Text

Amend 100 to License DPR-58,revising Tech Specs to Extend Certain Surveillances Due to Lengthened Cycle 9 Operation
	ML17324B184
Person / Time
Site:	Cook
Issue date:	12/20/1986
From:	Wigginton D; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML17324B185	List: ML17324B184;
References
	NUDOCS 8701050031
	Download: ML17324B184 (58)
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UNITEDSTATES l NUCLEAR REGULATORY COMMtSSION WASHINGTON, D. C. 20555

'I INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR PLANT UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

License No.

DPR-58 1.

The Nuclear Regulatory Commission (the Commi-ssion) has found that:

A.

The applications for amendment by Indiana and Michigan Electric Company (the licensee) dated October I and October 31,

1986, comply with the standards and requirements of the Atomic Energy Act of 1950, 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;:.

t 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:

8701050031 861220 PDR ADQCK 05000315 i

PDR Ql

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.100, are hereby incorporated in the license.

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

3.

The Technical Specification changes shall be effected within 45 days of receipt of this amendment.

4.

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

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

December 20, 1986 Dave L. Wigginton, Project Manager PWR Project Directorate

¹4 Division of PWR Licensing-A

SEE PREYIOUS CONCURRENCE DPWR¹4/DPWR-A PWR¹4/DPWR-A

DWigginton/mac

MDuncan 12/

/86 12/

/86 OGC/Bethesda

Scinto 12/

/86 PW

BJ WR-A gblood 12/i

/86

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 100FACILITY OPERATING LICENSE NO.

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

Remove Paqes 3/4 0-3 3/4 3-1 3/4 3-12 3/4 3-13 3/4 3-15 3/4 3-31 3/4 3-32 3/4 3-33 3/4 3-33a 3/4 3-47*

3/4 3-48 3/4 3-56 3/4 4-14 3/4 4-35 3/4 4-36 3/4 5-5 3/4 5-8 3/4 6-37~

3/4 6-38 3/4 7-6 3/4 7-17 3/4 7-28 3/4 7-45 3/4 8-3 3/4 8-5 3/4 8-6*

3/4 8-14 Included for Convenience Insert Pa 3/4 0-3 3/4 3-1 3/4 3-12 3/4 3-13 3/4 3-15 3/4 3-31 3/4 3-32 3/4 3-33 3/4 3-33a 3/4 3-47*

3/4 3-48 3/4 3-56 3/4 4-14 3/4 4-35 3/4 4-36 3/4 5-5 3/4 5-8 3/4 6-37*

3/4 6-38 3/4 7-6 3/4 7-17 3/4 7-28 3/4 7-45 3/4 8-3 3/4 8-5 3/4 8-6*

3/4 8-14 es

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3 4.0 APPLICABILITY SURVEILLANCE RE UIREHENTS b.

Surveillance intervals specified in Section XI of the ASME Boiler

, and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler and Pressure Vessel Code and applicable Addenda terminology for inservice ins ection and testin criteria Required frequencies for performing inservice inspection and testin activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Yearly or annually At least once per At least once per At least once per At least once per At least once per 7 days 31 days 92 days 184 days 366 days The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.

d.

Performance of the above inservice inspection and testing activities"shall be in addition to other specified Surviellance Requirements.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

4.0.6 By specific reference to this section, those surveillances which must be performed on or before July 31,

1987, and are designated as 18-month surveillances (or required as outage-related surveillances) may be 'delayed until the end of the Cycle 9-10 refueling outage (currently scheduled to begin during the second quarter of 1987).

For these specific surveillances under this

section, the specified time intervals required by Specification 4.0.2 will be determined with the new initiation date established by the surveillance date during the Unit 1 1987 refueling outage.

D.

C.

COOK

- UNIT 1 3/4 0-3 Amendment No.

100

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t 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONOITION FOR OPERATION 3.3.1.1 As a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.

APPLICABILITY:

As show'n in Table 3.3-1.

ACTION:

As shn~n in Table 3.3-1.

