ML20199L044
| ML20199L044 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/24/1997 |
| From: | Wharton L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20199L032 | List: |
| References | |
| NUDOCS 9712010262 | |
| Download: ML20199L044 (27) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION g
'f WASHINGTON. D.C. 30eeH001
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@AHA PUBLIC PGWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE
/mendment No. 182 micense No. DPR-40 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Omaha Public Power District (the licensee) dated May 20, 1996. complies with the standards and recuirements of the Atomic Energy Act of 1954. as amended (the Act),
anc the Commission's rules and regulations set forth in 10 CFR Chapter a:
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 safety of the public and (ii) that such activities will be conducted in compliance with the Commission's regulations:
D.
The issuance of this license 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, 9712010262 971124 PDR ADOCK 05000295 P
2; 2
r 12.
Accordingly.-Facility Operating License.No. DPR-40.is amended by changes to the Technical Specifications-as indicated in the attachment-to this-license amendment,- and paragraph 3.B. of Facility Operating License No.
DPR-40:is hereby amended to read-as follows:
B.
Technical SDecifications The Technical Specifications contained in Ap)endix A as
- revised through Amendment No. 182, are here?y incorporated in the license.
The licensee shall operate the facility in-accordance with the Technical Specifications.-
3.
- The-license amendment is effective as of its date of issuance to be -
implemented within 120 days from the date of issuance.
FOR THE NUCLEAR REGULATOR COMMISSION k
I L
L. Raynard Wharton, Project-Manager-Project Directorate IV-2 L
Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to.the Technical Specifications Date of Issuance: November ~24, 1997 Y
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t ATTACHMENT TO LICENSE AMENDMENT NO. 182 FACILITY OPERATING LICEWSE NO. DPR-40 DOCKET NO. 50 285 Revise Appendix "A" Technical Specifications as indicated below.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change, REMOVE PAGES INSERT PAGES 1
1 2-16a 2-16a 3-1 3-1 32 32 3-3 3-3 3-4 3-4 3-5 3-5 3-6 3-6 37 3-7 c
3-8 38 3-9 3-9 3-10 3-10 3-11 3-11 3-12 3-12 3-12a 3-12a 3-14 3-14 3 15 3-15 3-16 3-16 3-16a 3-16a 3-16b 3-16b 3-16c 3-16c 3-16d 3-16d 3-16e 3-16e 3-20d 3-20d
1 TECilNICAL SPECIFICATIONS TABLE OF CONTENTS PAGE DE FI NITI ONS.......................................................... I l.0 SAfTI'Y LIMITS AND LIMITING SAFETY SYSTEM SETTINGS................ 1 1 1.1
' Safety Limits - Reactor Core
.....................................11 1.2 Safety Limit. Reactor Coolant System Pressure.......
..................14 1.3 Limiting Safety System Settings. Reactor Protective System
..................16 2.0 LIMITING CONDITIONS FOR OPERATION............................. 2-0 2.0.1 General Requirements.......................,........... 2 0 2.1 Reactor Coolar System
.....................21 2.1.1 Operable Components.................................... 2 1 2.1.2 Heatup and Cooldown Rate................................. 2 3 2.1.3 Reactor Coolant Radioactivity...
,............ 2-8 2.1.4 Reactor Coolant System Leakage Limits........................ 2 11 2.!.5 Maximum Reacter Coolant Oxygen and Halogens Concentrations......... 213 2.1.6 Pressurizer and Main Steam Safety Valves....................... 215 2.1.7 Pressurizer Operability.................................. 2 16a 2.1.8 Reactor Coolant System Vents............................. 2 16b 2.2 Chemical and \\,elume Control System..
.................... 2 17 2.3 Emergency Core Cooling System.................................. 2 20 2.4 Containment Cooling
...... 2-24 2.5 Steam and Feedwater System.
...... 2-28 2.6 Containment System..........
.... 2 30 2.7 Electrical Systems.............
........ 2-3 2 2.8 Refueling Operations.......
...... 2-3 7 2.9 Radioactive Waste Disposal System
......... 2-4 0 2.10 Reactor Core........
.. 2-48 2.10.1 Minimum Conditions for Criticality.
..............248 2,10.2 Reactivity Control Systems and Core Physics Parameter Limits....
