Text

Amend 94 to License DPR-54,adding Criteria to Tech Specs to Reflect Addition of Two Diesel Generators & Associated Mods to Facility Emergency Electrical Distribution Sys
	ML20149L260
Person / Time
Site:	Rancho Seco
Issue date:	02/09/1988
From:	Knighton G; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20149L242	List: ML20149L239; ML20149L260; ML20149L276;
References
	NUDOCS 8802240166
	Download: ML20149L260 (51)
	v • d • e

Q QtC f[k UNITED STATES NUCLEAR REGULATORY COMMISSION n

"5 _

,1 WASHINGTON. D. C. 20555

%,...../

SACPAMENTO MUNICIPAL UTILITY DISTRICT DOCKET N0. 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION AMEN 0 MENT TO FACILITY OPERAT!hG LICENSE Amendment No. 94 License No. OPR-54 1.

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

A.

The application for amendment by Sacramento Municipal Utility District (the licensee) dated October 2,1986, as supplemented December 13, 1986, April 1, October 8 and 26 and November 17, 1987, complies with the standards and requirerrents of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the 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 regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and 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.

P

o-5 p 2.

Accordingly, the license is amenced 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. DPR-54 is hereby dmended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 94, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This amendment to the Technical Specifications shall become effective within 30 days of the issuance date. The implementation delay is provide to allow time for modification of affected procedures and promulgation of the changes to personnel.

FOR THE NUCLEAR REGULATORY COMMISSION o C Acid 67. / vaird George W. Knighton, Director W Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: February 9, 1988 1

1 i

February 9, 1988 s.

ATTACHMENT TO LICENSE, AMENDMENT N0. 94 FACILITY OPERATING LICENSE N0. DPR-54 p0CKET NO. 50-312 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert IV IV VII VII IX IX 3-2a 3-2a 3-2b 3-41 3-41 l

3-41a 3-42 3-41b 3-42a 3-42 3-42b 3-42a 3-42c 3-43 3-42d 3-42e 3-42f 3-429 3-42h 3-421 3-42j 3-43 3-43a 3-43b 3-43c 3-43d 3-55c 3-55c 3-56c 3-56c i

3-57b 3-57b i

3-93 3-93a J

4-7c 4-7c 4-30 4-30 l

4-31 4-31 4-34 4-34 4

4-34a 4-34a 4-34b 4-34c j

4-34d 4-34e 4-34f li 4-349 i

l i

j

> Remove I"S*#

4-34h 4-34i 4-34j 4-34k 4-341 4-35 4-35 4-41b 4-41b 4-91 4,91 4-92

R.8RCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued) l Section 3.14.5 Fire Hose Stations 3 56a 3.14.6 Fire Rated Assemblies 3-58 3.15 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION 3-60 3.16 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 3 63 3.17 LIQUID EFFLUENTS 3-70 3.17.1 Concentration 3-70 3.17.2 Dose 3 71 3.17.3 Liquid Holdup Tanks 3-72 3.18 GASEOUS EFFLUENTS 3 73 3.18.1 Dose Rate 3 73 3.18.2 Noble Gases 3 74 3.18.3 lodine-131. Tritita and Radionuclides in Pjrticulate Form 3-75 3.19 GASEOUS RA0 WASTE TREATHENT 3-78 3.20 GAS STORAGE TAtKS 3 79 3.21 SOLIO RADIOACTIVE WASTES 3-80 3.22 RADIOLOGICAL ENVIRONMENTAL MONITORING 3 81 3.23 LAND USE CENSUS 3 87 3.24 EXPLOSIVE GAS HIXTURE 3-89 3.25 FUEL CYCLE DOSE 3 90 3.26 INTERLABORATORY C0r1 PARIS 0N PROGRAN 3-92 3.27 NUCLEAR SERVICE ELECTRICAL BUILDING ENERGENCY HEATING 3-93 AND AIR CONDITIONING 3.28.

TDI DIESEL GENERATOR CONTROL ROOM ESSENTIAL 3-93a E NTILATION SYSTEM 3.29 METEOROLOGICAL 110NITORING INSTRUMENTATION 3 94 Amendment No. 25, 35, 5), 35 88,94 iv

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued)

Section Pajyt 4.26 RADIOLOGICAL ENVIRONMENTAL MONITORING 4-83 4.27 LAND USE CENSUS 4 116 4.28 EXPLOSIVE GAS MIXTURE 4-87 4.29 FUEL CYCLE 00SE 4-89 4.30 INTERLABORATORY COMPARISON PROGRAM SURVEILLANCE REQUIREMENT 4-90 4.31 NUCLEAR SERVICE ELECTRICAL BUILDING EMERGENCY HEATING 4-91 VENTILATION AND AIR C0401TIONING 4.32 TDI DIESEL GENERATOR CONTROL ROOM ESSENTIAL 4-92 VENTILATION SYSTEM 4.34 HETER 0 LOGICAL MONITORING INSTRUMENTATION 4 93 5

DESIGN FEATURES 5-1 5.1 SITE 5-1 5.2 CONTAIHMENT 5-2 5.2.1 Reactor Building 5-2

\\ \\

5.2.2 Reactor Building Isolation System 5-3 5.3 REACTOR 5-4 5.3.1 Reactor Core 5-4 5.3.2 Reactor Coolant System 5-4 5.4 NEW AND SPENT FUEL STORAGE FACILITIES 5-6 S.4.1 New Fuel Inspection and Temporary Storage Rack 5-6 5.4.2 New and Spent Fuel Storage Racks and Failed 5-6 Fuel Storage Container Rack 5.4.3 New and Spent Fuel Temoorary Storage 5-6 5.4.4 Spent Fuel Pool and Storage Rack Design 5-6 i

