ML17331B234

Proposed Tech Specs 3/4.3.4 Re Turbine Overspeed Protection Requirements

ML17331B234
Person / Time
Site:	Cook
Issue date:	02/15/1994
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17331B233	List: ML17331B232 ML17331B234
References
NUDOCS 9402240308
Download: ML17331B234 (12)

Text

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION 'PAGE 3/4. 2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE......'..."."------."...- "... 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR............................ 3/4 2-5 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR... . . ... ...-.-.- 3/4 2-9 3/4.2.4 QUADRANT POWER TILT RATIO............................... 3/4 2-13 3/4.2.5 DNB PARAMETERS MO DE 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ e ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 2-15 MO DES 2, 3, 4 and 5..................................... 3/4 2-17 3/4.2.6 ALLOWABLE POWER LEVEL................................... 3/4 2-19 I

3/4. 3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION................... - ~ 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION............. .... ..................... 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation.................... 3/4 3-34 Movable Incore Detectors.... 3/4 3-38 Seismic Instrumentation...........-.....-.---....... " .. 3/4 3-38a I Meteorological Instrumentation.......-.................. 3/4 3-39 Remote Shutdown Instrumentation...................-..- ~ ~ 3/4 3-42 Fire Detection Instrumentation. 3/4 3-46 Post-Accident Instrumentation.... .-- ~ ~ ~ ~ " ~ ~ ~ ~ ~ " -- -~ ~ ~ ~ 3/4 3-50 Radioactive Liquid Effluent Instrumentation......... 3/4 3-53 Radioactive Gaseous Process and Effluent Monitoring Instrumentation............ 3/4 3-62 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation............................. 3/4 4-1 D.C. COOK - UNIT 2 Amendment Ho. pj, 1O2 9402240308 'F40215 PDR ADDCK 050003l6 PDR

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 0 1 3/4.1.1 BORATION CONTROL ...........--................. - ~ ~ ~ ~ ~ B 3/4 1-1 3/4.1.2 BORATION SYSTEMS B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES B 3/4 1-4 4

3/4.2.1 AXIAL FLUX DIFFERENCE ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT ADiNNEL FACTOR AND NUCLEAR EÃHBQ.PY HOT CHANNEL FACTOR ......... ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 2-4 3/4.2.4 QUADRANT POWER TILT RATIO ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ B 3/4 2-5 3/4.2.5 DNB PLQQMETERS e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 2-5 3/4.2.6 ALLOVABLE POWER LEVEL ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 2-5 4

3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURE INSTRUMENTATION B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION B 3/4 3-la 4 4 0 C 0 3/4.4.1 . REACTOR COOLOT LOOPS B 3/4 4-1 3/4.4.2 and 3/4.4.3 SAFETY VALVES B 3/4 4-2.

3.4.4.4 P RESSURIZER ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ B 3/4 4-2 3/4.4. 5 STEAM GENERATOR TUBE INTEGRITY....................... B 3/4 4-24 3/4.4.6 REACTOR COOIANT SYSTEM LEAKAGE ...................... B 3/4 4-3 3.4.4.7 CHEMISTRY ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 4-4 3/4t4 8~ SPECIFIC ACTIVITY ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ B 3/4 4-5 COOK NUCLEAR PLANT - UNIT 2 XII AMENDMENT NO. W, ~ 142

I N STi? Ui"ENTAT ON 3 . 3.4 TURBINE OYEPSPEED?ROTECTION LIMIT.RG CONOITION FOR OPERATION 3.3.4.1 t least one turbine overspeed protection sys em halI be OPEUBLE APPLIC"BILIT HOOES 1, 2 and 3.

ACT! GN:

a. Mith on stop valve or one control valv per high pressure turbine s earn lead inoperable or with ne reheat stop valve or one reheat intercept valve per low p essure turbine steam lead.

inoperable, operation may continue or up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided the inoperab valve(s) is restor to OPERABLE status or at least one val in he af ected team lead is closed; otherwise, isolate the tu ine from the s am supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. Kith the above re . ired turb'ne overspeed pro-.ec 'on system otherwise i perabl , within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either restore the system to OPEP~ E s . us or isolate the turLine from the steam supply.

SUR'lEILLANCE RLOUIREMENTS 4.3.4.1.1 The provisions o Speci ic tion 4.0.'4 a'e not applicable.

l 4.3.4.1'.2 The above req red turbine o rspeed pro. ection svs em shall be dmonstrat d OPEPABLE:

a. At least o e per 7 days by cycli each of the following valves th ugh a. least one comple cycle from the running PQSltlOn

l. 4 ur high pressure turbine stop v ives.

2. Four high pressure turbine con rol ives.

Six low pressure turbine reheat s op v ives.

4. Six low pressure turbine ret'.e'at in ercep valves.

0. C. COOK - UN.'T 2 3/4 3-oo N ienwmefl l, .s~ I

At lees. once 31 "ays by dire observa .ion of tie move-ment of each of : . a"ove valve through ore complete cycle from the runnina position.

c~ At least once per 18 mc hs pericr..ance of a C:-All IcL CAI.I:R~T:0."I on the t ne ove "eed proto t on syst ..s.

d. 4t least once p . <0 months by di sass 'bl inc at lees. one of each of the ove valves and performina visual and surface inspection f valve seats, disks and s:ems d verifying no uracc p le flaws or corrosion.

