Text

Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application
	ML20205E503
Person / Time
Site:	Davis Besse
Issue date:	03/19/1999
From:	; CENTERIOR ENERGY
To:	;
Shared Package
ML20205E499	List: ML20205E496; ML20205E503;
References
	NUDOCS 9904050203
	Download: ML20205E503 (11)
	v • d • e

E l i

-I Qocket Number 50-346

. . License Number NPF-3 l- Serial Number 2589 Attachment

. . 1 l

l l

l TECilNICAL SPECIFICATION PAGES

! FOR LICENSE AMENDMENT REQUEST 98-0010 3 (10 pages follow) l l

l 1 l 1 i

I j

i 990405c203 990319 7 PDR ADOCK 05000346 P PDR ;,,

- J

Docket Number 50-346

^

Lic:nse Number NPF-3 Serial Number 2589 INDEX Attachment, Page 1 DElWTflONS SE'C TION' PAGE 1.0 DEFINITIONS DEFINED TERMS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 THERM AL POWER . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 RATED THERM AL POWER. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 OPERATION AL M ODE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 ACTION............................................................... 1-1 OPERABLE - OPERABILITY . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 R EPORTAB LE EVENT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . 1-2 CONTAINMENT INTEGRITY. . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 CHANNEL CALIB RATION. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 CHANNEL CHECK. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 CHANNEL FUNCTIONAL TEST . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 CORE ALTERATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3

. S HUTDOWN MARGIN. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 IDENTIFIED LEAKAGE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 UNIDENTIFIED LEAKAGE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 PRESSURE BOUNDARY LEAKAGE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 CONTROLLED LEAKAGE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 QUADRANT POWER TILT. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 DOSE EQUIVALENT I- 131. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 E-AVERAGE DISINTEGRATION ENERGY. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 STAGGERED TEST B ASIS. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 ;

FREQUENCY NOTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 l AXIAL POWER IMB ALANCE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 DELEDID_OITT.T.*T

.. hD-T TT.Y

~ - nTkf

~ . A.T.kf'.i'.CND.YW

~........................ ........... +-5 REACTOR PROTECTION SYSTEM RESPONSE TIME. . . . . . . . . . . . . . . . . . . . . . . . 1-5 U.lETY FEATURE RESPONSE TIME . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6 PH YS ICS TESTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 l STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM RESPONSE TIME. . . 1-6 l PROCES S CONTROL PROG RAM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6a i

DAVIS-BESSE, UNIT I I Amendment No. 38,86,93,170,

Docket Number 50-346 License Number NPF-3

~ ' Serial Number 2589 Attachment, Page 2 DEFINITIONS !

l per disintegration (in MeV) for isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95% of the total non- iodine activity in the coolant.

STAGGERED TEST BASIS j 1.21 A STAGGERED TEST BASIS shall consist of:

a. A test schedule for n systems, subsystems, trains or designated components obtained by dividieg the specified test interval into n equal subintervals,

b. - The testing of one system, subsystem, train or designated components at the beginning of each subinterval.

FREOUENCY NOTATION 1

1.22 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.

a AXIAL POWER IMll;ALANCE 1.23 AXIAL POWER IMBALANCE shall be the THERMAL POWER in the top half of the core expressed as a percentage of RATED THERMAL FOWER minus the THERMAL POWER in the bottom half of the core expressed as a percentage of RATED THERMAL POWER.

SHIELD BUP_D"O S 50RITY-1.24 DELETED SHIELD EL"LDS!O INTEOR.mf cha!! =ist v/h=:

a. Se ci- !ght dec= =d the b!:v/=: p=:S !!:::d in T;b!: '.5 1 ::: c!=:d =cep th: :i- !ght dec= = y bc =ed for nc mal tr=:i =try =d =i S. H::mer;= y v=:lla:!= ay ::= i . OPERABLE.

. The 2:1:ng mech =i = == iated vith each p= trati= (e.g., v 16, be!!cve: c '

O-Wag ) i: OPERAEL" REACTOR PROTECTION SYSTEM RESPONSE TIME 1.25 The REACTOR PROTECT' 'N SYSTEM RESPONSE TIME shall be that time interval from wl en the monitored ,.arameter exceeds its trip setpoint at the channel sensor until power inte;ruption at the control rod drive breakers.

I i

DAVIS-BESSE, UNIT 1 1? Amendment No. l e j

Docket Number 50-346 License Number NPF-3 S: rial Number 2589 Attachment, Page 3 CONTAINMENT SYSTEMS 3/4.6.5 SHIELD BUILDING EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.5.1 Two independent emergency ventilation ;ystems 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 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 ad.sorbers and verifying that the system operates for at least 15 minutes.

b. At least once each REFUELING INTERVAL or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:

DAVIS-BESSE, UNIT 1 3/4 6-28 Amendmeat No. 155,217

Docket Number 50-346 License Number NPF-3 Serial Number'2589

', ' Attachment, Page 4 CONTAINMENT SYSTEMS 1

SURVEILLANCE REQUIREMENTS (Continued)

1. Verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria ofless than 1% and uses the test procedure j guidance in Regulatory Positions C.5.a C.5.c and C.5.d of Regulatory Guide 1.52, !

