ML20086A225

Proposed Tech Specs Re Relocation of TSs 3/4.3.3.3, 3/4.3.3.4 & 3/4.4.11

ML20086A225
Person / Time
Site:	Davis Besse
Issue date:	06/23/1995
From:	CENTERIOR ENERGY
To:
Shared Package
ML20086A208	List: ML20086A207 ML20086A219 ML20086A225
References
NUDOCS 9507030110
Download: ML20086A225 (13)

Text

'.

l LAR 95-0012 Page 10 INDEX ,

l LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS '

SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS

'3/4.2.1 AXIAL POWER IMBALANCE . . . . . . . . . . .. 3/4 2-1 3/4.2.2 NUCLt.AR PEAT FLUX HOT CHANNEL FACTOR - Fo .... 3/4 2-5 ,

3/4.2.3 NUCLEARENTHALPYRISEHOTCHANNELFACTOR-F%.. 3/4 2-7

^

3/4.2.4 QUADRANT POWEP TILT. . . . . .... ... 3/4 2-9 3/4.2.5 DNB PARAMETERS. . . ... . 3/4 2-13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION .. 3/4 3-1 ,

3/4.3.2 SAFETY SYSTEM INSTRUMENTATION .

Safety Features Actuation System. . . 3/4 3-9 Steam and Feed Rupture Control System . . . .. 3/4 3-23 Anticipatory Reactor Trip System. . . . 3/4 3-30a 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation. . .... 3/4 3-31 Incore Detectors. . . .. . .. 3/4 3-35 Deleted Scis-ic Instrumentation . . . . . ..

Deleted Meteorological Instrumentation ...

Remote ~ Shutdown Instrumentation . . . 3/4 3-43 Post-Accident Monitoring Instrumentation. .... 3/4 3-46 Deleted Waste Gas System Oxygen Monitor . . 3/4 3-57 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation . . . 3/4 4-1 Shutdown and Hot Standby. . . . .. .. 3/4 4-2 3/4.4.2 SAFETY VALVES - SHUTDOWN. . . . . . . . . . . . . . 3/4 4-3 3/4.4.3 SAFETY VALVES AND PILOT OPERATED RELIEF VALVE -

OPERATING. . . . . . . .... 3/4 4-4 DAVIS-BESSE. UNIT 1 IV Amendment No. 38.86.I34 135.167.170 I74 9507030110 950623 PDR ADOCK 05000346 p PDR

LAR 95-0012 Page 11 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PMiE 3/4.4.4 PRESSURIZER . . . .. .. ......... 3/4 4-5 3/4.4.5 STEAM GENERATORS. . .... .. .. 3/4 4-6 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems . . .. . ... 3/4 4-13 Operational Leakage ... . . . . 3/4 4-15 3/4.4.7 CHEMISTRY . . . ... .. .. 3/4 4-17 3/4.4.8 SPECIFIC ACTIVITY .. . . .... 3/4 4-20 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System. . . . ... . . . 3/4 4-24 Pressurizer . . . .. . . . ... . 3/4 4-29 3/4.4.10 STRUCTURAL INTEGRITY. . . . .. . . 3/4 4-30 3/4.4.11 Deleted REACTOR COOLANT SYSTEM VENTS. . .

3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 CORE FLOODING TANKS . . . .. . 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T , t 280*F. . . 3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T,, < 780"F. .... . 3/4 5-6 3/4.5.4 BORATED WATER STORAGE TANK. . . . . . 3/4 5-7 DAVIS-BESSE. UNIT 1 V Amendment No. 135

