ML17319A577
| ML17319A577 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/25/1980 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17319A578 | List: |
| References | |
| NUDOCS 8009120048 | |
| Download: ML17319A577 (12) | |
Text
8 RECq UNITED STATES i'NUCLEAR REGULATORY COMMISSlON iV*SHINGTON,D. C. 20555 INDIANA AND i"/ICHICAH ELECTRIC COMPANY DOC'r'ET NO.
50-315 DONALD C.
COOY. NUCLEAR PLANT UNIT HO.
1 Al1ENDtlENT TO FACILITY OPERATING LICENSE Amendment No. 39 License Ho. DPR-58 1
~
The Nuclear Regulatory Commission (the Coranission) has found that A.
The application for am ndment by Indiana and Michigan Electric Company (the licensee) dated February 22 and i<ay 28,
- 1980, comp 1 1 es with the standards and requ irements of the Atomi c 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 provi sions of the Act, and the rules and regulations of the Comnission; 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 Corimission'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 Comnission's regulations and all applicable requirements have been satisfied.
8009120 048
2.
Accordingly, the 1 i cense is amended by changes to the Technical Speci ications as indicated in the attachment to this license amendment, and paragraph 2.C. (2) of Facility Operating License No.
DPR-5S is hereby amended to read as follows:
(2)
Techni ca 1 S eci fi'cat ions The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
39, are hereby incorporated in the license.
The licensee 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 REGULATORY CORI SS I ON Attachment Changes to the Technical
'pecifications Date of Issuance:
July 25, 1980 C
ef ve
- rga, Operating Reactors branch
<1 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT HO.
39 TO FACILITY OPERATING LICENSE NO.
DPR-58 DOCKET NO.
50-315 Revise Appendix A as follows:
Remove Pa es 3/4 3-29 3/4 3-30 3/4 3-33 3/4 3-34 3/4 8-3 3/4 8-4 Insert Pa es 3/4 3-21a 3/4 3-26a 3/4 3-29 3/4 3-30 3/4 3-33 3/4 3-33a 3/4 3-34 3/4 8-3 3/4 8-4
n TABLE 3.3-3 Cont)nued
. ENGIHEERED SAFETY FEATURE ACTUATIOH SYSTEM IHSTRUrlEHTATIOH n
CD CD FUNCTIONAL UHIT TOTAL HO.
OF CHANNELS Cl AHHELS TO TRIP.
n>IHIMUM CHANNELS.
OPERABLE APPLICAB(;E HODES MOTOR DRIYEtr AUXILIARY FEEDWATER PUMPS a.
Steam Generator Water Level- -- Low-Low b.
4 kv Bus Loss of Voltage 2/Stm.
Gen.
3/Stm.
Gen.
any Stm.
Gen.
2/Stm.
Gen.
1, 2, 3
2/Bus 2/Bus 2/Bus 1, 2, 3
7.
TURBINE DRIVEN AUXILIARY FEEDMATER PUMPS "
a.
Steam Generator Water Level -- Low-Low.
8.
LOSS OF POWER 2/Stm.
Gen.
2/Stm.
Gen.
1, 2, 3
3/Stm.
Gen.
any 2 Stm.
Gen; a.,4 kv Ous Loss of Voltage 3/Bus 2/Ous
-2/Ous, ';..
1, 2, 3, 4
b.
4 kv Bus Degraded Voltage
~ 3/Bus 2/Bus 2/Bus l,2,3,'4 O
TRBLE 3 3-4 Continued ENGINEERED SAFETY FEATURE ACTUATIOH SYSTEH INSTRUHENTATIOH TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOHABLE VALUES O
6.
l'IOTOR DRIVEN AUXILIARY FEEDHATER PUtfPS a.
Steam Generator Hater Level -- Low-Low b.
4 kv Bus Loss of Voltage 7.
TURBINE DRIVEN AUXILIARYFEEDWATER PUHPS a.
