ML20126J866

Amend 68 to License DPR-54,defining Operability & Surveillance Requirements for Plant Essential Electrical Sys & Operability Requirements for Components of Fire Protection Sys

ML20126J866
Person / Time
Site:	Rancho Seco
Issue date:	06/04/1985
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20126J859	List: ML20126J866 ML20126J890 ML20126J973
References
TAC-63030, NUDOCS 8506190108
Download: ML20126J866 (17)

Text

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U; ITED STATES NUCLEAR REGULATORY COMMISSION

,g WASHINGTON, D. C. 20555

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SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION AMENDfiENT TO FACILITY OPERATING LICENSE Amendment No. 68 License No. DPR-54

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by Sacramento Municipal Utility District (the licensee) dated February 17, 1983, as supplemented and revised by your letters of July 12, 1983 January 8 February 7 and March 18, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the

_ Comission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be '

conducted in compliance with the Comission's regulationst D. The issuance of this amendment will not be inimical to the comen defense and security or to the health and safety of the publict E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of facility Operating License No. OPR-54 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 68 are hereby incorporated in the hN P

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f UNITED STATES

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~* NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 g

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5 I June 5, 1985 DISTRIHuu %

M M t File) f  %, * * . . * ,o OR324 Rog i

tiemo File l RIngram l DOCKET No. 50-312 I

MEMOR ANDUM FOR: Docketing and Service Branch Office of the Secretary of the Commission Office of Nuclear Reactor Regulation FROM:

SUBJECT:

Sacramento Municipal Utility District One signed original of the federal Register Notice identified below is enclosed for your transmittal to the Of fice of the Feder 6 ) of the Notide are encfosed for your use.

Register for publication. Additional conformed copies (

O Notice of Receipt of Application for Construction Permit (s) and Operating License (s).

Time for Submission of Views Notice of Receipt of Partial Application for Construction Permit (s) and Facility License (s):

on Antitrust Matters.

Notice of Consideration of lisuance of Amendment to Facility Operating License.

U Notice of Receipt of Applicatigor,F.acility License (s); Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of lisuance of Facility License (s) and Notice of Opportunity for Hearing.

Notice of Availability of NRC Draf t/ Final Environmer.tal Statement.

C Notice of Limitco Work Authoritation.

Notice of Availability of Safety Evaluation Heport.

C Notice of lisuance of Construction Permit (s).

O Nniice of iisu.nce ci raciiiiv Operaiing License (i) or Amendment (i).

O Order.

O E emniion.

O Not ce of craniing oi nenet.

O Other: JIotice of_ Dental Elcase_ insert _ data on_tha 2nd-page-2nd-peregraph-of-this notice for a 30-dayhtetYCntion.per.iod. and_ call Carol _on extension _28340-to-inferwi her of_thcAte_insttled.__ Referenced _ documents _have_bcon-providad-pag.

Of f as of Nuclear Heactor Hegulatan Division of Licensing, ORaf4 Aostatet g [% ,

• 'rees r ,Rlngr4mggy ,

eu-as> .0RtH4:OL 6/ to /n5

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OFFICIAL RECORD COPY

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l, license. The licensee shall operate the facility in accordance with -

the Technical Specifications.

3. This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGU ATORY COP 911SSION hn Y. Stolz, Chief pe ting Reactors Branch #4 ision of Licensing e

Attachment:

Changes to the Technical Specifications Date of Issuance: June 4,1985 n

O e l l I

ATTACHMENT TO LICENSE AMENDMENT NO. 68 FACILITY OPERATING LICENSE NO. DPR-54 DOCKET NO. 50-312 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert vii vii ix ix 3-41 3-41 3-42 3-42 3-42a 3-42a 3-43 3-43

- 3-55a 3-56 3-56 3-57 3-57 3-57A 3-57a 4-33 4-33*

4-34 4-34 4-35 4-35

- 4-91

• 0verleaf page included for document completeness.

