Text

Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor
	ML20210G916
Person / Time
Site:	Davis Besse
Issue date:	07/26/1999
From:	; CENTERIOR ENERGY
To:	;
Shared Package
ML20210G718	List: ML20210G715; ML20210G883; ML20210G916;
References
	NUDOCS 9908030231
	Download: ML20210G916 (29)
	v • d • e

LAR 99-0002 INDEX Page 18 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL POWER IMB ALANCE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 2-1 3/4.2.2 NUCLEAR HEAT FLUX HOT CHANNEL FACTOR - Fo. . . . . . . . . 3/42-5 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - F% . 3/4 2-7 3/4.2.4 QUADRANT POWER 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 . . . . . . 3/43-1 3/4.3.2 S AFETY SYSTEM INSTRUMENTATION Safety Features Actuation System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/43-9 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 becre D:::::cr; Dekted. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-35 Del e ted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-37 Del e t ed . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-40 l Remote Shutdown Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-43 Post-Accident Monitoring Instrumentation . . . . . . . . . . . . . . . . . . . . . . 3/4 3-46 Deleted j "l=:: O= Systen: Oxygen Mee w-Deleted. . . . . . . . . . . . . . . . . . . . . 3/4 3-57 i 3/4.4 REACTOR COOLANT SYSTEM l 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/44-1 Shutdown and Hot Standby . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3/44-2 3/4.4.2 S AFETY VALVES - SHUTDOWN . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-3 3/4.4.3 SAFETY VALVES AND PILOT OPERATED RELIEF VALVE -

O PERATIN G . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/44-4 9900030231 990726 PDR ADOCK 05000346 P PDR '

DAVIS-BESSE, UNIT I IV Amendment No. 38,86,134,135, 167,170,174,201,

LAR 99-0002 Page 19 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4.4 PRES S URIZER. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/44-5 3/4.4.5 STEAM G ENERATORS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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 CH EM ISTRY Deleted. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-17 3/4.4.8 S PECIFIC ACTIVITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-20 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-24 Pre s su ri ze r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-29 3/4.4.10 STRUCTURAL INTEGRITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-30 3/4.4.11 De l e t ed . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...... 3/4 4-32 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 CORE FLOODING TANKS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 5-1 3/4.5.2 ECCS SUB S YSTEMS - T.v, 2 280 F. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/45-3 3/4.5.3 ECCS SUBS YSTEM S - T.yg < 280 F. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 5-6 3/4.5.4 BORATED WATER STORAGE TANK. . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 5-7 1

i DAVIS-BESSE, UNIT 1 V Amendment No. 135,201,

LAR 99-0002 Page 20 INDEX BASES SECTION PAGE 3/4.0 A P PLIC A B ILITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 DORATION 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 S YSTEMS 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 S AFETY VALVES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-1 3/4.4.4 PRES S URIZER. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-2 3/4.4.5 STEAM G ENERATORS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE . . . . . . . . . . . . . . . . . . . . . B 3/4 4-4 3/4.4.7 CHEMISTRY Deleted . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-5 3/4.4.8 S PECIFIC ACTIVITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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 3/4.4.1 1 Del et ed. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-13 DAVIS-BESSE, UNIT 1 IX Amendment No. 135,201,

LAR 99-0002 Page 21 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION HONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm / trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

a. With a radiation monitoring channel alarm / trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to withir, the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the chansvi inoperable,

b. With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes at the frequencies shown in Table 4.3-3.

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TABLE 3.3-6 (Continued) l TABLE NOTATION l ACTION 21 -

Vith the number of channels OPERABLE less than required by I the Minimum Channels OPERABLE requirement, comply with the l ACTION requirements of Specification 3.4.6.1. l ACTION 22 -

Vith the number of channels OPERABLE less than required by I the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12.

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LAR 994)002 Pag 230 REACTOR COOLANT SYSTFAi 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System leakage detection systems shall be OPERABLE:

a. S:::c-9=n:::n=phere peni ! :: radicacti.::y :ne "cc:ng :y :::n, ab. The containment sump level and flow monitoring system, and be. OneJFhe containment atmosphere gaseews radioactivity monitoring y:::: :.Jeaseous or oarticulatel APPLICABILITY: MODES 1,2,3 and 4.

