ML17278A424

Proposed Changes to Tech Specs 3/4.3.5 & 3/4.7.3 to Remove Requirements Re RCIC Sys,Reflecting Sys Downgrade as Result of Mods to Automatic Depressurization Sys Logic

ML17278A424
Person / Time
Site:	Columbia
Issue date:	10/04/1985
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17278A423	List: ML17278A422 ML17278A424
References
TAC-59820, NUDOCS 8510080207
Download: ML17278A424 (18)

Text

October 4, 1985 602-85-694 ATTACHMENT The following Technical Specification pages are attached to, and are a part of this amendment:

3/4 3-47 3/4 3-48 3/4 3-49 3/4 3-50 3/4 3-51 3/4 7-8 3/4 7-9 B3/4 3-4 B3/4 7-1

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INSTRUMENTATION 3/4. 3. 5 REACTOR CORE ISOLATIOH COOLING SYSTEM ACTUATION INSTRUMEHTATIOH MITING CONOITION FOR OPERATION

3. 3. 5 The reactor core isolation cooling (RCIC) system actuation i trumenta-tion ch nels shown in Table 3.3.5"1 shall be OPERABLE with their rip set"

points se consistent with the values shown in the Trip Setpoint olumn of Table 3.3. -2.

APPLICABILITY. OPERATIONAL CONOITIOHS 1, 2 and 3 with reac r s earn dome pressure greater than 150 psig.

ACTION:

ae With a RCI system actuation instrumentat' channel trip setpoint less conserv ive>than the value shown i the Allowable Values column of Tabl '.3;33.5"2, declare the c nnel inoperable unti,l',the channel is rest ed.yto OPERABLE statu with its trip setpoint adjusted consiste t wPh the Trip S point value.

b. With one or more RC system act tion .instrumentation channels inoperable, take the TIOll.ra ired by Table 3.3.3-1.

SURVEI LLANCE REOUIREMEHTS 4.3.5,1 Each RCIC system

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act tion ins umentation channel shall be demon-strated OPERABLE by the per fo ance of the HANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATIO operations at t frequencies shown in Table

4. 3. 5. 1-1.

4.3.5.2 LOGIC SYSTEM F NCTIONAL TESTS and simula ed automatic operation of all channels shall be erformed at least once per months.

WASHINGTON NUCLEAR - UNIT 2 3/4 3"47

l TABLE 3.3.5-l REACTOR CORE ISOLATION COOLING SYSTEH ACTUATION INSTRUllENTATION HINIHUH OPERABLE CHANNEL) fUNCTIONAL UNITS PER TRIP SYSTEH T ION

a. Reactor Vessel l er Level " Low Low, Level 2 2 50 yo b. Reactor Vessel Mater vel - lligh, Level 8 2(b) 51 I

c. Condensate Storage Tank Ma Level " Low Low 2 52

d. Hanna 1 Ini tia tion 1

, l(d) 53 nn *- - trip >>*

placing the

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in the tripped condit

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ed at least one other OPERABLE channel in the same trip system is monitoring that parameter.

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

(c)'ne trip system with one-out-of-two logi .

(d) One trip system with one channel.

~0 ~ l TABLE 3.3.5-2 REACTOR CORE ISOLATION COOLING SYSTEH ACTUATIOH INSTRUHEHTATIOH SETPOIHTS ALLOMABLE FUHCTIOHAL UNIT TRIP SETPOIHT VALUE

a. Reactor Vess Mater Level - Low Low, Level 2 > - 50 inches" > -57 i res

b. Reactor Vessel Ma Level " Higl>, Level 0 < 54.5 inches" inches

c. Condensate Storage Tan evel " Low Low** >440 ft3 in: > 440 ft 0 in..

elevation (1 ft 9 n elevation (1 ft-6 in tank level) tank level)

d. Hanual Initiation N.A. H.A.

Bases Figure 8 3/4 3-1.

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""provides automatic transfer from Cond sate Storage Tank to the A.

pres'sion Pool.