,LAR 95-0012 Page 12 INDEX

- BASES s SECTION A PAGE 3/4.0 APPLICABILITY ........ .. .... . 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 1-3 3/4.2 POWER DISTRIBUTION LIMITS ........ . . B 3/4 2-1 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR PROTECTION SYSTEM AND SAFETY SYSTEMS INSTRUMENTATION . . . . ...... B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION. . . ... .. B 3/4 3-2 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 . .. .. . B 3/4 4-1 3/4.4.4 PRESSURIZER . . . .......... .. B 3/4 4-2 3/4.4.5 STEAM GENERATORS. . . . . . ....... B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE. . .. .. B 3/4 4-4 3/4.4.7 CHEMISTRY . . ... ... . .. B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVTY. ........ ..... . B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS . . .. .. . B 3/4 4-6 3/4.4.10 STRUCTURAL INTEGRITY .. .. . .... B 3/4 4-13

-3/4.4.11 pel(tidHICHPOINTVENTS .......... ..

DAVIS-BESSE. UNIT 1 IX Amendment No. 135

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DAVIS-BESSE. UNIT 1 3/4 3-37 l

1 1

LAR 95-0012-Paga 14 TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION MINI.

MEASUREMENT INST .ENT INSTRUMENTS AND SENSOR LOCATIONS RANGE OP RABLE

' 1. Strong Motion Triaxial Accelerometers

~

a. Containment Concrete Foundation, Elev. 565 1 Ig 1

b. Containment Interior Secondary Shield Wall, Elev. 653 1 Ig 1

c. Auxiliary Building Basement Floor.

Elev. 545 + g 1

d. Station site - Minimum of 300 ft from containment vessel within the site boundary 1 lg - . 1

2. Peak Recording Accelerometers

a. Shield Building Top, Minimum Elev. 812 1 19 1

b. Auxiliary Building Roof, E v.

660 1 19 1

c. Control Room, Elev. 6 i 19 1

3. Seismic Trigger

a. Station site - nimum of 300 ft from containme vessel within the 1 - 10 Hz*

site boundary 0.005g -~0.029*** 1**

• Minimum Fre ency Response Range l

• • With cabin room indication

• • • Actuatio Range l DAVIS-BESSE. UNIT 1 3/4 3-38 Amendment No.156

-._ ' ". l LAR 95-0012 '

P:gn 15

(

j TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS i CHANNEL CHANNEL CHANNEL FUNCTIONAL INSTRUMENTS AND SENSOR LOCATIONS CHECK CALIBRATI TEST ,

1. Strong Motion Triaxial Accelerometers

a. Containment Concrete Foundation, M* R SA Elev. 565

b. Containment Interior Secondary l Shield Wall, Elev. 653 M* R SA )

J

c. Auxiliary Building Basement Floor,

• R SA Elev. 545

d. Station Site - Minimum of 300 ft from containment vessel within the -

site boundary M* R SA

2. Peak Recording Accelerometers

a. Shield Building Top, Minim Elev. 812 NA R NA )"

b. Auxiliary Building Roo , Elev.

NA R NA 660 NA R NA

c. Control Room. Ele . 623

3. Seismic Trigger l

a. Station Sit - Minimum of 300 ft l from cont nment vessel within the site bou dary M** R SA

• Except ismic trigger

• • With c inet room indication

/

/

/

DAVIS-BESSE, UNIT 1 3/4 3-39 Amendment No. 156

LAP. 95-0012 Page 16 INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION LIMITING CONDITION FOR OPERATION '

3.3.3.4 The meteorological monitoring instrumentation hannels shown in  :

Table 3.3-8 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

TSIR a. With one or more required meteorol gical monitoring channels 90o003 inoperable for more than 7 days, repare and submit a Special Report to the Commission pursu t to Specification 6.9:2 within

- the next 10 days outlining th cause of the malfunction and the plans for restoring the cha el(s) to OPERABLE status.

b. The provisions of Specif ations 3.0.3 and 3.0.4 are not applicable. ,

l l

SURVEILLANCE REQUIREME ,

S '

1 I

4.3.3.4 Each of he above meteorological monitoring instrumentation channels shall be demons ated OPERABLE by the perforinance of the CHANNEL CHECK and CHANNEL CALIB TION' operations at the frequencies shown in Table 4.3-5. ,

/ i DAVIS-BESSE. UNIT 1 3/4 3-40

l- 4 .

j) o:, lP alh l TABLE 3.3-8 .. s, c.

