ML17326A520
| ML17326A520 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/22/1980 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17326A519 | List: |
| References | |
| NUDOCS 8002270327 | |
| Download: ML17326A520 (30) | |
Text
ATTACHMENT 'B'O AEP:NRC:00313 REVISED TECHNICAL SPECIFICATION PAGES DONALD C. COOK NUCLEAR PLANT UNIT NOS. 1 AND 2
l 7
CHANGE NO.
AEP: NRC:00313
PLANT SYSTEMS AUXILIARY FEEDHATER SYSTEM LIMITING CONDITION FOR OPERATIOiN 3.7.1.2 At least three steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
- a. Two* feedwater pumps, each capable of being powered from separate emergency busses, and
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
With one auxiliary feedwater pump inoperable, restore at least three auxiliary feedwater pumps (two capable of being powered frorii separate emergency busses and one capable of being powered by an OPERABLE steam supply system) to OPERABLE status withlni 72 hours or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREIMEi ITS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:
- a. At least once per 31 days by:
- 1. Verifying that the steam turbine driven pump develops a discharge pressure of > 1285 psig at a flow of > 700 gpm when the secondary steam supply pressure is greater than 310 psig.
- 2. Verifying that each valve (manual, power operated or automatic) in the f1 ow path i nc1 udi ng va1 ves whi ch are locked, sealed or otherwise secured in position, is in its c'otrect position.
- b. At least once per 18 months by:
- l. Verifying that its each automatic valve correct. posi.tion in the flow path Safety Injection actuates to on a test signal.
8 are iwi.th'0; G COOK .- UN!T"l.-
D. C. COOK - UNIT 2 3/4 7-5
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued
- 3. Verifying that each pump operates for at least 15 minutes.
- 4. Cycling each testable power operated or automatic valve in the flow path through at least one complete cycle of full travel.
- 5. Verifying that each valve (manual, power operated or automatic) in the flow path, including valves which are locked, sealed or otherwise secured in position, is in its correct position.
- b. At least once per 18 months during shutdown by:
Cycling each power operated valve in the flow path that is not testable during plant operation, through at least once complete cycTe of full travel.
- 2. Ver ifying that each motor driven pump starts automatically upon receipt of each of the following signals:
a) Loss of main feedwater pumps.
b) Safety Injection.
c) Steam Generator Mater Level--Low-Low from one steam generator, 2 out of 3 channels.
- 3. Verifying that the steam turbine driven pump starts auto-matically upon receipt of each of the following signals:
a) Steam Cenerator Mater Level Low-Low from two steam generators, 2 out of 3 channels.
b) Reactor Coolant Pump Bus Undervoltage.
D.C.COOK-UNIT 1 3/4 7-6
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r ~ ~ I 60 100 200 250 300 350 400 Indicated Temperature, deg F FjgU( e 3,4 - 3 DONALD C. COOK UNIT NO. 1 REACTOR COOLANT CQOLDOMN LIMITATIONS APPLICABLE
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vo>>. vraznos up To 12 EFFECTzvE FULL powER YEARS
I CHANGE NO. AEP'NRC:00313 II' ], ~
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) ~ i ( RONIHISTRATI V"= CONTROLS 6.9 RcpOR ING R QVIRc.~~~TS (Continued) Seismic event analysis, Specification 4.3.3.3.2. Sealed Sourc leakage on exc ss of limits, Specification 4.7.7.1.3.
- g. Fire 0etection Instrumentation, Specification 3.3.3.7.
- h. Fire Suppression Systems, Specifica.ions 3.7.9.1, 3.7.9.2, 3.7.9.3 and 3 7.9.4.
6.10 RECORD RK =NTION 6.10.1 The following records shall be retained for at least five years:
- a. Records and logs of unit operation covering time interval at each power ievel.