. 2 50 2.10.3 DELETED l
2.10.4 Power Distribution Limits................................. 2-56 l
2.11 DE'.ETED i
Amendment No. '1,!5,27.32.38,52.5 t,
.e, c,o_n. o.n oc,i e_,i.n_,i.t_,.im,,182
v 2.0 LIMITING CONDITIONS FOR OPERATION l
-2.1 P-tor Coalant Syst-m (Continued)3 2.1.7 Pressurizer Operability
~Anolicability Applies to the status of the pressurizer and pressurizer heaters.
Obiective To specify minimum requirements pertaining to the pressurizer water volume and availability of heaters for accident conditions.
Specifications (1)
The pressurizer shall be operable with at least 150 KW of pressurizer heaters, and pressurizer inventory shall be maintained in a range of level 40.5% to 69.2%.
With th: pressurizer inoperable due to an inoperable emergency power a.
supply to the pressurizer heaters either restore the inoperable emergency, power supply within 72' hours or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. With the pressurizer otherwise inoperable, be in
- HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This is applicable for Modes'l and 2.
b.
' With the pressurizer level outside the above range, either restore the level within the specified limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This is applicable for Modes 1 and 2.
-l BAEi1 The requirement that 150 KW of pressurizer heaters and their associated controls be capable of being supplied electrical power from an emergency bus provides assurance that these heaters can be energized during a loss of offsite power condition to mcintain natural circulation at HOT SHUTDOWN. Either diesel generator is equipped with 225 KW of heater capacity. Either diesel will fulfill the minimum requirements of. this specification. The level should be maintained above the lower limit to prevent heater cutoff and 'the upper limit should not be exceeded to prevent going solid or reducing the effectiveness of the pressurizer sprays by immersion during an RCS swell transient.
216a Amendment No. 5466,182
o 3.0-SURVEILLANCE REOUIREMENTS 3.1
.. Instrumentation and Control Aeolicability Applies to the reactor protective system and other critice instrumentation and controls.
Obiective -
- To specify the minimum frequency and type of surveillance to be applied to critical plant instrumentation and controls.
Soecifications Calibration, testing and checking of instrument channels, reactor protective system and engineered safeguards system logic channels and miscellaneous instrument systems and controls shall be performed as specified in Tables 3-1 to 3-3a.
Balil Failures such as blown instrument fuses, defective indicators, and faulted amplifiers' which result in " upscale" or "downscale" indication can be easily recognized by simple observation of the functioning of an instrument or system. Furthermore, such failures are, in many cases revealed by alann or annunciator action and a check supplements this type of built in surveillance, if the channels are normally off scale during times when Surveillance is required, the CHANNEL CHECK will only verify that they are off scale in the same direction. Off scale low current loop channels are verified to be reading at the bottom of the range and not failed downscale.
Based on the District's experience in operation of conventional power plants and on reported nuclear plant experience, a checking frequency of once-per-shift is deemed adequate for reactor and steam system instrumentation. Calibrations are performed to ensure the presentation and acquisition of accurate information.
The power range safety channels are calibrated (heat balance adjustment only) daily l
against a calorimetric balance standard to account for errors induced by changing rod patterns and core physics parameters.
Other channels, subject only to the " drift" errors, can be expected to rem:in within
-acceptable tolerances.if recalibration is performed on a refueling frequency.
3-1 Amendment No. 9d22,125,157,182-l 4
3.0 SURVEILLANCE REOUIREMENTS 3.1 --
? Instrumentation and Control (Continued).
Sulgtantial calibration sh within a channel (essentially.a channel failure) mil be:
revealed during routine checking'and testing procedures.
l The minimum calibration frequencies of once-per-day (heat balance adjustment only) for l.-
the power range safety channels, and once_ each refueling shutdown for the process system channels, are considered adequate.;
The minimum testing frequency for those instrament channels connected to the Reactor-Protective System and Engineered Safety Features is based en ABB/CE probabilistic risk analyses and the accumulation of specific cperating history. The quarterly _ frequency for the channel functional tests for these systems is based on the analyses presented in the '
^
NRC approved topical report CEN-327-A, "RPS/ESFAS Extended Test Interval Evaluation," as supplemented and OPPD's Engineering Analysis EA-FC-93-064, "RPS/ESF Functional Test Drift Analysis."
