ML17321A914

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Proposed Tech Specs,Changing Tables 3.3-11,4.3-7,3.3-10 & 4.3-10 Re Vessel Level Instrumentation Sys & Core Exit Thermocouples.Related Info Encl
ML17321A914
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 10/11/1985
From:
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17321A913 List:
References
NUDOCS 8510160167
Download: ML17321A914 (18)


Text

ATTACHMENT 2 TO AEP:NRC:0856J PROPOSED CHANGES TO THE DONALD C.

COOK NUCLEAR PLANT UNIT NOS.

1 AND 2 TECHNICAL SPECIFICATIONS 8gfQfQPfb7, 8 ppgf P'pgp,,

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TABLE 3.3-11 POST-ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUMCHANNELS OPERABLE 1.

Containment Pressure 2 ~

3.

4 Reactor Coolant Outlet Temperature T

(Wide Range)

Reactor Coolant Inlet Temperature T

(Wide Range)

Reactor Coolant Pressure Wide Range 5.

Pressurizer Water Level 6.

Steam Line Pressure 7.

Steam Generator Water Level Narrow Range 8.

Refueling Water Storage Tank Water Level 9.

Boric Acid Tank Solution Level 10.

Auxiliary Feedwater Flow Rate 11.

Reactor Coolant System Subcooling Margin Monitor 12.

PORV Position Indicator Limit Switches***

13.

PORV Block Valve Position Indicator Limit Switches 14.

Safety Valve Position Indicator Acoustic Monitor 15.

Incore Thermocouples (Core Exit Thermocouples) 16.

Reactor Coolant Inventory Tracking System (Reactor Vessel Level Indication) 2/Steam Generator 1/Steam Generator 1/Steam Generator*

1/Valve 1/Valve 1/Valve 2/Core Quadrant One Train (3 channels/Train)

Steam Generator Water Level Channels can be used as a substitute for the corresponding auxiliary feedwater flow rate channel instrument.

PRODAC 250 subcooling margin readout can be used as a substitute for the subcooling monitor instrument.

      • Acoustic monitoring of PORV position (1 channel per three valves headered discharge) can be used as a substitute for the PORV Indicator Limit Switches instruments.

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1.

Containment Pressure 2.

Reactor Coolant Outlet, Temperature = T (Wide Range)

Reactor Coolant Inlet Temperature <<T (Wide Range)

Reactor Coolant Pressure - Wide Range Pressurizer Water Level 3.

4.

5.

6.

Steam Line Pressure 7.

Steam Generator Water Level, Narrow Range 8.

RWST Water Level

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Boric Acid Tank Solution Level 10.

Auxiliary Feedwater Flow Rate 11.

Reactor Coolant System Subcooling Margin Monitor 12.

PORV Position Indicator Limit Switches 13.

PORV Block Valve Position Indicator Limit Switches CHANNEL CHECK CHANNEL CALIBRATION 0

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Safety Valve Position Indicator Acoustic Monitor 15.

Incore Thermocouples (Core Exit Thermocouples) 16.

Reactor Coolant Inventory Tracking System (Reactor Vessel Level Indication)

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(1) Partial range channel calibration for sensor to be performed below P-12 in MODE 3.

R(1)

R(3)

(2) With one train of Reactor Vessel Level Indication irioperable, Subcooling Margin Indication and Core Exit Thermocouples may be used to perform a CHANNEL CHECK to verify the remaining Reactor Vessel Indication train OPERABLE.

(3) Completion of channel calibration for sensors to be performed below P-12 in MODE 3.

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TABLE 3.3-10 POST-ACCIDENT MONITORING INSTRUMENTATION o+

INSTRUMENT 0

I 1.

Containment Pressure 2 ~

3 Reactor Coolant Outlet Temperature T

(Wide Range)

Reactor Coolant Inlet Temperature - T (Wide Range)

Reactor Coolant Pressure Wide Range 4 ~

5.

Pressurizer Water Level, 6.