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3 4. 3 INSTRUMENTATION BASES 3/4.3.3.M RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive effluent gaseous instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents dux'ing actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance vith NRC approved methods in the OCDN to ensure that the alarm/trip vill occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions fox monitox'ing the concentrations of potentially explosive gas mixtures in the vaste gas holdup system. The OPERABILITY and use of this instxumentation is consistent vith the requirements of Genex'al Design Criteria specified in Section 11.3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.

3/ . . TURBINE OVERSPEED PROTECTION This specification x vided to ensure that turbine overspeed protection instrumentation a e turb speed control valves are OPERABLE and vill protect the tu m excessive overspeed.

Protection from turbine e sive overspee uired since excessive overspeed of the t e could generate potentially ing missiles vhich could act and damage safety related components, eq t or stru es.

COOK NJCL~ P<T - UNIT 2 B 3/4 3'-4 ANENDMENT NO. 115

Attachment 3 to AEP:NRC:1168A PROPOSED REVISED TECHNICAL SPECIFICATION PAGES

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION gAAG 3 4 2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR 3/4 2-5 3/4.2.3 NUCLEAR EPQQQZY HOT CHANNEL FACTOR 3/4 2-9 3/4.2.4 qUADRANT POWER TILT RATIO 3/4 2-13 3/4.2.5 DNB PARAMETERS MODE 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

' ~ ~ ~ ~ 3/4 2-15 MODES 2, 3, 4 and 5 3/4 2-17 3/4.2.6 ALLOWABLE POWER LEVEL 3/4 2-19 3 4 3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION .................... 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation .................. 3/4 3-34 Movable Incore Detectors 3/4 3-38 Seismic Instrumentation ........ 3/4 3-38a Meteorological Instrumentation ........................ 3/4 3-39 Remote Shutdown Instrumentation 3/4 3-42 Fire Detection Instrumentation ........................ 3/4 3-45

'Post-Accident Instrumentation . 3/4 3-50 Radioactive Liquid Effluent Instrumentation............ 3/4 3-53 Radioactive Gaseous Process and Effluent Monitoring Instrumentation.. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 3-62 3 4 4 REACTOR COOLANT SYST 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation ...... ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 4 1 COOK NUCLEAR PLANT - UNIT 2 AMENDMENT NO. M, 402

INDEX BASES SECTION PAGE 3 4 0 PPLICABILITY . . ................................. B 3/4 0-1 3 4 1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL ..................................... B 3/4 1-1 3/4.1.2 BORATION SYSTEMS .................. ................. B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES ........................... B 3/4 1-4 3 4 2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY HOT CHANNEL FACTOR B 3/4 2-4 3/4.2.4 QUADRANT POWER TILT RATIO B 3/4 2-5 3/4.2.5 DNB PARAMETERS B 3/4 2-5 3/4.2.6 ALLOWABLE POWER LEVEL B 3/4'-5 3 4 3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURE INSTRUMENTATION .............................. B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION B 3/4 3-la 3 4 4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS B 3/4 4-1' 3/4.4.2 and 3/4.4.3 SAFETY VALVES 3/4 4-2 3.4.4.4 PRESSURIZER B 3/4 4-2 3/4.4.5 STEAM GENERATOR TUBE INTEGRITY B 3/4 4-2a 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE B 3/4 4-3 3.4.4.7 CHEMISTRY B 3/4 4-4 3/4.4.8 SPECIFIC ACTIVITY B 3/4 4-5 COOK NUCLEAR PLANT - UNIT 2 XII AMENDMENT NO. QO, 407, 442

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3 4 3 INSTRUMENTATION BASES 3/4.3.3.10 RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive effluent gaseous instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria specified in Section 11.3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.

COOK NUCLEAR PLANT - UNIT 2 B 3/4 3-4 AMENDMENT NO.

Attachment 4 to AEP:NRC:1168A COOK NUCLEAR PLANT COST BENEFICIAL LICENSING ACTION DELETE UNIT 2 TURBINE OVERSPEED PROTECTION SYSTEM T/S to AEP:NRC:1168A Page 1 Delete Unit 2 Turbine Overs eed Protection S stem T S Re ulato Re uirement:

Cook Nuclear Plant Unit 2 Technical Specifications 3/4.3.4 requires that turbine overspeed protection valve testing be performed every 7 days, and a number of other detailed requirements, to assure that the Unit 2 turbine overspeed protection system is operable.

Effect of Re uirement:

There is a significant potential for the action item in T/S 3/4,3,4 to lead to a unit shut down. Also, the 7 day test frequency creates a constraint for mode changes, which increases outage critical path time.

ationale for Re lato Chan e:

Deleting this requirement will make the Unit 2 T/S consistent with the new standard T/S, and with the Unit 1 T/S. These requirements are unique to Unit 2.

A roximate Cost of Re uirement:

The requirement adds about 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> to critical path to each outage, because it does not permit a change from mode 4 to mode 3. At $ 250,000 per day for replacement power, 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> per outage, and approximately 11.5 outages remaining for Unit 2, the plant lifetime cost savings from eliminating this requirement is approximately $ 1,800,000.

Identification:

AEPSC initiated CBLA effort.

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