ML19319D891
| ML19319D891 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 11/25/1977 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19319D888 | List: |
| References | |
| NUDOCS 8003270550 | |
| Download: ML19319D891 (17) | |
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RANCHO SECO UNIT l TECHNICAL SPECIFICATIONS DEFINITIONS 1 9.4 Monthly - A time period from tne first to last day of a calendar month spaced to occur 12 times a year, l.9.5 cuarterly - A time period of three calendar renths spaced to occur 4 times a year.
l.9.6 Semi-Annual - A time period from January 1 and July I covering the sucsequent six months.
l.9.7 Biannually - A time period of 24 calendar months spaced to occur once in two years.
1.10 SAFE ["
Safety as ased in these Technical Specifications shall mean nuclear safety and shall encccpass all systems and components that haec or may have an effect on the health and safety of the general public.
1.11 FIRE SUPPRESSION SYSTtMS 1.11.1 The FIRE SUPPRESSION WATER SYSTEM shall consist of. water sources, pumps and distribution piping with associated sectionalizing control or isola-tion valves.
Cuch valves include yard hydrant valves and the first valve ahead of the water flow alarm device on each sprinkler header, hose standpipe or spray system riser which protect nuclear safety components.
1.11.2 The FIRE SUPPRESSION CARSON DIOXIDE SYSTEM shall consist of a CO2 source and distribution piping with sectionalizing control valves which protect nuclear safety components.
SbO 8003270 1-6
g RANCHO SECO UNIT I TECHNICAL SPECIFICATIONS Limiting Conditlens for Operation 3.14 FIRE SUPPRESSION 3 14.1 Instrumentation Soeci fica tion 3.14.1.1 As a minimum, the fire detection instrumentation for sach fire detection zone shown in, Table 3.14-1 shall be CPERASLE.
3.14.1.2 Vith the number of instruments OPERABLE less than required by the Minimum Instruments OPERABLE requirement:
4 a.
Within ene (1) hour, the zone will be centinuously occuoied or a fire watch patrol will be established to inscect the zone with the Inoperable instrument (s) at least once per hour; and b.
Restore the Inoperable Instrument (s) to CPERABLE status sithin fourteen (IL) days; or c.
Prepare and submit a special report to the commission, pursuant.. _ _ _ _
to Specification 6 9 2E, within the next thiyty,(30) days.out11ning_____
the cause of inoperability and the plans for restoring the instru-ment (s) to OPERAELE status.
3 14.2 Water Systed Soeci fi ca tion 3.14.2.1 The FIRE SUPPRESSION WATER SYSTEM shall be OPERABLE with:
Two ri h pressure pumps each with a capacity of 2000 gal / min a.
g with their discharge sligned to the fire suppression header.
b.
Three separate water supplies containing a minimum of 2,000,000 gallons each, c.
Automatic initiation logic for the operable fire pump.
3.14.2.2 with less than the above recuired equipmen,t, restore the inoperable equipmen t to CPERABLE status within 7 days or prepare and submit a Special Report to the Commission pursuan~t to Specification 6.9.2E within the next 30 days outlining the plans and crecedures to be used to provide for the loss of redundancy in this system.
i 3 14.2.3 With no FIRE SUPPRESSION VATER SYSTEM OPERASLE :
a.
Establish a backup FIRE SUPPRESSICN WATER SYSTEM within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, t
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RANCHO SECO UNIT I TECHNICAL SPECIFICATIONS Limiting Conditions for Operation
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3.14.2 3 (Continued) b.
Notify the Cornniission pursuant to Spe'cification 6.9.2E outlining the actions taken within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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c.
Preoare and submit a Special Report to the Comission oursuant to' Specification 6 9 2E within the next ten (10) days 6utlining the cause of inoperability and the plans for restoring the system to OPERABLE status, or d.
If a. above cannot be fulfilled, place the reactor in Hot Standby, within the next hour and Cold Shutdown within the following thirty (30) hours.