SURVE ILLANCE REQU IREMENTS 4.3.1,.1.1 Each reactor trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-1.

t 4.3.1.1.2 The logic for the interlocks shall be demonstrated OPERABLE prior to each reactor startup unl'ess performed during the preceding 92 days.

The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.

4.3.1.,1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reac.or trip function shall be de'monstrated to be within its limit at least nce per 18 months.

Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N

times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the "Total No, of Channels" column of Table 3.3-1.

The provisions of Specification 4.0.6 are applicable.

0.

C.

COOK-UN I '

Amendment No. 100

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~ 'FABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMEHThTION SURVEILLANCE RE UIRENFNTS FUNCTIONAL UNIT CIIAHHEL CllANNEL CllECK CA LIB RAT IOH CllhHHEL MODES IH Wll]CII FUNCTIONAL SURVEI LLANCE 2.

Manual Reactor Trip h.

Shunt Trip Function B.

Uncfervoltage Trip Function Power Range, Neutron Flux N.A.

N.A.

'H,A N,A D(2)>> M(3) and Q(6)

S/U (1) (10) 1>

2 3*

4*

5*

S/U (1) (10).,

~ *>>*

1, 2 and

3.

Power Range, Neutron Flux, High Positive Rate N.A.

.R (6) 1, 2

4 ~

Power Mange, Neutron Flux, lligh Negative Rate H.h.

(6) 1, 2

5.

Intermediate

Range, Heutron Flux R (6)

S/U (1) 2 and S

6.

Source

Range, Neutron Flux

, 7.

Overtemperature

~T S

M 8.

Overpower h T S

M+

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9.

Pressurizer Pressure--Low S

M g

10.

Pressurizer Pressure IIigh S

M 1).

Pressurizer Water LevelIligh S

M

+

o 12.

Loss of Flow - Single loop S

CD

+ Thc provisions of Specification 4.0.6 are applicable.

M and S/U(l) 2 (7),

3 (7),

4 and 5

],

2 2

1, 2

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REACTOR TR I P SY. I'I H INN'I'l<UHI'.N'I'ATION SUI<VI Il.l.hNCI RE Ul RFMFNTS Q

FUNCTIONAI. UN I'I' 13.

Loss of Flow - Two I~ps 14.

Steam Generutor Water Level-S Low-Low

<'IIANNII.

< 'I I I:.<'K

<'IlhNNI I.

<"hl.ll<l<h'I ION CIIANNII.

FUN('TIONAL TEST N.A MODES IN WllICIl SIIRVI ILLANCE REQII I I<EO I,

2 IS.

Steam/Feedwater Flow Mismatch and S

Low Steam Generator Hater Level I,

2 16.

Undervoltage - Reactor Coolant Pumps N.A.

17.

Underfrequency - Reactor Coolant Pumps N.A 1B.

- Turbine Trip A.

Low Fluid Oil Pressure B.

Turbine Stop Valve Closure N.A, N.A N. h.

N.h.

S/0 ( I )

S/U (I )

?

I ~

2

,'9.

Safety Infection Input from ESF N.A.

N.h.

H(4) l, 2

20.

Reactor Coolant Pump Breaker Position Trip N.A N.A N.A.

21.

0 o '2

'D 23.

Reactor Trip Breaker A.

Shunt Trip Function B.

Undervoltage Trip Function Automatic Trip Logic I'.eactor Trip Bypass Breaker N.A.

N.A.

N,h N.A.

M(S) (ll)and S/U(1) (ll)

N.A-M(5)(ll) and S/U(1) (11)

N.A..

- M(12) and S/U(l) (13) 3'*.5*

3*

4*

5*

3*

4*

5*

The provisions of Specifical:ion 4.0.6 are applicable.

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INSTRUMENTATION 3/4.3.2 ENGINEEREO SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONOITION FOR OPERATION 3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instrumenta-tion channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.

C APPLICABILITY: As shown in Table 3.3-3, ACTION:

a.

b.

Mith an ESFAS instrumentation channel trip setpoint less conserva-tive than the value shown in the Allowable Yalues column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION-requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip:Setpoint value.

'ith an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

SURVEIlLANCE RE UIREMENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST oPerationS for the NODES and at the frequencies shown in Table 4.3-2.

l, 4.3.2.1:2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test.

