ML17278A499

Proposed Tech Spec 3/4.3.5, RCIC Sys Actuation Instrumentation, Reflecting Downgrade Resulting from Mods to Automatic Depressurization Sys Logic

ML17278A499
Person / Time
Site:	Columbia
Issue date:	12/05/1985
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17278A498	List: ML17278A497 ML17278A499
References
TAC-59820, NUDOCS 8512100101
Download: ML17278A499 (19)

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INSTRUMENTATION 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONOITION FOR OPERATION 3.3.5 The reactor core isolation cooling (RCIC) system actuation instrumenta-tion channels shown in Table 3.3.5"1 shall be OPERABLE with their trip set-points set consistent with the values shown in the Trip Setpoint column of Table 3.3.5-2.

APPI ICABILITY: OPERATIONAL CONOITIONS 1, 2 and 3 with reactor steam dome pressure greater than 150 psig.

ACTION:

a. With a RCIC system. actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.5-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the TrtpWSetpoint value.

b. With one or more RCIC systemactuation instrumentation channels inoperable, take the ACTION~'required by Table 3. 3. 5-1.

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SURVEILLANCE RE UIREMENTS 4.3.5. 1 Each RCIC system actuation instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATIOH operations at the frequencies shown in Table

4. 3. 5 1-1.

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4.3.5.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

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TABLE 3. 3. 5-1 REACTOR CORE ISOLATION COOLING SYSTEH ACTUATION INSTRUHENIATION HINIHUH OPERABLE CIIANHEL)

FUNCTIONAL UNITS PER TRIP SYSTEH ACTION

a. Reactor Vessel Mater Level - Low Low, Level 2 50

b. Reactor Vessel Mater Level - lligh, Level 0 2(b) 51 C. Ta>>k Mater Level - Low Low 2 c

d. Ha>>ual Initiation 53 placing the trip system in the tripped condition provided 4't~ least one other Ol'ERADLE channel in the same trip system is monitoring that parameter.

(h) One trip system with two-out-of-two logic.

(c n s stem with one-ont- - glc.

(d) system with one charm

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TABLE 3.3.5-1 (Continued)

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION STATEMENTS ACTION 50 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement:

a. For one trip system, place the inoperable channel(s) and/or that trip system in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or

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With the number of OPERABLE channels less than rdquired by the Trip System requirement;dea'~~

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minimum OPERABLE

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T N 2- Ws th t e num er of A L c anne s ess than requs re Minimum OPERABLE Channels pegTiip System requirem, ace t, ast one inoperable chanel in their'ed condition within ou or declare tQ RGB-system inoperable.

ACTION 53 " With the numb ERAB ha els one less than required by thee n. m OPERABLE"Channels per r tern requirement, restore the inoperable'hannel to OPERABLE s 'thin 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declareq,the RCIC system inoperable.

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TABLE 3.3.5-2 REACTOR CORE ISOLATION COOLING SYSTEtl ACTUATION INSTRlJI1ENTATION SETPOIHTS ALLOWABLE FUNCTIONAL UNITS TRIP SETPOINT VALUE

a. Reactor Vessel Mater Level - Low Low, Level 2 > - 50 inches" > -57 inches

b. Reactor Vessel Mater Level - Nigli, Level 0 < 54 5 inches" < 56 inches C. 0 torage Tank Level - Low Low"" > 448 ft 3 in. > 448 f ft 6 it-la-t-'.A.

elevation evation (1 in.

I evel) tank level )

d. Hanua l See Oases Figure 0 3/4 3-1.

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TABLE 4.3.5.1-1 REACTOR CORE ISOLATION COOLING SYSTEH ACTUATION INSTRUHENTATION SURVEILLANCE RE UIREHENTS CHANNEL CflANNEL FUNCTIONAL CHANNEL FUNCTIONAL UNITS C I IEC K TEST CALIBRATION

a. Reactor Vessel Mater Level-(Low Low, Level 2) tr. Reactor Vessel Matev Level - lligh, Level (8) torage Tank Level - Low R

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P NT SYSTEMS SURVE LANCE REOUIREMENTS- Continued C. t least once per 18 months by:.

Performing a system functional test which i eludes simulated utomatic actuation and restart and verify ng that each agtomatic valve in the flow path actuate to its correct posjtion. Actual injection of coolant nto the reactor vessel may. be excluded.

2. Verify> g that the system will dev op a flow of greater than or equal to 600 gpm in the test f ow path when steam is supplied the turbine at a pry sure of 150 + 15, -0 psig."

3. Verifying th the suction f Wthe RCIC system is automatically transferred'fr the conden ate storage tank to the suppression pool on a conde ate stor e tank water level-low signal.

"The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure i adequate to perform the tests.

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INSTRUMENTATION EWjitg~

BASES 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMEHTATIOH The reactor core isolation cooling system actuation instrumentation is gcptaee, provi e initiate actions to assure adequate core cooling in th of reactor isolate the reactor vessel wit om its primary heat sink and the loss oviding actuation of water flow to the emergency core wd ed.

cooling equipment.