Amendment No. 24, 57, SV. W. 94 vil i

RAhCHO SECO UNIT 1 TECHNICAL $PLCIFICATIONS LIST OF TA8tES 2.3 1 REACTos PROTICTION SYSTEN TR!P SETTING LIMITS 29 3.3 1 PRIERY COOLANT SYSTEM PRES $URE !$0LATION VALYES

).22a 3.5.1 1 INSTRUMENTS OPERAT!WG CON 0!TIONS 3 27 3.6 1 SAFETY FEATURES CONTA!KMEWT 150LAT!0N VALYES 3 40 3.7 1 YOLTAGE PROTICTION SYSTEM RELAY TRIP YALUES 3 41a 3.7-2 VOLTAGE PROTECTION SYSTEM LIN! TING CONDITIONS 3-42k j

3.14-1 FIRE DETECTION INSTRUENTS FOR SAFETY SYSTEX5 3 55 3.14 2 WATER SUPPRES$10N 20KES 3-566 c 3.14 3 CARBON O!0XIDE SUPPRESSION ZONES 3-564 e 3.14.4 FIRE HOSE STATIONS 3g57a.b 3.15 1 RADICACT!YE LIQUID EFTLUCWT MON!T04!NG INSTRMWTATION 3 61 3.16-1 RAD 10ACT!YE GASES EFFLUENT MONITORING INSTRUMEWTATION 3 64 3.22-1 RADIOLOGICAL ENV! Row (WTAL MON!TORING PROGAM 3-83 3.12-1 REPORf!WG LEVELS FOR RAD 10 ACTIVITY CONCINTRIT10t33 84 IN ENY!ROMWTAL SAMLES 3.29-1 METEOROLOGICAL MONITORING INSTRUMENTATION 3 95 4.1-1 luSTRMWT SURVE!LLANCE REQUIRDOffs 4-5 4.1-2 MININ,'5 EQUIPIOff TEST FREQUENCT 4-8 4.1 3 M!N! MUM SAMPLING FREQUENCT 49 4.2 1 CAPSULE A$$EglY WITHDRAWAL SCHEDULE AT DAVI5-BESSE 1 4 12b 4.6-1 DIESEL GENERATOR TEST SCHEDULE 4-34j j

4.6-2 ADDITIONAL RELIABILITY ACTIONS 4-34k 4.14 1 SWUl8ERS ACCES$1BLE DURING POWER OPERATIONS 4 47c 4.17-1 MINIMUM NUMBER OF STEM GENERATORS TO BE 4 56 IMSPECTED DUR!uG IKSERVICE INSPECTION 4.17 2A STEM GENERATOR TUBE INSPECTION 4 57 4.17-28 STEM GENERATOR TVBE INSPECTION ($PECIFIC LIMITED AAEA) 4 57a 4.17-3 OT54 AVI!LIARY FEEDWATER EADER SURVEILLANCE 4 57b, 4-57c 4.19 1 RA010ACT!YE LIQUID EFFLUENT MONITOR!WG INSTRMNTATION 4 64

$URVE!LLANCE REQUIRDENTS 4.20 1 RAD 10ACT!YE GA$tous EFFLUENT MONITORING INSTRL80tTAT10N 4 44

$URYIILLMCI REQUIRDOffs ta

% 6aent No. M.. W pf. W X J C 26, si, V1 W,94

AANCHO SECO UN!? 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.1.1.7 The pressurizer shall be OPERABLE, except when the reactor is in COLD SHUTDONN, with 3 groups of heaters in two separate banks that j

are capable of being powered by the diesel generator trains. With the heaters in one bank non-OPERABLE either restore the bank to OPERABLE status within 3 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 HOT SHUTDOHN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With the heaters in both banks non-OPERABLE, either restore one bank 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 .

8ases A reactor coolant pump or decay heat removai pump is required to be in operation before tne boron concentration is reduced by dilution with makeup wa te r.

Either pump will provide mixing which will prevent suoden positive reactivity changes caused by dilute coolant reaching the reactor. One decay heat removal pump will circulate the equivalent of the reactor coolant system volume in one half hour or less.

(1)

The decay heat removal system su'etion piping is designed for 300 F and 300 thus, the system can remove decay heat when the reactor coolant system psig; low this temperature.

is be (2) (3)

One 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, pressurizer heaters, and reactor decay heat.

(4)

Both pressurizer code safety valves are required to be in service prior to criticality to conform to the system design relief capabilities.

The code safety valves prevent overpressure for rod withdrawal accidents.

(5) The Pressurizer code safety valve lift set point shall be set at 2500 psig = 1 percent allowance for error and each valve shall be capable of relieving 3a5,000 lb/hr of saturated steam at a pressure not greater than 3 percent above the set pressure.

The electromatic relief valve setcoint was established to prevent operation of the Safety Yalves during transients.

Two pump operation is limited until further ECCS analysis is perfomed.

When the re' actor is not critical but TAY is above 280* F, one steam generator provides sufficient heat removal capability for removing decay heat.

