ML20195F935

Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs

ML20195F935
Person / Time
Site:	Davis Besse
Issue date:	06/10/1999
From:	CENTERIOR ENERGY
To:
Shared Package
ML20195F909	List: ML20195F907 ML20195F912 ML20195F935
References
NUDOCS 9906150141
Download: ML20195F935 (16)

Text

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LAR 96-0013 Pag 311 INDEX ADMINISTRATIVE CONTROLS l

)

SECrlON

PAGF, Meeting Frequency..................................... 6-9 Qu oru m.............................................. 6-9 Re v ie w............................................... 6-10 A u d i ts...............................................

6-11 A u thori ty.............................................

6-12 Rec ord s..............................................

6-12 i

6.5.3 Technical Review and Control............................

6-12

]

1 6.6 REPORTABLE EVENT ACTION................................

6-12a j

6.7 SAFETY LIMIT VIOLATION OR PROTECTIVE LIMIT VIOLATION.

6-13 6.8 PROCEDURES AND PROGRAMS......'........................ 6-13 i

6.9 REPORTING REOUIREMENTS i

6.9.1 Routine Reports.......................................

6-14eg l

6.9.2 Special Reports........................................

6-18 fil0 RECORD RETENTION........................................ 6-18 6111 R ADIATION PROTECTION PROGRAM......................... 6-20 id2_HIGH RADIATION ARE A..................................... 6-20

. 6.13 ENVIRONMENTAL OUALIFICATION.......................... 6-21 6.14 PROCESS' CONTROL PROGRAM (PCP)......................... 6-22 i

6.15 OFFSITE DOSE CALCULATION M.ANUAL (ODCM).............. 6-22 t

j i

DAVIS-BESSE, UNIT 1 XVI Amendment No. 38,135,170,189, 99%150141 99%10 PDR ADOCK 05000346 P

PDR

LAR 96-0013 Paga12 INFORMATION ONLY APPLICABILITY SURVEILLANCE REOUIREMENTS 4.0.1 Surveill'ance Requirements shall be applicable during the OPERATIONAL H0 DES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.

4.0.3 Ftilure to perform a Surveillance Requirement within the allowed surveilknce interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERASILIlY requirements for a Limiting Condition for Operation.

The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.

The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable (equipment inoperability) outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Surveillance requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL N00E or other specified applicability condition i

shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as follows:

a.

Inservice inspection of ASME Code Class 1, 2 and 3 components and inservice testing of ASME Code Class 1, 2' and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a.

b.

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

i I

DAVIS-BESSE, UNIT I 3/4 0-2 Amendment No. 77,1/0,1A5,197 L

4 LAR 96 0013 Paga 13

. CONTAINMENT SYSTEMS HYDROGEN PURGE SYSTEM i

i LIMITING CONDITION FOR OPERATION 1

3.6.4.4 A containment hydrogen purge system shall be OPERABLE.

- APPLICABILITY: MODES 1 and 2.

ACTION:

l l

With the containment hydrogen purge system inoperable, restore the hydrogen purge system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVETI1 ANCE REOUIREMENTS 4.6.4.4 The hydrogen purge system shall be demonstrated OPERABLE:

. At least once per 18 months by initiating flow through the HEPA filters and charcoal a.

adsorbers and verifying that the system operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters on.

b.

In accordance with the Ventilation Filter Testine Program (VFTP1.^.: ':= ::: p -

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3 DAVIS-BESSE, UNIT 1 3/4 6-26 Amendment No. 155, 209,

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LAR 96-0013 Pags 14 CONTAINMENT SYSTEMS l

SURVFIII ANCE REOUIREMENTS (Continued)

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.s DAVIS-BESSE, UNIT 1 3/4 6-27 Amendment No. 155, 209

J LAR'96-0013

Pag 315 -

i CONTAINMENT SYSTEMS 3/4.6.5 SHIELD BUILDING EMERGENCY VENTILATION SYSTEM

' IlMITING CONDITION FOR OPERATION -

3.'6.5.1 Two iridependent emergency ventilation systems shall be OPERABLE.

APPLICABILITY: ~ MODES 1,2,3 and 4.

ACTION:

With one emergency ventilation system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SIIUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

L

' SURVFH I.ANCE REOUIREMENTS 4.6.5.1 Each emergency ventilation system shall be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes.