Operation with a tr ess conservative its Trip Setpoint but within its speci lowable Value is acceptable on t e 's that the differe ween each Trip Setpoint and the Allowable Value is u to or han the drift allowance assumed for each trip in the safety analyse .

3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATIOH The control rod block functions are provided consistent with the require-ments of Specifications 3/4. 1.4, Control Rod Program Controls, 3/4.2, Power Distribution Limits and 3/4.3. 1" Reactor Protection System Instrumentation.

The trip logic is arranged so thang trip in any one of the inputs will result in a control rod block.

Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is~acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal to or less than the drift allowance assumed for/each trip in the safety analyses.

3/4. 3. 7 MONITORING INSTRUMENTATION 3/4. 3. 7. I RADIATION NONI TURING INSTRUNENTATIOM.Q The OPERABILITY of the radiation monitoring instrumentation ensures that; (1) the radiation levels are continually measured in the areas served by the individual channels; (2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and (3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with 10 CFR Part 50, Appendix A, General Design Criteria 19, 41, 60, 61, 63, and 64.

3. 4. 3. 7. 2 SEISMIC MONITORING INSTRUMEHTATION The OPERABILITY of the seismic monitoring instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.

This capability is required to permit comparison of the measured response to that used in the design basis for the unit. This instrumentation is consistent with the recommendations of Regulatory Guide 1. 12, "Instrumentation for Earthquakes," Apri 1 1974.

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3/4.7 PLANT SYSTEMS BASES 3/4.7. 1 SERVICE WATER SYSTEMS The OPERABILITY of the service water systems ensures that sufficient cooling capacity is available for continued operation of safety-related equip-ment during norma'l and accident conditions. The redundant cooling capacity of these systems, assuming a single failure, is consistent with the assumptions used in the accident conditions within acceptable limits.

3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM The OPERABILITY of the control room emergency filtration 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 will remain habitable for operations per" sonnel during and following all design basis accident conditions. Continuous operation of the system with the heaters OPERABLE for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> during each 31-day period is sufficient to reduce the, buildup of moisture on the adsorbers and HEPA filters. The OPERABILITY of this~csystem in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rems op+less whole body, or its equivalent.

This limitation is consistent with thePequirements of General Oesign Criterion 19'f Appendix A, 10 CFR Part 50.

.7.3 REACTOR CORE ISOLATION-'COOLING SYSTEM Th eactor core isolati~o>cooling (RCIC) system is provided to ass adequate c cooling in the~event of reactor isolation from its prim heat sink and the s of feedwater flow to the reactor vessel without~ quiring actuation of any RCIC system is conse exceeds 150 psig. This pressure core cooling syste tively required to be OPERABLE whene essure is substantially below can provide adequate co

't the emeYgency core cooling system (ECCS) e uipment. The reactor pressure for which the low cooling for events requi~ing the RCIC system.

The RCIC 'system specifications a app 'cable during OPERATIONAL CONDITIONS 1, 2, and 3 when reactor vessel pressure ceeds 150 psig because RCIC is the p~ima~y non-ECCS source of emergency re co ing when the reactor is pressurized.

>>th the RCIC system ino able, adequate core ooling is assured by the OP'ERABILITY of the HpCS sy m and justifies the specs, ' 14 day out-of-service period.

The surveil~l ce requirements provide adequate assurance th RCIC will be OPERABLE w < required. Although all active components are tes e and full flow be demonstrated by recirculation during reactor operatio , a '

complet unctional test requires reactor shutdown. The pump discharge ps is m 'ntained full to prevent water hammer damage and to start cooling at the

.iest possible moment.

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/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM Is LIMITING CONDITION FOR OPERATION r ~

3.7.3 The reactor core isolation cooling (RCIC) system shall be:0 RABLE with an OPER LE flow pathcapable of automatically taking suction fro the suppress> n pool and transferring the water to the reactor pres re vessel.

APPLICABILI Y: OPERATIONAL CONDITIONS 1, 2, and 3 with reac r steam dome pressure grea er than 150 psig.

ACTION:

ip With the RCIC syst inoperable, operation may contin provided the HPCS system is OPERABLE; estore the RCIC system to OPERA E status within 14 days or be in at least HO SHUTDOWN within the next 12 urs and reduce reactor steam dome pressure to less than or equal to 150 sig within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.7.3 The RCIC system shall be demopstr ted OPERABLE:

a. At least once per 31 da b

1. Verifying by ventin thepggh point vents that the system .

piping from the p p ds charge;.Calve to the system isolation valve is filled th wat r.

2. Verifying tha each valve anual', pawer-operated, or automatic) in the flow ath that is not locked, soled, or otherwise secured in osition, is in it correct position.

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3. Veri fyi that the pump flow con ol 1 er i s in the correct positi n.

b. When tes d pursuant to Specification 4.0. by verifying that 'the RCIC pu p develops a flow of greater than o equal to 600 gpm in the t t flow path with a system head,corres onding to reactor vessel oper ting pressure when steam is being suppli to the turbine at 10 + 20, " 80 psig."

"Th provisions of Specification 4.0.4 are not applicable provide the s veillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pre ure is dequate to perform the test.

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