Text

Proposed Tech Specs Re Safety Impact of Bringing Tdi Diesel Generators on Line
	ML20206H162
Person / Time
Site:	Rancho Seco
Issue date:	04/01/1987
From:	; SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	;
Shared Package
ML20206H133	List: ML20206H128; ML20206H162;
References
	TAC-63030, NUDOCS 8704150277
	Download: ML20206H162 (41)
	v • d • e

RANCHO SECO UNIT 1 ,

TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued)

Section Page 3.14.5 Fire Hose Stations 3-57 3.14.6 Fire Barrier Penetration Fire Seals 3-58 3.15 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION 3-60 3.16 RADI0 ACTIVE 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 Iodine-131, Tritium and Radionuclides in Particulate Form - 3-75 3.19 GASEOUS RADWASTE TREATMENT ~3-78

, 3.20 GAS STORAGE TANKS 3-79 3.21 SOLID RADI0 ACTIVE WASTES 3-80 1

3.22 RADIOLOGICAL ENVIRONMENTAL MONITORING 3-81

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3.23 LAND USE CENSUS 3-87 3.24 EXPLOSIVE GAS MIXTURE 3-89' 3.25 FUEL CYCLE DOSE 3-90 3.26 INTERLABORATORY COMPARISON PROGRAM 3-92 147> 3.27 NUCLEAR SERVICE ELECTRICAL BUILDING EMERGENCY' HEATING 3-93 AND AIR CONDITIONING 3.28 TDI DIESEL GENERATOR CONTROL ROOM ESSENTIAL 3-94 4 VENTILATION SYSTEM

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l Proposed Amendment No. 147 ,

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B704150277 870401 2 .1 DR ADOCK 0500

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RANCHO SECO UNIT 1 TECHNICAL' SPECIFICATIONS LIST OF TABLES ,

Table .Page l 2.3-1 REACTOR PROTECTION SYSTEM TRIP SETTING LIMITS 2-9 3.5.1-1 INSTRUMENTS OPERATING CONDITIONS 3-27 3.5.5-1 ACCIDENT MONITORING INSTRUMENTATION OPERABILITY REQUIREMENTS 3-38b 3.6-1 SAFETY FEATURES CONTAINMENT ISOLATION VALVES 3-40 3-41a 3.7-1 VOLTAGE PROTECTION SYSTEM RELAY TRIP VALUES 3.7-2 VOLTAGE PROTECTION SYSTEM LIMITING CONDITIONS 3-41b-3.12-1 SAFETY RELATED HYDRAULIC SNUBBERS 3-51a-e

~3.14-1 FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS 3-55

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3.14-2 INSIDE BUILDING FIRE HOSE STATIONS 3-57a 3.15-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3-61 3.16-1 RADI0 ACTIVE GASES EFFLUENT MONITORING INSTRUMENTATION 3-64 3.22-1 RADIO!0GICALENVIRONMENTALMONITORINGPROGRAM 3-83 3.22-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS- 3-86 IN ENVIRONMENTAL SAMPLES 4.1-1 INSTRUMENT SURVEILLANCE REQUIREMENTS 4-3' 4.1-2 MINIMUM EQUIPMENT TEST FREQUENCY 4-8 4.1-3 MINIMUM SAMPLING FREQUENCY 4-9 4.2-1 CAPSULE ASSEMBLY WITHDRAWAL SCHEDULE AT DAVIS-BESSE 1 4-12b 147> 4.6-1 DIESEL GENERATOR TEST SCHEDULE 4-35d

< 4.6-2 ADDITIONAL RELIABILITY ACTIONS 4-35e 4.10-1 ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-42 l 4.10-2 OPERATIONAL ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-22a 4.14-1 DESIGNATED SAFETY RELATED HYDRAULIC SNUBBERS FUNCTIONALLY 4-47d,e

TESTED ONLY AS REQUIRED BY THE SNUBBER SEAL REPLACEMENT PROGRAM 4.17-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED- 4-56 DURING INSERVICE INSPECTION 4.17-2A STEAM GENERATOR TUBE INSPECTION' '4-57 4.17-2B STEAM GENERATOR TUBE INSPECTION-(SPECIAL LIMITED AREA) 4-57a

! 4.17-3 OTSG AUXILIARY FEEDWATER HEATER SURVEILLANCE 4-57b,c

! 4.19-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION. 4-64 SURVEILLANCE REQUIREMENTS

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4.20-1 -RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION _ 4-66

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SURVEILLANCE REQUIREMENTS-i Proposed Amendment No.147 1 ix ,

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

1. - Reactor Coolant Loop (A) and its associated steam generator and at least ~one associated reactor coolant pump,

2. R'e actor Coolant Loop tB) and -its associated steam generator and

. . at least one associated reactor coolant pump, .

3. Decay Heat Removal Loop (A) i I 4. Decay Heat Removal Loop'(B)

< With less than the above required coolant loops OPERABLE, .

immediately initiate corrective action ~ to ' return the required . ~

coolant' loops to OPERABLE status as soon as possible; be in COLD

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SHUTDOWN within 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .-

3.1.1.6 Reactor Coolant System High Point Vents i

A. The vent path on Loop A and vent path on Loop B[shall-be ,

operable and: closed during power operation.

B. The vent path on the pressurizer shall be operable and closed during power operation.

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

. provided the inoperable ' vent path is maintained closed with-.

power removed from the valve actuator of. allathe valves in the i inoperable vent path; restore the inoperable vent path > to ~

OPERABLE status within 30_ days. If the status is noti restored to operable in 30 days,- be in HOT STAN08Y'within 12: hours and.

in COLD SHUTDOWN within the following,30~ hours.'

D. With two or more of the above. reactor coolant system vent paths inoperable; maintain the inoperable . vent paths closed with power removed from the valve ' actuators of all' the valves in' the inoperable vent paths, and restore at least (two) of the-vent paths to OPERABLE status within 72: hours. If the status'is not restored to operable in 72. hours, be in HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD' SHUTDOWN within the following ~30 hours.

I 147>

3.1.1.7 The pressurizer shall be operable, except when' the reactor -is in - ~

cold shutdown, with 3 groups of heaters in two separate banks that' 4- are capable of being powered by the diesel generator trains.--With

i. the heaters in one bank inoperable,.'either restore the bank to-4 operable status within 15 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 shutdown 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 inoperable, either restore one bank I 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 shutdown '

3 within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .~ -

Proposed Amendment No.-147 -

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for.0peration Bases A reactor coolant pump or decay heat removal pump is required to be in

-operation before the boron' concentration is reduce'd by. dilution with makeup.

water. Either pump will provide mixing which will prevent sudden positive-J 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 suction piping is designed for 300 F and 300-psig; thus, the system can remove decay heat when the reactor coolant system is below this temperature. (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 2

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.

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valve lift set point shall be set at 2500 psig

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

4 The electromatic relief valve setpoint was established to prevent ope' ration of -

the Safety Valves during transients.

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

2 When TAV is below 280*F, a single reactor coolant loop or DHR-loop provides ,

sufficient heat removal capability for removing decay heat; but single failure

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considerations require at least two loops be 0PERABLE. 'Thus, if the reactor

_ coolant loops are not OPERABLE, this specification requires two DHR ' loops to -

be OPERABLE.

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

-RCS which may inhibit core cooling during natural circulation. In' compliance-

, with 10CFR50 Appendix R the power to all the-valve actuators in the vent path -

has been removed.

l 147> 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 4 maintain natural circulation at HOT SHUTDOWN.

i Proposed Amendment No.147 F

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b RANCHO SECO UNIT TECHNICAL SPECIFICATIONS Limiting Conditions for Operation

. REFERENCES (1) FSAR Tables 9.5-2, 4.2-1, 4.2-2, 4.2-4, 4.2-5, 4.2-6 (2)- '

FSAR' paragraph 9.5.2.2 and 10.2.2 t

(3) FSAR paragraph 4.2.5, (4) FSAR paragraph 4.3.8.4 and 4.2.4-

$ (5) FSAR paragraph,.4.3.6 and 14.1.2.2.3 1

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i Proposed Amendment No. 147 3-2b .

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RANCHO SECO UNIT 1

' TECHNICAL SPECIFICATIONS-Limiting Conditions for Operation 3.7 AUXILIARY 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 To define those conditions of electrical power availability necessary to provide for safe reactor operation and to provide for continuing availability of engineered safety features in an unrestricted manner.

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

147> A. At least two 220 KV lines are in service.

B. The switchyard voltage is 219 KV or above.

C. Both startup transformers, No. 1 and No.2, are in service.

D. Nuclear services 4160V buses 4A, 4A2, 4B, and 482 are operable.

E. Nuclear services 480V buses 3A, 3A2, 3B, 3B2, 2A1, 2B1, 2A3, 283, 2A4, and 284 are operable.

F. Two separate and independent diesel generator trains (train A is 4

both diesel generators A and A2, train B is both diesel generators B and B2) are operable each with:

1. Separate day tanks containing a minimum volume.of'65. percent of tank capacity (265 gallons) of fuel for each A and B and 50 percent of tank capacity (315 gallons) of fuel for A2 and B2.

2. A separate fuel storage system containing a minimum useable !

volume of 35,000 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.

G. Nuclear Service batteries BA, BB, BC, BD, BA2, 882, BC2, and 802, which supply vital 125 volt DC buses SOA, SOB, SOC, SOD, SOA2,

< SOB 2, SOC 2, and S002 are charged and in service. ,

H. Each vital 125 volt DC buses SOA, SOC, SOB, S00, SOA2, S082, SOC 2, and S002 shall have its normal battery charger aligned to

it.

I. Nuclear service inverters SIA2, S182, S102, and S102, and static

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switches H8TA3, H8TB3, .H8TC3, and H8TD3 are operable for 120 volt i

< AC vital bus power. l Proposed Amendment No. 147 l 3-41 l l

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RANCHO SECO UNIT 17 TECHNICAL SPECIFICATIONS-Limiting Conditions for Operation 3.7.2 The reactor shall not remain ~ critical unless all of the following requirements are satisfied:-

147> A. At least two 220 KV lines.shall be in service ^ except should all but one 220 KV line be removed from service .the operability of-the remaining 220 KV _line:shall be demonstrated by performing _

surveillance requirement 4.6.1.A within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . and at least once' per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .thereaf ter and surveillance requirement 4.6.3. A.4 is performed within 24. hours. If at least two 220 KV lines are not-in service within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ,;the reactor shall. be in hot shutdown .

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

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B.. Both diesel generator trains shall be operable except should one diesel generator train become inoperable ;the operability of at least two 220 KV lines shall be demonstrated by perfoming surveillance requi.rement.4.6.1.A within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once -

per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter and surveillance requirement 4.6.3.A.4 is performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and at least once per 7 days thereafter. If the diesel generator. train is not. restored to l

i operable status within 15 days,' the reactor shall be in hot

shutdown within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in cold shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . At the number of failures for the inoperable diesel generator indicated in Table 4.6-2 perfom the- Additional Reliability Actions prescribed in Table 4.6-2.

C. At least- two 220 KV lines and both diesel _ generator trains shall be operable except should all but one 220 KV line and one diesel I generator train both become inoperable the operability of.the ~

remaining 220 KV line shall be demonstrated by perfoming _

surveillance requirement 4.6.1.A within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at-least once per-8 hours thereafter, _and the diesel generator train shall be demonstrated to be operable by performing. surveillance requirement 4.6.3.A.4 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . If either the 220 KV line 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 shutdown within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in cold shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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

j D. At least two 220 KV lines shall be in service except should all 220 KV lines become-inoperable the operability of the.two diesel generator trains shall be demonstrated by perfoming surveillance requirement 4.6.3. A.4 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . This surveillance r requirement does not have to be perfomed for the diesel generator train (s) already in service. If at least one 220 KV line 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.

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- Proposed Amendment.No. 147 ,

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T RANCHO SECO UNIT'1 TECHNICAL SPECIFICATIONS '

Limiting Conditions for Operation -

147> 3.7.2 (Continued)

E. Both diesel generator trains shallL be operable except should both trains be inoperable the operability of.at-least two 220.KV lines shall be. demonstrated by perfoming surveillance requirement 4.6.1.A within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and.at:1 east once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

If one diesel generator train is not restored to operable status-within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the reactor shall- be in hot shutdown within, the '

next-6 hours and in cold shutdown.within~the following 30.

hours. With one: diesel ' generator train restored to operable -

-status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , follow 3.7.2.B.

F. Both startup transformers shall?be in service except should one startup transfomer become inoperable the. operability. of 'at least' two 220KV lines shall be demonstrated by performing surveillance requirement '4.6.1.A within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter and the diesel generator trains shall be demonstrated to be operable by perfoming surveillance' requirement 4.6.3.A.4 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . If startup transfomer no. l'is not' restored to operable status within 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 and in cold shutdown within the following~205 hours. If startup transformer no. 2 is not restored to operable status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , the reactor shall be~

' in hot shutdown within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in cold shutdown i within the following 205 hours0.00237 days 0.0569 hours 3.38955e-4 weeks 7.80025e-5 months .

G. If both startup transformers become inoperable, within one. hour l take action to place the reactor in hot shutdown within the:next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in cold shutdown within the following 205 hours0.00237 days 0.0569 hours 3.38955e-4 weeks 7.80025e-5 months .

H. Nuclear service buses as listed in 3.7.1.D and 3.7.1.E shall be operable except should one nuclear service bus become inoperable i

for greater than 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 and in cold shutdown' within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . If more than one nuclear service bus as listed in i

3.7.1.0 and 3.7.1.E should become inoperable, within one hour take action to place the reactor-in hot shutdown within the next

.l 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 ..

I Nuclear service batteries as listed in' 3.7.1.G shall be charged

j. I.

and in service except should one nuclear service battery become inoperable for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the reactor shall be in hot ~

l' shutdown within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in cold shutdown within the I following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . If-more.than one nuclear service battery as -

listed in 3.7.1.G should become inoperable within one hour take action to place the reactor in hot shutdown within the-next 6 )

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

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I J. Nuclear service battery chargers as listed in 3.7.1.H shall be -

-l operable except should one nuclear service battery have no

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battery charger for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the reactor q~

Prop'osed Amendment No.147 -

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, " RANCHO SECO UNIT 1-T

-TECHNICAL SPECIFICATIONS s

Limiting 1 Conditions' for_.0peration - 4

'-147> 3.7.2 J. (Continued)

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shall be'in hot shutdown within tihe 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 . - If a standby charger..is-

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aligned in place of its nonnal charger far _ greater. than.48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ,-

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the reactor shall' be in hot shutdown within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in cold shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . If more than one-nuclear service battery has.no . required battery charger as listed in 3.7.1.H, within one hour take action to place the reactor in hot shutdown within thej 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 .

i K. Nuclear service invertersiand static. switches as listed in 3.7.1.I shall be operable except should one inverter or static switch become inoperable for greater than 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 -and in cold shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ._ A static switch shall not be , aligned to .the backup source in place of- a operable nuclear service inverter'except.for . switching period. If more

. than one nuclear service inverter 'or static switch as listed in 3.7.1.I should become inoperable, within one hour take action to place the reactor in hot shutdown within the 'next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in' cold shutdown within the following 30-hours.

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1 L. Should the switchyard voltage ~ drop below.219KV, 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 KY, 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..

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 , the reactor shall be in hot sh'utdown 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 .-

! 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 operation are not penaitted unless the minimum requirements and action staterents of Table 3.7-2 are' met.

B. In the event the number of protective channels falls below that listed in Table 3.7-2, the plant will be brought to a hot .

shutdown within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . .

Propos.ed Amendment No. 147 .

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Bases The auxiliary electrical power systems are arranged so that no single failure.

can inactivate enough safety features equip 9ent 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 147> normal power supply to plant auxiliary loads can be provided through the two unit auxiliary transformers connected to the generator buses. Dnergency power for the nuclear service loads is obtained from two on-site diesel generator.

trains (train A is both diesel generators A and A2, train B is both diesel

< generators B and B2). Since the startup transformers are sized to carry full plant auxiliar'y 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-KV 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-KV line.

If there is a loss of all 220-KV remote connections, power to the safety features will be supplied by the diesel generator trains. The 35,000 gallons 147> of fuel stored in each storage tank permit operation of the diesel _ generators A and B for seven days. The 42,000 gallons of fuel stored in 'each storage tank

< permit operation of the diesel generators A2 and B2 for seven days. It is.

considered unlikely not to be able to secure fuel oil from an outside source during this time under the worst of we'ather conditions.

147> The set of eight 125 volt DC control buses (SOA, SOB, SOC, SOD, SOA2, 4 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.

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.[ Proposed Amendment No. 147 0 -

3-42a -

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

147p A. Definite Time Delay Trip Set Point 3771

38 5.0

0.5 (Drop Out)

B. Inverse 3771

38 N/A Time Delay Trip Set Point -

(Drop Out)-

70 Percent of Set Point 2640

27 3.0

0.5 NOTE 1 - For bus tripping, an additional 0.5 second time delay must be added.

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Proposed Amendment No. 147 3-42b m

147>

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

Total No. of Minimum Functional Number of Relays / Channel s Channels Action Unit Channels Channel To Trip Operable 2/ Bus .2 A 147> Undervoltage 3/ Bus 2 4

ACTION STATEMENTS Action A - With 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.

- Proposed Amendment No. 147 .

3-42c j .

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 147> Each redundant pair ("A" and "C", "B" and "D") of the eight 125 volt.DC control buses (SOA and SOC, SOB and SOD, SOA2 and SOC 2, and SOB 2 and S002) has

' a standby battery charger in addition to its nomal 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 .

nomal 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 _ t,han the nomal _ 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 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.

t 147> Four nuclear service inverters (SIA2, S182, SIC 2, and SID2) and static switches (H8TA3, H8TB3, H8TC3, and H8TD3) are required to be operable to power i

the 120 volt AC vital buses. -The nuclear service inverters are powered from diesel generators A2 and B2 and the static switches are powered from diesel generators A and B. This design ensures that upon loss of an i_nverter or' a 1

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 pemitted to be inoperable for up to 24. hours. ^ The static switch is only used as a backup for the inverter.- It is not pemitted 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 pr;tection for the 4160 volt nuclear service buses is 3771

38 volts. This corresponds to a nominal

- < switchyard voltage range of 219 KV.

REFERENCE FSAR, Section 8

$ ' Proposed Amendment No.147 43.

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation -

Table 3.14 (Continued)

FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS Minimum Operable Zone Instrument Location Heat Flame ;

Smoke, 75-1 B Switchgear Room (NSEB) 0 0 1 75-2 BB2 Battery Room (NSEB) 0 0 -- 1 75-3 BD2 Battery Room (NSEB) 0 0 1 76-1 A Switchgear Room (NSEB) 0 0 1 76-2 BA2 Battery Rcom (NSEB) 0 0- 1 76-3 BC2 Battery-Room (NSEB) 0 0 1 77-1 North B Electrical Equipment Room (NSEB) 0 0 1 77-2 South B Electrical Equipment Room (NSEB) 0 0 1 78-1 North A Electrical Equipment Room (NSEB) 0 0 1 78-2 South A Electrical Equipment Room (NSEB) 0 0 1 81 B Cable Tunnel / Shaft (NSEB) 0 0 3 0 3 82 A Cable Tunnel / Shaft (NSEB) ~0 84-2 B Mechanical Equipment Room (NSEB) .0' 0 1 84-3 A Mechanical Equipment Room (NSEB) 0 0 1 147> 105 Diesel Generator Bullding- ~0 3- 6 4 106 Diesel Generator Building 0 3 6 i

Pioposed Amendment No.147~

3-55a

w RANCHO SECO UNIT 1 TECHNICAL' SPECIFICATIONS Liriiting' Conditions for Operation Spray and Sprinkler Systems

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3.14.3 Specification 3.14.3.1 The : spray and/or sprinkler systems located in the following areas - '

shall be OPERABLE:

a. Control Room (Zone 3)

b. Controlled Area, Mezzanine Level (Zone 20)

c. Main -Lube Oil Area, Grade Levelf(Zone 32).

d. Grade Level (Zone 34)

e. North Diesel Room (Zone 40)

f. South Diesel Room (Zone 41) 9 West Controlled Area,- Grade _ Level (Zone 42)

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

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

j. NSEB B Cable Tunnel / Shaft (Zone-81) 1

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

1. NSEB' Mechanical Equipment Rooms A and B (Zone 84) 147> m. Diesel Generator Building (Zone 105)

< n. Diesel Generator' Building (Zone 106) 3.14.3.2 With one or more.of the above, items a through f, required spray.

and/or sprinkler systems are inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant ~ systems or components required to safely shut down and cool down the plant could_be damaged; for:other areas, establish an hourly. fire watch patrol. Restore the. system to OPERABLE status within 14 days or, in lieu of any ottier mport required by Specification 6.9, prepare and submit 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 the inoperability and the plans and schedule for restoring the system to OPERABLE status.

3.14.4 g System l

Specification 3.14.4.1 The CO2 systems located in the following areas sha'll be OPERABLE with a minimum capacity of 66 and a minimum pressure of 275 psig in j the storage tank.

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-a. Zone 12 West DC Control Room Mezzanine Level

! b. Zone 13 West 480 VAC Room Mezzanine Level

c. Zone 14 West Cable Tray Area

d. Zone 15 East Cable Tray Area .

e. Zone 16 East 480 VAC Room Mezzanine Level -

f. Zone 17 East DC Control Room Nezzanine Level g.- Zone 36 West Battery Room Grade Level .

Proposed Amendment No. 147 3-56

l 147>

RANCHO SECO UNIT 1 TECH;JICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.14-2 (Continued)

INSIDE BUILDING' FIRE HOSE STATIONS ID No. Location III Diesel Generator Building Hose Stations FPHS-D-001 Train A Engine Room Elevation O' FPHS-D-002 Train A Control Room Elevation .0' 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-D-006 Train B Mezzanine Elevation 18'6" l

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< Prop _os'ed- Amendment No.147 .

3-57b .

147>

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.27 Nuclear Service Electrical Building Emergency Heating Ventilation-and.

Air Conditioning System Applicability This specification applies to the operability of the Nuclear Service Electrical Building Emergency Heating Ventilation and Air Conditioning

. System.

Objective To assure that this system will be able to perfonn its designed -

function.

Specification 3.27.1 Both Nuclear Service Electrical Building Emergency Heating Ventilation -

and Air Conditioning trains shall be operable at all times except as noted in 3.27.2.

3.27.2 With one Nuclear Service Electrical Building Emergency Heating Ventilation and Air Conditioning train inoperable, 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 . With both Nuclear Service Electrical Building Emergency Heating Ventilation and Air Conditioning trains inoperable, restore the trains to operable status within 3.5 days or be in at least hot standby within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in cold shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Bases The Nuclear Service Electrical Building (NSEB) Emergency Heating Ventilation and Air Conditioning System is required to provide cooling to protect required

< electrical components in the NSEB.

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1 Proposed Amendme'nt No. 147 1

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RANCHO SEC0' UNIT TECHNICAL SPECIFICATIONS-Limiting Conditions for Operation 147> 3.28 TDI Diesel Generator Control Room Essential Ventilation' System Applicability This specification applies to the operability of the TDI Diesel Generator Control Room Essential Ventilation System.

Objective To assure that this system will be able to perform its design' function.

~

Specification 3.28.1 Both TDI Diesel Generator Control Room Essential Ventilation trains shall be operable at all times except as noted in 3.28.2 and 3.28.3.

3.28.2 With one TDI Diesel Generator Control Room Essential-Ventilation train inoperable,_ demonstrate the operability of the remaining train.

Restore the inoperable train to operable status within 15 days or be in at least hot shutdown within six hours and in cold shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

3.28.3 With both TDI Diesel Generator Control Room Essential Ventilation trains inoperable, restore at least one inoperable 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 shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . With one inoperable train restored to operable status, follow 3.28.2.

Bases The TDI Diesel Generator Control Room Essential Ve'ntilation System is required to maintain the temperature in the control room below 122*F to protectJrequired

< electrical components.

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3-93a l

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RANCHO SECO UNIT 1

- TECHNICAL SPECIFICATIONS

Surveillance Standards TABLE 4.1-1 (Continued)

INSTRUMENT SURVEILLANCE REQUIREMENTS Test Calibrate Remarks Channel Description Check (1) Compare voltmeter readings

57. Voltage Protection S(1)

R (2) Test using*undervoltage relay's

a. Undervoltage Relay M(2) 147> " TRIP TEST pusnbutton - NO Setpoint R quantitative measurements.

b. Undervoltage Relay M(2) 4 Time Delay

58. Containment Area'High S M(1) R (1) Test using installed source Range Monitor M N/A R

59. Wide Range Containment Water Level

60. ! Containment Hydrogen S M Q Analyzer M N/A R

61. Emergency Sump Level N/A R-

62. Containment Wide range M Pressure Monitor / Recorder M R ~'

63. .High Range Noble Gas S Effluent Monitors

- RB Exhaust Stack

- Aux. Building Stack

- Radwaste Vent S M(1) R (1) Test using installed source

64. Main Steam Line Radiation Monitors N/A. R

65. Subcooling Margin Monitors M

66. Incore Thermocouples M N/A R

67. Low Temperature Over N/A _1)

( R (1) Prior to cooldown.

. Pressure Protection M = Monthly P = Prior to each startup if not done previous week S Each shift D'. Daily Q = Quarterly R = Once during the refueling interval-

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W = Weekly SY = Semiannual Proposed Amendment No.147 4-7c

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Su'rveillance Standards

2. The test will be considered satisfactory if control board indication verifies .that.all components have responded to the actuation signal and the appropriate .

breakers'shall have complete'd their travel.

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

4.5.2.2 Component Tests A. Testing At least quarterly, Insarvice 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 i

Following Inservice testing of pumps and valves as required

. by paragraph 4.5.2.2.A required flow paths shall be demonstrated operable by verifying that each valve (manual, power-actuated or automatic) in the flow path that. is not- .

locked in position is in its normal operating position.

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

147> C. The pressurizer shall be tested as follows:

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

2. The power supply for the nuclear service backed pressurizer heaters shall be demonstrated OPERABLE at

least once per refueling interval by using the Nuclear

< Service Bus to energize the heaters.

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- Proposed Amendment No.-147 .

4-30 -

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~ RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Bases The Reactor Building emergency cooling systems and Reactor Building spray system are designed to remove the heat in the containment atmosph prevent the building pressure from exceeding the design '. pressure.gg 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 shield. 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.

147> The operability of the nuclear service bus backed pres:urizer heaters is

< demonstrated by energizing the heaters once per refueling interval.

REFERENCES i (1) FSAR, section 9. l t

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Proposed Amendment No. 147- -

4-31 .

RANCHO SECO UNIT 1-TECHNICAL SPECIFICATIONS

. Surveillance ' Standards 4.6 EMERGENCY POWER SYSTEM' PERIODIC TESTING Applicability Applies to the periodic testing and surveillance of the emergency power system.

Objective To. verify that the emergency power sources and equipment are operable ~

and respond properly when required.

Specification i

! 147> 4.6.1 Offsite Power Sources 1

A. Each of- the 220 KV lines _ required by 3.7.1.A _ shall be:

i Determined OPERABLE at least weekly by verifying correct breaker alignments and indicated power availability, and B. Each Start-up Transformer required in 3.7.1.C shall be demonstrated OPERABLE at least once per refueling interval by transferring nuclear service. buses as listed in 3.7.1.D l; from the normal startup transformer supply circuit to the alternate startup transformer supply circuit.

4.6.2 Nuclear service buses required by 3.7.1.D and 3.7.1.E 'shall be l

determined to be OPERABLE at least weekly by verifying correct'

! breaker alignment and indicated power availability.

