ML20082M801

Proposed Tech Specs,Relocating Requirements for Turbine Overspeed Protection Instrumentation to Selected Licensee Commitment Manual

ML20082M801
Person / Time
Site:	Mcguire, Catawba, McGuire
Issue date:	04/12/1995
From:	DUKE POWER CO.
To:
Shared Package
ML20082M795	List: ML20082M792 ML20082M801
References
NUDOCS 9504240380
Download: ML20082M801 (16)

Text

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NITACIIMENT 4a PROPOSED TECIINICAL SPECIFICATION AMENDMENTS FOR CATAWBA I

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9504240380 DR 950412 ADOCK 05000369 PDR I

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lIMITiNGCONDITIONSFOROPERATIONANDSURVEILLANCEREQUIREM __-

SECTION PAGE TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION............. 3/4 3-60  ;

TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLAN '

REQUIREMENTS.......................................... 3/4 3-61 ,

Remote Shutdown System................................... 3/4 3-62 TABLE 3.3-9 REMOTE SHUTDOWN SNITORING INSTRUMENTATION............ 3/4 3-63 TABLE 4.3-6 REMOTE SHUTD00 MONIlGRING INSTRUMENTAT SURVEILLANCE REQUIREMENTS................. ...............ION 3/4 3-64 Accident Monitoring Instrunentation...................... 3/4 3-65 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION.................. 3/4 3-66 TABLE 4.3-7 ACCIDENT MONITORING INSTRUM REQUIREMENTS....:.............ENTATIONSURVEILLANCE

........................... 3/4 3-68 Chl o ri ne Detection Systems. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3/4 3-70 TABLE 3.3-11,(Deleted)

Loose-Part Detection System..............................

3/4 3-79 Explosive Gas Monitoring Instrumentation................. 3/4 3-80 P TABLE 3.3-12 EXPLOSIVE GAS MONITORING INSTRUMENTATION............. 3/4 3-81 TABLE 4.3-8 EXPLOSIVE GAS MONITORING INSTRUMENTAT /

SURVEILLANCE REQUIREMENTS................ ................ION 3/4 3-83 /

Boron Dilution Mitigation System................... >

3/4 3-85 t 3/4.3.4 TURBINE OVERSFEEL FRGiECiiGN....R . M ............ 3/4 .....3-87 lk 3/4.4 REACTOR COOLANT SYSTEM '

3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation..............................

3/4 4-1  !

Hot Standby.............................................. 3/4 4-2 Hot l Shutdown............................................. 3/4 4-3 Cold Shutdown - Loops F111ed............................. 3/4 4-5 Cold Shutdown - Loops Not Ft11ed......................... 3/4 4-6 CATAWBA - UNITS 1 & 2 VI Amendment No. (Unit 1)

Amendment No. (Unit 2) v----e , - . .c.,

-.- . - n .-m,m~ - - ~. -- - - - - - - - - - - - -

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I BASES  !

i SECTION

_PAGE i 3/4.0 APPLICABILITY............................................... B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTR0L.......................................... B 3/4 1-1 3/4.1.2 B0 RATION i SYSTEMS.......................................... B 3/4 1-2 i 3/4.1.3 MOVABLE CONTROL ASSEMBLIES................................ B 3/4 1-3 i

i 3/4.2 POWER DISTRIBUTION LIMITS (Unit  !

1)......... ................ B 3/4 2-1 3/4.2.1 AXIAL FLUX DIFFERENCE (Unit 1)............................ B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND HUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR 1).................

(Unit B 3/4 2-1 3/4.2.4 QUADRANT POWER TILT RATIO (Unit 1)........................ B 3/4 2-3 I 3/4.2.5 DNB PARAMETERS (Uni t 1) . . . . . . . . . . . . . . . . . . . . . . .B. 3/4

. . .2-3

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3/4.2 2)........................

l POWER DISTRIBUTION LIMITS (UNIT '

B 3/4 2-5 3/4.2.1 AXIAL FLUX DIFFERENCE (Unit 2)............................ B 3/4 2-5 i

3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR, and REACTOR COOLANT SYSTEM FLOW RATE AND NUCLEAR ENTH RISE HOT CHANNEL FACTOR,(Unit 2).................ALPY......... B 3/4 2-7 3/4.2.4 QUADRANT POWER TILT RATIO (Unit 2)........................ B 3/4 2-9 i 3/4.2.5 1

DNB PARAMETERS (Uni t 2). . . . . . . . . . . . . . . . . . . . . . . . B

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. . .2-10 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION............... B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION................................ B 3/4 3-3 3/4.3.4 -TURcINEOVER;PEEDPROTECTION..Ikfr. tea.....................