1 b.

jn accordance with the Ventilation Filter Testine Procram (VFTP1 At :=:::::

cach REPJELI"O Ih",RVAL cr (!) :ft:r any ::m ::::! main::::::: en $: HEPA fi!::: cr chareca! 2&c6 r hc=ings, er (2) fc!!c e ng pairting, fire cr chemica! -

!:=: in any ventil tien rene cer nanicating.>ii10 sy::::= by:

)

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- DAVIS-BESSE, UNIT 1 -

3/4 6-28 Amendment No. 155,217 J

t

LAR 96-0013 Page 16 CONTAINMENT SYSTEMS SURVETILANCE REOUIREMENTS (Continued)

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Verifying that the system starts automatically on any containment isolation test signal; 3.

Verifying that the filter cooling bypass valves can be manually opened; and

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r

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l LAli 96-0013 l

' p'g317 ADD;if0NAL CHAl:GES PREVIOUSLY l

L CONTAINMENT SYSTEMS PROPOSED BY LEfiER Sen. l No. 25S7 Datelo/nh8 a

SURVEILLANCE REQUIREMENTS (Continued) 1 4.

Verifying that each system produces a negative pressure of greater than or j

equal to 0.25 inches Water Gauge in the annulus within 4 seconds after the fan attains a flow rate of 8000 cfm 10%. This test is to be performed with the flow path established prior to starting the EVS fan, and the other dampers associated with the negative pressure boundary closed.

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DAVIS-BESSE, UNIT 1 3/4 6-30 Amendment No. 3,135,155 1

LAN 96-0013 Paga 18 PLANT SYSTEMS 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.6.1 Two independent control room emergency ventilation systems shall be OPERABLE.

APPLICABILITY: MODES 1,2,3 and 4.

ACTION:

With one control room emergency ventilation system inoperable, restore the inoperable a.

system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 />.

b.

With one channel of Station Vent Normal Range Radiation Monitoring instrumentation inoperable, restore the inoperable channel to OPERABLE status, or isolate the control room normal ventilation system and place at least one control room emergency ventilation system train in operation within 7 days, c.

With both channels of Station Vent Normal Range Radiation Monitoring instrumentation inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, isolate the control room normal ventilation system and place at least one control room emergency ventilation system train in operation.

SURVEILLANCE REQUIREMENTS - 4.7.6.1 Each control room emergency ventilation system shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room air temperature is less than or equal to 110 F when the control room emergency ventilation system is operating.

b. At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes.

c. In accordance with the Ventilation Filter Testine Procram (VFTPt A: ' cast cace : ch RERJELING INTERVAL cr (1) fter =y ::=ctura! mainten=ce en $c HEPA fil::: cr chr.::ccl cici;r herin;;;, 0:- (2) fc!b".ing ;=in:ing, '!:: cr ch:mi=1 ::b=: in any

=n:!!: tic ::= :c==en!=fng i$ S::y;::= by:

l DAVIS-BESSE, UNIT 1 3/4 7-17 Amendment No. 135, 155,217,227 i

4

LAR 96-0013

)

Pags 19 i

PLANT SYSTEMS

]

I SURVEILLANCE REQUIREMENTS (Continued) i.

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2. Verifying that the control room normal ventilation system is isolated by a SFAS test signal and a Station Vent Normal Range Radiation Monitoring test signal; and l

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DAVIS.BESSE, UNIT I 3/4718 Amendment No. 134,135, 155,209,217.227 c

LAR 96-0013 Pcgs20 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 3.

Verifying that the makeup flow of the system is 300 cfm 10% when supplying the control room with outside air.

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I DAVIS-BESSE, UNIT 1 3/4719 Amendment No.155

1 h

q LAR 96-0018

- Page 21 i

ADMINISTRATIVE CONTROLS i

i 6.8.4 (Continued)

I

e. Radiological Environmental Monitorine Program (Continued)

I 3)

Participation in an Interlaboratory Comparison Program to ensure that j

independent checks on the precision and accuracy of the measurements of

]

radioactive materials in environmental sample mairices are performed as part of the quality assurance program for environmental monitoring.

f. Ventilation Filter Testine Program (VFTPh j

A nrogram shall be established to imnlement the followine reauired testing of safety reinted filter ventilation systems at the freauencies snecified in the VFTP and in accordance with Reenlatory Guide 1.52. Revision 2. ANSI /ASME N510-1980. and ASTM D 3803-1979 under the conditions noted in the orogram.

3 1.

Demonstrate for each of the safety related systems that an in-nlace test of the high efficiency narticulate air (HEPA) filters shows a nenetration and system bynass

< 1% when tested in accordance with Regulatorv Guide 1.52. Revision 2 and ANSI /ASME N510-1980 at the system flowrate snecified below. +/- 10%.

Safety Related Ventilation Svstem Flowrate Containment Hydronen Purge System 100cfm Shield Buildine Emergency Ventilation System HQQQ,gfm

- Control Room Emereency Ventilation System 3300cfm 2.