$ )l

. METEOROLOGICAL MONITORING. INSTRUMENTATION MINIMUM OPERA 8LE l INSTRUMENT- LOCATION

1. WIND SPEED 1

a. Nominal Elev. 612 l 1

b. Nominal Elev. 827

2. WIND DIRECTION l l

1

a. Nominal Elev. 612 I l

1

b. Nominal Elev. 827

~

I 3. AIR TEMPERATURE - DELTA T --

1 l a. Nominal Eley. 827-612 i )

1 DAVIS-BESSE, UNIT 1 3/4 3-41 9

- - - - - - - - ~ . - - _ - _ . _ _ _ _ _ _ _ _ _ _ __ -- -. _ . . . _ _ _ _ _

mg 5x

. e TABLE 4.3-5 5;i"

!! HETEOR0 LOGICAL MONITORING INSTRUMETATION SURVEILLANCE REQUIREMENTS .

a e, CHANNEL CHANNEL C; INSTRUMEt CHECK CALIBRATION M

1. WIND SPEED E

a. Nominal Elev. 612 D SA

~~

b. Nominal Elev. D SA

2. WIND DIRECTION

a. Nominal Elev. 612 D SA

b. Nominal Elev. 827 D SA k'

Zm y' 3. AIR TEMPERATURE - DELTA T

-0

a. Nominal Elev. 827-612 0 SA 6

. 'LAR 95-0012 ,

Page 19

' REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM VENTS h I

• LIMITING CONDITION FOR OPERATION -

3.4.11 The following reactor coolant system vent paths shall be operable:

a. Reactor Coolant System Loop 1 vith vent path through valves RC 08A and RC 4608B. s

b. Reactor Coolant System I.oop' 2 vith vent path through valves C 4610A and RC 46108.

c. Pressurizer; with vent path through EITHER valves RC11 nd RC 2A (PORV) l OR valves RC 239A and RC 200. ,

APPLICABILITY: Modes 1, 2 and 3 i ACTION:  ;

a. With one of the above vent paths inoperable restore the inoperable vent path to OPERABLE status within 30 day , or, be in HOT STANDBY vithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN withi the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. l

b. Vith two of the above vent paths inop able, restore at least one of  ;

the inoperable vent paths to OPERAB status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in .

• HOT STANDBY vithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in SHUIDOWN within the following 30 I hours.

1

c. With three of the above vent ths inoperable, restore at least two of the inoperable vent paths to PERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY vithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> d in HOT SHUTD0VN vithin the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. -

d. The provisions of spe fication 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

/

• I 4.4.11 Each reactor e olant system vent path shall be demonstrated OPERABLE at  !

least once per 18 mon s by:

1. Verifying 11 manual isolation valves in each vent path are locked in the ope position, and

2. Cycl each valve in the vent path through at least one complete cycle of 11 travel from the control room during COLD SHUTDOWN or REFUELING, a

3. Verifying flov through the reactor coolant vent system vent paths during COLD SHUTDOWN or REFUELING.

.ws DAV S-BESSE, UNIT 1 3/4 4-32 Amendment No. /11,135

9 LAR 95-0012 Paga 20 t ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission in accordance with 10 CFR 50.4 within the time period specified for each report. These reports snoll be submitted covering the activities identified below pursuant to the requirements of the applicable reference specifications:

a. ECCS Actuation. Specifications 3.5.2 and 3.5.3. .

i

b. De e Incperable Scismic Monitoring Instrumentation. Specification

c. 061st'ed Incperable "eteorological Monitoring Instrumentation.