I 4.6.3 Each diesel generator' train shall be demonstrated OPERABLE by verifying that both diesel generators in the. train are OPERABLE (A and A2, B and B2). Each diesel generator shall be demonstrated -

OPERABLE:

} A. In accordance with the frequency specified in Table 4.6-1_ by:

I

1. Verifying the fuel level in the day tank,

2. Verifying the fuel level in the fuel storage tank, 3.* Verifying the fuel transfer pump starts and transfers fuel from the storage system to the day tank,

Surveillance shall not be performed when a diesel generator

< train is not operable in accordance with TS 3.7.2.

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l - Proposed Amendment No. 1.47 _

4-34 -

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RANCHO SECO UNIT'1 \

TECHNICAL SPECIFICATIONS Surveillance Standards 147> 4. Verifying the die'sel starts from a manual signal and accelerates to a nominal 900 rpm for A and 8 and a nominal 450 rpm-for A2 and B2. The generator voltage .

and frequency shall be 4160 (+420) volts and 60 (+1.2) ~

Hz after the start signal. ;(Note 1) 5.* -Verifying the generator is synchronized and operates with its load between 2550 and 2750 kw for A and B and 3000 and.3300 kw for A2 and B2 for at least 60 minutes,(Note 1).

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

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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and ,

, b) From the storage tank at least monthly.

2. By sampling new fuel oil in accordance with ASTM 0270-65 (1975) prior to addition to the storage tanks ar d:

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

i) An absolute specific gravity at 6d/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 01298-77.

..?

1 All planned engine starts may be preceded by an engine prelube l I Note 1 period. With the exception of once per 184 days, all planned )

l engine starts may be preceded by warmup procedures recommended by the manufacturer and may also include slow starting and gradual loading so that mechanical stress and wear on the diesel engine is minimized. The testing performed once every 184 days shall !

I include fast starting (less than or equdl to 101 seconds).

Surveillance shall not be performed when a. diesel generator train or startup transformer is not. operable /in accordance with TS3.7.2.

' 4 Preposed Amendment No.147 .

4-35 -

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RANCHO SECO UNIT 1 LTECHNICAL SPECIFICATIONS

. Surveillance' Standards 147>

ii) A kinematic viscosity at' 40*C of greater than or equal to.1.9_centistokes, but less than or equgl to 4.1.centistokes, or Saybolt, .(SUS at 100 F) greater.than or equal to 32.6, .but less.

l than or equal to 40.1, iii) A flash point equal to' or greater than 125*F, and:

iv) Water and sediment 'of less' than or equal to e 0.05 percent by volume.

3

> , b) By verifying.within 31 days of obtaining the sample that the other properties specified in Table liof

~

/i - ASTM D975-81 are met when tested in accordance with ".

2.

ASTM 0975-81 except that the analysis.for sulfur.

' may be performed in accordance with ASTM D1552 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 D2276-73'-

(1978), and verifying that total particulate contamination is lessL than'10 mg/ liter when checked in accordance with ASTM D2276-73 (1978), Method A.

C.. At each refueling interval, by:

4

1. Diesel ~ Generator Inspections a) Subjecting the' diesel generators A and 8 to an inspection.in accordance with procedures. prepared in conjunction with the maintenance recommendations provided by its manufacturer for. this class of' standby service.

l b) Subjecting the-diesel generators A2 and 82 to an inspection in accordance with procedures _ prepared in conjunction with the' maintenance and I surveillance program recommended by the,TDI Owners Group in " Design Revision and Quality Revalidation Report for Rancho Seco," Appendix II.

Note 2 If one or more property is ou,t of spec, verify within an i additional 31 days that a sample of fuel oil from the fuel oil.

I storage' tank is within specification or replace the fuel oil within an additional 15 days.

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Propy:ied Amendment No.147 4-35a l

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RANCHO-SECO. UNIT:1:

TECHNICAL SPECIFICATIONS

.. Surveillance Standards ~

147> -

2. Simulating a loss of off-site power in conjunction with a s,afety1 features actuation signal . . (Note 4, Note 6) and all Verifying de-energization of the nuclear service ,

buses and operation of the load shedding cin:uitry.

b) Verifhingthediesel.startsontheauto-start signal .(Note 3),-.energizesi the nuclear service buses, verifyihg proper operation of the automatic' sload sequencing circuitry, and operates for. greater-

' f than or equal to 5 minutes'in this condition. '

/ ', After energization,,the steady state voltage and: f

, #. y f.,- -

frequency of the emergency buses. shall be -

./ /

-maintained at 4160 (+420) ' volts and 60 '(+ ?1.2)' Hz

/ ).r

'during this test.

< 3. Simulating a loss of foff-titte power and' verifying that'.

on interruption of the emeirgency 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 generator will be operated for at least 5 minutes in this condition.-

(Note 1)-

147> 4. Verifying the diesel generator cperates for at-least 24' hours (Note 1). During - the first-2 hours 'of this test, the diesel generator shall' be' loaded between 2650 and-i 2850 kw for A and B and 3000 and 3300 kw for A2 Land B2 .

4 and for the remaining 22l hours of this test,' the diesel ' J T generator shall be loaded between.2550 and 2750kw for~A l and B and 3000 and 3300kw for:A2 'and 82.

l Note 1 All planned engine starts may be preceded by an engine prelube-period. With the exception of once per 184 days, all planned

~

engine starts may be preceded by warmup procedures recommended by-f the manufacturer and may also include slow starting and gradual' loading 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 qual to.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).

Note 4 Prior to the performance of this test the. diesel generators shall-be operated at between 2550 and 2750 kw for' A and B and 3000 and '

3300 kw for A2 and B2 for at least 1. hour and until engine operating temperatures have stabilized.-

l Note 6 When the test required by specification 4.6.3.E is performed, then v l the test required by specification 4.6.3.C.2 is not- required to be l performed. ,

4 Proposed Amendment No.147 4-35b

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x RANCH 0'SECO UNIT 1 l TECHNICAL SPECIFICATIONS:

Surveillance-StandardsL At least once per 10 years,-by starting alli four diesel

~

'147> D.

' generators; simultaneously '(Note 3) and _ verifying that they -

accelerate to a nominal 900 rpm for A and 8 and a nominal 450 -

rpm for A2 and 82.within 10 seconds'after th'e start signal..

The. generator voltage and frequency shall be'4160 (+420).

volts and,60 (+1.2) Hz within 10.0 seconds after the start signal.-

. E. At least once per _10, years simulating a loss of off-site:

. power in conjunction with a simulated SFAS;(Note 5),'and

1. Verifying de-energization of the ' nuclear service buses and-load shedding from the nuclear service buses.,

2. Verifying the diesel: starts on the auto-start ~ signal, energizes the nuclear service buses with' permanently connected loads, . loads through the load sequencer and

~

-t operates for greater than or equal to 5 minutes while.

its generator -is loaded with the emergency loads. " Afters energization, the steady state voltage and frequency of!

the emergency buses'shall-be maintained at 4160 (+420) volts and 60 (+ 1.2) Hz during this test.

3. Verifying for the A and B diesel < generators that all ,3 automatic diesel generator trips, except engine i.

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 1 oil pressure and generator-differential, ~are automatically bypassed with an -SFAS.

< 4.5.4 BayNries i.n the 125 volt DC systems shall be tested as follows::

A. lThe voltage _ 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.

147>

Note All planned engine starts for the purpose of this 'surveillar.ce

. testing may be preceded by an engine prelube period._ The testing shall' include fast starting (less than or equal' to 10 seconds).

3 Note 5 All planned engine st' arts for the purpose of this surveillance testing may be preceded by an engine'prelube period. The testin shall' include-fast starting (in less than-or equal to 10 seccnds -

} and fast loading through the- sequencer.

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Proposed Amendment 147 l 4-35c

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J RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS'

' Surveillance Standards-C. Leach time data are recorded,- new data shall be compared with I:

old to detect signs of deterioration.

4 D. 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.

Bases 147> The operability of the 220KV lines, the nuclear service 4160V buses,.and the

~

nuclear service 480V buses are demonstrated by verifying correct breaker alignments and indicated power availability. Surveillance.4.6.1.8 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 demonstrate that the diesel generators will provide power for operation of safety features equipment. They also assure that the emergency generator contral system and the control- systems for -

the safety features equipment will function automatically in the event-of a loss of all nonnal a-c station service power, and upon receipt of a safety

'eatures actuation signal . The testing frequency specified is' intended to '

identify before it can . result in a system failure. The; fuel _ oil supply, starting circuits and controls are continuously monitored and any faults are-alanned and indicated. An abnormal condition in these systems would be signaled without having to place the diesel generators on test.

147> The limiting of the maximum load on the TDI' diesel generators A2 and B2 to less than the qualified load of 3300 kw provides assurance that the !

crankshaf ts will stay within the proven limits for high-cycle fatigue cracks. l Diesel generators A2 and B2 will be. loaded during surveillance testing between l- 3000 and 3300 KW which provides ' assurance that the qualified load of 3300 KW l will not be exceeded.

l At least once per 10 years a diesel generator test'will be performed l

simulating a loss of off-site power in conjunction with a simulated SFAS and loading of actual loads to the maximum extent possible without damaging plant l

systen.s (i.e., use of recirculation flow or manual valving out a system to l < protect plant components).

l Precipitous failure of the plant battery is extremely unlikely. The j l' surveillance specified is that which has been demonstrated cier the years to

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

REFERENCE

-(1) IEEE 308 Proposed Amendment No. 147 4--35d .

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, RANCHO SECO' UNIT 1 TECHNICAL SPECIFICATIONS ~

Surveillance' Standards:

-147> ELECTRIC POWER SYSTEMS j;

Table 4.6-1 DIESEL GENERATOR' TEST SCHEDULE-Number of Failure in Last-20 Valid Tests

Test Frequency: ...

1 At least monthly.

2 At least weekly **

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, 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 schedulef only

, valid tests conducted'after the license amendment issuance date shall'be included in the computation of the "last 20 valid tests."

- This test frequency shall be maintained until seven consecutive failure free demands have been performed and the number of failures in the last 20_ valid

< demands has been reduced to one or less.

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- Proposed Amendment No.147 4-35e .

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147>

TABLE 4.6-2 ADDITIONAL RELIABILITY ACTIONS No. of : failures No. of failures i in last 20 in last 100- )

valid test * -valid tests

Action g 3' 6 Within 14 days prepare and mai,ntain-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.

J f

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

1 Proposed Amendment No.147 1

4-35f e

147r - -

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

a) _ a summary 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 detemination'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) identification of all actions 'taken or.to be taken to 1). correct the root causes of failures defined in b) above and 2) achieve aigeneral-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 ,

Once i. licensee has prepared and maintain an . initial report detailing the diesel generator reliability 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 improvement program remedial action. The supplemental' report need-only update the failure / demand history for the affected diesel generator unit since the last report for that diesel generator. The supplemental report

~

shall also present an analysis of the failure (s) with a root'cause detemination, if possible, and shall delineate any further procedural, hardware or operational changes- to be incorporated into the site diesel generator improvement program and the schedule for implementation of those '

changes.

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

d y

Proposed Amendment No. 147. .

4-35g -

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._ .. ~ _ _ __ _ _ _ _ ___ __ .__ _ _ _ _ _ _ _

NOTE 2 TO TABLE 4.6-2'-

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& . DIESEL GENERATOR -REQUALIFICATION' PROGRAM : 'I i

(1) Perfom seven consecutive _ successful demands without a failure within 30 days of diesel ge.nerator. being restored to operable status from the a last failure and fourteen consecutive successful demands without a L failure _within 75 days of diesel generator of being restored .to .

operable status from the'last: failure.

(2) If one ~ failure occurs _ during- the first seven tests 'in the requalification test program, perfom seven successful demands withoutT y 4

an. additional failure within 30. days of diesel generator of being restored to operable status after the first. failure of the requalification test program'and fourteen consecutive successful-demands without a failure within 75 days'of being restored. to operable 1- status after the first failure of- the requalification test program.

(3) If one failure occurs during the second seven tests l(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. -

1 (4) Following the second failure during the requalification test program a declare the diesel generator inoperable and follow the ap'plicable 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.

! Af ter a diesel genrator has been successfully requalified, subsequent repeated' requalification tests will not be required for that diesel generator under the following conditions:

(a) The number of failures in the last 20 valid demands is less- than 5.

l (b) The number of failures in the last 100 valid demands is less than 11'.

} (c) In the event that following successful requalification of a diesel j 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). .

l j Requalifiction testing will not be required provided that after each valid 1 demand the number of failures in the last 20 and/or 100 valid demands has not i increased. Once the diesel generator is no longer in violation of the-i remedial action criteria above the provisions of those criteria alone will-

prevail. ,

}

Proposed Amendment No. 147 i 4-35h I

_ . _ . . . . - . _ . . _ _ . _ _ . _ . . _ . _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ . ~ _..l

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1 X -

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards.

Specification (Continued) l 4.10.1- C. . 2. (b) Verify that the HEPA filter' bank removes >99.9 percent -

! of the DOP when tested in-place in accordance with ~ ANSI ;

[ . _N510 while operating the filter train at a flow rate of g

~3200 cfm

10 pement.- ..

I D. Started on a manual signal and operated for,15 minutes _in each

i. 31-day period.

)

Bases The purpose of the Control Room /TSC Emergency Filtering System is-to limit the particulate and gaseous fission products and toxic products to which the Control Room area and Technical -Support Center would be subjected during -an-accidental radioactive or chemical release in or near the Auxiliary Building.

The system is designed with two redundant filter trains each of which consists .

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

! outside air.

'i t

j Since 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 l

that the system is available for its designed safety action. . During this test the system will be observed for unusual or excessive noise or. vibration when the fan motors are running. The flow of 1600 cfm makeup air was selected to l- limit the maximum radiation dose to occupants of the Control Room /TSC in an

]

accident. For this analysis, both chamoal filter banks were assumed to

L provide DF's of 10, while the HEPA filter DF is assumed to be 100. The -

J laboratory analysis to show >95 percent removal of methyl radiciodide is '

necessary to receive credit Tor a DF 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 5

at least equal to the design values.

~

147> The filtering system is automatically started and the nomal system isolated.

< when the radiation level or when the Chlorine level. increase.

! The testing required af ter painting, fire or chemical release, is:not' to be

, interpreted to include minor touch-up painting, housekeeping chemicals and

detergents, or other routine maintenance or housekeeping activities.

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il Proposed Amendment No.147 ~

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RANCHO SECO UNIT:1-TECHNICAL SPECIFICATIONS.

Surveillance Standards . ;

'4.31 l NUCLEAR-SERVICE ELECTRICAL BUILDING EMERGENCY HEATING' VENTILATION AND AIR CONDITIONING Applicability .

Applies to the Nuclear' Service Electrical Building '(NSEB) Emergency Heating ,

. Ventilation and.. Air Conditioning '(HVAC) System components.

Cbjective To verify that this' system and its components will be able to perform their design functions. .

i Specification 4.31.1 The NSEB Emergency HVAC'shall be:

4 I 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 flow rate of

24,500 cfm

10 percent.

2. Verify that the condensing ' unit is operational.

4 l Bases The purpose of the Emergency Nuclear. Service Electrical Building Emergency.

l HVAC is to limit high temperatures which the building would be subjected to upon loss of nomal cooling. The high temperatures will affect the environmental qualification of safety related electronic equipment housed .

within the NSEB which is used to support the Control Room /TSC upon accident

' conditions. The system is designed with an air handling unit and a condensing-unit which are activated upon high temperature ' signals.

i Since this system is not nomally operated, a periodic test is required to j ensure its operability when needed. Monthly testing of this system will show l that the system is available for its safety action.. During this test the system will be observed for unusual or excessive noise or vibration when the fan motors are running. The air flow of 24,500 cfm was selected to limit the temperatures in the building to 80*F maximum (with the exception of the cable

{r shafts).

! , The system is automatically started when the temperature in the NSEB 147x Switchgear Room exceeds 95*F.

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l Proposed Amendment No. 147 -

4-91 l I f

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I 147>

. RANCHO SECO UNIT 1-TECHNICAL SPECIFICATIONS Surveillance Standards -

4.32- TDI DIESEL GENERATOR CONTROL ROOM ESSENTIAL VENTILATION SYSTEM-

- Applicability 4

Applies to the TDI Diesel Generator Building ' Control Room Ventilation System

-components.

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

Specification 4

4.32.1 The Diesel Generator Control Room Essential Ventilation-System shall

- be:

i i Demonstrated operable at least once per 31 days by initiating . U 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. l Bases u

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

!._ System is to limit high temperatures which the local control room would be j subjected to upon loss of normal cooling. The high temperatures will affect 4

the environmental qualification of safety related electronic equipment housed l.

within the Diesel Generator Control _ Room. .This Control Room is designed with-4 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 i fan motors are running. The air flow alarm of 10,000 cfm was selected to ' i ensure that the temperatures in the diesel generator control room will stay i 4 below the maximum of 122 degrees F maximum. 4 The system is automatically started by a thermostat when the temperature in

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

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I Proposed Amendment No.147

[ 92 i

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ENCLOSURE 10 RESPONSE TO THE NRC'S 00ESTIDNS ON PROPOSED AMENDMENT 147

- 1. NRC Ouestion Discuss the Class 1 and non-Class 1 interfaces,

a. _ Battery Chargers

b. Pressurizer Heaters District Response

1. a . - H48GA, H48G8, and H48N1 are the only three chargers that are powered from the TDI diesels,-and are classified as isolation devices.

Unacceptable influence on the Class 1E system is precluded by the_

following design features:

1) The battery chargers are Class '1. - Each charger is protected by two physically-separated Class 1 input circuit breakers. One of these circuit breakers is located inside the charger and the other is in a Class 1 load center

2) DC output circuits from chargers H48GA, H48G8, and H48N1 are routed in dedicated conduits to inverter SIGA, inverter SIG8, and DC panel SCN1 respectively

3) The circuit from the charger to the load (inverter or DC panel) is protected by a Class 1 DC charger output circuit breaker. In addition, each load (inverters SIGA and SIG8, as well as panel ~ SON 1) is protected by an incoming breaker. Each inverter also has an output breaker. AC panels powered from these. inverters have incoming and branch circuit breakers. Panel SONI also has an incoming breaker and branch circuit breakers

4) The circuits from switchboard SONI and inverter-powered panels SIGA-1, S1J, S1G8-1 to the loads are physically and electrically separated from Class 1 circuits

5) Testing of the charger has demonstrated its current limiting capability.

The testing conducted by the vendor (PCP) demonstrated the following:

a) The charger successfully passed one minute dielectric test AC to ground 2000V; AC to DC 2000V; DC to ground 1500V b) The short circuit test was successful c) The transient voltage test was successful.

i Di s t rict ' Resp

ns')

1.b. The emergency pressurizer heaters motor control centers (MCCs' S2A2, S282) are powered from the Nuclear Service Buses, but are tripped off and not automatically reloaded should'a safety features actuation signal or a loss of offsite power signal initiate bus unloading.

There is no restriction to reloading these MCCs. They can be reloaded from the Control Room. This is the design reviewed and accepted i previously by the NRC. (See May 1, 1980 NRC letter to J.J. Mattimoe

.and September 9, 1985, NRC letter to R.J. Rodriguez, attached.) No modifications are being accomplished on.these MCCs or emergency pressurizer heaters under this technical specification submittal.

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,7 UNITED STATES t

NUCLEAR REGULATORY COMMISSION

_, '8 p,

. wAssinsuw.c.c.2 ossa

's jj

, . (._.7.Cfd/ ... May 1, 1980" Docket No. 50-312-l 1[

Mr. J . ' J . Mattimoe Assistant General Manager and Chief Engineer Sacramento Municipal Utility District 6201 S Street '

> Sacramento, California 95813 1

Dear Mr. Mattimoe:

Enclosed for your information is the staff's evaluation for the Rancho , ,

Seeg Nuclear Generating Station of the actions you have taken to satisfy '

the Category "A" items of NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recomendations." This evaluation -is based on your submitted documentation and the discussions between our staff at a site ~ visit on March 17 and 18,1980. ,

$ Based on our evaluation, we conclude that with the exception of Items -

) 2.1.3a and 2.1.7a, you have satisfactorily met all Cat.=very "A" require- '

~

ments. In our letter of February 1,1980, we concluded that equipment

( .

availability would preclude implementation of Item 2.1.3a by January ,

I- 1980, but stated that it should be implemented no later than June 1, 1980. Item 2.1.7a has been the subject of a separate review and was discussed in our letter of February 26, 1980. Our Office of Inspection and Enforcement will verify the adequacy of implemented procedures.

These items are discussed in our evaluation.-

It should also be noted that Item 2.1.9, which was classified neither Category "A" or "B", has also been the subject of separate reviews.

The tasks required to be completed under this item are listed in Table B-2 of NUREG-0578. . In this regard, you have made submittals relating to Tasks 1 through 4 and 7 of Table B-2. Our evaluation of your completion of Tasks 1 and 2 was documented in NUREG-0565, " Generic Evaluation of Small Break Loss-of-Coolant Accident Behavior in Babcock

& Wilcox Designed 177-FA Operating Plants." Your submitta.ls related to Tasks 3, 4, and 7 are still under staff review. Your preliminary proposals with respect to Tasks 5 and 6, which have been the subjects

- of meetings betweert Babcock & Wilcox operating reactor plant licensees i

and the NRC, are also still under staff review. Evaluations of the incomplete Tasks will be the subject of additional staff reports.

s e

e

Mr. J. J. Mattimoe : May 1, 1980

(*

These evaluations do not address the Technical Specifications necessary-to ensure the limiting conditions for operation and the long-tem oper-ability surveillance requirements for the systems modified during the Category "A" review. You shoul_d be considering the proposal of such Technical Specifications. We will be in comunication with you on this item in the near future.

Should you have any questions regarding our evaluation, please contact us. ,

Sincerely.

p f

- Robert W. Reid, Chief -

Operating Reactors Branch #4 .

Division of Licensing i

Enclosure:

Evaluation for Rancho Seco ec w/ enclosure:

( -

See next page-t 9

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EVALUATION OF LICENSEE'S COMPLIANCE WITH CATEGORY "A"' ITEMS OF NRC RECOMMENDATIONS

- RESULTING FROM TMI-2 LESSONS. LEARNED i

, i SACRAMENTO MUNICIPAL UTILITY DISTRICT RANCHO SECO NUCLEAR GENERATING STATION 1

( ,

DOCKET NO. 50-312 Date: May 1,1980 *

w. .c . . - - , - ~ , - - - . - . - - , . . - - - , , . - - - . - , ,

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.2 l.la- EMERGENCY POWER SUPPLY REOUIREMENT i

The Sacramento Municipal Utility District has determined based o l

lations-and startup testing experience that a minimum of 126 kilow -

pressurizer heaters, which according to the' licensee correspon

' within two hours after loss of offsitebank of pressurizer heaters e

' circulation 'at hot standby conditions. power to establish and maintain natura1 total heat loss was 106 kilowatts. Startup testing demonstrated that the this-calculated and measured' heat have been accepted for other' pressurized water reactors. loss is sim We conclude that a

pressuri'zer during normal hot standby conditions. sufficie i

I of pressurizer heater capacity to each emergencThe.; watts

! dundant group of heaters are supplied from non y diesel generator. Each re .

I centers during all modes of operation. safety related motor control j centers art powered from emergency buses.These non-safety related motor control 1

i actuation loaded signal, on the safat,)t husetthese heater breakers will be tripped and-w v

diesel generators can be All actions to afrom he these heateFs roomfrom the t

f accomplished the contral The licensee t

t.

has these stated pressurizer that procedures heaters on the safety have buses. been modified covering the '

1

! 1 .

i i

.met Based on our review of the above design, we conclude that 'the l the emergency power supply requirements for this item.

4 the adequacy of the licensee's procedures andVerification pressurizer r

of' heater p supply

{ modification will be performed by the Office of Inspection and' Enf and documented in an appropriate inspection report.

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ReliefValve-(PORV)ancBlockvalves) EMERGENCY POWE t :

i The a battery current which isdesign not safetyhas grade. its PORV powered from a 125 volt DC

i i~

However, the charger for the battery is b .

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.'. #e, UNITE 3 STATES

! n NUCLEAR REGULATORY COMMISSION f

,I wasumorow.o.c.aoses i

\...../ September 9, 1985 Docket No. 50-312 ,

1 Mr. Ronald J. Rodriguez Executive Director, Nuclear Sacramento Municipal Utility District ,

6201 S Street .

P. O. Box 15830 , f Sacramento, California 95813

Dear Mr. Rodriguez:

SUBJECT:

AMENDMENT NO. 74 TO FACILITY OPERATING LICENSE NO. DPR-54, PRESSURIZER HEATER TESTING

, Thet commission has, issued the enclosed Amendment No.74 to Facility Operating

License No. OPR-54 for the Rancho Seco Nuclear Generating Station. This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated October 29, 1984.

The amendment veh tte Tectmical SpecifinHW defining. the t*< Hag, requirements for those pressurizer heaters powered from Class IE power sources .

A copy of the Safety. Evaluation.is also enclosed. Notice of Issuance will be included in the Cosmission's Biweekly Notice.

. Sincerely, W

Sydne r. Project Manager Operating Reactors Branch #4 Division of Licensing

Enclosures:

1. Amendment No. 74 to DPR-54 l' '

2. Safety Evaluation ', C )(h h h' cc w/ enclosures: .

See next page p e..

n ee6 A

- ,, UNITE] STATES

[ g NUCLEAR RECULATORY COMMISSION t, j WASHINGTONa C. C. 20888 SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312

[ ,

RANCHO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICEllSE e

e Amendment No. 74

/

License No. DPR-54

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

A'. The application for amendment by Sacramento Municipal Utility I District (the licensee) dated October 29, 1984, complies with the i 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;

8. The facility will operate in conformity with .the application, the e the provisions of the Act, and the rules and regulations of the Conmission; 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 ar.andment will not be inimical to the comon 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.

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. DPR-54 is hereoy amended to read as follows: !,

6 m r l,d v r !U)r J 1 /

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Technical Specifications ,

The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 74 , are hereby incorporated in the license. The licensee shall operate the facility. in accordance with the -.

Technical Specifications.

t

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

. , . . 7 FOR THE NUCLEAR REG TORY ' COPHISSION ohn . Stolz, Chief ating Reactors Branch #4 i

Division of Licensing i

Attachment:

Changes to the Technical i +

Specifications ,

Date of Issuance: September 9,1985 ,'

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ATTACNMENT TO LICENSE AMENDMENT NO.74 FACILITY OPERATING LICENSE N0. DPR-54 DOCKET NO. 50-312 I Replace the following page of the Appendix A Technical Specifications with the enclosed page as indicated. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.

Remove Insert f 4-35 4-35 i

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[ :; .

RANCHO SECO UNIT 1

~ TECHNICAL SPECIFICATIONS.

Surveillance Standares 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.

i The tests specified will be considered satisfactory if control ,

room indication and/or visual examination demonstrates that all components have operatec properly. I 4.6.6 The pressurizer shall be tested as fcilows:

A. The pressurizer water level shall be determinee to be witnin its

r limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

I 8.5 The power supply for the pressurizer heaters shall be demonstrated OPERABLE at least once per 18 months bym. -

i using the Nuclear Service bus to energize the hesters.

i Bases l ,

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 tne manual energization of the A. Train Control' l l'

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 38,

.382 intertie breakers are automatically closed-and the-B Train Control Room

, essential HVAC System is automatically energized. The 3A-3A2 ane 38-382 i interties are not required if the event is only a safety features actuation.

The testing frequency specified is intended to identify and permit correction of any meenanical or eldctrical deficiency before it can result in a system

failure. The fuel oil supply, starting circuits and controls are continuously monitored and argy faults are alarmed and indicated. An abnormal condition in

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

]

j 1 Precipitous failure of ta= plant libattery is extremely unlikely. The surveillance specified is that which has been demonstrated over th,e years to provide--an indication of a cell becoming unserviceable long befort it fails.

f i

REFEREkCE s r j (1) IEEE 308

4 i .

Amendment No. U , ff , 74 4-35 4

.#,,W**%g. .