Revision 2, March 1978, and the system flow rate is 8,000 cfm 2 10%;

2. Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatery Guide 1.52, Revision 2, March 1978, meets the laboratory testing l criteria of Regulatory Position C.6.a* of Regulatory Guide 1.52, Revision 2, March 1978, for a methyliodide penetration of less than 1%; and l

3. Verifying a system flow rate of 8,000 cfm

10% during system operation when tested in accordance with ANSI N510-1980. ,

1

c. After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying, within 31 days after removal, that .: laboratory analysis of a representative carbon sample obtained in '

accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory tescing criteria of Regulatory Position C.6.a* of Regulatory Guide 1.52, Revision 2, March 1978, for a methyliodide penetration ofless than 1%.

d. At least once each REFUELING INTERVAL by:

1. Verifying that the pressure drop across the combined HEPA f;lters'and charcoal adsorber banks is less than 6 inches Water Gauge while operating the system at a flow rate of 8,000 cfm i 10%;

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

3. Verifying that the filter cooling bypass valves can be manually openedg-and

The test is performed in accordance with ASTM D 3803-1979 with the following conditions:

1) equilibrate for 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months at 30*Cn0% relative humidity (RH),2) challenge for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months at i 30'Cn0% RH,3) clution for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months at 30*Cn0% RH.

l DAVIS-BESSE, UNIT 1 3/4 6-29 Amendment No.43,135,155,209,217

[

L L

l Docket Number 50-346 '

License Number NPF-3 3

Serial Number 2589 !

' Attachment, Page 5 l CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

\

4 Deleted V::ifying S;;:=h :.y:,:::n p :d := ;: ;n::v: p::==:: ef g ::: r San er l

4:;;;! :: 0.25 inche "' ::: 0 rg: in 'h: == != ;;it'- 1 =c 36 efter Se f n '

!= 0:v rc:: cf 8^"J cf:n ; 10" . Si :=:i: :: be p=fer:=d i^ S: E::

p S =::b!!d:d pi r :: :n-' ; S EVS f ,: d Se :Sc d =p=: =::c*ed !S the-c:gni;; p===: 5 : d=y :!=ed,-

e. - After each complete or partial replacement of a HEPA filter bank, by verifying thet the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% in accordance with ANSI N510-1980 for a DOP test aerosol while operating the system at a flow rate of 8000 cfm i 10%.

f. After each complete or partial replrcement of a charcoal adsorber bank, by verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% in accordance with ANSI N510-1980 for a halogenated hydrocaibon refrigerant test gas while operating the system at a flow rate of 8900 cfm i 10%. )

i l

1

)

l i

\

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

i Docket Number 50-346 l.

' ~

License Number NPF-3 )

' ' Serial Number 2589 1

Attachment, Page 6 CONTAINMENT SYSTEMS S IELD BUILDING INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.5.2 Shield buildine inteerity SHIELD BUILDING B50RT shall be maintained.

APPLICABILITY: MODES 1,2,3 and 4 ACTION:

Without shield buildine integrity SH"" D BUILDING STTEORrrY, restore,ghg;1d buildine intcerity SW" ^ BUILDI"O INTEGRP'( within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least l HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the l following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 1

4.6.5 2J Shield building intecrity SHIELD BUILDI"O IN7EORrrY shall be demonstrated at least once per 31 days by verifying that airtight doors and the blowout '

panels listed in Table 4.6-1 are :losed except when the airtight doors are being used for normal transit entry and exit.

4.6.5.2.2 Shield buildine intecrity shall be demonstrated at least once oer REFUELING INTERVAL bv verifying that each Emergency Ventilation System train oroduces a agggjye oressure of creater than or eaual to 0.25 inches Water Gauce in the argtglus within 4 seconds after the fr.n attains a flow rate of 8000 cfm " 10%. This tesi is to be nerformed witMhe flow cath established orior to startine the EVS fan. and the other damners associated with the negative oressure boundary ginsei l

l DAVIS-BESSE, UNIT I 3 M 6-31 Amendment No.

Docket Number 50-346

, License Number NPF-3

. SerialNumber2589 Attachment, Page 7 FORINFORMATIONDNLY Page 3/4 6-32 Deleted.