Steam Generator Hater Level -- Low-Low 0.
LOSS OF.POHER a.
4 kv Bus Loss of Voltage 4 kv Bus Degraded Yoltage
> 10K of narrow range instrument span eacl>
steam generator 3196 volts'ith a
'-second delay
> 10'f. of narrow range instrument span each steam generator
3196 volts with a 2-second delay 3196 volts with a 2.0 min. time delay
> 9C of narrow range instrument span each steam generator 9196+10 volts with a 3I.2 second delay
>.9X of'arrow range Tnstrument span each s team genera Lol 3196+if l vnl ts wi Lh a
2+.2 second delay I
3196+10 volts jwith a
'.0 minute + 6'econd time delay
TABLE 3.3-5 Continued ENGINEERED SAFETY FEATURES
RESPONSE
TIMES INITIATING SIGNAL AND FUNCTION 6.
Steam Flow in Two Steam Lines-Hi h
Coinci ent with Steam Line Pressure-Low
RESPONSE
TIME IN SECONDS a.
b.
C.
d.
e.
9
~
h.
Safety Injection (ECCS)
Reactor Trip {from SI)
Feedwater Isolation Containment Isolation-Phase "A"
Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System Steam Line Isolation
< 13.0¹/23.0¹¹
< 3.0
< 8.0
< 18.0¹/28.0¹¹ Not Applicable Not Applicable
< 14.0¹/48.0¹¹
< 8.0 7.
Containment Pressure--Hi h-Hi h
a.
Containment Isolation-Phase "B"
c.
Steam Line Isolation d.
Containment Air Recirculation Fan
< 45.0 Not Applicable
< 7.0
< 660.0 8.
Steam Generator Water Level--Hi h-Hi h
a.
Turbine Trip-Reactor Trip b.
Feedwater Isolation
< 2.5
< 11.0 9.
Steam Generator Water Level--Low-Low a.
Motor Driven Auxiliary Feedwater Pumps
< 60.0 b.
Turbine Driven Auxiliary Feedwater'Pumps
< 60.0 10.
4160 volt Emer encv Bus Loss of Volta e a.
Motor Driven Auxiliary Feedwater Pumps
< 60.0 D.
C.
COOK-UNIT 1
3/4 3-29 Amendment No.
39, Unit 1
TABLE 3.3-5 Continued TABLE NOTATION Diesel generator starting and sequence loading delays included.
Response
time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging
Diesel generator starting and sequence loading delays not included.
Offsite power available.
Response
time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.
Diesel generator starting and sequence loading delays included.
Response
time limit includes opening of valves to establish SI pa.h and attairment of discharge pressure for centrifugal charging pumps.
D. C.
COOK-UNIT 'l 3/4 3-30 Amendment No. 39, Unit l
TABLE 4.3-2 Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE E UIREMENTS FUNCTIONAL UNIT 4.
STEAM LINE ISOLATION a.
Manual b.
Automatic Actuation Logic c.
Containment Pressure High-High d.
Steam Flow in Two Steam LinesHigh Coincident with T
Low or Steam Line PQfsure--Low 5.
TURBINE TRIP AND FEEDWATER ISOLATION a.
Steam Generator Water Level--High-High CHANNEL CHECK N.A.
N.A.
CHANNEL CALIBRATION N.A.
N.A.
CHANNEL FUNCTIONAL
, TEST M(1)
M(2)
M(3)
MODES IN WHICH SURVEI LLANCE RE UIRED 1,2,3 1,2,3 1, 2, 3
1, 2, 3
1 2
3 6.
MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS a.
Steam Generator Water Level --Low-Low b.
4 kv Bus Loss of Voltage 1,2 3
1,2,3
TABLE 4.3-2 Cont'lnued ENGINEERED SAFETY FEATURE ACTUATION SYSTEll 'INSTRUllENTATION SURVEILLAtlCE RE UIREI1ENTS CHANNEL CHECK a.