- - UNITED STATES

. , . ! g NUCLEAR REGULATORY COMMISSION c e. wasumarow.o.c.meess 1

ISAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 74 TO FACILITY OPERATING LICENSE NO. DPR-54 SACRAMENTO MUNICIPAL UTILITY DISTRICT j RANCHO SECO NUCLEAR GENERATING STATION DOCKET NO. 50-312 7

I. INTRODUCTION A. DESCRIPTION OF PROPOSED ACTION ;

The proposed action would' amend Section 4.6.6.B of Appendix A of the facility Technical Specifications. This section specifies the testing requirements for the pressurizer heaters that are capable of being energized from emergency power supplies in the event of a loss of offsite power. Instead of the present reouirement that power be transferred from the "...nomal to the emergency power supply..."

and the pressurizer heaters then be energized; the proposed change would provide that the power capability be demonstrated by using the Nuclear' Service Bus to energize the pressurizer heaters.

B. BACKGROUND INFORMATION One of the reconsnendations of the TMI-2 Lessons Learned Task Force (NUREG'-0578) was the provision of emergency power for the number of pressurizer heaters required to maintain natural circulation conditions in the event of a loss of offsite power. In addition, the NRC's Generic Letter of July 2,1980, forwarded model technical specifications which prescribed appropriate means for testing this group of pressurizer heaters and requested licensees to apply for amendment of facility technical specifications to incorporate these model technical specifications. The Sacramento Municipal Utility

. District (the licensee) responded to this request on.0ctober 8, 1980, by proposing technical specifications which were substantially

. identical to the model. These were subsequently approved by the NRC on March 27, 1981. -

By letter dated October 29, 1984, the licensee requested amendment of these specificatioris to pemit a change in the method of verifying heater operability. This evaluation addresses the acceptability of this request.

l II. EVALUATION s '

prior to the accident at TMI-2, there was no requirement that pressurizer i heaters be capable of being energized from emergency power sources. i

, These loads, therefore were typically served by non-Class 1E electrical b {

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i buses. With ' adoption of this requirement, licensees were required to

develop new procedures or implement modifications to permit these loads 1 4

-to be energized by Class 1E sources - particularly the emergency diesel :

i generators. In addition, the requirement led to the incorporation of )

4 present specification 4.6.6.8 which follows the model technical-l specification and states:

! l "The emergency power supply for the pressurizer heaters shall be demonstrated OPERABLE at least once per 18 months by transferring - J power from the normal to the emergency power supply and energizing / '

the heaters."

i i The licensee states they have performed this verification regularly by j starting the diesel generators and energizing the pressurizer heaters from this power source. The licensee,also notes, however, that their method for complying with the TMI requirement was to modify the ,

electrical distribution system so the required number of pressurizer ' '

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( heaters would always be energized from redundant Class 1E buses. Thus, ,

! .no special switching procedures would be required. The licensee now i j observes that with this modification, no useful purpose is served by the ,

i present practice of starting the diesel generators in order to energi2e ,

i the pressurizer heaters. The licensee bases this statement on the fact-i that the designated groups of pressurizer heaters are always served by I the Class 1E Nuclear Safety Buses. Thus, as far as energizing these

! heaters is concerned, it is immaterial whether the Buses are supplied by

, the diesel generators or from offsite power. As long as the Nuclear.

~ Service Buses can be powered from either of these sources, the heaters i

! can be energized. As a result of these considerations, the licensee has ; ,

! proposed to revise specification 4.6.6.8 to read as followsr ' '

! "The power supply for the pressurizer heaters _shall be demonstrated

OPERA 8LE at least once per 18 months by using the Nuclear Service j Bus to energize ths heaters."

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j Regarding this request, we note the licensee'.s implementation.of the l

! NUREG-0578 recommendation concerning power supplies for pressurizer i heaters (Item 2.1.1) was reviewed by the NRC staff and approved by NRC i letter dated May 1, 1980. We also note the installed modification and i l associated procedures were reviewed and found acceptable, as documented j l in.NRC Inspection Report 50-312/80-23, dated August 13, 1980.

As for the effect of the change in test methods, our review of the j i licensee's electrical drawings confirms that the designated pressurizer ,

heaters are permanently connected to-the respective Nuclear: Service i

l Buses. We therefore agree with:the licensee that the pressurizer heaters will be capable of being powered whenever the Nuclear Service Buses are ,

! energized - regardless of the source of power. Thus, since the sole l 1 purpose o' the onsite emergency power system is to provide power-to-the j

! Nuclear Service Buses, and this function is already confirwed by other !

l tests, there does not appear to be any safety benefit to be derived from

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requiring the licensee to start the diesel generators merely for the

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!* 3 purpose of energizing the pressurizer heaters. Indeed, such a requirement could be counter-productive by unnecessarily increasing diesel generator wear. Accordingly, we conclude the change requested by

! the licensee will not reduce the present level of safety and is acceptable. .

III. ENVIR0tMENTAL CONSIDERATION This amendnent involves a change in a surveillance requirement. We f have' determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents t l that may be released offsite, and tht there is no significant increase in individual or cumulative occupational radiation exposure. The Consnission has previously issued a p oposed finding that this amendiaent l involves no significant hazards consideration and there has been no a public conssent on such finding. Accordingly, this amendment meets the -

i eligibility criteria for categorical exclusion set forth in 10 CFR 51.22 ;

(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement 4

or environmental assessment need be prepared in connection with the <

) issuance of this amendment.

! IV. CONCLUSION ! -

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We have concluded, based on the-considerations discussed above. -that (1) there is reasonable assurance that the health and safety of the public

will not be endangered by operation in the proposed manner, and (2) such

! activities will be conducted in compliance with the Commission's

. regulations, and the issuance of the amendnent will not be inimical to i l

4 consnon defense and security or to the health and safety of the public.

l Date: September 9,1985 '

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! Principal Contributor:

l G. Zwetzig i

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2. NRC Ouestion Justify why there is no Class 1 indication of diesel generator status in the control room.

t District Response District response will be provided by April 10, 1987.

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3. NRC'Ouestion Explain-the changes in the system interactions from the original submittal 7

to the latest submittal.

District Response i

The interactions removed are explained below:

. 1. Containment and Containment Emergency Sump Level Inputs to the Computer

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L' The level devices were powered from chargers that did not have~

! transfer switenes or a backup supply. They now do (ECN R-0955) and I will be continually powered from either GEA2 (primary) or GEA (backup). Consequently there is no interaction.

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2. Reactor Coolant System High Point Vent Valves The valves are powered from the GEA2(GEB2) diesels. Two parameters

! used to evaluate the need for operation of these valves are powered I from the NNI-X power system (OSTG 1evel and pressure). The NNI-X was'

powered from diesel GEB with a backup from GEA. This was an interaction.

l I Because the NNI-X is now powered from GEA2, this is no longer an i interaction (ECN R-0927). '

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3. Pressurizer Emergency Heaters i The pressurizer heaters are supplied from GEA2(GEB2) while the RCS

pressure indication is powered from the NNI which was supplied from i GEB(GEA). Because the NNI has been moved (ECN R-0927) and is now l supplied from GEA2, there is no longer an interaction.

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! The two new interactions shown result from the movement of the Auxiliary l reedwater System from diesels GEA(GEB) to diesels GEA2(GEB2).

f An additional interaction which is not in the December 19, 1986, submittal

! has been identified. The standby battery chargers (H4BAC and H4BBD) are l powered from the diesels GEA2(GEB2) while the normal chargers are supplied

! from diesels GEA(GEB). If the swing' charger is in use, an interaction ;

! exists with a loss of the diesel-supplying power to the standby chargers.

l This condition would cause loss of the 125V DC and 120V AC vital power for i this train after 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (minimum) when the battery has been discharged.

4 The present design addresses this problem by placing a Technical 4

Specification' limit (3.7.1.H) on the use of the swing charger. This 4

interaction is not considered an adverse interaction.

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4. NRC'Oulstion

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-Justify the deletion of the.overvoltage protection relay trips. \;p[

Di-trict ResDonse Overvoltage Control T

To insure greater continuity'of the power supplies to the Class 1-switchgear and motor control centers, _and to minimize emergency starting of the Class 1 diesel generators, the District proposed to modify.the

- method for dealing with overvoltage conditions on the class 1 electrical buses at Rancho Seco. This change will replace the overvoltage trip relays with an overvoltage alarm and monitoring system which will maintain the same maximum voltage limits as at present. .These overvoltage trip i relays have, on two occasions in 1985, tripped the Class 1 buses off from offsite power, and caused unnecessary emergency starts of the Class 1 diesel generators.

The overvoltage (OV) trip relays were installed voluntarily in response to

' the letter " Safety Evaluation and Statement of Staff Positions Relative to the Emergency Power Systems for Operating Reactors" from Robert W. Reid to j J.J. Mattimoe, dated June 3, 1977, which appeared to require both overvoltage trip relays and undervoltage trip relays to automatically

initiate disconnection of offsite power sources when voltage limits were j exceeded. (Position 1 of June 3. 1977 letter is titled "Second Level ?

! Under or Over Voltage Protection With a Time Delay.") .

The OV trip relays had been in service for several years when, in_1985, 0V l trips occurred on two separate occasions. The first event was caused by a

! transient overvoltage condition during starting of a reactor coolant pump, l and the second event occurred with a switchyard voltage of 236.8 kV (within the normal voltage range).

4 In view of the two OV trip events in 1985, the District has concluded, as l have other utilities, that to correct Class 1 bus overvoltage conditions, 4

it is more sensible to rely on operator action than it is to rely upon 4 automatic tripping. Additionally, an overvoltage condition is less l critical to electrical equipment and, therefore less time-sensitive than a corresponding undervoltage condition. Operator actions designed to i maintain the existing limits on overvoltage conditions are planned as j follows:

, 1. An alarm at 4500 volts will alert the operator to initiate actions, <

per procedure, that request the SMUD dispatcher to attempt to lower the grid voltage at Rancho Seco.

2. Continuing printouts of the Class 1 bus voltage will allow the operator to monitor the bus conditions until the voltage returns to the normal range. Selected loads could be added to the buses to help reduce the

! voltage.

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3. If' th2 ab:va act'ie:s do n:t ~ result in a sufficisnt 'rsducticn in :

vsltag2, th2 cperater will parallel th2 diesol-g:nsrater with th2-offsite supply,' first insuring that the. bus load is not above the-rating of the diesel generator, and.then disconnecting the bus from 3,. the offsite power source-

4. If the bus voltage exceeds 4626 volts at'any time, the' operator will disconnect the Class 1 bus from the offsite supply without delay, thus-initiating automatic starting and-loading of the diesel generator.

Should the diesel generatorchave been started, it would first be shutdown. This' assures that'there will be no out-of-phase connection of the diesel generator due to immediate closure of _ the diesel _s generator breaker.-

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$ The foregoing steps ~will-be taken for each bus which experiences an overvoltage condition. 'These procedures will be revised prior to restart.

It should be noted that there will be no change in the maximum voltages allowed in the Class 1 electrical system. Therefore, the analysis of.

operating voltage ranges for Class 1 equipment included in the District's response to Guideline #11 of Enclosure 2 in the letter from NRC's William Gammill to All Power Reactor Licensees, dated August 8,1979, is .still applicable. The District-response to Guideline #11 is attached.

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I GUIDELINE #11 I? To provide assurance that actions taken to assure adequate voltage

. levels for safety loads do not result in excessive voltage, assuming the ~ ,

"" maximum expected value of voltage at the connection to the offsite circuit,.

f a determination should be made of the maximum voltage expected at the e terminals of each safety load and its starting circuit. If this voltage exceeds the maximum voltage rating of any item of safety equipment immediate

[* remedial action is required and NRC shall be notified.

RESPONSE TO GUIDELINE #11 The District has performed a review of data on voltage in the

< Rancho Seco switchyard. Based on this review, the animum expected switch- .,

/j yard voltage is 239kV. For the existing transformation ratios (Sketches 2-7)

, and assuming a no load condition, the maximum voltage.on the 4.1'6-kV system is 4531 volts and on the 480-V system is 511 volts. These voltages are 2 l

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equal to or less than the maximum voltage ratings of any safety equipment li j.( except the 460-V motors and motor-operated valves (MOV's).

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,, An analysis for each type of safety-related equipment is listed below. Ij This. analysis was based on the maximum steady-state voltage allowed (4626V) l by the overvoltage protection relays since this voltage is higher than the 8i*

/ , maxi'um a expected voltage and represents the permissible extreme.

Motors & Motor-Operated Valves - The 4160-volt motors are designed ,

to operate at a maximum voltage of volts which is less than the maximum '

7 calculated vcitage of 4626 volts (111 percent of 4160V). The 460-volt l 3 motors and motor-operated valves have a maximum. voltage rating which is l L less than maximum calculated voltage of 521 volts (113 percent of 460V). l I - i

[ Operation of the motors and motor-operated valves at these voltages is

[; acceptable for the following reasons:

a. Operation at the maximum expected switchyard voltage is an extreme condition that is only expected to occur on rare occasions and for short durations.. (Note - Operating time of MOV's during this condition is further limited by their inherent short-time operating duty.)

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b. The maximum calculated voltage condition conservatively assumes that there is absolutely no auxiliary load operating (i.e: no voltage drop) when the maximum expected switchyard voltage occurs. 4 N

p , c. The maximum calculated voltage condition conservatively 2' assumes operation at two percent above the seximum expected l~ - '

voltage (i.e., it allows for relay inaccuracy).

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d. The motors and motor-operated valves will be" operating at less than 110 percent of rated voltage when equipment opera-tion is initiated by an STAS due to' voltage drop in the

' electrical system.

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l e. The maximum voltages calculated will produce a torque that [

3 is only slightly greater than the torque that would be-produced at the nominal maximum voltage of 110 percent.

I' However, due to voltage drop during starting and operation of.a motor, the maximum voltage at the terminals of the

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motor and the increase in torque will be reduced. The MOV

\ circuits have minimal voltage drop during starting and operation.

?s Therefore, it is possible for the MOV's to produce a slightly greater torque than that produced at 110 percent voltage. However, operation of the MOV is limited by a

.. torque switch. .Therefore, the excessive torque is not applied to the valve and operation during .the overvoltage ;

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condition is acceptable.

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'r t f. The motor manufacturers contacted did not expect any adverse effect to their equipment due to tha slight overvoltage j.: levels being considered. Operating instructions published

4 by oro motor manufacturer

indicate the following character-Jh I istics for operation of their motors above rated voltage.

i i Percent of Full Load Percent of Full Load Percent Percent Temp.

E, Rated Voltane Efficiency Current . Torque Rise 100 100 100 100 -

110 101.5-102 93 121 (-)3 to (-)4*C 120 100+ 89 144 (-)S: to (-)6*C .

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From the above data, it is indicated that motors are not i- particularly sensitive to overvoltage. Efficiency at 7

120 percent voltage, for example,- is even better than at rated voltag'. e 3 Overvoltage alarm relaying is being added to the 480-V safety buses to alert the operator should an unusual over--

voltage condition (greater than 110 percent of 460V) occur.

Battery Charmers - The battery chargers are qualified to operate at full load with a maximum input voltage of 528 volts (114 percent of 460V) which is above the maximum calculated voltage of 521 volts.

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Installation, Operation and Care of " Duty Master" Nuclear Service Class IE Integral Horsepower Induction Motors, Reliance Electric Instruction Manual B-3645, December, 1977.

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Heat Tracina System - The heat tracing system for the safety--

related pipes, tanks, and valves containing boric acid consists of strip ,

type resistance heating tape, transformers and thermostats. All of this I equipment should be capable of operating at the maximum calculated voltage .

of 521 volts. .l

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MCC Control Circuits - The control voltage for nach 480-volt MCC l feeder circuit is obtained from a feeder line tap through a 450 to 120 volt-stepdown control power : transformer with the maximum expacted switchyard . voltage of of 239 kV, this voltage will not be exceeded. The maximum voltage rating for the most limiting component is.132 volts. The 480-volt 2 4 . safety bus overvoltage alarm setpoint corresponds to 132 volts on ths l unloaded secondary of the control power transformer. ..

Overvoltane Relay Setpo' int - In case the maximum calculated' d* voltage is exceeded the analysis indicates that the District's overvoltage relay should be set at 4580. volts (110 percent of 4160V) witich, assuming a

p no load condition, corresponds to a maximum of 112 per. cant of 460 volts on

}Y . the 480-V system. This setpoint is equivalent to' a voltage of 242kV. in the

switchyard. With this setpoint, the relay will protect the safety-related

- equipment. The relay is set a higher voltag.e than the maximum expected voltage and will not cause spurious trips. It has a definite time delay 4

, set at 3 s.aconds and operates in series with an external time delay relay

set at 0.5 seconds.

I GUIDELINE #12 i Voltage-time settings for undervoltage relays shall be selected

!( so as to avoid spurious separation of safety buses from offsite power.

1 during plant startup, normal oper,ation and shutdown due to startup and/or

' ;.' operation of electric loads.

RESPONSE TO GUIDELINE #12 i The setting 'for the undervoltage relay was selected to assure

, protection of the safety equipment as explained in.the response to Guide-line #10. The setting selected avoids spurious separation of the safety buses from offsits power during plant startup, normal operation and shut-down due to starting and/or operation of loads providing the switchyard voltage is above 218kV. This level is below the 221-kV voltage defined as -

the normal minimum voltage for the switchyard.

GUIDELINE #13 Analysis documentation should include a statement of the assump-tions for each case analyzed. .

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5. NRC'Ouestion 1 Discuss how the District will address the requirements of Generic Letter 84-15 Table 4.8-2.

. District Response The proposed Technical Specifications have been revised to contain the clarified requirements of Generic Letter.84-15, Table 4.8-2.

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6. NRC Ou7stirn

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Clarify the intent of Notes l'and 2 as used in Technical Specification 4.6.3 and its applicability.

District Response 1 1

Note I has been divided into three separate notes to clarify the exact-

-surveillance testing requirements. Note 1 addresses the monthly i surveillance testing requirements. Note 3 addresses the refueling interval surveillance testing requirements. Note 2 has been renumbered to Note 4. Note 5 addresses the 10 year interval surveillance testing requirements. The revised notes are included in the proposed Technical Specifications.

7. 'NRC O'uesti"n Discuss the operation, power-source, and seismic classification of HVAC-dampers as described in Tables 3 and 4 of ECN A-3748 [DBR).

District Response These HVAC dampers are numbered as HV-55711 through'HV-55714. They are interlocked to operate (i.e., open and shut) when the associated essential air handling unit (AH-DG-1 A-and AH-DG-18) starts and stops. The air handling unit is thermostatically-controlled by the temperature in the'

' diesel control room, energizing whenever 110 degrees F is reached.

The dampers are motor-operated and powered by 120 volt AC panels (S1A4 and S184) which, in turn, are. powered from Class 1 480 volt AC panels (S2A4 and-S2B4). Upon loss of power. .the dampers fail AS-IS, but they can be manually-operated by a handwheel (drawings M17.07-6 and M17.07-7). The dampers are classified as seismic Category 1 and quality Class 1.

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r8. NRC Outstirn Discuss the air supply system to 'the diesel and potential ~ common' mode failures since-these are not Class I compressors. -. Discuss the effect_of loss of air on the pneumatic controlsfand diesel operability.

District Response The air. supply system to each diesel is comprised of an air compressor, an

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air dryer, two air receivers, and associated piping, instrumentation, valves, and. strainers. The piping and other components between the air receivers and-the diesel are designed and fabricated to seismic Category-1

.and quality Class 1 ASME III standards._ The air receivers.themselves meet Category 1 and Class 1 ASME VIII standards. The Class 1 components are

. protected from failures in the Class 2 portions (i.e., compressor, dryer, i and associated components) by isolation and check valves. Each pair of air receivers is capable of starting the engines at least ten times, as -

proven by pre-operational testing, without reliance on its air compressor.

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All parts of the starting air system _for each diesel engine are isolated from each other electrically and physically, including the process piping and instrumentation. This design greatly reduces the chances of common mode failure.

Although the air receivers can supply enough air to start each engine, they also supply control air so that the protective functions of the engine (such as the low lube oil pressure trip) will operate properly. .An i air supply is not required to maintain the diesel engine running-l continuously, though there are other concerns. As discussed in the Design' Basis Report for this modification (ECN A-3748), as the air receiver pressure drops, an alarm will sound at 225 psig, but there will be no other effect because control air pressure is normally maintained by a PCV at 60 psig. The next alarm will occur when the air receiver pressure, :

l hence the control air pressure, reaches 53 psig. If the control air. ,

pressure continues to drop below its alarm setpoint at some point a pneumatic sensor will attempt to use the residual air in the tubing to shut down the-engine. As a result, the spring-loaded fuel rack shutdown cylinder may partially, yet momentarily'close, causing a significant change of engine speed and subsequent unloading of generator loads.

. Although the engine will resume its normal operating speed, at this point j 4 all protective shutdowns will have been lost. Should this scenario occur l to one diesel system, the redundant train would be available to take over 1 the emergency loads.

Therefore, to avoid a common mode failure of generator unloading, the engines require a long term supply of control air to maintain power.to their emergency loads. This need is common to both engines. During pre-operational testing, the District will verify and repo~t on the l capability of the air receivers to maintain at least 60 psig for engine '

control air over a-prolonged time period.

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9. NRC Ounstirn-Discuss the operational differences between LOOP and SFAS signals upon the buses. (See page 4, " Description of Electrical Distribution System at Rancho Seco.")

District Response Each 4KV bus (S4A, S4A2, S4B and S4B2) has a sequencing circuit that is independent of any other. The active inputs.to each are an SFAS signal and an undervoltage signal. For Train A (buses S4A and S4A2), the SFAS signal comes from a single'SFAS cabinet and therefore the two independent sequencers (S4A and S4A2) respond concurrently. The B train is set up similarly.

The undervoltage signal comes from each individual bus (S4A, S4A2, S48, and S482) and therefore the_four buses respond independently. With or without an SFAS, the bus sequencer is responding and therefore could be considered " responding independently". A simple functional block diagram is attached for clarification.

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UNDERVOLTAGE SEQUENCER S4A TRAIN 'A' .

i SFAS UNDERVOLTAGE SEQUENCER

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, UNDERVOLTAGE SEQUENCER S4B TRAIN 'B' SFAS ,

2 BUS UNDERVOLTAGE SEQUENCER S4B2 i

GlocK .b t A 6 AL A M -l l

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l 10.lNRC Ouestirn

. ' Explain lthe~ similarities / differences between;the circuitry'and operation !j of the bus unloading (sequencer) circuitry and diesel: generator ~ breakers i

of buses 4A(B) and 4A(B)2. (DBR for ECN A-3660, App. D,-Section 11.1.,

page 0-1). ' Explain what is meant by the term similar-in Section II, item.7, page 3 of DBR for ECN A-3660.

District Response l

The' design feature-discussed in item 1 of Section II-allows the resetting -

-of the undervoltage sequencing circuitry when the bus voltage returns to normal. -This feature is added-in parallel-to the existing reset s*3nal,-

diesel generator breaker closed.

The design' feature that item 7 adds to the 480 volt Load Center circuit breaker (s)-(i.e., supply breaker for 3A2(382)) is automatic reclosure following bus unloading and subsequent ~ reloading. The existing design between Buses 4A and~3A (4B and 38) has this feature and uses the 4A(48) l circuit breaker as-the operating (i.e., trip and reclose) circuit breaker. Functionally, the 4A2/3A2(482/382) circuit breaker combinatior, operates the same as :the 4A/3A(4B/3B) circuit breaker combination, except that the 3A2(3B2) Load Center circuit' breaker (s) is the operating (trip and reclose)-circuit breaker (s).

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11. NRC Outstirn Justify operation with tie-breaker in racked out position. (See DBR'for ECN A-3660, Appendix D,Section II. item 3., page D-2.)-

District Response The maintenance tie circuit breakers will be racked out and under administrative control (i.e., used by procedure only). They would be used for maintenance during cold :hutdown. .They are currently not intended for use under any Casualty Procedures, but this District commitment.is not

intended to preclude this use. Their use in a Casualty Procedure will be-reviewed carefully under existing procedures controlled pursuant to 10 CFR 50.59. The procedure controlling the maintenance tie circuit breakers will be revised prior to restart.

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12. NRC Ouestirn Justify.the change in NSST transformer-rating from_10MVA (original submittal)-to.7.5 MVA (present submittal). (See DBR for ECN;A-3660,

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Section II.5, Appendix'D.)

District'ResDonse The original submittal reflected theLDistrict's plans to upgrade the'NSST transformer rating to 10 MVA. However, the District' determined that this-upgrade could be postponed.

In accordance with Generall Design Criteria 17, the Rancho Seco' electrical auxiliary system was designed for and has-the capability of supplying either safety train afrom either-start-up transformer, and it will maintain acceptable minimum voltage within the full range of switchyard voltages as defined in the technical specification. No overload on Transformer X74

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will exist under this condition.

An overload condition on X74 occurs only under the following circumstances: ,

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COMMENT i 1. Upon the lo:s of startup To get to this configuration.

l transformer (SU) No. 2 requires extensive manual actions both safety trains must be including, but not limited.to:

} fed from SU No. l. This

Turning off the DGs that have i operation of both safety started due to. loss of bus trains on SU No. 1 is voltage (incoming train) performed under the technical

Assuring all. loads on the j specification LCO for SU. incoming train are off 1

Connecting the train to S.U. No.

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Restarting the loads

Note that a stringent tech spec LCO is imposed here-(loss of one ;

~offsite power source).

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2. Makeup Pump (P236) has This condition means the HPIs were -l been connected to one nuclear secured because all are 100%

bus and it is operating. capacity.

. 3. A LOCA condition occurs sub- The probability of sequential

sequently to #2, above. events is small.

, 4. All loads required to mitigate This' condition means a scenario i the consequences of the LOCA that does not allow operator are connected to Buses S4A, termination when the operator

-S4A2, S4B and S482 and are- has indication of safety function.

operating. being satisfied by only one 100% capacity train.

! l i__- _ .

Undsr thssa circumstanccs, the transfermer would b2 op2 rating approximately 7% cvsr its rating with:ut fans. This evarlead can b2 sustained for a period in excess of four hours without any accelerated loss of-life. During this four-hour period an operator can take necessary action to reduce the-loads to within the transforner rating. This would be expected as the operators secure redundant full capacity loads. If the overload condition is allowed to persist for longer than four hours,-the transformer will not experience catastrophic failure. It will-simply suffer an additional loss of life (accelerated aging). For. example, if the overload persists for a 24-hour period, the transformer loss of' life would be 0.25% in addition to the normal loss of life (0.0369%) the transformer would experience if it were loaded at 100% rating for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (reference Calc Z-EDS-E0661).

Should the overload condition occur coincident with minimum switchyard voltage, a low voltage condition could occur at the safety-related buses.

Under this circumstance, undervoltage relays will automatically disconnect the buses from the offsite power system, and the diesel generators will be connected and loaded, in accordance with the requirement of Branch Technical position PSB-1 paragraph B.b.2.

Two items should be noted:

1. From the above discussion, no manual intervention is required for the safety systems and their associated equipment to perform their required functions

2. A condition where both safety trains are fed from the Nuclear Station Service Transformer (X74) is a very unusual situation.

't i

s

--13. NRC Ous:stirn-Discuss the environmental and seismic classification of the static and manual switches. (See DBR for ECN R-0953 .~Section II.0, page 3.).

District Response The switches are. environmentally qualified for their environment and they are seismic. category.1.

14..NRC Ouistion Provide a copy of NRC-letter Reidlto Mattimoe dated June 3, 1979 (see D8R for, ECN- R-1045, Section .II, 8.2, page 5).

District' Response-

-A copy is attached.

4

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[ ,, NUCt.

uwiTro sraras EAR REGUI.ATORY-cOMMiss10N l

.; g WASHINGTON, D. C. 20555 June 3,1977 (e..../

l.

1. l 1 . '; -

Docket No.: 50-312 , .