The low temperature setpoint power operated relief valve (PORV) CHANNEL FUNCTIONAL TEST verifies operability of the actuation circuitry using the installed test switches. PORV actuation could depressurize the reactor coolant system and is not required.
3-2 Amendment No. M1,182 I
e TAMLE 3-1 MINIMUM FREOUENCIES FOR CHECKS. CALIBRATIONS AND TESTING OF REALM PROTECTIVE SYSI'EM Channel Description Surveillance Function Frequency Surveillance M4 hod i
I.
- Power Range Safety a.
Check:
S a.
Chsunels
- 1) Neutron Flux il CHANNELCHECK l
- 2) 'Ummal Power
- 2) CHANNEL CHECK l
b.
Adjustment D*
b.
Channel adjustment to agree with beat balance l
calculation.
c.
Test Q'"
c.
CHANNEL FUNCTIONAL TEST l
' 2.
' Wide-Range Logarithmic a.
Check S
1 CHANNEL CHECK l
Neutron Monitors b.
Test
- P b.
CHANNEL FUNCTIONAL TEST l
3.
Reactor Coolant Flow a.
Check S
' a.
CHANNEL CHECK l
b.
Test Q'u b.
CHANNEL FUNCflONAL TEST l
c.
Calibrate R
c.
CHANNEL CALIBRATION
-l 3-3 Ar.wi.J mut No. 60,43,182
a TABLE 3-1 (Continued)
MINIMUM FREOUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF REACTOR PROTECTIVE SYSTEM Channel Description Surveillance Function Frequency Surveillance Method 4.
'Ihermal Margin / Low a.
Check:
5 a.
Pressure 1)
Pressure 1)
CHANNEL CHECK Setpoint 2)
Pressure 2)
CHANNEL CIIECK l
l Input b.
Test Qh b.
CIIANNEL FUNCTIONAL TEST l
l c.
Calibrate:
R c.
1)
Temperature 1)
CHANNEL CALIBRATION Input 2)
Pressure 2)
CHANNEL CALIBRATION '
Input 5.
liigh-Pressurizer a.
Chek S
a.
CIIANNEL CHECK l
I Pressure b.
Test Q
b.
CIIANNEL FUNCTIONAL TEST l
c.
Calibrate R
c.
CHANNEL CALIBRATION
[
3-4 A ; ".-..t No. M3.182 '
- 3. -
TABLE 3-1 (Continued) -
o MINIMUM PREOUENCIF.S FOR CHECKS. CALIBRATIONS AND TESTING OF REACTOR PROTECTIVE SYSTEM Channel Desmataos Surveillance Function Frequency WW Method 6.
Steam Generator inel a.
Check S
a.
CHANNEL CHECK b.
Test Q"
b.
'. CHANNEL FUNCTIONAL TEST l
c.
Calibrate R
c.
CHANNEL CALIBRATION '
l 7.
. Check S
a.
. CHANNEL CHECK.
.l Pressure-b.
Test Q
- b. '
CHANNEL FUNCTIONAL TEST l
c.
Calibrate R
c.
CHANNEL CALIBRATION :
l.
o.
Containment Pressure a.
Test Q
a.
CHANNEL FUNCT10FAL TEST l
b.
Calibrate R-b.
CHANNEL CALIBRATION
~[
9.
. Enss of Lead a.
Test P
a.
CHANNEL FUNCTIONAL TEST l
10.
Manual Trips a.
Test P
a.
CHANNEL FUNCTIONAL TEST
'l 11.
Check S
a.
CHANNEL CHECK l
Differential Pressure b.
Test Q
b.
CHANNEL FUNCTIONAL TEST l
c.
Calibrate R
c.
CilANNEL CALIBRATION l
3-5 Amendment No. 37443,182
o-w TABLE 3-1 (Continued)
MINIMUM FREOUENCIES FOR CHECKS, CAllBRATIONS AND TES11NG OF REACTOR PROFITCTIVE SYSTEM Channel Description Surveillance Function Frequency Surveillance Method 12.
Reactor Protection a.
Test Q"
a.
CHANNEL FUNCllONALTEST l
System D>gic Units l
' 13.
Asial Power Distribution a.
