ML17319B624

Amends 60 & 43 to Licenses DPR-58 & DPR-74,respectively, Revising Tech Specs to Reflect Installation of RMS

ML17319B624
Person / Time
Site:	Cook
Issue date:	09/09/1982
From:	Varga S Office of Nuclear Reactor Regulation
To:
Shared Package
ML17319B625	List: ML17319B624 ML17319B626 ML17319B627
References
NUDOCS 8211030254
Download: ML17319B624 (39)

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0 Yg+~ y*~*4 UNITED STATES 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. 60 License No.

DPR-58 1.

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

A.

B.

C.

D.

E, The application for amendment by Indiana and Michigan Electric Company (the licensee) dated August 20, 19B2, 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 The issuance of this amendment is in accordance with 10 CFR Part 51 of'he Commission's regulations and all applicable requirements have been satisfied, 8Z1 1030250'20909 PDR ADOGK 05000315 PDR

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2 2.

Accordingly, the license is amended by changes to the Technical Specifications as indi cated 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:

(2)

Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 50

, 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 COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 9,

1982 r)

Steven A. Varga, Chief Operating Reactors Branch gI Division of Licensing

ATTACMENT TO LICENSE 'AMENDMENT AMENOMENT NO.

60 TO FACILITY OPERATING LICENSE'NO.'OPR-58 NP DOCKET NO. "50-'315 Revise Appendix A as follows:

Remove Pa es 3/4 3-19 3/4 3-20*

3/4 3-26 3/4 3-35 3/4 3-36 3/4 3-37 3/4 3-38 3/4 4-13*

3/4 4-14 3/4 9-9*

3/4 9-10 3/4 3-'19 3/4 3-20*

3'/4 3-26 3/4 3-35'/4 3-36 3/4 3-37 3/4 3-38 3/4 4-13*

3/4 4-14 3/4'-9*

3/4 9-10

• Included for convenience

TABLE 3.3-3 (Continued)

E:ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION n

nOO FUNCTIONAL UNIT 3.

CONTAIAKNT ISOLATION a.

Phase "A" Isolation

1) Manual

2) From Safety In)ection Automatic Actuation Logic TOTAL NO.

OF CHANNELS MINIMUM CHANNELS CHANNELS TO TRIP OPERABLE APPLICABLE MODES 1,2,3,4 1,2,3,4 ACTION 18 13 b'hase "B" Isolation

1) Manual

2) Automatic Actuation Logic

') Containment Pressure-High-High

.3 1,2,3,4 1,2,3,4 1,2,3 18 13 16 C ~

Purge and Exhaust Isolation O

1) Manual

2) Containment Radioactivity-High Train A

3) Containment Radioactivity-High Train B

1,2,3,4 1,2,3,4 i>2,3,4 17 17 17

>>IuiI. J. ~-3 Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT

~4.

STEAM LINE ISOLATION TOTAL NO.

CHANNELS OF CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES ACTION a.

Manual b.

C.

d.

Automatic Actuation Logic Containment Pressure--

High-High Steam Flow in Two Steam Lines--High Four Loops Operating 1/steam line 1/steam line 1/operating 1, 2, 3

steam line 2

1 2

1,2,3 1,2,3 3¹¹ 2/steam 1 ine 1/steam 1 ine 1/steam 1 ine any 2 steam lines 18 13 16 Three Loops Operating 2/operating steam line 1¹¹¹/

operating steam line 1/operating steam line 15

CD n

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS n

CD CD FUNCTIONAL UNIT 2.

Containment Radioactivity High Train A TRIP SETPOINT

~ 2 x normal channel reading ALLOMABLE VALVES Q 2 x normal channel reading 3.

Containment Radioactivity High Train B 4.

STEAM LINE ISOLATION 2 x normal channel reading 2 x normal channel reading a,

Manual b.

Automatic Actuation Logic c.

Containment Pressure High-High d.

Steam Flow in Two Steam Lines--

High Coincident with TavR Low-Low or Steam Line rressure--

Low 5.

TURBINE TRIP AND FEED MATER ISOLATION Not Applicable Not Applicable

~ 2.9 psig

~1.42 x 10 lbs/hr from 0%

load to 2)% load.

Linear from 1.42 x 10 l)s/hr at 20X load to 3.88 x 10 lbs/hr at 100%

load.