However, single efailure considerations require that botn steam generators be operable.

When TAV is below 280*F, a single reactor coolant loop or CHR locp prontoes i

sufficient heat removal capability for removing decay heat; but single failure considerations require at least two loops be OPERABLE.

Thus, if the reactor coolant loops are not OPERA 8LE, this specification requires two ChR loops to be OPERA 8LE.

The purpose of the high point vents is to vent noncondensible gases from the ACS which may inhibit core cooling during natural circulation.

In compliance 1

with 10CFRSO Appendix R the power to all the valve actuators in the vent patn has been removed.

Amendment No. N,88,87,M,94 3-2a k

lc -

i RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation There are 3 groups of heaters in bank 2, and 3 groups of heaters in bank 3 that are capable of being powered by the diesel generator.

Each set of the 3 groups of heaters has a nominal rating of 126 kw which provides assurance that these heaters can be energized during a loss of offsite power condition to maintain natural circulation at HOT SHUTDONN.

REFERENCES (1)

USAR Tables 9.5-2, 4.2-1, 4.2-2, 4.2-4, 4.2-5, 4.2-6 (2)

USAR paragraph 9.5.2.2 and 10.2.2 (3)

USAR paragraph 4.2.5 (4)

USAR paragraph 4.3.8.4 and 4.2.4 (5)

USAR paragraph 4.3.6 and 14.1.2.2.3 l

l l

1 I

i Amendment No. 87.94 3-2b

}

t RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.7 AUXILIARY ELECTRICAL SYSTEMS Soecification i

3.7.1 The reactor shall not be brought critical unless the following conditions are met:

Aeolicability 3

HEATUP until STARTUP.

A.

At least two physically independent circuits between the offsite transmission network and the onsite Class 1 distribution system are in service.

B.

The switchyard voltage is 219 KV or above.

C.

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

D.

Nuclear services 480V buses 3A, 3A2, 38, 382, 2Al, 2B1, 2A3, 283, 2A4, and 2B4 are operable.

4 E.

Two separate 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:

4 V

1.

Separate day tanks containing a minimum volume of 65 percent of tank capacity (265 gallons) of fuel for each A and B and j

50 percent of tank capacity (315 gallons) of fuel for A2

)

and 82.

2.

A separate fuel storage system containing a minimum useable i

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.

F.

Nuclear Service batteries BA, BB, BC, BD, BA2, BB2, BC2, and

]i BD2, which supply vital 125 volt DC buses SOA, SOB, SOC, 500, SOA2, 5082 SOC 2, and S002 are charged and in service.

1 i

G.

Each vital 125 volt DC bus SOA, SOC, SOB, 500 SOA2, 50B2, l

SOC 2, and 5002 shall have its normal battery charger aligned to it, j

H.

Nuclear service inverters SIA2, SIB 2, SIC 2, and $102, and static l

switches H8TA3, H8TB3, HBTC3, and HBT03 are operable for 120 volt AC vital bus power.

i l

Amendment No. 46,68,81,94 3-41

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied.

Soecification A.

Two physically independent circuits between the offsite transmission network and the onsite Class 1 distribution tystem.

Aeolicability STARTUP through P0HER OPERATIONS Action Should all but one offsite circuit be removed from service a.

Within I hour 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 requ.irement 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 *,

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

i l

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

Amendment No, 46.68.87,94 3 42

-l j

)

l RANCHO SECO UNIT 1 4

TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.7.2 The reactor shall not remain critical unless all of the following requiraments are satisfied.

Soecification B.1 Both diesel generator trains shall be OPERABLE prior to leaving COLD SHUTDOHN conditionf.

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-OPERABLE diesel generators in a train result in that train being non-OPERABLE.

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

Acolicability 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:

a.

Within I hour the operability of at least two offsite circuits shall be demonstrated by obtaining acceptable results from i

performing surveillance requirement 4.6.1.A; and at least once per B hours thereafter; or go to 3.7.2.C.

b.

If any single diesel generator became non-OPERABLE 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-OPERABLE 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-OPERABLE condition was 6

established, the reactor shall be in HOT SHUTDOHN within the l

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

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

l J

l Amendment No. 31,46,56,68,87,94 3 42a l

i

1 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation i

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

Soecification C.

At least two offsite circuits and both diesel generator trains shall be OPERABLE.

Aeolicability STARTUP through P0HER OPERATIONS Action Should all but one offsite circuit and one diesel generator train both become non-OPERABLE a.

within I hour the operability of the remaining offsite circuit shall be demonst*ated 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, b.

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

With 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 3.7.2.8 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 LCO 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 non-OPERABLE diesel generator is

stored to OPERABLE status, i

3 42b Amendment No. p,99,5G,dd,87,94

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied.

Soecification D.

At least two offsite circuits shall be in-service.

Acolicability STARTUP through POWER OPERATIONS Action 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 diesel generator shall be demonstrated to be OPERABLE by obtaining acceptable results by seqeentially 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 .

With 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-OPERABLE condition was established.

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

1 i

t i

i Amendment No. JJ Jf,J@,$$,37,94 3 42c l

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied.

