Text

Proposed Tech Specs,Consisting of Suppl 2 to Rev 2 to Proposed Amend 147,concerning Diesel Generators
	ML20236S088
Person / Time
Site:	Rancho Seco
Issue date:	11/17/1987
From:	; SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	;
Shared Package
ML20236S084	List: ML20236S082; ML20236S088;
References
	TAC-63030, NUDOCS 8711240212
	Download: ML20236S088 (47)
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ATTACHMENT:2-REVISED'TECHNI' CAL SPECIFICATI0N'PAGES

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' RANCHO SECO UNIT 1~

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" TECHNICAL SPECIFICATIONS

-TABLE OF CONTENTS (Continued).

'Section P3gg l3.14.5 Fire Hose Stations 3-57

3.14.6 Fire Barrier Penetration' Fire Seals 3-58 3.15.

, RADIOACTIVE LIOUID EFFLUENT-INSTRUMENTATION 3-60 g

3.16

-RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 3-63 3.17-

'LIOUID EFFLUENTS-3-70 3.17.1 Conc'entration 3-70 3.17.2 Dnie.

3-71 3.17.3:

'Liould Holduo Tanks 3-72 3.18' GASEOUS EFFLUENTS' 3-73 3.18.1:

Dose Rate 3-73 l'

3.18.2

Noble Gases 3-74 L

3.18.3

' Iodine-131'. Tritium and Radionuclides in Particulate Form 3-75 3.19 GASEOUS RADHASTE TREATMENT.

3-78

3.20.

. GAS STORAGE TANKS 3-79 3.21 SOLID RADI0 ACTIVE HASTES 3-80 3.22'

~ RADIOLOGICAL ENVIRONMENTAL MONITORING 3-81 3.23 LAND USE CENSUS 3-87

'3.24 EXPLOSIVE GAS MIXTURE 3-89 3.25, FUEL CYCLE DOSE 3-90 3.26 INTERLABORATORY' COMPARISON PROGRAM 3-92 147--

.3.27 NUCLEAR SERVICE ELECTRICAL BUILDING EMERGENCY HEATING 3-93 AND AIR CONDITIONING

<3.28

-TDI DIESEL GENERATOR CONTROL ROOM ESSENTIAL 3-94 VENTILATION SYSTEM Proposed' Amendment No. 147 iv b

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TECHNICAL SPECIFICATIONS O

1 TABLE 0F; CONTENTS"(Continued).

/ l'Section :

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[4.26j RADIOLOGICAL ENVIRONMENTAL' MONITORING-

'4 [ m4127

. LAND USE CENSQ$~

4-86 4.28t EXPLOSIVE' GAS MIXTURE' 4 1 1

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'4.29' FUEL' CYCLE' DOSE-4-89' S

'4.30 ~

>INTERLABORATORY' COMPARISON PROGRAM SURVEILLANCE REQUIREMENT 4-90'.

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4.31I NUCLE.AR: SERVICE ELECTRICAL BUILDING EMERGENCY HEATING 4-91'

' VENTILATION AND AIR CONDITIONING T

147 -

4.32.

TDI DIESEL ~ GENERATOR CONTROL ROOM ESSENTIAL 4-92 VENTILATION SYSTEM

.51

. DESIGN' FEATURES 5-l' i

15.1L.

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5-1 v

5.2a

' CONTAINMENT 5-2 5.2.lT Reactor Buildina 5 L 1

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5.2!2

. Reactor Buildina Isolation System 5-3 a

5.3.

REACT 0'R 5-4

5.3.11 Reactor Core-5-4

a-5.3.2.

Reactor-Coolant System 5 rb

?5;4' NEW AND SPENT FUEL STORAGE FACILITIES 5-6 5.4.1l

'New Fuel Inspection and Temocrary Storage Rack 5-6 h

l 5.4.2.:

Etw and Soent Fuel Storace Racks and Failed 5-6

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Fuel Storaae Container Rack 5.4.3'

'New and Soent Fuel Temocrary Storage 5-6

.5. 4 ' 4 -~

Soent Fuel Pool and Storage Rack Design 5-6 p

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h Proposed Amendment No. 147 vii L

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RANCHO SECO UNIT 1 F

TECHNICAL SPECIFICATIONS LIST OF TABLES Iablit P_aga 2.3-1 REACTOR PROTECTION SYSTEM TRIP SETTING LIMITS 2-9 3.5.1-1 INSTRUMENTS OPERATING CONDITIONS 3-27 3.5.5-1 ACCIDENT MONITORING INSTRUMENTATION OPERABILITY REQUIREMENTS 3-38b 3.6-1 SAFETY FEATURES CONTAINMENT ISOLATION VALVES 3-40 3.7-1 VOLTAGE PROTECTION SYSTEM RELAY TRIP VALUES 3-41a 3.7-2 VOLTAGE PROTECTION SYSTEM LIMITING CONDITIONS 3-41b 3.12-1 SAFETY RELATED HYDRAULIC SNUBBERS 3-51a-e 3.14-1 FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS 3-55 3.14-2 INSIDE BUILDING FIRE HOSE STATIONS 3-57a 3.15-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3-61 3.16-1 RADI0 ACTIVE GASES EFFLUENT MONITORING INSTRUMENTATION 3-64 3.22-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3-83 3.22-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS 3-86 IN ENVIRONMENTAL SAMPLES 4.1-1 INSTRUMENT SURVEILLANCE REQUIREMENTS 4-3 4.1-2 MINIMUM EQUIPMENT TEST FREQUENCY 4-8 4.1-3 MINIMUM SAMPLING FREQUENCY 4-9 4.2-1 CAPSULE ASSEMBLY HITHDRAHAL SCHEDULE AT DAVIS-BESSE 1 4-12b 147-4.6-1 DIESEL GENERATOR TEST SCHEDULE 4-35d 4.6-2 ADDITIONAL RELIABILITY ACTIONS 4-35e 4.10-1 ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-42 4.10-2 OPERATIONAL ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-22a i

4.14-1 DESIGNATED SAFETY RELATED HYDRAULIC SNUBBERS FUNCTIONALLY 4-47d,e TESTED ONLY AS REQUIRED BY THE SNUBBER SEAL REPLACEMENT PROGRAM 4.17-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED 4-56 DURING INSERVICE INSPECTION 4.17-2A STEAM GENERATOR TUBE INSPECTION 4-57

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4.17-2B STEAM GENERATOR TUBE INSPECTION (SPECIAL LIMITED AREA) 4-57a 4.17-3 OTSG AUXILIARY FEEDHATER HEATER SURVEILLANCE 4-57b,c 4.19-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 4-64 SURVEILLANCE REQUIREMENTS 4.20-1 RADI0 ACTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION 4-66 SURVEILLANCE REQUIREMENTS Proposed Amendment No. 147 ix l

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L RANCH 0 SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Reactor Coo' ant Loop (A) and its associated steam generator-l

1..

and at least one associated reactor coolant pump, 2.

. Reactor. Coolant Loop (B) and its associated steam generator and at.least one associated reactor coolant pump,

'3.

. Decay Heat Removal Loop (A) 4.

Decay Heat Removal Loop (B).

With'less than the above required coolant loops OPERABLE, immediately initiate corrective action to return the required coolant loops to OPERABLE status as soon as possible; be in COLD SHUTDOHN within 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

3.1.1. 6 '

Reactor. Coolant System High Point. Vents A.

The vent path on Loop A and vent path on Loop B shall be operable and closed during power. operation.

B.

The vent path on the pressurizer shall be operable and closed

.during power operation.

C.

With one of the above reactor coolant system vent paths inoperable, STARTUP and/or POWER OPERATION may continue 1

provided the inoperable vent path is maintained closed with power removed from the valve actuator of all the valves in the

inoperable. vent path; restore the inoperable vent path to OPERABLE status within 30 days.

If the status is not restored to operable in 30 days, be in HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and i

in COLD SHUTDOHN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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D.

