Text

Amend 91 to License DPR-58,revising Tech Specs to Change Setpoints in Channel for Overpower Delta T,Overtemp Delta T, Loss of Flow Trips & Reactor Coolant Temp to Protect Against DNB
	ML17326A981
Person / Time
Site:	Cook
Issue date:	09/03/1985
From:	Varga S; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML17326A982	List: ML17326A981; ML17326A983;
References
	NUDOCS 8509170090
	Download: ML17326A981 (10)
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 91 License No.

DPR-58 1.

The Nuclear Regulatory Commission (the Comission) has found that:

A.

The application for amendment by Indiana and Michigan Electric Company (the licensee) dated July 30, 1985, as supplemented by letters dated August 8, 1985 and two letters dated August 13, 1985.

complies with the standards and requirements of the Atomic 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 provisions of the Act, and the rules and regulations of the Commission; 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 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.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.

DPR-58 is hereby amended to read as follows:

~09~ >0090 850903<~

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(2)

Technical S ecifications The Technical Specifications contained in Appendices A

nd 8 as revised through Amendment No.

91

, are hereby incorporated in the license.

The licensee an shall operate the facility in accordance with the Technical Specifications.

3.

These Technical Specifications are to become effective within 30 days of issuance.

4.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR EGULATORY COMMISSION ven rga Ch' 81 Operating Reactor s a c Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 3, 1985

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

91 FACILITY OPERATING LICENSE NO.

DPR-58 DOCKET NO. 50-315 Revise Appendix A as follows:

Remove Pa es Insert Pa es 2-9 3/4 2-17 3/4 3-17 3/4 3-21 3/4 3-22 2-9 3/4 2-17 3/4 3-17 3/4 3-21 3/4 3-,22

TABLE 2.2-1 REACTOR TAlP SYSTEII 1HSTRUHEIITAT1011 TRIP SETPOlllTS FUIICT LOHAL Ull1T 1.

Hanual Reactor Trip 2.

Power Range, Ileutron Flux 3.

Power Range, IIeutron Flux, lligh Post tive Rate h.

Poser

Range, Ileutron Flux, lllgh llegative Rate 5.

1ntermediate

Range, tleutron Flux 6.

Source

Range, tleutron Flux 7.

Overtemperature aT B.

OverpoMer.aT 9.

Pressurizer Pressure-l.oM 10.

Pressurizer Pressure lllgh 11.

Pressurizer Mater Level--lllgh 12.

Loss uf Floe Design floM is 91,600 gpm per loop.

TA1P SETPOINT Ilot Appl icablo r

Low Setpoint - c 25k of RATED

. TIIEAISL PO)IER lligh Setpoint.- <'109K'of RATED

.TIIEAfNL POIKR c 5g of RATED TIIERHAL POWER with a time constant

> 2 seconds c 5g of AATED TIIEAHAL POWEA siting a time constant

> 2 seconds c 25~ of AATED TIIERNL POWER

< 105 counts per second See llote 1

See llote 2

> 1065 psig

< 2305 psig t

c 92$ of instrutaent span I

> 90$ of tlcsliJfl floM per loop*

ALLOWABLE VALUES Not Applicable I

Low Setpoint - c 26%of RATED TIIEAHAL POIIEA lllgh Setpoint -

< 110%of RATED TIIEANL POllER c 5.5$ of RATED TIIEAHAL POWER with a time constant

> 2 seconds c 5.5 (of RATED TIIERNL POWER with a time constant

> 2 seconds

< 30 <sf RATED TIIERINL POWER

< 1.8 x 105 counts per second See Ilote 3 See llote 4

> 1855 psig

< 2395 psig

< 93$ of instrument span I

>89.1% of desiqn flow per loop+

n n

Cl C) 7C Note 2:

TMLE 2.2-l (Continued)

. REACTOR TRIP SYSTEN IH TRUKNTATION TRIP SETPOIIITS NOTATION (Continued) t3S Overpower aT

< aT tK<-K5 ~

- K6 (T-T"}-f2{al)]

0 T3 where:

aTo

- ~

Extrapolated aT at DESIGN TIIERHAL POMER T

s Tla

~

K4 a

K5 ea K6 Average temperature, F.