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TABLE 3.3.5-1 (Continued)

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION STATEMENTS ACTI 50- With the number of OPERABLE channeIs less than requi d by the Minimum OPERABLE Channels per Trip System requireme t:

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

For both trip systems, declare the R C system inoperable.

ACTION 51 - Wit the number of OPERABLE channels 1 s than required by the mini m OPERABLE channels per Trip Sy em requirement, declare the RC .system inoperable.

ACTION 52 - -

With the mber<of OPERABLE chan ls less than required by the Minimum OP BLE~Ghannels. per T p System requirement, place at least one in'operable charm 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 /> r 'declare the CIC system inoperable.

ACTION 53 - With the number o OPERAS channels one less than required by the Minimum OPERAB Ch ifnels per Trip System requirement, restore the inoperab e channel to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare t RCIC system inoperable.

WASHINGTON NUCLEAR .- UNIT 2 3/4 3-49

TABLE 4.3.5.1-1 RLACTOR COAL'SOLATIOH COOLING SYSTEH ACTUATIOH IHSTRUllLHTATION SURVEILLANCE RE UIRE lTS CllANNEL CIIAHHEL FUNCTIONAL OIANNEL FUHCTIOHAL UNITS CIIECK TEST CALISRATION

a. Reactor Vessel ter Level-(Low Low, Level

b. Reactor Vessel Mater S Level - lligh, Level (8)

c. Condensate Storage Tank Level - Low II g+ R

d. Manual Initiation N.A.

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PLAHT SYSTEMS 3/4. 7. 3 REACTOR CORE ISOLATION COOLING SYSTEM IMITING CONDITION FOR OPERATION

3. 3 The reactor core isolation cooling (RCIC) system shall be OP RABLE with an 0 RABLE flow path capable of automatically taking suction fro the suppre sion pool and transferring the water to the reactor pres re vessel.

APPLICABI TY: OPERATIONAL CONOITIONS pressure g ater than 150 psig.

l, 2, and 3 with reac r steam dome ACTION:

With the RCIC sys em inoperable, operation may contin e provided the HPCS system is OPERABLE, restore the RCIC system to OPER LE status within 14 days or be in at least HO 'SHUTDOWN within the next+~ 2 ours and reduce reactor steam dome pressure t less than or equal to 950~ 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 REOUIREMEHTS 4.7.3 The RCIC system shall be emons ated OPERABLE:

a. At least once per 31 day y:

l. Verifying by ve~ti g at the high point vents that the system piping from Ath'e> mp dis arge valve to the system isolation valve is fill"1'ithwater

2. Verifying t t each valve (ma ual, power-operated, or automatic) in the flo path that is not 1 ked, sealed, or otherwise secured 'osition, is in its c rrect position.

3. Verif ng that the pump flow contro ler is in the correct posi ion. I

b. When t sted pursuant to Specification 4.0.5 b verifying that the RCIC ump develops a flow of greater than or e al to 600 gpm in the test flow path with a system head correspon ng to reactor vessel o rating pressure when steam .is being supplied t the turbine at 000 + 20, - 80 psig."

" he 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 's adequate to perform the test.

WASHINGTON NUCLEAR UNIT 2 3/4 7-8

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PLANT SYSTEMS URVEILLANCE RE UIREMENTS Continued C. At least once per 18 months by:

Performing a system functional test whic includes simulated automatic actuation and restart and ver'fying that each utomatic valve in the flow path act es to its correct po ition. Actual injection of cool nt into the reactor vessel may e excluded.

2. Verifyin that the system wil develop a flow of greater than or equal t 600 gpm in the est flow path when steam is supplied to e turbine a pressure of 150 + 15, -0 psig. "

3. Verifyinggt at t s ion for the RCIC system is automatically transferee ,from t condensate storage tank to the suppression pool on.a cPodens e torage 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 is adequate to perform the tests.