With two or more of the above reactor coolant system vent paths inoperable; maintain the inoperable vent paths closed with power removed from the valve actuators of all the valves in the j

inoperable vent paths, and restore at least (two) of the vent J

paths to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

If the status is not

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restored to operable in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , be in HOT STANDBY within 12 j

hours and in COLD SHUTDOHN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

j 147-1 3.1.1.7 The pressurizer shall be OPERABLE, except nen the reactor is in COLD SHUTD0HN, with 3 groups of heaters in two separate banks that i

are capable of being powered by the diesel generator trains. With the heaters in one' bank non-OPERABLE, either restore the bank tc l

OPERABLE status within 3 days or be in at least HOT STANDBY withi.,

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.the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

I Hith the heaters in both banks non-OPERABLE, either restore one bank l

to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 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 HOT SHUTDOHN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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Proposed Amendment No. 147 3-2

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Limiting Conditions ~ for Operation' s

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A ' reactor coolant sump or! decay heat: removal pump.is required to be in__

E Loperation'before tie boron concentration is' reduced by' dilution-with makeup w,

[waterC Either pump will? provide mixing which will' prevent sudden positive 1

reactivity; changes; caused-by dilute; coolant reaching the reactor. One decay j

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% ' 4, heat removaltpump.will circulate the' equivalent of the reactor coolant _ system j

H volume:inLone half hour or less~.. -(l).-

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,e gTh'el decay heat lremovaltsystem suction' piping is-designed for 300 Fcand,300 losig; thus,.theLsystem can remove' decay heat when the reactor' coolant system fp, < '

isLbelow.this temperature.s :(2).' (3).

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J 10ne pressurizer code; safety' valve. is capable of preventing overpressurization

'when'the reactor. is' not/ critical since its relieving capacity is greater than-

% that required.by the' sum of the available heat sources.which are pump energy,.

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_ 4) Both pressurizer code fy 1 pressurizer heaters,land' reactor' decay heat.

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Jsafety. valves are required to _be in service prior.to criticality to _ conform.

(tolthe system design relief capabilities. The code safety valves prevent

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overpressure for rod ^ withdrawal; accidents.

(5) The pressurizer code safety Lvalve lift set point-shall be set at 2500 psig 1 percent allowance.for 1

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, error,and.each' valve shall be capable'of relieving 345,000 lb/hr of. saturated steam at a pressure not: greater than 3 percent above the set pressure.

Theielectromatic relief. valve setpoint was established to prevent operation of

the Safe.ty Valves during transients.

Two pump operation'is-limited until further ECCS analysis is performed.

Hhen6TAV is below 280*F, a single reactor coolant loop or DHR loop provides

! sufficient heat removal < capability for removing decay heat; but single fai. lure considerations' require at least.two loops be OPERABLE.

Thus, if.the N

reactor coolantJ1 oops.are not OPERABLE, this specification requires two DHR loops to:be' OPERABLE.

2The purpose of the high point vents is to vent noncondensible gases from the

.RCS^which may inhibit core cooling during na_tural circulation.

In compliance iwith,10CFR50 Appendix R the power to'all the valve actuators in the vent path

.has been removed.

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There are.3 groups.of heaters.in bank 2, and 3 groups of heaters in bank 3

147$

that'are capable of being powered by the. diesel generator.

Each set of the 3

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groups of. heaters has a nominal rating of 126 kw which provides assurance "thaththese heaters can be energized during a loss of offsite power condition n

jtomaintainnatural-circulationatHOTSHUTDOWN.

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RANCHO.SECO UNIT 1 D

TECHNICAL SPECIFICATIONS r#

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Limiting Conditions for Operation-l i.

REFERENCES.

'(1)-

FSAR' Tables' 9. 5--2, 4.2-1, 4. 2-2, 4.2-4, 4. 2-5, 4. 2-6 L, -

(2)

FSAR paragraph 9.5.2.2 and-10.2.2 w.

-(3)'

FSAR paragraph 4.2.5

(4)

FSAR paragraph'4.3.8.4 and 4.2.4-f i(5)

FSAR paragraph'.4.3.6 and 14.1.2.2.3 a;;

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,1 RANCHO SECO UNIT 1 j

-TECHNICAL SPECIFICATIONS

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v Limiting Conditions for Operation f

3.7 AUXILIARY ELECTRICAL SYSTEM _S S.peci fication.

3.7.1

' The reactor.'shall not be brought critical unless the following

' conditions are met:

.p, Anolicabilitv HEATUP until STARTUP.

1147+

A.

At least two physically independent circuits between the offsite L

transmission network and the onsite Class 1 distribution system are in service.

B.

The switchyard voltage is 219 KV or above.

c C.:

Nuclear services 4160V buses 4A, 4A2, 48, and 4B2 are operable.

D.

Nuclear. services 480V buses 3A, 3A2, 3B, 382, 2A1, 2B1, 2A3, 2B3, 2A4,'and 2B4 are operable.

E.

Two sepa' rate and independent diesel generator trains (train A is both diesel generators A and A2, train B is both diesel

' generators B and B2) are operable each with:

.l.

Separate day tanks containing a minimum volume of 65 percent 4

of tank capacity (265 gallons) of fuel for each A and B and 50 percent of tank capacity (315 gallons) of fuel for A2 and B2.

2.

A separate fuel storage system containing a minimum useable o

. volume of 37,000 gallons of fuel for each A and B and 42,000 gallons of fuel for each A2 and B2.

3.

A separate fuel transfer pump for each engine of a train, o'

'F.

Nuclear Service batteries BA, BB, BC, BD, BA2, BB2, BC2, and BD2, which supply vital 125 volt DC buses SOA, SOB, SOC, S0D, SOA2, SOB 2, SOC 2, and S002 are charged and in service.

L G.

Each vital 125 volt DC buses SOA, SOC, SOB, S0D, SOA2, S082, SOC 2, and S002 shall have its normal battery charger aligned to t

it.

H.

Nuclear service inverters S1A2, SlB2, S1C2, and S1D2, and static switches H8TA3, H8TB3, H8TC3, and H8TD3 are operable for 120 volt AC vital bus power.

+-

Proposed Amendment No. 147 3-41

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r RANCHO SEC0' UNIT 1 TECHNICAL SPECIFICATIONS-4 I

Limiting Conditions for Operation

- 3.7.2 The reactor shall not remain' critical unless all' of.the following requirements are satisfied.

Specification L147- !

A.

.Two' physically independent circuits between the offsite ~

~ transmission network and.the onsite Class 1 distribution system.

I

- Anolicability STARTUP through POWER OPERATIONS i

. Action

?

- Should all but one offsite circuit be removed from service La.

'Hithin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the _ operability of the remaining offsite circuit shall-be demonstrated by obtaining acceptable results from performing surveillance requirements 4.6.1.A and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

b.

'If any diesel generator has not been successfully tested within the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , demonstrate its operability by performing surveillance m

' requirement 4.6.3.A.4-for each such diesel generator, separately, y,

.within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months *.

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-If at least two offsite circuits are not in service within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , the reactor shall be in HOT SHUTDOWN 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 .

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'* This test'is required to be completed regardless of when the non-0PERABLE diesel generator is restored to OPERABLE status.

Proposed Amendment No. 147 3-41a I

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation l147-13.7.2

.The reactor shall not remain critical unless all of the following requirements are satisfied.

Specification

.B.I. Both diesel generator. trains shall be OPERABLE prior to leaving COLD SHUTD0HN conditions.. A diesel generator train is made up-of two diesel generators, GEA and.GEA2 for one train, and GEB

-and GEB2 for the other train. One or two non-0PERABLE diesel generators in a train result in that train being non-0PERABLE.

Specification B.2 Diesel generators GEA, GEB, GEA2, and GEB2 shall be OPERABLE.

+

Aoolicability STARTUP through POWER OPERATIONS Action-Should.any single diesel generators (GEA, GEB, GEA2, or GEB2) become non-OPERABLE then complete all of the following actions:

t a.-

Hithin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the operability of at least two offsite circuits shall be demonstrated by obtaining acceptable results from performing surveillance requirement 4.6.1.A; and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; or go to 3.7.2.C.

b.

If.any single diesel generator became non-0PERABLE due to any cause.other than preplanned preventive maintenance or testing, then if any diesel generator has not been successfully tested within the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , demonstrate its OPERABILITY by performing surveillance requirement 4.6.3.A.4 for each such diesel generator, separately, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months *; or go to 3.7.2.E.1 or 3.7.2.E.2.

c.

If the non-0PERABLE diesel generator is not restored to OPERABLE STATUS within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from when the non-0PERABLE condition was established, the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTD0HN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

This test is required to be completed regardless of when the non-OPERABLE diesel generator is restored to OPERABLE status.

1 Proposed Amendment No. 147 3-41b

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RANCHO SECO UNIT 1 4:

! TECHNICAL SPECIFICATIONS E

Limiting Conditions for' 0peration-147 ' '!3.7.2i The reactor'shall. not\\ remain critical unless ~ all of.the-following requirements'are satisfied.

b

- Specification R

JC.

