ML20155D779

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Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition
ML20155D779
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 10/27/1998
From:
CENTERIOR ENERGY
To:
Shared Package
ML20155D770 List:
References
NUDOCS 9811040022
Download: ML20155D779 (10)


Text

LAR 98-0010

~ Page 10 INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS DEFINED TERMS.......................................................

1-1 THERM AL PO WER..................................................

1-1 RATED THERM AL POWER..............................................

1-1 OPERATIONAL MO DE.................................................,

1-1 ACTION...............................................................

-11 OPERAB LE - OPERABILITY.............................................

1-1 REPORTAB LE EVENT...................................................

1-2 CONTAINMENT INTEGRITY.............................................

1-2 CHANNEL CALIBRATION......................

1-2 CHANNEL CHEC K.....................................................

1-2 CHANNEL FUNCTIONAL TEST........................................

1-3

)

C ORE ALTERATION................................................

1-3 S H UTDOWN M ARGIN..................................................

1 IDENTIFIED LEAKAGE................................................

1-3 UNIDENTIFIED LEAKAG E...............................................

1-4 PRESSURE BOUNDARY LEAKAGE.......................................

1-4 CONTROLLED LEAKAGE...............................................

1-4

. QUADRANT POWER TILT..............................................

1-4 j

DOSE EQUIVALENT I-131..............................................

1-4 E-AVERAGE DISINTEGRATION ENERGY................................

1-4 STAGGSRED TEST B ASIS................................................

1-5 FREQUENCY NOTATION............................................

1-5 AXIAL POWER IM BALANCE............................................

1-5

. DRI F.TEDm'IIT_Ct n D_1 T.i.f n_ yhtr' T. AT".fT.~AD. T.T. V..'..............................

4-6 C

.. ~.

REACTOR PROTECTION SYSTEM RESPONSE TIME........................

1-5 SAFETY FEATURE RESPONSE TIME....................................

1-6 PH YS ICS TESTS.......................................................

1-6 STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM RFJPONSE TIME...

1-6 i

PROCESS CONTROL PROGRAM......................................

1-6a

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tu 9811040022 981027 I PDR A."DCK 05000346:

P PDR a.

DAVIS-BESSE, UNIT 1 I

Amendment No. 38,86,93,170,.

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LAR 98-0010 Page11

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DEFINITIONS per disintegration (in MeV) for isotopes, other than iodines, with half lives greater than l

15 minutes, making up at least 95% of the total non-iodine activity in the coolant.

- STAGGERED TEST B ASIS -

-1.21 A STAGGERED TEST B ASIS shall consist of:

a.

A test schedule for n systems, subsystems, trains or designated components obtained by dividing 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 1.22 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.

AXIAL POWER IMBALANCE 1.23 AXIAL POWER IMBAL,ANCE shall be the THERMAL POWER in the top half of the core expressed as a percentage of RATED THERMAL POWER minus the i

THERMAL POWER in the bottom half of the core expressed as a percentage of RATED THERMAL POWER.

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SHIELD BUILDING IFEORITY 1.24 DELETED SHIELD BUILDING INTEORID' take*is: v hen 3.

The airtight decra and-the b!cvecu: panels !!:ted in Tab!: 1.5 : are c!csed except de airtight decr may be used for normal transi: entry and exi:

b. The emergency venti!a:!ca sys:em is OPERABLS:
c. S :caling mechanism associa:cd vi$ cach penetration (e.g., velds, be!!nws-er O rings)is OPERABLE.

i REACTOR PROYECTION SYSTEM RESPONSE TIME 1.25 The REACTOR PROTECTION SYSTEM RESPONSE TIME shall be that time interval frorr when the monitored parameter exceeds its trip setpoint at the channel sensor until power interruption at the control rod drive breakers.

DAVIS-BESSE, UNIT I l-5 Amendment No.

LAR 98-0010 INFORMATION ONLY CONTAINMENT SYSTEMS 3/4.6.5 SHIELD BUILDING EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION

]

3.6.5.1 Two independent emergency ventilation systems shall be OPERABLE.

APP.LICABILTI'Y: 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 l

SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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 adsorbers 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:

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

LAR 98-0010

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Page 13

. CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) u 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 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 i 10%;

1 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 Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing 1

criteria of Regulatory Position C.6.n* of Regulatory Guide 1.52, Revision 2, March

~

1978, for a methyliodide penetration ofless than 1%; and 3.

Verifying a system flow rate of 8,000 cfm i 10% during system operation when tested in accordance with ANSI N510-1980.

After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying, within 31 days after c.

removal, that a laboratory analysis of a representative carbon samp:e obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing 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 filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the system at a flow rate of 8,000 cfmi 10%;

2.

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

Verifying tha, %e filter cooling bypass valves can be manually openedgend

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  • The test is performed in accordance with ASTM D 3803-1979 with the following conditions:
1) equilibrate for 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> at 30 Cn07o relative humidity'(RH),2) challenge for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 30 CSO% RH,3) elution for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 30 Cn0% RH.

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

- LAR 98-0010 Page 14 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

4. Deleted _V: ifying :'-: ::ch sy;:::n p:cdurez a nega::ve pre =ure cf g ::::: Sun c:

eque' :c 0.25 :n:h:2 "la::: 0;;;;i:'he annu!u. "9 4 :: cent afte:'h fan

in:

f'.cv/ =:e of S^^^ :fm : 10%. Thi;:::: is :c be p :fermed

.S de f'cv.

p;S :::,^'"": d p:ic:'c :: fng Se EVS far, and de cSer & uper r ~cej.::d..;S the-ewga&c p :=ure beun& y-eloseek e.