ACTION:

a. With the reauired containment sumn level and flow monitorine system inonerable. oneration may continue un to 30 davsprovided Surveillance Reqqhgment 4.4.6.2.1.d is nerformed at least ong,q per 24 houm

b. With the remJred contaimnent atmosobere radioactivity monitor inonerable. oneration may spntinue un to 30 davggylded; I. Containment atmosnhere crab samnles are obtained and analyzed at least once ner 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

QI

2. Survdllance Requirement 4.4.6.2.1.d is nerformed at Iggstonctner 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

p. With the above reauired ACTION and associated comnletion time not m_qLie 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 followine 30 hogre

d. With the reauired containment atmosnhere radioactivity monitor and the containment sumn level and flow monitorine system inonerable. enter TS 3.0.3 immediatelv.

Wi:': caly :vec cf S :Seve required 1 :Lage de:':::ica sy;::= OPERABLE, cperatica =y continue for up :c 30 day:; provided grab =p!= :: c5::dned : nd en::!y=d a: le=: ene per 21 curr ; her 1:

quired g=:cus c: p;nicub:: radicact: ::y :-hcring :.y20: : : . :ncper;5!:; cSer = 5: : : a: ! =:

HOT STAMDBY "hh 'h: nex 6 hc= and in COLD SHL"DO" .."'" ;it fe!!c. ing ?O Fcurr SURVEILLANCE REQUIREMENTS 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by:

a. Containment atmosphere particulate monitoring system-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3.

DAVIS-BESSE, UNIT 1 3/4 4-13 Amendment No.

LAR 99-0002 INFORMATION ONLY REACTOR C00 TANT SYSTEM SURVEllt ANCF REQUIREMENTS (Continued)

b. Containment sump level and flow monitoring system-performance of CIWINEL CALIBRATION at least once cach REFUELING INTERVAL. l

c. Containment atmosphere gaseous monitoring system-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3 1

i DAVIS-BESSE, UNIT 1 3/4 4-14 Amendment No. 218

LAR 99-0002 Page 32 INFORMATION ONLY REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System. leakage shall be limited to:

a. No PRESSURE B0UNDARY LEAKAGE,

b. 1 GPM UNIDENTIFIED LEAKAGE,

c. 150 GPD primary-to-secondary leakage through the tubes of any one l steam generator,

d. 10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System,

c. 10 GPM CONTROLLED LEAKAGE, and

f. 5 GPM leakage from any Reactor Coolant System Pressure Isolation Valve as specified in Table 3.4-2.

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

a. With any PRESSURE B0UNDARY LEAKAGE, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the fol. lowing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 except as permitted by paragraph c below. j

c. In the event that integrity of any pressure isolation valve specified in Table 3.4-2 cannot be demonstrated, POWER OPERATION may continue, provided that at least two valves in each high pressure line having a non-functional valve are in and remain in, the mode corresponding to the isolated condition.(a)

d. The provisions of Section 3.0.4 are not applicable for entry into MODES 3 and 4 for the purpose of testing the isolation valves in Table 3.4-2.

" Motor operated valves shall be placed in the closed position and power supplies deenergized.

DAVIS-BESSE, UNIT 1 3/4 4-15 Ordee-dt4W20/8 Amendment No. 436dB0220

X LAR 99-0002 Page 33 INFORMATION ONLY REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.6.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:

a. Monitoring the containment atmosphere gaseous or particulate radioactivity at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. Monitoring the containment sump level and flow indication at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c. Measurement of the CONTROLLED LEAKAGE from the reactor coolant pump seals to the makeup system when the Reactor Coolant System pressure is 2185 i 20 psig at least once per 31 days.

d. Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during steady state operation.

e. An evaluation of secondary water radiochemistry for determination of primary to secondary leakage through the steam generators at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during steady state operations.

4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-2 shall be individually demonstrated OPERABLE by verifying leakage testing (or the equivalent)'to be within its limit prior to entering NODE 2:

a. After each refueling outage,

b. Whenever the plant has been in COLD SHUTDOWN for 7 days, or more, and if leakage testing has not been performed in the previous 9 months, and

c. Prior to returning the valve to service following maintenance, repair or replacement work on the valve.

d. The provisions of Specification 4.0.4 are not applicable for entry into MODES 3 or 4.

4.4.6.2.3 Whenever the integrity of a pressure isolation valve listed in Table 3.4-2 cannot be demonstrated, determine and record the integrity of the high pressure flowpath on a daily basis. Integrity shall be determined by performing either a leakage test of the remaining pressure isolation valve, or a combined leakage test of the remaining pressure isolation valve in a series with the closed motor operated containment isolation valve. In addition, record the position of the closed motor-operated containment isolation valve located in the high pressure piping on a daily basis.