The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by inter lock operation.

4.3.2.1.3 The ENGINEEREO SAFETY FEATURFS

RESPONSE

TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months.

Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the "Total No. of Channels" Column of Table 3

3 i

A

The provisions of Specification 4.0.6 are applicable.

0.

C.

COOK-UNIT 1

Amendment No. lpp

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J' TAOLE 4.3-2 EHGIHEERED SAFETY FEATURE ACTUATlOH SYSTEfi IffSTRINEHTATION R El ffCE RE Ul EH TS FUNCTIONAL UHIT

~ l.

SAFETY IftJECTIOH, TURBINE TRIP, FEEDLfATER ISOLATION> AHD >IOTOR DRIVEN AUXILIARYFEEDlrfATER PUHPS a.

Manual lnitiation b.

Automatic Actuation Logic c.

Containment Pressure-High d.

Pressurizer Pressure-Low e.

Differential Pressure Between Steam Lines--High f.

Steam Flow in Two Steam Lines Iligh Coincident with T

Low or Steam Line PNksur eLow 2.

COffTAIHiiEHT SPfNY a.

Manual Initiation b.

Automatic Actuation Logic c.

Containment Pressure--High-I{igh CINHHEL CIIECK N.A.

N.A.

H.A.

CIIAHNEL taLIDRATION N.A.

N.A.

tf.A.

CIIAHffEL FUNCTIONAL TEST Ii(1)

M(2)

H(3)

M(1)

N(2)

M(3j HOOKS IH MHICH'URVEILLANCE RE UIRED 1,2 ~ 3,4 l, 2, 3, 4

1, 2.

3 l, 2, 3 1, 2, 3 l, 2, 3 1,2,3,4 1 ~ 2S 3I 4 l, f,.3

+

The provisions of Specification 4.0.6 are applicable.

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TABLE 4.3-2 Continued EHGltIEEREO SAFETY FEATURE ACTUATIOH SYSTEH ItISTRUMEHTATION SURVEILLANCE RE UIREHENTS n

n C)

C) 7C I

FUIICTIORAL UNIT 3.

COHTAIIIHEIIT ISOLATION a.

Phase "A" Isolation 1)

Hanual 2)

From Safety Injection Automatic Actuation Logic b.

Phase "0" Isolation

')

Hanual 2)

Automatic Actuation Logic 3)

Containment Pressure--

High-High CIIAHNEL CHECK N.A.

N.A..

N.A.

CIIAHtIEL CALIBRATION N.A.

N.A.

CHANHEL FUtICTIOHAL TEST H(1) ti(2)

H(1)

H(2) ti(3)

NODES IN MIIICH SURVEILLANCE RE UIRED 1

2,'3, 4

1,2,3,4 1,2,3,4 1,2,'3,4 1,2,3 C.

Purge and Exhaust Isolation 1)

Hanual 2)

Containment Radio-ac t 1 v 1 ty-Iligh N.A.

N.A.

1,2,3,4 1, 2, 3, 4

0

+

The provisions of Specification 4.0.6 are applicable.

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TABLE 4.3-2 (Continued)

LNGINCERED SAFFTV rrhIUR) hrliNTION SYSIEH INSTR))HENTATION 5IIIIIICILLANCER. IIIIIEIIEIII5 Fl)NCTIONAL UNIT 4.

STEAH LINE ISOLATION a.

Hanual h.

Automatic Actuation Logic c.

Containment Pressure--

High-tligh d.

Steam Flow in Two Steam Linestligh Coincident with T

Low-Low avg Pressure--Low CHANNLL CHECK N. h.

N. A.

C))hNNEL CALlDRhllnN N.h.

N. h.

CHANNEL FUNCTIONAL TEST H(2)

H(3)

HODES IN NIICtl SURVEILLANCE RE UIREO 1;2,3 1,2,3

'I, 2, 3

1,2,3 5.

TURBINE TRIP AND FEE!)Whit.R ISO)A) lt)N a.

Steam Generator Water S

I.eve 1--tligh-IIigh 6.