Demonstrate for each of the safety related systems that an in-nlace test of the charcoal adcorber shows a nenetration and system bynass < 1% when tested in accordance with Reenlatory Guide 1.52. Revision 2 and ANSI /ASME N510-1980 at the system flowrate snecified below. +/-10%.

1 Safety Related Ventilation System Flowrate j

Containment Hydronen Puree System 100 cfm i

Shield Buildine Emereency Ventilation System 1000_cfm i

Control Room Emereency Ventilation System 3300cfm 3.

Demonstrate for each of the safety related systems that a laboratory test of a samnle of the charcoal adsorber. when obtained as described in Reenlatorv Guide i

1.52. Revision 2. shows the methyl iodide nenetration less than the value snecified i

DAVIS-BESSE, UNIT 1 6-14c Amendment No.170 i

i

n l:

LAR 96-0013 Page 22

. ADMINISTRATIVE CONTROLS I

i 6.8.4 (Continued) -

f.

Ventilation Filter Testine Program (VFTP) (Continued) below when tested in accordance with ASTM D 3803-1979 at a temocrature of 30 C and creater than or caual to the relative humidity (RH) soecified below.

with the followine conditions:

1) couilibrate for 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />

2) challenee for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

3) elution for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Safety Related Ventilation System Penetration M

' Containment Hydrocen Purce System

.lfg 20fg j

Shield Buildine Emereency Ventilation System Jfg 2Qfg j

Control Room Emereency Ventilation System jfg 2Qfg 4.

Demonstrate for each of the safety related systems that the cressure droo across

)

the combined HEPA filters. the orefilters*. and the charcoal adsorbers is less than the value soecified below when tested in accordance with Reculatory Guide 1.52.

Revision 2 and ANSI /ASME N510-1980 at the system flowrate soecified belom

+/- 10E

- Safety Related Ventilation System Delta P Flowrate Containment Hydrocen Purce System 25 inches Water Gauee 100 cfm Shield Buildine Emereency Ventilation System 6 inches Water Gauge.

8000cfm j

Control Room Emercency Ventilation System 4.4 inches Water Gaung 3300cfm

• Containment Hydronen Purce does not contain orefilters.

5.

Demonstrate that the heaters for the safety related Containment Hydronen Purce System dissinate 2000 watts +/- 20% when tested in accordance with ANSI /ASME N510-1980.

' The orovisions of SR 4.0.2 and SR 4.0.3 are anolicable to the VFTP test freauencies.

DAVIS-BESSE, UNIT 1 6-14d Amendment No.

1

m

' LAR 96-0013 Pags23 i

i ADMINISTRATIVE CONTROLS 6.9 REPORTING REOUIREMENTS -

BOUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the appropriate Regional Office unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) tendment to the license involving a planned increase in power level, (3) installation of fuel 11 a has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.

Any corrective actions that were required to obtain satisfactory operation shall also be described.

Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup

)

test program, (2) 90 days following resumption or commencement of commercial power 1

operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial 1

i i

u i

DAVIS-BESSE, UNIT 1 6-14e Amendment No. 93

LAR 96-0013 Paga24

p. -

AEDiTM!:!. CHANUf.S FXVi3'my i

CONTAINMENT SYSTEMS PMDC M UGR lSc*n'.Nn.2557

(,m m b;hif)'

t 3/4.6.4 CGMBUSTIBLE GAS CONTROL Th s OPERABILITY of the Hydrogen Analyzers, Containment Hydrogen Dilution System, en i Hydrogen Purge System ensures that this equipment will be available to maintain the maximum 1 ydrogen concentration within the containment vessel at or below three volume pe: cent following a LOCA.

The two redundant Hydrogen Analyzers determine the content of hydrogen within the containment vessel.The Hydrogen Analyzers, although they have their OPERABILITY requirements in this Specification, are considered part of the post-accident monitoring instrumentation of Specification 3/4.3.3.6, Post-Accident Monitoring Instrumentation.

The Containment Hydrogen Dilution (CHD) System consists of two full capacity, redundant, rotary, positive displacement type blowers to supply air to the containment. The CHD System controls the hydrogen concentration by the addition of air to the containment vessel, resulting in a pressurization of the containment and suppression of the hydrogen volume fraction.

The Containment Hydrogen Purge System Filter Unit functions in conjunction with the CHD System and is designed to release air from the containment atmosphere through a HEPA filter and charcoal filter prior to discharge to the station vent. The_reauired Hydrocen Purce Svstem filter testine is nerformed in accordance with the Ventilation FilleLTestine Procram (YIEPLThe VFTP includctlesting HEPA filter performance. charcoal adsuber_efficiench minimum system flow rate. and the ohvsical oronerties of the activated charcnaUggggral use and

[Qll2EiDUPI.cific operamasWpecificlestfrgguencies_anditdditional informatioc are discussed ittdetail in the VFTP.