Order-dated 4/20/81 DAVIS-BESSE, UNIT 1 3/4 4-16 Amendment No. 64rl-35,180,196r 220

LAR 99-0002 Page 34 INFORMATION ONLY TABLE 3.4-2 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES VALVE NUMBERS (b) HAXIML'4 ALLOWABLE L'EAXAGE (a)(c)

. SYSTEM I 1

Decay Heat Removal CF-30 1 5 0 gpm' l

1. )

Decay Heat Removal CF-31 1 5 0 gpm i 2.

OH-76 1 5 0 gpm l

3. Decay Heat Removal Decay Heat Removal DH-77 1 5.0 gpm 4.

Notes:

(a) 1. Leakage rates less than or equal to 1.0 gpm are considered acceptable.

2. Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are considered acceptable if the latest measurtd rate has not exceeded the rate determined by the previous test by an amount that rtduces the rargin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.

3. Leakage rates greater than 1.0 gpm out less than or equal to 5.0 sps are considered unacceptable if the latest measured rate exceeded the rate determined by the previour test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.

4. Leakage rates greater than 5.0 gpm art considered unaccept'ahle.

(b) Valves CF-30 and CF-31 will be tested with the Reactor Coolant system pressurt >1200 psig. Valves OH-76 and DH-77 will be tested with normal Core Flooding Tank pressure which is >S75 psig. Mini-num differential test pressure across each valve shall not be less than 150 psid.

(c) To satisfy ALAPA requirements, leakage may be measured indirectly (as from the performance of pressure indicators) if acccmplished in accordance with appr12Ved procedures and supported by computations showing that the method is capable of demonstrating valve comp 1tance with the leakage criteria.

I DAVIS-BESSE, UNIT 1 3/4 a-16a Order dtd. 4/20/81

LAR 99-0002 Page 35 D., U.A.(W. A,, D,, t'A, A. ~ T. ..A. M. . T. C,. V. .O,T. n. k.A.

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(Pages 3/4 4-17 through 3/4 4-19 have been deleted.)

The next page is 3/4 4-20.

DAVIS-BESSE, UNIT 1 3/4 4-17 Amendment No.

r

LAR 99-0002 Page 36 TARIE4-44 REAGTOR-COObANT SYSTEM GHRMIST4W-MMIT6 STEADY STATE TRANSIENT PARAMETER hiMIT IJMIT DISSG1WEDOXYGEN" GOJOppm f 1.00 ppm GHbOR4DE G04& ppm FbOGRIDE GO.-14f pm

% mi

%>m

'bimiHiet-applicablMh4'ag c 250?44 DAV48-BESSEd4 NIT-4 3/1

IS

l

! LAR 99-0002 Page 37 T.A.D. .T. .C., A A, O E A.M, A,,D P,~IM,LA

. . A. ,TT. .O. V. .O.T. C. 1. .X.

CIl.. C. 1.X. T O,T. D. , V. T. T.

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PARAMETER ANAM'S!c rnF@UFM DISSOLNED4X-YGEN* At-least cr.cc cac4t424teurs

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GHIBRIDE At4eastence eac!: 72 !: cum N

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LAR 99-0002 Page 38 RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE (Hydrogen rich systems not designed to withstand a hydrogen explosion)

LIMITING CONDITION FOR OPERATION 3.11.2 The concentration of oxygen in the waste gas system shall be limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.

APPLICABILITY: At all times.

ACTION:

a. With the concentration of oxygen in the waste gas system greater than 2% by volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above limits, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b. With the concentration of oxygen in the waste gas system greater than 4% by volume and the hydrogen concentration greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 2% by volume without delay,

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2 The concentrations of oxygen in the waste gas system shall be determined to be within the above limits by monitoring the waste gases in the waste gas system, as required by S;=if.caticr. 3.3.3.0.

l l

DAVIS-BESSE, UNIT 1 3/4 11-2 Amendment No. 86,170,

LAR 99-0002 Page 39 3/4.3 INSTRUMENTATION BASES 3/43.3 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 Deleted The OPERABILITY cf the in:cre de::::cr:; nsures hat he n;;;:;ure:r. nts obtained fre:n un of thi ;y:;:::r. accura::!y repre=n: the spatial neutron flux distributica cf the reae:ct ecre. See Bases Figures 31 and 3 2 for exa:nples of acceptab!: n.ini:num in:cre dete :cr arrange:nent; 3/4.3.3.3 SEISMIC TNSTRUMENTATION Deleted 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION Deleted 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 I B 3/4 3-2 Amendment No. 201, !