At least two offsite circuits and both diesel generator trains-m f'

,shall/be OPERABLE.

.Anolicability STA'RTUP through'P0HER OPERATIONS.

? Action.

.Should'all but one offsite, circuit and one dies'el generator train g

bothlbecome:non-OPERABLE

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withinf1' hour the operability of the remaining offsite circuit a.

'shall be demonstrated by obtaining acceptable results from performing surveillance requirement 4.6.1.A; and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter,

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within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months each diesel generator.shall be demonstrated to be

'0PERABLE by obtaining acceptable results by.' sequentially performing surveillance requirement 4.6.3. A~.4*.

This 4

surveillance requirement shall not be performed on diesel

generators already running.

.If either the offsite circuit or the. diesel generator train is not i

restored to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTD0HN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

(

-Hith:the diesel generator train restored to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , follow 3.7.2.A, with the remaining 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO which commenced at the time the offsite circuit was not in service.

With the offsite

.)

circuit restored to service within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , follow 3.7.2.B or.

3.7.2.E.1, with' the remaining 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LC0 which commenced at the time the initial diesel generator or diesel generator train was not in service.

This test is required to be completed regardless of when the 7<

non-0PERABLE diesel generator is restored to OPERABLE status.

' Proposed' Amendment No. 147 3-41c

I 1.

k RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation

' 147+

- 3.7.2.

The reactor..shall'not. remain critical unless all of the.following requirements are satisfied.

Specification

.D. : At-least two offsite circuits shall' be in-service.

.Acolicabilitv STARTUP through POWER OPERATIONS i

I Actiori

.i

.Should.both offsite circuits become non-0PERABLE

a. 'within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months each die'sel generator shall be demonstrated to be OPERABLE by obtaining acceptable results by sequentially performing surveillance requirement 4.6.3.A.4*.

This surveillance requirement'shall not be performed on diesel generators already running.

~

If at least one offsite circuit is not returned to service in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Hith one off-site circuit restored to service within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , follow 3.7.2.A, whose 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO commenced at the time the initial non-0PERABLE condition'was established.

This test is required to be completed regardless of when the non-0PERABLE diesel' generator is restored to OPERABLE status.

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' Proposed Amendment No. 147 3-41d

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Cond' itions for Operation 147*

3.7.2

.The reactor _ shall not remain critical unless all of the following requirements are satisfied.

- Specification' l

E.1 Diesel generator combinations GEA and GEA2; and GEB and GEB2 shall be OPERABLE.

Aeolicability.

i STARTUP through P.0HER OPERATIONS h

l Action Should the following, diesel generators combinations (GEA and GEA2; or

'GEB and GEB2) become"non-0PERABLE then complete all of the following actions:

~

a.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the operability of at least two offsite circuits shall be demonstrated by obtaining acceptable results after performing surveillance requirement 4.6.1.A; or go to 3.7.2.C.

b.

If any diesel generators begome'non-0PERABLE due to any cause other than preplanned preventive maintenance or testing, then if 3

any diesel generator has not been successfully tested within the previous '24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , demonstrate its OPERABILITY by performing surveillance requirement 4.6.3.A.4 for each such diesel generator, separately, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months *; or go to 3.7.2.E.2.

c.

If GEA and GEA2; or GEB and GEB2 combinations are non-0PERABLE 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after the first inoperability, the reactor shall be in HOT SHUTDOHN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within i

the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d.

If one non-0PERABLE diesel generator in the GEA and GEA2; or GEB and GEB2 combination is returned to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , follow the 3.7.2.B.2.c. LC0 which commenced at the time the initial non-0PERABLE condition was established.

)

l

This test is required to be completed regardless of when the non-0PERABLE i

1 diesel generator is restored to OPERABLE status.

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Proposed Amendment No. 147 3-41e

s RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation

'.147 +

3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied.

Specification E.2 Diesel generator pairs GEA and GEB; GEA and GEB2; GEB and GEA2; and GEA2 and GEAB2 shall be OPERABLE.

' Applicability STARTUP through POWER 0PERATIONS Action Sh'ould. diesel generator pairs GEA and GEB; GEA and GEB2; GEB and GEA2;.or GEA2 and GEB2 become non-0PERABLE then complete all of the following' actions:

a.

.Hithin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the operability of at-least two offsite circuits shall. be. demonstrated by obtaining acceptable results after performing surveillance requirement 4.6.1.A; cr be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOHN within the following.30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , b.

If GEA and GEB; GEA and GEB2; GEB and GEA2; or GEA2 and GEB2 diesel generators are non-0PERABLE 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after the second inoperability, the reactor shall be in HOT SHUTDOWN 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 .

c.

-If one non-0PERABLE diesel generator in the GEA and GEB; GEA and GEB2; GEB and GEA2; or GEA2 and GEB2 non-0PERABLE pair is-o; -

returned to OPERABLE. status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months go to 3.7.2.B.2 and follow the LCO-which commenced at the time the initial non-OPERABLE condition was established.

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Proposed Amendment No. 147 3-41f j

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RANCHO SECO UNIT 1

'm iTECHNICAL. SPECIFICATIONS j

/

Limiting Conditions for Operation

)

a :.

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1474.

3.7.2: The reactor shall not remain critical' unless 'all of the following l

requirements-are satisfied.

, L.t:

YI Specification u/t

F. Nuclear service busesLas listed in 3.7.1.C and 3.7.1.D shall be OPERABLE.

'Acolicability I

STARTUP throughtPOWER OPERATIONS

' Action l

tone nuclear service bus or one. train of. nuclear service buses may be

. removed from s'ervice for not more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months provided that all equipment:on the other train of nuclear service buses is OPERABLE.

'Should one nuclear service bus or one train of nuclear service buses

~

L become non-OPERABLE for. greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , a.

the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTD0HN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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Proposed Amendment No. 147 l-3-41g

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RANCHO SECO UNIT 1

^

TECHNICAL SPECIFICATIONS L

Limiting Conditions for Operation 1474' 3.7.2 The ~ reactor,shall 'not remain critical unless all of the following

~

' requirements are satisfied.

L Specification G.

Nuclear service batteries as listed'in 3.7.1.F sh'all be charged

~ and in-service.

Aeolicability STARTUP'through.POWEROPERATIONS Action Should one. nuclear.. service battery become non-OPERABLE for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , a.

the' reactor shall be in HOT.SHUTDOHN 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 .

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- Proposed Amendment No. 147 3-41h

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r s _o.f t,

m RANCHO SECO UNIT 1-.

d

. TECHNICAL SPECIFICATIONS 2

Limiting Conditions for Operation

^

. 147+

.3.7.2. 4.The reactor.'shall.not. remain critical unless all of-the following Requirements'are satisfied.

' Soeci fication -

L H'. Nuclear: service battery chargers as listedrin 3.7.1.G shall be OPERABLE.

JAnolicability u

+

STARTUPfthrough POWER OPERATIONS-Aciton-

,Shouldonefnuclear'servicebatteryhavenobattery;chargerfor

. greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , a

a.'

the reactor =shall be in HOT SHUTDOHN 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~ hours.

If. a: standby charger is aligned in place of its. normal charger for

' greater:than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months b.

.the reactor shall be.in. HOT SHUTD0HN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and-in COLD SHUTD0HN within the:following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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Proposed Amendment No. 147 3-411 1

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.i RANCH 0'SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation-

! 147-+

3.7.2 The reactor.shall not remain critical unless all of the following

-requirements are satisfied.

{

Specification

[

I.

Nuclear service inverters and static switches as listed in 3.7.1.H shall be OPERABLE.

Aeolicabilitv-STARTUP'through POWER OPERATIONS Action

..Should one inverter'or static switch become non-OPERABLE for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , a,

the reactor shall be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and

~

in COLD SHUTDOHN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , l

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Proposed Amendment No. 147 3-41j

i RANCHO-SECO UNIT l~

TECHNICAL SPECIFICATIONS Limiting Conditions for Operation t

k

.147 '

3.7i2-The reactor shall'not 7emain critical'unless all of the following

1

. requirements are satisfied.

T Specification 1

'J.

The switchya,rd voltage is'at least 219KV.

Aeolicability 3

STARTUP through POWER,0PERATIONS

.. Action.

Should the witchyard' voltage drop below 219 KV,

a., " positive' actions, within the District's procedures, will be implemented.,in an attempt to return the voltage to at least 219 j

KV.

i If the s'witchyard voltage goes below 219 KV, s

- n

b. ~both diesel generator trains shall be demonstrated OPERABLE within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months by obtaining acceptable results from performing surveillance requirement 4.6.3.A.4.