T

>~ 541 F avg

%~600 psig steam line pressure Not Applicable Not Applicable

~3 psig 1.56 x 10 lbs/hr from 0%

load to 2)% load.

Linear from 1.56 x 10 1)s/hr at 20X load to 3.93 x 10 lbs/hr at 100X load.

T

>~ 539 F

+580 psig steam line pressure O

a.

Steam Generator Mater Level--

High-High

~67% of narrow range instrument

~68% of narrow range instrument span each steam generator span each steam generator

s t L

~.

st INSTRUMENTATION 3/4. 3. 3.MONITORING INSTRUMENTATION RADLOTION MONITORING INSTRUMPiiTATION LZKETING CONDITXON FOR OPERATION 3.3,3.1 The radiation monitoring instrumentation chaanels shown in Table 3.3-6 shall be OPEEEELE with their alarm/trap setpetnts within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

a.

With a radiation monitoring channel ala~/trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to withia the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.

b. 'ith oae or more radiation monitoring channels inoperable, take the ACTION showa in Table 3.3>>6.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are aot applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring iastrumentatioa channel.

shall be demonstrated OPERABLE by the performance of the CHh2WiH. CHECK, CHANNEL CALIBRATION and CHANNEL FPifCTIONAL TEST operat" oas during the modes: and at the frequencies shown ia Table 4.3-3.

D. C. COOK~IT 1

3/4 3-3S Amendment No.

60 asw s

~

~

nOQ

~

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TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION ALARM/TRIP SETPOINT MINIMUM CHANNELS OPERATION MODE INSTRUMENT OPERABLE MEASURFMEHT BANGE ACTION 1.

MODES 1,2,3, 6

4 a.

AREA MONITOR

i. Upper Containment b.

PROCESS MONITORS i, Particulate ii. Noble Gas 2.

MODE 6

~2 x normal channel reading

~2 x normal channel reading

~2 x normal channel reading 10 to 10 mR/hr 19 1.5x10 to 1.5 uCi 20 10 to 10 uCi/cc 20 a.

TRAIN A

i. Containment Area Radiation Channel-VRS-1101 ii. Particulate Channel-ERS-1301 iii. Noble Gas Channel-ERS-1305

1. 5x10 to 1. 5 uCi 10 to 10 uCi/cc

<2 x normal channel reading

<2 x normal channel reading any 2/3 Channels

-1 4

~2 x normal channel reading 10 to 10 mR/hr 22 O

b.

TRAIN B

i. Containment Area Radiation Channel-VRS-1201 ii. Particulate Channel-ERS-1401 iii. Noble Gas Channel ERS-1405 any 2/3 Channels Same as 2.a Same as 2.a Same as 2.a Same as 2.a Same as 2.a Same as 2.a 22 3

a.

Spent Fuel Storage

~ 15 mR/hr 10 to 104 mR/hr 19

> With fuel in storage pool or building.

t r

~ TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 19 With the number of channels OPERABLE less than required by the Hinimum Channels Operable requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per day.

ACTION 20 With the number of channels OPERABLE less than required by the Hinimum Channels Operable requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 22 With the number of channels OPERABLE less than required by the >linimum Channels Operable requirement, comply with the ACTION requirements of Specification 3.9.9.

This ACTION is not required during the performance of containment integrated leak rate test.

D.

C.

COOK -'NIT 1 3/4 3-37 Amendment No.

&0'

TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS nOO I

OPERATING MODE/IiSTRUMENT 1.

MODES 1, 2, 3,

& 4 a.

AREA.".OXITOR

i. Upper Containment b.

PROCESS iA'ONITORS CHANNEL CHANNEL CHECK CALIBRATION CHANNEL FUNCTIONAL TEST MODES FOR WHICH SURVEILLANCE IS RE UIRED lB 2, 3

& 4

i. Particulate ii, noble Gas S

~ S R

R M

M 1, 2, 3

& 4 2.

MODE 6 a.

TRAIN A

i. Containment Area Radiation Channel ii. Particulate Channel iii. noble Gas Channel S

S S

R R

R M

M M

6 6

6 O

b, TRAIN B

i. Containment Area Radiation Channel ii. Particulate Channel iii. noble Gas Channel S

S S

R R

R M

M M

6 6

6 3

a.

SPENT FUEL STORAGE S

• With fuel in the storage pool or building.

TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION 1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION Sample Size Result Action Required

~

Result Action Required Result Action Required A minimum of S Tubes per S. G.

C-1 C-2 C-3 None Plug defective tubes and inspect additional 2S tubes in this S. G.

Inspect all tubes in this S. G.. plug de.

fective tubes and inspect 2S tubes in each other S. G.

Prompt notification to NRC pursuant to specification 6.9.1 N/A C-1 C-2 C-3 All other S. G.s are C-I Some S. G.s C-2 but no additional S. G. are C-3 Additional S. G. is C-3 N/A None Plug defective tubes and inspect additional 4S tubes in this S. G.

Perform action for C-3 result of first sample None Perform action for C-2 result of second sample Inspect all tubes in each S. G. and plug defective tubes.

Prompt notification to NRC pursuant to specification 6.9.1 N/A N/A C-I C-2 C-3 N/A N/A N/A N/A N/A None N/A N/A N/A N/A N/A Plug defective tubes Perform action for C-3 result of first sample 3

g/

Where N is the nuinber of steam generators in the unit, and n is the number of steam generators inspected N

during an inspection

REACTOR COOLANT SYS 3/4.4,6 REACTOR COOLANT SYSTEM LEAKAGE LEDGE DETECTION SYSTEMS LETTING CONDITION 'FOR 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required gaseous and/or particulate radioactivity monitoring channels are inoperable; otherwise, be in at least HOT STANDBY within the next 6

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

SURVEILLANCE RE UIREKNTS

'4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by:

a.

Containment atmosphere particulate and gaseous (if being used) monitoring system-performance of GAEL

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 CHANNEL CALIBRATION at least once per 18 months, c.

Containment humidity monitor (if being used) - performance of CHANNEL CALIBRATION at least once per 18 months.

DE C.

COOK >> UNIT 1

3/4 4-14 Anendment No.

60

0

. REFUELING OPERATIONS COOLANT CIRCULATION LIMITING CONDITION FOR OPERATION 3.9.8 At least one residual heat removal loop shall be in operation.

APPLICABILITY:

MODE 6.

ACTION:

a.

b.

c ~

With less than one residual heat removal loop in operation, except as provided in b. below, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System.

Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

The residual heat removal loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.8 A residual heat removal loop shall be determined to be in operation and circulating reactor c'oolant at a flow rate of > 3000 gpm at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D.

C.

COOK - UNIT 1

3/4 9-9 Amendment No. 60

REFUELING OPERATIONS CONTAIRKNT PURGE AND EXHAUST ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9. 9 The Containment Purge and Exhaust isolation sys tern shall be OPERABLE.

APPLICABILITY:

MODE 6 ~

ACTION:

With the Containment Purge and Exhaust isolation system inoperable, close each of the Purge and Exhaust penetrations providing direct access from the containment atmosphere to the outside atmosphere.

The provisions of Specification 3.0.3 are not applicab'e.

SURVEILIJDCE REQUIREMENTS 4.9. 9 The Containment Purge and Exhaust isolation system shall be demonstr ated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the star t of and a t lees t once p er 7

d ays during CORE ALTERATIONS by verifying that Containment Purge and Exhaust is'olation occurs on manual initiation and on a

high radiation signal from each of the Containment radiation instrumentation monitors.

D. C.

COOK, - UNIT 1 3/4 9

1O Amendment No

~ 60

~

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0

)t**g0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY E

DOCKET NO. 50-'316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

43 License No.

DPR-74 1.

The Nuclear Regulatory Commission

('the ComIission) has found that:

A.

B.

C.

D.

E, The application for amendment by Indiana and Michigan Electric Company (the licensee) dated August 20, 1982, 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; The issuance of this amendment will not be inimtcal to the common defense and security or to the health and safety of the public; and The issuance of this amendment is fn accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfjed,

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this 'license amendment, and paragr aph 2.C. (2) of Facility Operating License No. DPR-74 is hereby amended to read as follows:

(2)

Techni ca 1 S ecificat ions The Technical Specifications contained in Appendices A and B, as revised through Amendment No-43, are hereby incorporated in the license.

The licensee shall operate the faci lity in accordance with the Technical Specifications.

3.

This license amendment is effecti ve as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION steven A. Varga, Chief Operating Reactors Branch 41 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 9, 1982

e I

ATTACHMENT TO '

GENS E 'MENDMENT AMENDMENT NO.

