ML20198F876
| ML20198F876 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/22/1997 |
| From: | Hebdon F NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198F881 | List: |
| References | |
| NUDOCS 9801120193 | |
| Download: ML20198F876 (10) | |
Text
,
- **:09 p
5 UNITED STATES i
g j
NUCLEAR REGULATORY COMMISSION o
F WASHINGTON, D.C. acaewooi 4.,...../
i FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEFSBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION.
CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLAN(1Q SEMINOLE ELECTRIC COOPERATIVE. INC.
fJiY OF TALLAHASSEE DOCKET NO 50 302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.162 License No. DPR-72 1.
The Nuciear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power Corporation, et al.
(the licensees) dated July 29,1997, as supplemented on October 29,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulatior.4 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 (1) that the activities authorized by this amendment can be conducted without endangering the health and saiety 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.
9001120193 971222 PDR ADOCK 05000302 P
I 4
2-2, Accordingly, the license is amended by changes to the Technical Spscifications 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 Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.162, are hereby incorpnrated 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 and shall be implernented within 30 days.
FOR THE NUCLFAR REGULATORY COMMISSION Frederick J. Hebdon, Director Project Directorate ll 3 Division of Reactor Projects - 1/II Office of Nucinar Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: December 22, 1997 4
i l'
l
=. _.
ATTACHhnENT TO LICENSE AMENDMENT NO.1(a 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 verticallines indicating the area of change.
Remove Replace 3.3 41 3.3 41 B3.3126 B3.3126 B3.3127 B3.3127 B3.3131 B3.3131 B3.3138 B3.3138 B3.3138A B3.3138B f
4 PAM Instrumentation 3.3.17
'Toble 3.3.17 1 (pose 1 of 1)
Peet Accident mentterine Instrw entation COWelflout REFEREWCED FROM FUNC180N kEinnaED CRA&ELS REGUIRED ACfl0N 0.1 1.
Wiele sance seutron Flum 2
E
- 2. RC8 Not Leg Temperature 2
E 3.
RC8 Prosaure (Wiele tonee) 2 E
4 Reecter Caotont Itwentory 2
F 3.
Sersted Weter Storage Tank Level 2
E 6.
Niph Pressure injectlen Flow 2 pe-Injectlen line E
7.
Centelement Sump Weter Level (Flood Level) 2 E
8.
Centairveent Pressure (Expected Post Accident 2
E l
Range) 9.
Centairment Pressure (Wide Range) 2 E
- 10. Centairment teolation valve Position a per penetratiente)(b) g
- 11. Centefruent Area Radiation (Nish tonee) 2 F
- 12. Contalruent Nydrogen Conce..tration 2
E
- 13. pressuriser Lent 2
E 14 Steen Generator Water Level (start * @ Rente) 2 pvr CTSG E
- 15. Steen Generator Water Level (operating tense) 2 per 075G E
- 16. Steen Generator Pressure 2 per Of8G E
- 17. Emersoney Feechseter Tonk Level 2
E
- 18. Core talt Temperature (seck w )
3 per core spandrent E
l
- 19. Emergency Feedwater Flow 2 per CTSG E
- 20. Law Preseure Injectlen Flow 2
E
- 21. Degrees of $ 4ceeting 2(d)
E
- 22. Emergency Diesel Generator kW Indication 2(8)
E (a) kly one peeltlen Indicotten to respaired for penetrettens with one Centret 'een Indicator.
(
(b) het required for f eetation vetwee dose associated penetration le teolated by at least one closed and l
aleectivated outematic volve, closed annust velve, blind fienee,. check volve with flow through the votw secured.
(c) h e trWlcater per EDC.
l l
(d) These two channele of escoeting margin are becked w by either of two trWicetiene of escoeting mergin booed on eleller inpute throoph the Safety Peremeter Oleplay System (BeOS). At least one SeOS channet must be evellebte to provids this becke. With both spos chamete IWOPERA8LE, Canditlen C le e,pticebte.
Crystal River Unit 3 3.3-41 Amendment No. 162
PAM Instrumentation B 3.3.17 i
i BASE 5 1
LCO The.following list is a discussion of the specified (continued) instrument Functions listed in Table 3.3.17-1.
3.