Check:
S
- a. -
I) ' Axial Shape
- 1) CH ANNEL CHECK'
.I Index Indication
- 2) Upper Trip Setpoint
- 2) CHANNEL CHECK l
Indication
- 3) ' lower Trip Setpoint
. 3) CHANNEL CHECK l
Indication b.
Test Q"
b.
CHANNEL FUNCTIONAL TEST l
c.
Calibrate R
- c. -
CHANNEL CALIBRATION l
Notes: (1) 'Ihe quarterly tests will be done on only one of four channels at a time to prevent reactor trip.
(2) Calibrate using built-in sinm'ated signals.
(3) Not required unless the reactor is in the power operating condition and is therefore not required during plant startup and shutdown penods l
3-6 Amendment No. '",!22.H 182 '
o TABLE 3-2 MINIMUM FREOUENCIES FOR CHECKS, CALIBRATIONS AND 175I1NG OF
~
ENGINEERED SAFETY FEATURES. INSTRUMENTATION AND CONTROLS Chamael Description Survestlance Functice Frequency Sur, umare lv-thod 1.
Pressurizer Pressure low a.
Check S
a.
CHANNEL CHECK -
l-b.
Test QP*
b.
CHANNEL FUNCTIONAL TEST l
c.
Calibrate R
c.
CHANNEL CAUBRATION -
l 2.
Pressurizer Law a.
Calibrate R
a.
CHANNEL CALIBRATION g-Pressure Blocking Circuit 3.
Safety Injection a.
Test Q
a.
CHANNEL FUNCTIONAL TEST l
Actuation logic b.
Test RM b.
CHANNEL FUNCTIONAL TEST l
3-7 A.--
". _ a No. 54,ua,182
~
1 0-
~ -
TABLE 3-2 (Continued) '
MINIMUM FREOUENCIES FOR CHECKS. CALIBRATIONS AND TES11NG CF ENGINEERED SAFETY FEA1FRES. INSTRUMENTATIO!. AND CONTROLS Channel Description Surveillance Function Frequency SurveMance Meeed 4.
Containment Pressure a.
Test Q
a.
CHANNEL FUNCTIONAL TFST High Signal b.
Calibrate R
b.
CHANNE" CALIBRATION
[
5.
Test Q
a.
CHANNEL FUNCTIONAL TEST (Sirrmlation Actuation logic of PPLS and CPHS 2/4 logic) b.
Test RM b.
CHANNEL 1UNCT10NALTEST l
6.
Contamment Radiation a.
Check D
a.
CHANNEL CHECK -
High Signal
- 3-8 Arnendment No.'!52."? '??.182
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e.
TABLE 3 2 (Continued)
MINIMUM FREOUENCIES FOR CHECKS, CAllBRATIONS AND"IESTING OF ENGINEERED SAFETY FEATURES. INSTRUMENTATION AND CONTROLS Channel Description Surveiilsnee Function Frequency Surveillance Method 6.
(continued) b.
Test Q
b.
CHANNEL FUNCTIONAL TEST c.
Calibrate R
c.
Secondary and Electronic Calibration performed at refueling frequency. Primary calibration performed with exposure to radioactive sources only when required by the secondary and electronic calibration.
7.
Manual Safety injection a.
Test R
a.
CilANNEL FUNCTIONAL TEST Actuation
-l 8.
Manual Containment a.
Check R
a.
Observe isolation valves closure.
Isolanon Actuation b.
Test R
b.
CilANNEL FUNCTIONAI, TEST l
9.
Manual Containment a.
Test R
a.
CHANNEL FUNCTIONAL TE70
]
Spray Actuation I
10.
Automatic Load a.
Test Q
a.
CIIANNEL FUNCTIONAL TEST ll Sequencers 11.
Diesel Testing See Technical Specification 3.7 3-9 Amendment No. 5?, ' ! ',' 53. ' 63,!??,182
TABLE 3-2 (Contirmed)
MINIMUM FREOUENCIES FOR CHECKS. CALIBRATIONS AND TFSTING OF ENGINEERED SAFETY FEATURFA INSTRUMENTATION AND COSTROIS -
Channel Description Surveillance Function Frequency Surveillance Method 12.
Diesel Fuel Transfer a.
Test M
a.
