ML19317G747
| ML19317G747 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/18/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19317G740 | List: |
| References | |
| NUDOCS 8004010577 | |
| Download: ML19317G747 (21) | |
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NUCt. EAR REGULATORY COMMISSION Il,.,i wAsmmaron. o. c. mss
,,*....,I SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION
_ AMENDMENT TO FACILITY OPERATING LICENSE Amend:ent No.18 License No. DPR-54 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The aoplication for amendment by Sacramento Municipal Utility District (the licensee) dated Auoust 1, 1977, as supplemented i
December 16, 1977, complies with the standards and requirements of the Atomic Eneroy Act of 1954, as amended (the Act), and l
the Comission's rules and renulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application.
the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the 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.
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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 $4 is hereby amended to read as follows:
i (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.18. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment becomes effective 30 days after the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION dd U-Robert W. Reid, Chief l
Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifkations Date of Issuance: February 18, 1978 e
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ATTACHMEMk TO LICENSE AMENDMEt!T NO.18 FfCILITY OPERATIrm LICENSE NO. OPR-54 DOCKET NO. 50-312 i
Revise Appendix A as follows:
Revise Paces Insert Paces 1-6 3 3-58 4 4-60
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6-1 6-1 i
Fig. 6.2-1 Fig. 6.2-1 Fig. 6.2-2 Fig. 6.2-2 6-3 6-3 6-9 6-9 6-11 6-11 6-12d 6-12d New pages and chances on the revised pages are shown by marginal lines.
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to RANCHO SECO UNIT I
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TECHNICAL SPECIFICATIONS DEFINITIONS 1.11 FIRE SUPPRESSION SYSTEMS 1.11.1 T'he FIRE SUPPRESSION WATER SYSTEM shall consist of water sources, pumps and distribution piping with associated sectionalizing control or isola--
tion valves.
Such 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 cobponents.
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Amen $entNo. 18 1-6
t 3.13 Reserved i
l Amendment tio.18 3-52 e
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS t
Limiting Conditions for Operation 3.14 FIRE SUPPRESSION 3 14.1 instrumentation Specification 3 14.1.1 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3 14-1 shall be OPERABLE.
3 14.1.2 With the number of instruments OPERABLE less than required by the Minimum instruments OPERABLE requirement:
a.
Within one (1) hour, the zone will be continuously occupied or a fire watch patrol will be established to inspect the zone with the inoperable instrument (s) at least once oer hour; and b.
Restore the inoperable Instrument (s) to OPERABLE status within fourteen (14) days; or c.
Prepare and submit a special report to the Commission, pursuant to Specification 6.95.E, within the next ten (10) days outlining the cause of inoperability and the plans for restoring the Instru-ment (s) to OPERABLE status.
3 14.2 water System
.Soeci fi cation 3.14.2.1 The FIRE SUPPRESSION WATER SYSTEM shall be OPERABLE with:
Two high' pressure pumps each with a capacity of 2000 gal / min a.
with their discharge aligne*d to the fire suppression header, b.
Two 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 required equipment, restore the inoperable equipment to OPERABLE status within 7 days or precare and submit a Special Report to the Commission pursuant to Scecification 6.9.5.E within the next 10 days outlining the plans and procedures to be used to provide for the loss of reduncancy in this system.
3 14.2.3 With no FIRE SUPPRESSICN WATER SYSTEM OPERABLE:
a.
Establish a backup FIRE SUPPRESSION WATER SYSTEM within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
l' 3-53 Amendment No. 18
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3 14.2.3 (Continued) b.
Notify the Commission pursuant to Specification 6.9.5.E. outlining j
the actir's taken within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
j c.
Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.5.E within the next ten (10) working days outlining 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 six (6) hours and Cold Shutdown within the following thirty (30) hours.
i Amendment No.