Miie Ranae Neutron Flux Two wide-range neutron flux munitors are provided for post-accident reactivity monitoring over the entire range of expected conditions.
E indicationovertherangeof10'pchmonitorprovides to 100% log rated power covering the source, intermediate, anc power l
ranges.
Each monitor utilizes a fission chamber neutron detector to provide redundant main control board indication. A single channel providos recorded information in the control room. The control room indication of neutron flux is considered one of the primary indications used by the operator following an accident.
Following an event the neutron flux is monitored for rea:tivity control.
The operator ensures that the reactor trips as necessary and that emergency boration is initiated if required.
Since the operator relies upon this indication in order to take specified manual action, the variable is included in this LCO. Therefore, the LCO deals specifically with this portion of the string, i
l 2.
Reactor Coolant System (RCS) Hot Leo Temoerature i
Two wide range resistance temperature detectors (RTD's), one per loop, provide indication of reactor coolant system hot leg temperature (T ) over the range of 120' to 920'F.
Each T measuremer $ provides an input to a control room indicator.
Ihannel B is also recorded in the control room. Since 'he operator I
relies on the control room indication 'ollowing an accident, the LCO deals specifically w th this portion of the string.
T, is a Type A variable on which the operator bases manual actions required for event mitigation for which no automatic controls are provided.
(continued)
Crystal River Unit 3 8 3.3-126 Amendment No. 162 i
PAM Instrumentation B 3.3.17 BASES LCO 2.
. Reactor Coolant System (RCS) Hot Leo Temeeraturg (continued)
Following a steam generator tube rupture, th~e affected 1 1
steam generator is to be isolated only after T falls 3
below the saturation temperature corresponding to the pressure setpoint cf the main steam safety valves.
For event monitoring once the RCP's are tripped. T is 3
used along with the core exit tem >eratures and RCS cold leg temperature to measure tae temperature rise across the core for verification of : ore cooling.
3.
RCS Pressure (Wide Ranoel RCS pressure is ransured by pressure transmitters with a span of 0 3000 psig. Redundant monitoring capability is provided by two trains of instrumentation. Control roem and remote shutdown panel indications are provided. The control room I
indications are the primary indications used by the operator during an accident. Therefore, the LCO deals specifically with this portion of the instrument string.
RCS pressure is a Type A variable because the operator uses this indication to adjust parameters such as steam generator (OTSG) level or pressure in order to monitor and maintain a controlled cooldown of the RCS fo11 cuing a steam generator tube rupture or small brean LOCA.
In addf tion, HPI flow is throttled based 9
4 (continued)
Crystal River Unit 3 B 3.3-127 Amendment No.162
. s PAM Instrumentation B 3.3.17
^
BASES LC0 8,9.. Containment Pressure (Eroacted Post Accident Ranas and (continued)
Wide Ranae)
The containment pressure variable is. monitored by two ranges of pressure indication.
Expected post-accident range ( 10 to 70 psig) and wide range (0 to 200 psig) pressure indication each provide two channels of pressure indication. Channel A and B wide range containment pressure are recorded in the associated
'A' and 'B' EFIC Rooms.
The low range is required in order to ensure instrumentation of the necessary accuracy is available to monitor conditions in the RB during DBAs. The wide range instrument was required by Regulatory Guide 1.97 to be capable of monitoring pressures over the range of atmospheric to three times containment design pressure (approximately 165 psig).
Thus, it was intended to wonitor the RB in the event of an tecident not bounded by the plant safety analysis (i.e.,aSevereAccident).
These instruments are not assumed to provide information required by the operator to take a mitigation action specified in the accident analysis.
As such, they are not Type A variables. However, the monitorsaredeemedrisksignificant(Category 1)and are included within the LCO based upon this consideration.
1 (continued)
Crystal River Unit 3 B 3.3-131 Amendment No. 162
s
~
PAM Instrumentation B 3.3.17 BASES-LCO
- 18.. Core Exit Temnerature (Backun)
(continued) following a steam generator t9be rupture or small break LOCA. Operator actions to maintain a controlled cooldown, such as adjust'ng OTSG level or pressure, would be prompted by this indication.
L 19.
Emeroency Feedwater Flow EFW Flow instrumentation is provided to monitor operation of decay heat removal via the OTSGs. The EFW injection flow to each OTSG (2 channels determined from a differential pressure me one associated with each EFW injection line is urement calibrated to a span of 0 gpm to 1000 ppm.
