ML20126G989

Proposed TS 3/4.3.3.5, Instrumentation - Remote Shutdown Intrumentation & TS 6.9.2, Special Repts Adding Testing Requirements for Transfer Switches Used to Meet 10CFR50,App R (Fire Protection) Requirements

ML20126G989
Person / Time
Site:	Davis Besse
Issue date:	12/23/1992
From:	CENTERIOR ENERGY
To:
Shared Package
ML20126G981	List: ML20126G975 ML20126G982 ML20126G989
References
NUDOCS 9301050031
Download: ML20126G989 (9)

Text

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Docket Numbsr 50-346 License Number NPF-3 Serial Kamber 2101-Atttchment' Page 6 INSTRUMENTATION REMOTE SHUTDOWN INSTRUMENTATION t

LIMITING CONDITION FOR OPERATION J

[ 3 3.3.5.

0.0.;.: The remote shutdown monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with readouts displayed external to the co g rpeg.  %

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ACTION:

a. With the number of OPERABLE remote shutdown monitoring channels less than redrtd by Table 3.3 9, either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTOOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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The provisions of Specification 3.0.4 are not applicable. i

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SURVEILLANCE REQUIREMENTS

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4.0.0.5 ach remote shutdown monitoring instrumentation channel shall l

[ 7te demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL b (

b CALIBRAT . ION operations'at ,

__ - tne frequencies shown in Table 4.3-6.

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DAVIS-BESSE, UNIT 1 3/4 3-43 9301050031 921223 .

PDR ADOCK 05000346 p PDR

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' - . Docket Nu:bst 50-346-Licensa Nu2bar NPF-3 4 Ferial Nunbar 2101

Attachment Page 7 ,

Insert for new Lc0 3.3.3.5.2 The control circuits and transfer switches required for a serious control room or cable spreading room fire shall be OPERABLE.

l Insert for new Action b I Vith one or more control circuits or transfer switches required for a serious control room or cable spreading room fire inoperable, restore 4 the inoperable circuit (s) or switch (es) to OPERABLE status within 30 days, or prepare and submit a Special Report to the Commission pursuant i to Specification 6.9.2 within the next 30 days outlining the action j taken, the cause of the inoperability, and the plans and schedule for i restoring the circuit (s) or switch (es) to OPERABLE status, 1

Insert for new SR 4.3.3.5.2

' At least once per 18 months, verify each control circuit and transfer.

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switch required for a serious control roc = or cable -spreading room fire

is capable of performing the intended function.

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TABLE 3.3-9 $z*2 REMOTE SHUTDOWN MONITORING INSTRLMENTATION 35E5 Y E E

'n' N 528

" MIEllRSE 3 @ da READOUT MEASUREMENT nem e d, $

INSTRUMENT LOCATION RANCE OPEeaar e d

1. Reactor Trip Breaker Indicattom (a) 480v F&DC CN. 2

~ OFIN-CLOSE (a) 1 (Trip Breaker A)

Switchgear Roce i

(b) 480v E&DC CH. 1 (b) 1 (Trip Breaker 5) i i

Switchgear Room .

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(c) 480v F&DC CN. 2 (c) 1 (Trip Breaker C)

Switchgear Room (d) CRDC Cabinet Rees (d) I (Trip Breaker D) w 2. Reactor Ceolant Temperature - Not Leg Aux. Shut 4wn Fanel 1

L 520-420 *F 1 -

• 3. Reacter Coelant System Pressure Aum, Shutdown Fanel 0-3000 peig Q

4. Presouriser Level Amm. Shutdown Fame 1 0-320 inche immed i

5. Steam Generator Outlet Steen Fressure Aux. Shutdown Fame 1 0-1200 peig 1/eteam generator 7.

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, Centrol Red Foottise Switches Control Rod Drive 0, 25, 50. 7 rd  !

& Control Cabinets.

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• EST h REMOTE SBUTDOUN MONITORING INSTRUMENTATION SURVEILLANCR REQUIREMENTS "5"

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INSTRUMENT CBECK CALIBRATION

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1. -Reactor Trip Breaker Indication M N.A. .:

2. Reactor Coolant Temperature-Hot Legs M R

3. Reactor Coolant System Pressure M R

4. Pressurizer Level M R

• 5. Steam Generator outlet Steam Pressure M R w

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u. 6. Steam Generator Startup Range Level N R mM l

7. Control Rod Position Switches M N.A. O ay, I W "#3 C

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j Docket Number 50-346 j License Number NPP-3

. Serial Number 2101

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THIS PAGE PROVIDED j 3 /I. 1 NSTRUMENTATION 3ASES i

i l 2/4.3.2 MONITORING INSTRUMENTATION 3/a.2.2.1 2.ADIATION MONITORING INSTRUMENTAT!0ji

! The OPERABILITT of the radiation monitoring channels ensures that 1) the

! raaiation levels are continually measured in the areas served by tne

! individual channals and 2) the alara or automatic action is initiated when the

racistion level trip setpoint is exceeded.