Pump run to refill day tanic.
Pump 13.
SIRW Tank low a.
Check S.
a.
CHANNEL CHECK I
level Signal b.
Test Q
b.
CIIANNEL FUNCTIONAL TEST l
c.
Calibrate R
c.
CIIANNEL CALIBRATION l
14.
Safety injection a.
Check S'*
a.
Verify that level and pressure Tank Irvel and Pressure are within limits.
.l 1
3-10 Auu4.mut No. !!',!9,!?!.182
TABLE 3-2 (Continued)
MINIMUM FREOtfENCIES FOR CHECKS. CALIBRATIONS AND TESTING OF ENGINEERED sal'ETY FEATITRES. INSTRINENTATION AND CONTROLS Channel Descrisnion Surveillance Function Frequency Surveillance Method 14.
(continued) b.
Calibrate R
b.
CifANNEL CALIBRATION l
15.
Boric Acid Tank level a.
Check W
a.
Verify that level is within limits.
Verify that tmguaime is within limits.
16.
Boric Acid Tank a.
Check W
a.
Temperature 17.
Steam Generator Low a.
Check S
a.
CilANNEL CIIECK l
Pressure Signal (SGIS) b.
Test Q*
b.
CIIANNEL FUNCTIONAL TEST l
c.
Calibrate R
c.
CIIANNEL CALIBRATION l
3-11 A-L - ; No. ' ? ',"? ' ?2,182 y
TABLE 3-2 (Continued)
MINIMITM FREOliENCIES FOR CIIECKS. CALIBRATIONS AND TFSTING OF ENGINEERED SAFETY FEATliRES. INSTRiiMENTATION AM CONTROLS
(
Channel Descri Wien Surveillance Function Frequency Surveillance Method Verify that tmgu.iure is within limits.
18.
SIRW Tank Temperature a.
Check D"*
a.
b.
Test R
b.
Measure temperature of SIRW tank with standard laboratory instru-ments.
19.
Manual Recirculation a.
Test R
a.
CIIANNEL FUNCTIONAL TEST l
Actuation 20.
Recirculation Actuation a.
Test Q
a.
CIIANNEL FUNCTIONAL TEST l
Logic b.
Test RS b
CilANNEL FUNCHONAL TEST l
Verify voltage readings are above l
a.
Check S
a.
21.
4.16 KV Emergency Bus low Voltage (Loss of alarm initiation on degraded voltage Voltage and Degraded level - supervisory lights *on".
g' Voltage) Actuation logic b.
Te=t Q
b.
CIIANNEL FUNCTIONAL (EST I
c.
Calibrate R
c.
CIIANNEL CELIBRATION l
22.
Manual Emergency Off-site a.
Test R
a.
CIIANNEL FUNCTIONAL TEST l
Power IAw Trip Actuation 3-12 Animiumnt No. A' !53 '" '72. 182
TABLE 3-1 (Continued)
MINIMtN FREOUENCIES FOR CHECKS, CAllBRATIONS AND TESTING OF ENGINEERED SAFFR FEATURES. INSTRtNENTATION AND CONTROLS Channel Description Surveillance Function Frequener Surveillance Method 23.
a.
Check:
S a.
- 1) Steam Generator 1)
CHANNEL CHECK Water level Low (Wide Range)
- 2) Steam Generater 2)
CHANNEL CHECK Pressure lo w b.
Test:
QRS b.
- 1) Actuation logic 1)
CHANNEL FUNCTIONAL TEST c.
Calibrate:
R c.
- 1) Steam Generator 1)
CHANNEL CALIBRATION Water level low (Wide Range)
- 2) Steam Generator 2)
CHANNEL CALIBRATION Pressure lo w
- 3) Steam Generator 3)
CHANNEL CAllBRATION Differential Pressure High 24 Manual Auxiliary Feedwater a.
Test R
a.
CHANNEL FUNCTIONAL TEST Ac'uation NOTES: (1) Not required unless pressurizer pressure is above 1700 psia.
(2) CRIIS monitors are the containment atmosphere gaseous radiation monitor and the Autiliary Building Exhaust Stack gaseous radiation monitor.
(3) Not required unless steam generator pressure is above 600 psia.
(4) QP - Quarterly during designated modes and prior to taking the reactor critical if not completed within the previous 92 days (not applicable to a fast trip recovery).