Each differential pressure transmitter provides an input to a control room indicator and the plant computer.
EFW Flow is used by the operator to detemine the need to throttle flow during accident or transient conditions to prevent the EFW pumps from operv.ing in runout conditions or from causing excessive RCS cooldown rates when low decay heat levels are present.
EFW Flow is also used by the operator to verify that the EFW System is delivering the correct flow to each OTSG. However, the prih.ary indication of this l
function is provided by OTSG level.
These instruments are not assumed to provide information required by the operator to take a mitigation action specified in the safet As such, they are not Type A variables. y analysis.
However, the monitors are deemed risk significant (Category 1) and l
are included within the LCO based upon this i
consideration.
i t
(continued)
Crystal River Unit 3 8 3.3-138 Amendment No.162
I PAM Instrumentation B 3.3.17 BASES' LCO
- 20.. Low Pressur#LIn_iection Flow (continued)
L0w pressure injection flow instrumentation is
>rovided to monitor flow to the RCS following a large 2reak LOCA.
It is also used to monitor LPI flow during piggy back operation following a small break LOCA. The low pressure injection flow to the reactor
[2 channels, one associated with each LPI injection line)isdeterminedfromadifferentialpressure measurement calibrated to a span of 0 gpm to 5000 gpm.
The LPI flow indication is used by the operator to throttle the flow to s 2000 gpm prior to switching the pump suction from the BWST to the RB sump. This assuresadequatenetpositivesuctionhead(NPSH)is maintained to the pump. The indication is also used to verify LPI flow to the reactor as a prerequisite to termination of HPI flow.
Since low >ressure injection flow is a Type A variable on which tie operator bases manual *ctions required for event miti are provided, gation for which no automatic controls it has been included in this LCO.
21.
Decrees of Subcoolina Two channels of subcooling margin with inputs from RCS hot leg temperature RCS pressure are prov(T ), core exit temperature, and i5ed. Multi >1e core exit temperatures are auctioneered wit 1 only the highest temperature being input to the monitor. A note has been arided to indicate that the two channels of subcooling margin are backed up by either of two indications of subcooling margin based on similar inputs through the Safety Parameter Display System (SPDS). At least one SPDS channel must be available to provide this backup. With both SPDS channels INOPERABLE, Condition C is applicable. This is considered necessary because the core exit thermocouple inputs to the subcooling margin monitors are not environmentally qualified.
The T inputs to i
the subcooling margin monitors and SPDS o,perate over a range of 120 to 920'F.
The core exit temperature inputs operate over a range of 150 to 2000'F and 150 (continued)
Crystal Rive Jnit 3 8 3.3 13BA Amendment No.162
_ _ _ _ _ _ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - ' - - ' ' - - - ~ - - - - - - - - - ~ - - - - - - - ' - - - ~ - - - - ~ ~ - - ~ ~ ~
w 1
l PAM Instrumentation B 3.3.17 BASES LCO
- 21.. Deareas of Subcoclina (continued) to 2500'F for the subcooling margin monitors and SPDS, respectively.
RCS pressure inputs operate over a range of 200 to 2.500 psig.
The subcooling margin monitors are used to verify the existence of, or to take actions to ensure the restoration of subcooling margin. Specifically, a
.oss of adequata subcooling margin during a LOCA requires the operator to trip tse reactor coolant
, pumps (RCFs), to ensure high or low pressure injection, and raise the steam generator levels to the inedequate subcooling margin level. Since degrees of subcooling is a Type A variable on which the operator bases manual actions required for event mitigation for which no automatic controls are provided, it has been included in this LCO.
22.
Emeroency Diesel Generator. kW Indication TheEmergencyDieselGenerator(EDG)providesstandby (emergency) electrical power in the case of Loss of OffsitePower(LOOP).
EDG kW indication is provided in the control room to monitor the operational status of the EDG.
EDG Power (kW) output indication is a type A variable bscause EDG kW indication provides the control room operator EDG load management capabilities.
EDG load managem6nt enables the operator to base manual actions of load start and stop for event mitigation.
(continued)
Crystal River Unit 3 8 3.3-1388 Amendment No. 162
~~'
_