H01'OR DRIVEN AUXILIARY FEE'OWAIER I'UHPS 1,2,3 aO b.

C.

S teati Generator Mater Level--Low-Low 4 kv Bus Loss of Voltage Safety injection Loss of Hain Feed Pumps N.h.

N.A.

H(2)

R 1,2,3 1,2,3

. 1, 2, 3

1, 2, 3

+ The provisions of Specification 4.0.6 are applicable.

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TABLE h. 3-2 Continued EIIGIttEERED SAFETY FERTURE'CTUATIOtt SYSTEM ItlSTBUI1CHTATIOtt FUIICTIOIIAL VII IT Ctlnttttr.L CIIECK CIIAIIIII:L CAI. I OIIATI Ot{

CIIAIItlEL FUflCT IOHAL TEST IIODES Itl MlllCII SUBVE ILLAttCE BE VIREO 7.

1UBOItlE DRIVElI AUXILIARYFEEDMATER PUHPS a.

Steam Generator Mater Level--Lov]-Low R+.

1, 2, 3 b.

Reactor Coolant Pump Ous Undervoltage 0.

LOSS OF POWER a.

4 kv Ous Loss of Voltage b.

4 kv Ous Loss of Voltage fl.A.

S, 1 ~ 2 ~ 3 1,2,3,4 1,2,3,4 I

Tive provisio>>s of Specification 4.0.6 are applic.able.

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, TABLE 3.3-9 REMOTE SHUTDOtN MONITORING INSTRUMENTATION n

CD I

CAI I

INSTRUMENT 1.

Reactor Trip Breaker Indication 2.

Pressurizer Pressure 3.

Pressurizer Level 4.

Steam Generator Pressure 5.

Steam Generator Level READOUT LOCATION MEASUREMENT RANGE Hot Shutdown Panel in OPEN-CLOSE Unit No 2 Control Room Hot Shutdown Panel in 1700-2500 psig Unit No.

2 Control Room Hot Shutdown Panel in 0-100K of Unit No.

2 Control Room instrument span Hot Shutdown Panel in 0-1200 psig Unit No.

2 Control Room Hot Shutdown Panel in 0-100K wide range Unit No.

2 Control Room instrument span MINIMUM CHANNELS OPERABLE 1/trip breaker

. 0 1

ll 1/steam generator 1/steam generator

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INSTRUMENT TAnLE 4.3-6 REMOTE SIIUTOO)lH MONITORING IHSTRUMENTATIOH xamaniisrrm~rmrznr CllANHEL CIIECK OIAHNEL CALIDRATIOH l.

Reac tor Tr lp Breaker Indica t ion 2.

Pressurizer Pressure 3.

l'ressurlzer Level Steam Generator Level 5.

Steam Generator Pressure H.A.

N.h.

+ The provision of Specification 4.0.6 are applicable

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n C7 CI 7C IN STRUl1ENT TABLE 4.3-7 POST-ACCIOENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREHENTS CllANNEL CNECK CHANNEL CALIBRATIOil 1.

Containment Pressure 2.

3.

4.

Reactor Coolant Outlet Temperature - TROT (Wide Range)

Reactor Coolant Inlet Temperature - TCOLp (Mide Range)

Reactor Coolant Pressure - Mide Range R

O 5.

Pressurizer Mater Level 6.

Steam Line Pressure 7.

Steam Generator Mater Level - Narrow Range 8.

RWST Mater Level 9.

Boric Acid Tank Solution Level 10.

Auxiliary Feedwater Flow Rate ll.

Reactor Coolant System Subcooling Hargin Monitor 12.

PORV Position Indicator. - Limit Switches 13.

PORV Block Valve Position Indicator - Limit Switches I'4.

Safety Valve Position Indicator - Acoustic Monitor R *

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The provisions of Speci fication 4. 0. 6 are applicable.

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~r REACTOR COOLANT S 3/4.4.6 REACTOR COOLANT SYST&t LEDGE LEAMGE DETECTION SYSTEMS LLfITINGCONDITION POR OPERATION 3.4.6,1 The following Reactor Coolant System leakage detection systems shall be OPERABLE:

a.