Steam Line Pressure 7.

Steam Generator Water Level Narrow Range 8.

Refueling Water Storage Tank Water Level 9.

Boric Acid Tank Solution Level 10.

Auxiliary Feedwater Flow Rate 14.

Safety Valve Position Indi:cator-- Acoustic Monitor 15.

Incore Thermocouples (Core Exit'Thermocouples) 16.

Reactor Coolant Inventory Tracking System (Reactor Vessel Level Indication) 11.

Reactor Coolant System Subcooling Margin Monitor 12.

PORV Position Indicator Limit Switches***

13.

PORV Block Valve Position Indicator Limit Switches MINIMUM CHANNELS OPERABLE 2/Steam Generator 1/Steam Generator 1/Steam Generator*

1/Valve 1/Valve 1/Valve

, 2/Core Quadrant One Train (3 channels/Train)

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Steam Generator Water Level Channels can be used as a substitute for the corresponding auxiliary feedwater flow rate channel instrument.

PRODAC 250 subcooling margin readout can be used as a substitute for the subcooling monitor instrument.

      • Acoustic monitoring of PORV position (1 channel per three valves headered discharge) can be used as a substitute for the PORV Indicator Limit Switches instruments.

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TABLE 4.3-10 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT CHANNEL CHECK CHANNEL CALIBRATION 1.

Containment Pressure 2.

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Reactor Coolant Outlet Temperature - T (Wide Range)

Reactor Coolant Inlet Temperature T

(Wide Range)

Reactor Coolant Pressure Wide Range 5.

Pressurizer Water Level 6.

Steam Line Pressure 7.

Steam Generator Water Level Narrow Range 8.

RWST Water Level 9.

Boric Acid Tank Solution Level 10.

Auxiliary Feedwater Plow Rate 11.

Reactor Coolant System Subcooling Margin Monitor 12.

PORV Position Indicator Limit Switches 13.

PORV Block Valve Position Indicator Limit Switches 14.

Safety Valve Position Indicator Acoustic Monitor 15.

Incore Thermocouples (Core Exit Thermocouples) 16.

Reactor Coolant Inventory Tracking System (Reactor Vessel Level Indication)

M(2)

R(1)

R(3)

(1) Partial range channel calibration for sensor to be performed below P-12 in MODE 3.

(2) With one train of Reactor Vessel Level Indication inoperable, Subcooling Margin Indication and Core Exit Thermocouples may be used to perform a CHANNEL CHECK to verify the remaining Reactor Vessel Indication train OPERABLE.

(3) Completion of channel calibration for sensors to be performed below P-12 in MODE 3.

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ATTACHMENT 3 TO AEP:NRC:0856J INFORMATION PROVIDED BY WESTINGHOUSE ELECTRIC CORPORATION REGARDING PROPOSED CHANGES TO THE DONALD C.

COOK NUCLEAR PLANT UNIT NOS.

1 AND 2 TECHNICAL SPECIFICATIONS

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Westinghouse Water Reactor Electric Corporation Divisions HUCLELR OPS. DIVISION

'"'><co'85 Reed:

Resp.

AttI Person:

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ee:.g'Q.Xe Cire l/~(5 d.. WAN czerk:

. /Eel Box 355 Pinsburgh Pennsylvania 15230 0355

,cPCZ+C AEP-85-783 August 12, 1985 NS-OH.S-OFL-85-367 Mr.

M.

P. Alexich, Vice President and Director Nuclear Operations American Electric Power Service Corporation One Riverside Plaza

Colunbus, Ohio 43216 Attention: Mr. A. B. Auvil AMERICAN ELECTRIC POWER SERVICE CORPORATION D.

C.

COOK UNIT 162

Dear Mr. Alexich:

The attached docunent provides the information requested during the July 25, 1985 conference call and noted in your letter AWS-237, dated July 31, 1985.

Please call with any coments or questions.