Sh'ould the switchyard voltage not be restored above 219 KV within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ',

c.

the reactor shall be in HOT SHUTDOWN 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 .

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i Proposed Amendment No. 147 3-41k

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 147-3.7.3 The voltage protection system trip setting shall be as stated in Table 3.7-1.

3.7.4 Voltage Protection System Limiting Conditions A.

STARTUP and POWER OPERATION are not permitted unless the minimum requirements and action statements of Table 3.7-2 are met.

B.

In the event the number of protective channels falls below that

. listed in Table 3.7-2, the plant will be brought to a HOT SHUTDOWN within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

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Proposed Amendment No. 147 3-42 1

J

p' RANCHO SECO UNIT 1

'1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 1

flaifti The auxiliary electrical power systems are arranged so that no single failure can inactivate enough safety features equipment to jeopardize plant safety.

l The normal source of power to the redundant nuclear service loads is by the two startup transformers to connect the 220-KV station switchyard. All of t'ne 147*.

. normal power supply to plant auxiliary loads can be provided through the two unit auxiliary transformers connected to the generator buses.

Emergency power for the nuclear service loads is obtained from two on-site diesel generator trains'(train A is both diesel generators A and A2, train B is both diesel generators B and B2). Since the startup transformers are sized to carry' full plant. auxiliary loads, if plant auxiliaries' power is not available from the unit auxiM ary transformer, it will'be obtained from the startup transformers.

The five 220-KV transmission lines are not under the direct control of the Rancho Seco station. Therefore, all five cannot be assumed to available at all times. However, extensive reliability and protective features are utilized so that.the probability of losing more than one source of 220-KV power from faults it, low.

By1 requiring that two.220-KV lines are in service L*

prior to startup, one circuit will be immediately available following a loss of the onsite alternating current diesel power supplies and the other offsite 220-KV line.

If there is a loss of all 220-KV remote connections, power to the safety features will be supplied by the diesel generator trains. The 147-37,000 gallons of fuel stored in each storage tank permit operation of the diesel generators A and B for seven days. The 42,000 gallons of fuel stored in each storage tank permit operation of the diesel generators A2 and B2 for seven days.

It is considered unlikely not to be able to secure fuel oil from an outside source during this time under the worst of weather conditions.

147-The set of eight 125 volt DC control buses (SOA, SOB, SOC, SOD, SOA2, SOB 2, SOC 2, and SOD 2) are arranged so that loss of one bus will not preclude safe shutdown or operation of safety features systems. During periods when one plant battery is de-energized for test or maintenance, the associated 125 volt DC bus can be supplied from its battery charger.

Proposed Amendment No. 147 3-42a

h RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE 3.7-1 VOLTAGE PROTECTION SYSTEM RELAY TRIP VALUES EQUIVALENT TIME DELAY UNDERVOLTAGE RELAYS 4160 BUS VOLTS (SECONDS) NOTES 1 (VOLTS) 147-A.

Definite Time Delay Trip Set Point 3771 2 38 5.0 0.5 (Drop Out)

B.

Inverse 3771 e 38 N/A Time Delay Trip, Set Point (Drop Out) 70 Percent of Set Point 2640 27 3.0 z 0.5 NOTE 1 - For bus tripping, an additional 0.5 second time delay must be added.

Proposed Amendment No. 147 3-42b

s s

147+

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= RANCHO SECO UNIT 1~

~

m.

TECHNICAL-SPECIFICATIONS.

i TABLE 3.7 (Note 1)I l

l

. Total No. of Minimum y

Functional

' Number of Relays /.

Channels Channels Action j

! c.- : Unit

. Channels

. Chancel To Trip Operable L l 47-+

Undervoltage 3/ Bus 2

2/ Bus 2

A..

j

+

-l 1

ACTION STATEMENTS Action:A -

Hith the number of OPERABLE channels.one less than the total Number of Channels,' operation may proceed provided both the Lfollowing; conditions are satisfied:

a.. LThe. Inoperable l Channel is placed in-the tripped condition within one hour.

3 b.

The Minimum ~ Channels OPERABLE requirement is met; however, one

, additional; channel-may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance'e testing.

o Note.1: The table is not applicable when the plant is in ~ cold shutdown.

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Proposed Amendment.No. 147 3-42c L

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RANCHO SEC0' UNIT 1 TECHNICAL SPECIFICATIONS

(;

Limiting Conditions for Operation Bases -(Continued)L 147-Each redundant pair ("A"' and "C'!,

"B" and "D") of the eight 125 volt DC control. buses (SOA and SOC, SOB and SOD, SOA2 and SOC 2, and SOB 2 and S002)

A

. has a' standby. battery charger in addition to its normal battery charger. On i

C the loss of power from one battery charger per pair the standby battery charger is put in service. However, the standby charge can be aligned in place'of'its normal charger for only 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months because the standby battery charge is powered.from a different diesel generator than the normal battery charger..There are potential interactions after 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months that could occur upon the loss-of-off-site power and a single diesel generator failure. This 0~

situation has not been analyzed but by limiting the time this configuration

.could exist, the probability of occurence'is sufficiently low to justify limited operation in'this condition.

During periods.of station operation under the condition of electrical system i

degradation, as, described above in Specification 3.7.2, the operating action i

required is to start and run sufficient standby power supplies so as not to compromise the safety of the plant. As seen in Specification 3.7.2, a time limit is placed on operation during certain degraded conditions based on the reliability of the available power supply.

'147-Four nuclear service inverters (S1A2, S182, S1C2, and $1D2) and static switches (H8TA3,'H8TB3, H8TC3, and H8TD3) are required to be operable to

' power the 120 volt AC vital buses. The nuclear service inverters are powered from diesel generators A2 and 82 and the static switches are powered from diesel generators A'and B.

This design ensures that upon loss of an inverter or a single diesel generator the-120 volt AC vital buses will

' continue to. receive ~ power and that there are no system interactions. One nuclear service inverter or static' switch is permitted to be inoperable for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The static switch is only used as a backup for the inverter.

It is not permitted'to be used when an inverter is operable except for switching period because it receives power from the nuclear q

service 480V buses and there is no battery backup available.

The voltage protection system is designed to isolate the nuclear service l

buses from the startup transformers before the voltage drops below the L

allowable operating limit of the equipment.

The undervoltage protection for the 4160 volt nuclear service buses is 3771 38 volts.

This corresponds 4

to a nominal switchyard voltage range of 219 KV.

REFERENCE FSAR, Section 8 Proposed Amendment No. 147 3-43

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' RANCHO SECO UNIT 1

~ TECHNICAL SPECIFICATIONS-Limiting Conditions for Operation Table 3.14-1 '(Continued) oc

. FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS Minimum Operable LZone' Instrument Location Heat Flame Smoke l75-1 LB Switchgear Room (NSEB) 0 0

1 17512 BB2 Battery Room'(NSEB) 0 0

1

'75-3 BD2 Battery Room (NSEB) 0 0-1 s

o-l76-1

. A' Switchgear' Room (NSEB) 0 0

1 i

176-2:

BA2: Battery Room (NSEB) 0 0

1

.76-3

.BC2' Battery. Room (NSEB) 0 0

1 77-l' ; North.B Electrica12 Equipment Room (NSEB) 0 0

1 77-2. South"B Electrical Equipment Room (NSEB) 0 0

1 f

78-11 North A Electrical Equipment. Room (NSEB).

0 0

1 78 South A'Electrica1' Equipment Room (NSEB) 0

'O 1

' 811

'B Cable Tunnel / Shaft (NSEB) 0 0

3 82 A' Cable. Tunnel / Shaft (NSEB) 0 0

3 84 B Mechanical Equipment Room (NSEB) 0 0

1 84-3.

A Mechanical! Equipment Room (NSEB) 0 0

1 147*'

'105' Diesel Generator Building 2

3 2

106 Diesel Generator Building 2

3 2

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Proposed Amendment No. 147 l

3-55c p

t.

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.14.3 Sorav and Sprinkler SvJtems.

Specification

-3.14.3.1 The spray and/or sprinkler systems located in the following areas I

shall'be OPERABLE:

a.

Control Room (Zone 3) b.

Controlled Area, Hezzanine Level (Zone 20) i c.

Main Lube 011 Area, Grade Level (Zone 32) d.

Grade Level (Zone 34) e.