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

Acolicability STAR 1UP through P0HER OPERATIONS Action Should the following diesel generators combinations (GEA and GEA2; or GEB and GEB2) become non-OPERABLE 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 become non-OPERABLE due to any cause cther thar preplanned preventive maintenance or testing, then if any diesel ge.'etator has not been successfully tested within the pravious 24 hNrs, demonstrate its OPERABILITY by performing surveillanca requirement 4.6.3.A.4 for each such diesel genei&ior, 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-OPERABLE 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 SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUT 00HN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , d.

If one non-OPERABLE 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. LCO which commenced at the time the initial non-OPERABLE condition was established.

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

1 Amendment No. JI,A6,50,68,81.94 3 42d

}

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS

^

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

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

Aeolicability STARTUP through POWER OPERATIONS Action Should diesel generator pairs GEA and GEB; GEA and GEB2; GEB and GEA2; or GEA2 and GE32 become non-OPERABLE then complete all of the following actions:

a.

Within I hour the operability of at least two offsite circuits shall be demonstrated by obtaining acceptable results after performing surveillance requirement 4.6.1.A; or be in HOT t

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-OPERABLE 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 SHUTDOHN 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 , If one non-OPERABLE diesel generator in the GEA and GEB; GEA and GEB2; GEB and GEA2; or GEA2 and GEB2 non-OPERABLE pair is 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.

1 l

i..o4 oc so. ix,,,se. B,87.,4 3 42.

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied.

Soecification F.

Nuclear service buses as listed in 3.7.1.C and 3.7.1.0 shall be 00ERABLE.

Aeolicability STARTUP through PCHER OPERATIONS Action One nuclear service bus or one train of nuclear service buses may be removed from service 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 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 SHUTCOHN 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 .

t i

i l

Amendment No. 31,46,J6,68,87,94 3 42f j

~

s \\,

.)

i RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS l 3.

Limiting Conditions for Operation 3. '/. 2 The reactor shall not remain critical ualess all of the followiag requirements are satisfied.

hi fintion G.

Nuclear service batteries as listed in 3.7.1.F shall be charged and in-service.

Acolicability STARTUP through P0HER OPERATIONS 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 SHUTDOHN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

I Amendment No. 31,46,50,60,81,94 3-42g

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied.

Soecification H.

Nuclear service battery chargers as listed in 3.7.1.G shall be OPERABLE.

Acolicability STARTUP through P0HER OPERATIONS Action Should one nuclear service battery have no battery charger 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 SHUTDOHN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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 SHUTDOHN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLO SHUTDOHN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l Ameniment No. 31,66,50,68,87,94 3-42h

_ _ _ - ~. _

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.7.2 The reactor shall not remain critical unless all of the following l

requirements are satisfied.

Soecification j

I.

Nuclear service inverters and static switches as listed in l

3.7.1.H shall be OPERABLE.

-l l

Acolicability l

l STARTUP through P0HER OPERATIONS Action I

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 , j

a.

the reactor shall be in HOT SHUT 00HN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and

.f I

in COLD SHUT 00HN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l 0

Amendment No. 94 3-421 l

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied.

Soecification J.

The switchyard voltage is at least 219KV.

Acolicability STARTUP through POWER OPERATIONS Action Should the switchyard 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 KV.

If the switchyard voltage goes below 219 KV, 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.

Should 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 SHUT 00HN 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 .

An2ndment No. 94 3-42j

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 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 SHUTDOHN within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Amendment No. JJ,pp,$$,94 3-43 e

l 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)

A.

Definite Time Delay Trip Set Point 3771 z 38 5.0 z 0.5 (Drop Out) 8.

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

F Amendment No. 46,50,87,94 3-43a

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE 3.7-2 (Note 1)

Total No. of Minimum Functional Number of Relays /

Channels Channels Action Unit Channels Channel To Trip Operable Undervoltage 3/ Bus 2

2/ Bus 2

A ACTION STATEMENTS Action A -

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

a.

The Inoperable Channel is placed in the tripped condition within one hour.

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 testing.

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

l Amendment No. 46,87.94 3-43b y

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS 4

Limiting Conditions for Operation 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 loads is by the two startup transformers to connect the 220-KV station switchyard. All of the 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 8 is both diesel generators B and 82). Since the startup transformers are sized to carry full plant auxiliary loads, if plant auxiliaries' power is not available from the unit auxiliary 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-XV 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 and the other offsite 220-XV 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 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 82 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.

The set of eight 125 volt DC control buses (SOA, SOB, SOC, 500, SOA2, SOB 2, SOC 2, and S002) 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.

Amendment No. H.H.88,94 3-43c

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Haiti (Continued)

Each redundant pair ("A" and "C", "B" and "0") of the eigh^ 125 volt DC control buses (SOA and SOC, SOB and S00, SOA2 and SOC 2, ano SOB 2 and S002) has a standby battery charger in addition:to its normal battery charger. On 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 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 degradation, as described above in Specification 3.7.2, the operating action required is to start and run sufficient standby power supplies so as not to t

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.

Four nuclear service inverters (SIA2, SlB2, SlC2, and SID2) and static switches (H8TA3, H8TB3, H8TC3, and H8T03) are required to be operable to power the 120 volt AC vital buses.

The nuclear service inverters are l

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

The voltage protection system is designed to isolate the nuclear service buses from the startup transformers before the voltage drops below the allowable operating limit of the equipment.

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

This corresponds to a nominal switchyard voltage range of 219 KV.

