ML17321A328
| ML17321A328 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/03/1984 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17321A327 | List: |
| References | |
| NUDOCS 8412070289 | |
| Download: ML17321A328 (6) | |
Text
ATTACHMENT 2 TO AEP:NRC:0895A PROPOSED CHANGES TO THE DONALD C.
COOK NUCLEAR PLANT UNIT NOS.
1 AND 2 TECHNICAL SPECIFICATIONS
~
~
~ i 8412070289 841203 PDR ADQCK 05000315 P
t II
E; REACTOR COOLANT &VS HOT STANDBY LIMITINGCONDITION FOR OPERATION 3
4 1
2 a.
At least two of the reactor coolant loops listed below shall be
~
~
~
OPERABLE:
1.
Reactor Coolant Loop 1 and its associated steam generatoz and reactor coolant
- pump, 2.
Reactor Coolant Loop 2 and its associated steam generator and reactor coolant
- pump, 3.
Reactor Coolant Loop 3 and its associated steam generator and reactor coolant pump, 4..
Reactor Coolant Loop 4 and its associated steam generator and reactor coolant pump.
b.
At least two of the above coolant loops shall be in operation
'::= Unless..the.reactor. trip breakers are disconnected.*
c At: least one of the above coolant loops shall be in 'opera'tion "'"
ed.
- if the reactor trip breakers are disconnecte APPLICABILITY:
MODE 3
ACTEON:
a.
With less than the above required reactor coolant loops
- OPERABLE, restore the required loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be
'n 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 />.
b.
With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation.
SURVEILLANCE RE U1REMEN S 4.'4.1.2.1 At least the above required reactor coolant pumps, if not'n."
operation, shall be determined to be OPERABLE once per 7 days by verifying correct breeaker alignments and indicated power availability.
4.4.1.2.2 At least one cooling loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- All reactor coolant pumps may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided (1) no operations are permitted that would cause dilution of the reactox coolant system, boron concentration, and (2) core outlet temperature is maintained it least 10 F below saturation tempexatuxe.
0 D. C.
COOK - UNIT1'/44 2
AMENDMENT NO.
REACTOR COOLANT SYSTEM HOT STANDBY LIMITINGCONDITION FOR OP RATION 3.4.1.2 a.
At least two of the reactor coolant loops listed below shall be OPERABLE:
1.
Reactor Coolant Loop 1 and its associated steam generator and reactor coolant pump, 2.
Reactor Coolant Loop 2 and its associated steam generator and reactor coolant pump, Reactor Coolant Loop 3 and its associated steam generator and reactor coolant pump, 4.
Reactor Coolant Loop 4 and its associated steam generator and reactor coolant pump.
,':, b.:" -.At"l.east.;two of the. above. coolant.loops;.shall. be in;oper'ation I
Unless the reactor trip.breakers are disconnected.
At least one of the above coolant loops shall be in operation if the reactor trip breakers are disconnected.
~
APPLICABILITY:
MODE 3 ACTION:
a.
With less than the above required reactor coolant loops
- OPERABLE, restore the required loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 />.
b.
With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation.
SURVEILLANCE RE UIREMENTS 4.4.1.2.1't least the above required reactor coolant pumps, if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breeaker alignments and indicated power availability.
4.4.1.2.2 At least one cooling loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
All reactor coolant pumps may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided (1) no.
operations are permitted that would cause dilution of the reactor coolant system boron concentration, and (2) core outlet temperature is maintained it 0
least 10 F below saturation temperature.
D. C.
COOK - UNIT 2 3/4 4-2 AMENDMENT NO.
m~ SAFE Seers SETTmaS relfabflfty of the Reactor Protectfon System.
Thfs trfp fs redundant to the Steajs Generator Water Level Lowbrow trip.
The Steam/Feedwatar F1ow mismatch portion of this trfp is activated when the steam flow exceeds the feedwater f1ow by c 0.71 x 10< lbs/hour.
The Steal Generator Low Mater level portion of the trip is activated when the water level drops below 25 percent, as indicated by the narrow range inst+ment.
These trip values fnclude sufffcfent allowance fn excess of normal operating values to preclude spuHous tHps but will initiate a reactor trfp before the steas generators are dry.