As a backup to the CHD System and the Containment Hydrogen Purge System, the capability to install an external hydrogen recombination system has been provided.

3/4.6.5 SHIELD BUILDING 3/4.6.5.1 EMERGENCY VENTILATION SYSTEM The OPERABILITY of the emergency ventilation systems ensures that containment vessel leakage occurring during LOCA conditions into the annulus will be filtered through the HEPA filters and charcoal adsorber trains prior to discharge to the atmosphere. This requirement is necessary to meet the assumptions used in the safety analyses and limit the site boundary radiation doses to within the limits of 10 CFR 100 during LOCA conditions.

Hggauired emercency ventilation filter testinc is nerformed in accordance with the Ventilation Filter Testine Procram (VFTPL The VFTP includes testine HEPA filter oerformance. charcoal adsorber efficiency. minimum system flow rate. and the ohvsical nronerties of the3ctivatedsharcoalhgggalyse and followinc specific ooerationst Snecificlqsl Roguencies and.adslitional information are discussed in detail in the VFTP, DAVIS-BESSE, UNIT 1 B 3/4 6-4 Amendment No. 68,167,183, Correction Ltr dated 5/17/94 I

l

' LAli 96-0013 Page 25 INFORMATION ONI.Y PLANT SYSTEMS

_B AS ES

,~

the flow pat'. can be established. The ability for local, manual operation 'a demonstrated by verifying the presence of the handvheels for all manu n valves and the presence of either handvheels or available power..pply for motor operated valves.

3/4.7.2 STEAN GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allovable fracture toughness stress limits. The limitations of 110*F and 237 peig are based on a steam generator RT of 40*F and are sufficient to prevent brittle fracture.

NDT 3/4.7.3 COMPONENT COOLING WATER SYSTEM The' OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions. The redundan't cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.

3/4.7.4 SERVICE MATER SYSTEM The OPERABILITY of:the serrice water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal'and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with

)

the assumptions used in the safety analyses; 3/4.7.5 ULTIMATE HEAT SINK

~

The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to either 1) provide normal cooldown of the facility, or 2) to mitigate the effects of accident conditions within acceptable limits.

The limitations on minimum vater level and maximum temperature are 4

based on providing a 30 day cooling water supply to safety related equipment vichout exceeding their design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants" March 1974.

3/4.7.6 CONTROL ROOM EMERCENCY VENTILATION SYSTEM The OPERABILITY of the control room emergency ventilation system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system.and 2) the control room vill remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. Thio limitation is consistent with the requirements of General Design Criterion 19 of Appendix "A",

10 CFR 50.

DAVIS-BESSE, UNIT 1 B 3/4 7-4 Amendment No.103

LAR 96-0013 Pag 326 PLANT SYSTEMS BASES The Station Vent Normal Range Radiation Monitoring isolation function provides that under the required conditions, an isolation signal will be given. The Station Vent Normal Range Radiation Monitors provide isolation and shutdown of the control room normal ventilation

. system.

With one or both channels of Station Vent Normal Range Radiation Monitoring instmmentation inoperable, the provisions of Action statements b or c, respectively, are applicable. The provisions of Action statement a are not applicable.

Under the Action statements for inoperable Station Vent Normal Range Radiation Monitoring instrumentation, should the control room normal ventilation system be isolated and at least one train of the control room emergency ventilation system be placed in operation, these systems would be in a state equivalent to that which they would be in following an actual high radiation condition. Plant operation can continue indefinitely in this state, provided that control room temperature can be maintained in an acceptable range, with the control room emergency ventilation system obtaining fresh-air makeup as described in the Updated Safety Analysis Report Section 9.4.1," Control Room."

Surveillance Requirement 4.7.6.1.e.2 requires verification that the control room normal ventilation system can be isolated by a Station Vent Normal Range Radiation Monitoring test signal.

Additional testing requirements for the Station Vent Normal Range Radiation Monitorinr instrumentation are provided in the ODCM for gaseous effluent releases.

The reauired control room emereency ventilation system testine is cerformed in accordance with the Ventilation Filter Testine Procram (VFTP). The VFTP includes testine HEPA filter oerformance. charcoal adsorber efficiencv; minimum system flow rate. ruid_the ohvsical oronerties of the activated charcoal. Soecific test frecuencies and additional information are discussed in detail in the VFTP.

)

l 1

DAVIS-BESSE, UNIT 1 B 3/4 7-4a Amendment No. 227