(5) Not required to be done on a SIT wi'.h inoperable level and/or pressure instrumentation.'
(6) Not required when outside ambient air temperature is greater than 50*F and less than 105'F.
(7) Tests backup channels such as derived circuits and equipment that cannot be tested when the plant is at power.
l 3-12a Anwndnwnt No. 4 ?.9 " !22.'n, !'2J82 -
TABLE 3-3 (Continued)
MINIMUM FREOUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS Surveillvice Channel Description Function Frequenev SurveiBaece Mctbod 4.
DELETED 5.
Primary to Secondary a.
Check D
' a.
CHANNEL CHECK Leak-Rate Detection Radiation Monitors b.
Test Q
b.
CHANNEL FUNCTIONAL TEST (RM-054A/B, RM-057) c.
Calibrate R
c.
Secondary and Electrome calibration performed at refueling fiu,wxy. Primary Calibration performed with exposure to radioactive sources only when required by the secondary and electronic calibration.
6.
. Pressurizer Ixvel a.
Check S
a.
Verify that level is within limits.
l-i b.
Check M
b.
CHANNEL CHECK l
c.
Calibrate R
c.
CHANNEL CALIBRATION l
7..
CEA Drive System a.
Test R
a.
Verity proper operation of all CEDM. system -
Interlocks interlocks, using simulated signals where necessary.
b.
Te:t P
b.
If haven't tren checked for three months and plant is shutdown.
I 3-14 Am ndment No. 153474.182
TABLE 3-3 (Contit ued)
MINIMUM FitEOUENCIES FOR CHECKS, CALIBRA~l10NS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS -
Surveillance Channel Description -
Function Fi;,.auv Surveillance Method 8.
Dropped CEA Indication a.
Test R'
a.
Insert a negative rate of change power signal to all four Power Range Safety Channels to test alarm.
b.
Test R
b.
Insert CEA's below lower electrical limit to test dropped CEA alarnt 9.
Calorimetric Instrumen-a.
Calibrate R
a CHANNEL CALIBRATION l
tation
.10.
Control Room Ventilation a.
Test R
a.
Check damper operation for DBA mode.
b.
Test R
b.
Check control room for positive pressure.
.. i 11.
Containment Humidity a.
Test R
a.
CilANNEL FUNCTIONAL TEST l
Detector 12.
Interlocks-Isolation Valves a.
Test R
a.
CHANNEL' FUNCTIONAL TEST l
[
on Shutdown Cooling Line 13.
Control Room'Ihermome-a.
Test R
a.
Compare reading with calibrated ter thermometer. If not within + 2*F.
replace.
1 3-15 Amendment No. ??.!23.'5'.182 l
1
n TABLE 3-3 (Continxd)
MINIMUM FREOUENCIFS FOR CHECKS. CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRt' MENTATION AND CONTROLS Surveillance Channel Description Function Frequency Surveillance Medied
=l 14 Nuclear Detector Well a.
Check S
a.
CHANNEL CHECK Cooling Annulus Exit Air Temperature Dettttors b.
Calibrate R
b.
CHANNEL CALIBRATION
.l 15.
P.cac'or Coolant System a.
Check M
a.
Calculation of reactor coolant flow rate.
Flow 16.
Pressurizer Pressure a.
Check S
a.
CHANNEL CHECK l
17.
Reactor Coolant Inlet a.
Check S
a.
CHANNEL CHECK l
Temperature 18.
Low-Temperature Set.
a.
Test PM a.
CHANNEL FUNCTIONALTEST (excluding
[
point Power-Operated actuation)
I Relief Valves b.
Calibrate R
b.
CilANNEL CALIBRATION l
3-16 Amendment ?!. ? ??.?a ",182
TA:LE 3-3 (Continued)
MINIMUM FREOUENCIES FOR CHECKS. CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS Suneillance Channel Description Function Frecuenev Surveillance Method 19.
Auxiliary Feedwater Flow a.
Check M
CHANNEL CHECK l
b.
Calibrate R
CHANNEL CALIBRATION l
20.
Subcooled Margm Monit a.
Check M
CIIANNEL CllECK
[
b.
Calibrate R
CHANNEL CALIBRATION l
21.