One of the containment atmosphere particulate radioactivity monitoring channels (ERS-1301 or ERS-1401) b.

The containment sump level and flow monitoring system, and c.

Either the containment humidity monitor or one of the containment atmosphere gaseous radioactivity monitoring channels. (ERS-1305 or ERS-1405).

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With only two-of the above required leakage detection systems

OPERABLE, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the

. required gaseous and/or particulate radioactivity monit'oring channels are inoperable;

othen4se, be in at least HOT STANDBY within tha next 6

hour s

< and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS I

4.4.6,1 The leakage detection systems shall be demonstrated OPERABLE by.'.

Containment atmosphere particulate and gaseous (if being used)

'monitoring system-performance of CAMEL

CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3, b.

Containment sump level and flow monitoring system-performance of CHAPEL CALIBRATION at least once per 18 months,*

c.

Containment humidity monitor (if being used).~

performance of QiANNEL CALIBRATION at least once per 18 months.

The provisions of Specification 4.0.6 are applicable.

D. C.

COOK - UNIT 1

3/4 4-14 Amendment No. l00

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REACTOR CCOL'HT 5'(Si-9 RELIEP VALVc5 - QPcRATIHQ LIHITIHG COHOIT OH FOR OPcRAT OH 3.4.U.

Three power operated r lief valves (PORYs) and their associated block valves shall be OPERABLE.

APP~ ICABIL ~Y:

830E5 1, 2, and 3.

ACTION:

kith one or more.PORY(s) inooerable, wi"Sin I. hour either restore the PQRY(s) to OPERABLc situs or close the associated block valve(s) and:reacve power fram -Ne block valve(s); otherwise, be'..in at leas HQT STMOBY wiNin t.ae nex 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLO Sit~iOMH within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

1

b. 'i 5 one or acre 51cck valve(s) irocerab'.e, wi hin 'our ei her

(~) restore the block valve(s) w OPERABt=c situs, or (2) close he block valve(s) and remove oower from Ne block valve(s), or {3) close

~J:e associated,.PCRY(s) and remove power;r"m the associated sol'enoid valve(s); ot."elise e in at least HOT STAHOBY within the next.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COL3 SHUTQQMH w:thin.ne fol',=~ing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ."

c.

ine provisions

o. Scecificaticn 3.0." zre not aoplic&le.

SL'RYE:L'H~'."E:UIR~~EH. 5 4, g 'l0

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'T bosch of the three PQRYs shall be demcnstr ated OPERABLE:

b.

At 14as cnc>> "er 31 days 5y perfo~ance of a CHAHHEL rdHCTIOHAL excluding vaive operation, and At leas-once per 18 months by performance of a CHAHHEL CALXBRATEQH. *"

iel; when ACTIQH 3.4.I~.5.(3) is applied, no report pursuant tc Speci ication 6.9.%.9:s requi."ed fcr he FQRV.

+ The provisions of Specification 4.0.6 are applicable.

D. C.

COOK - UNIT 1 3/4 4-35 Amendment No. 100

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REACTOR COOLANT SYSTEH 9UgyE>LLAHCE RE UIR&EHTS Continued) 4.4.11.2 Each of the three block valves shall be demons rataf OPERASLE at least once per 92 days by operating the valve tnrougn one complete cycle of full travel..

The block valve(s) do not have to be tested nor is a report required pursuant to Speci fication 6. 9. 1. 9 when ACTIOH 3.4.11. a is applied.

4.4.11.3 The emergency power supply for the PORVs and block valves sha11 be demonstrated OPERABLZ at least once per H months by operating the valves through a complete cycle of full travel while the emergency buses are energized by the onsite diesel generators and onsite plant battecies.

This testing can be performed in conjunction with the requirements of'pecifications 4.8.1.1.2.b and 4.8.2.3.2.c.*

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The provisions of Specification 4.0.6 are applicable.

D. C.

COOK - UNIT 1 3/4 4-36 Amendment No.

100

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PlBGNCY CORE COOLING SYSTEMS SURYKILI 'NCK REQUIREMENTS (Continued )

d.

At least once per 18 months by:

l.