T)mrefore. the required capacity and starting tfme requfreients of the auxflfary feedwater puaps are reduced and the resulting thermal transient on the Reactor Coolant Systea and steam generators is minimized.
Undervolta e and Underfre uen
- Reactor Coolant P
Busses The Undervoltage and Underfrequency Reactor Coolant Pump Bus trips provide reactor care protection against ONB as a result of complete loss of forced cadi'ant-. fl:ow.:.- The=,.speci. fied setpoints,assure.
a..reactor trip ytgnal is generated befor'e the low flow trip setpofnt is 'reached.
" Tiaie delays are'ncorporated in the 'underfrequency'and undervoltage trips to prevent spurious reactor trips from momentary electrical power transients.
For undervoltage, the delay is set so that the time required for a signal to reach the reactor tHp breakers following the simultaneous tHp of two or more reactor coolant pump bus circuit breakers shall not exceed
{O.9) seconds.
For underfrequency, the delay is set so that the time required for a signal to reach the reactor tHp breakers after the underfrequency tHp setpofnt is reached shall not exceed (0.3) seconds.
On decreasing power the Undervoltage and Underfrequency Reactor Coolant Pump Bus trips are auteaatfcally blocked by P-7 (a power level of approximately 10 percent of RATEQ THERMAL POMER with a turbine fapulse chamber pressure at approximately 10 percent of full power equivalent);
arid o
increasing power, reinstated automatically by P-7.
T~i A Turbine Trip causes a direct reactor trip when operating above P-7.
Each of the turbine trips provide turbine protection and reduce the severity of the ensuing transient.
No credit was taken in the accident analyses for operation of these trips.
Their functional capability at the specified trip settings is required to enhance
.the overall reliability of the Reactor Protection System.
0.
C.
COOK - UNIT 1
8 2-7 AMENDMENT NO.
relfabflfty of the Reactor Protection System.
This trip fs redundant to the Steaa Generator Water t.evel Lowbrow trip.
The Steam/Feedwatar Floe Nslatch portion ot'his trfp fs activated when the steam flow exceeds the feedwater floe by c 0.71 x 10< lbs/hour.
The Steaa Generator l.ow Water level portfon of the trfp fs activated when the water level drops below 25 percent, as fndfcated by the narroe range fnstnawnt.
These trip values include sufficient allowance fn excess of normal operatfng values to preclude spurious trips but &11 fnftfate a reactor trfp before the steII generators are dry, Therefore.
the required capacity and startfng tice requf~ts of the auxiliary feedwaCer pulps are reduced and the resulting thermal transfent on the Reactor Coolant Systaa and steam generators fs mfnfmfzed.
Undervolta e and Underfre uen
- Reactor Coolant P
Busses The Undervoltage and Under frequency Reacto~ Coolant Pump Bus trips provide reactor core protection.against OHB as a result of complete loss of forced
'coo'lant".flow.='.-The specified setpoints.'assure a reactor,.trip. signal is generated before the low flow trip setpoint is reached; Time delays are incorporated in the underfrequency and undervoltage trips to prevent spurious reactor trips from momentary electrical power transients.
For undervoltage, the delay is set so that the time required for a signal to reach the reactor trip breakers following the simultaneous trip of two or more reactor'.coolant pump bus circuit breakers shall not exceed (0.9) seconds.
For underfrequency, the delay is set so that the tfae required for a signal to reach the reactor trip breakers after the underfrequency trip setpoint is reached shall not exceed (0.3) seconds.
On decreasing power the Undervoltage and Unde<frequency Reactor Coolant Pump Bus trips are automatically blocked by P-7 (a power level of approxfmately 10 percent of RATEO THERMAL RMR with a turbine impulse chamber pressure at approximately 10 percent of full power equivalent);
and on increasing power, reinstated automatically by P-7.
Turbine Trip A Turbine Trip causes a direct reactor trip when operating above P-7.
Each of the turbine trips provide turbine protection and reduce the severity of the ensuing transient.
No credit was taken in the accident analyses for operat:ion of these trips.
Their functional capability at the..specified trip settin'gs is required. to enhance the overall reliability of the Reactor Protection System.
O.
C.
CQOX - UNrT Z B 2-7 AMENDMENT NO-