PORV Operation and Acoustic a.
Test M
CllANNEL FUNCTIONAL TEST l
Iosition Indication l
b.
Calibrate R
CIIANNEL CALIBRATION 22.
PORV Block Valve Operation a.
Check Q
Cycle valve. Valve is exempt from I
and Position Indication testing when it has been closed to comply with LCO Actim. 2,tatement 2.1.6(5)a.
b.
Calibrate R
Check valve stroke against limit l
switch position.
l 23.
Safety Valve Acoustic a.
Test M
CIIANNEL FUNCTIONAL TEST l
Position Indication b.
Calibration R
CilANNEL CALIBRATION l
24.
PORV/ Safety Valve Tail a.
Check M
CilANNEL CHECK l
Pipe Temperature b.
Calibrate R
CIIANNEL CALIBRATION
.l 3-16a Anu lum.: No. 3a.9 "a !182
e TACLE 3-3 (Continued)
MINIMUM FREOCEMC!ES FOR CHECKS. CALIBRATIONS AND TFATING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS Sur eillance g
Channel Descrisdion Function Frequency Surveillance Method 25.
Containment Purge Isolation
- a. Check M
a.
Verify valve position using control l
room indication.
Valves (PCV-742A, B, C. & D)
- 26. -
Containment Hydrogen
- a. Check M
a.
CHANNEL CHECK l
Monitors (VA-81 A&B)
- b. Test Q
b.
Calibrate spanhero using sampic gas and check flow rates.
- c. Calibrate R
c.
CllANNEL CALIBRATION l
27.
Containment Water Ixvel
- a. Check M
a.
CHANNEL CHECK l
Narrow Range (LT-599 & LT-600j
- b. Calibrate R
b.
CHANNEL CALIBRATION l
Wide Range (LT-387 &
- a. Check M
a.
CilANNEL CHECK-l LT-388)
- b. Calibrate R
b.
CilANNEL CALIBRATION I
28.
Containment Wide Range
- a. Check M
a.
CHANNEL CHECK.
I Pressure Indication
' b. Calibrate R
b.
CHANNEL CAllBRATION I
29.
Toxic Gas Detectors:
Comprison of readings from redundant YlT-6288A&B (Cl)
- a. Lheck S
a.
channels.'
YIT-6286A&B (IICI, IIAO,)
- b. Calibrate M
b.
Calibrate span /zero using calibration card.
- c. Calibrate R
c.
Calibrate spanhero adjustment with calibration sud, and verify using gas st ndards.
3-16b Anwedesi No. M ^* *?.*,"",,182
o TABLE 3-3 (Continued)
MINIMUM FREOUENCIES FOR CHECKS. CALIBRATIONS AND TESTLNG OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS Surveinance '
Chm =mel Description Function Frequency Surveiunnee Method YIf 4287A&B (N H, Nil,)
- a. Check '
S a.
Comparison of readings from redundant channels.-
- b. Calibrate Q-b.
Gas calibration.
30.
Core Exit Thermo-
- a. Check M
a.'
CHANNEL CHECK
^ !
couple
- b. C-Jibrate R
b.
CHANNEL CAUBRATION
~l-31.
Heated Junction Thermocouple (YE-Il6A and YE.116B)
- a. Check
-M a..
CHANNEL CHECK l
- b. Calibrate R
b.
CHANNEL CAUBRATION l
t PM - Prior to scheduled cold leg cooldown below 300"F; monthly whenever temrerature remains below 3007 and reactor vessel head is installed.
3-16c Ani J..--t No. " '",' !",! r 182
't
~.
O TABLE 3-3A
- MINIMIIM FREOUENCY FOR CHECKS. CAllBRA'h ONS AND RNCTIONAL TESTING' OF AI. TERNATE SHtTI1MMVN PANELS (A1-185 AND AI-212)
AND EMERGENCY AtrXILIARY FEEDWATER PANEL (Al-179) INSTRUMENTATION AND CONTROL CIRCUITS Surveinance Ch===*I Descristies Function Frequency Surve4N==se Method 1.
WIDE RANGE
- a. CHECK M
- a. :
- CHANNEL CHECK -
l-LOGARITHMIC POWER AND
- SOURCE RANGE MONITORS
- b. ' CALIBRATE R
b.