REFERENCE USAR, Section 8 3-43d Amendment No. H,4,$$,57.94 i

RANCHO SEC0 UNIT 1 TECHNICAL $PECIFICATIONS I

Limiting Conditions for Operation TABLE 3.14-1 l

FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS (Continued)

Detection Number of detectors in zones.

Zone Instrument Location All Required to be OPERA 8LE Heat

' Flame Smoke 87 NSEB Computer Roos 8 0

0 5

89 NSEB Computer Room A 0

0 5

104 Technical Support Center 0

0 15 105 Diesel Generator Building 2

3 2

v 106 Diesel Generator Building 2

3 2

109 Chemical Lab Area 0

0 19 Auxiliary Building 110 Auxiliary Feedwater Pump Area 0

4 0

)

j 3-55c Amendment No. $$, 94

- - ~

-,,,-e,,

.:_,-....---_..,-,_,--m,

-c

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.14-2 WATER SUPPRESSION ZONES (Continued)

ZONES AREAS 41 South Ofesel Generator Room - Grade Level, Auxiliary Building 42 Electrical Penetration Roos, Grade Level, Auxiliary Building 43 Chemical Mix Area - Grade Level, Auxiliary Building 46 Hut Area - Basement Level Auxiliary Building 47 Pipe Penetration Area - Basement Level, Auxiliary Building 81 NSEB B Cable Shaft 82 NSEB A Cable Shaft 83 NSEB Corridor,1 foot Level 84 NSEB Corridor, 21 feet Level 85 NSEB Corridor, 40 feet Level 87 NSEB Computer Room B 89 NSEB, Computer Room A 104 Technical Support Center, 40 feet level of Aux. Bldg.

105 Diesel Generator Building 106 Diesel Generator Building

~110 Auxiliary Feedwater Pump Area 3-56c Amenchnent No. )!I, 94 I

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting conditions for Operation Table 3.14-4 FIRE HOSE STATIONS ID No.

Location FFHS-T-009) 2 Stations Ea.st Wall Elevation 20' FPHS-T-010)

FPHS-T-011) 2 Stations West Wall Elevation 20' FPHS-T-012) 1 FPHS-T-013 1 Station North Wall Elevation 40' FPHS-T-014 1 Station South Wall Elevation 40' FPHS-T-015) 2 Stations East Wall Elevation 40' FPHS-T-016)

,FPHS-T-017) 2 Stations West Wall Elevation 40' T

-T-018)

Iv Hydrants FHV-002 Hydrant No. 2

)

FHV-003 Hydrant No. 3 FHV-024 Hydrant No. 24 FHV-026 Hydrant No. 26 V

Diesel Generator Building Hose Stations FPHS-D-001 Train A Engine Room Elevation O' FPHS-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' FPHS-0-006. Train B Mezzanine Elevation 18'6" 3-57b Amendment No. 85, 94

RANCHO SECO UNIT I TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.27 Nuclear Service Electrical Buildina Emeroency Heatina Ventilation and Air Conditionina System Soeci fication 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 shall not exceed 104*F.

Acolicability HEATUP through P0HER 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.

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

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 lea:F: 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 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

1 fMifti 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.

l j

Amendment No. 94 3-93 i

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation I

(

3.28 TDI Diesel Generator Control Room Essential Ventilation System l

Soecification 3.28.1 Both TDI Diesel Generator Control Room Essential Ventilation trains l

shall be OPERABLE.

Aeolicability HEATUP through POWER OPERATIONS l

Action a.

With one TDI Diesel Generator Control Room Essential Ventilation train non-OPERABLE, demonstrate the operability of the remaining train.

Restore the non-OPERABLE train to OPERABLE status within 3 days or be in at least HOT SHUTDOHN l

within six hours and in COLD SHUTDOHN within the following 30 l

hours.

l l

b.

With both TDI Diesel Generator Control Room Essential Ventilation trains non-OPERABLE, restore at least one non-0PERABLE 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 fo11cwing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . With one non-OPERABLE train restored to OPERABLE status, continue with Action a. above us;ng the time the remaining non-0PERABLE condition was established as the start of the LCO.

l 111 111 The TDI Diesel Generator Control Room Essential Ventilation System l

is required to maintain the temperature in the control room below

{

122*F to protect required electrical components.

j Amendment No. 94 3-93a l

RANCNB SECO WIIIT I TECHNICAL SPECIFICAllou1 Serveillance Standeres TAett 4.1-1 (Centlawed)

INSTauntNT Suett!LLANCE afgulatntNTS Channel Gescriptfee Check Test Calibrate temarks p

g$. Safety Velve Positten In.

dicator (Seckup Detecterl e

2 Aceostic M

N/A a

=

0

57. Voltage Pretection (1) Test using underveltage relay's (Definite and Inverse "TRIP TEST." No quantitative w"

Time Delay Relays) esasurements.

a.

Undervoltage Relay N(1)

N/A R

b Voltage Setpoint b.

Undervoltage Relay N(1)

N/A R

O Time Delay SF. Voltage Protectfen 1(18 fil Ceapere weltmeter readfags

e a.

thederveltage N

8 h.

Overvet tage N

A c.

Time teley N

a SS. Centefament Area Nigh 3

Nils R

(18 Test estag f astelled source Asege Montter

59. Ufde Reage Caetalsmeet N

II/A A

Water tevel M

N.