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.Section Page 4.26 RADIOLOGICAL ENVIRONMENTAL MONITORING .4 83 4.27 LAND USE CENSU'S 4 86 -

4.28 EXPLOSIVE GAS MIXTURE 4-87 4.29 FUEL CYCLE DOSE 4-89 4.30 INTERLABORATORY COMPARISON PROGRAM SURVEILLANCE 4-90 REQUIREMENT 4 31 NUCLEAR SERVICE ELECTRICAL BUI . DING EMERGENCY HEATING 4-91 VENTILATION AND AIR CONDITIONING

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ozster r n TURIS .5-1 5

5-1 ,

5.1 SITI 5-2 5.2 CCN"N 5.2.1 Emac or Building 5-2 5.2.2 asactor Building Isolation System 5-3 3~'

5.3 IEACTOIL 3.3.1 Essetor Core 3 -t.

3.3.2 Imactor Coolant system 5-4 3.4 NEW AND 5FINT TUEL STOEAGE TACILITIES 5-6 5.4.1 New Tual Inspection and Temporary Storage Rack 5-6 5.4.2 New and Spent Tual Storage lacks and Tailed Tual Storage Container Rack 5-6 5.4.3 New and spent Tual Temporary Storage 5-6 5.4.4 Spent Tual Fool and Storage Rack Design 5-6 vii Amendment No. 7tI, 57, 68

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS LIST OF TABLES Table g 2.3 1 REACTOR PROTECTION SYSTEM TRIP SETTING LIMITS 2-9 3.5.1-1 INSTRUMENTS OPERATING CONDITIONS 3-27 3.6-1 SAFETY FEATURES CONTAINMENT ISOLATION VALVES 3-40 3.14-1 FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS 3-55 3.14-2 3-57a INSIDE BUILDING FIRE HOSE STATIONS }

3-61 3.15-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3-64 3.16-1 RADI0 ACTIVE GASES EFFLUENT MONITORING INSTRUMENTAIION 3-83 3.22-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3-86 3.22-2 REPORTING LEVELS FOR RADIDAGTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 4'-3 4.1-1 INSTRUMENT SURVEILLANCE REQUIREMENTS 4-8 4 1-2 NINIMUM EQUIPMENT TEST FREQUENCY -

4-9 4.1-3 MINIMUM SAMPLING FR'EQUENCY 4-12a 4.2-1 CAPSULE ASSEMBLY WITHDRAWAL SCHEDULE AT DAVIS-BESSE 1 4-13 4.2-2 INSERVICE INSPECTION SCHEDULE 4-42 4.10-1 ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-22a 4.10-2 DPERATIONAL ENVIRONMENTAL RADIATION MONITORING PR03 RAM 4-47c 4.14-1 SNWBBERS ACCESSIBLE DURING POWER OPERATIONS 4-56 4.17-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION 4-57 l 4.17-2 STEAM GENERATOR TUBE INSPECTION 4-57a, 4.17-3 OTSG AUXILIARY FEEDWATER HEADER SURVEILLANCE 4-57b -

4-64 4.19-1 RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l

l 4-66 l 4.20-1 RADIDACTIVE GASEQUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS-iX Amendnent No.18, 53, pp,68 .

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4 AANCHO SECO UNIT 1

• l TECHNICAL SPECIFICATIONS Limiting Concitions for Operation l 3.7 AUX!LIARY ELECTRICAL SYSTEMS Applicability Applies to the availability of off-site and on-site electrical power for station operation and for operation of station auxiliaries. -

Objective ,,

TcL define snose conaitions of electrical power availanility necessary to orovide for safe reactor operation ano to provide for continuing availanility of engineerea safety features in an unrestrictea manner..

Specification 3.7.1 The reactor shall not be'brougnt critical unless tne following conditions are met:

A. All nuclear service buses, nuclear service switengear, anc nuclear service load shedaing systems are operable.

8. Two 220 KV lines are in service.

C. One 6900 volt reactor coolant pump motors bus is energizec.

D. Emergency diese1' generators A ana 8 are operable and at least l 35,000 gallons of fuel are in eacn storage tank.

E. Plant ba'tteries are charged and in service.

F. Two out'cf three battery chargers are operable for 125 volt DC buses "A" and "C" and "8" and "D".

G. Cr.e out of two battery chargers are operable for eacn 125 VDC bus "A2" and "82."

M. Three out of four inverters SIA. 518. 51C. and 51D. ano botn inverters 31A2 and 3182 are operable for 120 volt AC vital bus power.