43 TO FACI'LITY'PERATING LICENSE'NO. 'DPR-74 DOCKET'NO. 50-316 Revise Appendix A as follows:

Renove Pa es 3/4 3-17*

3/4 3-18

3/4 3-24 3/4 3-33*

3/4 3-34 3/4 3-35 3/4 3>>36 3/4 3-37 3/4 3-38*

3/4 4-13*

3/4 4-14 3/4 9-9 3/4 9-10*

Insert'Pa es 3/4 3-17+

3/4 3-18 3/4 3-24 3/4 3-33*

3/4 3-34 3/4 3-35 3/4 3-36

. 3/4 3-37 3/4 3-38*

3/4 4-13*

3/4 4-14 3/4 9-9 3/4 9-10*

• Included for convenience

CD TABLE 3.3-3 Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION n

CD CD 7C FUNCTIONAL UNIT 2.

CONTAINMENT SPRAY a.

Manual b.

Automatic Actuation Logic c.

Containment Pressure--

High-High TOTAL NO.

OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES 1, 2, 3, 4 1,.2,3,4 1, 2, 3

ACTION 18 13 16 This Technical Specification will not be effective until after the 1982 refueling outage.

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION A

OO pc I

FUNCTIONAL UNIT 3.

CONTAIAKNT ISOLATION a.

Phase "A" Isolation

1) Manual TOTAL NO.

OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES 1,2,3,4 ACTION 18

2) From Safety Injection Automatic Actuation Logic b

Phase "B"-Isolation 1,2,3,4 13 lA I

00 O

C ~

1) Manual

2) Automatic Actuation Logic

3) Containment Pressure-High-High Purge and Exhaust Isolation

1) Manual

2) Containment Radioactivity-High Train A

3) Containment Radioactivity-High Train B

2 1,2,3,4 172.374 1,2,3 172,3,4 1,2,3,4 1,2,3,4 18 13 16 17 17 17 This Technical Specification will not be effective until after the 1982 refueling outage,

0

TABLE 3.3-4 Con~Cloned EttGIttEERED SAFETY FEATURE ACTUATIOtt SYSTEM ItlSTRUMEHTATIOH TRIP SETPOItlTS FUNCT IOHAL UNIT 2..

CONTAIttHEtlT SPRAY a.

Manual Initiation b.

Automatic Actuation Logic c.

Containment Pressure ltigh-lligti 3.

CONTAINMEHT ISOLATIOtl a.

Phase "A" Isolation 1.

Manual 2.

From Safety In)ection Automatic Actuation logic b.

Phase "0" Isolation

~

TRIP SF.TPOINT'lot hppl icabl e ttot hppl i cable

< 2.9 psig Hot hppl icable Not Applicable ALLOklAOLE VALUES tlot hppl icable Hot Appl icable

< 3.0 psig Hot hppl Icabl e tlot hppl i cable 1.

Manual 2.

Automatic Actuation Logic Hot Applicable tlot Applicable 3.'ontainment Pressure--Ili gh-lligh

< 2.9 ps ig c.

Purge and Exhaust Isolation ttot Appl icable tlot hppli cable

< 3.0 psig 1.

Manual 2.

Containment Radioactivity

.,--Iligh Train A 3.

Containment Radioactivity Iligh Train B tlot Applicable

< 2 X normal channel reading

~ 2 x normal channei reading Hot hppl icabl e

< 2 x normal channel reading

~ 2 x normal channel reading This Technical Specification will not be effective until after the 1982 refueling outage.

TABLE 4. 3-2 Continued TABLE NOTATION (1)

Manual actuation switches shall be tested at least once per 18 months during shutdown.

All other circuitry associated with manual safe-guards actuation shall receive 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.

This Technical Specification will not be effective until after the 1982 refueling outage.

0.

C.

COOK - UNIT 2 3/4 3-33 Amendment No. 43

0

INSTRUMENTATION 3/4.3.3 MONITORING XNSTRUMENTATXON RADIATION MONITORING INSTRUMENTATION LYING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown Table 3.3-6 shall be OPERABLE stth thais alatelttlp setpeitts slthln the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTTON:

a.

With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3,3>>6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.