{

LAR 99-0002 Page 40 4

LACK R ADI AL

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t -- a ipm M Inom In8Tumenteden Specifkstion Assertable Minlawm OUADRANT POWER Tit =T Arrangement ,

Drkted DAVIS 4 ESSE, UNP' 1 B 3/13 5

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LAR 990002 Page 42 INSTRUMENTATION BASES 3/4.3.3.9 WASTE GAS SYSTEM OXYGEN MONITOR

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DAVIS-BESSE, UNIT 1 B 3/4 3-4 E 3/13 6 Amendment No. 86,170, '

LAR 99-0002 INFORMATION ONLY .

REACTOR COOLANT SYSTEM BASES l 1

3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS l

The RCS leakage detection systems required by this specification are '

provided to detect and monitor leakage from the Reactor Coolant Pressure Boundary. These detection systems are consistent with the recommendation of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973.

3/4.4.6.2 OPERATIONAL LEAKAGE PRESSURE B0UNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative'of an impending gross failure of the pressure boundary.

Therefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN. {

I Industry experience has shown that, while a limited amount of leakage is <

expected from the RCS, the UNIDENTIFIED LEAKAGE portion of this can be reduced to a threshold value of less that 1 GPM. This threshold value is sufficiently low to ensure early detection of additional leakage.

The steam generator tube leakage limit of 150 GPD through any one steam generator ensures that the dosage contribution from tube leakage will be limited to a small fraction of 10 Cts Part 100 limits in the event of either a steam generator tube rupture or steam line break. A 1 GPM total primary to secondary leakage limit is used in the analysis of these accidents.

The 10 GPM IDENTIFIED LEAKAGE limitation provides allowance for a limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.

The CONTROLLED LEAKAGE limit of 10 GPM restricts operation with a total RCS leakage from all RC pump seals in excess of 10 GPM.

The surveillance requirements for RCS Pressure Isolation Valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA. Leakage from the RCS Pressure Isolation Valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.

I DAVIS-BESSE, UNIT 1 B 3/4 4-4 Amendment No. -1607 220

LAR 99-0002 Page 44 REACTOR COOLANT SYSTEM BASES 3/4.4.7 CHEMISTRY Deleted T.u~_.. i. :.~

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3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months doses at the site boundary will not exceed an appropriately small fraction of the Part 100 limit following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM. The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRC of typical site locations. These values are conservative in the specific site parameters of the site, such as site boundary location and meteorological conditions, were not considered in this evaluation. The NRC is finalizing site specific criteria which will be used as the basis for the reevaluat. ion of the specific activity h.mi.ts of th.is site. This reevaluation may result m h.igher limits.

DAVIS-BESSE, UNIT 1 B 3/4 4-5 Amendment No.

1 LAR 99-0002 Page 45 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIOUID HOLDUP TANKS Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.

~

3/4.11.2 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas treatmer.: system is maintained below the flammability limits of hydrogen with oxygen. Maintaining the concentration of hydrogen or oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

The concentrations of oxycen in the waste cas system is determined to be within accentable limits by monitorine the waste cases in the waste cas system as reauired by the USAR Technical Reauirements Manual

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DAVIS-BESSE, UNIT 1 B 3/4 11-1 Amendment No. 86,135,170, 1

j

Docket Number 50-346 License Number NPF-3 Serial Number 2608 Enclosure 2 COMMITMENT LIST THE FOLLOWING LIST IDENTIFIES THOSE ACTIONS COMMITTED TO BY THE DAVIS-BESSE NUCLEAR POWER STATION (DBNPS) IN THIS DOCUMENT.

ANY OTHER ACTIONS DISCUSSED IN THIS SUBMITTAL REPRESENT INTENDED OR PLANNED ACTIONS BY THE DBNPS. THEY ARE DESCRIBED ONLY FOR INFORMATION AND ARE NOT REGULATORY COMMITMENTS.

PLEASE NOTIFY THE MANAGER - REGULATORY AFFAIRS (419-321-8466) AT THE DBNPS OF ANY QUESTIONS REGARDING THIS DOCUMENT OR ANY ASSOCIATED REGULATORY COMMITMENTS.

COMMITMENT DUE DATE

1. Relocate TS 3/4.3.3.2,3/4.3.3.9 and 3/4.4.7 These changes are to be implemented to the DBNPS Updated Safety Analysis within120 days after NRC approval Report Technical Requirements Manual. of the License Amendment, and no ;

later than the removal of TS 3/4.3.3.2, 3/4.3.3.9 and 3/4.4.7 from the TS.

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