I. Both start,up transformers. No.1 anc No. 2, are in service.

J. The switerward voltage is 215 KY or above.

K. The interconnections between 460 volt switchgear 3A and 3A2, anc 38 and 382 are operable.

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

A. One 220 KV line sna11 be fully operational and capable of carrying nuclear service ano auxiliary power except as specified in D below.

I 3 41 Amendment No. $$,pp

O AANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation B. Both startup transfomers shall be in service except Wt one will be sufficient if during the time one startup transfomer is inoperable, the associated diesel generator is started and run continuously. ,

C. Both diesel generators

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shall be opersole except that from and after the date that one of the diesel generators is made or

.. found to be inoperable for arty reason, reactor operation is pemissible for the succeeding 15 days provided that during such 15 days the operable ofesel generator shall be load tested daily and both startup transfomers are available. If the diesel is not returned to service at the end of 15 days, the other diesel will be started and run with at least minimum loac continuously for an additional 15 days. If at the ena of the second 15 days the diesel is not returned to service, the reactor shall be brought to the cold shutcown condition within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. ,

D. If the plant is separated from the system while carrying its own auxiliaries, or if all 220 KV lines are lost, continued reactor operation is pemissible providea that one emergency diesel generator is started anc run continuously until a transmission line is restored.

E. The essential nuclear service electrical buses, switchgear, load sheading, and automatic ofesel start systems shall ne operable except as provided in C above and as required for surveillance testing.

F. Nuclear service batteries are charged and in service except that one nuclear service battery may be removed from service for not more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

G. Both sets of nuclear services buses 4A, 4A2 and 48, 482 are operable except that one set of nuclear service buses (4A, 4A2 or 48, 482) may be removed from service for not more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided that' all equipment on the other set of nuclear service buses is operable.

H. If the sw'itchyard voltage goes below 219KY, positive actions, I within the District's procedures, will be implemented in an

[ attempt to return the voltage to 219KY. If the switchyara

, voltage goes below 217KV or remains below 219KY for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, one electrical division will be operated on its diesel generator independent of off-site power. The other electrical division will be operated on off-site power with its associated diesel generator on standby status. The switchyard voltage must be returned to 219KV within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Switenyare voltage above 219KV will allow unrestricted plant operation.

3-42 Amendment No. U , $$, Jp, 58

RANCHO SECO Uh!T 1 TECHNICAL SPECIFICATIONS Limiting Conoittons for Operation 3.7.3 If both diesel generators become inoperable, the unit shall be placed <

in the cold shutdown condition.

l 3.7.4 The pressurizer sna11 be OPERA 8LE with at least 126 kw of pressurizer neaters. With the pressurizer inoperable due to inoperaole emergency power supplies to the pressurizer heater either restore tne inoperable emergency power supply within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STAND 8Y witnin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in NOT SHUTDOWN witnin sne fullowing 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3.7.5 The voltage protection sysam trip setting snall be as stateo in Table 3.7-1.

3.7.6 Voltage Protection System Limiting Conottions A. Startup and operation are not permitted unless the minimut:

requirements and action statements of Table 3.7-2 are met.

8. In the event the number of protective channels falls below tnat listed in Table 3.7-2, the plant will be brougnt to a hot shutdown witnin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

i Bases The auxiliary electrical power systems are arranged so that no single failure i

can inactivate enough safety features equipment to jeopardize plant safety.

The normal source of power to the redundant nuclear service loans 'is by the two startup transformers connected to the 220-KY station switchyard. All of the normal power supply to plant auxiliary loads is provided tnrougn the two unit auxiliary transformers connected to the generator buses. Emergency power for the nuclear service loads is obtained from two on-site diesel generators.

Since the startup transformers are sizes to carry full plant auxiliary loans, it plant auxiliaries' power is not available from the unit auxiliary transformer, it will be obtainee from the startup transformers.

The five 220-KY transmission lines are not under the direct control of tne Rancno Seco station. Therefore, all five cannot be assumed to be available at all times. However, extensive reliability and protective features are utilizac so that the probability of losing more than one source of 220-KY power from faults is low. By requiring that two 220-KV lines are in service prior to startup, one circuit will be immediately available following a loss of the onsite alternating current diesel power supplies ano the other offsite 220-KY line. If there is a loss of all 220-KY remote connections, power to the safety features will be supplied by the diesel generators.