- b. Records and legs of principal maintenance ac.ivities, inspec-tions, repair and replacement o- principal items'f equipment
~ e related to nuclear safety.
c All REPGPTA3L OCCURR='(CKS submi t d to the Ccmmission. Records o st r ieillanc activi.ies, inspections and calibra-tions required by these Technical Specifications. Records of reactor tests and experiments.
~
- f. Records of changes mad to the proc dures required by Soecific; tion 6.8.'1.
g, Records of radioactive shipments.
- h. Records of sealed sourc leak tests and resul.s.
Records o, nnual physical inventory of all seal d sourc material of record. 1 6.10.2 Tne following r cords shall be retained, or the duration of the p(-,inc",descry Facili:y Operacing Lic nse:
- a. Records and drawing chances re=lecting Jnit design radifi-
..,::....cati cns" mad . to.,sys:~ms. and,.equi ibad., in .:he:-F inal Sa ety"Analysis Repcr .
b'. "Records of r'ew and ii radi:a:ed'uel inventory; fuel-transfers and assembly burnup h scories.
- 0. C. CCCi< - U(lIT 1 6-19 Amendment io gg 23
CHANGE NO. AEP:NRC:00313
j ~ ~ AOMINISTRATIVE CONTROLS J occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
- a. Reactor protection system or engineered safety feature instru-ment settings which are found to be less conservative than those established by the technical specifications but which do not. prevent the fulfillment of the functional requirements of affected systems.
- b. Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown re-quired by a limiting condition for operation.
c~ Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems. d., Abnormal degradation of systems other than those specified in 6.9.1.8 c above designed to contain radioactive material resulting from the fission process. SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Oirec.or of the Office of Insp'ection and Enforcement Regional Office within the time period specified for each report. These reports shall be submitted covering the activities indentified below pursuant to the requirements of the applicable reference specification: a ~ ECCS Actuation, Specifications 3.5.2 and 3.5.3.
- b. Inoperable Seismic t<onitoring Instrumentation, Unit No. 1 Specification 3.3.3.3.
- c. Inoperable tteteorological tlonitoring Instrumentation, Un'it No. 1 Speci fication 3.3.3.4.
- d. Fire Detection Instrumentation, Specification 3.3.3.8.
- e. Fire Suppr ssion Systems, Specifications, 3.7.9.1, 3.7.9.2, 3.7.9.3 and 3.7.9.4.
- f. Seismic event analysis, Specification 4.3.3.3.2.
D. C.'OOK'- 'UNIT 2 6-18
DONALD C. COOK NUCLEAR PLANT UNIT NO. 1 CHANGE NOS. 5 AND 6 AEP: NRC: 00313
TABLE 2.2-1 (Continued REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS a i
'UNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 8 .13. Steam Generator Water >17/ of narrow range instrument > ypfpf narrow range instrument
Level Low-Low span-each steam generator span-each steam generator
~
I 6 6
.
14.. -Steam/Feedwater Flow < 0.71 x 10 lb/hr of steam flow < 0.73 x 10 lbs/hr of steam flow
~
., -: Mismatch and Low Steam at RATED THERMAL POWER coincident at RATED THERMAL POWER coincident Generator Water Level with steam generator water level with steam generator water level
> 25% of narrow range instru- > 24K of narrow range instru-ment span--each steam generator ment span--each steam generator
'-.l5; Undervoltage-Reactor > 2750 volts-each bus > 2725 volts-each bus
.Coolant Pumps
-'.
- 16. llnderfrequency-Reactor > 57.5 Hz - each bus > 57.4. Hz - each bus Coolant Pumps a .
;17. Turbine Trip
'.A. Low Trip System > 800 psig > 750 psig
- - '. Pressure Turbine Stop Valve Closure
> lX open > lX open
- .18..Safety Injection Input Not Applicable Not Applicable from ESF 19.:Reactor Coolant Pump Not Applicable Not Applicable Breaker Position Trip
~
TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
- 6. MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS
- a. Steam Generator Water 2/Stm. Gen.