4

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1

't . Sacramento Municipal' Utility District l

)[ -

4 8 -

ATTN: Mr. J. J. Mattimore l

.. ; Assistant General Manager

}.',

and Chief Engineer

- l 6201 S Street i '

i .'. . P. O. Box 15830 - - ,

,. Sa'cramento, California 95813 .

' .4 z.....--.,..-----_ .

- , = - . - - - < - -

-!i . Gentlemen .

f

~

u RE: RANCN0 SEC0 HUCLEAR GENERATING STATION .- .,

s . :. .

F

m. .

f.*

We are currently reviewing the onsite emergency power systems of all .

- ,. . operating nuclear power' facilities to assess the susceptibility of.

their safety related electrical equipment with regard to-(1) sustained.

degraded voltage conditions at the offsite power sources and (2) inter-

. action between the offsite and onsite emergency power systems. ,

.~. ;. ,.

We htye completed' oui

review of licenseo responses *to our previous ,

l . i generic request for infonnation relative to the electrical power 3

3- !, distribution systems. Based on this initial review, we have prepared {

the Safety Evaluation and Statement of Staff Positions contained in t

. * ,(; .

Enclosure 1.

f :

We request that you compare the current design of the emergency power

.'.? systems at your facility (ics) with the Staff Positions stated in the

!: enclosure and:

(1) propose plant modificatioas as necessary to meet the Staff

_ .i , Positions, or .

3 (2) provide a detailed analysis which shows your facility ucsign

. has equivalent capabilities and protective features.

Idditionally, we require that certain technical specifications be incorporated into all facility operating ifconses. Model tecnnical l . specifications, consistent with the Staff Positions contained in j ] Enclosure 1, are provided in Enclosure 2.

i Accordingly, we request that you apply, within forty-five days of b[ . .. the receipt of this letter, for an amendment to your factif ty operating l -

a

. license (s) to incorporate comparabic technical specifications to those presented in the enclosure. Addt clonally, you should provide a description and a schedule for the completion of any plant associated ,

modifications. .

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. Sacramento Municipal.Uti,11ty District 6

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'Wyou have any questions " this matt,er, please contact us.

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. Sincerely,. - -

.~ .

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. Robert W. Reid, Chief

.li

.. .. Operating Reactors Branch f4 '

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i .

. 'DiYision of Operating Redctors .

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Enclosuret: . .- _. !

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V

.. - le . Staff Positions * .

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.5e:raee..: Mu.1: m .D *4. ENCLOSURE 1 ,, .

st

...;5AFETY EVALUATION AND STATEMENT OF STAFF POSITIONS ,

i . .M;... .

. i) . W . ;.l.. RELATIVE TO THE EMERGENCY POWER SYSTEMS

,i s;

' ~ * *

?. FOR OPERATING' REACTORS 3 .

. - A. INTn00ucTION - -

s. ,

^

8

_. _- ! . . The onsite emergency power systems of operating nuclear power._f.ac_ili.. ties _.__, ,

~ ~ ... . ._. ._ .__._.... .. -..--....-. ,

--] -are biting re' viewed"to is'sessthesusceptibiytyoftheirassociated

. 't n* ~

_redunda'nt safety-related ele <8trical equipment to: -

g*: .. . .

i

(a) Sustained. degraded voltage Conditions at1the offsite power ,

i source; and

-? *i, -

^

(b) Interaction of the offsite and onsite emergency power systems.

I 1

, ; . We have completed our review of the responses to our generic request for

! ' . '.". ; additional informationl/ relative to the electrical power distribution .

{

e i: '

systems of currently operatina nuclear power facilities. In response

!,- to our request, all licensees have analyzed their system designs to

) ..

e determine that the voltage levels at the safety-related buses have

- been optimized for the full load and minimum load conditions that are expected throughout the anticipated range of voltage variations for g .

the offsite power sources. The transformer voltage tap adjustmer.s

.. that were necessary to optimize the . voltage levels have been accomplished. .

3 .

In addition to the $bove corrective actien, we have developed the following

s. -

staff positions for use in1 valuation of each of the operating nuclear 1

.., power plants with regard to the two items identified above. These position %

,1 l.' 8 were developed on the basis of our review of the licensee response to our

. s ,n.ea p w ,w ~ -

.- 3/ Letters to all licensees, dated August 12 and 13,1976.

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requests for additional information and of other related infonnation as cited in the text. '

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f 3. P0$fTIONS .

! ! 1) Position 1: Second I.evel of Under-or-Over Voltace Protection with a Time Delay .

L, .q!*' ' .,* _ _. .

-~" ~~~

We require ~ that a.second re~yel'of voltage protection for~ the' -

~ -

$ p. ,

onsite power system be provided and that this second level of rly E..

voltage protection shall satisfy the followino criteria:

}. ,

a) The selection.of vgitage and time set points.shall be

!4 ,

determined from an analysis of the voltage requirements of

. .:f I .. '.

the safety-related loads at all onsite system distribution -

ir: . &

. levels; ,- ,

i.'. j b) The voltage protection shall include coincidence logic to-

,,.! preclude spurious trips of the offsite power source; -

53 c) The time delay selected shall be based on the following conditions:

j,- (1) The allowable time delay, including margin, shall not -

i, .

exceed the maximum time delay that is assumed in the

[ FSAR accident analyses;- ,

(2) " Die time delay sha11' minimize the effect of short l,. '

duration disturbances from reducing the availability f 'I of the offsite power source (s): and

~.

.- (3) The allowable tica diration of a degraded voltage .

. condition at all distribution system levels thall i . .

not result in failure of safety systems or components; i*

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. I* ' d) The voltage monitors shall automatically initiate the disconnection t-

.h'. >..of offsite power sources whenever.the voltage set point and time delay limits have been exceeded;

e). The voltage monitors shall be designed to satisfy the requirements

~~

!i of IEEE Std. 279-1971, " Criteria fcr Protection Systems for Nuclear T ;.- , .. r . - -a.-

r =- ; -?: : -- --

i,2;.j_. ._ u ---::.

-Power Genergting Statibns"; an*d y, ' . .. _.

j, ;, , f) The Technical Specifications shall include limiting conditions for i*

operation,' surveillance requirements, trip set points with minimum-i -

. q' .

. a.nd... maximum ifaits, and alfowable values for the second-level

1 voltage protection eenitors.

M..

y

, .i .

3 : ., General Cesign Criterion 17 (GDC 17) " Electric Power Systems", of Appendix

,' l

' A. " General Design Criteria for Nuclear Power Plants," of 10 CFR Part 50 1 I ~ requires: (a) two physically independent circuits from the offsite trans-

. s mission network (although one of these circui.ts may be a delayed access

3 4 circuit, one circuit must be automatically available within a few seconds

'[ following a loss-of-coolant accident); (b) redundant onsite A.C. power

'n supplies; and (c) redundant D.C. power supplies.

4, GDC-17 further requires that the safety function of each a.c. system (assumin I.

.. the other system is not functioning) shall be to provide sufficient capacity and capability to assure thgt: (a) specified acceptable fuel design limits t and the design conditions for the reactor coolant pressure boundary are

j t

Ihxceeded as a result of ar$ticipated operational occurrences; and (b core 'is coole4 and containment integrity and other vital functions ar.e . .

j ", , maintained during any of the postulated accidents. '

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' Existing undervoltage monitors automatically perform the required func-I ' '

< .' ' ; tion of switching from eoffsite power, ttftr preferred oower source, to the 1

,}. -

_. . redundant onsite power sou?ces when the monitored voltage degrades to a F'

.. level o'f between 50 to 70 percent of the nominal rated safety bus p . - '

This is usually accomplished after a one-half to one second tiefe delly.

t-~

. . These undervoltage eenitors aredesigned to function on a complete loss b ~'

of" ~the offsite power. source. . - .' *

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~ = - "-

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t ~ , * .* .

The offsite power system is the common source which normally sucolies i

power to the redundant safety-related buses. Any transient or sustained

',A 3- *'

degradation of this comon source will be reflected onto'the onsite g- '.

. system's safety-related buses.

~

. e *

,, :: 'A sustained degradation of the offsite oower system's voltage could 1- .s ~

p. . ..

result in the loss of capability of the redundant safety loads, their

[ .l-

' control circuitry, and the associated electrical components required

' ' for perfoming safety functions. -

j{ The operating procedures and guidelines utilized by electric utilities U'

and their interconnected cooperativu oroanizations minimize the aro-e' bability for the above conditions to occur.

" However since deoradation of an offsite power system that could lead to or cause the failure of redundant safety-related electrical equipment is unacceptable, we require l

e

the additional safety margins associated with implementation of tha ~

tl -

protective measures detailed above. .

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2) Position 2: Interaction of Onsite Power Sources with load _

I* '

4:

j Shed Feature i

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U .

lie'requibt that the current system designs automatically prevent '

9 *.

5 1

[l load sh,edding of the emergency buses once the onsite sources arej The

3. ,

sirpplying power to all sequenced loads on the emergency buses.

j l .

,I l

b j

- ? .. design shall also

- - - _ . . . . _ . , . 7- - -

include the capability of the load j she

to be automatically reinstaled if the onsite source-supply breakersI i ! ,

are tripped. The' automatic bypass and reinstatement feature shall be

], . *

' nrified during the periodic festing identified in Position 3. . .. .

[. ~. .

J

-In the event an a'dequate basis can be provided for retaining 'the loa

(-

.* * .shed feature when loads are energized by the onsite power system, we -

.ill require that the setpoint value in the Technical Specifications, ' . .,

I !.

o '.

,w. -

~

.which is currently specified as "... equal to or greater than..." be j"

The l-

amended to specify a value having maximum and minimum limits. !

l s*

licensees' bases for the setpoints and limits. selected must be do

[*

I GDC 17 requires that provisions be included to minimize the probabi c

. 3 of losing electric power from any of the remaining supplies as a resu of or coincident with the loss, of power generated by the~ nuclear pcwer h

,e unit, the loss of power from the transmission network, or the loss u - power from the onsite electric power supplies.

[{ ,

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n. 4* * .

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g 4 L. :, . The functional safety requirement of the " loss-of-offsite power

, ionitors' is to ' detect the loss of voltage on the offsite (preferred) 0

power system and, to initiate the necessary actions required to trans-

. y ,

i, for the safety-related buses to the onsite system. The load shedding.

M, .. )

i, _f.

r _ feature, which is rsquired to . function prior _to _ connecting-t_he o_ns._ite . _

idl ..I power sources to their respective buses can adversely interact with

,' j the onsite power: sources if the load shedding feature is not bypassed y .[. . .. ..

j (. lafser it has perfonned its required function. :The' load shed feature-n- 3 f

g, ,,

,should also be reinstated to allow ittto perfonn its function if the onsite sources are interrupted and are subsequently required to be -

s, !

jp .; t i ..

reconnected to their respective buses. *

.- .* t .

k. * -

i -

3) Position 3: Onsite Power Source Testing s.

We require that the Technical Specifications include a test requirement to demonstrate the full functional operability and inoependence of the

'..[

,}. onsite power sources at lea .. once per 18 months during shutdown. The Technical Specifications shall include a requirement for *asts: (1)

.l' .

simulating loss of offsite power 'in conjunction with a safety injection

, actuation signal; and (2) simulating interruption and subsequent reconnection of onsite power sources to their respective buses. Proper operation shall be de,tennined by: .

-: - 4) Verifying that on loss of offsite powar the emergency bu::es have

+ -

been de-energized and that the loads have been shed from the

., 3 ..

, emergency buses in accordance witti design requirements. .

I

, _ _ . _ _ _ _ , -- _ _ _ ,_ _ _ ~

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b) Yerifying that on loss of offsite power the diesel gener h

, . j .

start from ambient condition on the autostart signal, t .

x>

' buses are energized with permanently connected loa

) '

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~*

onnected emergency loads are energized through the load ' .

3, }, i .

i

sequencer, and the system operates for five minutes I ~ 1 _ _.,

?.. l _._. - l - -

3. . , .- -

,, ,- generators

- , . , ~are~1oa'dedMtitiie .*

emergency loads.- ~. . . . . . - _ _ - -

[ ~~~ ~ , _ c.

j "I . . .

e

c). Verifying that on, interruption of the .onsite sources ~ th f

, a _,

are shed from'*the emergency buses in.accordance with de 1i A r .- '

Q l' ('*-!

i- : requirements and that subsequent loading of th'e onsite sour i- <; : . *

is through the load sequencer.

j l1 , .

E,-

GDC 17 requires that provisions bej included to minim

- , [. ,

j,

.et losing electric power from any of the' remaining supplie 1

ic.;.

,0f or~coidi:ident Mth' thi loss of hwer generated by the n

-

shit, .the loss of power* *from the transmission network, or th ij.b-i .. . . - .

6 Power from the onsite electric power supplies.

\,, * ;.) * .; :. . - 1,

.. . 3. L. ..

The testing requirements identified in Position 3 will deinonstrate

, .the capability of the onsite power system to perform itsrequired .

s, ;

. function.

9 ,, The tests will also identify undesirable interaction 4

a between the offsite and, onsite emergency power systems.

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' .i TABLE 3.3-3 (Continued)- i'

~~

5 N,.3

-~. *2

. ;.) -! i -

..: ENGINEERED! SAFETY FEATURE ACTUATION' SYSTEM4 amsuntwiATION

- ~ *. . t.,..

:; * .5 ~.- -

., '1 {- ,,

t ?

MININUM "

. i;( .

.- TOTAL it0. : THANNELS f , . ./. 's FtNCTIONAL UNIT - *

CilANNELS

,, 0F CHANNELS

iAPP(ICA8LE 1 .'t 'E' LOSS OF POWER

TOTRIPi. a.

WERABLE'

. DP'ERATING MDDES** ACTI0ll*** . - E i.E

'I : * * .,

a. 4.16 kv Emergency Bus O

Undervoltage (Loss of

. r !

cVoltage) '

b 4(3)/ Bus 2/8us 3(2)/8us 1. 2. 3 A or a. . .k< l

b. 4.16 kv Emergency Bus .

m lc -

Undervoltage (Degraded , .

, Voltage) .. ' ~. .

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k*.1 4(3)/ Bus 2/ Bus 3(2)/8us . [1,2.3

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09 n'

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(Entries in parenthesis are applicable for

u.

2 out of 3 coincidence logic) .O **F.i'

!* J 1-

- Required when ESF equipment is ~

- required to be operable .

- k y O* Action A for 2 out of 4 logic .

' 1 'i. y]; - -

O -l Action B for 2 out of 3 logic ~

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. TABLE 3.3 3 (Continued)

s i-s .. .: .

. I. .

ACTION STATEMENTS *

' ~?.. *

' . . . ACTION A

- With the number of OPERABLE channels one less than the t E - Total Number of Channels operation may proceed provided

.. - both of the following conditions are satisfied:

i -

I '

! ; a. The inoperable channel is placed in the tripped

.s , - .

-i condition within one hour. - l H tr Z--

-.=e- -

'- " - " '~~ "

~ ~ L ..

. . i 6.-The Minimum Channelt 0FERABLE requirement 1s

~

T"

- T; ' t .

. S, net; however, one additional channe) may be

. 1 bypassed for up 'to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance

< . testing per Specification (4.3.2.1.1).

?. *;.-

e n T' ACTION 8

.4 -

? - With the number of OPERABLE Channels one less tien the

. i. C. - ' Total Number of Channels operation may proceed until l.

performance of the next required CHANNEL FUNCTIONAL

'* .. ,, 1 - --

TEST provided the inoperable channel is placed in the

.. 5 -

tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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.2 TRIP )Miw .Ui'

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FUNCTIONAL UNIT TRIP W -

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VALUES ---

LOSS OF POWER -J -

a.

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' . .c ELECTRICAL PCWER SYSTEMS

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J- SURVEILLANCE REtVIREMENTS 4.8.1.1.X Each diesel generator s' hall 'be hi.rsted OPERABLE:

a. At least once per 18 sonths during shutdown by:

4 >- 8 1 1. Simulating a loss of offsite power in conjunction with a safety injection actunden test signal, and:

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and i pad shedding from the energency busses.da of W mm h ~

c. g- p * - - 3 ,

b) Verifying the diesel starts from ar:6fent condition s -

i l:i en the auto-start signal, energizes the emergency 7,

j-

. liesses with peranently connected loads, energizes

.the auto-connected emergency loads through the load

sequencer and operates for > 5 minutas while its

!.p .

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gamerator is loaded with the emergency loads.

~

n p ..- c) Verifying that on diesel ger:erator trip, the loads 3 ,

- are shed fica the emergency usses and the diesel.