North Diesel Room (Zone 40) f.

South Diesel Room (Zone 41) g.

Hest Controlled Area, Grade Level (Zone 42) h.

East Controlled Area, Grade Level (Zone 43) 1.

South and East -20' Level (Zone 46) j.

NSEB B Cable Tunnel / Shaft (Zone 81) k.

NSEB A Cable Tunnel / Shaft (Zone 82) 1.

NSEB Mechanical Equipment Rooms A and B (Zone 84) 147-m.

Diesel Generator Building (Zone 105) n.

Diesel Generator Building (Zone 106) 3.14.3.2 Hith one or more of the above, items a through f, required spray and/or. sprinkler systems are inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in'which redundant systems or components required to safely shut down and cool down the plant could be damaged; for other areas, establish an hourly fire watch patrol.

Restore the system to OPERABLE status within 14 days or, in lieu of any other report requireu by Specification 6.9, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.5.E within l

the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

3.14.4 CO2 System Specification 3.14.4.1 The CO2 systems located in the following areas shall be OPERABLE with a minimum capacity of 66 and a minimum pressure of 275 psig in the storage tank:

a.

Zone 12 Hest DC Control Room Mezzanine Level b.

Zone 13 West 480 VAC Room Mezzanine Level c.

Zone 14 Hest Cable Tray Area d.

Zone 15 East Cable Tray Area e.

Zone 16 East 480 VAC Room Mezzanine Level f.

Zone 17 East DC Control Room Mezzanine Level g.

Zone 36 West Battery Room Grade Level Proposed Amendment No. 147 3-56

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RANCHO-SECO UNIT 1 U

TECHNICAL' SPECIFICATIONS' S. R I

C Limiting-Conditions for Operation

. '?

' Table 3.14-4~ (Continued)-

INSIDE BUILDING FIRE HOSE. STATIONS o

py

.ID No.

Location Ll47h III.

! Diesel ~ Generator Building Hose S'tations FPHS-D-001 Train A' Engine Room Elevation O' b: w,

1FPHS-D-002 Train A Control Room Elevation O' FPHS-D-003' Train'A Mezzanine Elevation 18'6"

' FPHS-D-004' Train B Engine Room Elevation O'-

-FPHS-D-005 Train B Control Room Elevation O' n

t FPHS-D-006 Train B Mezzanine Elevation 18'6" b

c-0

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Proposed Amendment No. 147 t-3-57b

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.147*

j RANCHO SECO UNIT 1!

TECHNICAL SPECIFICATIONS 3

[

Limiting. Conditions for Operation p

V

.3.27 Nuclear Service' Electrical Buildina Emeroency Heatina Ventilation

{

and Air Conditioning Svstam.

)

Specification

]

p 1

N 3. 27.1 '- Both Nuclear Service Electrical Building Emergency Heating Ventilation and Air Conditioning trains shall be OPERABLE.

3.27.2 'The room temperatures in the NSEB shalllnot exceed 104*F.

Anolicability HEATUP through POWER OPERATIONS Action a.

With one Nuclear Service Electrical. Building' Emergency Heating

- Ventilation and Air Conditioning train non-OPERABLE, restore the train to OPERABLE status within 7. days or 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 following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

Hith both Nuclear Service Electrical Building Emergency Heating Ventilation and Air Conditioning' trains non-0PERABLE, restore the trains to OPERABLE status within 3.5 days 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 hours.

c.

If any room temperature in the'NSEB exceeds 104'F,' reduce the room temperature to less than 104*F within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at least HOT STANDBY within the next 6' hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

j Bases The Nuclear Service Electrical Building (NSEB) Emergency Heating Ventilation 'and Air Conditioning System is required to provide cooling to protect required electrical components in the NSEB.

. Proposed Amendment No. 147 3-93 ma-._

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS m

' Limiting Conditions for Operation L1477 -

3.28 TDI Diesel' Generator Control Room Essential Ventilation System

. Specification 3.28.1 Both TDI: Diesel' Generator Control Room Essential Ventilation trains shall be OPERABLE.

Acolicability HEATUP'through POWER OPERATIONS Action a.

With one TDI Diesel Generator Control Room Essential Ventilation train non-OPERABLE, demonstrate the operability of the remaining train. Restore the non-0PERABLE train to OPERABLE status within 3 days or be in at least HOT SHUTDOHN within six hours and in COLD SHUTDOHN within the following 30

hours, b.

Hith bothLTDI Diesel Generator Control Room Essential Ventilation trains'non-0PERABLE, restore at.least one

-non-OPERABLE train to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in

~

at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOHN within.the'following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . With one non-0PERABLE train restored to OPERABLE status, continue with Action a. above-using the time the remaining non-0PERABLE condition was established as: the start of the LCO.

Bases The TDI Diesel Generator Control Room Essential Ventilation System is required'to' maintain the temperature in the control room below 122*F to protect required electrical components.

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L Proposed Amendment No. 147 3-93a l

L L

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RANCHG SECO UNIT 1-i L

TECHNICAL SPECIFICATIONS o'

Surveillance Standards s

t-i TABLE 4.1-1l(Continued),

N

INSTRUMENT SURVEILLANCE REQUIREMENTS y ;,.

Channel Description Check-Test Calibr' ate

-Remarks I

l.57. : Voltage Protection:

-(1) Test using undervoltage relay's.

i >

s L.147 + T

.[(DefiniteandL!nverse

" TRIP TEST." No quantitative

yd *

T1: ne ' Delay Relays) -

measurements, 1

a.

Undervoltage Relay M(1).

N/A R

Voltage Setpoint -

b. ' undervoltage Relay --

M(1)

N/A R

'r-

' Time Delay

-:58. ; Containment, Area High S

M(1)

R (1) Test using installed source Range Monitor-M N/A R

.59.. Wide Range Containment

. Water Level L 60. Containment Hydrogen.

S-M Q

u.

.i?

0 Analyzer

.61. -Emergency. Sump Level-M

.N/A

'R

.62. -Containment Wide range-M N/A R

J Pressure. Monitor / Recorder 3

634., H1gh Range Noble Gas

.S M:

R-Effluent Monitors

- RB Exhaust Stack

'- Aux. Building Stack

- Radwaste Vent J

'64[ Main Steam Line Radiation -

S, M(1)

R (1) Test using installed source Monitors l 65, r Subcooling Margin Monitors-M N/A R

66. Incore Thermocouple:

M N/A R'

4

-67 ' Low Temperature Over.

N/A (1)

R (1) Prior to cooldown

. Pressure Protection k

S = Each shift M = Monthly P = Prior to each startup if not done previous week l

D = Daily.

Q = Quarterly R = Once during the refueling interval

[~,

W = Weekly SY = Semiannual I

p-Proposed Amendment No. 147 1

4-7c i

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 2.

The test will be considered satisfactory if control board indication verifies that all. components have responded to the actuation sigr.a1 and the appropriate breakers shall have completed their travel.

3.

Additionally it shall be verified that the NSCH flow through each operating cooler exceeds 1400 gpm and air flow through the cooler exceeds 40,000 cfm.

4.5.2.2 Component Tests A.

Testing At least quarterly, Inservice testing of Reactor Building Spray pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).

B.

Flow Path Verification Following Inservice testing of pumps and valves as required by paragraph 4.5.2.2.A required flow paths shall be demonstrated operable by verifying that each valve (manual, power-actuated or automatic) in the flow path that is not locked in position is in its normal operating position.

Positions of locked valves shall be verified in accordance with the provision of Section XI of the ASME Boiler and Pressure Vessel Code.

147-C.

The pressurizer shall be tested as follows:

1.

The pressurizer water level shall be determined to be within its limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

2.

The power supply for the nuclear service backed pressurizer heaters shall be demonstrated OPERABLE at least once per refueling interval by using the Nuclear Service Bus to energize the heaters.

Proposed Amendment No. 147 4-30

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. RANCHO SECO UNIT'1 b

4 TECHNICAL SPECIFICATIONS-e Surveillance Standards h

Bases h

3 The Reactor Building emergency cooling systems and Reactor Building spray j

Isystem are' designed to: remove the heat in the containment.atmosph tg to 9

prevent.the' building pressure from exceeding the design pressure.t u.

lTh'e delivery capability. of one Reactor Building spray pump at'a. time can be-tested.by' opening the' valves in the line from the borated water-storage

tank,-opening the corresponding valve in the test line, and starting the

~ corresponding pump.. Pump discharge pressure and flow indication demonstrate i

b performance.

s With.the pumps shutdown and the borated water storage tank outlet valves closed..the Reactor Building spray injection valves can each be opened and closed by operator action. With the Reactor Building spray inlet valves l'

' closed, air can be blown through the test connections of the Reactor Building spray nozzles to demonstrate that the flow paths are open.