3-42a Amendment No. N , # ,68 r

_ ....- ,-- _ _ - -.,---..,.-.,-eu . - - . . _ . _ . _ - _ , _ _ .

RAhCHO SECO UN!T 1

, . TECHNICAL SPECIFICATIOh5

. Limiting Conditions for Operation )

The 35,000 gallons of fuel stored in each storage tank permit operation of the two diesel generators 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 conoitions. _ -

l The set of four 125 volt DC control panelocards (50A, 508, SOC, 500) and the i set of two 125 volt DC control pane 1 boards (50A2, 5082) are arrangen so t. hat

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i loss of one bus will not prec;1ude safe shutoown or operation of safety features systems. During portsds when one plant battery is oe-energizeo for tekst or maintenance, the associated 125 volt DC bus can De supplien frum its l battery charger.

Each reouncant pair ("A" and "C", "B" ano "D") of safety features actuation and reactor protection 125 volt DC ouses has a s andby battery charger in sodition to a battery charger for each bus. The 125 volt DC buses "A2" anc

'82" each, has a standby battery charger. Loss of power from one battery charger per pair of reoundant DC buses or for DC bus "A2" or "82" has no significant consequence since a standby battery charger is available. In aedition, each 125 volt DC bus can continue to receive power from its respective battery without interruption.

Sufficent redundancy is available with any three of the four 120 volt AC vital

< power buses (51A, 518, 31C SID) in service such that reactor safety is assured. Every reasonable effort will be mace to maintain all safety instrumentation in operation. Following criticality, continued operation with inverters out-of-service as stated in Specification 3.7.1.H is governed by tne individual LCOs for the components powered by the out-of-service inverter.

During periods of station operation under the condition of electrical system degracation, as described above in Specification 3.7.2, the operating action requireo is to start and run sufficient stanoby power supplies so as not to compromise the safety of the plant. As seen in Specification 3.7.2, a time limit is placea on operation during certain degraded conditions baseo on the reif acility of the available power supply.

The requirement that 126 KW of pressurizer heaters and their associated controls being capable of being supplied with electrical power from an emergency bus provides assurance that these heaters can be energized during a loss of offsite power condition to maintain natural circulation at NOT SHUTDOWN.

The voltage protection system is designed to isolate the nuclear service buses from the startup transformers when the bus voltage exceeds the allowaole operating limits of the equipment. The allowable operating range for the 4160 volt nuclear service buses is 3733 to 4626 volts and 397 to 521 volts for the 480 volt nuclear service buses. This corresponds to a switchyard voltage range of 215 to 244 KY. This range of switchyard voltage encompasses the normal operating range of 221 to 239 KY.

REFERENCE FSAR, Section 8 l

3-43 l

Amendment No. U , y ,68 i

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting concitions for Op6 ration Table 3.14-1 (Continuad) - -

FIAE' DETECTION INSTRUMENTS F04 SAFETY SYSTEMS L

Minimum Opersole Z'one Instrument Location Neat Flame Smoke 75-1 8 Switchgear Room (nSDJ 0 0 1 75-2 882 Sattery Room (NSEB) 0 0 1.

75-3 802 sattery Room (kSGJ 0 0 1 76-1 A Switchgear doom (NSEB) 0 0 1 76-2 SA2 Sattery Room (NSE8) 0 0 1 76-3 SC2 Sattery Room (NSE8) . 0 0 1 77-1 Nortn 8 Electrical Equipment Room (NSG) 0 0 1 77-2 South 8 Electrical Equipment Room (NSU) 0 0 1 78-1 North A Electrical Equipment Room (NSES) 0 0 1 78-2 South A Electrical Equipment Room (NSD) u u 1 81 8 Cable Tunnel / Shaft (NSG ) 0 0 3 82 A Cable Tunnel / Shaft (NSEB) 0 0 3 84-2 5 Mechanical Equipment doom (MSE8) 0 0 1 84-3 A Mechanical Equipment Room (NSES) 0 0 1 i

i l 3-55a l

l Amendment No. 68

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AAnLMO SECU UNIT 1 (ECHNICAL $PECIFICATIONS Limiting Conditions for Operation 3.14.3 Sorar ana Sprinkler Systems Specification 3.14.3.1 The spray ana/or sprinkler systems locaten.in the following areas shall be OPEAA8LE: ,

s. Control Room (1,ase 3)