CHANNEL CAUBRATION
-l
- (Al-212) -
'2.
REACTOR COOLANT COLD
- a. CHECK M
a.
CHANNEL CHECK
-[ ;.
LEG TEMPERATURE (Al-185)
- b. CALIBRATE R.
b.
CHANNEL CAUBRATION
[
3.
REACTOR COOLANT HOT
- a. CHECK M
a.-
CHANNEL CHECK
[
LEG TEMPERATURE (Al-185)
- b. CAUBRATE R
b.
CHANNEL CAUBRATION l'
4
' PRESSURIZER LEVEL
- a. CHECK M
s.
CHANNEL CHECK l
- ( Al-185)
' b. CALIBRATE R-b.
CHANNEL CAUBRATION
_l l
S.
VOLUME CONTROL
- a. CHECK M
a.
. CHANNEL CHECK TANK LEVEL (Al-185)
- b. CALIBRATE R
b.
CHANNEL CALIBRATION.
l 6.
ASP CONTROL
- a. TEST R
a.
CHANNEL FUNCTIONALTEST l.
CIRCUITS (AI.185)
Amendment No. 435,182 3-16d
i
.o-TABLE 3-3A (Contimm!) -
MINIMUM FREOUENCY FOR CHECKS. CAtlBRATIONS AND RNAL TESTING OF ALTERNATE SHirTDOWN PANELS (Al-185 AND Al-212).
AND EMERGENCY AUXILIARY FEEDWATER PANEL (Al-179) INSTRUMENTATION AND CONTROL CIRCt.TTS Surveillance Channel Description Function Frequency Surveillance MMbed 7.
STAM GENERATOR
- a. CHECK M
a.
. CHANNEL CHECK l
LEVEL, WIDE RANGE (Al-179)
- b. CALIBRATE R
b.
CHANNEL CAUBRA110N l-8.
- a. CHECK M
a.
CHANNEL CHECK LEVEL, NARROW RANGE (AI 179)
- b. CAUBRATE R
b.
CHANNEL CAUBRA110N 9.
SEAM GENERATOR
- a. CIIECK M
a.
CHANNEL CHECK l
PRESSURE (Al-179)
- b. CALIBRATE R
b.
CHANNEL CALIBRATION l
10.
PRESSURIZER PRESSURE
- a. CHECK M
a.
CHANNEL CHECK l'
(Al-179)
- b. CAUBRATE R
b.
CHANNEL CAUBRATION l
11.
EAFW CONTROL
- a. TEST R
a.
CHANNEL FUNCTIONAL TEST
- - l CIRCUITS (Al-179) t i
3-16e Amendment No. 425,182 wi
. m o~ ;
TABLE 3-5 (Continued)
- USAR Seetion Test Freeuancy Referumee 10c.
(continued) -
4.
Automatic and/or manual initi-R' ation of the system shall be demonstrated.
11.
Containment Cool-1.
Demonstrate damper action.
- 1 year,'2 years. 5 years, and'every 5 '
9.10' ing and Iodine years thereafter.
Removal Fusible ~
Linked Dampers 2.
Te4 a spare fusible link.
' 12.:
. Diesel Generator Calibrate R
-8.4.3 Under-Voltage Relays '
13.
- Motor Operated Verify the contactor pickup value at R
- Safety injection
.585% of 460 V.
- loop Valve Motor '
Starters (HCV-311.
314,317,320,327, 329,331,333,312.
~ 315, 318, 321) 14.
Pressurizer Heaters Verify control circuits operation R
for post. accident heater use.
15.
Spent Fuel Pool -
Test neutron poison samples for 1, 2. 4. 7. and 10 years after Racks dimensional change, weight, neutron installation, and every 5 years
.g-attenuation change and specific thereafter.
gravity change.
16.
Verify all manual isolation During each refueling outage just -
Gas Vent System valves in each vent path are prior to plant start-up.
in the open position.
2.
Cycle cach automatic valve in R
the vent path through at least one complete cycle of full travel from the control room.
Verification of valve cycling may be determined by observa-
- tien of position indicating lights.
3.
Verify flow through the reactor R
coolant vent system vent paths.
3-20d Arnendment No. ,M 9.75.'".M.'55."".182
-