ML20137L222

Rev 1 to Proposed Amend 137,changing Tech Specs to Add Water Deluge Sys in Area of Auxiliary Feedwater Pumps

ML20137L222
Person / Time
Site:	Rancho Seco
Issue date:	11/25/1985
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20137L201	List: ML20137L199 ML20137L222
References
TAC-59510, NUDOCS 8512030387
Download: ML20137L222 (10)

Text

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RANCHO SECO UNIT 1 )

TECHNICAL SPECIFICATIONS  !

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' TABLE OF-CONTENTS (Continued) I 2'Section Page 137> 3.14.5 Fire Hose Stations 3-56a

-- < 3.14.6 Fire Rated Assemblies 3-58

'3.15 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION 3-60 3.16 RADI0 ACTIVE GASE0US 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 3.22 RADIOLOGICAL ENVIRONMENTAL MONITORING 3-81 3.23 LAND USE CENSUS- 3-87 3.24' EXPLOSIVE GAS MIXTURE 3-89 l l

3.25 FUEL CYCLE DOSE 3-90 3.26 INTERLABORATORY COMPARIS0N PROGRAM 3-92 '

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I Proposed Amendment No. 137, Rev. 1 iv "8512030387'851125 i PDR ADOCK 05000312 PDR l P_ -

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RANCHO SECO UNIT 1 i F 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

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3.6-1 . SAFETY FEATURES CONTAINMENT ISOLATION VALVES 3-40 l

3. 7-l' YOLTAGE PROTECTION SYSTEM RELAY TRIP VALUES 3-41a 3.7 ' VOLTAGE PROTECTION SYSTEM LIMITING CONDITIONS 3-41b 4

3.14-1 FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS 3-55 137V .3.14-2 WATER SUPPRESSION ZONES ~ 3-56b,c 3.14-3 CARBON DIOXIDE SUPPRESSION ZONES 3-56d,e

< . 3.14-4 FIRE HOSE STATIONS 3-57a,b 3.15-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3-61

-3.16-1 RADI0 ACTIVE GASES EFFLUENT MONITORING INSTRUMENTATION 3 3.22-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3-83 3.22-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS 3-86

. IN ENVIRONMENTAL SAMPLES'

4.1-1 INSTRUMENT SURVEILLANCE REQUIREMENTS 4-3 4.1-2 MINIMUM EQUIPMENT TEST FREQUENCY 4-8 4.1-3 MINIMUM SAMPLING FREQUENCY- 4-9 4.2-1 CAPSULE ASSEMBLY WITHDRAWAL SCHEDULE AT DAVIS-BESSE 1 4-12b

'4.14-1 SNUBBERS ACCESSIBLE DURING POWER OPERATIONS 4-47c 4.17-1 MINIMUM NUMBER OF STEAM GENERATORS TO BEL 4-56 INSPECTED DURING INSERVICE-INSPECTION

4.17-2A STEAM GENERATOR ~ TUBE INSPECTION- 4-57

[ 4.17-28 ' STEAM GENERATOR TUBE INSPECTION (SPECIFIC LIMITED AREA) 4-57a U

. 4.17-3. OTSG AUXILIARY FEEDWATER. HEADER SURVEILLANCE 4-57b,  !

4-57c i- 4'.19-1 , RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 4-64 1 SURVEILLANCE REQUIREMENTS ~

!~ 4.20-1 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION 4-66

-SURVEILLANCE REQUIREMENTS

, Proposed Amendment No. 137, Rev. l' iX

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation ,

3.14.2.1 (Continued) )

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b. Two separate water supplies containing a minimum of 2,000,000 l gallons each.

c. An OPERABLE flow path capable of taking suction from the circulating water system and the Site Reservoir or the Folsom South P.nal and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation ,

valves to the yard hydrant curb valves, the last valve ahead '

of the water flow alarm hvice on each sprinkler or hose standpipe, and the last valve ahead of the deluge valve on each deluge or spray system required to be OPERABLE per Specifications 3.14.3.1 and 3.14.5.

3.14.2.2 With one pump and/or one water supply inoperable, restore the inoperable equipment to OPERABLE status within 7 days or, in lieu 137>< of any other report required by Specification 6.9, prepare and .

submit a Special Report to the Commission pursuant to 137>< Specification 6.9.5.E within the next 30 days outlining the plans and procedures to be used to restore the inoperable equipment to OPERABLE status or to provide an alternate backup pump of supply.

3.14.2.3 With no fire suppression water system OPERABLE:

a. Establish a backup fire suppression water system equivalent to Specification 3.14.2.1 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. In lieu of any other report required by Specification 6.9, submit a Special Report in accordance with Specification 6.9.5.E:

1) By telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

2) Confinned by telegraph, mailgram of facsimile transmission no later than the first working day following the event, and c.

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In writing within 14 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

d.. If a. above cannot be fulfilled, place the reactor in Hot Standby within the next six (6) hours and cold shutdown within the following thirty (30) hours.

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l Propc:cd Ame@nt No.137, Rev. 1 3-54

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS ~

Limiting Conditions for Operation TABLE 3.14-1 FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS. (Continued).