Verifying automatic isolation and interlock acticn of the RHR systan from the Re ctor Coolant Systen when the Reactor Coolant Systen pressure is above 600 psig.

2.

A visual inspection of the c ntainment sump and ver fying that the subsysten suction inlets are not restr icted by-debris and that the sump components (trash racks.

sere ns, etC.)

ShOW nO eVidepCe Or StruC:ural diStreSS Or

~normal corrosion.

At least once per 18 months, durino shutdown, by:

l.

Yerifying that each automatic valve in the low path ac~~ates to i:s corre": position on a Safety Injection test signal.

2.

Verifying that each cf the.ollowin= comps start automatically upon r c ipt o= a sa ety;n'ec:icn

. st signal:

a)

Co ntr fugal c'waar"..'ng ump b)

Safety injection pump c)

Residual hea.

removal pump f.

By verifying that each of the,ollowing pumps develoos he indicated discharge pressure on recirculation low wnen tested purSuant tO SOeCifiCatiOn ".0.5 at least once per 3l deYs on a STAGGERED TEST BASES.

1.

Centrifugal charging pump 2405 psig 2.

Safety Injection pump

~

1445 psig 3.

Residual, heat r enoval pump

~

195 psig g.'y verifying :he correct position of e'ch mechanical stop for the tne following

-,ergency Core Ccolinc System throttle valves:

1.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following ccmpletion of each valve stroking operation or mainteranco on

..".e valve when the,EC"S sub-systans are required to be OPERA8LE.

Tne provisions of Specification 4.0.6 are applicable' lpp amendment No.

O.. C.

COOK - UNIT 1 3/4 5-5

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EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS 4.5.3. 1 The E"CS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.

4.5.3.2 All charging pumps and safety injection pumps, except the above required OPERABLE cha. ging pump, shall be demonstrated inoperable, by verifying that the motor circuit breakers have been removed from their electrical power supply circuits, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever the temperature of one or more of the RCS cold legs is less than or equal to 170'F as determined at least once per hour when any RCS cold leg temperature is between 17O F and 200'F.

The provisions of Specification 4.0.6 are applicable.

D.

C.

COOK - QNIT l.

3/4 5-8 Amendment No.

C I

f

CONTAINMENT SYSTEMS REFUELING CANAL DRAINS..

I LIMITING CONDITION FOR OPERATION 3.6.5.8 The refueling canal drains shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With a refueling canal drain inooerable, restore the drain to OPERABLE status prior to increasing the Reactor Coolant System temperature above 200'F.

SURVEILLANCE RE UIREHENTS 4.6.5.8 Each refueling canal drain shall be demonstrated OPERABLE priol to increasing the Reactor Coolant System temperature above 200 F after each partial or complete filling of the canal with water by verifying that the blind flange is removed'from the drain line and that the drain is not obstructed by debris.

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D.

C.

COOK-UNI1 1

3/4 6-37 C

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COHTAIHMEHT SYSTB5 OIVIDER BARRIER SEAL LIMITING CONOITION FOR OPERATIO 3.6.5.9 The divider barrier seal shall be OP~BABLE.

APPLICABILITY:

NOOES 1; 2, 3 and 4.

AC, 'tON:

Mith the divider barrie seal inooerable, restore the seal to OPERABLE status prior'to,incre sing the Reactor Coolant System temperature above 200'F.

SURVEILLANCE REOUIR~~RTS 4.5.5.9 The divider barrier seal shall be determined OPEQBLE at least once per 18 months during shutdown by:

a.

Removing two divider barrier seal test couoons and veri ying

.hat the physical properties of the tes.

couoons are within.he acceptable range of values shown in Table 3.6-2.

b.

Visually inspec.ing at least 95 percent of the seal's entire length and:

1.*

Verifying that the seal and seal mounting bolts are pro-perly installed, and 2.

Verifying that the seal material shows no visual evidence of deterioration due to holes, ruptures, chemical at:ack,

abrasion, radiation

damage, or changes in physical appearances.

The provisions of Specification 4.0.6 are applicable.

0. C.

COOK-UNIT 1

3/4 6-38 Amendment No.