Next page is 3/4 6-33.

l i

i l

l l

1 I

i i

I i

i l

DAVIS-BESSE, UNIT 1 3/4 6-32 Amendinent No. 93,205 l l

Docket Number 50-346

License Number NPF-3

. Serial Number 2589 Attachment, Page 8 TABLE 4.6-1 I ACCESS OPENINGS REQUIRED TO BE CLOSED TO ENSURE SHIELD BUILDINGINTEGRITY L AIR TIGHT DOORS DOOR NO. DESCRIIYrION i

ELEVATION l 100 Access Door from the No.1 ECCS Pump Room 545' (Room 105) to Pipe Tunnel 101 l 104A Access Door from Stair AB-3 to the No. I 555' ECCS Pump Room (Room 105) 105 Access Door from Passage 110A to the area above 555' the Decay Heat Coolers

)

107 Access Door from the No. 2 ECCS Pump Room 555' (Room 115) to the Miscellaneous Waste Monitor Tank and Pump Room (Room 114) 108 Access Door from the No. 2 ECCS Pump Room 555' (Room 115) to the Detergent Waste Drain Tank and Pump Room (Room 125) 201-A Access Door from Corridor 209 to the No.1 565' Mechanical Penetration Room (Room 208) 204 Access Door from Passage 227 to the Makeup 565' i Pump Room (Room 225) 205 Access Door from Passage 227 to the No. 2 l

565' Mechanical Penetration Room (Room 236) 307 Access Door from Corridor 304 to the No. 3 585' Mcchanical Penetration Room (Room.103-308) 308 Access Door from Corridor 304 to the No. 4 585' Mechanical Penetration Room (Room 314)

IL BLOWOUTPANELS TOTAL NO. LOCATION ELEVATION 1

No. 2 Mechanical Penetration Room 565' (Room 236) 6 No. 3 Mechanical Penetration Room 585' (Room 303) 6 No. 4 Mechanical Penetration Room 585' (Room 3!4)

DAVIS-BESSE, UNIT 1 3/4 6-33 Amendment No.

- Docket Number 50-346 I License Number NPF-3 {

I

~ Serial Number 2589 Attachment, Page 9

_ CONTAINMENT SYSTEMS ,

f BASES

3/4.6,4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the Hydrogen Analyzers, Containment Hydrogen Dilution I l

System, and Hydrogen Purge System ensures that this equipment will be available to maintain the maximum hydrogen concentration within the containment vessel at or below three volume percent following a LOCA.

The two redundant Hydrogen A931yzers determine the content of hydrogen within the containment vessel. The Hydrogen Analyzers, although they have their OPERABILITY requirements in this Specification, are considereo part of the post-accident monitoring instrumentation of Specification 3/4.3.3.6, Post-Accident Monitoring Instrumentation.

The Containment Hydrogen Dilution (CHD) Systen. consists of two full capacity, I

redundant, rotary, positi" displacement type blowers to suppi> . air to the containment. The CHD '

System controls the hyorogen concentration by the addition of aiuo the containment vessel, resulting in a pressurization of the containment and suppression of d'e hydrogen volume fraction.

3 The Containment Hydrogen Purge System Filter Unit functions ia 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.

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

l. 3/4.6.5 SHIFT n BUILDING 3/4.6.5.1 EMERGENCY VENTILATION SYSTEhi The OPERABILITY of the emergency venti!ation 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. Tht.proner functionine of the EVS fam. damners. filters. adsorbers. etc.. as a system is verifigd by the ability of each train to nroduce the reauired system flow rare.

DAVIS-BESSE, UNIT I B 3/4 6-4 Amendment No. 66,167,183, Correction Lir dated 5/17/94 i

Docket Number 50-346 License Number NPF-3

" Serial Number 2589

'}

Attachment, Page 10 CONTAINMENT SYSTEMS BASES 3/4.6.5.2 SHIELD BUILDING INTEGRITY Shield buildine inteerity SH'" "S!O EUII DING SF'EORM cnsures that the release of radioactive material from the containment vessel will be restricted to those lea associated leak rates assumed in the safety analysis. The closure of the airtight doors and blowout panels listed in Table 4.6-1 ensure that the Emergency Ventilation System provide a negative pressure between 0.25 and 1.5 inches Water Gauge within the annulus between the shield building and containment vessel and within the interconnecting m penethation rooms after a loss-of-coolant accident (LOCA). This restriction, in conjunctio the operation of the EVS, will limit the site boundary radiation doses to within the limits o(

10 CFR 100 during accident conditions.

In the event shield building inteeritv. includine the canability of the EVS to orovide a necative cressure of ereater than or eaual to 0.25 inches Water Gaune. is n

! buildine integrity must be restored within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Twenty-four hours is a reasonable comnietion time considerine the limited leaknee design of the containment and the low probability of a Design Basis Accident occurrine during this time oeriod.

3/4.6.5.3 SHIELD BUILDING STRUCTURAL INTEGRITY Deleted l

t 1

i i

l

! )

DAVIS-BESSE, UNIT 1 B 3/4 6-5 Amendment No. 135,205 I

ML20205E503

Text

Navigation menu

Search