.- is loaded with the en_e,5 minutes rgency loads.while its generator *

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15. NRC Ouestion Clarify tie breaker operation as described in SRP 8.3.1,Section III.2.b.
e 's
[ District Resoonse The maintenance tie is at the 480 volt level between i. Bus switchgear 3A and'A2 Bus load center 3A2. On the B train the maintenance tie is
, correspondingly between the 480 volt Bus 3B and the 82 Bus 382.
ri F The interlocks between the tie breakers and the main feeder breakers are totally at the 480 volt level. The second paragraph under " System Design" should read "These ties can only be closed manually when the final configuration is completed. Additionally,.each tie breaker can only be closed if at least one of the main feeder breakers to-the 480 volt buses are open."
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-16. NRC Ourstion Justify any non-compliance with Regulatory Guide l.75. :(See SRP 8.3.1, ']
Section-III.2.c). -l
-District Response .
LI . . . 'l m.;r The District will provide a response by May 11, 1987.
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17.iNRC Ouestien Discuss Technical Specification surveillance requirements when startup transformer is out of service.
District ResDonse The asterisk on Proposed Technical Specification 4.6.3.A has been revised
~to state " Surveillance shall not be performed when a diesel generator train or startup transformer is not operable in accordance with TS 3.7.2." This revision will limit diesel generator train testing when.there is an inoperable startup transformer, and ensure-that the diesel generator trains are available if a loss-of-offsite power were to occur. This revision addresses the-NRC concern in IE Information Notice 84-69, Supplement I, " Operation of Emergency' Diesel Generators" of operating a diesel generator (s) train paralleled to the grid when the other train is inoperable.
1'8. NRC Outstien Discuss the restoration of offsite power following the loss of offsite power.
District Response Essentially, the return to offsite power would be the reverse of paralleling the diesel generator to the offsite supply. Both the diesel generator breaker and the normal supply breaker (not the alternate) will have sync-check relays installed (ECN R-0415) prior to restart.
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'19. NRC Outstirn-Provide a statement as to the fact that there are no changes to the 220 KV
. system.
District Response No changes to the offsite power system (220 KV-system) are being made under this proposed technical specification. 'The responses in Enclosure-6, SRP 8.31, III.3., relative to our 220 KV system, are descriptions of our. existing plant and were provided for completeness of review.
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20. NRC Ouistien Discuss vibration of diesel generator. Instrumentation.
District Response Two panels with pressure gauges for jacket water, lube oil, and fuel oil are mounted on the engine or the auxiliary skids. These gauges have no control function and provide only local indication. The engine control panel, which is used for local control and monitoring, is free-standing and floor-mounted in a separate control room. This provides substantial vibration isolation. .Further, actual vibration readings were recorded during initial pre-operational testing and were found to be very low, almost unmeasurable.
221. NRC Oesstirn
~ Discuss fresh air intakes ~ relative to NUREG/CR-0660.
District ResDonse The diesel building for.these engines has five fresh' air intakes which provide the following primary functions: ' engine combustion air, engine
. room and mezzanine ventilation, and engine control room ventilation.
Engine combustion air is filtered and obtained through a' dedicated pipe
. and intake louver which is.11 ft. 6 in, above ground level. The immediate area is paved with asphalt and surrounded by a masonry wall 17 ft. 8 in.:
-high. The low 1 height of the louvers is required to avoid exceeding 125 degrees F for combustion air, since .the intake louver is in the vicinity of the discharge of the radiator cooling fan discharge (at a height of-17 ft. 7 in.). The surrounding masonry well provides protection to the intake from wind-blown dust at.this lower elevation.
Engine room ventilation is provided from two louvers,-one-large one located at grade level, and another for mezannine equipment-located 21.ft.
above grade level, and also from the air. exhausted from the engine control room. The surrounding area under both louvers is paved with asphalt.
Engine control room ventilation is provided by a dedicated, filtered intake which is 19 ft. 6 in. above grade level. The surrounding area is also paved with asphalt.
The diesel building stands alone and is ' separate from other plant ~
buildings. All fresh air intakes are located on the walls of the diesel
, building, and the ventilation discharge is located on the roof at about-1: 40 ft.'above grade. Engine exhaust gases are even higher, discharging at j 54 ft. 4 in. above grade level. This arrangement greatly reduces the chances of circulating hot cooling air or exhaust gases into the plant.
buildings.
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22. NRC Questi*n-Discuss compliance with SRP Section 9.5.2, Lighting and SRP 9.5.3, Comm'Jnications .
District Response Additional emergency battery pack lights will be added prior to restart to support an Appendix R event. These battery pack lights are seismically-supported, but are not, the type which have been vendor seismically-qualified to IEEE 344. This lighting on the engine and generator control panels would be ' locally switched on by operator action, as required.
Sound power phone jacks have been added in each diesel generator building control room and engine room, and are connected to the control room.
23. NRC'Ouistitn Discuss method for keeping sediment out of diesel generators during long runs which require fuel oil storage tank refill.
District Response The suction line for the fuel oil transfer pumps is located about 9 ft.
from the discharge of the fill line. When the 12 ft. diameter tank is nearly full and is being topped off, the sediment will not be stirred up significantly. If the tank needs substantial fuel oil while the associated
. engine is operating, the cross-connect' piping may be aligned to use the storage tank-of the other engine while fuel oil is being added to the tank with a low level, thus minimizing the amount of sediment which could be passed to an operating engine. The operation of cross-connected configuration and an appropriate limitation on operation in this configuration will be addressed in procedure A.02B, Section 3.5 prior to restart from the present outage.
24. NRC Ounstirn Provide a statement as to the' fact that at' low level alarm in the
" day tank" we have one hour worth of fuel left in the " day tank."
District Response
The low level alarm in each " day tank" is set at 39 in. above the bottom of the tank. This corresponds to about 39 cu. ft. of fuel oil. Reducing this by 10% for an extra margin gives 36 cu. ft. . At a load of 3500 KW, the engine consumes approximately 33 cu. ft. of fuel oil each hour. With these considerations, the engine will operate for at least 65 minutes after receiving the day tank _ low-level alarm. As a result of NUREG-1216 on the TDI Owners Group Program, the maximum engine load _will be limited
'~
to 3300 KW, thus prolonging this operating time to an estimated 70 minutes, j
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25. NRC Ourstien Discuss-tornado missile-protection for fill and vent line of the fuel oil storage tanks.
District Response
.The fuel oil storage tank fill lines are protected from tornado missiles because they are not exposed. Each fill line connection is located below a cast iron manhole cover plate which is. embedded in the top of the concrete vault for each fuel pil storage tank.
The vent lines for the storage tanks are located oat ground level just above the storage' tanks. Although they are not designed to withstand tornado missiles, another path exists to vent *the storage tanks. The overflow line for the day tank connects to the storage tank without intervening valves; the vent for the day tank can also vent the storage tanks through the overflow line, and vice versa. The vent for the day tank is on the roof of the diesel building at an elevation of about 37 ft.
It is not plausible that both of these vent paths will become plugged and thereby preclude proper engine operation.
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26. NRC Ouestien What,is the margin 'in the radiator fan design and how long can' the diesel
~
generators operate without the fans' operating?
District Response The radiator assembly is designed to handle a-heat load of about'12 million BTUs/hr, and the diesel engines give off about 10 million BTUs/hr at 3850 KW (110%'of nameplate rating). This gives a calculated design-surgin of about 19%. As a result of NUREG-1216 on the TDI Owners Group Program, the maximum engine. load will be-limited to 3300 KW, which will
. provide even more margin in the cooling capacity of the radiator.- The
! actual margin of the radiator-system will be determined during pre-operational testing.
The radiator fans are not thermostatically controlled. When the engines are running, the fans also run (except that~a loss of offsite power will delay fan turn-on for 35 seconds). Each fan has an individual circuit breaker for protection. The engine has been operated for two hours at 3500 kw during a cooler-day without the benefit of five fans. Therefore, assuming that the pre-operational performance test confirms the amount of design margin, the loss of a single fan does not pose a-significant
-degradation to the cooling capacity of the radiator.
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27. NRC Ouistirn Discuss the methods to prevent foreign material getting into the lube oil system.
District Response Because the lube oil system is a closed system for this engine design, there are no exposed areas for contamination of the , lube oil. The sump tank fill connection has a threaded cap to maintain system cleanliness.
Further, because of minor blowby past the piston rings, the engine crankcase has a very : light positive pressure. This positive pressure also prevents the entry of foreign material into the lube oil, system.
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28. NRC Ouistien ~
j Discuss how the lube oil level could be checked during loss-of-offsite '
power.
l District Response- i The level in the lube oil sump can be checked.in two ways, both of which-are independent of electrical power. One is to use the local sump dipstick, the other is to use a pneumatic level gauge from the engine-control panel. Although there is no emergency lighting in the engine room, the dipstick is readily accessible and may be read with a flashlight. The engine control panel will be illuminated with emergency lighting, thus making it easier to determine the sump level from-the ,
engine control room.
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29. NRC Ou7stion Discuss recommended vendor modification to lube oil system to provide full pressure lube to-turbocharger on-startup. Also clarify submittal as,to what part of engine is prelubed.
District Response The District has_ implemented the vendor recommended modifications for turbocharger-bearing-lubrication, including both drip lubrication during standby conditions and the use of a bypass valve to provide full flow from the keepwarm lube oil pump just prior to and during engine starts.
1 The prelube or keepwarm lube oil pump-supplies oil to the main engine oil header, permitting almost all of :the engine to be warmed and lubricated via the normal lubrication flow path. The-only exceptions are the-
. turbocharger bearings (described above) and the rocker arms (which receive lubrication only during actual engine operation to minimize leakage into the piston combustion area).
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30. NRC Ouestion
. Provide additional justification for the equipnent ' inoperable time allowed by proposed Technical Specification 3.27, " Nuclear Service Electrical Building Heating, Ventilation and Air Conditioning System".
District Response The NSEB HVAC system is a Class 1 emergency redundant system that is.
actuated by a high-temperature signal with loss of power supply to the normal'NSEB HVAC system. The normal NSEB HVAC system is a class 2 system which provides temperature control and it would be available except during any conditions that would result in its loss of its power supply. The normal and emergency NSEB HVAC systems are each thm train systems.
This arrangement of a normal system with a Class 1 emergency redundant system is analogous to the normal and emergency Control Room /TSC Filtering System. Technical Specification 3.13 on the emergency Control Room /TSC Filtering system was the basis for the equipment inoperable times for the NSEB HVAC system.
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ENCLOSURE.ll CIVIL ENGINEERING OUESTIONS
. l. NRC Question Why are the allowable soil bearing values different from values listed in FSAR7 District Response The Diesel Generator Building (DGB) is over two hundred feet from the original plant, at this location, the FSAR values would not have been applicable.'Thus, a foundation investigation.was performed by Bechtel in-1981 to establish allowable bearing pressures. The differences in allowables are due to different soils (e.g., differences in location and
! depth). A reference to the foundation report will be included in the DBR. In the next revision of the USAR, the DG8 soil bearing allowables will be included.
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2. NRC Ouistion In the' seismic design using the factor method, are only'two components 4
used?
District ResDonse )
No. The component factor method .uses 3 components.
The factors are 1.0, 0.4, and 0.4. The factor 1.0 is applied to the highest component. In calculation Z-DG8-C0122, the components factor method was used in the
-static seismic analysis for shear wall designs. In the shear wall design of the building, the three directional earthquake forces were. considered.
The three components (directions) are accounted for by all walls. Each wall was loaded with a vertical component and a horizontal component in the direction parallel with the wall. In summary, each wall will resist two directions and the building.will resist all three directions.
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3. ;NRC Outstion What is the basis for using 15% damping for cable tray?
District Resoonse ' ' '
The FSAR (attached) allows the use of 10-15% damping for bolted steel at SSE. ANCO Engineering : Testing supports 15% damping for cable trays. The 4
testing parameters and (DG8) cable tray conditions are equivalent. The cable tray was designed by Bechtel using Bechtel's Design Guide 2.7. ANCO Engineer's Test results provide a basis for this design guide.
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SACRAMENTO MUNICIPAL UTILITY DISTRICT R A' CHO S'!CD 5U0_iAR G'it ERA" f G S"A" Di Ut " N0.~
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. ) A. SA!E"Y A! A_YS S RE)0R" 1
Vo ume V :
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Percent Critical Da: ping- L A-Stress Le'rel f Type and Condition I' Percentare of'
] of Structure Critical 5amping
'f
.1. i.ow, well below a. 'lical piping, sys- 0.5 proportional limit, teme-or equipment
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stresses below 1/a b. *ielded structural 0.5 to 1.1 yield point steel, reinforced I or prestressed con-crete, nc cracking, F i
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no join't slip ,
2. Working-stress, no l a. Vital piping, sy's- 0.5 to 1.0 more than about 1/2 cens or ac,uipment. l10 l yield point b. tJelded structural- !
steel, prestressed- ,
t
, concrete, well rain- 1 l forced concrete . !
1 (only slight cracking) '
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c. Reinforced concrete. I to 3
, with considerable ;
cracking i
d. -Bolted and/or. riveted' 3 to 7- j10 steel I
3. At or just below a. Vital piping, -
0.5 to 2.0 yield point }10 syscens,_ or equipment
b. { {
Welded structural : 5' i i
steel, prestressed I concrete (without Complete loss in
. prestress) .
c. Prestressed concrete 7.
e
' with no prestress left
d. Peinforced concrete 7 to 10 -
e. Bolted and/or riveted 10 to 15 i steel i 4 Varies a. Rocking of entire :
5 (0BE); 9 (DBE) structure
b. Translation of entire l . -
i 30 (OSE and DBE) s c ruc t,ure .
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4. NRC Ou stion What DG8 components can resist a 175 mph wind and missiles?
District ResDonse The Diesel Generator Building, radiator walls, building. louvers, exhaust silencers, and all perimeter building / radiator wall exterior doors'can resist a 175 mph wind and missiles. The doors will be modified to meet this criterion before restart. The DBR will be revised to reflect this modification.
The design missiles are already included in the DBR. The remaining questions on the Probablistic Risk Assessment (PRA) on vertical missiles hitting the diesel generator radiators will be resolved prior to restart from the next refueling outage, or appropriate design modifications will be implemented.
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5. NRC Ouestion
-Were.the Cooling Towers considered in the DG8 missile population (similar towers have collapsed in England due to high winds)?
District Response- ;
No. The Rancho Seco Towers are thicker and have more reinforcement than the English towers (FSAR-Section 5.5.3, Cooling Towers). Further, our towers were designed for a 150 mph wind (i.e., based upon a shape of factor 0.5.) Considering the towers design features and the fact that'the j debris from the England collapse fell almost exclusively within the pond '
area, the potential cooling tower missiles were not included in the PRA of the DGB.
In addition, the towers are on the opposite side of the plant site ;
approximately 700 feet from the DGB.
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ENCLOSURE 12 FIRE PROTECTION 00ESTIONS
1. NRC Question Page 15 of the submittal commits to 10CFR50 Appendix R. Is it the District's intent to commit to all of 10CFR50 Appendix R or perhaps to 10CFR50 Appendix A and Appendix R, Sections III. G, J and 0? The District should review and make a clarification.
District Response The Design Basis Report for ECN A-3748 states that the fire protection system shall meet the requirements of 10CFR50 Appendix R. This statement applies only to the new Diesel Generator Building and does not represent an overall plant commitment to 10CFR50, Appendix R. The District's commitments for Rancho Seco regarding 10CFR50 Appendix R have been previously addressed in the District's response to Generic Letter 81-12 and the 1985 Rancho Seco fire Hazards Analysis Report. (i.e., the District complies with 10 CFR 50 Appendix R Sections III.G, J, L, and 0).
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2. NRC Ouestion Are the fire alarm detection circuits.from the local control panel to the
-deluge valve supervised? If so, how.
District Response ECN R-0767 is upgrading the fire alarm panel in the Diesel Generator Building. The fire alarm circuits to the deluge valve will be supervised by the Pyrotronics RM300 releasing device module. A trouble signal is transmitted to show an open circuit when the system is not in alarm.
l Additionally, all wiring is monitored by the panel for ground faults, i
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3. NRC Outstion-
"Are emergency lights required in the diesel generator building for any
~
safe shutdown operator actions?
District Response Emergency lighting in the new Diesel Generator Building.is required for.
safe shutdown operator actions, and will be installed prior to restart.
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4. NRC Ouistien The submittal identifies.several components which are UL listed. Those .
identified do not include the local alarm panel. Make a statement .
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regarding the panel listing. & v(
District Response following completion of-ECN R-0767, the fire alarm panel will consist of' Pyrotronics System 3 modules mounted inside a NEMA 12 enclosure. The Pyrotronics System 3 configuration is listed by Underwriters Laboratories',
Inc. as a control panel for NFPA 72A, 72B, 72C and 720 applications.
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5. NRE-Question f
iTwo. separate underground tunnels provide train A/ train 8 separation
!c. between the diesel generator building and the NSEB. Provide a-brief description of the electrical ties in the NSEB to verify Appendix R separation is maintained.
District Response Train A/ train 8 separation is maintained throughout the NSEB for all safe shutdown' circuitry related to the new diesel generators. As described in the Updated fire Hazards Analysis for Rancho Seco, Revision 2, September 1985, the NSEB complies with 10CFR50 Appendix R, Sections III. G, J. L, and O. This compliance.is maintained.with the new diesel generator circuitry.
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6. NRC Ouestion ,
~
Has the District verified that the unprotected structural steel support'ing floors and roof will retain its integrity during a fire so as not to compromise fire barriers?
District Response The diesel generator building floors and roof will retain their structural integrity during a fire. The reinforced concrete floors and roof are ,
designed to be structurally adequate without consideration of the steel beams. The beams functioned as falsework supports'during construction and >
have been left in place for piping / mechanical equipment supports, failure' of the beams will not affect the integrity of..the reinforced concrete.
floor or roof slabs. ,
i A copy of the design calculations for the teinforced concrete slabs (SMUD Calc No. Z-DGB-C0126) and structural steel ( M)D Calc No. Z-DG8-C0128) are attached.
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.O' g1SMUD RANCH SECO NUCLEAR GENERATING STATION
