ML17284A582

Proposed Tech Specs Modifying Section 3/4.7.3,Table 3.3.7.1-1 Re Radiation Monitoring Instrumentation to Reflect Mods in Sys Configuration & Operation

ML17284A582
Person / Time
Site:	Columbia
Issue date:	10/24/1988
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17284A581	List: ML17284A580 ML17284A582
References
NUDOCS 8811040306
Download: ML17284A582 (9)

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~'~mw~rim sssr~~assmwss&S N4L3~rdaesseammrsmsmm SSSSsewsSSS Ssss&JV'S" IHSTRUMEHTATIOH 3/4.3.7 MONITORING IHSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION s 3.3.7.1 The radiation monitoring instrumentation channels shown in Table 3.3.7.1-1 shall be OPERABLE with their ala/p setpoints within the specified limits.I APPLICABILITY:

As shown in Table 3.3.7.1-1.

ACTION: as b.With a radiation monitoring instrumentation channel ala>W set" point exceeding the value shown in Table 3.3.7.1-1, adjust e set-point to within the limit within S h+s or declare the channel inoperable.

with one or more radiation monitggng channels inoperable, take the ACTION required by Table,3.3.

1.4 c.The provisions of Specifica s 3.0.3 and 3.0.4 are not applicable.

~s SURVEILLANCE RE UIREMENTS 4.3.7.1 Each of the above required r'adiation monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL.CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the.conditions and'at the frequencies shown in Table 4.3.7.1-1.

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~50 POC PSQRAQOC P MASHINGTON NUCLEAR-UHIT 2 3/4 3-58'TTACHMENT 1 (Page 1 of 3)

TABLE 3.3.7.1-1 RADIATION HONITORING INSTRUHENTATION IN STRUHENTATION 1.Hain Control Room Ventilation Radiation Honitor 2.Area Monitors a.Criticality Honitors 1)New Fuel Storage Vault 2)Spent Fuel Storage Pool HINIHUH CHANNELS OPERABLE 2/intake'PPLICABLE CONDITIONS 1,2,3,5 and" ALARM/SETPOINT<5000 cpm<5 R/h(a)<20 mR/h ACTION 70 71 TABLE NOTATIONS"Mhen the main condenser air evacuation system is, in operation.

AMith fuel in the new fuel storage vault.8With fuel in the spent fuel storage pool.(a).Alarm setpoint set IAM 10 CFR 70.24.a.1.ACTION STATEHENTS ACTION 70 a~;/k b.ACTION 71.G 6~,;((;.(.(c (5 ass,c;l.J~aero(c;c~

~Mith one of the required monitors inoperable, y4ace-the-inoperaMe-chann&~4e-h4pped--cen4WAea within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />;restore the inoperable channel to OPERABLE status within%days, or, within the nextl'x hours, initiate and maintain operation of the control room emergency filtration system in/the pressurization mode of operation.

Mith both of the required monitors inoperable, initiate and maintain operation of the control room emergency filtration system in the pressurization mode of operation within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.Mith the required monitor inoperable, assure a portable continuous monitor with the same alarm setpoint is OPERABLE in the vicinity of the installed monitor during any fuel movement.If no fuel movement is being made, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

N'I INSTRUMENTATION BASES CONTROLLED COPY 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION The reactor core isolation cooling system actuation instrumentation is provided to initiate actions to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without providing actuation of any.of the emergency core cooling equipment.

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.3/4.3.6 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 3/4.3.1 Reactor Protection System Instrumentation.

The trip logic is arranged so that a 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

.3/4.3.7.1 RADIATION MONITORING INSTRUMENTATION 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~u4emrbi~cHon.

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.The criticality monitor alarm setpoints were calculated using the criteria from 10 CFR 70.24.a.1 that requires detecting a dose;rate of 20 Rads per minute of combined neutron and gamma radiation at 2 meters.The alarm setpoint was determined by calculational methods using the gamma to gamma plus neutron ratios from ANSI/ANS 8.3-1979, Criticality Accident Alarm System, Appendix B and assuming a critical mass was formed from a seismic event, with a volume of 6'6'6't a distance of 27.7 feet from the two detectors.

'he calculated dose rate using the methodology is 5.05 R/hr.The allowable value for the alarm setpoint was, therefore, established at 5R/hr.3.4.3.7.2 SEISMEC MONITORING 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.WASHINGTON NUCLEAR" UNIT 2 B 3/4 3"4 Amendment No.51~ATTACHMENT 1 (Page 3 of 3)