.. b. Controlled Area, Me nanine Level (Zone 20) 1 c. Main Lube 011 Area, Wrade Level (lone 32)

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d. Grade Level (Zone 34)

e. North Ofesel Aoom (4one 40)

f. South Diesel Room (Zone 41J 9 West Contro11ec Area, Grade Level (tone 42)

East Contro11ec Area, Grade Level (Zone 43) i

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, 1. South ano East -20' Level (lone 46)

J. MSEB 8 Cable Tunnel / Shaft (Zone 81)

k. MSE8 A Caole Tunnel / Shaft (Zone 82)

1. MSE8 Mechanical Equipment dooms A ana 8 (lone 84) 3.14.3.2 With one or more of the above, items a through f, required spray and/or sprinkler systems inoperable, within one hour estantish a  ;

continuous fire watch with bacuup fire suppression equipisent for  ;

those areas in which redundant systems or components required to safely shut down and cool down tne plant coule be aanaged; for other 1 areas, establish an hourly fire watch patrol. Restore the system to

,' OPEAASLE status within 14 days or, in lieu of any other report l

required by Specification 6.9, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.5.E within tne next 30 days outlining the action taken, the cause of the inoperability anc the plans ano scheoule for restoring tne system to OPEAABLE status.

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3.14.4 CD, System Specification 3.14.4.1 The CO2 systems located in the following areas shall ne OPERASLE with a minimum capacity of 665 and a minimum pressure of 275 psig in i the storage tank.

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a. lane 12 West DC Control Aous Me usnine Level i

b. Zone 13 West 480 VAC Room Neuanine Level

c. Zone 14 West Caole Tray Area

d. Zone 15 East Cable Tray Area j

. v. Zone 16 East 44) VAL doom Menanine Level l f. Zone 17 East DC Control doom Neuanine Level .

g. Zone 36 West dattery Room Grace Level  : f i l

g kW k f Amendment No. Jp, y,68 .

l

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BANLHO SECO unit 1 TECHNICAL SPECIFICATI0h3 Limiting wnditions for Operation 3.14.4.1 (Continued)

h. Zone 37 West 4160 VAC Room -

1. Zone 38 East 4160 VAC Room J. Zone 39 East Battery Room i ,

k. Zone 40 morth Diesel doom

1. Zone al South Diesel Room

m. Zone 19 Communications Room

n. Zone 75 8 Switchgear koon NSEB

o. Zone 76 A Switchgear Room NSEB

p. Zone 77 8 Electrical Equipmen Acom NSEB

q. Zone 78 A Electrical Equipment Room NSEB l 3.14.4.2 With one or more of the aoove requirva 002 systems inoperaole, within one hour estaolish a continuous fire weten witn backup fire

. suppression equipment for those areas in wnich renuncant systems or components required to safely shut down ano cool oown the plant could be damaged; for other areas, estaolish an hourly fire weten patrol.

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Restore the system to UPERA8LE status within 14 days or, in lieu of any other report required oy Specification o.9, prepare ano suosit a Special Report to the Commission pursuant to Specification 6.9.5.E within the next 30 days outlining the action taken, the cause of tne inoperability and the plans and schedule for restoring the system to OPERA 8LE status.

3.14.5 Fire Nose Stations Specification

! 3.14.5.1 The fire hose stations in the following locations sna11 be OPERA 8LE.

a. All inside stations specified in Table 3.14-2 l b. %erant 2 1

c. %drant 3

d. Hydrant at'soordinates N59'17; E30+20

e. garant at coordinates n58+83; E32+83 3.14.5.2 Wita one or som of the fire hose stations souve inopersole, route an additional equivalent size fire hose to the unprotectec arentss from

, an OPERAdLE hose station within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the inuperacia fire hose is l the primary means of fire suppression; otherwise, route tne additional l hose within 24 nours. Restore the fire nose station to OPEdadLE status within 14 days or, in lieu of any other report required by Specification 6.9 prepare ano suosit a Special Report to tne I Caumission pursuant to Specification 6.9.5.E within tne next 30 days outlining the action taken, the cause of the inoperability and plans and schedule for restoring the station to OPEAABLE status.

j 3-57 5mendment No. N M, $7, 68 4

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RANCNU SECO UNIT 1 TECHNICAL SPECIFICATI0kS Limiting Gonettions for Operation Table 3.14-2 _ .