The equipment, piping,evalves, and instrumentation of the Reactor Building

' emergency cooling system are arranged so that they can be visually inspected.

The cooling units.and associated piping.are' located outside the-l secondary concrete shield. Personnel can eriter the eactor Building during R

power operations to inspect and maintain this equipment. The nuclear service cooling water piping and valves outside the Reactor Building are inspectable at all times.'

147-+

.The operability of the nuclear service. bus backed pressurizer heaters is demonstrated by energizing the heaters once per refueling interval.

t i

REFERENCES

(1)

FSAR, section 9.

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i Proposed Amendment No. 147 4-31

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K' RANCHO SECO UNIT l.

.m'M TECHNICAL SPECIFICATIONS:

Surveillance Standards 5- '

4.6<

EMERGENCY POWER SYSTEM PERIODIC TESTING Specification :

147-

' 4.6.1 Each.of. the. required independent circuits between the offsite transmission. network;and the onsite Class 1 distribution. system

?shall be:

. A. f Determined 0PERABLE'at:least weekly by verifying correct

~

3 b'reaker. alignments and indicated power availability, and.

DemonstrateddPERkBLEatleastonceperREFUELINGintervalby

-B1 transferring ~' nuclear service buses as listed in 3.7.1.C from

,the n'ormal.startup transformer supply circuit to the alternate

/startuptransformersupplycircuit.

- ADolicability s-p HEATUP through P0HER OPERATIONS I

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I Proposed Amendment No. 147 4-34

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~4.6: Emergency: Power System Periodic. Testing; (Continued) c Specifications'-

L 4.' 6 ' 2 ) Nuclearjservice buses required by 3.7.1.C and 3.7.1.0 shall'be l

' determined'to be OPERABLE'at least weekly by. verifying correct L

. breaker. alignment and indicated power availability.

Aeolicability-HEATUP:through POWER OPERATIONS

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F l i Proposed Amendment No.'147 4-34a I

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards i

L147h 14.6 Emergency Power l System' Periodic Testing -(Continued)-

4.6.3i Diesel generator., operability Aoolicability g

At:all times :

l

'1 Specifications b

. Each diesel generator train shall be demonstrated OPERABt.E by verifying that A

both' diesel generators in the train are OPERABLE (GEA anC GEA2, GEB and

=GEB2).

A.

In accordance with the' frequency specified 'in Table 4.6-1 by:

1.

Verifying:the fuel level in the day. tank.

s

'2.

Verifying the fuel level in the fuel storage tank,

.3.*- Verifying the fuel transfer pump starts and transfers fuel from the' storage system to the day tank, 4.

Verifying the diesel starts'from a manual signal and accelerates to a nominal 900 rpm for A'and B and a nominal'450 rpm for A2 and B2..The generator voltage and frequency shall be 4160 (1420) volts and 60 (11.2) Hz t.fter the start signal.

(Note 1)

'5.*

Verifying the generator is synchronized, and within the next 90 I

-seconds; loaded between 2550 and 2750 kw for A and B and 3000 and 3300 kw for A2 and B2 and operates with this load for at least 60 minutes.

(Note 1).

Note:1 All planned engl.ne starts may be preceded by an engine prelube period. With the' exception of once per 184 days, all planned engine s' tarts.may be preceded by warmup procedures recommended by the r

manufacturer and may also include slow starting (greater than 10 i

seconds) and gradual loading (greater than 90 seconds) so that mechanical stress and wear on the diesel engine is minimized. The l

testing performed once every 184 days shall include fast starting

.(less:than or equal to 10 seconds) and fast loading (less than or equal to 90 seconds). Whenever a fast start is performed, the D

diesel generator shall start within 10 seconds.

'* Surveillance shall not be performed when a diesel generator train or offsite circuits is not operable in accordance with TS 3.7.2.

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?Verifyingithe diesel generator is? aligned to provide _ emergency 1

. power to the' nuclear-service buses:atithe conclusion of the

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Atitheinumber of failures'for'the inoperable diesel generator e

indicated.in Table 4.6-2 perform the' Additional Reliability.

4*

" Actions prescribed'in Table 4.6-2.

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-Fue1~0ilcStorage

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1 :,9 7By: removing accumulated water:

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a)xFrom the day tank at least monthly and after each occasion 1

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when the. diesel is operated for.. greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and

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ew b)M From the storage tank at least monthly.

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By sampling now fuel.' oil in accordance with ASTM D4057-81 1

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-(1981)- prior tul addition to the storage tanks and:

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N a) - By verifying:in accordance with the tests specified in ASTM m3 W

D975-81? prior to addition.to the storage tanks that the 1

. sample has:

g

C 11).. An/ absolute specific gravity at' 60/60*F of. greater than

, g' ~

or equal to 0.83 but.less than or equal to 0.90 or an yg.

1 API' gravity at.60*F of greater than or equal to 26' Et, 1

degrees butlless than'or equal to 38 degrees in a

4 accordance with ASTM 01298-77.

' ['

ii) Al kinematic'viscosi.ty at 40*C of greater than or equal

.to 1.9 centistokes, but.less than.or equal to 4.1 Lcentistokes, or Saybolt Viscosity, (SUS'at.100*F) of. greater than or equal to 32.6, but less than or equal to 40.1 measured in accordance with 3.

ASTM D-88-81.

,a iii).

' A. flash point equal to or greater than 125'F, and iv) Hater and sediment of less than or equal to 0.05 percent'byr volume.

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that.the:other properties specified in Table;1.of-

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I ASTM D975-81 are met when tested.in accordance.with' s ASTM.D975-81,: except ~ that the analysis 'for sulfur may be performed in accordance with ASTM D1552-79 i.

or ASTM D2622-82.- (Note 2)'

4>,p'

~ 'At.least MONTHLY by obtaining a sample' of: fuel oil from-

3.

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',W L.the: storage tanks in accordance with ASTM D4057-81:

t(1981),;and verifying that total particulate:

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' contamination is-less than 10 mg/ liter when checked:in

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1accordance with ASTM.D2276-73 (1978),' Method A.

'?pg.

L,. f Note 2. Iffone or,more properties are out of specification, within' 62 days

.of obtaining the bad. fuel oil, verify that an additional sample of -

g 7,

fuel l oil from the fue1Loil storageitank is within' specification, gr.

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me emptyJandLrefill the: tank with a new shipment of fuel oil within

.774 days of-the original out-of-specification sample.

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. Surveillance Standards h

.147m C. 'At each. refueling interval, by

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Diesel Generator Inspections.

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a). Subjecting-the diesel generators A and B to an-

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inspection in accordance with procedures prepared-in conjunction with the1 maintenance-' recommendations.

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prov.ided by its manufacturer for this class of

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. standby service.

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'b)' Subjecting'the diesel generators A2'and B2 to an g

.inspectio_n in.accordance.with procedures. prepared L

in conjunction with the. maintenance 'and surveillance 7' '

- program. recommended by the TDI Owners Group in

" Design Revision and Quality Revalidation Report' t

J E for Rancho Seco," Appendix II.

t 1

2.

Verifying the generator capabi.lity to reject a load

equivalent to o.r greater than the HPI: pump for A and B and:the'AFH pump.for'A2 and B2 while maintaining engine

!speedcless than or equal:to 75% of the difference-between nominal speed-and'the overspeed trip setpoint, or 15%'above nominal whichever is less..

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3.. Verifying thel generator capability to reject a load of between 2550 and 2750 kw for A and B and between 3000 '

.i and 3300.for A2 and B2 without tripping.

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' Proposed Amendment No. 147 4-35b

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RANCHO SECD UNIT 1 e

TECHNICAL SPECIFICATIONS Surveillance Standards l

147-*

4.

Simulating a loss of off-site power in conjunction with a safety features actuation-signal, and i

- a) Verifying de-energization' of the nuclear service buses and operation of the load shedding circuitry.

b) - Verifying the diesel. starts on the auto-start signal, energizes the nuclear'. service buses with permanently connected loads, loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads. After energization, the steady state voltage and frequency of the emergency buses

.shall be maintained at 4160 ( 420) volts and 60 (i 1.2) Hz during this test.

c) Verifying for the A and B diesel generators that all automatic diese1~ generator trips, except engine overspeed, ground fault and generator differential, i

and verifying for the diesel generators A2 and 82 that.all automatic diesel generator trips, except engine overspeed, low lube oil pressure and generator differential, are automatically bypassed with an SFAS.