C ~

With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQVXHZK'AATS 4.3.3. 1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the, CHARNEL CHECK, CHANNEL CALIBRATION and CEQIAAEL FUNCTIONAL TEST operat" ons during the modes and at the frequencies shown in Table 4.3-3.

This Technical Specification will not be effective until after the 1982 refueling outage.

D. C. COOK~IT 2 3/4 3-34 Amendment No, 43

TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION OPERATION MODE/INSTRUMENT MINIMUMCHANNELS OPERABLE HIGH ALARM/TRIP SETPOINT MEASUREMENT RANGE ACTION 1.

MODES 1,2,3, 6

4 a ~

b.

AREA MONITOR

i. Upper Containment PROCESS MONITORS

i. Particulate ii. Noble Gas

-1 4

W2 x normal channel reading10 to 10 mR/hr 19 C

-4 x normal channel readingl.5x10 to 1.5 uCi

-7

-2 2 x normal channel

.reading 10 to 10 uCi/cc 0

2.

MODE 6 a.

TRAIN A

i. Containment Area Radiation Channel-VRS-1101 ii. Particulate Channel-ERS-1301 iii. Noble Gas Channel-ERS-1305 any 2/3 Channels

-1 4

~ x normal channel reading 10 to 10 mR/hr

<2 x normal channel reading 1.5xl0 to 1.5 uCi

-7

-2

<2 x normal channel leading 10 to 10

/

22 b.

TRAIN B

i. Containment Area Radiation Channel-VRS-1201 ii. Particulate Channel-ERS-1401 iii. Noble Gas Channel ERS-1405 any 2/3 Channels Same as 2.a

.Same as 2.a Same as 2.a Same as 2.a Same as 2.a Same as 2.a I

22 3

a.

Spent Fuel 'Storage

~15 mR/hr 10 to 10 mR/hr l 9

-1 4

" With fuel in storage pool or building.

This Technical Specification Mill not be effective.until after the 1982 refueling outage.

(

~

I TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 19 With the number of channels OPERABLE less than required by the Hinimum Channels Operable requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per day.

ACTION 20 - With the number of channels'PERABLE less than required by the Hinimum Channels Operable requirement, comply with the ACTION requirements of Specification 3,4.6.1.

ACTION 22 - With the number of channels OPERABLE less than required by the Hinimum Channels Operable requirement, comply with the ACTION requirements of Specification 3.9.9., This ACTION is not required during the performance of containment integrated leak rate test, I

This Technical Specification will not be effective until after the 1982 refueling outage.

C D. C.

COOK - UNIT 2 3/4 3-36 amendment No. Q

TABLE 4.3-3 n

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS nOO I

OPERATING MODE/INSTRUMENT 1.

MODES 1, 2, 3,

& 4 a.

AREA MO.'R ITOR

i. Upper Containment b.

PROCESS MONITORS

i. Particulate ii. Noble Gas CHANNEL CHANNEL CHECK CALIBRATION R

R CHANNEL FUNCTIONAL TEST M

M MODES FOR WHICH SURVEILLANCE IS RE 0IRED 1,2,3&4 1, 2, 3

& 4 1, 2, 3

& 4 2.

MODE 6 I

a.

TRAIN A

i. Containment Area Radiation Channel ii. Particulate Channel iii. Noble Gas Channel S

S S

R R

R M

M M

6 6

6 b.

TRAIN B

i. Containment Area Radiation Channel ii. Particulate Channel iii. Noble Gas Channel R

R R

M M

M 0'

III a.

SPENT FLEL STORAGE

• With fuel in the storage pool or building.

l"is lechnical Specification will not be effective until after the 1982 refueling outage.

y'

~

~

"C, INSTRUMENTATION I

MOVABLE INCORE DETECTORS LIMIrING CONDITION FOR OPERATION 3.3.3.2 The movable incore detection system shall be OPERABLE with:

a.

At least 75! of the detector thimbles, b.

A minimum of 2 detector thimbles per core quadrant, and c.

Sufficient movable detectors, drive, and readout equipment to map these thimbles.

APPLICABILITY: When the movable incore detection system is used for:

a.

Recalibration of the excore neutron flux detection

system, b.

c ~

CTION:

Monitoring the QUADRANT POWER TILT RATIO, or Measurement of F H, F~(Z) and F

N xy ith the movable incore detection system inoperable, do not use the system or the above applicable monitoring or calibration functions.