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v CALCULATION SHEET LAO M23 &P3 CALC. NO.- i ' As-s x -.\
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. SIGNATURE ,' " -
DATE '
'b A
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' ' ) M - # '# - ./
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JOB NO. -
SUBJECT ' '~ " * ' # -
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88.9 2
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CALCULATION SHEET* " ""'"
CALC. NO- C 66-6_
SIGNATURE - e*w ~w- ,'
DATE 7 23.// ~
CHECKED DATE I
% PROJECT R A AIC140 . SERO A/UCLF iP STA T IO V JOB NO. ' 2 5 3 d-69 SUBJECT diECl GE VC E.FCD 3'd G ~~
et m o S_u SHEET _ OF - 5O SHEETS E L. (Cr 19 '-6 ' /-)5"-6' 1
3
=REOuEHcY =uMCTIon/ =OR S LA.LG 4
5 Jj,y DidrAt. factors bs;4 s f/of A/o./.
6 8/o/ A/o.2
.X. b X3 XM -
7 7
g];3 1 1 1 l s o. 5 3 8. f 4
ic .
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0- 1 O I 28.6 52.2 u
,h5 -
t o i o 18.3. 27 0
'a' z
' .L JP o n t i s2s is 4 _
' 35~t 19 C3 o o o o 15 3 2o.4 2i 4 22 2 l 2'
24
'C3 4 o 1 i o 22. g . 29:3 25 i
1 itssumc. i.derydahon funchow f l
k in relo tids exiny Jeyees of sM.s (a'istn&dion for freguehef) roefor. 't x,a x 4x _
.hbe: polinomial cf secod.. onfer; F= A, (x * + sx -) +- Az (x2 +x]) + As (xi xs +-x, N.:'-xx xs +x,'<)
i
} -
1-A4 xzq + Ag x, g, + 4g - =/sr- . s / 6 / ~A to. /
~
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j L F2 = e GP+x., i ) +- &fc*+ z 9*)+85G i&+M x2+x x + 4%) +
z2 ..
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i
" CALCULATION SHEET '
CAL.C. NO '~ ' $$' f~ 8 br/- W 'b DATE -
SIGNATURE DATE 7 2 3. R / CHECKED Cf(O A/U Cf_E 4 R S . m o Af JOB NO- ' E 3 3 d -69
% PROJECT RJMC46
.. DI S* I- QEMEF M E 6LDG SHEET /2 OF SO SHEETS SUBJECT )
fnp SLAn L. ( 4 t Fs'- G ' iM 3 4 '-6 "
'1
= fpsoueucy .=uncriON COR W L5 (caV7) 3 l 4
+S +- 8 g x,x,+Sg for slal Mo.2 4 x, y, s
6 roe de r'erm11, . y coe ffici eds A. , , ,oJ Son dory cencli fion s IO 2s, --2 Az = 4 A ., % + Ag + Af5 0.5 G) 12 .
2. Q + h, -- As = 2 8. 6 %
2Ap Ag +- A s = I8,3 (s)
Q ln A, +2A2.'2 Az + A 4 +Ag= 2 5? 6 (4)
'= . ._ .
~
2a A,=IE3 (s) '
Ag+ A , +A2.+A3 = 22 G @)
22 23 (0-(s) + 2A +443 2 + Aa = TD,5 - 18.3 - 12, Z (7) 2s
= 27; 6- 2 6, 6 = - I . I
+[7)-(2.)t(6)->44 3 27 2.
A3 = -O. 275 (8)
(4)-(2) -b(8) + A 3 ss =1 ,
31 A = 1.55-3 (9)
_ v" -
~
(6} --(9)h(8) (spa 2 = 22. 4 - 1. 55 " . 275-ME5.=S.025 Oo)
, 36 -
~ ~ "
" CALCULATION SHEET .a v cac. no C- 659-8 SIGNATURE #""~ e "NI" DATE 23 # / CHECKED b DATE
~
C
, PROJECT R :.vc o aE-O Muc L=$ T AT'o V JoS NO. M -'
D EEEL GENE RArop_ PA'O C. SHEET -m op IJ SHEETS SUBJECT '
C2 6 'A E N t 8'P . - . p '% ,,
1 2 = R c Q U E.Al c y FU MCT-tom TOR ELAES (C.OMT.)
3 5
nou (2)-(5) - zx(ne) ---
s
,4, = z.s. c - is. s -z-c.o25 = I. 25' OD (3) s (5 ) (9) =yA l a. s I. 55- i s. 3 = - o . I C2).
9 to o == I
\.ss 61+g) +e.o25(>q+xi-)-o.zrs(x.%"x,x2 +xzax %%)+:1.25xN i2
- o.I y x + 1s.a -
=4 u_4 r=, .%. i
,, I3 (w G;m ilo r-w/o.f Ot- sl N o . 2.
32."
(7)
=
9:5 -
/
= o. 57 5 (B) = 4 83 = 25 + 2o.4 - 52. d = - 2. S 63 2a (9) = 25'I - 3 2,2 (- o. s7s) = .6, = 4.0 s- .
(io) = B2 = 29. 3 - (-o. 575) - 4 o=20 4 = 5,425 2'
21 On) = % = 32.z-20.4 -2<5:425: = O. 95~
2' (vz? = z v.o- 2o.4 - 2< 4.os - o. s-By.
28 29
F1- 4.os (x,*'+x,2-) + 5415-(xa. ' %*) - 0.575 (x,x +w+-x
. a x,+x 2 a x}
31
+ O.9 5 X2 Xq t o.5p,x3 +20.4 -
% s.LAs no.z.
a, _ . ___ _
-34 ,
35
~7 36 ,
I
OW CALCULATION SHEET v ~'" !
CAtc. No C 459- 8
. SIGNATURE Nv& r- *: > DATE 7' bN CHECKED ##~ DATE >
SECO c'^ NLf C L EM $~.iTi O M 2 39- 6 $7
- PROJECT DC@ JOB NO.
CEHEPt CR E- D G SHEET O OF 1 ' SHEETS SUBJECT DIESEL e, . < ->; w --.5 neat s, u . - : w - e i I
i !
'SLASS NA TURM FREQUENC/ Es \
i FOR. SPEC /F/C &OUM.D 4R Y COMD/770 C ;
5 6
Mezon :u slab
X2. X,= 0.603 1
'o 1 Xz=c.23 B See. p.p.
y3 5 o_5 X, = OA44 C 6 59-8 2 x, 4 , g, f 73 Y,'
S id. N o. 2.
is y
~
is 16 g 34 -
l 17 g n^
1s . ,, , ,
Q: 405 (,6o3*+- o ,W* ) +-54 9 fo.23g
60.192'#-) -o. STS[o. 6o3 = c.t 92 21
" o.6 0'S - C 2 6 g 0. 2 5 8 - o. e4
+ o .M.4 " o.19 2. )
22
" ~
24
+ 0. 99xo.za8 " o.192 " o.s 0. 60,3- o.4% + zo,4 = 2 5.1 -cps
F= 2.5, \
g._ c.ps ~~
5%.all 'ns.e.2 2 A Ns 4 ' s u s.
25 . l 2s Big v
roch slo o ,
)
l I 1 Az ,
X,.= o.357 !
" " l z = 0,568.
-- X Se a.
,3. p i 30.E x S= 0. 825. - C 659-8 '
32 y' M3 X4
O.556~ .
l
-~ ~
v Slg N o. {
3a -
. y, a 51 _
M I
. ~ . . . . . .
" CALCULATION SHEET v
%.s CALC.no C W '-*
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DATE 21 W CHECKED DATE SIGNATURE c < 6 6ECO MllC LE AR STATION JOB NO. IU
~
PROJECT E AA/C#C SG EM b b LM SHEET T OF SC SHEETS SUBJECT Y E S EI- '-T9'-6" FL TR S LA S EL. ' *1 16 '- 6 "
1 SLM NATURAL. FR EO L!ENCIEs Fot. SPECIPIC SouMDARY CO C I" OA!3 3
(coMT.)
4 f,- 1.55(a 3S7' ' O. e23*) +G O.29(0. ase* + o.556') - 0.2'5'lo. 557 6
+ 0. 556 + c.3sa < 0. 823 - a ss7- O. 35e?" o.823.< o. SSS) --
8
-/,2 & a bs's < a SSG - c./ - o..ss 7- cs.223 + I5.3 10
"
P= l 9. 4 cp s -
Si o slo / (cv E2.. / W - G
12 .
' 5 LAB ROOF SMALL 1$
15 x=
. ~
.J x = 0. 661
y = 0,37/
" xs x, in x3=.0,525
'* e x4 = a z7/
Y x, Sla d. M. 2.
21
" 34 23 24 a
F =40s-fo. 664 *+ o.52s* ) .~ +.6T423(a 37t *
o. ' 7! 0 -- 0. 675 fb GM O. 664' o S7/ a a 57/ s0.525+ 0.525> Q 27/) + 0. 9 6?* a 3 7/ o. 27/ +
=
+0.5x 0. 664 x j~26~+ 20. 4J '
30
F= 2 4. & cfoS
- s.mo// s/a A @ El. / 9 9 '- 6 "
33 _
a . _ _ -
3 35
~ " ~ '
^ CALCULATION SHEET CALC. NOS 6 E'O I W' ! CHECKED I+*^ DATE
'~ b!
SIGNATURE -
DATE \
< C SECO A/UCLEAR .5 7A Tt C tl JOB NO. I2334~ 5 \
m PROJECT W?O GENMATOP SL.D6 -FLOOTSHEET N OF 5'I SHEETS .
SUBJECT _.D/ESEL l GL)-@ @ EL f4) 18 '-& '~ . /*r 34 '- 6 "
l 1 b 2 cceu r"o site stAa oeste M 1 0
' Comp. slab seebn E n u a l. 4 scb S h :n $bss I I h A
h - '-
o3 o , *A o' 'o s- . -_~'.
f s
- . s! D I! ,
c O -
N. AXl$
y g s ,
/
v r o
~ w !2cS" o ; .. , c -7 ,1 g . - . -
'y . f; h -As 38 855"
,vAs- ,
R53 ll
=
{
u.7,-
q ' 'v 27-84 T=A3 }3 ;
io o j l 31 .
'* (Ref. - 3.N. cern:co , ;=a..d<wesal s L=68" d kinkred comrdg p. s 3f
, p 15 O Locab ct N. A. : k=y in,p r(n.pf - n, o E s_ 2 9-1o6 Ps - 2 9xto h =B,06
.where, n'=_c s r
o 57, oco- g4;p 57 coo p,=o p=rcho o{- sfee( o effe.cti%. are a of c.oncrede_
Es - deel m odw(as, i i
n 5
24 Ec- concrde mockig (AC.l 318-77, B.5.l)
A3- (24.8)'5 9. In _a 2s - 3= = = Z 3 66_-10
= 64 (68)"(s 8. ass)" .
A s = 2 4. 8 sp.in sleel secfion area l fa
^
c{ ~ L ' - distance & ky of. coere '-
C. G.
of s$eef .sec fion 31 d = 2 5's + *" = s s. es's~ "
O=
. k=\ 2x 8. 0 6M 58& Io + (8. 06- Sl?3 es ter') c. 06 nu.to~' l
'5 l 1
m
k = 0.3206 _
___.ue,_
^ so.
. CALCULATION SHEET -
CALC.NO C b E N-#
' DATE OO
"' # 8' CHECKED b TE SIGNATUREhh r.
4 ANC/40' $EC A/L!C '_ = i # 37.'!? JOB NO. I
~
O PROJECT SE A/EP 90 *iD6 2 $O SHEETS SUBJECT O/58Eb SHEET OF cz. cop Sz j. : gi f.tu -+*: .2e 54 -f "
5 Ce vn c,o s,Me s LAs, DESIG N ,#ces :-)
2 k d =_ 0.s2 06x3 e.ess = Jz.45 "'
8 /
Consbruc/ ion sba 9 e /caifs t'opplieal bel ore coticrole reo.ch isty 75 % Sf-r.e n o M), xsf (Sce DL1/sn a7?f';
~
s
' w' (see A/SC ff. 5-57)
4er SL A-8 .340 STL D ECKi AiG ,005 "Y '
,O/5 *A BEAM W E/ C//7' ) {* n ,", $'i) i.~
COA /57;9dCT LOADS . 050 y 1
x,-y
~
12 L A ,
' 0.4/O KSP j
.O ! TOT 4t -
u Wg = 0. 41 '(.o~ Ys j ' = 2 . 32 ><fi'T lmb an plied elSer- en n ar-e le. A4 /~ea c!el 75ll S/r'
( df.-) ,- - -
y 1)f=J .a L 04D(esf) E !. . ! ? P '- 6 " E! 183Q' l 2o
< E Oll/P& FEN T c . coSc o. c 75 Y NVACjP/FE '$C4.6LE TRAYS o. Os'C o,!Oo LEAW COA / CRETE 6 " lbck 0, 0 5'3 '
" .eootkG q' R jys. O . 00-G n
.DL! TO7 4 L. C. /Sf C,/75 27 w,'=
o , /57- (5 'f = a foxe r ca et. ix!4" wl = irs- (5 *,
. = 0. 97 > .t a e e t.183 '-6 "
2 G 33 24 36 35
-7 sm,
1 ~ ~ ' ' "
CALCULATION SHEET cgg no C G59~8 '
N" DATE #3 8# CHECKE / TE SIGNATURE .-p.
UCLE/P 5 7 2. 7 /0 6/ 3og na, i2 2 ~' -- 657
.-. PROJECT R A-A/C)J O ShC O SL 3 C N OF $O SHEETS SUBJECT &5SSI G E W M c P. SHEET FLOOR 2 AE ' -
I?" '- 6 '--6
1' 2
Coptpcsi7z- GLAS MS/Giv /Eo.vr)
'* EL. 17 P'- 6 " ' _ht . /g3 '-6 "
L/VC- L.OA-D (L L) O.O3/ O./25 SEISkt. VEnr0B E - a '8 (ot. + oL'+a 25 LL) O./04 0. t//
7 ei . t r 7<G "; __ 6 ==. /O s a o 2/ + o. to; =O,294 xse 9
~
L /75 + o 125 +- c. tit =-o. 4 // xsr E . ia3'-t ';
11
' ' EL. lif '-b ' , eW = , 2 94xf f)' == l. K k ! i= _
EL . 18 S'-C "; W 9,gjjx(5Kf=2,.23 lc L i= '
d'* 17 Maximum ~/cenc/iag <nomenh y
/V/, = 2.52 -(555)'/8 = 306.3x-Fr
x-Fr EL. 19 9'-6 " i Mt = /. 666 {52. 5~}
5 = 22 0 21 EL. 183'-6 hfL = ,33 c (52. 5 g = 30ZG k-iT .
y
M.
22 0 i
= O, 7Z @ SL, / W--6 " -
y ggg5
Mc = z ou =. I, o .o @ EL. /8 W-6,
=
pg Mmax = Mt e Al n = 306.3+- 2zo = 52G' 3 u -# 7 eet.ier's*
m ~
M.mg = 3 ozg+ 3 c&s * #rg.7 w-vr y st_. ie3'-s "
M .
- _. CALCULATION SHEET cat.c. no C GS F- 8 WNb DATE 8 03- CHECKED N E ?- / 5 -B/
- SIGNATURE .k'[' #e
, PROJECT . W M~ u'? Sbc0 <k'~ ' EH 3 --A- o.< < ,ogno,:2 p s- 4:~
DIEEEL GE/EP MOA S ! .D G SHEET Y OF SA SHEETS sus 3EcT "
Cf.CnP ._ / J.- 8 =.'. . (4 } ! 8'-E " = / f 's.5 4 '-h "
COMPOGITE E! As DES /CN l' CONT;)
~2 Effc.c/We- sfa b W/id lb a
6 =(V)~ 4 L s b, = Q '(32. 6^),= s?. / 2E = 97. 5~ "
s 6=
7 W h . l} R [ == (h -
Q lf.2 ff7 &
6 = /G f rf b = 16' (255)~ "+ ??P& =(4/7 94)'
Rec urred' sechon in o clu li. fr M .-
13
" I f c R E L I,0 9 - 6 :
5',;; = Iz-,_52a.3= g,y 263. Ifin '
3
.ccat a t.. /83'-6 ": Sig = i2-es.9A4 - 5c6. 95in
,'l l
% =-(f. 55+. ss~ Af. ,/4) SS ; Sg = 2i3 in *
in 3
u.199'-s' : 5~f ==
," EL I83'-6"; & = [(i.35'+
/. 5 5 "-o. 35 </, c.isto.7z)-2ta go) 2/5 '
362 in ' = 34I Aeb.<af fran sforme/ sucfion <noinen f of inerita- in ferrn s s,L slee/ pro,cerfie c :
(
zn = rs
As (rs -i~)* + Erc + A (n-7)*h wAcre Ic ' Ac -
ina- f a f iner/ia- a s d' area-
~
of co.nrpresS,or,-a b4 orfion af concif'e res'l_ 7/k, = /1/s.cs.-
.n =t.cfive 1;, As
/
~ W shel W si
= 52,21 - /2 4 f - 4 5,<f7 j,,
~
f- -
f y, 2 '; '! is. u,__in- - _
5'2.2l- l2.4's- 3j7,76;n
= f= .
i CALCULATION SHEET CALC. NO C 559- 5 SIGNATURE 'f /-- e C #' ' '"' DATE O'#I 'S ' CHECKED' - TE
'/C#C C '/'/ CI EM ' 7' # '
JOB NO. ' ~b 3 PROJECT
' SUBJECT NO SE ' O! O 6 SHEET U ~OF I^' SHEETS' zi cco 51 u ' EL
WA~W
.1 -> <2'-E> " =t '-:5 " -s ~
COMPO5lTE SLAS D55/GiV [CGVT) 3 Ifl = 2850 + .24 8 (is.SG - 3 9, 76) * +-
5
( ## - '- 68 x /2.45x(45?9-5976)*]
7 X o./24 .
'o 4
.Z~ll == 2 5, 565~ jn 4. za) Air caece Ac laa / J l, = 2 5)565 3 9. 76 = '~-43 in' > 5li . .
13
In sh! ksy a s.si n e S$ = 5$ ,
. D
17 Effec livi sechen -
m aa'u his Seff =
connec.har.c:
$f. Sf,..-S) s
.SAear .
Vg = , 8 5 fe, '.4cl2.
For con orde .
= Q85x4[G8x/L45)l2 (Alsc p.,. 5-3e) :
/h = // 439 , -
n
/
/~or- sfeel f = YN =. M'0'2 N 2 = 444. 4 x C7
~
ocy !
l capa s,'yf V'g :
~
U/hmale dud.s ' s/> ear-
=
v'f my i
= /3. 3 x- Fog, 3} " & 57 u D , fl = 4 k s.i see A41. ll. 4 Atsc p. 5-3 9) bl ,
m- ninber of sh ds (le hare- eero q n,ay
- ,,, , is p.,,g = - -
I.x l'
as in =
32 5' /2 = IG sh 6 1
E- -
~ ~ " " "
" CALCULATION SHEET ~
cam NO C- 6 69- /7
' SIGNATURE b'h
~
DATE
- ' '- ! ,2 CHECKED ATE' I S Er O S D'~!O 'l /2 3, U.-2 pnOJECT RANCuO !C L =A C 3ng un_ l l
SUBJECT d/ESEZ- ' CF^/FAAW ~ F l 0 6 SHEET 17 OF O SHEETS
cos ::.n 5c n,ia s,u ,-,s<-p 1
CONPQS/ 75 ~SLA5 DE,S/CN l'COAf7-)
3
-l i
Vf = /6'!B,.5 " 2 /2. 8- K 2/26' El. . / W-6 '.* in '
w (34/-213
% fz = 25 ' = 50f
# 3
[ l_ , 1 8 5 ' - b ,' Sgr = ZIS +& 69 362 -- 2/3) -= 3l 6 in i
"* /3 <;rfb are, greejer /Aa n Sc h.
" :5' S fre ss s lee. / -O, K -
i3 a C A e.c k. eon a r.e +c. s,43.cs 15 Yf6C lVB $6 CflCh~ (7) fyf/ /ri 2 f~/37.$ 0
1. .
con cre/e jorojoerfie G ;
a S *eh - S& ~ 8 76l[t2.-4&n/)'
' EL..' W-6" ; S*,y = 50 l'= 39 76 Q1-45so.12.4) = 7752 in 3 22 ,
/
in'
~
, e t.. t a s'-s" : s g.9 = 3ie > 29.7s (u2. Ass o.;z4)-e, ise
<conerek sk.s5 -
{~ = y') ; -= a e l k . ' . w L &
. [c_ = -
= 0, 9 /. k.si 4 L 8. k.s,'
Q / 38
=
w rche -
o. k .
31 32 i % .
~ ~
~-
= i 36 38 .
- u .n
CALCULATION SHEET
~!/
I CALC. NO b b ,O SIGNATURE ' # DATE CHECKED bd DATE b
' i PROJECT _- AAA*HO SECO NSfCSAS S TO Y/OW Jag No, l? 55 Y ~ W _
SUBJECT /NMd MM#^M N
NO 0AA D SHEET N OF 0 SHEETS l
. . TER MME CNEck 2
{OM@S/76 6 l A 3 3 0*4/6 AY 4
y,y" q ccared or 44v/ry 08 CWC45fy SLA/3 a n I p -
'b: 25.sF " . .
! fee a e
~~
n 4
~ '
NEurRAL Mlb cl=
C Yts //
v n
. _ _ ,, , d= z6m Ccmstri t&criOO 10
=
it f -% -
Sp 3/ 3 /n.'
N 27 x 84 ks=24.S I .L -
I:MSc x.
NepSli"2 Q.EpH - HMptAL. Axts /W THE SL+rb. I.= P!E NEk7x+ t ;
_}: AX/s /slocATSO /M TM s 5t Ais ,_ 0 kLf TW& PcA7/o M M THE S LAC 5 4ocArsD 4/.Sova THE AEWrn;A1.,,. Ax/ S /S CoMS/DEAtaa 5/=F5C7NG /N RES/Sr/N4 S 7MESCE.g. ( K d G $ ra u c rt/ K h L R N trt N K S p l @ pf& [cch:~
~
. S h f [.O A b 4 d h f Z-Q & kt-~. $~V) 1* ~
E = 530mf e
11=Eslgc
=55om49 S.GO x s o PSI - 29 o x to 8 06 1 ES,~ ' 2 9.c x 1o' Pst? 3 6 xioG 22
~
hc. = EMcr/rs Age opcoNCASTE 47' JY0fXM$ /.CAO
= -
.= bg -
a.w h= i
/ ~
- . . Ac E- ro8 x 2 s. s 2 /5.N m- .
==
.coct.oq cc * /+ '(ps t Q +0 SY ~~l 2,
= k.a x zs.s /
_ 2./s.ty- 4 ,^ , z2 +x 281Mz'.S .! 4 fi\ s.s s s en rs to. s* 25.5)-I ~ -
~
J am
= / 2 . A5- /*
as
~ 4. f 4 0. S V-fc r,-
n
~. -<~;. sissstn.7s+$.sxis s) - /Z~W
- Q l. 12 / *
._ . _ - , _ = . ._ -~ _ - - - _
^ '
CALCULATION CHEET
, scALC. No.?-SS9- 8
~
3IGNATURE - #* DATE CHECKED DATE PROJECT GNO ECO YOCf fad $ 7AT/OM JOB No. N Y ~C0 SUBJECT ESSNL SEWE$r 34 C4 - Eleo)? St.A6 gugg, ,s n, ;g SHEETS A L TEANA TE cpgey 1 (Ont'rtrouG-C* bc b' fkS c + 55 2 .
s
= 2/S./4 h2 45) 3 f(z4.8[26Al) + 28so _
y 3 x 2S.S Eti
c ;; I h N 7 $ /)?o 8
9 c5 s.b OfC f/CM HaDuluS,' 13o7704 :7&EL f/SEg , COMfours $@ca 10 by' ** hg 3 g 59 $7s === Qb
! QE ysy,, u.w + n.ss s ,
14
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17
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18 19 20 21 22 23 24 25 -
26 U ,
4 2s
' 30 31
~
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Y~y3* -
x 35
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CCALCULATION CHEET _. Cp.C. No C G W-8 Y ~
I #
fe " *DATE CHECKED TE _
SIGNATURE rCff0 lll/C ' E A O W A TI') W Jos no, I U 5 A ~ 5 5 5
~ . PROJECT U ?lG UO
?l D 6 SHEET U7 OF M SHEETS SUBJECT DIf868- CE VEM (*~'O # E!_ . - -- EA - 6
.:L n 3 lL. .:p = l_ 1 tog '-4 1
2 FREDu2A/C/ES GF COMPOS / TE S'AS
~ "
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GvASA s 916o)
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p;',""=$~ C <g n f .::::. i . ,
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%o 'p _
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sec= / LL -sec c
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2a
.k- lflb -oh Con C/~8k k- freguenc;/ of concrele dol , c,o.s l~e effeaftve mome ;L- c.t inei-/;a.
off c% l oni Wic'/b fos l e. Sfa $ ferconartfe.,, rr 4 sfry in ferrn s of l
,oc , unti L L - sec wa sc a/ cor>p7o.c i/e. s/af Y F~b 3a fcy ==
5f ,,, wlere $ =-6 8 "- Seam Yaeino l 22 J., cci
~~ O " slecNve ~~moseul f heribo. of concre/e' sfa }; ~ -l
Y^
Ie'cp == (Is + Z j - Z ,) h, wAere. n=
% .s $"' O!24
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./ CALCULATION CHEET LJ cat.C. NO C 65 9- 8 SIGNATURE ~ edMuI/"' DATE OO 8/ CHECKED '
ATE ! ~
r (7 e- PROJECT RA hlCP O RECO NGCLEJ-P STATIOW soa no, 125 54-659 SUBJECTD/OOOb GEM 5PATO8 OLD S ~ SHEET 3I OF SO SHEETS FLOOR SLAB El it) /8 '-6 * ; l H 34'-6 "
' i
-- FREQUENCY OF COA 4POS/TE SLi4Bs @ONT)
I s= 2850 in
5 l~ V,l= Z /2. 8 ' /<fs
=- See berigr)
Camp. S(d Vs = 44u If = 2 6 6~72in
for
~
Amila lich.s 3~ce fryueneji co/ca /a lions ,
. hvTsfortned ~ bec N E~ , pro p //e5 _ Yelabi 5?E
)',' . _-
consSchN sfage- aan Sc
'I$9/ecU
~ ~
Zjff=(2,8s5 44c,((25572-2,8 sc))/O I2F
~ ~
. Pe.(4 == l49,' 500 in * - 7. 2/ ~ Fr 4 ~l 7.2/ st2; ,3 g~
- ^
n s 3 = .
\
coy- 68 h _ (25 5) _ , ggy ,, s , o, gog. & s
_ _ l2 _ . _ /2 - . __ ..
l a !
f = 4.5" 2E $l/2
= f, 56 2.5 l XTZoak in wrvix . coir M io n : ..
~~~),p s/al .145 >zsr/i2 = ,sto gs,
, 005
-_ beams/L deoki.f- wwyh f-
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TC~l~E l Dl-- --
0 33 W -
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/' CALCULATION CHEET cat.c. No C 659- g Q'
' SIGNATURE he W Nf' DATE 03 8/ CHECKED DATE
~ '
.pnoJEcr RA AICllO 'SEr0 HUCLEAR - S~rATICAF sog no, /23 34- 659 ~
SUBJECTD/ESEL S E N E R M ~T O f Bl DS SHEET 31 OF bO SHEETS I Floop etApg El. H)tet-g": t+) .ss -gr 1
FREQUENc/Es OF~ COMPOSITE. S/A/&S Go/YT)
EL , / 9 9 '- 6 " E L. /2.3 '-6
s 6
l Con Con Cr&fe- 6 ~dbck , 05~3 ks F Roo lll q' Acof ihsuk:ti! , 006 k.s C -~ '
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12 D.3 0-/-517 "2 u
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=-
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,s
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/ co y
- 3 2, z_ ,
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l} = -
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2,
[~ , l. 2 7- , p. 5 g 2 g- } ~~, }g _}{gz ig3 s T~ _~
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CALCULATION SHEET "
CALC. NO C #U"8 SIGNATURE d' '<I2' r P '
DATE N # #' CHENEG ' ^ TE
) G
~ n' PROJECT 'Q A WCHO S ECO NLJC LEAR S TA 7~ yng no_ 'l2 3 5 4- c2 SUBJECT D/E'3EL GENEDATOW BLDG - CLOOR SHEET Sb OF SO SHEETS SL.A : G EL f-II 9'-4 " E L. f.+) M '- S " '
1 2 DE StGN FCR 8 LAB @ El..e)34' <5 "
3 6 ..
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y
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=
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17 y.
18
s . .
DEA-D t CA-D )%c 2o 2,
2 5 5 in %k concre?$ s!ob : ./5"- =0 BM "" l 22 E#gu,pment
0 05D 23 vAc., p/pE g' C&6LE TRAY : 6.o50 ~
2<
l ean concre}e 6" tack l 0.053 2s
_ pooRn,o g' t- in su /ci Nori .
'0' 4 2s "
% Ta l _ pg ! 0. 478 kse
/_./VE L OA:.D ,ca ==
C. O3/ lesp mnca. seisec toso oee n, =g(j%.pzeph.) .52G178+
23 -
+ . 25 x. O 3/) ^ -
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as fg e.t58 ksP as *) .
C, CALCULATION SHEET 1 ~~"'"I CALC. NO- C N-8 SIGNATURE
'7/e -
M
DATE O# N CHECKED' -' # dATE O~
, PROJECT _O/KN0 tSECo h'lACl- E A R. 37~4 T saano,/2 M4-69 SUBJECT 9/OSEl- CEA/fAATOE SLUG-/~L004 SHEET D _ OF $C SHEETS eS L A-B @ ~L /4I /8 / ,
~ L f*1 34/--6
1 2
DESIGAI r~cz SLAB @ El.. (*) 5-9'-6;" (COA /7)
Oes coi>hk! Efa/ / cad,.& = MJ nt. +/7,A.t +t 7 Ps.
s O = / Ax. 978 +/ 7 03/ +t.7x.155 =LO2 esp
, /o -_
Since bouitbr;t coir difion.s iti do lh L. a n d
S d;>e cfio>,s casde con s werd simila t-,
.6 5 = C wgL 4; %-C 5 S J s ,_ = s g 4 __ 3 2. 5' #
q = ,f i.s
~~
g.c =. I4/
, ws since wq g . p, y 1s -l 17 / /4/
= 0.92 4 2o P WS = /.02 x 0. 876 = 0.89
~
>c s ;;- l 22 vV_ i =I.02: ' - 0. B 'l = 0. 13 e s.F Usig lbeory of {/,ree m onten fs, EEf. DESIGN egferior* memeWS U Gf to . O, ,
. 0F KfELDED rnom. Of therfic 9 tt e l' , g e f STRUC7t/RES ~
28
g. 8. /-22. Mz g. gg g ) . . ,3, ; ,g I
ao l 31
R _
web S
Q, ffM32. $
t -
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m, j . _ _ . .
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3 ,
l
" CALCULATION SHEET -"
. wc, no C 6 59-8 \
SIGNATURE 8f'i a- 4D DATE 9- 4A/ CHECKED E !d * !
i c-m, PROJECT ANON 0 EEEO ]VUCLEAR OTAT JOB NO. l2 N ~ U ?
SUBJECT S/686/_ NA/64ATOk A/O$~ SHEET 3b OF O SHEETS-
Loot ,sst+e e et ime'-s * -in ac-6" '
1 DE~S IGAl r=0K st.A B GO EL. (+) 54'-6 " (cour.)'
Ffil6
=
/
/h N th. N Mme,a armpm
, .0 , 5 '
~*
, 'we n6 IO
.mo rne nis al {*ce 01 4 in k rna l "9 il Q = M,,, = 118 ," Rj c. e s 32.x,_ D. s q-i = ,oay; 1.
i 15
' ) )y (P t
}
} 1s .
S 1, Is . _ _
" m .s 2.
21
==
Try 9 7 e iz "; A S #. 6 0 in*,'ja- ,2,, ,g'p.co124 L J-21"12Q(%)-zzoii.,
= g. Asfr , , gg ,.,,
a . swbi2. -
~
z, M = . 7 < & < As = (9- -$ )
=
d = 4 -'" }lw'm-8 '
=
k= o. p gor. 0 (2Lo * *z")/>z = 5Z7 u 'M n s,,. w i s 31 .
Ty -g69 e 12"'- A, = l ce in ; ^=
c =as
' d- =' . jg g = /,4 7 in d.2ss:-)y.f,..{#
)' -- -
lik;,j% -
65x4' (2- .
, y =fZ4M2-,p,ong pye
b[ CALCULATION bHEET j gy, SIGNATURE MM DATE 5 #f8/ CHECKED O~b'b!
6 c-m; PROJECT _ RANCHO SECO MUCLEAR S TA TIO N soa no. /B M-66~P SUBJECT O/OSES 6EA/6MATOM S/ DS Fl OOR. SHEET 34 or en SHEETS SL A-8 GD EL. (A 34/-6 /; ) / 2 '-4
1
2 DE.S/GW fog SL AB g EL (+) 34'-6 " (coNr) 3
%g =. 9- 6o </. o - (2s:44 ^f)/Iz. =102.5N-ma4?
'8 Mo n t o, x.
Chact gbear, 10 l'
Shear sfrayH [or pure conm fe.
Vs A ((l 4, d = 2x (4,000 nz-za.4 = 55,5' k ' '
'l 172 an~m acfiy shear (on miaWe sugarr')
is v = 4 es
p-i .now + l3 =iank g,Q=333 Skea f~~~
2a re.ifofcs-wn.h reof }4E&.
CAec6 L - h /iro clico :-
n
==
L -g,on q an>[o,m loa / ;4 ,- ac ' ren,o Af
=
pase/ .-
W=
P0 - r.x.z.-
. i = 0.45 k.s t=
= -
It &)4 /fuzs sa- pc ss ' r,f ) +p -/
' wz g =/,oE = 0. 9 f = 0.13 k.ss=
f.
s .
3.
~
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CCALCULATION CHEET "
CALC. NO C 6SF-6 SIGNATURE ' p # l# DATE 8/ CHECKED h'* " ~
/ C ATE m PROJECT l ANC MO SEr0 A/UCLEAR STAT saa no. /2354-659
., ' SUBJECT D/ESE i SE /! EAATO d S b D 'S ~ SHEET 37 OF 5O l = Loo! ru em et. r-> ie'-c. " ec onsq~ SHEETS 2
DES /GN FOL . SLAB @E/ . (+) 34'-6" @oA/7)' ~
3 4 -
! l W i=.41 l l 5 '
f f Y n } } f i I v i i y -' W,t =.15 s Al d2 -h5 as.o ,
, 5~s. o ,
8 a
=
Use. +beorv o!- -F h ree. ro omen +s
( Re F. D5SIG N OF WELDED STR.U CTUR55 p.
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'O'^ 6 0#
2 N7z(36 +53) =-- 6 $ * '
3 a 8
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4 Bx53
5) = $ 62h. 4-er
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= M= 2 9,Azl '.'
g_,gy -9.b k-nh7
" Q= 54.4 .
n A'
=
~a V664][ N 456 n d ~
=
. M Q,4y M"' %I :
l li
' ' Ig,6 .
IW
= e, ar.a,, -A4**6 Z = g)4
= Ml 6 (k)
Mn = '3*"*~ =
22 8 45~ 6 (k) .
) -M;= -@llfcf$(&4 = 5$4 [k) 3.
= Mz = -54r F/2 +- 45 & = 16.5 (e) .
L
1
^ '
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CALCULATION SHEET "
CALC, NO C 659-8 SIGNATURE -- 7"'i' !W ' N CHECKED ~b [
v c' DATE DATE
, PROJECT _ RA A/ Cit-O - scro A/UCLEAK l'7%T saa no, /2 334-6 57 SUBJECThl Esci GEyjEP A' TOR BLhG~ SHEET ?? OF SO FLOOP SHEETS d'L A-8 G E/ f+134% "- EL. 41/RI4 ti 2
DES /GM roR, &AB @ EL (+) 3P-6 " (coMr)
DeNrmit1e S/7 ear VO lUes va 4 e =
N' f - - 5.88 (k) ;
Y=' I
,; 6 1'+ = 8.86~ (k) \
'=
\/c = ' *[ + f31 = 4.47' b)
V*. o !3 ' 53 __ K4.t ,. g ,42_. (g) is A, 53 _
i 5.t6 4.p.
} is '
Sh ear ch ro g m. l
\s \g.,68 n .
--3 y
N tat is no ai ,MA , 2 1. 6 34.5 16.5 vt -
22 Max , ac%en.f- in i s pn u
25
. ( = 5, SS e H.4 . "U'" =.9Z,E k c,}. K e M
~
27
=
y,,,,4 c4 de v/a. l[3
, k.{m= $4. L- + OA.& ' - 4.ATul = A- 9.~I
, ==- #[k) 8overns 7r~f: $6@l7', As ='44x12- y = . 5 7 in z
)' u a = 85*x4x
.59xbo ~~
/2 := ^ , 8 'f- ,a,,~ 2(==24'- i.5" )g V =12.1zrier as M .f<, srx sofE125 **l)b2 = 5~z G(k)y mM .as n;-z.4
4. s
--~
' CALCULATION SHEET - ' --
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cAtc.NO C 65 Y-8F -