Centefament Iqrdregen 1

M q

- Analyser St. Energency sesy Level N

II/A R

St. Centefament Wide reage M

N/A 8

Pressere stealter/ Recorder

63. Istgh sange alable Gas 1

N A

ttflueet staatters

- AS Enl.eust Stack

. Assa. Bulldf ag 5 tack

- aedweste vent l

l 84 stein Steen Line mediatlee 1

Mll) a (1) Test estag f astelled searce Noesters

45. Subcesitag Norgfa 80 setters N

N/A a

44. lagere Thermecesples N

N/A R

47. Lou Temperatere ever.

3/4 (1)

A (Il Prfor to coeldeias.

Pressere Protectica (ENOV)

RANCHO SEC0 (JNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 2.

The test will be considered satisfactory if control board indicatien verifies that all. components have responded to the actuation signal 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 Comoonent 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)(1).

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.

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 pre:ssurizer heaters shall be demonstrated OPERABLE at least once per refueling interval by using the Nuclear Service Bus to energize the heaters.

/

Amendment Noi 76,94 4-30

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards-SA191 The Reactor Building emergency cooling systems and Reactor Building spray system are designed to remove the heat in the containment atmosphgre to prevent the building pressure from exceeding the design pressure.t31 The 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 performance.

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 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, valves, 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 secondary concrete shleid.

Personnel can enter the Reactor Building during 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.

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

REFERENCES (1)

USAR, section 9.

Amendment No. 76,87,94 4-31

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards-4.6 EMERGENCY POWER SYSTEM PERIODIC TESTING Specification i

4.6.1 Each of the required independent circuits between the offsite transmission network and the onsite Class 1 distribution system shall be:

A.

Determined OPERABLE at least weekly by verifying correct breaker alignments and indicated power availability, and B.

Demonstrated OPERABLE at least once per REFUELING interval by transferring nuclear service buses as listed in 3.7.1.C from the normal startup transformer supply circuit to the alternate startup transformer supply circuit.

Aeolicability HEATUP through P0HER OPERATIONS Amendment No. 38,H,88,81,V4 4-34

~_

l

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards-4.6 Emergency Power System Periodic Testing (Continued) i Soecifications 4.6.2 Nuclear service buses required by 3.7.1.C and 3.7.1.0 shall be determined to be OPERABLE at least weekly by verifying correct breaker alignment and indicated power availability.

Acolicability HEATUP through POWER OPERATIONS k

1 i

Amendment No. 38,46,63,g!,94 4-34a

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.6 Emergency Power System Periodic Testing (Continued) 4.6.3 Diesel generator operability Aeolicability At all times Saecifications Each diesel generator train shall be demonstrated OPERABLE by verifying that both diesel generators in the train are OPERABLE (GEA and 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, 2.

Verifying the fuel lavel 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 82.

The generator voltage and fr4quency shall be 4160 (1420) volts and 60 (11.2) Hz after.the start signal.

(Note 1) 5.*

Verifying the generator is synchronized, and within the next 90 seconds loaded between 2550 and 2750 kw for A and B and 3000 and 3300 kw for A2 and 82 and operates with this load for at least 60 minutes.

(Note 1).

Note 1 All planned engine starts may be preceded by an engine prelube i

period. With the exception of once per 184 days, all planned eN ne starts may be preceded by warmup procedures recommended by the 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 testing performed once every 184 days shall include fast starting i

(less than 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.

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

AmendmentNo./f,94 4-34b

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 6.

Verifying the diesel generator is aligned to provide emergency power to the nuclear service buses at the conclusion of the test.

7.

At the number of failures for the inoperable diesel generator indicated in Table 4.6-2 perform the Additional Reliability Actions prescribed in Table 4.6-2.

B.

Fuel Oil Storage 1.

By removing accumulated water:

a)

From the day tank at least monthly and after each occasion when the diesel is operated for greater than I hour, and b)

From the storage tank at least monthly.

2.

By sampling new fuel oil in accordance with ASTM 04057-81 (1981) prior to addition to the storage tanks and:

a) By verifying in accordance with the tests specified in ASTM D975-81 prior to addition to the storage tanks that the sample has:

1) An absolute specific gravity at 60/60*F of greater than or equal to 0.83 but less than or equal to 0.90 or an API gravity at 60'F of greater than or equal to 26 degrees but less than or equal to 38 degrees in accordance with ASTM D1298-77.

ii) A kinematic viscosity at 40*C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes, 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 ASTM D-88-81.

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 by volume.

Amendment No. 94 4_34e

RANCHO SECO UNIT 1

=

TECHNICAL SPECIFICATIONS Surveillance Standards-b)

By verifying within 31 days of obtaining the sample that the other properties specified in Table 1 of ASTM 0975-81 are met when tested in accordance with ASTH 0975-81, e;: cept that the analysis for sulfur may be performed in accordance with ASTM D1552-79 or ASTM D2622-82.

(Note 2) 3.

At least MONTHLY by obtaining a sample of fuel oil from the storage tanks in accordance with ASTM 04057-81 (1981), and verifying that total particulate contamination is less than 10 mg/ liter when checked in accordance with ASTM 02276-73 (1978), Method A.

Note 2 If one or more properties are out of specification, within 62 days of obtaining the bad fuel oil, verify that an additional sample of fuel oil from the fuel oil storage tank is within specification, qr empty and refill the tank with a new shipment of fuel oil within 77 days of the original out-of-specification sample, 4

Amendment No. 94 4-34d 1

i RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards.