Level -- Low-Low 3/Stm. Gen. any Stm. Gen; 2/Stm. Gen. 1,2,3 14*
- b. 4 kv Bus 2/Bus 2/Bus 2/Bus 1,2,3 14*
Loss of Voltage
- 7. TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS
- a. Steam Generator Water 2/Stm; Gen. 2/Stm. Gen. 1, 2, 3 Level -- Low-Low 3/Stm. Gen. any 2 Stm. Gen.
- 8. LOSS OF POWER
- a. 4 kv Bus 3/Bus 2/Bus 2/Bus 1,2,3 14*
Loss of Voltage b- 4 kv Bus 3/Bus 2/Bus 2/Bus 1,2,3 14* Degraded Voltage
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a TABLE 3.3-4 Continued t ENGINEERED SAFETY FEATURE ACTUATION SYSTEt1 INSTRUMENTATION TRIP SETPOINTS J 'FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
.6."- t)OTOR DRIVEN AUXILIARY FEEDMATER PUMPS
- a. Steam Generator Mater > 174 of narrow range >17%%d of narrow range Level -- Low-Low instrument span each instrument span each steam generator steam generator
- b. 4 kv Bus 3196 volts with a 3196 + 18 volts with a Loss of Voltage 2 second delay 2 + .2 second delay
.7. TURBINE DRIVEN AUXILIAP". FEEDMATER PUMPS.
- a. Steam Generator Mater ~
> 17% of narrow range >17% nf narrow range Level -- Low-Low instrument span each instrument span each t steam generator steam generator I
"8.'. "LOSS OF Pt'MER I 3l96 volts with a 3196 + 18 volts with a 4 kv Bus 2 second delay 2 + .2 second delay Loss of Voltage l b 4 kv Bus 3596 volts with a 2.0min. volts with, Degraded Voltage delay 'ime 3596 + 18 a 2.0 minute + 6 aectnd h time delay
- I I I
TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION U VEILL NCE E UIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST RE VIREO
- 4. STEAM LINE ISOLATION
- a. Manual N.A. N.A. M(1) 1,2,3
- b. Automatic Actuation Logic N.A. N.A. M(2) 1,2,3
- c. Containment Pressure--
High-High M(3) 1,2,3
- d. Steam Flow in Two Steam 1, 2, 3 Lines--High Coincident with T -- Low or Steam Line
'flksure--Low
- 5. TURBINE TRIP AND FEEDWATER ISOLATION
- a. Steam Generator Water Level--High-High R 1,2,3
- 6. MOTOR DRIVEN AUXILIARY FEEDLIATER PUMPS
- a. Steam Generator Water 1, 2, 3 Level--Low-Low
- b. 4 kv Bus 1 2 3 Loss of Voltage
TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL MODES .IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE CHECK CALIBRATION TEST RE UIRED
; FUNCTIONAL UNIT
- , 7..: TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS Steam Generator Water Level--Low-Low R 1,2,3 r
- 8.'OSS OF POWER
'. 4 kv Bus Loss of Voltage 1,2,3=-
4 kv Bus 1,2,3 Degraded Voltage
DONALD C. COOK NUCLEAR PLANT UNIT NO. 2 CHANGE NOS. 5 AND 6 AEP:NRC:00313
C) TABLE 2.2-1 Continued) REACTOR TR!P SYSTEM INSTRUHENTATION TRIP SETPO!NTS
'FUNCTIONAI UNIT TPIP SETPOINT ALLOWABLE VALUES
~ '13:; Steam Level Generator Water
- Low-Low
= 2~ of span
~ 01
-
narrow range instrument each steam generator .