Steam Generator (later Level--Low-Low 8.
LOSS OF POWER a.
4 kv Bus Loss of Voltage 4 kv Bus Degraded Voltage FUNCTIONAL Ul'lIT 7.
TURBINE DRIVEN AUXILIARYFEEOllATER PUMPS CllANNEL CHAHNEL FUNCTIONAL CALIBRATION TEST llODES IN MHICH SURVEILLANCE IEIEUE I III EE
- 1. 2'3 1, 2, 3, 4
1, 2, 3, 4
TABLE 4.3-2 (Continued TABLE NOTATION (1)
Manual actuation switches shall be tested at least once per
']8 months during shutdown.
All other circuitry associated with manual safe-guards actuation shall rece'ive a
CHANNEL FUNCTIONAL TEST at least once per 31 days.
(2)
Each train or logic channel shall be tested at least every other 31 days.
(3)
The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying either a vacuum or pressure to the appropriate side of the transmitter.
D. C.
COOK-UNIT 1
3/4 3-34 Amendment No. 39, Unit 1
Z:-rUIc"=l<=!'TS 'Continue ')
3.
Varifving the fuai level in the
-,uer storage
- tank, Verifying that a sample o-, diesel fuel
=roMi tne =ual stolaoe t nk is within the acceptable
~'m'ts s"eci=',ed in Table l o-,
ASTN 0975-c8 when checked
-,or viscosity, wa ~r and sediment, Veri=ying the fuel trans=er pump can be started from the'ontrol panel and t ans-,ers
=uel from the s.orage system
,o the day tank, VerifJ'nc he diesel s
ar 5
m amb;an conc i '
on y
~I ~
Ver'-,J ng the generatcr is synchronized, loaded
.o
> 1750 kw, and opera"es
=or
> cG minutes anc Ver'.fving the
>ower diesel canerator is aiicnad to provide
- o the associia-ad amer"encv
'"ussas.
At least onc per ic;,cnths curine shu:"'"
r, y:
't
~ '
Subj tin= the ciasei"to
=n 'rs"
- cn '.n ac"ordarc w>th procedures prepared in conjunction wi'h its znu ac ure, '-
-r ccmmendazions for this class o= standby service, Ver ify;rg -he cener ator capab i I itJ 0 re-.ect a load 00 kw w I lout triop i ng, 3.
Simulating a loss o= of=site'ower
',n conjunction <ith a safety injec ion s ignal, and:
a)
Verifyina de-anergization o-the emergency busses and load shedding rom.he emeroency busses.
b)
Ver"',fying the diesel s ar.s from ambient condition on the auto-start s',gnal, energizes re emergency busses with permanently connec-ed loads; energizes he auto-connect d emergency loads d.rough t e load saquencer and opera-es for 5 minu~~s whi;e i:s generator is loaded wi h the erne. cency loads.
c)
Veri=ying tha-on d',esel cenerator "rio, ".he loads ar shed frcm he
=merce. cy buses and "he ciasa'.
resett-ng of the d'.esai
- t. io lockout relay, tne emergency
'"uses
=re anergi=ed with "erm-nentiy co,.-
nec ed loads, the auto-connected emergency lo-cs
=-". e enerai=ed
- hrouan the
'broad s-cuancer and the oiesa!
operates for Q : minutes wn (e i=s "enerator s
0.
C.
COOK - Ul(IT 1
3/4 8-3 Amendment Ho. 39, Unit 1
ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS Continued)
\\
4.
Verifying the diesel generator operates for > 60 minutes while loaded to
> 3500 kw.
5.
Verifying that the auto-connected loads to each diesel generator do not exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of 3650 kw.
6.
Verifying that he automatic sequence timing relays are OPERABLE wi' each load sequence-time within + 5X of its required value and that each load is sequenced on within the design allowable time limit.
D.
C.
COOK - UNIT 1
3/4 8-4 Amendment No. 39, Unit 1