5.'

Simulating a' loss of off-site power and verifying that on interruption of the emergency power sources the loads are shed from'the nuclear services buses in l

accordance with design requirements and that subsequent loading of the emergency power sources is through the automatic load sequencing circuitry.

The diesel generator will'be operated for at least 5 minutes in y

this condition.

(Note 3)

' Note 3. All planned engine starts for the purpose of this surveillance testing may be preceded by an engine prelube period. The testing shall include fast starting (less than or equal to 10 seconds).

l I

' - Proposed Amendment No. 147 4-35c l

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Surveillance Standards

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.6.p Verifying the' diesel generator operates for at least 24

v y i147-* '

j 2.4

' ' hours (Note.1). - During the first 2. hours of this test, g-

.the. diesel generator:shall be.1oaded.between-2650 and 6 L4 2850 kw:for.-A'and B 'and 3000 and 3300 kw for A2 and 82

^

[% 4 and for.the? remaining 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months of this test, the diesel

! generator shall be: loaded between 2550 and 2750kw for A o,

y

'and B and 3000 and 3300kw for A2'and B2. Hithin five

~

. minutes after completing this:24-hour' test, perform T

surveillance requirement 4.6.3.C.4.b).

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'7.

Verifying that the auto-connected loads to each diesel l

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l generator do not exceed the 2000-hour rating of 2850 kw 1

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for A and-B 'and 3300 kw for' A2 and B2.

1 1

D. 'At least once per 10 years or after any modifications,which j

1' could : affect' interdependence, by starting all four diesel

. generators simultaneously (Note 3) and verifying that they

'i

' accelerate to a nominal 900 rpm:for A and B and a nominal

)

450 rpm for.A2'and-B2 within 10 seconds after the start m

signal.

The generator voltage and frequency shall be 4160

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-( 420) volts and 60 (11.2) Hz within 10.0 seconds after the start signal.

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N iNote.1 A11Lplanned' engine starts may be preceded by an engine prelube l

period. 'Hith the exception of once per 184 days, all planned engine i

' starts'may be. preceded by warmup procedures recommended by the H g~

manufacturer and may also include slow starting (greater than 10 seconds) and gradual loading (greater than 90 seconds) so that mechanical' stress and wear on the diesel engine is minimized.

The i

I testing performed once every.184 days shall include fast starting

^

(lessithan or equal to 10 seconds) and fast loading (less than or equal to 90 seconds). Whenever a fast start is performed, the diesel generator shall start within 10 seconds.

Note'3R All' planned engine starts for the purpose of this surveillance testing may be preceded by an engine prelube period.

The testing shallginclude fast starting (less than or equal to 10 seconds).

i

Proposed Amendment No. 147 4-35d y

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R'NCH0:SEC0~ UNIT 1.

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' Sneci fication :

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.147*.. 4. 6 '. 4 ;

Batteriesiin the 125 volt DC' systems shall be: tested as-follows:

p

'. A.

-The voltage and specific gravity of each pilot cell shall be measured and recorded weekly.

1 K

B.

-The specific gravity, level and' voltage of each cell shall be

~i measured and recorded every month.

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- C.

. Each. time data _are recorded,-new data.shall be compared with

old to detect signs of deter.ioration.

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D.'

Durin'g each. refueling interval, the' battery shall be subjected to a rated load.or equivalent test.

The battery voltage as a n'

function of time shall be monitored to establish that the battery performs as expected.

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Proposed Amendment 147

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Bases 147-The operability'of.the'offsite circuits, the nuclear service 4160V buses,

~

.'and the nuclear service 480V buses are demonstrated by verifying correct breaker alignments and indicated' power availability.

Surveillance 4.6.1.B

= can only be. performed during a refueling shutdown when both diesel generator Ltrains. are operable or the core is flooded to 37 feet to ensure the required rdecay heat removal capability is available.

.The tests 'specified are designed to demonstrate that the diesel generators will provide power.for' operation of safety features equipment.

They also assure that'the emergency generator control system and the' control systems for. the~ safety features equipment will' function automatically in the event

.of a loss of all normal a-c station service power,-and upon receipt of a

~ safety features. actuation signal. 'The testing frequency specified is

. intended'to identify before-it can result in a system failure.

The fuel oil

' supply, starting circuits and controls are. continuously monitored and any faults are alarmed and indicated. An abnormal condition in these systems would be signaled without having to place the diesel generators on test.

' 147-The" limiting of the maximum load on the TDI diesel generators A2 and B2 to less than the qualified. load-of 3300.kw provides assurance that the crankshafts will' stay within the proven limits for high-cycle fatigue cracks.

Diesel generators ~A2 and B2 will be loaded during surveillance testing between 3000 and 3300 KH which provides assurance that the qualified load of 3300 KH will not be exceeded.

. t.-least once per refueling outage a diesel generator test will be performed A

' simulating a loss of _off-site power in conjunction with a simulated SFAS and

' loading.of actual loads'to the maximum extent possible without damaging plant systems (i.e., use of recirculation flow or manual valving out a system to protect plant components).

~

Precipitous failure of the plant battery is extremely unlikely.

The surveillance specified is that which has been demonstrated over the years to prov.ide an indication of a cell becoming unserviceable long before it fails.

-REFERENCE (1)-

IEEE 308

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Proposed Amendment No. 147 I

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4-35f g

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2.

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS L

Surveillance Standards l

l<

147-ELECTRIC POWER SYSTEMS Table 4.6-1 DIESEL GENERATOR TEST SCHEDULE Number of Failure in Last-20 Valid Tests

Test Freauency 1

At least MONTHLY 2

At least HEEKLY**

Criteria' for determining number of failures and number of valid tests shail be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, Revision 1, August 1977, where the number of tests and failures is determined on a per diesel generator basis.

For the purposes of this test schedule, only valid tests conducted after the license amendment issuance date shall be included in the computation of the "last 20 valid tests."

- This test frequency shall be maintained until seven consecutive failure free demands have been performed and the number of failures in the last 20 valid demands has been reduced to one or less.

Proposed Amendment No. 147 4-35g

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TABLE 4.6-2

]

ADDITIONAL RELIABILITY' ACTIONS No.'of failures.

iNo. of' failures inslast 20

in last'100-t

valid-test *>

' valid ~ tests Action

,y

/

3.

6 Hithin 14 days prepare and maintain a report for NRC audit' describing the

,l diesel generator reliability improvement program implemented at.

1 s

the site. Minimum requirements for

.i the report are indicated in Note 1 to l

this table.

A:

5-

'11" Perform a requalification test i

program for'the affected diesel generator.

Requalification test

'l M

program requirements are indicated in Note 2'to this table.

. ; S. -

j; a.-

For the purposes of this schedule, only valid tests conducted after the license amendment, issuance date shall be included in the computation of the "last 20 valid tests" and "last 100 valid tests."

l?

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' Proposed Amendment No. 147 4-35h e

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NOTE 1 - TO TABLE 4.6-2.

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REPORTING REQUIREMENT' f

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J s a minimum-the Reliability Improvement Program report for NRC audit shall l

A Jinclude:

l 31

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. a), a summary;of all tests'(valid and invalid).that occurred within the time j

period-over which the-last 20/100 valid. tests were performed.

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b) Lanalysis ofLfailures and determination of root causes.of failures-c) 1 evaluation-of each of the recommendations of NUREG/CR-0660, " Enhancement

~

of Onsite Emergency Diesel Generator Reliability in Operating Reactors,"

with respect to their application:to the Plant-

' d)~. identification of all actions.taken or to be taken to 1) correct the root causes of failures defined in b) above and 2) achieve a general improvement of diesel generator reliability J

A Le) th'e schedule for-implementation of each action from d) above j

[,

i f) -an assessment of the existing reliability of electric power to 1

-f

engineered-safety-feature equipment m.y

! Once a licensee.lhas prepared an' maintain;an initial report detailing the

~

d l

i

? diesel generator reliabilityLimprovement program at his site, as defined l

'above, the licensee need prepare'only a. supplemental report within 14 days 1..

after each. failure during a valid demand ~for so.long as-the affected diesel

generatorf unit continues to. violate the criteria (3/20 or 6/100) for the e

' reliability improvement program remedial action. The supplemental report need only update-the failure / demand history for'the.affected diesel generator unit since the last report for that diesel generator. The 1

supplemental report shall also present an analysis of the failure (s) with a root cause determination, if possible, and shall delineate any further

. procedural, hardware or operational changes to be incorporated into the site diesel generator improvement program and the schedule for implementation of those' changes.