B 3/4 3-7 l ,

CATAWBA - UNITS 1 & 2 XII t Amendment No.1 (Unit 1) I Amendment No. (Unit 2) '

INSTRUMENTATION 3/4.3.4 =T"ROINE OVERSPEED PROTECTIO"De.(c.te LIMITING CONDITION FOR OPERATION 3.3.4 At least one Turbine Overspeed Protection System shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTI -

a.

With one stop valve or one control valve per high pressure rbine i(eam line inoperable and/or with one intermediate stop y e or one ntqrcept valve per low pressure turbine steam line inop able, restb e the inoperable valve (s) to OPERABLE status wit n 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or clo the turb ate least one valve in the affected steam li (s) or isolate from the steam supply within the next 6 ours.

b.

With the ab e required Turbine Overspeed Prote ion System otherwise inoperable, w hin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine rom the steam supply.

SURVEILLANCE REQUIREMENTS 4.3.4.1 The provisions of Spec 1 tion 4.0. are not applicable.

4.3.4.2 The above required Turbine 0 demonstrated OPERABLE: rsp d Protection System shall be a.

At least once per 7 days w

• e in ODE 1 and while in MODE 2 with the turbine operating, by yeling e h of the following valves through at least one to lete cycle m the running position:

1) Four high press e turbine stop val s, 2)

3) Six low press e turbine intermediate top valves, and Six low pre ure turbine intercept valv .

b. At least once er 31 da the turbine perating, ys bywhile directinobservation MODE 1 and of wh th le in MODE 2 with each of t movement of valves, above valves and the four high pressure urbine control rough one complete cycle from the running p ition,

c. At 1 on st once per 18 months by performance of a CHANNEL IBRATION e Turbine Overspeed Protection Systems,* and d.

t least once per 40 months by disassembling at least one of e h of the above valves (including the four high pressure turbine contr valves) and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion.

This surveillance need not be performed until prior to entering HOT STANDBY following the Unit 1 first refueling. (This applies to Unit 1 only.)

CATAWBA - UNITS 1 & 2 \

3/4 3-87 AmendmentNo.t b Unit 1)

(Unit 2)

Amendment 110.  % l

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INSTRUMENTATION i BASES .

3/4.3.3.11 BORON DILUTION MITIGATION SYSTEM

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The operability of the Boron Oilution Mitigation System ensures that pro-tection sent. against a loss of shutdown margin from a boron dilution event is pre-This system multiplication of theuses two source reactor core. range detectors to monitor the subcritical An alarm setpoint is continually calcu-lated as 4 times the lowest measured count rate, including compensation for background and the statistical variation in the count rate. Once the alarm setpoint is exceeded, each train of the Boron Dilution Mitigation System will automatically shut off both Reactor Makeup Water Pumps, isolate flow to the charging pumps from the Volume Control Tank, and align the suction of the charging pumps to highly borated water from the RWST. l These actions automa-tically isolate the potential sources of diluted water and allow injection of highly borated water into the Reactor Coolant System.

In the event that the Boron Dilution Mitigation System is inoperable or not operating, the Source Range Neutron Flux Monitors may be used to provide protection against a loss of shutdown margin from a boron dilution event. If the Source Range Neutron Flux Monitors are used to monitor the subcritical i multiplication of the reactor core, the alarm setpoint must be calibrated and i periodically above checked tocount the steady-state ensure that it is less than or equal to one-half decade rate.

up Water Pumps must be verified as below specified limits.In addition, the flow from t These actions ensure '

that adequate time is available for the operator to recognize and terminate a dilution event prior to a loss of shutdown margin.

3/4.3.4 -T"ROI"E 0"CRSPEE0 PROTECTIO" pdetel ThisJ ecification is provided to ensure that the turbine av protection ins .

tat Q and the turbine speed cont and will protect the turbine essi ve s are OPERABLE eed. Protection from turbine excessive overspeed is requ yir generate potentila ly-damagTng missiles which could imexcessive_overspeed damage of the turbine t

safety rM et Ccomponents, equipment, or structures.

t CATAWBA - UNITS 1 & 2 B 3/4 3-7 Amendment No\Unit 1)

Amendment No. Unit 2)

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l ATTACIIMENT 4b PROPOSED TECIINICAL SPECIFICATION AMENDMENTS FOR MCGUIRE I

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'INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE.REOUIREMENTS SECTION PAGE TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.......................... 3/4 3-54 Accident Monitoring Instrumentation....................... 3/4 3-55 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION.................. 3/4 3-56 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION.