Detection Number of detectors in zones-Zone' Instrument Location All Required to be OPERABLE

- Heat Flame Smoke l

87 NSEB Computer Room B 0 0 5 89 NSEB Computer Room A 0 0 5 104 . Technical Support Center. 0 0 15 109 Chemical Lab Area - 0 0 19 Auxiliary Building 4

- 137>< 110-- Auxiliary Feedwater Pump Area 0 4 ,

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l Propo' sed Amendment No. 137, Rev. 1 3-55c l

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS

' Limiting Conditions for Operation l

137>< -Table 3.14-2

, WATER SUPPRESSION ZONES ZONES AREAS

137> .3 Control Room - Turbine Deck, Auxiliary Building 5 South East Uncontaminated Area - Turbine Deck, Auxiliary Building 6 North West' Uncontaminated Area - Turbine Deck, Auxiliary Building 7- ~ Contaminated Area - Turbine Deck, Auxiliary Building ,

10 Mezzanine Level - Turbine Building 18 Air Condition Equipment Room - Mezzanine Levels  ;

Auxiliary Building 19 Communication Room - Mezzanine Level, Auxiliary Building l 20 Electrical Penetration Room - Mezzanine Level, Auxiliary

- Building

- 31 Auxiliary Lube Oil Area - Grade Level, Turbine Building 32 Main Lube Oil - Grade Level, Turbine Building 33 Hydrogen Seal Oil Unit j ,

~34 Heater !iater Pump Area - Grade Level, Turbine Building

.35 Main. Feed Pump Area 1

< 40 North Diesel Generator Room - Grade Level, Auxiliary

< Building l

l Proposed Amendment No.137, 'Rev.1 ~

3-56b

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RANCHO SECO UNIT 1 '

TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.14-2 WATER SUPPRESSION ZONES (Continued) l ZONES AREAS 137> 41 South Diesel Generator Room - Grade Level, Auxiliary Buf1 ding 42 Electrical Penetration Room, Grade Level, Auxiliary Building 1

43 Chemical Mix Area - Grade Level, Auxiliary Building 46 Hut Area:- Basement Level, Auxiliary Building

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47 Pipe Penetration Area - Basement Level, Auxiliary Building 81 NSEB B Cable Shaft 82 NSEB A Cable Shaft 83 NSEB Corridor,1 foot Level 84 NSEB Corridor, 21 feet Level 85 .NSEB Corridor, 40 feet Level 37 NSEB Computer Room B

<- 89 NSEB Computer Room A fi Proposed Amendment No. 13i, Rev. 1 3-56c i T f

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation  !

Table 3.14-3 CARBON DIOXIDE SUPPRESSION ZONES ZONES AREAS

-137 ' + 11 West Battery Room - Mezzanine Level, Auxiliary Building 12 West Battery Charger Room - Mezzanine Level, Auxiliary Building 13 West 480V Switchgear Room - Mezzanine Level, Auxiliary Building 14 West Cable ~ Shaft - Auxiliary Building 15 East Cable Shaft - Auxiliary Building i 16 East 480V Switchgear Room - Mezzanine Level, Auxiliary

Building-17 East Battery Charger Room - Mezzanine Level, Auxiliary Building 19 Communication Room - Mezzanine Level, Auxiliary Building.

36 West Nuclear Battery Room -' Grade Level, Auxiliary Building 37 West 4160 Y Switchgear Room - Grade Level, Auxiliary Building 38 East 4160 Y Swit:hgear Room - Grade Level, Auxiliary Building 39 East Nuclear Battery Room - Grade Level, Auxiliary Building.

'40 ' North Diesel Generator Room - Grade Level, Auxiliary e Building J

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Proposed Amendment No. 137, Rev. 1 l 3-56d i

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o. .e.

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.14-3 CARBON DIOXIDE SUPPRESSION ZONES, Continued ZONES AREAS

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137- + 41 South Diesel Generator Room - Grade Level, Auxiliary Building 53-54 Turbine Area 75 NSEB Switchgear Room B 76 NSEB Switchgear Room A

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77 NSEB B Electrical: Equipment 78 NSEB A Electrical Equipment l 79 NSEB Battery GB

+ 80 NSEB Battery GA Proposed Amendment No.137, Rev.1 3-56e

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards

a. Once per 31 days by visual inspection of the station to assure all equipment is available at the station.

b. Once per 18 months inspect and replace all gaskets in the couplings that are degraded, and remove the hose for

, inspection and re-racking.

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c. Once per three (3) years, partially open hose station valves to verify valve operability and no valve blockage.

d. Once per three (3) years by removing and replacing all hose with new hose that meets or exceeds NFPA guidelines or recommendations.

137>< 4.18.6 Fire Rated Assembifes' 4.18.6.1 Each of the fire rated assemblies specified in Section 3.14.6.1 shall be verified to be functional:

a. At least once per 18 months by a visual inspection.

b. Prior to returning a fire rated assembly to functional status following repairs or maintenance by performance of a visual inspection of the affected fire rated assembly (s).

Proposed Amendment No. 137, Rev. 1 4-62 0

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls Special Reports 6.9.5 Special reports shall be submitted to the Director of the Regulatory Operations Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

A. A one-time only, " Narrative Summary of Operating Experience" will be submitted to cover the transition period (calendar year 1977).

B. A Reactor Building structural integrity report shall be submitted within ninety (90) days of completion of each of the following tests covered by Technical Specification 4.4.2 (the integrated leak rate test is covered in Technical

< Specification 4.4.1.1).

1. Annual Inspection

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2. Tendon Stress Surveillance

3. End Anchorage Concrete Surveillance

4. Liner Plate Surveillance C. In-Service Inspection Program x '

D. Reserved for Proposed Amendment No. 43 137k- E. Status of Inoperable Fire Protection Equipment 30 days (3.14.1.2, 3.14.2.2, 3.14.3.2, 3.14.2.3, 3.14.5.2, 3.14.4.2, i -4 3.14.6.2)

F. Reserved for Proposed Amendment 125 G. Radioactive Liquid Effluent Dose 30 days (3.17.2)

H. Noble Gas Limits 30 days (3.18.2)

, I. Radio-Iodine and Particulates 30 days (3.18.3)

I Proposed Amendment No.137

, 6-12f s