LVT/lsv Very truly yours, (7

A. P.

Suda, Manager Great Lakes Area Projects Department cc: M.

J.

V.

J.

S.

D.

J.

R.

W.

B.

M.

P. Alexich G. Feinstein VanderBurg Markowsky H. Steinhart R. Hafer R.

Jensen W. Jurgensen G. Smith Svensson J. Parvin, 9

4 Attached for your information are recommended technical specification modified tables to reflect the above stated guidance.

These include Table 3.3-11, "Post-Accident Honitoring Instrumentation,"

and Table 4.3-7, "Post Accident Honitoring Instrumentation Surveillance Reuqirements."

0361G:ll/GEL/885

0 TABLE 3.3-11 POST-ACCIDENT flONITORItlG ItlSTI'UHENTATIOtt INSTRUMENT 1.

Containment Pressure 2.

Reactor Coolant Outlet Temperature - THOT (Wide Range) 3.

Reactor Coolant Inlet Temperature - TCOLD (Wic'e Range) 4.

Reactor Coolant Pressure - Wide Range 5.

Pressurizer Water Level 6.

Steam Line Pressure 7.

Steam Generator Mater Level - Narrow Range 8.

Refueling Water Storage Tank Water Level 9.

Doric Acid Tank Solution Level 10.

Auxiliary Feedwater Flow Rate 11.

Reactor Coolant System Subcooling llarqin tloni tor 12.

PORV Position Indicator - Limit SvIitches~"*

13.

PORV Block Valve Position indicator - Limit S;(itches 14.

Safety Valve Position Indicator - Acoustic l1oaitor LS. 5e<<gr yes J Lcyck 7-<(~% on

'Steam Generator Water Level Channels can be used as a substitute fcedwater flow rate channel instrument.

    • PRODAC 250 subcooling margin readout can be us>.3 as a substitute ins trument.

~'*Acoustic monitoring of PORV position (1 channel per three valves as a substitute for the PORV Position Indicator - Limit Switches MltlltlUl'ICIIAtitlELS OPERABLE' 2/Steam Gen rator 1/Steam Generator 2

1/Steam Generator*

1**

1/Valve 1/Valve 1/Valve

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fTv%%'A (

for the correspondir.g aux liary for th sub ooling monitor

- headered discharge) can be used instr nents.

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nnn I flSTPtl!IEllT POS'I'-ACCIOENT l1ptIITORING It!STRIIiII'IITATIOtfSURVEILLANCE RE UIREHEtITS CIIAI:IlCL CIIKll CIIA/INEL C)rL I DiZATI O'I 4J I

C J1 Os IJl CL I'3 D

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C 1.

Co>>tainment Pressure 2.

Ite,ictor Coolant Oiitlet Tcrirperature - TI.OT (Itide Range) liOT 3.

Ite)ctor Coolarit Inlet Temperature - TCOIO (Wide itange)

Itr..'rctor Coolant I'r'essure - Wide Range S.

I'i essurizer lla ter Level 6

St eli'I L I rli.'

i essrll'e 7.

Sti.am Gcr'.er ator 1'at. r Level - ttar'row Range 0.

IIWSI lla ter Level 9.

Log ic Ac id Tairl: Solu t ion, Level 10.

Au:ciliary Feedrr,r ter Florr Rate 11.

Iteactor Coolant Syste;n SvLcool ing Margin Honitor 12.

I'ORV I'ositinn Iriilic.itor - Limit S'rite!res 13.

I'OllV Block Valve Posit.io>> I>>dicat.or - Limit S:vt.ches II.

'; ilety V)lve I'ositi.in 1>>rlicator - Acoustic!loni.or 15.

Rema VeeaeL LeveL Indication R

SubcooLing bhaga Indication and Coze E~ TherrrrrocoupLes may be auQCitated (oh. Ae ~pose o$

CHAMNEL CHECK Jour. Ae OPERA8LE channeL o$ Rea~z VmdeL LeveL Tndicr~n.

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