SURVEILLANCE REQUIREMENTS.......................... 3/4 3-57 Explosive Gas Monitoring Instrumentation.................. 3/4.3-71 TABLE 3.3-13 EXPLOSIVE GAS MONITORING INSTRUMENTATION............. 3/4 3-72 TABLE 4.3-9 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.......................... 3/4 3-75 .

Loose-Part Detection System .............................. 3/4 3-78 3/4.3.4 TuRcIN: cv:RSrt:0 PROT::TIcu. .t?;kd7.4. . . . . . . . . . . . . . . . . . . . 3/4 3-79

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3/4.4 REACTOR C00LANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation.............................. 3/4 4-1 Hot Standby.............................................. 3/4 4-2 Hot Shutdown............................................. 3/4 4-3 Cold Shutdown - Loops Fi11ed............................. 3/4 4-5 McGUIRE - UNITS 1 and 2 VIII Amendment No. [(Unit 1)  %

Amendment No.1 (Unit 2) S

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SECTION PAGE  !

3/4.0 APPLICABILITY................................................

B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS. f 3/4.1.1 BORATION CONTR0L.......................................... B 3/4 1-1  !

N 3/4.1.2 BORATION SYSTEMS.......................................... B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES................................ B 3/4 1-3 '

3/4.2 POWER DISTRIBUTION LIMITS G i s  !

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 RISE HOT CHANNEL FACT 0R........................ B 3/4 2-3 > i r

3/4.2.4 QUADRANT POWER TILT RATI0................................. B 3/4-2-5 (.

3/4.2.5 DNB PARAMETERS............................................ B 3/4 2-5 j 3/4.3 INSTRUMENTATION t 3/4.3.1 and 3/4.3.2 REACTOR TRIP and ENGINEEREO SAFETY FEATURES t

ACTUATION SYSTEM INSTRUMENTATION........................ B 3/4 3-1  !

3/4.3.3 MONITORING INSTRUMENTATION................................ B 3/4 3-2 3/4.3.4 T'J CINC 0" CRC 7CCO 700TCCTION. 94 l*.D4k . . . . . . . . . . . . . . B. .3/4

. . . 3-5

.. l 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS'AND COOLANT CIRCULATION............. B 3/4 4-1 [

3/4.4.2 SAFETY VALVES............................................. B 3/4 4-2 " '

3/4.4.3 PRESSURIZER............................................... B 3/4 4-2 3/4.4.4 RELIEF VALVES............................................. B 3/4 4-3  !

3/4.4.5 STEAM GENERATORS.......................................... B 3/4 4-3 i

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. McGUIRE - UNITS 1 and 2 XVI Amendment No. (Unit 1)

Amendment No.1 (Unit 2)

INSTRUMENTATION 3[4.3.4 TUROINC 0"CRS?((0 PROTCCTION Peldd LIMITING CONDITION FOR OPEliATION 3.3. t least one Turbine Overspeed Protection System shall be OP ABLE.

APPICABILI -

MODE 1.

- ACTION:

a. With one valve or one governor valv er high pressure turbine steamleadinMrableand/orwithone eat stop valve or one reheat interceptN41ve per low pres re turbine steam lead inoperable, 4

restore the inoperalr4 valve (s) OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or close at least one M1ve1 i e affected steam lead (s) or isolate the turbine from the stea pply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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b. With the above requir urbin yverspeed Protection System otherwise inoperable, within ours isolat the turbine from the steam supp19 SURVEILLANCE REQUIRE S 4.3.4.1 Th rovisions of Specification 4.0.4 are not appli le.

4.3.4. To assure operability of the above required Turbine Overs ed 5 tec nSystem,aninserviceinspectionofthevariouscomponentsof% pro- is 4 ,

tem are carried out in accordance with the " Turbine Overspeed Reliabt ity (

Assurance Program." ( ,

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McGUIRE - UNITS 1 & 2 3/4 3-79 Amendment No. (Unit 1)

Amendment No. (Unit 2)

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BASES 3/4.3.3.10 LOOSE-PART DETECTION INSTRUMENTATION sufficient capability is available to detect loose meta reactor system and avoid or mitigate damage to allowable out-of-service times and Surveillance.. reactor system components. The with the recommendations of Regulatory Guide 1.133, " Loose-Part De Program for the Primary System of Light-Water-Cooled Reactors," Ma .