SIGNATURE
a-
-W M*aDATE O! CHECKED '
ATE 6/
. PROJECT _R AA/C//O SEr0 NUCL EA R STAT saa no. 12354-659 SUBJECT MESEL GEWEWATOP B l. D G ~ . SHEET 2* 40 9 00L OF-
.SL A-8 (5 EL . /~/18 '~g " EL f*)5d4 " SHEETS 1
2 De~S/CA/ FOA S/AB S EL, G) 3d -6 1
" @cM7-)
%,-- ca w <n, u;<a s
M,, y 49,7 '/. 3 33 =g 3 (k)$?Mp-o'J,C,.. .
. l f "p , y ,2
~ = 0.0022 <f% ,,= 0. 003s3 N bintt>the/ hen f it oh Set 1TICien$.
=
7r~t t 8 cp 12' ;
=
As = 0, 7 9in .
10
'?,$,g =
"~
, o.gg l. /6 in ; d=24 "-i5 -as "=2 z. o -
13 u,,=a r- o.wso 't),r. rez- 6> ,e .
~
A 0' j'* y_y,,,lf 2
=
~0. 0 0 M J nin
<T -
//o>,en-/- O, k .
'
Prowde-
f q 12" - p ,.cor,s s a m,,om 31 Check. shear-33 v; s.se 6) f = 2 is,on' x /2x 22r35 4 L > V = 8.$ $ ( k)
O n
28
M 31 32
. -. ~ ~~
-. g wshe "
M ~
~
[ CALCULATION CHEET ~-- W a0 3 3 5>P i CAL.C. NO C 659-8 SIGNATURE baro W DATE CHECKED
~~
~
G v G TE
-* PROJECT SAhl0NO WC ^lUOLEAS ET~ JOB NO. lI33#~ S 59 SUBJECT D/ESOL CCA/6MA7'O El DS - SHEET 40 SO
. : o >r si. A-e m y m m'-6 " - cl . M'-6 ' OF SHEETS 1
2 DES /EN FOA SLAB @ iE L. [+] /8 Q "
3 1
s
/ oa./S !
l
i 7
bEA-D L.OA-D
Ksf \
25S;n Msk. concrele slad , bl 9 NVAc,79e g' caUe -/rof ,IoO Equihnen-f
,07b
~
,, ~r +al p ,= 0.494 kse l 22 :
L/vG Lokp = 0. /25' sse
')
. SetSMic toad OBE Q = 0,2[fo.494 ~.25x./25)= [32l ,
. h is . 7o~ /a, [ [ g7 p [ ,'_
E
\
19 1
20
O = /. 4
,, I f" +-/, 7x $ +- /. 9?% = 1 l
23 J. 4x OA94 + 4 7" ./25 +4 9x, /52 =/:rg ss a 2.3
a - ' -
a g S = - f g ..
e S= SLO ^
, j f bS =I65 gr ;
_ Y _* x L * ,
a
$ 52.f U si
' j Ws 6*x / 85~ L b4*
~~ a,
^^ ~
) L* *4 0 h. 14/L 3 g 4- _' .5,/ -
Q
-[g 4
=
m gg4 g -32.f) =5'65
-, , . - ,,u- , ,..,_. -- - -
3 - [ CALCULATION SHEET " **"*"'
CALC. NO C 6 5 7'P
' SIGNATURE >>- W DATE
O O 8/ ~
CHECKE TE PROJECT K A AICI O EECO ducL E.AQ STA~roAt JOB NO.. l2? 3 # ~dS9 SUBJECT S/6SEL SEA /E#JTOA 343 & -
fl.D00 St. A A' tre Et . f+) 18 -!., F EL . f
s Er d"- f'is -
SHEET dl OF IO SHEETS 1
2 3
xesieu son sus e ei. R)ie'- 6 (cavn) 5 we =
p. /4.n = i.16/s.o = o.n le se a
W, = A lb- O 29 = 0 9/ ?S/=
h/g = j w, f *; f = saser (cnar spn) (usc) m q l o.9/ ds a 4' = fq, L k (e l - ,j u )
'* or '* *~ p s/ w
% # f @ l2.", d' E 25~f '-t 4S- ,] == ZZ, 44 ur =-
1s f ",2 2.g *000SII*/>.ini Ws
!'fD N""#?' W # f M - Y /
i.' , .
b4 = 97 7 N. - -
17 h [g. ., c- s, y A =
4 18 .
2a for- 9ea>a N=74.z2#.5-f:=5+'(Q
Proyfde s's L direc/ ion
,heit [f@ l2.' for cen Shma (wje s.e.S
/f .11732 S~
==
Ske.cS: . s.l1W l V
WLx.S z t 3= y fif t g./=)27 \
g \
1 7 7 4 g =- 3 5 .+ k.
'. Dess;9n swmenary' for- ' g/a4 des /seri a i
%4 'n- L-mq S-a;.,p Mv, x-prk M, **/n 1c h" e. rrtia R.ra ti. L V, v.e Re. mark
.s L 5 k4r k/s)c l EL.M18%* $1912" 4 9gtz' y{ j 2
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Yg Vy Yu>),/.c EL. (+)34'-d#A!ptz" 4 fetz" $ IG2. $$,f o.o. n om -[f} lQ0,4 '-l$,hf %s, ow,fe,m,,,,e
, 9. . pa,,, r. .
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cat.C. no C 639-6 SIGNATURE - Wd DATE #E 8! CHECKED' '
'#'#' /C' ~ ~$/
~, PROJECT RANCHO SEco- WucLE A R star ,og un_ iz 23 4 _ s 5 9 SUBJECT O/E6EL- #EA/FEATC#- 8LD6 SHEET M- OF AO F(A ON. S l A-8 SHEETS (T C/ f A 3 4 /. C " A I J E !. ( " l M .- i m =. - .:.z, . . . .
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,2 "
s SIGNATUR E - M DATE /
CHECKED ' ' " ' ' #'
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SUBJECT -
- NU D ~ ' #M ** --'" ~dHEET IA OF. - :' J SHEETS s~a m . : . = -..- .
Q. Ag,,,- '
Ed. i .9 ' 6 [R ~ = - 3 = r:P-//] !
2 b 50 19= e 3 ~5"
----- :' f, //
s 73 p .5 5 , .,
4 2 o. 9 ra C
6 6; = 27.*7 M e q g 7 ~~~~
l~Yh 4fl's c2
=
EI wd.ees ;-p
~
= o. 7g ;,;.= o.e e
.dGU /
it M'= j p"Q 'ggi.y = 0. 0 0 f f a = 3c. w i t = 369, c = ,.a, x to c
,a < - - - .- u,
.L -
,:; ; i< >e ar.
,=
.L L - 2 Jo e . 'c v
a pr Tc = f! br (= o.coc/ . n= .= { ,- ~YZ
/ -rif= 0. 0 5 iis - -o
/
17 Ic = o. erinf= 3%
.Te = /o 77 'Y :,
,a
[ = g g,y
'E 9 D- %C.00% 36[
0. O M M
's =
36o0 de'ox /o37 21 t- = /7 96 Hz
/*/* El $ W,0 3 #1 23
. / . 8. M 2 7 ofdc 25 t~ W S l $C. .
27 . . . .
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31
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p .. _ . _ . . _ . .. .. ._.. .. - . . ,
y ...- ... . . .
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~ - _.- - . , - _ ... y _ _ _ . . _ . . _ . . _ . , _,..,m.- - - -
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CALCULATICN SHEET CALC. NON-S
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SUBJECT .
9 N * -
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SHEET M 'e OF C SHEETS
.: r~ .= 1. = - ;,
Cis7;cr:::b.-:3 d: SECair7 C. Yo c . 0;# .to,. Y . ;
C/esr sfairs A: 20.S' B: 54' Ose Marrcus Ade7%od. - .
A So. o 1
, , e, = y = 0 897 u.ce o- fo doef ,$ rom case G G-)Cg "o. 0 79 x -N g
I '
R C,4 = 0 039 (+b. G 'O. 0--lE g. s
0)p C6~ 0 OCl h)f_ Ca, "f.CZJ* ,.
12 . ,
1
' I s ~' ,, t l
14
'Z)ir!. ;i /g - 0 7 4 !& < p. 7/ 1i A
!Cac{s A '
f5eiofeo)f
~
'bl '= A 4& p. 494 2 0 6 9 gr.j'~ ,- -
b 19 LL = /. 7x D./25 + /.9w A /92=- D. 4(e M.tf 4
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l
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PROJECT EAhk & 4 Gro AluCL EAR STAT /or/ JOB NO. I2 W~ AS?
SUBJECT /)/6584 6 EA/EAA7' oat Bi 34 SHEET' OF A0 SHEETS CLOCM .fL M S s'r FL . f* 1 5 4 /- 4
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SUBJECT J/Ef222. &##E4 A DA, 3L8 SHEET b OF $9 SHEETS 5490t SLAGS oc EL. i+I 34'~4 "
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f ThlM 8 Aid @ l2O.C .
22 (TYP.) h fg[y,c f W M
=
22 ~
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. / g .
- i 2s .
Atole. Exisfin rebars, #faticance w.
2' nd s4 ban yGr c riff pvpow3 8
30 31
~
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SIGNATURE h 8"db DATE I M' O CHECKED
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PROJECT A D 6660 ^//>Cl E4 A DFOM JOB NO. /2 3 3 h @
O SUBJECT O/8S8/- S6A/EAA-TdA.- 8 IOd - SHEET 54 OF SHEETS
G *M St 2 83 m EL . M 2 4 '- 6
2 AEIAJFOA.CEMEA)T* A00ubD / C/CMA. DEN /NG (CDAJT) 3 O
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s $9 0 5 i E A etz' FACE' cx' pAELT* 0 Nl \J N
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a
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n -
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30 . j
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t CALC. NO C 4 f*- 4
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PROJECT A AN CI#O 06[0 'JUCl S M S~rA'r OAJ JOB NO. l *W~W l)
SUBJECT blfSf f- SS ^IEA 70A- 0 LO$ SHEET 'f OF SHEETS S L A A S /*D EL . f4) ~2 4 '- 4 "
~
r/.00A 1
1 9 peiamceusar nouwb aacuar cesaac (com-)
3 Weigh f of same ona w/o o, ey f 'nushiwiv 5
s x
/so = 2 6. 3 L
(/of 2. (2.CS)~ 177/r /060 * ,
c'~ o ,g s j ,g j,,p p g,g,,,
Gne e it. )5Sunse /be aclobfional bars #V C side of fle ofening) . o se spaced' .So
'o !ce t e s+r,o eo.cA jaf i 19// /Re /2.in sp2ci>S 4'e /we.en .
in a, n Ne,9
-9 bars; CA<ek. Mis s ~ a t! s e = <> , **
' ,4r /ca ds ci, /rik</c>ry areo _!
u ,= 4- g i, a w,, . Use .s/oh, foacfs fronr. ^ )
b" ~ calc ' ' C 65%=-8 (Page.-3_4) -
$~ L= fs' f __
= 8 '- '. - Po ~ /- 2 h*
" . ,w =
va+yat .amater h , {a- f =;,,,,,"n..y '
4'l ,oa e a
e G L (f). 3#-6 '-
a ..
.. ~
a v = !. q- 0. 2 5 = 0. 389 I
' 7~ /a/ w .= = t. oz 14. 5 "b e.K 3 f:.i,y l-}74.;g) 2*
22
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2, --
-= g(gi; .q-jy ;
c- .
,L .'
= , g1. y,4g+;;9_,2 . '
=- 50.0. k-f7 _
S wrmfwe -
rore7g- up N m
= y. : 7 .
.~
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= rr w~ * ;g; m , '
' nr (4,'t.o)(go)
&,.p. ra. re,e dl = o.8S &f, = (o.fs)(12)(4)= 588 in m
8) fee //ve depN d = 24 E "f
2t. 44sh
&"" (cen.sswa/sw/g/ --
l Maitaram oIlo aAle ,s/n / re /**o -
x n
= o. 75 pi = 0. 7S o.85(a2S)4-" ir, - ^ to 87 .. i ^,, = 0. 02 /4 -
R u. .
t *1 w ouson1
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CALCULATION CHEET
, 9.ALC. No C ^f9- 0 1: ./7 -
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e
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PROJECT A A A'l "O SEld ^l" [ ' E A S~I" 0 JOB NO. !I U '~ b -
SUBJECT 3/ffE/ GS A/6AA /*SA diJ d SHEET ## OF SHEETS FLOOL SLABS e EL . f+13 d '~ 6 "
1
' AE/h)fdA.CEM EN 7~ AAou^Jo C IRCdL A A. 0/WDigg froy7)
O ;
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g 6
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2 /,44 b & , - .iD, k. .
16 , ,
17 ,.
g .
i.
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/ =8/"; at =
26.VI2 ,,4 ,, ,, , 3 g)b , g, g 3 g 2,
/,.
.g 4-8I 22
//{5
/O Maa,- w l- *
-n - (.2. 03 )(8tj'-= io,s &. ,,
22 i 7 f49 Nor"nl-relars cofaclly fr- 6 w i a'e. beoin, 2 #5 a ' %
(2x0.E/)to)
(o.pg)(6*)(4)' " 'N n
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i n ,) ~ * * ~
i
, " CALCULATION CHEET
CALC.NO C $59-E
" WO DATE 'd 8 3 CHECKED '" DATE
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.., SIGNATURE PROJECT A A AlC#C ECC NL/CLEA A 6 N/CA/ JOB NO. D 3 E87 SUBJECT Of 6.66L G E A/ G A M C 4- 9 l. M SHEET. #7 OF i' SHEETS
=toct s:.a g c , e t.. -,w-+-
' R G/Aff0A CGA4EA/7' MQu ^ip ci A.c ut. A A., CSE.A'is]G (cof) 2 :'
1 CAecJe. .sh ea.c s /resses.
6 '
s Com/s ,4l/owal le = if r2 f Vf' '= ass-2 I40*o -= /07b~fso' ,
7 8
Sdear e/ress jr G 96 " ?com.' [
-lox = H\6 psi >
,, g, ,, v'.=. -lo7. 5p' ;
! 14
)*
, ,i 8I" Shear Stress for heorn 16
2. 03 c 8 I/r2. -
i.
i.
' 2 <..id 22.19 l' ' ' V<2 f k-For consider rebar codribu 4ian
' k 96 " DLum skear res;s. , Fonce. (since. --a wise 11 is 22 far from i h, e po e.;+y) n ..
3 Y v
== G$ASGy+ mg > bch -
= 6.6 4.o < 6 0. +- W" I 2 *2I 44, t= gg 7,5 k
,1 l00 O Q !!.,,,
= = 3 &. A <'~5 \/q
,, U*Ax
@At $ bear for~ ofher beam ch $$Q Sa n t.
3,, . . . - df rac.{ ton -@ . ..
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= -
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CALC. NO C Ef#- 8 SIGNATURE dh Ob DATE / #d' 8 3 CHECKED' E
PROJECT 4 A AJC #C S Cto AlvCL E A A- 3 'O JOB NO. /2 8 3 4 -~ 6.N SUBJECT O'6fE L 66Al6# 47'o d- O 'O #" SHEET #8 OF 5' SHEE.'S
.: cool S L A-B $ Mb G L. M 3 A 4 "
1 2 gix) fog.ceusAIT JacuMb c)Acut.AA. OfEN/WG (coAlt) 3 4
gg,3f,3 morrianf dia 8 ra rn [ rom p. 5 5- C 6S9-6 0, acroSS the 2 S f "59
)Y Wi'sy P 57 Reclis rdoute. Zo*/. $ momeni : 0.2.- it 8 = 2 L /, #
in W Re.d @ ib u k d 6 4 -
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lowd;og g p ,- -
p p -
" (4,l.cds or '
4ts .
o
=
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'5#[8 h $,#
S p, = [2 , (i.e i 7 -o.as)+ k i.oz 'yN} _ 7= l y, g 22 (
24 k
, Pz = ( 426 3 (i.4 +1.1-o.ss) + i.oz. 4- q)/z = H.o F'iXecI end mornenk ,
y . P, a.k(ar re) ;- P2. o,.L z (azte) _
, un zet g e z-2' o9.s. ) (is.s)(n)(is.s+ 32.s-) + p.g3,)(9)gsy .n.ye Qsa '
.= t970
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x w a M.,5,Q1.s)(t70%s5Ymo+n.5)
" e(32.y;' 2(32.5)Z-
(M.oY.f.o)4N9.Ooz.s
O '8 mo . . .. .
CALCULATION CHEET CAL.C. NO C (,f9 6
N"> Mb I' I 'N CHECKED
! TE
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' Sl2NATUR E DATE
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PROJECT A A-blC 180 SEL C A)U CL EA-A_ cTATroAJ 30gnoIM&- M e (_o C SHEET #8 OF I
SHEETS SUBJECT _, DIE SEC. cream A. A7 o A.
C L O O A. (L A a S <a E L. * * * ? d !- t,
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3
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(rr) 31.F .e
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22
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=
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CALCULATION CHEET CALC. NO. C & S4-4 Sl* NATURE
# - M DATE l' /# CHECKED
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I / y V PROJECT A AA)C"O S&O AlllCl 6 A A C TA*YIO h! JOB NO. !2 3 W W SUBJECT.D/6SEL /EGAA"4 A-7DA. 8 Les SHEET !O OF , to SHEETS C.o t n A. st_4 RS /*D Gl. /*)34 '~C" '
, i , . ._ - : . .u a . - - ~ i 3 4ElWOACEMEAIT Abound CIACUL Ak 00CA)/A)G [C0hlI' 3
4 ,
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10 12 Addilroao / -nf R=2 1087 =377.4% N y..
,, OL .-
Since He . in o imo n l- c epily desp ' f l
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19 20 21
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em ,,,.4 --.-,m ,,+ * . - - - - - . , - - -,emm -
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CaC.no C667-8 CNATURE- h W /I/" DATE /' /4 O CHECKE ~ 7 ATE I PROJECT A S*^IC l'O SGCC AiucL EA A s7 A 7,w saano,/23% - 6 9 SUBJECT 2/DO 4#A./64 A N4 S404 SHEET SO4 , . OF 80 SHEETS FLoca SL.A? c =' / .* < 4 4 "
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. CALCULATION COVER SHEET
{ SussECT EM' "'N Y O O ~I#'/ '7'9 calc.no. 7l'@-9/ST i
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l RECORD OF ORIGINAL ISSUE AND REVISIONS "
"",V- l C EFTA E
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. .v i .. ..
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CALCULATION COVER SHEET C-6 8 e,_ R A NC.uO SECO NucL STM. ;o, no, '2 20 J- 69 .N.ET 1 or t.4
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TOTAL NO. OF SHEETS I_CCEC O b ! "b
k l. !*** N '- h '#
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D'ISCIP LIN E DATE ! ! CALC.NO. A
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HOCKER SIG " '
D '* *** """ ' M DATE 30*b OU ALITY CLAsslF.
'Iket . Os RECORD OF ORIGIN AL 155UE AND REVISIONS REVISION DESCRIFTION DATE ORIG CMR GL G5 CHIEF
_0 ' ORIG /NA!.- /SSUE a 30 !:. Q 1Ar'H. dt ,. W l
l l I 1
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I I I I RESULT 5 OF CHECKER REVIEW IO REVISION NO.
ITEM DESCRIFTION f
I I I FIN AL RESULT NUMERICAL DIFFERENCES INITI A L l
. AC E fiQ.I SIGNIFICANTI NO CORRECTIONS N2CE55 A R Y DATE , pg,gg l ,
b FIN AL RESULT NUMERICAL DIFFERENCES INITI A L I
] A_R_g SIG NIFICA NT. NECESS A RY CORREC. l j TlONS H AVE BEEN M ADE. DATE i l
CHECK M ADE SY ATTACHED ALTERN ATE ' I I A I*
C A LC U L ATIO NS, SIGNATURE NAME
.. SJ $ t f - - --
Pcler 5rstib9-
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. V' ko e snowATun oxyg -r// /9i cHEcKro A b m .z a, . p;g
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1 i .
2 d o 1 T t: Q A - % e. Fl o o R. T. L A?.>% AT YL.Ct)\i-E A N C CC -I 3 A R T. TO E.T. D15\ G,4 E O Nod- Comfoastt ' tat . a .
R:'M E\J ER , TO PCuR TWYSE St.Attk Tn T. FOQM ti Ptovtot o 5 GY sittL FL oca. O rcx Ado Tr it. lutA M T-n Amrt .
THE STTEL 4: L o o n. Otrcs mus a s. e4ou- Q esasi At.
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kVAC CuCT 3. O h)CM \t\l
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" Ib Rid C.otLt. O ISE Q - CL A 15 . This, cHMTR OF cAtcu ATLo m At so I NCt.k O C Trte c Rai N t. A u 4 A y a t A m t,;
13
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l. LOG.D At %"Tt P ML ATE.O tM C H A P T P R. d - 4"z Eo, - l REG. 'D1z m c. ed c RtT Ent A. TH E. .WEEL F A Am E5 P'o R.
" O tt.in cr N ED FO R C.ctr acrz prAO FLo o G s. A R.L.
loa O S ( c5,4.sTRu.crio rd Lo^o s PLLLs s wt p.s C.c Nc carR Air o FoR. M AX . mom a tar & 1H E A R . So P5 F Co v:T Ru.tTied loa O , CA N LATER. o u AE A'tTRitttTED
I'0 W A R,D i CABLE TG, AY , pgpg3 AtjD HVAC Gupp0RT t,0A05.
22 FOR. CRA4E. @ Ht0AY BEArvt O tstGed t,$r u A cs ARE APPL \EO .Ars Dutcetato 14 C H A PTf q, c.- 6 59.t<
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Re AERE Mcts *,- .(1). AT S c. if\ A to u A t., \l 0 L . 8 .., 1 0 8 0 . .
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C.A) /QC C. O va 9.\ G,hT - C9. A 14 C CAtG.
av 30 31 32
33 e '
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cat.C. no C ' 4 59 ' I a SIGNATURE
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W ATE 7- #
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JOB NO. ' 2I *U SUBJECT
'-** '* r - '* *
ON e / '** SHEET 3 OF N SHEETS
/ ricp! ts EL. f. o !s '. f. " i.-l 6 *2 '- 4, ' ~
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= 9. /2 r 7
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DATE CGNATURE DATE EA W uo O E *C MUdt 8Ae Sm /cN .,o8 uo.
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cat.c. No ?- W * ' ^
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SIGNATURE A e/f M $ f*C C PC MA 4 ^~'O JOB NO.
50 PROJECT O/ML Cy M . '3 - SHEET 5 OF SHEETS suaJECT rcyr rege ,_ 37-ec.r:-nes avct - '
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CALCULATION CHEET CALC NO I SED *10 si: NATURE
' ' DATE 7 M/A I CHECKED # ' ** ATE O~b~ [ ,
PROJECT RANeWo 4Eco WLitL . *at A n n ) Jos NO. I N d*SEO C F )l E P AT A R B l_t t L O ' M fe b 0F M SHEETS SUsJECT_nitertic OtE M Ln sTee t .necas av et <-> s: e,, SHEET
. c-3 w. c i
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l
-2 SEAM No. Q
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stAa : 24 iw. conc. + 3,, orcw._4ve.rk.s 25 5 '
,& i.*2 *, . . . < .,
O S
La AoixG:- xsr.
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l i
8 El AM W1 P :o.oi5 N ett : ttti 6 A traction rr. tort.
' S o 040 m Ax . tweA a,.
! couST tcAD$:-
! 'o TotAt.:- ao.4to tr A m wAcmo a 6' 8" c/c I
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i 13 is M %,,. Gj 9 P1 , 2 33 x 3 o 5b G x'6c's 4
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8.
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Vs4x= G_k 4. F 2 13x3o.57.-
+ 5 , 4o. s e 17 -
2. .. . .
'8 TRY W 27X $4 (CcH5tDER SEAM TO RE. LATfEA1.W SLIPPORT'f D BY STEft, Dtct. . ) ,
Gxw s 2t3 tuh Lx: 2 650. Ig* ; cl. 3 26 71 IN . k.mis . O . 44 lu ,
l si !
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hhw M w , ses.t xiz ,i7,4 ,,5;, pg , , o.gx yn s t 4 w,si, O SMx '2,l'h ) ,,g, a ggggg egigeg g u
av
" V YMAN s
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a

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31 U
& ,, s td L4 PL I
, s v2 35 v 2,o.s v t728 , _5 x & o.5 x t 72 6 32 384 El +4 8. E T. 384 x 29 ooox 286o 4e x,29ooox2650 ;
s o .65 + di o (,' a o6llM.( 4t ,s ,
s 1.ol6 tN
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CALCULATIEN CHEET CALC. NO.C ' S " O * ( O
^ ~
DATE 7!24 !b CHECKED ' '* TE
~
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., SIGNATURE ,
PROJECT f2 AN t* ll O 4ECO MLICL - ST ATI O N JOB NO. N Yd*SEO 7 A Fi!ETS SU8JE CT Otit te t C
u E t' .T o R E 1 ' ' L OEtLt1/*fr-) ' 8- 6,,SH E E TN N ' 6'
. OF it o eic*n o t i STE E L . n oo sts AT 1
K 2 gtggt y g4Mggg 47 g((+) *N.6 ,
gjq Ps 6(FOR M AY. McH[NT.)
3 SEAM NO. Q , ,,
w3233%/t,yt,
& *
a e .- - -
GLAB : 24 19. CONC. + 3 Dick.AVC.TR.s 25 5 . , &
5 Lo ADIN G *- WSF.
'
I'O '
" S'AO(WII) 1*(2125)(0 l6 "/rl) = 0 34 o c u.
' Ctt.c rew,ig o , :. io.oc5 g,414% s Rs 314 32
EE AM WT. - :o.oi5 NcTE: 'tSE 5 AT REACTiod Pt Tcft.
Con 5T. (cab 5 - t O.OGO M A x . t u t A a..
Tota,t.:- so.410 stAM WAcwt,: 5' 8" c/c n
'8
'to = 0 4 \ KS F. x 5 6 7 n: . : 2.M R/ Lit .
13 1 7 Ex6 , 23 64 6 9 PL ,2 nvs.
, r t- x .
M m45. r.
8 +
, Jn S 4 - -
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+ 5 . !4 M M l -
i is TRY W T8 X 3 6 (CCH5tDER BEAM TO BE LATERALLY surronfro
" SY STEEt. Dtct . ) ,
6xv = 67 6. m 3 L x - 6f C IM* ; d. s 17' 7014. kws . O 30 l .
t.
, as 28 FLEXUpl Cuick :
83 F3 216 Kd .
8*
bx M m_- ,Z6 6A x 2 ,, g 3g g si, 19 : o.(fx r3 m z 4 ssi.
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88 I
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4 at I
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= n4 u. t
5 0'ZMN 2 0.p l4 s+ 0 00.423 0 07 41M. < Aw' , o *
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CALCULATION CHEET
, CALC. NO.C' W
10
. SIGN ATUR E "* DATE 7,!N ,!# I CHECKED ' * 'I E
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PROJECT - R AN C M O 4ECO MUEL- bT ATI O b) JOB NO. N Nd*SEO SUBJECT MWL OENE" W R E ll' L O U'l I" E OF O CHEETS iTPiff*?!'O t.L STE E L . FL.co R.s AT E L (-) i 81 6,,SH E ET. C ', 3 4 '. 5 "
t i il K 2 ST E.E L FRAPtlRG AT r.Lp) 34 6 ; Lg P: 6(pag g Ay, goggny )
3 SEAM N O. co s l l7 K/tv t .
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0 34 o g 7
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80 TOTAL -
0 410 B f AM SPACiMCr .
61S C/C et
't0 - 0 4 \ KSF, x SJ 7 n . : 1 17 R/ LFt -
is 7
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L 'Z.
TR'T W 1 8 x '6 5 (CcH5totR BEAti TO BE LATERAtg SUPPORTED SY LTEEt. DECE , ) ,
l Sxx : 57 6 tu ; Lx : 5 t o lu* ; cl. = 1 7 7 0 IN . E m s 0 3 0 lu .
ai 2
FLEX uP.E CHEC U 2'
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. 8bx M = 19 36 x r z 2 4.o3 esi. Fby = 0.(h: Fg n I4v.si.
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27
% ^x' '
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,, e,x ,
DErLECTtoM c.H t!C W.:
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, - 0 00 8 + 0.ol5 :.0 0 2313. ( 4,,vxf .F.11 1
, 3 6, so m
.. o.A.
i
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J CALCULATION CHEET
- b CALC. NO C'0"D*lo Sl: NATURE ^^ ~
DATE 7!7dIEI ,
CHECKED / *' *" ATE K~b [
PROJECT R A N (" M O 4EC& N Li f* L . STATtab) JO8 NO. IU M*$FO SUBJECT _ ole W L C F M E t"* t,To ft E t1i L O tt.) fw- 9 O F ._ SHEETS St D'tCTtfD3 - ST E E L . Cl oo ftS AT EL (+) ' 6! 6,, SHEET. C ', 3 4 L 6
1 K
g7 ggt pR4ntgg 47 y,t,(+) gg Ps S
2 ; troR M Ar. Howfut) 8 EEAM MC.
@ { wz2 35%rt.
SLAS: 24 ItJ .CO NC. + ~5 DECK AVE.TR.* 25-*&h 6 ,. a + , * + *a 5
LoADiHG:- W5F.

k* * *
! S'.A5 (WET) -(2125)(016 "/rd)
0 34 o M *X UL.Decw.t d G :- tO.0o5 gi e %l '9 Rs 321 9
\t.
:- : o oi5 HeTE:-titt 5 AT REACTio>l Pr. rait.
EE AM WT.
COMST. (oAb5 *- 5 0 O G O_ t4 AX . $Ht All..
TOTAL t- 80 410 t rA M '5 PAC u4 G :. 6
8" C/c 11 iz
.LQ = 0 4 \ KSF. X 5 6 7 Th. 2 2 33 K,/ LFt -
'8 l g
]
14 g g,. . 3 c.0 9 PL ,2 9 <t4 5 ' #'"5 79 % re.-x .
l j 1s S f D -
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. 11 9 w l
n -
z -
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EY STEft. DEct ),
1 6xx = 57 4 1x ; Lx : 510 .
In* ; d = 17 7014. t.w ' 0 3 0 iu .
I.
21 22 FLEX URE CW ad-22 F3 2. 16 kai .
bx M -- , . 79 ?A x iz als 53xsi. Fb, m 0.Sx F 3m 14 sti.
n Sxx 576 J ,, o,g
" sana cunew .
j 27
[V - wax . 2E' 9 c.4
F3 = 14 4 xst.
a db l.7 7050i30 ,.4. p. gd) Tv s ,., e , w, ,
! DurtstTic4 tHuct.:
! si l kn 7
A -
334 El 4
s w L ~ +~ PL I
4 8. EI
G x Z'11d f4 *.5 x 1728 4 6 x 14 5 x 1728
?.84 x zsooo x 8 4-3 4 4 x ?.'3 000 K 6 +.3
= o.p57 + o.o36 s o.5518. <A '-
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JCALCULATION CHEET '
CALC.NO C*S69*lO l
~ ~
SIGNATURE DATE 24, I CHECKED TE
~ PROJECT E A M CM & CCfo Mu CL . $""A-r c h) JOB NO. 5 3 #- W SUBJECT Di* M '- UN"O MN "D'7*MS -
SHEET 10 op O SHEETS
< -n ' e c n t u t. su t.rtcoe A- s t fM t e a r :M 1A4