INSIDE SUILDING FINE NOSE STATIONS l W No. Location ,,

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Auxiliary Bulloing Nose Stations i HS 1 +40 ft. Level Corridor oy Counting Room NS 2 +40 ft. Level Corrioor Across from Control doom NS 3 +40 ft. Level Corrioor by Chemistry La0 MS 4 +40 ft. Level Corridor by Cleaning 200c NS 5 +20 ft. Level in Ventilati,on Equipment Room

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NS 6 +20 ft. Level Corridor by Comunicattuns Room NS 7 Grade Level by CRD Cooling Water Meat Exchanger MS 8 +20 ft. Level Corridor by Ventilation Equipment Woom l NS 9 +20 ft. Level Corridor by A/C Equipment Room

! MS 10 Grade Level Corridor by Diesel Generator Room

! NS 11 Grade Level Corridor Across from East 4160 Switchgear Roon NS 12 Grace Level Corrioor Across .from East dattery Room MS 13 Grade Level Corridor by East End Stairwell NS 14 Grace Level by Weste Solidification Area MS 15 -20 ft. Level NPI hmp A Roon

.NS 16 -20 ft. Level Containment Penetration Valve Area NS 17 -20 ft. Level Corridor by Wasta lies Decay Tank Acom NS lb -20 ft. Level Corridor dorth or dA Evaporator nous MS 19 -47 ft. Level Stairway by East ano West DNA Pump Rooms MS 20 -20 ft. Levg1 Corridor East of NPI Pump 8 Moom II NSES Nose Stations MS 21 MSEB First Floor North NS 22 ASE8 First Floor South

NS 23 MSE8 Second Floor morth MS 24 aSES Second Floor South i

4 3-57a Amendment No. M, 68

. . RANCHO SECO UNIT 1 TECHNICAL SPECIFfCATIONS Surveillance Standards 4.5.3.2.8 1. The section of the system that is downstream of the pump suction isolation valve shall be tested by use in normal operation or by hydrostatically testing at 180 psig.

2. The section of the system from the containment emergency sump isolation valve to the pump isolation valve shall be tested at no less than 52 psig as a containment local leak rate test under para 4.4.1.2. .

3. Visual inspection shall be made for excessive leakage from components of the system. Any excessive leakage shall be measured by collecting and weighing or hy another equivalent method.

Bases The leakage rate limit for the Decay Heat Removal System is a judgment value based on assuring that the components can be expected to operate without mechanical failure for a period on the order of 200 days after a loss of coolant accident. The test pressures achieved either by normal system operation or hy hydrostatically testing, give an adequate margin over the highest pressure within the system after a design basis accident. Similarly, the pressure tests for the return lines from the containment to the Decay Heat Removal System are. equivalent to the, peak calculated pressure after a LOCA. A Decay Heat Removal System and Reactor Building Spray System sum total leakage rate of 6.0 gal /h will limit offsite exposures due to leakage to insignificant levels relative to those calculated for leakage directly from the Reactor Building in the design basis accident. The dose to the thyroid calculated as a result of this leakage is 7.21 rem for a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> exposure at the site

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boundary. (1)

REFERENCES (1) FSAR, paragraph 14.3.9.3.

a e

Amendment No, g 68 4-33 1

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 46 EMERGENCY POWER SYSTEM PERIODIC TESTING Applicability Applies to the periodic testing and surveillance of the emergency power system. - -

Objective -

To verify that the emerge'ncy power sources and equipment are operable ynd respond properly when required.

Specification l

4.6.1 At intervals not to exceed one month, a test of the diesel generators will be performed to verify proper operation of these emergency power sources and associated equipment. This test will be perfomed to assure that:

A. Each diesel generator can be started from the control room.

B. Each diesel generator can be synchronized with its associated 4160 volt nuclear service bus.

4.6.2 During each refueling interval, a test of the diesel generators and emergency start circuits shall be perfomed to verify that these emergency power sources and associated equipment are operable by:

A. Simulating a loss of offsite power in conjunction with a safety features actuation signal, and:

1) Verifying de-energization of the nuclear services buses and operation of the load shedding circuitry.

