Commission, Sebring Utilities Commission, Seminole Electric Cooperative, City of Tallahassee, FL |
| Shared Package | |
| ML20077L960 | List: |
| References | |
| TAC 49356, DPR-72-A-066 NUDOCS 8309120046 | |
| Download: ML20077L958 (11) | |
Text
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[0, UNITED STATES
[(
g NUCLEAR REGULAYORY COMMISSION WASMGTON, D. C. 20656 p
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FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNEi.L CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA 3EACH AND UTILITIES COMt1ISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEBRING UTILITIES COMMISSION SEMIN0LE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKETNO.50-302I CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 66 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 14, 1983, and as supplemented on January 20, July 6, and July 14, 1983, 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 Comission; 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 Comission'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.
e309120046 030825 DR ADOCK 05000
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-2 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 TheTechnichfSpecificationscontainedinAppendices f
A and B, as revised through Amendment No. 66, 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 the date of its issuance.
FOR THE NUCLEAR REGULA. TORY COMMISSION O
>QNH $
'Jo F. Stolz, Chief Op ating Reactors Branch *4
( Di ision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 25, 1983 s
1 ATTACHMENT TO LICENSE AMENDMENT NO. 6G FACILITY OPERATING LICENSE NO. OPR-72 l
DOCKET NO. 50-302 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages ar'e identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document compl etenes s.
Pages 3/4 3-:8 3/4 3-19 2/4 3-20 3/4 3-21 B3/4 3-1 e
v 9
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TABLE 3.3-5 (Cont'd)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITI ATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS
- 7.
Centainment Radioactivity-High a.
Reactor Building Purge Isolation 15
- gi Main Feedwater Pumo Turbines A and B Control Oil Low yf 8
a.
Emergency Feedwater Actuation Not Applicable 9
OTSG A and B Level Low-Low a.
Emergency Feedwater Actuation Not Applicable
- Diesel Generat'or starting and sequenca loading delays included.
Response time limit includes movement of valves and attainment of pump or blower discharge pressure.
CRYSTAL RIVER - lMIT 3 3/4 3-17a Amendment No. 38
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_T_A_BLE 4.3-2 y
ENGINEERED SAFETY FEATURii ACTUATION SYSTiiM INSTRUMENTATION SURVEILLANCE ItEQUlitEMENTS
>r iS CIIANNEL
' MODES IN willCil CliANNEL CilANNEL FUNCTIONAL SURVEILLANCE W
FUNCTIONAL UNIT ClltiCK CALIBRATION TEST ltEQUIRED C
h 1.
SAFETY INJECTION a.
High Pressure Injection l
1.
Manual Initiation N/A N/A R
5 or 6 2.
React'or Building Pressure liigh S
R M(2) 1, 2, 3 3.
RCS Pressure Low S
R M
1, 2, 3 7
4.
RCS Pressure Low-Low 5
R M
1, 2, 3 5.
Automatic Actuation Logic N/A N/A M(1)(3)(5) 1, 2, 3, 4 l
b.
Low Pressure injection l
1.
Manual Initiation N/A N/A R
5 or 6 2.
Reactor Building Pressure liigh 5
R M(2)
I, 2, 3 3.
RCS Pressure Low-Low S
R M
1, 2, 3
,E 4.
Automatic Actuation Logic N/A N/A M(1) (3) 1, 2, 3, 4 2.
REACTOR BUILDING COOLING a.
Manual Initiation N/A N/A R
Sor 6 g
b.
Reactor Building Pressure liigh S
R M(2) 1, 2, 3
{
.c.
Automatic Actuation Logic N/A N/A M(1)(3)(5) 1, 2, 3, 4
hABLE4.3-2(Cont'd) h ENGINEERED SAf ETY FEATURL ACTUATION SYSTI.its INSTRUMENTATION SURVE 7:
CilANNEL liODES IN WillCil CllANiiEL CllANNEL FUNCit0NAL SURVEILLANCE CilECK CALIBRA110N IEST R E_QU IR_EI) __
- FUNCTIONAL UNIT g;
e gg 3.
REACTOR BLDG. SPRAY a.
Reactor Bldg. Pressure liigh-High coincident with IIPI Signal 5
R M(4) 1, 2, 3 b.
Automatic Actuation Logic N/A N/A M(1)(3)(5) 1, 2, 3 M
[, 4.
OTilER SAFETY SYSTEMS u) a.
Reactor Bldg. Purge Exhaust Duct isolation on liigh Radioactivity 1.
Gaseous s
Q M
All Modes b.
Steam Line Rupture Matrix l.
Low SG Pressure N/A R
N/A 1, 2, 3 i[
2.
Automatic Actuation Logic N/A N/A M
1, 2, 3 5.g c.
Emergency feedwater n
[,
1.
Main feedwater Pump Turbines S
R N/A 1, 2, 3 o
A and B Control Oil Low 2.