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2. 'o 33 4Nj ~
3 SGAM NO. l BEA M WT:- ( As suMY) O OG klF. 1 " "
ii.u a m
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li 12 m g, , 9 48x G50+14-02x.s.64v wa 83f-C c5 y, \) ?3*/2 _ ;;, c [q u 1i 'b b a ,,,
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" lL n is -
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ao 2'
TE.Y W 7,1 x 4 4. ( CONilOGR EE AM To SY 1.ATmt'.y su PPCR~2 O SY 22 FRAms N'G (EE Am L )
23 g ,.= .5 7 41 in . M= 5IQ inA.
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25 FLEX u r> E CM c V 1- -[g, Mmu , 4 6 7d x t 2. , i3. s . esi-a S. 57 6 2'
i%: o.66x ~6 C. = 7 4 esi. t c. K.,
" SimAQ Ot tck t -- hv Rt ., t 4. B . 3. [ 8. v.s,i ,
a d.tus 57+70 x O 3o f y : Q A M *h C. : \ h A 1 0 0 ,* 6 .k DF ALEC f t MM CM RV t" 32 p t s 22 A3 \60ML . t oo x 64 76 x t t.13 - = c , l g4 is , .-
" E T. zsooo x sm Agm : L x l 2. 3 tt, n x t 7. , o.377 in -
., o.k 3G0 '5Go .. -

CALCULATION SHEET " CALC. NO C-( 5 9 -lo E
SIGNATURE (
~ ^
DATE 7!24 !2I CHECKED' ' '
DATE !O ~ 7-
. PROJECT Q A9 C46 6 EGO N tt C L . ST A7 t o d aos so, t 2 E % G 5 9 SUBJECT \ESE'. G EH E R A7 o R Rui L 01 k)Ce SHQET-U O SHEETS t T p *J cT u m A t. ST'EL . A. C C R.*; A7 EL.f+), iC -tS" f f -! *..'.f-6'
' K CONTE O 3,gg 2 3.o A AT E L (+ ) 1 +,- d ,, "
2 GTEEL !"R A M t tu C, i 3 Sipm no. & 2.- 2*9 __
0 85 A.6l BEAM WT .- CASSLLME ) 0 05 KLF. I 3 V I I s
A i 4.
, _ 11 33 m x Ri : 21-23 R2 5 /7'#l REACTida FRe<n h2 96S c
,o .. ..
g . 23.o ;
11 12
~
R i : 9 UX 3 SS+ 2W 5~M + 5 M.83p os x IlWy=. 2. / 23
l
'* 11 31 1 l
C5" Rt: 5 x.4 5. 4- Z 3 o ;< 5;O + 9 -d'Jx '2-75 + d 05 x \ \ II/2 4 7 N 1 11
- 3 ~5
's -
2 b%4 5 2,.
17 olx 5 s6 - E x 0 b - e do s A S-(6/ r 9l33 F t . k. .
2a ,
1 zi 3pyr ylE135 ( CONSI D ER. EEAM To BE 1.ATERAU.Y SUPPORTED 22 EY F R AM t fJ G EEAmb . )
2' So: 57,6 id; In: S J O in 43 2: L7 70 ig b : o. 3 0 in, 24
=
Fi;xupe ciaat t :- I w %sxx -. .
s s x iz.
s36
. ta-oy ni .
2' Fbx:a.44x 36 24 ysie*
' 3 2'
MAR CHECK 1- .h __ Ri g z/.z3 g o,. t<.s,i,
" c. . tw t.77am o 30 Fv =0 4x36:14 4 K55dk BFFLECTI4M OlEcK.!-
32
& "E, O"
- A e iso ML* - - \ so x . 9I.33 x \l .'51, _ o..( 4 3. ln ._
E. T. 2.9000X 6iO 6 ALLOW ; = l x l'1 I \ *Ll% \ 2. . o .17 7 in *
- . C.k 35
~^ fo 'k60 1, . uq yggx3g- .-
T CCALCULATION SHEET s CALC. NO C - '{
SIGNATUR
^ ' '~
DATE 7/EA /II CHECKED' '# '
DATE
~ ~
, PROJECT R Aucu o c.ec c nuct. Errr o d ;osuo.OEM W SUBJECT D! E M' I-D)EUUIk D'I 9 DIb -
SHEfT 11 OF M SHEETS e.~ R tt riu W M SiiF'. . Floc Q 8 AT E L l-" i I E - C (* '- u-4"
' Ccqp g 2 s3gg, pagyttrM AT EL(t)14 I' e a B,EAm do. c. . Ib7 1708 6' SLAG 24 iu couc. 4 g QEOc; AVE.TRk : 25-[ [0 5 LO A dim C- := ic,,s ts . b): 2. 33 YLFt .
SLAB (.wtT) :,-(2125 .)(0 Ikh 0 340 +S$+"
, , e .
7 STL. Deck t MG : - e c.co S L - 30 5 7t-8 13,E A m w r. ;- - c.o 15 w t
-* rs=6/ l Com.T. Loe.oS :-
-o c5 c Ru646
'8 TcT AL c O 4(O REF. SiiA M No. g(@
i2
'LA : 0 41tsr.:6 67 Ft :
~2 33 t</L1:6 -
13 Rt: 12 Ox22 5
D otX 14 9+ EX f 0 25 " Z nx sod /2 _ 54 6
j
's 3c 5
]is 17 gt, gg 7g, { $* e 17 01Xib t- G-4 7X6 + 2 3 3X3C- 72 .,, g[, ), K is -
ici5_
]
,a 1
2o NmA>e s 5T- l X l4 5 - 2 33x lt T/2. - 5x 42. 5 , 474 7f tae . g.
21 22 1 3'f W 2.7 x ll4 ( ( O N SID E E. E E A M TD BE !. ATE R A t.LY st!PP c RT E 2'
3 TEEL Deck ),
6xx
7.9S in 3
rwx 3 4oso ind ,; d, 27 29 in j hw s o 57 in.
" n Exurn cHEct .
=
=
-k M = 474- 76 t2 .19.os W. Fu , c.co.w 293 ' z+ usi.e...a
. '. Sxx . .
Sil EA.A C P EC K. :- -
so Y M^* 2 '54'6 . c.4x 36 = 14 4 ksi-12 ct . tus 27 2s x 0 57 * .3 5 / ssi.. Fv '
O>>
i
, .Desc.ec.Tiou catex :- A _~ tso s t _
~
ieox 47s.74 xso s' EL zeooox4oso Q p LM \ '2 :. _ 30'5'* \ *I- ., \.0\6 in
O ' $b 5 *
. O. k.
m 16o 36o
i
/
CALCULATION SHEET '~'
~~"~'I d CALC. NO C-( SS-l O l SIGNATUR E - "'
--' DATE b CHECKED l'"
DATE
~
~ PflOJECT PAMCDC <*'o
- - M LI C L - STAT \OO JOB NO. UEI d
b N
~
SUBJECT D t i? M L d '~ M E R ATO P- A3.'i l D i e l 4 SHEET !'O O O SHEETS rrpurupaL ' r s = L . ct o g et s p - g er.u _r e :.i in , .s. . .e F .
CcuTED i n x. t g s STE EL FRAMtNG AT EL.C+) 34-4 S. 31 7 fp6 rp3r7 i BEAM No. @ ,, ,, 1N5 Ur zG 5
SLAB: 24 lN CcNC.t3 DECK ole THK.=Z5 6 ! Y v [so-z 33 M"-
, .y '.
I**
LOAtt%:- re n KsF.
L:30 5' 7 s LAG LWET ) :-(3125)(016 p) = 0 340 .
- [
8 STt.. decking :- = 0 006 Rt R2.*
But i WT. :- : o.c15 CONST LCADS :- -o-050 TOTAL = 0 410 12 LJ : C 41 ts; X 5 67 Ft. : 2 33 14/ LFt . FOR. Fr_
REF Q 2 s x h o S- , 33 7.xi,2s-t4 M AX . - Id L .* RL P x j.2 5 : z . 3 3 M c s 3 is 8 -
4 4 3 4 -
T46 Sh %
4 ~
V M.w :WL+Pi .t. P.z. g z .3,-; x g o. c; , g .,. g . 7 . :. 7 2 42* .
is . 2 :. ,_ . z. .
TT4Y W 27 X S4 (CONStDER. BEAM 'To BE LATER ALLY Suf f cRTED 3Y STEEL DECK ) ,
$<x :- 2 6 IN ; Lxy : 2850 My d : 26 7 t id ; 'tw : c.4 6 W .
22 2a
L EX U R ~ C H E. C K *. -
22 '
25 d;w M a ^* - 348 S 'x 12. :. t9 66 ud 4 24 wsi :. o. v .
= .. Sxx z n.,
2' SHEAi;t CMEck 1- .
s' Iv - Vma = 7 2 4 2- ., g .g g ,, g ,
' d.tw Zs 7txo 46 Dws-ilcTro d ege cy,,, t - A sto L4 PM P2.0. 3t$, : 4[ l
' 3"/ - . 4 3 84. EI. 9 4 8 El ,24 EI.
i x f.5_E 2..j2S seso.svt72.8 oco x 2 & so sx Ao.Iki7za 3.i . 7 x i.ze. .
33 2;jgA x -:4 K ZS C Oo M2.fSo 24 %2 Soo0 X2KGo
, h,x ?,0. s .--% x t.zs .) tr z. s = o.s4e"+ o - os t"+ o o 9 G.%
0 707 si,.. L
. . o. a
' I 4
= ==>*.*
CALCULATION SHEET CALC.NO C'560*lo -
SIGNATURE C*e -A' DATE E, U ## CHECKED' # '" ATE
~ ~
PROJECT I2 A N f' W O ' CECO 14tl C L - ST AT10 b3 JOB NO. I2Md*S50 i
SUBJECT DIESCL O FN E D' C S R E l' ' L OENL fw- OF M SHEETS
$T O 't f* T H D b. L STE E L. . rt.co R.S AT (+) ' 61 6,, SHEET. C4 2 4 '- 6
' VO I O 2 ST E.E t. F rat 4L RG AT 1L,(,+) is'. 6" ; g,g P= 5froR MAY. M0H 3
SEAM M O.
stAa : z4 m.Coac. + 3
{ orCuve.Tx..= zs5
.l,. . e .. +
uJs : 6 Kfat.
+ <.
5 La ADtM G:- W 5 F.
c L ~ -30 5 f t - ~
SLAS NET) :-(2125)(016 "/rl.) = 0 34 o m x.
- 7 STL.necmac :- : o. c es g,:44 65 g s .44.L=
w.
s geTE:-uSE 6 AT REACTION PT. TOR EE At4 WT. ;- :.c.OI5
- 0 0 :,0 M Ax. SucAa..
COMST. (cab 5 *- ,
TOTAL - 0-410 BrAM SPACnMCr 5 -' #- C/c 11 "LQ = 0 41 KSF. x f U Yh. : 15 R/ LFt -
a g % .:. OL' ,PL , 2 6 x S c) s} :stsa. , uc . 5 re.g .
} is S 4 -
& 4
= _.z 6 x 30 5 ., g V 84x = e.___L + P , 44,45 e 17 , "[. 1 .
TR'T W77x84 (CcHSIDER BEAM TO BE.1.ATEEAtti SLIPPORTED S'r STEEL. DEct . ) ,
Gxx = 2 G th Ixx: 28 50 In* y cl. = 26 71 iu. tio - C'4e iu.
mi !.
" FLEX URE CHEhe -
F:r : "16 k si .
Obx: S** M= = 340 5x :z. ,.g9,g gic3;, 73, - o.66x F3s r4 w.si.
J 213 _, o. v .,
SHrAR cuECK ;
27
=
8v _%, _ 44 65 < % 63 Fv = c +i F =3 14 4 w.si.
= d.tw Z4 7i x o 46 .,
e, x ,
DEFLECTIOM CHECE.:
31 1
) " - d _ s to L 4
4 'PL
__5 5 8 2 6 >c 16dx l72 E 3 8 4 x. 7LSOOOK 2.8 50 ,4 & x2Soo ox2f52
. 5x30 5)c 172 8 384 EI. 42.EI
= o.6l + 0-06 =. 0- 67. la . (, Aattom = L^'
l
3. 3(O =l.0164n O . K.
CALCULATION CHEET cAtc.No C659 to SIGNATURE o bM- M q DATE OM -
CHECKE - ATE 3!
a o STATION aos go, /2 W- 6W PROJECT RA N CHO S Nu c_ LEA.R SUBJECT DESEL. GEN E MTO R 6 l_.D C, SHEET 15 or M SHEETS, STR uc,7-U D A L STiEEL nD EL . M 54 '-6 4 0 . - . - .
~
. . . DESIGH FoR. 'i i & TYPE _ B eAMs ~
3 y . __ . _ - . _ _ - . _ _ . _ . .
4 5
e l0 ?'
h?E'. '
1 A va)alale. O fh '
j
~
.f 7
k ' {- .___ M'-6" _4op_olcoof_ slo (>
.a 3 ._., I ) .=._ __3 . _
3 2'-o '
roof 9loh'+hekru 1 ,J O'- S clecking :
_._._3 t_, _.. @__, .
..{.
18 'r6 - -log w,2,8 y _
._2i _ _.
O'6" concrmp% ad_co_mes- mes i2 _
1
l>_73,~_ 4ank '
ll _ , 5 '-8 " ,, 5 '-8 " , S'8 ~ .
5'-8 "/h o[-3 * - meun F._ju e s O ; o '-t' a llo a.M&l<e+.
a
, .}34s9 . . . - _ _ . .
9 O-5 " - ct ne h Ao(k epiectio i :i;
O!F -t..
: . i
- lo % " 'adat/ah/e !
sk(v) _ seu. Ju).
.. . _ _ J d .L ] 'F1 L "I#_
Laceds _
2,
_ - . t. io'-2 ~ +
A v. Sek. -
il- - . - .
22
% L (w ef) { 2. izs) -(o.16) = o.34o _k6F .._ _
2' Steel elecking o.cos._._ .
2' Cen.s4. loads o,oso _ _ _ . _ _ .
25 o.ses wsr
= -
Linear iacedine w= (o.3 9 5) (s.! 67M..
- QW z.) =_2..ogM~ 2.8 lc.te- ^_ .
2' 30 z.24 - - - -
M ,= wL*+ PL 2.za,00.nF 5'-Oo.r 3,
3 4 g #__y_0 - s2.ig ,x
~ ~ ~ ~ ~ ~ -
33 b, *~ wLg+ P,_i_ = (2.26)[Io.i7) g + ~ ~ 5 I=c. (, C ~~ ~ -_ - .-
l CALCULATION CHEET " " " *" l CALC. NO C 6 6 % lo l SIGNATURE b W b DATE O22 'bE CHECKE DATE f
' [ [ .
PROJECT RANcip0 deco Nuc LEAR. STATroN ;og go, I2 334- 669 SUBJECTD EEL GENERATOR SLbG SHEET IS OF O SHEETS' STR uc.Tu 9 A L STEEE-L re; EL. A 34 '-6
1 G bESIUI FOR, @ (CON 7'j .- .
TN W 6 x3/- . . _
5 ,
[= d.o.o in ; dw = 0.28F in $4 = 3 l ~U Fr
._ _ _I. =_[l I 0 . in 4 ; I S = 2 7. 5 _.tn 3 Shesses _ _ . . . - _ _ _ . _ _ _ . _. _ _ _. . _
to 7 ..-y 4 2 , g ,, .; z --_ . . . .. -- . - - - - .-(56 -
4= y-=
=_ l 8,4 ks; e E =_ o.66y. F " 24 to.
y
-y 16. 6 --
3k -- - - -
is jv =j 4~ (8.zo)(0,2ss) 7.5 ksi <c Fv .4 F1 = !4.4 ks
~
_ _ _ _ . _ _ .
3 4re % es 0, K -
Deflecen _
18 m
5mL 4 +
PL 3 = (5)(2.2s)(io.rt) 62f (sI(io.ri 12)I=_.
g = 384 EI 48 EI
,, ('564)(27000) (r 10) +(48)(27,000)(i 22 L.
Io.iv-12.
== 0.232 i n < .A cW
~~
O' M la 23 360 %o 24 2'
bePleckn O.W.
" check leo,n wei h+
2e $ assurved
0. o3 I' = o. O I4 [ra4:o M=W <c. O.O2 -
O, K ' -
2.24 ~ ^
31 e
34 -
36
I t.Ac osas srs CALCULATION CHEET cat.C. NO; C 60V~l0 S!Ib SIGNATURE ' 6*
v Nb DA(E9 cr 2 2d N CHECKED ATE s s RANc40 ECO NUCLEAR. STATION aos no, I2 3 34- 669 PROJECT GE NE RATO R BLDG SHEET 17 OF M - SHEETS EJBJECT DidSEL STA.UCTU R AL STEEL db G L . /4 3 4 '-6' g .
I 1 ' u.s (M,,~) k . _ . .
) ep -fh o vo.t i cdle d c .
= _ _ . -
g_ _ . .
p __.
r ,, ,, ,,
1 1
$ 4 to ,
1 ,,
p
,, g ,, p .f. } :::. l[
_ tw a c -: '
2 ,_ . 6 -e st - _
Lectds _._ _ .
gu _ _ _ _ _ _ . _ .
'* [ 3, g,;_. --
(~' g ._. . . _(io.n)(s.o) ~+ 4.o(.3 k._..-
P = (o. 3 vs) ..-
i ~
M 9~e .
Mx \
23 .J O ) e [f67) +
d.o3) =_155. 2 Ari_.I.
is 152.2. -
~ ~ ~ ~ ~ Lx = (2 3, I U +- 5' D.02) = 25~. ~~f~ k.
i _ _Z 18 Tg w 12x65 . _ _ .
d = 12.I2 in >
Nm = O. 3% ; v%= 65 lb/Fr 3
L= x7 Sb3In" i $n=07.9in
,$tresse) I 26 M ~ 2
== 2 1. 2: ksi < F = 24 .ks;
_ ft,= 3
=
tc 5'g_ g 12. 4 V 2.87
['l
l, cl
*bI '
, (0.3h(lz.lz) . _ - - .
e G+resses o, k . _ _ . . _ -
- M m,. = Gs c s ) d 7) /s = 2. 3 5 < , oz -152. 2.= S .04 ___
DeGecbn w __.
- i 3 A ' P a (5 L - 4#)
2 RL* ' ,s
,, E- = t. 2 4 e 1
+-
<se I %w.LE r '==' " " U E F
l CALCULATION CHEET CAL.C. NO C669-lO SIGNATURE* b> C NM DATE N'N CHECKE DATE !3!
/
PROJECT RAblCHO SECO {Nu c.t_.EAL S7~A-Troy sog no. /23 3 4-659 SUBJECTM6SC-L SENGA A-Tot 8LO 6 SHEET IN OF SHEETS STRUCTu AAL STEEL- GD EL. f+) 34/-6" 1
bESIGN PDR. Q (cout) _ . _ _
6 See pwimS. (a e o/t. _
5 A __ (23, i o)(y3 )2-4,(E67)$ 0H) _ _ _ _ _ .
6
{
~ -
+
24 x (29; o00)(533) - ^ - -
. - + . [5D [l~l) (I A4k + f5')[0.065) (l$4) ...== o.002S=.__\ . -
10 48s(2%odo)(5~53) .--(564)(2% xcl(533) - 900
. . 6 [ .z '($_ _ _ _ _- _\ .- . _ . _ _ _ . - . _ - . . . . _
13 L $oo _ (L /cdl 36o . _ _ . _ _ . _ _
[O, K
~ ~~
s D e..f E -}-;o n _ _ _ _ . _ _ _
17 180 ML Z
~ ~ ~ ~
is b __ 18o 155.2. 4 r72. 0. 52. , =~'f ~ ~~ o~~~K~~
g3
= . .
z.yooo -535 se 572 .
21 22 23 24 l
26 27 29
^
30 35 36
LAO ttt3 M3 CALCULATION CHEET g,_ , o SIGNATURE - e MM DATE O2 ,24. E CHECKE TE , ,!
PROJECT RANCMC 8ECO NLICLEA l 07~4T JOB NO. 0 3 3 b SUBJECT DIES EL GENERATOR. 8 LDG #
SHEET IS OF O '
SHEETS 6TR UCT U 0 AL ATE E L dLD E L. M34'-6 I
1
. DES /6N POK (R) ?-
\t . . - .
S.
a IS P. 51p ~
G *
_ ___
6 y 7 ,
8 d'
,.s42" to'-2 2.is - -
_ . . _ _ ~n _. . _ . . .- _ . _ . _ _ _ _ _
n
. . . . -Loads W - (0.3$5) A y' >l = ~ 1.32- k [FT; T T e- . _
<=
~
e -,
U - (o, sis) (Q(Io.I7) + No,is) '[ 4- (o.osi)((o.ri) 17 $g4 g z-- - - -. -
M, = .12M 8 } + (36'0) b'") + '")
21
2 == 559,8'"
23
\/xv =- s ' + O ' ' ' zK" ") +- is " ) 0.@= ss.e' a
2' Kl 27 n4 TrY
= ,
~
E = 27. 2.9 in j ( = 0.57 in ; w, = n4 L6/Fr; T = 4,o90..*n4 j $ = 297 in5, lil .~ ~
L j
- 33
,, N. = o.uq -(3 as)2.== 33 3 ,g. #
e -
3
sz4.1 = is7 --
\
'[ t .o3 essfi~nov WAs good
t i m non CALCULATION SHEET CAL.C. NO C 9-IO . i
. SIGNATURE N D" / DATE O2- -
CHECKE ATE
/ G \
PROJECT RA+/CAC 45ECO ^/UC LE AR STAT, sog no_ !2W-62 l l
SUBJECT d El 4M b bL3C SHEET 2O OF O SHEETS SYo u cruk A L- STEEE L @ d?L. /;-\; 4 '- b '
i 2
yg3;gg pog g (cont) 3
,$ !-ress e.s !
s !
M= E3 9 8 A2-O(5/ = 2 1.7 Est < Ft = 24 L3;
$* = 5 29f
S=
'y
= = 3. 6 kS,- < h =. lA . A c.SI o
, .t, d #s7)(2729) 10
~
" , Stresse3 or. .
ia D eC!s c-I-lo n io V (3 z
{ A _ PEGL*-4cy 2 pu_ t
+
y (, %) t 3
17 .
L .- . 24(L) E.T g. ' 4 g eI. 334 - ~7
__- 55 (V3)[M5a5)2-4-(io,nf]q4, 5, (5 O.5)b I4 ~~
2. A 4 (2.g oco) (4,090) ' A8 (2.gooc)(A,o?o) 2o a'
+~ Sfl.12 + o. t0 (3 o.5Y bH) l l 22 c 84 - 0.0015 -
23 (27,ooo) (4, o Po).. _. . . _ _ . - . .
667 < 360
D e B e c t;a n .. 0 , K ._ _ . _ .. _ . . - - - _ . . .--
2.
u.__._._...-...-. . . - . . _ _
27
.. i 30 ,
si
_m *
. . . ~ . _ _ _ . .
I '32 . ~.
1 / , --
33 35 .
,. - - _.- -, y _ , ._. _..
~ "*"
i CALCULATION CHEET CALC.NO C~$ 6 3-IO
~
SIGNATURE
^ ^
' ^ DATE 7,!f E !I' CHECKED UDATE
~
PROJECT RAWcun CEC A kltic L . STATIoAl JOB NO. lW d*$64 SUBJECT Uf 64 #1- O E ME D ATO ft T4
O G . SHE T 2! F M SHEETS
<rnue.Tu ut s,T e s t , t=l.c o A $ AT El [M i 6 " . l+ ) 1 44 CouTE D.
2 BERM CdN N E CTlokkS .
3
FRAMEO BEAM CO N oJECTI C fd.5 Cwtra 2 cup ANGLrs.,) . l 5 - - . _ _ _ _ _ _ . _ . _ . _ _ _ _ .W ITR INSE RT PLATES * !
i S eat 4 MAX DESIGli f.dAO CoNHECTie GOLTs. FASTENER FASTENEtt gtAM t* FoA 7
react 457, STRENGM ANGLES. A ~626 N 00LIBLE GEAp EEA9t W . $ CO N N. FOR-M<. SIZE. %iu = 0 45d.twA KO. SI2E CAP.: t. hI!5t) o tAtmmr.
8 ktps Yl.) d- Taste I D N r'oIdf' n
b W27x84 40 5 79 6' 2L9//gh 5' 7[ \26' <7 5tt9 o w27X84-5
= gs.o
'2 M W.la n 5 22.o 34 4" 2LG53ff'a f6 7' 6/tE ? 40x% 8 yr sns-3 ss @@
9[
15 h W27xil4 658 LOO 8* El5%8/g 5 7/3 12 6 * ..
5 245 wa73it4-s et22 N b W27x84 72 4I 79 6 ZLGr.h3/d 6 7/6 126 . f St W17384 -5 7fE s%0 V[ a' W (Sx s5-5 8
WE8xS5.21 o' 3 4 4". Z ts=3%d 3 7' Syg$
@ 3
,8
'" M
c
@ w21nse 4a.ss' 7g & zisys'gg s yg* 2s' 6 =35 0 wa7 xe 4-s 21 wp
~
@ W843\ if $ - 2885'gb 2. 7/g* 50 6 5/g 's":27 *'#!
2 W 8x 3I- 2, 22
3 k W Zx(5-3
@ Wl2.765 2Sd '5 o 6 2/553(63 7/g 76 g#
I tr n g i,y gy7jg h/zpiM -s W27xito 68 3 100 4)(, 2/573/f4 5 72 12 6 94g g 3'
i 29 NOTE .- Fv = d-4 Fy = 0 4 x 3,6 = (4 4 kti.
c(, = DEPTH OF'.IW " BEM tM (McHES CAISC TABLE) t.w - Taictc. Ness of WEG OF"W BEAM IN INQtEt (AtSc TABLE..
4: = NIN . THlCK Altsi OF , '2 x L Titici<Ne.s! oitw" W HICH,EVER 15. LESS
(12 t40 .,0 F EO LT1, , C: DIA OF B ot.TS .
! THE BEAM conHL HAv E. GEE 4 DECLGdEO Fog mi4. As % 1TRINGTH OF MEMEER $kNAs2 f
cADAca-/ cE EW ' F6(1 6EAtw h WitFU w h A L Q f M ff o M I f 10 F O
[ CALCULATION SHEET s " """ I LC. NO - 4 6 9 - I C i
/M SIGNATURE
^ - OJATE 7/3#!S/
CHECKED DATE
~
~b/
- PROJECT RA MCHB SECO NLLCL. STATiod JOB NO. f 2 M A- S 6 9 SUBJECT bIESEL f-F W s n A e P. rAu s t.D 1 NC'- SHEET N OF N SHEETS c:,- Qu e r u o A L ST E EL . F LOO R5 AT E L (* 31 @' ( . I: ( l ? a '- 4 ' '
2
. co N T ED.- ,
,r a p 32C)x8"e
/ 190 % or WELD 59 2
, STttDScEttTEp. COON; p gg z 3
c ..T. / , _-
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...GPACEO (Z O.C.
5
(.d -
i d BIEGINt4 t trG. . 6" i
p. ~ j

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m,1 M A'< Fl2.c ta E A .
7
h. 1
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d -$iu os Ftt R.tllSH ED
. l,.'b -
QI I
i S
s. S-( STRucTttRAL ;
-.E STL. C.09TRA-CTO Is C
! & IMITA LL ED S'T lG i
I d- HIM iM F(ELD -
12 , e; x -
i. ', ;.
".vi is !: 4*
! ' _ - /wgt3
. i 2
g / \ B ,
y _ . . .
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i is -
19
~
20 2i
['a-3
,\ # Z7 Y/ 2I l l
,- n ,y 22 l'43 2 4
e th -
l! ERECTtoM cup t_
l = ; AT THf. OPTLOM OF CONTRACTOR,, ,
25 - -
, , . VC TIo N A a
', ( $7 h ,SoLTS 27 ,
w , g' 15/ [$ HOLES tA BEAM WCS ;
u
. gEr786 g[ Stari i.;J ANGLEi, H ARDEnf0 MAstif RS ao N
'+u
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j
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33 - -
3 -
_: 7 Lsx U.x2 3/s cue A.wates.
= -
1 J
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v CALCULATION SHEET ~,
CALC. NO O* 5 # C-IO
~ ~
" ~ ~~ I #
DATE CHECKED ' ATE SIGNATU PROJECT RAMCMA SEC0 Mu Cl . CTATIO M - JOB NO. I2 3M
b@
i .-
73 OF O SHEETS SUBJECT C1ESEL C E N EN ATOE Eill LD' M C-
=8 CCR1 AT CL [+ SHEET \t7-4 L gi t;;- ) 2 .a . :
[fG u tilt 0 A L ST E E L
~1 CONT 3 D .
2 3
STEEL 1: R. M M tJ C2 AT E L . C+) 15 - 8 $ C+.) 3 4 '- 6" 4
5 DESIGN OF LEDGEE A N GLE s
g 7 l_ _l (- ,
. [, ,,t
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/ \ *t-P 4 -4 ImEM PI- TYIE h N -.
8 1 4 .
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f s Qn"
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CHEct FOR M Ax . r A h]TILEVEC. ' cI Assurns L 5 x 1x5/g(ty ,
1
. . 3 -
= '- .. a. = %4g : 4 5/245*
4 DEFLacTica @ cat 4TtLEMER 590 &: LO o-
" BEI DEFLECTt ord @ htD.D LE OF 'L' = Wd
" ~& S 4 EI. .
( FLXE0 G BOTH EMDS).
=
4
=
, ,. us ca. _
eL4 .
=
8 EI L84 EI .
t =
' " le M= ;. c. = L f, et 4 5 :.l 71
= 42 8 6 ~4 7. 63
f. fnAx, D14TANCE tid GER. L caN BE rriso s
" " 3 0 6 03 CAtGLEV E9 : q : 1-7! FE 'e ( ' - 8/.g -
O=
_u-
. _ _ l l 35
$5 .
l
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CALCULATION SHEET
CAL.C. NO 0'563*IO SIGNATUR E DATE I 3, # CHECKED DATE
~
, 1 s PROJECT PANCMO 6C00 idllCl SY YI O N JOB NO. O U-
SUBJECT Dt25T- Cr ? dFC M o E E'11 L C I SIfe M OF SHEETS 9'rp u c T U i> A L 'f F F G . FLOO 2 5 M GLL-A)SHEETI A !'~! <
I4 A1N-4 i
Co t4T E D. -
1 s CHECK F1 EX LI RE *.-=
10 : I3K/Ft ( RYT IbEAM) C A LCS.)
C. Co vs rosa. THE WORST CASE) 1 1*3 x 4 6 s
th = (6 L - -
2.*f7 F 6 - tc.
o L Z. 12-7 yQy {$glg g byg , l. 3$ { ,
$o[. of b
Su :- t 24 ,63
3'776 '"3 O
. k, 2 !9 x tz ,s i .s w $4 , , z.ie x a , 7,o g, m 3 77., %
j io @, nor - 1 - 8.9 3. 7M
@ acT.cr4 @rce
" ANGLE ); u HEED C.o NT1'd4ouILN G.Y $TE E!. FLcc R DECK. .
12
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c. e .
O. 6x FU = C 6x36 : H wti.
a 7 v . I ta
/ NI
N k*
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.': J
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in - w. .
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6d6 7 g Z $,,.= e Y fea'clF.=( b )
at j 2 7 x 1?- .<c. S r254
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5 $9Y . 5 49'Tx C . l 7 9 0 lssi, 2* b I
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m -
a 27 hRF Fb.
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+ 57917D .
o 6 9 8 ( f 1.d.R ,
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= G Bar - % .= na q u s i , 4 2 2. . scsi . :. _ o. w . .
" WEL D DE S,t G M - .
m bT REsi OF WELO Duv_ To MomEMT.
= ,
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a. blN Call. ~ lMCM . *
= bd 4x5 -
as
" CALCULATION SHEET "
CAi.C. NO C* d6 b * ! O SIGNATURE DATE 7!I 3,/ I CHECKED DATE
~
- PROJECT RAvicu o esto N(ICL ST ATic N JOB NO. 57 *$
b 9 N E 2 I*TO E Sll il Ol N SHEET 25 0, 44- sHsETs SUBJECT D i i 1 '" L STI? U C TU 9 A L s 'r!"TL , FL O O RS fi EL/*)(plt : CL %s!<
C2OMTE_D 2
-3 .[,7 , s,Ta t st or wato ouc To v rartcAt t.oA o .
s P: 1.E .7 4 D 5 85 x,
1 7
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8 h_ ,. g,[}[ g [g g gap, g gpq s 2b 2x4 8
10
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15
) 17 D mid - A s. PER. 'TA TLLE' l .17 2 A oF At S C. .
= -
M on tat At. nicz.an d er w mcsa net sei,4ec = 3/g
,9
= ., Dn19 1/4 t acq' o < D mia .
21 .
==
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V&' .
23 2.
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(( ALLrf La t t.D $T& E. 4" Lon.
26 17 29 30 31 33 l
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.' 1 CALCULATION CHEET CALC.NO. C~ D ~O SIGNATURE
- N' DATE 7!=I! ! CHECKE
^ ' ~
o IE !# !#I .
O ,
PROJECT "* W" M'd - 7"# 'O JOB NO.
~
~~
~
~ - -
SUBJECT *N d ' # P"~' D ?*-?#- SHEET 26 OF O SHEETS e; ~.a. *r-; =L.e- :t _- . t .s > _: . .;.:'
1 Fi W H e c P s as.1 c=e:MEc7icir ,
3 I.};. a k , k2 tw -3.S *+ *El
2 . 3. 71C~
38 matx.
DETERHWlF~ 7"HE kJE'Lb Ei_32 5
2L5s3L% Wira S 2047'5 Botr 'DsA . , 7f' nL g .
v 3 y7 g l
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PROJECT R A N ( u rj ffro AJ b & T4W0N JOB NO. IU3
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LC.NO C' S ba9*1 O S12 NATURE N # - - DATE '
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T ' O d JOB NO. 'E -IbS SUBJECT D' y g( (, E O M CdQ % t $_ C t tTG SHEET 31 OF M SHEETS c n ; c - u o 4 ._ t c et . : < oc .U A n 4 /P' 4 mm o ; f
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en 31 e , 32 - . ~_ - [ n . .......-.....-......--.-.-_..-..--a----- -7. . NRC Ouestion Are there any bus ducts or cable trays which penetrate the barrier between the train A and train B diesels? District Response There are-no bus ducts or cable trays which penetrate the 3-hour rated barrier between the train A and train B diesels. s I i I

1 a

4 l ~8. NRC Questions Ducts exceeding four. feet in width are shown without sprinklers under them. How does the District comply with NFPA 13 on this issue? District Response A sprinkler will be added by ECN R-0767 under the wide duct on each mezzanine to comply with NFPA 13. 4 4 . 1 l

9. _NRC Ouestion Summarize the changes to shutdown procedures, for a fire in any fire area, as a result of the new diesels.

District Response The changes to shutdown procedures as a result of the new diesels are summarized below. These changes will be incorporated prior to restart.

a. Actions resulting from a fire in any fire area where alternate shutdown is required.

- Operator action is required to secure isolation in the NSEB. - Operator action is required in the new diesel generator building to negate spurious fire-induced conditions and restore normal diesel generator operation,

b. Actions resulting from a fire in any fire area where alternate shutdown is not required.

- Operator action is required in the control room to negate any fire-induced spurious conditions in any one diesel generator. I 6 L t i

10. NRC Ouestion Sprinklers in the diesel generator building appear to be spaced approximately five feet apart. Has the District addressed Cold Soldering?

District Response Sprinkler lines in the Diesel Generator Building are spaced approximately five feet apart and are located midway between the root beams. The sprinkler heads are physically located just above the bottom of the beams and are therefore, not subject to cold soldering. I [ i t

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

ML20206H162

Text

Dear Mr. Mattimoe:

Enclosure:

Dear Mr. Rodriguez:

SUBJECT:

Enclosures:

Attachment:

- r-J.py.w.e.y.:,,p.~:; ' . ~ ,TM.y.G.W. ,.. g.Ke~.

sn*- ma.n s.neww.vw'ararexs s w m

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