2) Verifying the diesel starts from ambient condition on i the auto: start signal and energizes the nuclear l

services buses, and by verifying proper operation of the automatic load sequencing circuitry, including

. manual closing of the A Train intertie breakers from 1 the Control Room and manual energization of the A Train essential HVAC from the Control Room. The B Train intertie breakers are automatically closed and the B Train Control Room essential HVAC System is automatically energized. The diesel generators will be operated for at least 5 minutes in this condition.

3) Verifying that on diesel-generator trio, the loaa shedding circuitry operates properly and the diesel restarts on the auto-start signal, anc by verifying proper operation of the automatic loaa sequencing circuitry. The diesel generator will be operated for at least 5 minutes in this conoition.

B. Load testing the diesel generators to 5FAS capacity.

Amendment No. # , H , 58 4-34

, , RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS.

Surveillance Standards 4.6.5 Diesel generator fuel oil supply shall be tested as follows:

A. During the monthly diesel generator test, the diesel fuel oil transfer pumps shall be monitored for operation.

8. Once a month, quantity of the diesel fuel oil shall be logged and checked 'against minimum specifications.

. The tests specified will be considered satisfactory if control room indication and/or visual examination demonstrates that all components have operated properly.

4.6.6 The pressurizer shall be tested as follows:

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

B. The emergency power supply for tne pressurizer heaters snall be demonstrated OPERABLE at least once per 18 months by transferring power from the normal to the emergency power supply and energizing the heaters.

Bases 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. They assure the manual closure of the 3A, 3A2 intertie breakers. The tests also assure the manual energization of the A Train Control Room essential HVAC System functions in the event of a loss of all normal AC station service power and upon receipt of an SFAS signal. Tney assure tne 3B, 3B2 intertie breakers are automatically closed and the B Train Control Room essential HVAC System is automatically energized. The 3A-3A2 and 38-382 l interties are not required if the event is only a safety features actuation.

The testing frequency specified is intended to identify and pemit correction of any meenanical or electrical deficiency 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.

Precipitous failure of the plant battery is extremely unlikely. The surveillance specified is that which has been demonstrated over the years to l Provide an indication of a cell becoming unserviceable long before it fails.

REFEREkCE (1) IEEE 308 Amendment No. U , 68 4-35

HANCho bECO UNIT 1 TECHNICAL 5ptCIFICATIOkS Surveillance Standacds .

4.31 WUCLEAR SERVICE ELECTRICAL du!LDING EMERGENCY MEAT!nd VENT!LAT!0m AND mn wnumunanu Asoficasility Y Applies to the nuclear Service Electrical Building (hiL8J Neating Ventilation and Air Conditioning (HVAC) System components.

Objective To verify that this system and its components will ne sole to perfom their design functions.

Specification 4.31 .1 The NSEB Emergency HVAC sna11 be:

A. Demonstrated operable at least once per 31 days o3 Initiating flow through the essential air handling unit.

1. 'ferify that the air handling unit maintains a flow rate of 24.500 cfm

• 10 percent.

2. Verify that the condensing unit is operational.

I hus -

The purpose of tne Emergency Nuclear Service Electrical Suf1 ding HVAC is to limit high tamperatures which the building woulo be sucjec.ed to apon loss of normal cooling. The nigh temperatures will affect the environmenal galification of safety related electronic equipment houno within the ASE8  !

unich is used to support the Control Roam /TSC upon accievit conoitions. The system is designed with an air handling unit ano a concensing unit which are activated upon high temperature signals.

Since this system is no): nomally operated, a periodic test is requireo to

ensure its operant 11ty wNen neeeed. Monthly testing of this system will show that the system is available for its safety action. during this test the system will be osserved for unusual or eACessive noise or Vibration when the fan motors are running. The air flow of 24.500 cfm was selected to limit the

,' temperatures in the huilding to up*F maximum (with the exception of the caele shafts).

The system is automatica11g started when tne temperature in tne NSE8 Switchgear Room escoeds 95 F. except upon loss of offsite power'; in which case, tne system can os annually startee by the operator.

1 I

l 4-91 Amendment No. 68

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