The provisions f Specifications 3.0.3 and 3.0. 4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.2 The movable incore detection system shall be demonstrated OPERABLE by normalizing each detector output when required for:

b.

c ~

Recalibration of the excore neutron flux detection

system, or Monitoring the QUADRANT POWER TILT'RATIO, or Measurement of F<H, F~(Z), and F

N xy'his Technical Specification will not be effective until after the 1982 refueling outage.

0.

C.

COOK - UNIT 2 3/4 3-38

CDO A

TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION O

1ST SAMPLE INSPECTION 2NO SAMPLE INSPECTION 3RD SAMPLE INSPECTION Sample Size Result Action Required Result Action Required Result Action Required O

ID Cl CDO C+

Me CD A minimum of S Tubes per S. G.

C-1 C-2 C-3 None Plug defective tubes and inspect additional 2S tubes in this S. G.

Inspect all tubes in this S. G., plug de fective tubes and inspect 2S tubes in each other S. G.

Prompt notification to NRC pursuant to specification 6.9.1 N/A C-I C-2 C-3 AII other S. G.s are C-I Some S. G.s C-2 but no additional S. G. are C-3 Additional S. G. is C-3 N/A None Plug defective tubes and inspect additional 4S tubes in this S. G.

Perform action for C-3 result of first sample None Perform action for C-2 result of second sample Inspect all tubes in each S. G. and plug defective tubes..

Prompt notification to NRC pursuant to specification G.9.1 N/A N/A C-I C-2 C-3 N/A N/A N/A N/A N/A Wone N/A N/A N/A N/A N/A

'Plug defective tubes Perform action for C-3 result of first sample O

c+

CD 3

g Where N is the number of steam generators in the unit, and n is the number of steam generators inspected during an inspection

)

~

g ~ ~

~

1N 1

REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT. SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4,6.1 The following Reactor Coolant System leakage detection systems shall be OPERABLE:

I 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.

AC1 ION:

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required gaseous and/or particulate radioactivity monitoring channels are inoperable; otherwise, be in at least HOT STANDBY within the next 6

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

SURVEILLANCE REQUIREMENTS 4.4.6.1 The leakage detection systems shall be demonstrated OPER&LE by:

a.

Containment atmosphere particulate and gaseous (if being used) monitoring system-perf ormance of CHANNEL

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

Containment sump level and flow monitoring system-performance of CHA1THEL CALIBRATION at least once per 18 months, c.

Containment humidity monitor (if being used) - performance of CHANNEL CALIBRATION at least once per 18 months.

This Technical Specification wil] not be effective until after the 1982 refueling outage.

D. C.

COOK - UNIT 2 3/4 4-14 Amendment No.

43

~

~ s i 4 C

I

REFUELING OPERATIONS CONTAIN1KNT PURGE AND EXHAUST ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9. 9 The Containment Purge and Exhaust isolation system shall be OPERABLE.

APPLICABILITY:

MODE 6.

ACTION:

With the Containment Purge and Exhaus t isolation sys tern inoperable, close each of the Purge and Exhaust penetrations providing direct access from the containment atmosphere to the outside atmosphere.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE(}UIREMENTS 4.9.9 The Containment Purge and Exhaust isolation system shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7

days during CORE ALTERATIONS by verifying that Containment Purge and Exhaust isolation occurs on manual initiation and on a

high radiation signal from each of the Containment radiation instrumentation monitors.

This Technical Specification wi11 not be effective until after the 1982 refueling outage, D. C.

COOK - UNIT 2 3/4 9-9 Amendment No.

43

REFUELING OPERATIONS MATER LEVEL - REACTOR VESSEL LIMITING CONDITION FOR OPERATION 3.9.10 At least, 23 feet of water shall be maintained over the top of irradiated fuel assemblies seated within the reactor pressure vessel.

APPLICABILITY: During movement of fuel assemblies or control rods within

~p h

0 ACTION:

Mith the requirements of the above specification not satisfied, suspend all operations involving movement of fuel assemblies or control rods within the pressure vessel.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREHENTS 4.9.10 The water level shall be determined to be at least its minimum required depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during movement of fuel assemblies or control rods.

This Technical Specification will not be effective until after the 1982 refueling outage.

C.

COOK - UNIT 2 3/4 9-10 Amendment No.

43