C.

At each refueling interval, by:

1.

Diesel Generator Inspections a)

Subjecting the diesel generators A and B to an inspection in accordance with procedures prepared in conjunction with the maintenance recommendations provided by its manufacturer for this class of standby service.

b) Subjecting the diesel generators A2 and B2 to an inspection in accordance with procedures prepared in conjunction with the maintenance and surveillance program recommended by the TDI Owners Group in "Design Revision and Quality Revalidation Report for Rancho Seco," Appendix II.

2.

Verifying the generator capability to reject a load equivalent to or greater than the HPI pump for A and B and the AFH pump for A2 and 82 while maintaining engine speed less than or equal to 75% of the difference between nominal speed and the overspeed trip setpoint, or 15% above nominal whichever is less.

3.

Verifying the generator capability to reject a load of between 2550 and 2750 kw for A and B and between 3000 and 3300 for A2 and B2 without tripping.

Amendment No. 94 4-34e I

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards I

4.

Simulating a loss of off-site power in conjunction with a safety features actuation signal, and 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 buse2 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 (1 20) volts and 60 (

4 1.2) Hz during this test.

c) Verifying for the A and B diesel generators that all automatic diesel generator trips, except engine overspeed, ground fault and generator differential, 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 accordance with design requirements and that subsequent loading of the emergency power sources is through the automatic load sequencing circuitry.

The diesel generai:or will be operated for at least 5 minutes in 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).

1 Amendeent No. 94 4-34f

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards.

6.

Verifying the diesel generator operates for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (Note 1).

During the first 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of this test, the diesel generator shall be loaded between 2650 and 2850 kw for A and B and 3000 and 3300 kw for A2 and 82 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 and B and 3000 and 3300kw for A2 and B2. Within five minutes after completing this 24-hour test, perform surveillance requirement 4.6.3.C.4.b).

7.

Verifying that the auto-connected loads to each diesel generator do not exceed the 2000-hour rating of 2850 kw for A and B and 3300 kw for A2 and B2.

D.

At least once per 10 years or after any modifications which could affect interdependence, by starting all four diesel generators simultaneously (Note 3) and verifying that they accelerate to a nominal 900 rpm for A and B and a nominal 450 rpm for A2 and 82 within 10 seconds after the start signal.

The generator voltage and frequency shall be 4160 (1 20) volts and 60 (11.2) Hz within 10.0 seconds after the 4

start signal.

Note 1 All planned engine starts may be preceded by an engine prelube period. 'Hith the exception of once per 184 days, all planned engine starts may be preceded by warmup procedures recommended by the 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 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 diesel generator shall start within 10 seconds.

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 Amendment No. 94 4-34g

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards-Soecification 4.6.4 Batteries in the 125 volt DC systems shall be tested as follows:

A.

The volt:ge and specific gravity of each pilot cell shall be measured and recorded weekly.

B.

The specific gravity, level and voltage of each cell shall be measured and recorded every month.

C.

Each time data are recorded, new data shall be compared with old to detect signs of deterioration.

O.

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

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

Aeolicability At all times l

Amendment No. 46,94 4-34h

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards ELECTRIC POWER SYSTEMS Table 4.6-1 DIESEL GENERATOR TEST SCHEDULE f

Number of Failure in Last-20 Valid Tests

Test Freauency 1

At 1 east MONTHLY 2

At least HEEKLY**

i l

l l

l

Criteria for determining number of failures and number of valid tests shall be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, j

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 i

schedule, only valid tests conducted after the license amendment issuance l

dats shall be included in the computation of the "last 20 valid tests."

I

- 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.

Amendment No. 94 4-341 l

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.6-2 ADDITIONAL RELIABILITY ACTIONS No. of failures

'No. of failures in last 20 in last 100 valid test

valid tests Action 3

6 Hithin 14 days prepare and maintain a report for NRC audit describing the diesel generator reliability improvement program implemented at the site.

Minimum requirements for the report are indicated in Note 1 to this table.

5 11 Perform a requalification test program for the affected diesel generator.

Requalification test program requirements are indicated in Note 2 to this table.

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

Amendment No. 94 4-34j

1 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards s

NOTE 1 TO TABLE 4.6-2 REPORTING REOUIREMENT As a minimum the Reliability Improvement Program report for NRC audit shall include:

a) a st.smary of all tests (valid and invalid) that occurred within the time period over which the last 20/100 valid tests were performed.

b) analysis of failures and determination of root causes of failures c) 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) identificationofallactionstakenortobetakento1)correctthe root causes of failures defined in b) above and 2) achieve a general improvement of diesel generator reliability e) the schedule for implementation of each action from d) above f) an assessment of the existing reliability of electric power to engineered-safety-feature equipment Or.cc a licensee has prepared and maintain an initial report detailing the diesel generator re!iability improvement program at his site, as defined above, the licensee need prepare only a supplemental report within 14 days after each failure during a valid demand for so long as the affected diesel generator unit continues to violate the criteria (3/20 or 6/100) for the reliability improvemont program remedial action.

The supplemental report need only undate thu ?ailure/ demand history for the affected diesel gritrator unit since the last report for that diesel generator.

The 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 eperational changes to be incorporated into the site diesel generator improv6 ment program and the schedule for implementation of those changes.