WASHINGTON NUCLEAR - UNIT 2 3/4 7-9

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IHSTRUMENTATIOH BASES 3/4 3.5 RE CTOR CO ISOLA OH COO NG SYST ACTUAT H INSTR ENTATIO The eactor ore iso ation c ling sy em actu ion ins rumentat'on is rovided to init ate act'ons to sure ad uate co e coolin in the vent of reactor isolati n from ' prim y heat nk and e 'loss f feedwa er flow to the re ctor ve sel wit out prov ding ac ation o any of he emerg ncy core cooli g equip ent.

Operat'on with a t trip q less onservat' than ts Trip etpoint but wi hin its specifi d Allow ale Valu is acce able o the basi that the d fferenc betwee each Tr p Setpo'nt and t e Allow le Value is equal to or ess tha the dr t alloy nce ass ed for ach tri in the s fety analyses.

3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION 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 3/4.3pl Reactor Protection System Instrumentation.

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

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Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value,~s acceptable on the basis that the difference between each Trip Setpoin+6 hnd 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 MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitorijg 'nstrumentation ensures that; (1) the radiation levels are continually measure 'j,q the areas served by the individual channels; (2) the alarm or automatic aqtaon 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 MOHITQRING INSTRUMENTATION 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," April 1974.

MASHINGTOH HUCLEAR - UNIT 2 B 3/4 3-4

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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 normal and a'ccident 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 ratjj~g for the equipment and instrumentation cooled by this system and (2) the control room will remain habitable for operations per sonnel during and following~a~l<l design basis accident conditions. Continuous operation of the system with+he 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 OPERABI/Ip of this system in conjunction with control room design provisions is based op ~l'miting the radiation exposure to personnel occupying the control room to 5 regs, or less whole body, or its equivalent.

This limitation is consistent with th&~equirements of General Design Criterion 19 of Appendix A, 10 CFR Part 50.

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The reactor core isolation cooling (RCIC)'~system is provided to assure adequate core cooling in the event of reactor~Nolation from its primary t sink and the loss of feedwater flow to the reactor vessel without requi ng actuation of any of the emergency core cooling system (ECCS) equipm . The C system is conservatively required to be OPERABLE whenever re tor pressure exce s 150 psig. This pressure is substantially below that f

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~ which the low pressur core cooling systems can provide adequate core coo ng for events requiring e RCIC system.

The RCIC sy m specifications are applicable uring OPERATIONAL CONDITIONS 1, 2, and 3 when rea or vessel pressure exceed 50 psig because RCIC is the primary non-ECCS source f emergency core co ing when the reactor, is pressurized.

With the OPERABILITY period.

RCIC system of the HPCS ino system a 'ti able, equate core cooling'is assured by the fies the specified 14 day out-of-service The surveillance requ'ents provide dequate assurance that RCIC, will be OPERABLE when requir . Although all act e components are testable and full flow can be demo trated by recirculation db 'ng reactor .operation, a complete function test requires reactor shutdown. he pump discharge piping is maintained f to prevent water hammer damage and start cooling at the earliest pos le moment.

W INGTON NUCLEAR - UNIT 2 B 3/4 7-1

OPERATING LICENSE NPF-21, RE(VEST FOR TECHNICAL SPECIFICATION AMEND-MENT TO REFLECT REACTOR CORE ISO-LATION COOLING (RCIC) SYSTEM DOWN-GRADE RESULTING FROM MODIFICATIONS, TO AUTOMATIC DEPRESSURIZATION SYS-TEM (ADS) LOGIC STATE OF WASHINGTON

Subject:

COUNTY OF BENTON I, G. C. SORENSEN, being duly sworn, subscribe to and say that I am the Manager, Regulatory Programs, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that I have full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information and belief the statements made in it are true.

0ATE 2 +c Ec& , 1985 G. C. ORENSEN, Manager Regulatory Programs On this day personally appeared before me G. C. SORENSEN to me known to be the individual who executed the foregoing instrument and acknowledged that he signed the same as his free act and deed for the uses and purposes therein mentioned.

GIVEN under my hand and seal this W day of 1985.

otary Pu lic in an for the State of Washington Resi ding

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