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RANCHO SECO UNIT I TECHNICAL SPECIFICATIONS u
Limiting Condition for Operatio'n TABLE 3.14-1 FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS Zone Instrument Location Minimum Operable 1
11 Battery Room, Mezzanine Level 4
12 West DC Control Room, Me::anine Level 2
13 Vest 480 VAC Rocm, Mez:anine Level 2
14 West Cable Tray Area 2
15 East Cable Tray Area 2
16 East $3 VAC Room, Mez:anine Level 2
17 East DC Control Rcom, Me::anine Level 2
36 West Sc :ery Room, Grade Level 4
37 West 4160 VAC Room 2
38 East 4160 VAC Rcem 2
39 East Battery Recm 4
40 North Diesel Room 2
41 South Diesel Recm 2
44 Reactor Coolant Pumps A and S 1
44 Reactor Coolant Pumps C and D 1
- 45 Electrical Penetration Area, Grade Level 2
'47 North -20' Level, Auxiliary Building 2
48
-47' Level, Auxiliary Building 2
e 3
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.14.3 Sorav and Sorinkler Systems Sceci fication 3 14.3.1 The spray and/or sprinkler systems located in the fcilewing areas shall be OPERABLE:
a.
Control Room (Zone 3) b.
Controlled Area, Mez:anine Level (Zone 20) c.
Main Lube Oil Area, Grade Level (Zone'32) d.
Grade Level (Zone 34)
North Diesel Room"(Zone 40) e.
f.
South Diesel Room (Zene 41) g.
West Centro 11ed Area, Grade Level (Zene 4Z) h.
East Controlled Area, Grade Level (Zone 43) 1.
South and East -20' Level (Zene 46)
With a ' spray and/or sprinkler system inoperable establish a 3 14.3 2 a.
continual fire watch with backup fire sucoressien eculpment for the unprotected area (s), within one (1) hour.
b.
Restore the system to CPERABLE status within fourteen (14) days or prepare and submit a Special Report to the Commission pursuant to Specification 6.C.2E within the next thirty (30) days outlining the cause of inoperability and tne plans for.estoring the system to CPERABLE status.
- 3 14.4 CO, Svstem Soecification 3 14.4.1 The CO2 systems located in the folicwing areas shall be OPERABLE with pa minimum capacity of 66% and a minimum pressure of Z75 psis in the storage tank, a.
Zone 12 West DC Control Reem Mezzanine Level b.
Zone 13 Vest 4c0 VAC Recm Me::anine Level c.
Zone 14 West Cable Tray Area d.
Icne 15 East Cable Tray Area e.
Zone 16 East 480 VAC Recm Me::anine Level f.
Zone 17 East DC Control Room Mezzanine Level g.
Zone 36 West sattery Room Grade Level i
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation
'3 14.4.1
~(~ continued) h7 'Ione 37 West 4160 VAC* Room I.
Zone 38 East 4160 VAC Room J.
Zone 39 East Battery Room k.
Zone 40 North Diesel Room 1.
Zone 41 South Diesel Room 3.14.4.2 a.
With a CO2 system' inoperable, establish a continual fire watch with backup fire suppression equipment for the unprotected area (s), within one (1) hour.
b.
Restore the system to OPERABLE status within fourteen (14) days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next thirty (30) days outlining the cause of inoperability and the plans for restoring the system to CPERABLE status.
3.14.5 Fire Hose Stations Soecification 3 14.5.1 The fire hose stations in the following locations shall be OPERABLE:
Al'1 stations in the Auxiliary Building a.
b.
Hydrant #2 c.
Hydrant #3
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d.
Hydrant at coordinates N59+17; E30+20 e.
Hydrant at coordinates E30+20; E32'20 3.14.5.2 with a hose station inoperable, route an additional ecuivalent capacity hose to the unprotected area from an CPERABLE hose station wi,th.in_ene,(1) hour.
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation
'3 14.6 Fire Barrier Penetration Fire Seals Soecification 3.14.6.1 All penetration fire barriers protecting safety related areas shall be functional.
3 14.6.2 Vith a penetration fire barrier non-functional, a continual fire watch shall be established to monitor at least one (1) side of the affected penetration within one (1) hour.
Bases OPERASILITy of the fire detection Instrumentation ensures that adecuate warning capability is available for the prompt detection of fires.
This capability is required in order to detect and locate fires in their early stages.
P romp t
' detection of fires will reduce the potential for damage to safety related equip-ment and is an integral element in the overall facili ty fi re protection program.
In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is returned to service.
The OPERABILITY of the fire suporestion systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located.
The fi re suppression system consists of the water system, scray and/or sorinklers, C03, and fire hose stations. The collective capability of the fire suopression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program.
in the event that portions of the fire suppression syst' ems are ineperable, alter-nate backup fire fighting equipment is required to be made available in the
~ affected areas until the affected equipment can be restored to service.