100

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C

PLANT SYSTEMS SURVEILLANCE RE UZREMENTS (Continued) 3.

Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secu ed in pos'ticn is in 'ts correct position.

4.

Verifying that each automatic valve in the flow path is in the fully open position whenever the auxiliary feedwater system is placed in automatic control or when above 10%

R TED THECAL POWER.

This requirement is not applicable

=or those portions of the Auxiliary Feedwater System being used intermittently to maintain steam gene ator level.

b.

At least ence per 18 months during shutdown by:

Ver'fy'ng that each autcmatic valve in the flow path ac uates to its correct position upon receipt of the a"propriate engineered safety eatures actuation test.

s gnal recui ed by Speci=ication 3/4.3.2.

2.

Verifying that each auxiliary feedwater pump starts as cesigned automatically upon receipt of the appropriate

- encineered safety features a"tuation test signal required by Specification 3/4.3.2.

The provisions of Specification 4.0.6 are applicable.

D C.

COOK - UNIT 1 3/4 7-6 Amendment No.

100

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3/4.7.4 ESSENTIAL SERYICE MATER SYST N LIMITING CONDITION FOR OPERATION 3.7.4.1 At least two independent essential service water loops shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACiION:

Nth only one service water loop OPERABLE, restore at least two loops to OPERABLE status within T2 hours or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOMN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

URVEILLANC= R:OU R~ENTS 4.7.4.1 A

least two essential service water loops shall be demonstrated OPERABL a.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equip-ment that is not locked,

sealed, or otherwise secured in position, is in its correct position.

b.

At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signaI.*

c.

At least once per 3l days on a STAGGERED TEST BASZS by verifying that each pump develops at least 93i of the discharge pressure for the applicable flow rate as determined from the manufacturer's pump Performance Curve-

The provisions of Specification 4.0.6 are apptidable.

D.

C.

COOK - UNIT I 0/8 7-r >

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PLANT SYSTEHS SURVEILLANCE REQUIREMENTS Co t1 ed b.

At least once per 18 months:*

1.

By performing a system functional test which includes simulated automatic actuation of the system, and:

a)

Verifying that the automatic valves in the flow path actuate to their correct positions on a test signal, and b)

Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel.

2.

By inspection of deluge and preaction type system spray'eaders to verify their integrity-3.

By inspection of each open head deluge nozzle to verify no blockage.

c.

At least once per 3 years by performing an air flow test through each open head deluge header and verifying each open head deluge nozzle is unobstructed.

The provisions of Specification 4.0.6 are applicable.

D C COOK - UNIT 1 4

3!4 7-45 Amendment No,100

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7.

3.

ions of Specification 4.0.6 aze applicable.

Hli I 3/4 8-3 Amendment No.

The provi s D. C.

COOK -

U ne sgP I

Veri-,v-'ng.he

-,ua\\ level in the fuel storage t=-nk,

'i g/ /

t Ver-'fying that a sample of diesel fuel from ".he =uel gt" ] 7 tank is within the acceptable limits spec-fied in Tab)<gt j'STM 0976-66 when checked for viscosi'y, wa 'r and sadf>>I'I Verifying he fuel transfer pump can be started from Qg~

control panel and trans, rs fuel from the storage sy54@~

Verify':ng the diesel starts rom ambien condiation, Yerisying.he generator is synchronized, loaded o >'i

.,: gy.,

kw, and operat s for>> 60 minu.as, and Vari-,iing.he diesel carer=-tor is alicnad to provide s->>=-ndby pcwar o tha soci t d e:-,e".

ncy -'-'ssas.

least once per 18 months dur';ng shu".coun "y:

Subjecting the diesel o an inspec'ion in accordance

'dgf~," v;lpP ~j proc dures prepared in conjunc.ion'wi 2 i w anu-.ac u

'!',-">>".>> ",S r>>coInsendations for this class oi standby service Yerifyirg.he genera or capabisli.y to re-'ec.

a load Oe Simulating a loss of offsiie power in conjunction ~it0 jj@~+A'afety injection signal, and:

a)

Verifying de-energization of the emergency busse~,.',

and load shedding from the emergency

busses, b)

Verifying the diesel 's arts from ambient cond)~,~~t>'g on the auto-s art signal, ener gizes De emeroo<c/~

s busses with permanently connec ad loads. energisesr'[

the auto-connected emergency loads through the 1<~+...

sequencer and ope. ates

=or

> 5 minutes whi;e i.$

'".@~';~;

generator is loaded with the emergency loads.