4 In' addition to;.the"above, submit'a' yearly data report on the diesel generator reliability.

l I

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Proposed Amendment No. 147.

4-35i 4

m

RANCHO SECO UNIT 1 j

TECHNICAL SPECIFICATIONS Surveillance Standards NOTE 2 TO TABLE 4.6-2 DIESEL GENERATOR REOUALIFICATION PROGRAli (1)

Perform seven consecutive successful demands without a failure within 30 days of diesel generator being restored to operable status from the last failure and fourteen consecutive successful demands without a 147-~

failure within 75 days of diesel generator being restored to operable status from the last failure.

(2)

If one failure occurs during the first seven tests in the requalification test program, perform seven successful demands without 147-~

an additional failure within 30 days of diesel generator being

(

restored to operable status after the first failure of the requalification test program and fourteen consecutive successful demands without a failure within 75 days of being restored to operable status after the first failure of the requalification test program.

1 (3)

If one failure occurs during the second seven tests (tests 8 through

14) of (1) above, perform fourteen consecutive successful demands without an additional failure within 75 days of the failure which occurred during the requalification testing.

(4)

Following the second failure during the requalification test program declare the diesel generator inoperable and follow the applicable requirements of Specification 3.7.2.

The diesel generator shall not be considered operable until the diesel generator has successfully j

requalified.

1

(

(5)

During requalification testing the diesel generator should not be l

147-*

tested more frequently than at 24-hour intervals each.

1 After a diesel genrator has been successfully requalified, subsequent q

repeated requalification tests will not be required for that diesel l

generator under the following conditions:

]

147- -

(a)

The number of failures in the last 20 valid tests is less than 5.

j 147--

(b)

The number of failures in the last 100 valid tests is less than 11.

l (c)

In the event that following successful requalification of a diesel l

generator, the number of failures is still in excess of the remedial L

action criteria (a and/or b above) the following exception will be allowed until the diesel generator is no longer in violation of the remedial action criteria (a and/or b above).

Requalifiction testing will not be required provided that after each valid 147-~

tests the number of failures in the last 20 and/or 100 valid tests has not increasqd. Once the diesel generator is no longer in violation of the i

remedial action criteria above the provisions of those criteria alone will I

prevail.

Proposed Amendment No. 147 l

L 4-35j l

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s RANCHO SECO UNIT 1 s

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. TECHNICAL SPECIFICATIONS Surve'llance Standards

,4

..(Continued) 1 Specification.

A l4.10.1 C.

-2.

.(b) Verify that th'e HEPA filter bank removes 199.9 percent of the DOP when tested in-place in accordance with ANSI N510 while operating the filter train at a flow rate of 3200 cfm 10 percent.

D. -

Started on a manual signal and operated for 15 minutes in each 31-day period.

Bases The purpose of the Control. Room /TSC Emergency Filtering System is to limit

the particulate and gaseous fission products and toxic products to which the Control Room area and Technical Suppart Center would be subjected during an accidental: radioactive or chemical release in or near the Auxiliary

. Building.. The system.is designed with two redundant filter trains each of which consists'of a moisture separator, a heater, a high efficiency particulate filter, two banks of charcoal filters, a second high efficiency

+a

. particulate filter and a booster fan to pressurize the Control Room and Technical Support Center with outside air.

147---

Because-this system is not normally operated, a periodic test is required to 1

ensure its operability when needed. Monthly testing of this system will show that the system-is available for its designed safety action. During this test the system will be observed for unusual or excessive noise or vibration when-the fan motors are running.

The flow of 1600 cfm makeup air was selected-to limit the maximum radiation dose to occupants of the Control i

4 Room /TSC in'an accident.

For this analysis, both charcoal' filter banks were assumed to provide DF's of 10, while the HEPA filter DF is assumed to be 1

100. 'The laboratory analysis ^to show 195 percent removal of methyl l

radiciodide is necessary to receive credit for a DF of 10.

l Refueling interval testing will verify the mothyl iodide removal efficiency of the charcoal and-the amount of leakage past the charcoal and HEPA filters

/

Late at least equal to the design values.

147-The filtering system is automatically started and the normal system isolated when the radiation level or when the Chlorine level increase.

'M The. testing' required after painting, fire or chemical release, is not to be interpreted to include minor touch-up painting, housekeeping chemicals and detergents, or other routine maintenance or housekeeping activities.

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Proposed' Amendment No. 147 4-41b

_______-_______-___a

s RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.31 NUCLEAR SERVICE ELECTRICAL BUILDING EMERGENCY HEATING VENTILATION AND AIR CONDITIONLMG Specification 4.31.1 The NSEB Emergency HVAC shall be demonstrated operable at least once per 31 days by initiating flow through the essential air handling unit and verifying:

1.

Verify that the air handling unit maintains a flow rate of 24,500 cfm 10 percent.

2.

Verify that the condensing unit is operational.

Acolicability At all times Bases The purpose of the Emergency Nuclear Service Electrical Building Emergency HVAC is to limit high temperatures which the building would be subjtcted to upon loss of normal cooling.

The high temperatures will affect the environmental qualification of safety related electronic equipment housed within the NSEB which is used to support the Control Room /TSC upon accident conditions. The system is designed with an air handling unit and a condensing unit which are activated upon high temperature signals.

Since this system is not normally operated, a periodic test is required to ensure its operability when needed. Monthly testing of this system will show that the system is available for its safety action.

During this test the system will be observed for unusual or excessive noise or vibration when the fan motors are running.

The air flow of 24,500 cfm was selected to limit the temperatures in the building to 80*F maximum (with the exception of the cable shafts).

The system is automatically started when the temperature in the NSEB 147--

.Switchgear Room exceeds 95'F.

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Proposed Amendment No. 147 4-91

g r

j e,

t c

3.,.,

147-RANCHO SECO UNIT 1 O

Y TECHNICAL SPECIFICATIONS 3.

Surveillance Standards o

'4.32 TDI'DIESEt, GEtiERATOR CONTROL ROOM ESSENTIAL VENTILATION SYSTEM Soeci ficatiort" c'

4.32.1 The' Diesel Generator Control Room Essential Ventilation System shall

'be demonstrated operable' at'least once per 31 days by initiating flow' throughjthe essential air handling unit by verifying that'the air

handling unit maintains a flow rate greater than the low flow alarm setpoint.

Anolicability At all times-Bases

-The purpose of.the'TDI Diesel Generator Control Room Essential' Ventilation 4

System is to limit high temperatures which the local control room would be subjected'to upon loss of normal cooling. The high. temperatures will affect the. environmental qualification of safety related electronic equipment housed within.the Diesel Generator Control Room. This Control Room is

. designed with an air handling unit which is activated upon a high temperature ~ signal'.

Since.this system is not normally operated, a periodic test is required to ensure'its. operability when needed. Monthly testing of this system will

.show that.the system is available for.its safety action. During this test

.the_ system'will be observed for unusual or excessive noise or vibration when the fan motors are. running.. The air flow alarm of 10,000 cfm was selected j

.to ensure that the temperatures in the diesel generator control room will 1

stay below the maximum of 122 degrees F maximum.

The system is automatically started by a thermostat when the temperature in

.the Diesel Generator Control Room equals or exceeds 110 degrees F.

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A Proposed Amendment No. 147 b,

4-92 l (

_--_____________Q

v t e Letter Sequence Other
TAC:63030, (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request, Request, Request, Request Acceptance... Supplement, Supplement, Supplement, Supplement Administration Meeting Questions Answers Results Approval, Approval, Approval, Approval, Approval, Approval Other: A11745, Evaluation of DSR-48 Emergency Diesel Generator Crankshafts at Rancho Seco Nuclear Generating Station, ML20126J866, ML20126J973, ML20135E867, ML20149D631, ML20149F003, ML20196E677, ML20196E697, ML20206H162, ML20212B420, ML20214K863, ML20215G661, ML20234C529, ML20234C558, ML20234D524, ML20234D615, ML20234D649, ML20235M565, ML20235Q511, ML20236L543, ML20236N639, ML20236N713, ML20236S088, ML20237B265, ML20237B279
MONTHYEAR1987-12-29 [Table View]

ML20236S088

Text

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