Spbdification 3.3.3.'.

d. Seismic event analysis. Specification 4.3.3.3.2.

e. 9ted

f. Deleted 9 Inoperable Remote Shutdown System control circuit (s) or transfer switch (es) required for a serious control room or cable spreading room fire Specification 3.3.3.5.2 6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:

a. Records and logs of facility operation covering time interval at each power level.

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety,

c. All REPORTABLE EVENTS.

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e. Records of changes made to Operating Procedures.

f. Records of radioactive shipments.

g. Records of sealed source and fission detector leak tests and results.

h. Records of annual physical inventory of all sealed source material  ;

of record.

DAVIS-BESSE. UNIT 1 6-18 Amendment 9.I2.65.86.

106.I25.I70.I74.I87

LAR 95-0012 Pcg2 21 i 3/4.3 INSTRUMENTATION BASES 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3 1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the  ;

radiation level trip setpoint is exceeded.

3/4.3.3.2 INCORE DETECTORS i The OPERABILITY of the incore detectors ensures that the measurements obtained  !

from use of this system accurately represent the spatial neutron flux distribution of the reactor core. See Bases Figures 3-1 and 3-2 for examples of acceptable minimum incore detector arrangements.

3/4.3.3.3 SEISMIC INSTRUMENTATION Delhtsd The OPEP^BILITY of the scismic instrumentetion ensure: that i,0fficient capability is available to promptly determine the magnitude of a scismic event 50 that the rc pon:0 of those feature: important to sfety-may be evaluated. Tht cc:abi'ity t required to permit c0lr:arison of the meccured respon 0 to tiat used in the design bas t for tic facility. Thu instrumentation is centistent with the rec 0=cndation: Of Regulatory Cuide 1.12 " Instrumentation for Earthquake:." ^pril 1971 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION D61etid The OPER^,BILIlY of the meteorological instrumentation encurc: that suffi~c'icnt 0tenti 1 radttion dose to themeteorological dataoft available public as a result routinc orfor c timatingrc^Icase of accidental radioactive materich to the atmosphere. Tht capability u required te evaluate the need for initiating protective mcacurc to protect the health and safety of the pubik. This instrumentation t con:htent with the recc~:"endation: Of Regulatory Cuide 1.23 "Oncite Mcteorological Programs."

r& _ , , nw

. - m, ~ , .

3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of DAVIS-BESSE. UNIT 1 B 3/4 3-2

LAR 95-0012  :

Pag 2 22  :

l 1

i REACTOR COOLANT SYSTEM BASES l c

3/4.4.10 STRUCTURAL INTEGRITY a

The inspection programs for ASME Code Class 1. 2 and 3 components, except i steam generator tubes ensure that the structural integrity of these  :

components will be maintained at an acceptable level throughout the life of  ;

the plant. To the extent applicable, the inspection 3rogram for these i components is in compliance with Section XI of the ASiE Boiler and Pressure

' Vessel Code.  :

)

The internals vent valves are provided to-relieve the pressure generated by I steaming in the core following a LOCA so that the core remains sufficiently <

covered. Inspection and manual actuation of the internals vent valves 1)  !

ensure OPERABILITY. 2) ensure that the valves are not stuck open during normal-  !

operation, and 3) demonstrates that the valves are fully open at the forces i equivalent to the differential pressures assumed in the safety analysis.

3.4.4.11 HIGH POINT VENTS Ddli(sd The Reactor C001:nt Sy; tem high point vents are installed per _

NUREC'0737 ite: !I.S.1 requirccr nonconden :bIcga cnts. The :bility of +50 n t:b":te:

c^crcapability bubble: cnsure ste of venting c reactor  ;

c00 ling system to restore natural circulation following a small brcok los: Of ,

cccl:nt 2 Cident.

o i

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t DAVIS-BESSE. UNIT 1 B 3/4 4-13 Amendment No. 85  ;

I

. - . . . , - - - _ _ _ _ - _