In the event that the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major fire
' suppression capability of the plant. The requirement for a twenty-four (24) hour
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i report to the Commission provides for prcept evaluation of the accectability of the corrective' measures to provide adecuate fire suppression capability for the continued protection of the nuclear plant.
The functional integrity of the fire barrier penetration seals ensures that fires will be confined or adecuately retarded from spreading to adjacent portions of the facility.
This design feature minimizes the pessibility of a single fire rapidly involving several areas of the facility prior to detection and extinguish-ment.
The fire barrier penetration seals are a passive element in the facility fire protection program and are subject to periodic inspections.
During periods of time when the seals are not functional, a continual fire watch l
Is required to be maintaint d in the vicinity of the affected seal until the seal is restored to functional status.
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.18 FIRE SUPPRESSION SYSTEM SURVEILLANCE 4.18.1 Instrumentation 4.18.1.1 Except for fire detection instruments inaccessible during power operation, each of the fire detection instruments in Section 3.14.3.1 shall be demonstrated OPERABLE at least semi-annually by a CHANNEL FUNCTIONAL TEST.
4.18.1.2 Instruments inaccessible during pcwer operation shall be demonstrated OPERABLE by performing specification 4.18.1.1 a and b at each refueling.
4.18.l.3 The circuitry associated with the detecter alarms shall be demonstrated
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OPERA 8LE at least once every six (6) manths for all NFPA Code 72D Class A supervised ci rcui ts.
4.18.2 The FIRE SUPPRESSICN VATER SYSTEM shall be demonstrated CPERAblE:
a.
Weekly by verifying the water supply volume.
b.
Monthly on a STAGGERED TEST SASIS by starting each pump and operating.it for at least fifteen (13) minutes on recirculation ficw.
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c.
Annually by cycling each testable valve through one complete cycle.
d.
Semi-annually by a system flush up to each test fixture.
e.
At least once per refueling interval:
1.
By performing a system functional test which includes simulated automatic actuation of the system throughout its operating seo.ence and verifying that each automatic valve in the flow path actuates to its correct position.
2.
By verifying that each pump will deveico a flow of at
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least 2000 spm at a system minimum pressure of 125 psig.
f.
At least once per three (3) years by performing flow tests of the system in accordance with Chapter 5, Section il of Fire Protection Handbook, Ik h Edition published bf National Fire t
Protection Associatioa.
g.
Monthly by verifying that each valve (manual, power operated or auto =atic) in the flow path is in its correct position.
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h.
The fire pump diesel engine shall be demonstrated OPERABLE:
1.' Monthly by verifying; a.
The fuel storage tank contains at least 250 gallons of fuel, and b.
The diesel starts from a=bient conditions and operates for at least 20 minutes.
2.
At least once per refueling interval by:
a.
Subjecting the diesel to an inspection in.
accordance with procedures prepared in.
conjunction with its manufacturer's recocmen-dations for the class of service, a.d b.
Verifying the diesel starts from ambient conditions on the auto-start signal and operates fcr 1 20 minutes while loaded with fire pump.
3.
Quarterly by verifying that a sample of diesel fuel from the fuel storage tank, obtained in accordance with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM-D975-74 with respect to viscosity, water content and sedi=ent.
1.
The fire pump diesel starting 24-volt battery bank and charger shall be demonstrated OPERABLE:
1.
Weekly by verifying that:
a.
The electrolyte level of each battery is above the plates, and b.
The overall battery voltage is 2 24 volts.
2.
Quarterly by verifying that the specific gravity is appropriate for continued service of the battery.
3.
At least once per refueling cycle by verifying that:
a.
The batteries, cell plates and battery racks show no visual indication of physical da= age or abnormal deterioration, and b.
The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.
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RANCHO SECO UNIT 1
~m TECHNICAL SPECIFICATIONS Surveillance Standards 4.18.3 The spray and/or sprinkler syster.s shall,be demonstrated to be OPERABLE:
Annually by cycling each testable valve through one complete cycle.
a.
b.
Each REFUELING INTERVAL:
1.
By performing a system functional test which includes simu-lated automatic actuation of the system and verify that the automatic valves in the flow path actuate to their correct positions; and 2.