OTSG A and B Level Low-Low 5
R.
N/A 1, 2, 3, 4
TAnl.E 4.3-2 (Cont'd) nW d
ENGINEERED SAFETY FEATURE ACTUATION SYSTliM INSTRUMENTATION StJItVEILLANCE IIEQUlliEMENTS
-i>r N
CllANNEL MODES IN WillCII CllANNEL CllANNEL FUNCTIONAL SilitVEll. LANCE y
p FUNCTIONAL UNIT CilECK CAI.InitATION TEST ItEQtJIRED 8
C~
f 5.
REACTOR BUILDING ISOLATION u
a.
Manual Initiation N/A N/A R
5 or 6 b.
Reactor Building Pressure liigh 5
R M(2)
I, 2, 3 s
c.
. Automatic Actuation Logic.
N/A N/A M(1)(3)(5) 1, 2, 3, 4 l
d.
Manual Initiation (IIPI Isolation)
N/A N/A R
5 or 6 u3 e.
RCS Pressure Low g
y (ElPI Isolation)
S R
M 1, 2, 3 E$
f.
Automatic Actuation Logic (llPI Isolation)
N/A N/A M(1)(3)(5)
I, 2, 3, 4 j
i l
8 n
rt 5
=
TABLE 4.3-2 (Continued)
TABLE NOTATION (1)
The CHANNEL FUNCTIONAL TEST of the Automatic Actuation Logic need only demonstrate one combina. tion of the three two-out-of-three logic combinations that are operable provided that a different combination is tested at each test interval, such that all three combinations will be confirmed to be operable by the time the third successive test is completed.
(2) The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying pressure to the appropriate side of the transmitter.
(3)
Each logic channel shall be tested at least once every other 31-day period (applies only to Test Groups HPI-3, LPI-l and LPI-2 for the j
duration of Fuel Cycle 5 - see (5) below).
I (4)
Reactor building pressure High-High signal only.
I (5) Monthly CHANNEL FUNCTIONAL TEST of the Automatic Actuation Logic circuitry has been waived for all Test Groups with the exception of Test Groups HPI-3, LPI-l and LPI-2 for the duration of Fuel Cycle 5'-for Crystal i
River Unit 3.
1 CRYSTAL RIVER UNIT 3 3/4 3-21 Amendment No. 66
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INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm / trip setpoints within the specified limits.
APPLICABILITY:
As shown in Table 3.3-6.
ACTION:
a.
With a radiation monitoring channel alarm / trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or declare the channel inoperable.
b.
With o'ne or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
J SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrementation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRA-TION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in Table 4.3-3.
CRYSTAL RIVER - UNIT 3 3/4 3-22
3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR PROTECTION SYSTEM (RPS) AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM (ESFAS) INSTRUMENTATION The OPERABILITY of the RPS and ESFAS instruhentation systems ensure that 1) tne associated ESFAS action and/or RPS trip will be imtiated when the parameter monitored by each channel or combination thereof exceeds its setpoint, 2) the specified coincidence logic is maintained, 3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance, and 4) sufficient system functional capability is available for RPS and ESFAS purposes from diverse parameters.
The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.
The surveillance requirements specified for these systems ensure that the overal system functional capability is maintained comparable to the original design standards.
The periodic surveillance tests performed at the m,inimum frequencies are sufficient to demonstrate this capability. The ESFAS Functional Unit CHANNEL FUNCTIONAL TESTS shall be performed in accordance with Regulatory Guide 1.22 (Revision 0,1972).
The measurement of response time at the specified frequencies provides assurance that the RPS and ESFAS action function associated with each channel is completed within the time limit assumed in the safety analyses. No credit was taken in the analyses for those channels with reponse times indicated as not applicable.
Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such test demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizing replacement sensors with certified response times.
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CRYSTAL RIVER - UNIT 3 B 3/4 3-1 Amendment No. 66
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3/4.3 INSTRUMENTATION BASES 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the r3d5ation monitoring cnannels ensures that
- 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
3/a.3.3.2 INCORE DETECTORS The OPERABILITY of the incore detectors ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.
See Bases Figures 3-1 and 3-2 for examples of acceptable minimum incore detector arrangements.
3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that suffi-cient capabilit) is available to promptly determine the magnitude of a seismic event so that the response of those features important to safety -
may be evaluated.
This capability is required to permit comparison of the measured response to that used in the design basis for the facility.
This instrumentation is consistent with the recommendations of Safety Guide 12 " Instrumentation for Earthquakes", March 1971.
3/4.3'.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health ard safety of the public.
This instrumentation is consistent with the reconsnendations of Regulatory Guide 1.23 "0nsite Meteorological Programs", February 1972.
3/4.3.3.S REMOTE SHUTDOWN ;NSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of CRYSTAL RIVER - UNIT 3 8 3/4 3-2