>>Af span -
narrow range instrument each steam generator I 6 6 14~ Steam/Feedwater Flow < 1.47 x 10 lb/hr of steam flow < 1.56 x 10 lbs/hr of steam flow
, Hismatch and Low Steam t at RATED THERMAL POWER coincident at RATED THERHAL POWER coincident Generator Water Level with steam generator water level with steam generator water level
> 25- of narrow range instru- > 24K of narrow range instru-ment span each steam generator ment span - each steam generator
.15; -Undervoltage - Reactor > 2750 volts - each bus > 2725 volts -'each bus
.: 'Coolant Pumps 16'. Underfrequency - Reactor . ! > 58.2 Hz - each bus ~ 58.1 Hz - eaa h bus Coolant Pumps 1
'17; Tur bi ne Tr i p /
- . A. Low Trip System > 58 psig > 57 psig Pressure
-
".- B. Turbine Stop Valve
'losure I > lX open < ll open I
18e Safety Injection Input ; Not Applicable Not Applicable from ESF 19; Reactor Coolant Pump Not Applicable
.: Breaker Position Trip
TABLE 3.3-3 (Cont)nued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CNANNELS CHANNELS APPLICABLE
- OF CUANNELS TO TRIP OPERABLE MODES ACTION "FUNCTIONAL UNIT
'6. MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS
- a. Steam Generator Water 2/Stm. Gen.
Level -- Low-Low 3/Stm. Gen. any Stm. Gen. 2/Stm. Gen. 1,2,3 14* b, 4 kv Bus 2/Bus 2/Bus 2/Bus 1,2,3 14+ Loss of Voltage
~
7 TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS 2/Stm. Gen. 2/Stm. Gen. 2o' 14*
- a. Steam Generator Water, 1 s Level -- Low-Low 3/Stm. Gen. any 2 Stm. Gen.
- 8. LOSS OF POWER I
g/Bus 2/Bus 2/Bus 1, 2, 3 14*
- a. 4 kv Bus Loss of Voltage
- b. 4 kv Bus 3/Bus 2/Bus 2/Bus 1,2,3 Degraded Voltage I
~ ~
~ V e
TABLE 3.3-4 (Continued \ ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS n CD CD FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 6.- MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS
- a. Steam Generator Mater Level -- Low-Low
> 2lgof narrow range instrument span each
> 2lpf narrow range instrument span each steam generator steam generator b, 4 kv Bus 3196 volts with a , 3196
+ 18 volts with a Loss of Voltage 2 second delay 2 + .2 second delay 7;. TURBINE DRIVEN AUXILIAPY FEEDWATER PUMPS'-
- a. Steam Generator Water > 21$ of narrow range > 2lgof narrow range Level -- Low-Low I
instrument span each instrument span each steam generator steam generator
'8; LOSS OF PG'HER 3196 volts with a 3196 a 18 volts with a
- a. 4 kv Bus 2 second delay 2 + .2 second delay Loss of Voltage I 1
- b. 4 kv Bus 3596 volts with a 2.0min.
Degraded Voltage time delay 3596 + la volts vfth, a 2.0 minute + 6 second
'
time delay
4 .A<<~ 4>>y'>>0 a 4a < ~ aL>> sk w.>>$ i,>><>>>u>>>> iW>>~O>>h>>>>J>>t <<>>lrA4llllA4'4<<~CA>>w&l>>lsA&rJa~>>WWe <<>><<>><<>>W>>a<<1>>>>WWel>>~t<<w>>>>krwL'l o ~aul Q TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURE ACTUATIOH SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS Pl C) C) 7% CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST RE UIRED 7.. 'URBINE DRIVEN AUXILIARY FEEDWATER PUMPS
- a. Steam Generator Water Level--Low-Low S 1,2,3 8, . LOSS OF POWER
- a. 4 kv Bus Loss of Voltage 1,2,3
- b. 4 kv Bus 1,2,3.
Degraded Voltage
ATTACHMENT 'C'O AEP:NRC:00313 SOUTHWEST RESEARCH INSTITUTE REPORT; SWRI:.'ROJECT 02-4770 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM FOR DONALD C. COOK UNIT NO. 1 ANALYSIS OF CAPSULE T}}