• I I I I f I I L RE REMQTE INTAKE¹I (VEST)AH TYPICAL I I IV 11 VALVES CLOSE ON HIGH"HIGH RADIATION ALARH VALVES I (TYPICAL)I OPEN ON I FAZ 0 I I NORMAL ROOF JNTAKE RADWASTE BLDG NO EHO 51C DIV I I VALVES OPEN ON I FAZ I I , EHO EHO EHO EHO lf NC 51A 52A DIV If I DIV II EHERG fILTER II ll II.Il II ll I I I I 1 l 52B NC 51B NC DIV II I IDIV I EHERG FILTER II II II ll II I I.I I f I DIV I 54A-1 DIV II 54B-1 51A-1 IB-1 DIV I V II FAN S4A DIV I FAN S4B DIV II fAN 51A DIV I FAN 51B DIV II CONTROL ROOM CLOSE QN FAZ NQ o EHO 52C DIV II REMOTE INTAKE¹2 (EAST)RR TYPICAL I'I I I I I I I RE J I I I DIV 1 EHO EHO 150 CFH EHO 51D DIV I.52D DIV II FO52E 0 51E DIV II DIV I GEND FLGV IN LINE-NO FLGV IN LINE FC=FAIL CLOSED FG=jAIL OPEN NC=NORHALLY CLOSED NO=NORMALLY OPEN LO=LOCKED OPEN LC=,LOCKED CLOSED Ap-ANNUNCIATOR Hl RE=RAD ELEHENT RR=RAD RECORDER EHO~ELECTRO HYDRAULIC OPERATOR MAN=HANUAL OPERATOR FAN 53A DIV I FAN 53B DIV II PURGE EXHAUST FAN 51 750 CFM EXHAUST DEENERGIZE ON FAZ FAZ=HIGH DRYWELL PRESSURE LOV REACTOR VESSEL WATER LEVELS REACTOR BUILDING VENTILATION EXHAUST HIGH RADIATION.

INFORMATION DRAWING ONLY SEPT 22, 1988 P lfhSHINGTON PUBLIC POKER b3 supper svsvzM RICHLAND, MASHINGTGN 99352-0968 TITLE ORIGINAL WNP-2 PARTIAL CONTROL ROOM VENTILATION SYS REMOTE INTAKE 01 (WEST)RE IV II RE AH TYPICAL CLOSE ON FAZ 0 NQ EHO 52C DIV II MAN HAN MAN 0 0 1 51A 52 A DIV II MDIV II EMERG I FILTER I I I I I I I I l 529 51B NO DIV II I DIV I I I 1 I I I I I J t I DIV I 54A-1 DIV II 54B-1 EMERG FILTER 51A-1 DIV I 51B-1 DV II F'AN 54A DIV I FAN 54B DIV II FAN 51A DIV I FAN 51B DIV II CONTROL ROOM DETERH'D DETERH'D NORMAL ROOF INTAKE RAD WASTE BLDG NO 0 FC EHO 51C DIV I REMOTE INTAKE 112 (EAST)DIV RR TYPICAL EHQ 150 CFH EHO 51D FO NC DIV I.52DFO Q DIV II FQ52E N DIV II FO 51E DIV I~GEM D FLOW IN LINE-NO FLOW IN LINE FC=FAIL CLOSED FO=FAIL OPEN NC=NORMALLY CLOSED NO=NQRHALLY OPEN LO=LOCKED OPEN LC-" LOCKED CLOSED AH=ANNUNCIATOR Hl RE=RAD ELEHENT RR=RAD RECORDER EHO=ELECTRO HYDRAULIC OPERATOR HAN=MANUAL OPERATOR FAN 53A DIV I FAN 53B DIV II 750 CFH EXHAUST DEENERGIZE ON FAZ CURRENTLY DEENERGIZED PURGE EXHAUST F'AN 51 FAZ=HIGH DRYWELL PRESSURE LQW REACTOR VESSEL WATER LEVE4 REACTOR BUILDING VENTILATION EXHAUST HIGH RADIATION.

INFORMATION DRAWING ONLY SEPT 22, 1988 P 1fASHINGTON PUBLIC POlfER 43 SUPPLY SYSTEM RICHLAND, WASHINGTON 99352-0968 TITLE CURRENT WNP-2 PARTIAL CONTROL ROOH VENTILATION SYS n?'E REMOTE INTAKE¹1 (VEST)IV II TYPICAL NGRHAL ROOF INTAKE RADVASTE BLDG NO EHO 51C DIV I MAN HAN l 528 NO 5}B NO DIV II].DIV I FHERG FILTER I I I I I tI I 1 NO 51A NO 52A DIV I)DIV II t I I t I I f 1~J I I DIV I 54A"1 DIV II 54B-1 EHERG FILTER 51A-1 IB-I DIV I V II FAN 54B DIV II FAN 54A DIV I FAN 51A DIV I FAN 518 DIV II CLOSE ON F'AZ 0 FC NQ EHO 52C DIV II REHOTE INTAKE¹2 (EAST)RE DIV I RE RR TYPICAL EHO DETERH'D CONTROL ROOM EHO DETERH'D 51D FO DIV I 52DFG DIV II FO 52E FO 51E DIV II DIV I UZMl FLQV IN LINE~-NO FLOV IN LINE FC=FAIL CLOSED FO=FAIL OPEN NC=NQRHALLY CLOSED NO=NORMALLY OPEN LO=LOCKED OPEN LC=LOCKED CLOSED AH=ANNUNCIATOR Hl RE=RAD ELEHENT RR=RAD RECORDER EHQ=ELECTRG HYDRAULIC OPERATOR MAN=MANUAL OPERATOR FAN 53A DIV I FAN 53B DIV II 750 CFH EXHAUST DEENERGIZE ON FAZ PURGE EXHAUST FAN 51 FAZ=HIGH DRYMELL PRESSUREj LOV REACTOR VESSFL MATER LEVELS REACTOR BUILDING VENTILATION EXHAUST HIGH RADIATION.

INFQRHATION DRAWING ONLY SEPT 2P 1980 ymiDNoToN puaUc poma 4'3 SUPPLY SYSTEM.RICHLAND, MASHINGTGN 99352-0968 TITLE PROPOSED VNP-2 PARTIAL CONTROL ROOH VENTILATION SYS

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