By inspecti in of spray headers to verify their integrity; and 3
By inspection of each nozzle to verify no blockage.
4.
At least once per three (3) years by performing an air flow test through each spray / sprinkler header and verifying each spray / sprinkler nozzle is unobstructed.
4.18.4 The CO2 system shall be demonstrated OPERABLE:
a.
Veekly by veri fying the CO2 storage tank level and pressure.
b.
Each refueling interval by verifying the system electro manual pilot val cas and associated' ventilation damcers actuate automati-cally and aanually to a simulated actuation signal. A flow test shall be made to verify flow from each nozzle.
4.18.5 Each fire hose station shall be verified.to be OPERABLE:
a.
Monthly by visual inscection of the station to assure all equip-ment is available.
b.
Each refueling interval by removing the hose for inspection and re-racking and replacing all gaskets in the couplings that are degraded.
c.
Once per three (3) years, partially open hose station valves to verify valve operability and no blockage.
d.
Once per three (3) years by conducting a hose hydro-static test at a pressure at least 50 psig greater than
,the maximum pressure available at that hose station.
4.18.6 Penetration fire barriers shall be verified to be functional by a visual inspection:
a.
At least once each refueling interval; and b.
Prior to declaring a fire penetration seal functional fol lowing repairs or maintenance.
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m 6.0 ADMINI,STRATIVE LON... LS 6.1 RESPONSIBILITY 6.1.1 The Plant Superintendent shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.
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6.2 ORGANIZA ION 0FFSITE 6.2.1 The offsite organization for facility management and technical support shall be as -shcwn on Figure 6.2-1.
FACILITY STAFF 6.2.2 The facility organization shall be as shewn on Figure 6.2-2 and:
a.
Each on duty shif t shall be ecmposed of at least the minimum shift crew composition shown in Table 6.2-1.
b.
At least one licensed Operator shall be in the Control Recm when fuel is in the reactor, c.
At least two licensed Operators shall be present ln the Centrol Room during reactor startup, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified in radiaticn protection procedures shall be on site when fuel is in the reactor.
ALL CORE ALTERATIONS after the initial fuel loading shall be e.
directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator limited to Fuel Handling who has no other concurrent responsibilities during this operation.
f.
A Fire Brigade of 5 members shall be maintained en the site at all times. This excluces 2 members of the minimum shif t crew necessary for safe shutdown of the plant and any personnel required for other essential functions during a fire emergency.
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6-1
BOARD OF DIRECTORS SF.CR ET A RY TREASURFR ATTO(t N EY ACCOUNTANT IN'DCPENDENT CONSULTANTS MANAGEMENT PERIODIC SAllLTY AUDIT GENERAL M ANAGER SA!!LTY RfWlEW OF RANCl!O SECO Ol'ERATIONS COMMITTEE l
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- CONTROLLER OPERATIONS Cll!EF ENGINEER QUALITY SYSTEMS & PROCEDURES RAFF ASSURANCE
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.R NT HYDRO DATA DMRIDtJTION OPERATIONS PRCCESSING PLANNINC DEPARTMENT DEPARTMENT D EPARTM ENT NUCLEAR GENERAL DISTRIBUTION OPERATIONS OPERATION SE.V!C ES D71A RTMENT DEPARTMENT DEPARTMENT PURCHASES CUSTOM ER GENERATION ENGINEE!tlNG SERV:CES
& STORES DEPARTMENT DEPARTM ENT DEPARTM ENT f
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J for Fire Protection Program FIGURE 6.21 l
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ATTLt:DAiJTS Responsible for Fire Protection Progrant T
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l'!. ANT ot:C AutZ Al tou ctI AltT It ANcuo :,t.c:o UNIT 1 13ANCllO S!?CO UNIT 1 TliCilNICAI. SPtic!!:lC ATIONS
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ADMINISTRATIVE CONTRCLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the operating staf f Shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions.
6.4 TRAINING 6.4.1 A retraining and replacement traininc program for the' operating staff shall be maintained under the direction of the Training
_ _, Supervisor and shall meet or exceed the requirementr and"recommenda-tions of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Pa r t. 55. - -
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_ 6_4.2. -- - A t ra i n i ng prog ram f o r te F i re lfr i ga d e s ha l l be ma i n ta i ned und e r the direction of the Safety Technician and shall meet or exceed the requirements of Section 27 of the NFPA Code - 1976.