/

Indicated Tavg at-DESIGN THERIOL POIKR 577 1 F 1.089 0.0177/

F for increasing average temperature and 0 for decreasing average temperature II 0.0011 for T > T"; Ks 0 for T c T" s3S t3 ee The functton generated by the rate lag controller for $

dynamic compensation Time constant utilized in the rate lag controller for Tag g

10 secs.

S

~

Laplace transform operator tlote 3:

a emote 4:

Q f2(af)

Tire channel 's maximum The chanrrel's maximum f1 laI) as defined in llote 1 above.

trip point sl>all not exceed its computed tr/p point by trip point shall not exceed its computed trip point by more than 2.5 percerit.

more than 3.4.percent.

n s

n OO 7C

+e teLK 3.2-1 DNB PARAHETERS LIHITS PARAI'IETER Reactor Coolant System Ta>9 Pressur)zer Pressure Reactor Coolant System Total Flmr Rate h Loops In Operat)on at RATEO TIIEAHAL POMER c 570 4F

> 2220 ps)a~

/

g J' 1.386 x,108 1bs/hr h Loops In Operation at DESIGN TIIEBI<AL POMER 579 PF

> 2220 ps)a*

> 1.386 x 100 1bs/hr 3 Loops ln Operation at RATEO TIIEHHAL POWER

2220 ps)a*

>0.9917 x I00 Ibs/br hlI

~

m t not app ca e

ur ng e$ ther a TllERI'IAL POIKR ramp )ncrease fn excess of 5 percent RATED THERIACAL POWER per m(nute or a TIIEINAL POMER step increase in excess of 10 percent RATED TIIERHAL POMER.

TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT f.

Steam Flow in Two Steam Lines-High MIHIMUM TOTAL HO.

CHANNELS CHANNELS OF CHANNELS TO TRIP OPERABLE APPLICABLE MODES 3NE ACTION Four Loops Operating Three Loops Operating COINCIDENT MITH EITHER T --Low-Low Four Loops Operating Three Loops Operating 2/steam line 2/operating steam line 1 T /loop 1T/

operating loop 1/steam line any 2 steam 1 ines 1HN/

operating steam line 2 T any loops any operating loop 1/steam line 1/operating steam line 1 T any 3 loops 1T in any avg two operating loops gg**

14*

15 14*

'5

TABLE 3.3-3 Continued EHGIHEEREO SAFETY FEATURE ACTUATIOH SYSTEH IHSTRUHEHTATIOH C)

FUNCTIONAL UNIT COINCIDENT MITH EITHER T

--Low-Low Four Loops Operating Three Loops Operating OR, COINCIDENT M]Tfl Steam Line Pressure-Low Four Loops Operating Three Loops Operating 5.

TURBINE TRIP 5 FEEOHATER ISOLATION TOTAL HO.

CHANNELS OF CHANNELS 70 TRIP 1

T

/loop 1

T /oper-avg ating loop 2 Tav anY loops any operating loop l pressure/

2 pressures loop any loops 1 pressure/

1 pressure operating loop in any oper-ating loop HIHIHUH CllANNELS OPERABLE 1Tany 3 loops 1

T in any two operating loops 1 pressure any 3 loops 1 pressure in any 2 oper-ating loops APPLICAOLE NODES 3ff**

ACTION 15 144 15 a.

Steam Generator Mater Level--

lllgh-illgh 3/loop 2/loop in 2/loop in any oper-

.each oper-ating loop ating loop 1, 2, 3

14*

TABLE 3.3-3 Continued TABLE NOTATI Of'l "Trip function may be bypassed in this MODE below P-ll.

"Trip function may be bypassed in this MODE below P-12.

"" The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode.

The provisions of Specification 3.0.4 are not applicable.

~Rod drop testing in accordance with specification 4.1.3.3, Rod Position Indication Calibration, and hot zero power physics testing may proceed prior to the correction of RTD Calibration Curves for cross-calibration results..et the beginning of cycle.

ACTION STATEMEN'S ACTION 13 - With the number of OPERABLE Channels one less than the Total Number of Channels, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOW"l within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ;

however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2. 1.1.
ACTION 14 - With the number of OPERABLE Channels one less than the Total Number'f Channels, operations may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within l hour.
ACTION 15 - With a channel associated with an operatinq loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT SHUTDO';lN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ;
however, one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2. l.l.
ACTION 16 - With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condi:tion and the Minimum Channels OPERABLE requirement is met; one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.1.
D.
C.
COOK-UNIT 1 3/4 3-22 Amendment No. 91

ML17326A981

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