3/4.3.4 TL'P"INE 0"ERSPECO PROTECTION -- 12cleted pro This specification is provided to ensure that the turbine overspeed and wil fon instrumentation and the turbine speed control valves are OPER c turbine exceotect the turbine from excessive ov.erspeed. Protection turbine could gene overspeed is required since excessive oversp of the tures except the new e potentially damaging missiles. All egory I struc-of turbine missiles withouvault at McGuire, are desi 9 to withstand effects b.

housed inside (FSAR Section 3. . adverse impact o e safety related equipment h and 10.2 .

To assure turbine overspeed a " Turbine Overspe Tests and inspections associated wi ance with station procedures, h1 ability Program" protection against is implemented.

rogram will be performed in accord-

'ntenance war s schedules as appropriate. deviations from thequests and/or outage work >

identified through t pecified maintenance, calibrati ram or deficiencies are evaluated b' has been af e Power Company to determine if operabor testing activities or def ed and appropriate action taken such as correctinof the system c s ce. ncy, performing compensatory action, or removing the turbine deviationrom i

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McGUIRE - UNITS 1 and 2 B 3/4 3-5 Amendment No. (Unit 1)

Amendment No.' (Unit 2)

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ATTACIIMENT Sa PROPOSED SELECTED LICENSEE COMMITMENT PAGES FOR CATAWBA l

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,16.7- INSTRUMENTATIOM 16.7-5 TURBINE OVERSPEED PROTECTION COMMITMENT:

a. At least one Turbine Overspeed Protection System shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

REMEDIAL ACTION:

a. With one stop valve or one control valve per high pressure turbine steam line inoperable and/or with one intermediate stop valve or one intercept valve per low pressure turbine steam line inoperable, restore the inoperable valve (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or close at least one valve in the affected steam line(c) or isolate the turbine from the steam 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. With the above required Turbine Overspeed Protection System otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isulate the turbine from the steam supply.

TESTING REQUIREMENTS:

a. The above required Turbine Overspeed Protection System shall be demonstrated OPERABLE: l l

1. At least once per 7 days while in MODE 1 and while in  !

MODE 2 with the turbine operating, by cycling each of I the following valves through at least one complete cycle from the running position:

a) Four high pressure turbine stop valves, b) Six low pressure turbine intermediate stop valves, and c) Six low pressure turbine intercept valves.

2. At least once per 31 days while in MODE 1 and while in MODE 2 with the turbine operating, by direct observation of the movement of each of the above valves I and the four high pressure turbine control valves, j through one complete cycle from the running position,

3. At least once per 18 months by performance of a CHANNEL Chapter 16.7 Page 14

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CALIBRATION on the Turbine Overspeed Protection Systems, and

4. At least once per 40 months by disassembling at least one of each of the above valves (including the four i high pressure turbine control valves) and performing a i

visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion.

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REFERENCES:

N/A i

BASES: i l

l 16.7-5 TURBINE OVERSPEED PROTECTION This commitment is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety-related components, equipment, or structures.

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Chapter 16.7 Page 15

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4 ATTACilMENT Sb PROPOSED SELECTED LICENSEE COMMITMENT PAGES FOR MCGUIRE i

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JNSTRUMENTATIAN i

16.7-5 TURBINE OVERSPEED PROTECTION '

G-QHN1]MEHis

a. At least one Turbine Overspeed Protection System shall be OPERABLE.

APPLICABILITY: MODE 1.

REMEDIAL _ACTIQH:

a. With one stop valve or one governor valve per high pressure turbine steam lead inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam lead inoperable, restore the inoperable valve (s) to OPERABLE status '

within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or close at least one valve in the affected steam lead (s) or isolate the turbine from the steam 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. With the above required Turbine Overspeed Protection System otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the.

steam supply.

TESTING REQUIREMENTS:

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a. To assure operability of the above required Turbine Overspeed Protection System, an inservice inspection of the various components of this system are carried out in accordance with the

" Turbine Overspeed Reliability Assurance Program."'

BEFERENCES: N/A H_ASES:

16.7-5 TURBINE OVERSPEED PROTECTION This commitment is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.

Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles. All Category I structures except the new fuel vault at McGuire, are designed to withstand effects of turbine missiles without Chapter 16.7 Page 13 I

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any' adverse impact on the safety related equipment housed inside (FSAR  ;

Section 3.5.2.7 and 10.2.3). To assure protection against turbine  ;

overspeed a " Turbine Overspeed Reliability Program" is implemented. l Tests and inspections associated with this program will be performed in accordance with station procedures, maintenance work requests and/or outage work schedules as appropriate. All deviations from the l program or deficiencies identified through the specified maintenance, calibration or testing activities are evaluated by Duke Power Company to determine if operability of the system has been affected and appropriate action taken such as correcting the deviation or deficiency, performing compensatory action, or removing the turbine from service.

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