6.5 REVI EV AND A';DIT 6.5.1 PLANT REVIEW COMMITTEE (PRC)
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CUNCTION
---4 5.1.1
---The Plant Review Committee shall function to advise the Plant Superintendent on all. matters related to nuclear safety.
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--- COMPOS IT I ON
- 5.1. 2 -
The Plant Review Committee shall be composed of the':
Chairman: Technical Assistant
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- Member:
-Assistant Superintendent Nucrea'r" Plan't 0perations Membe r:
Assistant Superintendent-Technical Support
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- -- Member:
Maintenance Supervisor Member:
Chemical and Radiation Supervisor ---"
Other members as the Plant Superintendent may appoint from time to time.
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Amendment No.
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_.. _.. v ADMittlSTRATIVE CCNTROLS AUDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the MSRC. These audits shall encompass:
a.
The conformance of facility operation to all provisions contained within the Technical Specifications and applicable
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licensed conditions at least once per year.
b.
hhe performance, training and qualifications of the entire facility s-taff at least once per year.
c.
The result of all actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months.
d.
The performance of all activities required by the C.uality Assurance
, _,,P rogram to meet the criteria of Appendix "B",
10 CFR 50, at least once per two years, e.
The Facility Emergency Plan and implementing procedures at least
'nce per two years.
f.
Tne Facility Security Plan and implementing procedures at l e'as t cnce per two years.
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g.
Any other area of facility operation considered appropriat,e by by the MSRC or the General Manager.
h.
Compliance with fire protection requirements end implementing procedures at least once per two (2) years.
4 I:
An independent fire protection and loss prevention inspectic, and audit shall be performed annually utilizing either cualifier offsite licensee persone.el or an outside fire protection fi rm.
J.
An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
AUTHORITY 6.5.2.9 The MsRC shall report to and advise the General Manager on those areas of responsibility specified in Section 6.5 2 7 and 6.5.2.8.
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.m ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
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a.
The provisions of 10 CFR 50.36 (c) (1) (i) shall be ccmplied with immediately.
b.
The Safety Limit violation shall be reported to the Plant Superintendent, the Chairman of the MSRC and to the Commission immediately.
c.
A Safety Limit Violatio'n Report shall be prepared. The report shall be reviewed by the PRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility comoonents, systems or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission, the MSRC and the Plant Superintendent within ten (10) days of the violation.
6.8 PROCEDURES 6.8.1 Vritten procedures shall be established, implemented and maintained covering the activities referenced below:
s a.
The applicable procedures recommended in Appendix "A",of Regulatory Guide 1.33, November 1972.
b.'
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
d.
Security Plan implementation.
e.
Emergency Plan implementation.
f.
Fire Protection Procedures implementacion.
6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PRC and approved by the Plant Superintendent prior to implementation and reviewed periodically as s'et forth in each document.
6.8.3 Temporary changes to procedures o' 6.8.1 above may be made provided:
i a.
The intent of the original procedure is not altered.
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-ADMINISTRATIVE CONTROL' b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
c.
The change is documented, reviewed by the PRC, and approved by the Plant Superintendent within 7 days of implementation.
6.9 REPORTING REC.UIREMENTS ROUTINE REPORTS AND RE?ORTABLE OCCURRENCES 6 9 1 Information to be reported to the Commission, in addition to the recorts required by Title 10, Code of Federal Regulations, shall be in accordance with the Regulatory Position in Revision 4 of Regulatory Guide 1.16, " Reporting of Operating information - Appendix "A" Technical Specifications".
SPECIAL REPORTS 6.9.2 Special reports shall be submi tted to the Director of the Regulatory Operations Regional Of fice within the time period speci.fied for each report.
These reports shall be sucmitted covering the activities identified below pursuant to the requirements of the applicable reference specification:
A..
Startuo Resort A summary report of unit startup and power escalation testing o
and an evaluation of the results from these test programs shall be submitted wi thin 60 days 'following commencement of commercial power operation. The test results shall be compared with design predictions and specifications.
B.
A Reactor Building structural integrity report shall be submitted within CO 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).
.I Annual Inspection
.2 Tendon stress surveillance 3
End anchorage concrete surveillance
.4 Liner plant surveillance C.
Inse,rvice inspection Program.
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D.
(Reserved for Proposed Amendment No. 43).
E.
Status of inoperable fire protection equipment.
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