2/4.3.3.0 INCORE DETECTORS

! The OPERABILITT of the incore detectors ensures that the sessurements cotained j from use ci this system accurately represent the spatial neutron flux i districution of the reactor core. See Bases Figures 3-1 and 3-2 for examples l

of acceptable minimum incore detector arrangements.

i 3/4.3.3.3 SEISMIC INSULUMENTATION

} The OPERASILITT of the seismic instrumentation ensures that sufficiant capacility is available to promptly determine the ensaitude of a seismic event so tnat the response of those featuras important to safety may be evaluated, i

This capability is required to 9:rnit comparison of the measured response to

! that used in the design basis for the facility. This instrumentation is

' consistent with the recommendations of Regulatory Guide 1.12 " Instrumentation j for Eartaquakes," April 1974.

l 3/4.3.3.4 METEOROLOGICAL INSTRUNINTATION The OP3ARILITT of the meteorological instrumentation ensures that sufficient meteorological data is available for estinating potential radiation doses to j the public as a result of routine or accidental release of radioactive j saterials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public. This instrumentation is consistent with the recoemendatioss of

Regulatory Guida 1.23 "Onsite Meteorological Programs," February 1972.

3/4.3.3.5 REMOTE SEUTDOVN INSTRUNINTATION The OPERABILITT of the remote shutdown instrumentation ensures tnat sufficient cacao 111ty is available to permit snutdown and maintenance of 1

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Docket Number 50-346

} Liconse Number NPF-3

] Ser4a1 Humber 2101 Attachment

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! 3/4.3 INSTRUMENTATION 3ASES i

EMOTE SHUTOOWN INSTRUMENTATION (Continued)

-0T STANDBY of the facility from locations outside of the control room.

This capability is required in the event control room habitability is lost c w<w s ftdMPT F! > AC t'ED 3/ D T3$6 N S E DENT ~M YOTORING INSTRUMENTATION j The OPERABILITY of the post-accident monitoring instrumentation ensures

nat sufficient information is available on selected plant carameters to monitor and assess these varisoles following an accident. The containment aydrogen Analyzers, althougn they are considered part of the plant cost-accident monitoring instrumentation, have their OPERABILITY requirements located in Specification 3/4.6.4.1. Hydrogen Analyzers.

3/4.3.3.7 CHLORINE DETECTION SYSTEMS - Deleted 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION Deleted d.

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AVIS-BESSE, UNIT 1 3 3/4 3-3 Amencmen: %. 3,32.!Z)32,15f,157,14 w r .,~-,

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j- Docket Numb 2r 50-346

' License Number NPF-3 l -Serial Number 2101

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Page 12 l

4-I Insert for TS 3/4.3.3.5 Bases l

SR 4.3.3.5.2 verifies that each Remote Shutdown System transfer switch l and control circuit required for a serious control room or cable

! ' spreading room fire performs its intended function.- This verification - --

j is performed from the remote shutdown panel and-local;y, as- 1 i appropriate. This vill ensure that if the control room becomes.

I inaccessible, the unit can be safely shutdown from the remote shutdown j panel and the local. control stations.

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Docket Numbar 50-346 License Number NPF-3 Serial Number 2101' Attaghment Page 12 ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Ccmission in accordance with 10 CFR 50.4 within the time period specified for eacn report. These reports shall 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.

b. Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

c. Inoperable Meteorological Monitoring Instrumentation Specification 3.3.3.4.

d. Seismic event analysis, Specification 4.3.3.3.2.

e. Deleted 4 Deleted ~

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. 5.10 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 i 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.

i. 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.

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DAVIS-3 ESSE, UNIT 1 6-18 Amenoment No. ?,72,65,26,70E.735 MOD

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Docket Nunbar 50-346 License Number NPF-3 Serial Number 2101 Attachment Page 14 Insert for New 6.9.2.g

g. Inoperable Remote Shutdown System control circuit (s) or transfer svitch(es) required for a serious control room or cable spreading room fire, Specification 3.3.3.5.2.

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