, c)

Yerifying.hat on diesel generator trip, the loan~

>~ >~,

shed from:he emergency buses and the dises2l re s.arts on the auto-s.ar signal following manual reset ing of the diesel trip lockout relay, the '~j3;.

emergency "uses are energi=ed uith pe.manen'Iy c-..w

':";,.'ec.ed

loads, the au.o-connec ad emergency Ioacs S.

energized

hrough the load seouenc r and

-he a',est'P operates

."r Q 5 minutes while i:s generator

,g loaded ui:h "he amergercy '.o'~si

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ELECTRICAL POMER SYSTEMS SHOTO ONN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE a.

One circuit between the of. site transmission network and the onsite Class lE dis:ribution system, and b.

One diesel generator with:

1.

A day tank containing a minimum of 70 gallons

o. fuel, 2.

A uel storage system con.airing a minimum of 42,000 gallons of fuel, and 3.

A fuel.rans, er pump.

AP~LICABILI=.Y:

MODES-5 and 6.

ACTION:

With less than the above minimum required A.C. electrical oower sources OPERABLE, suspend all ooeratiors involving CORE ALTERATIONS or positive react'viiy cnanges until the minimum reouired A.C. electrical power sourc s are restored to OPERABLE s:atus.

SURYE'LLANCE REQUIREMENTS 4.8.1.2 The above required A.C. ele trical oower sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirenents of4.8.1.1.1 and 4.8.1.1.2 except for requirenent 4.8.1.1.2a.6. *

The provisions of Specification 4.0.6 are applicable.

0.

C.

COOK -UNIT 1

3/4 8-5 Amendment No.

10p

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ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS (Continued) 0 The pilot cell specific gravity, corrected to 77 F and full electrolyte level (fluid at the bottom cf the

...aximum level indication mark), is K 1.200, 3.

The pilot cell voltace is ~ 2.10 volts, and 4.

The overall battery voltage is ~ 250 volts.

b.

At 'east once per 92 days by verifying that:

l.

The voltage of each connected cell is > 2.10 volts under

'oat charge and has not decreased more than 0.05 volts rom the value observed during the original acceptance

test, and 2.

he specific gravi y, corrected to 77 r" and full e'ectro'yte level (fluid at the bottom of the maximum

'e;el inc'cation mark), of each connected ce'1 is

.:CC and has not decreased more than 0.03..from the.

.aiue observed guring the previous test, and

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3.

The elec..rc vte level cf each connected cell 's between

-he tcp of the minimum level indication mark and the bo"tom c= the maximum 'evel incicaticn mark.

c.

At 'east ence per 18 months by ver'ing that:

.he cells, cell plates and batte

~

racks show no'isual indication of physical damage o

abnormal deterioration.

2.

The cell-to-cell and terminal connections are clean, ticht, free o ccr osion and coated with anti-co rosion material.

3.

The battery charger will supply at least 10 amperes at 250 volts for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

d.

At least once pe 18 months, during shutdown (MODES 5 or 6), by ver"=ying that the battery capacity is adeauate to supply and maintain in OPERABLE status the emergency loads for the times specified in Table 4.8-2 with the battery charger disconnected.

The battery terminal voltage shall be ra'ntained + 210 volts throughout the battery se vice test.

e.

At least once per 60 months, during shutdown (MODES 5 or 6),

b> -verifying that the battery capacity is at least 80'b of the manufacturer's rating when subjected,to a performance discharge test. This performance discharge test shall be per ormed in place of the battery service test.

The provisions of Specification 4.0.6 are applicable.

D. C.

COOK - UNIT 1 3/4 8-14 Amendment No.

1QQ

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ML17324B184

Text

Attachment:

RESPONSE

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