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

l l

Amen ant No. 94 4-34k

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards l

NOTE 2 TO TABLE 4.6-2 DIESEL GENERATOR REOUALIFICATION PROC,BM j

(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 failure within 75 days of diesel generator being restored to operable j

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 an additional failure within 30 days of diesel generator being l

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.

(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 requalified.

(5)

During requalification testing the diesel generator should not be tested more frequently than at 24-hour intervals each.

1 After a diesel genrator has been successfully requalified, subsequent repeated requalification tests will not be required for thr.t diesel generator under the following conditions:

(a)

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

l (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 generator, the number of failures is still in excess of the remedial 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).

j i

Requalifiction testing will not be required provided thht af ter each valid e

tests the number of failures in the last 20 and/or 100 valid tests has not l

increased. Once the diesel generator is no longer in violation of the remedial action criteria above the provisions of those criteria alene will prevail.

Amendment No. 94 4-341

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards.

HA111 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 trains are operable or the core is flooded to 37 feet to ensure the required decay heat removal capability is available.

The tests specified are designed to demorstrate 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 l

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 i

supply, starting circuits and controls are continuously monitored and any l

faults are alarmed and indicated.

An abnormal cnndition in these systems j

would be signaled without having to place the diesel generators on test.

The limiting of the maximum load on the TDI diesel generators A2 and 82 to less than the qualified load of 3300 kw provides assurance that the crankshafts will stay within the proven limits for high,g le fatigue cracks.

Diesel generators A2 and B2 will be loaded during survelisance testing i

between 3000 and 3300 KH which provides assurance that the qual'fied load of 3300 KH will not be exceeded.

At least once per refueling outage a diesel generator test will be performed simulating a loss of off-site power in conjunction with a simulated SFAS and i

loading of actual loads to the maximum extent possible without damaging

)

l plant systems (i.e., use of recirculation flow or manual valving out a system to protect plant romponents).

Precipitous failure of the plant battery is extremely unlikely. The surveillance specified is that which has been demonstrated over the years to 1

provide an indication of a cell becoming unserviceable long before it fails.

j REFERENCE (1)

IEEE 308 1

Amendment No. 31,68,74,87,94 4-35

~

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Soecification (Continued) 4.10.1 C.

2.

(b) Verify that the HEPA filter bank removes 199.9 percent of the 00P when tested in-place in accordance with ANSI N510 while operating the filter train at a flow rate of 3200 cfm : 10 percent.

Started on a manual signal and operated for 15 minutes in each D.

31-day period.

BAuti The purpose of the Control Room /TSC Emerge'ncy Filtering System is to limit the particulate and gaseous fission products and toxic products to which +he Control Room area and Technical Support Center would be subjected during....

accidental radioactive or chemical release in or near the Auxiliary Building.

The system is designed with two redundant filter trains each of 4

which consists of a moisture separator, a heater, a high efficiency particulate filter, two banks of charcoal filters, a second high efficiency particulate filter and a booster fan to pressurize the Control Room and Technical Support Center with outside air.

j Because this system is not normally operated, a periodic test is required to l

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 The flow of 1600 cfm makeup air vibration when the fan motors are running.

was selected to limit the maximum radiation dose to occupants of the Control 1

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

radioicdide is necessary to receive credit for a OF of 10.

Refueling interval testing will verify the methyl iodide removal efficiency of the charcoal and the amount of leakage past the charcoal and HEPA filters are at least equal to the design values.

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

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.

Anendment No. 39,70,94 4-41b

o RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards.

4.31 NUCLEAR SERVICE ELECTRICAL BUILDING EMERGEWCY HEATING VENTILATION AND AIR CONDITIONING Applicability Applies to the Nuclear Service Electrical Building (kSEB} Heating Ventilation and Air Conditioning (HVAC) System components.

Objective To verify that this system and its components will be able to perforu their design functions.

Specification 4.31.1 The NSEB Emergency HVAC shall be:

A.

Demonstrated operable at least once per 31 days by initiating flow through the essential air handling unit.

1.

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

2.

Verify that the condensing unit is operational.

Bases The purpose of the Emergency Nuclear Service Electrical Building HVAC is to limit high temperatures which the building would be subjected to upon loss of norual cooling.

The high temperatures will affect the environmental qualification of safety related electronic equipment housed within the NSE8 which is used to support thJ Control Room /TSC upon acciderit conditions.

The system is designed with an air handling unit and a condensing unit which are activated upon high tenperature signals.

Since this system is not nonnally 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 minimum air flow of 24,500 cfm was selected to limit the temperatures in the building to 80*F maxiuum (with the exception of the cable shaf ts).

The system is automaticallz started when the temperature in the WSEB Switchgea' Room exceeds 95 F.

l r

Amendment No. 68,87.90.94 4 91

^

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.32 TDI DIESEL GENERATOR CONTROL ROOH ESSENTIAL VENTILATION SYSTEM Soecification 4.32.1 The Diesel Generator Control Room Essential Ventilation System shall be demonstrated operable at least once per 31 days by initiat'ng flow through the essential air handling unit by verifying that the air handling unit maintains a flow rate greater than the low flow alarm setpoint.

Aeolicability At all times Raiti The purpose of the TOI Diesel Generator Control Room Essential Ventilation 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 environmentcl 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 to ensure that the temperatures in the diesel generator control room will 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.

i t

l Amendment No. 94 4-92

--

ML20149L260

Text

Attachment:

Navigation menu

Search