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

f.

After each complete or partial replacement of a charcoal adsorber bank, by verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria ofless than 1% in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 8000 cfm 210%.

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

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LAR 98-0010 q,

' Page 15 :

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-CONTAINMENT SYSTEMS SHIELD BUILDING INTEGRITY LIMITING CONDITION FOR OPERATION

=

3.6.5.2 Shield buildine intecrity SH! ELD BUILD!'!O !" TEOR!TY shall be maintained.

APPLICABILFfY: MODES 1 7,3 and 4

' ACTION:

LWithout shield buildine intecrity SHIELD BUILD!'!O !"TEOPJTY, restore shield buildine intecrity SHIELD BUILD!MO '"TEORITY within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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. The provisions of Snecification 3.6.5.1 are not annlicable.

- SURVEILLANCE REQUIREMENTS I

4.6.5.2d Shield buildine intecrity SPIELD BU!LD!'!O INTEORITY 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 closed except when the airtight doors are being used for normal transit entry and exit.

- 4.6.5.2.2 Shield buildina intearity shall be demonstrated at least once ner REFUELING

' INTERVAL by verifyine that each Emercency Ventilation System train produces a

_ negative pressure of creater than or eaual to 0.25 inches Water Gaune in the annulus within 4 seconds after the fan attains a flow rate of 8000 cfm 10%. This test is to be

. Derforms.si with the flow nath established orior to starting the EVS fan. and the other

._ damners associated with the necative cressure boundary closed.

DAVIS-13ESSIL UNIT 1 3/4 6-31 Amendment No.

3 LAR 98-0010 Page 16 INFORMATION ONLY l

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Page 3/4 6-32 Deleted.

Next page is 3/4 6-33.

DAVIS-BESSE, UNIT 1 3/4 6-32 Amendment No. 93,205 r-e.,,

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- LAR 984)010 -

Page 17 '

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~ TABLE 4.6-1 l

. ACCESS OPENINGS REQUIRED TO BE CLOSED TO ENSURE SHIELD BUILDING INTEGRITY

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AIR TIGHT DOORS QQOR NO.

DESCRIPTION ELEVATION

100 Access Door from the No.1 ECCS Pump Room 545' (Room 105) to Pipe Tunnel 101

'104A -

Access Door from Stair AB-3 to the No.1 555' ECCS Pump Room (Room 105) s 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 i15) to the Miscellaneous Waste Monitor Tank and Pump Room (Room 114) a 108 Access Door from the No. 2 ECCS Pump Room 555' (Room i15) to the Detergent Waste Drain Tank and Pump Room (Room 125) 201-A Access Door from Corridor 209 to the No. I 565' Mechanical Penetration Room (Room 208) 204

' Access Door from Passage 227 to the Makeup 565' Pump Room (Room 225) 205 Access Door from Passage 227 to the No. 2 565' Mechanical Penetration Room (Room 236) j 307

. Access Door from Corridor 304 to the No. 3 585' Mechanical Penetration Room (Room),Sj-308) 308 Accesa Door from Corridor 304 to the No. 4 585'

- Mechanical Penetration Room (Room 314)

II.

BLOWOUT PANELS l

' TOTAL NO..

LOCATION ELEVATION 1

No. 2 Mechanical Penetration Room 565'

[

L(Room 236) 6 No. 3 Mechanical Penetration Room 585'

(Room 303)

-6.

No. 4 Mechanical Penetration Room 585'

- (Room 314)

. DAVIS-BESSE, UNIT 1 :

3/4 6-33 Amendment No.-

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< LAR 98-0010 s

Page 18 CONTAINMENT SYSTEMS BASES 3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the Hydrogen Analyzers, Containment Hydwgen Dilution 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 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 contaimaent vessel, resulting in a pressurization of the containment and suppression of the hydrogen volume fraction.

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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.

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 L

The OPERABILITY of the emergency ventilation systems ensures that containment i

vessel leakage occurring during LOCA conditions into the annulus will be filtered through the l

HEPA filters and charcoal adsorber trains prior to discharge to the atmosphere. This requirement l.

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 200 during LOCA conditions. Ibaggpg functioning of the EVS fans. damners. titters. adsorbers. etc..jts a_sntemis3crifiedhvJhe4dlity l

of_each train to nroduce the reaulted system flow rate.

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DAVIS-BESSE, UNIT 1 B 3/4 6-4 Amendment No. 66,167,183, Cortection Ltr dated 5/17/94 n

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  • , LAR 98-0010 Page 19 CONTAINMENT SYSTEMS BASES 3/4.6.5.2 SHIELD BUILDING INTEGRITY ShicM_bididine intecrity SHIELDING BULDING INTEORITY ensures that the release of radioactive material from the containment vessel will be restricted to those leakage paths and 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 (EVS) can 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 mechanical penetration rooms after a loss-of-coolant accident (LOCA). This restriction, in conjunction with the operation of the EVS, will limit the. site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

In_the event shield buildine integrity. includine the canability of the EVS to orovide a ncentive cressure of creater than or eoual to 0.25 inches Water Gauce. is not maintained. shield huildine intecrity must be restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Twenty-four hours is a reasonable completion time considerinz the limited leakace desien of the containment and the low pigbability of a Design Basis Accident occurrine durine this time oeriod.

3/4.6.5.3 SHIELD BUILDING STRUCTUR AL INTEGRITY Deleted l

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

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