18 3,54
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RANCHO SECO UNIT l TECHNICAL SPECIFICATIONS Limiting Conditions for Operation TABLE 3.14-1 FIRE DETECTION IMSTRUMENTS FOR SAFETY SYSTEMS Zone instrument Location Minimum Operable 4
11 Battery Room, Mezzanine Level 12 West DC Control Room, Mezzanine Level 2
13 West 480 VAC Room, Mezzanine Level 2
2 14 West Cable Tray Area 2
15 East Cable Tray Area 16 East 480 VAC Room, Mezzanine Level 2
17 East DC Control Room, Mezzanine Level 2
4 36 West Battery Room, Grade Level j
37 West 4160 VAC Room 2
38 East 4160 VAC Room 2
4 39 East Battery Room 2
40 North Diesel Room 41 South Diesel Room 2
44 Reactor Coolant Pumps A and B 1
1 44 Reactor Coolant Pumps C and D 45 Electrical Penetration Area, Grade Level 2
47 North -20' Level, Auxiliary Building 2
2 48
-47' Level, Auxillary Building I
Amendment No. 18 3-55
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3 14.3 Spray and Sorinkler Systems 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 Level (Zone 32) d.
Grade Level (Zone 34) e.
North Diesel Room (Zone 40) f.
South Diesel Room (Zone 41) g.
West Controlled Area, Grade Level (Zone 42) h.
East Controlled Area, Grade Level (Zone 43) 1.
South and East -20' Level (Zone 46)
Vith a spray and/or sprinkler system inoperable establish a 3 14.3 2 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 Soecial Report to the Commission oursuant to Specification 6.9.5.E within the next ten (10) days outlining the cause of inoperability and the plans for restoring the system to OPERABLE status.
3 14.4 CO, System 1
Specification 3 14.4.1 The CO2 systems located in the following areas shall be OPERABLE l
with a minimum capacity of 66% and a minimun pressure of 275 psig in the storage tank.
a.
Zone 12 West DC Control Room Mezzanine Level b.
Zone 13 West 480 7AC Room Mezzanine Level c.
Zone 14 West Cable Tray Area d.
Zone IS East Cable Tray Area e.
Zone 16 East 480 VAC Room Mezzanine Level f.
Zone 17 East DC Control Room Mezzanine Level g.
Zone 36 West Battery Room Grade Level Am:ndment No. 18
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.m RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3 14.4.1 (continued) h.
Zone 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 With a CO2 system inoperable, establish a continual fire watch 3.14.4.2' a.
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 oursuant to Specifica-fon 6.9.5.E within the next ten (10) days, outlining the cause* of inoperability and the plans for restoring the system to OPERABLE status.
3 14.5 Fire Hose' Stations Specification 3 14.5.1 The fire hose stations in the following locations shall be OPERABLE:
a.
All stations in the Auxiliary Building b.
Hydrant #2 c.
Hydrant #3 d.
Hydrant at coordinates N59+17; E30+20 e.
Hydrant at coordinates N59+17; E32+20 3.14.5.2 with a hose statien inoperable, route an additional eautvalent size ~
hose to the unprotected area from an OPERABLE hose station within one (1) hour.
9 3-57 l
_ g ndment No. I8
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RANCHO SECO UNIT 1 I
TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3 14.6 Fi re Barrier Penetration Fire Seals
'Soecification I
I 3.14.6.1 All penetration fire barriers protecting safety related areas shall be functional.
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3 14.6.2 With 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.
Beses OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires.
This capability is rsquired in order to detect and locate fires in their early stages.
P rompt j
detection of fires will reduce the potential for damage to safety related equip-ment and is an integral element in the overall facility fire 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 suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in cny portion of the facilit.y.here safety related eculpment is locat:d. L f!-=
suppression system consists of the water system, spray and/or sprinklers, CO.,,
cnd fire hose stations. The collective capability of the fire su pression 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 tha fire suppression systems are inoperable, 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.
i in the event that the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major fire j
suppression capability of the plant. The reout rement for a twenty-four (24) hour repo rt to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate 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 adequately retarded from spreading to adjacent portions of the facIIIty. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility pr or to detection and extinguish-ment. The fire barrier penetration seals are a passive element in the facility fire :::rotection orogram and are sut lect to periodic inscections.
During periods of t!me when the se :s are not functional, a continual. fire watc5 is recuired to be maintained in the vicinity of the affected seal until the sea!
Is restored to functienal status.
3-58 A=endmenth!o. 18
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RANCHO SECO UNIT I TECHNICAL SPECIFICATIONS Surveillance Standards 4.18 FIRE SUPPRESSION SYSTEM SURVEILLANCE
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4.18.1 Instrumentation 4.18.1.1 Exceptforfiredetectioninstrumentsinaccessibleduringpower operation, each of the fire detection instruments in Table 3 14-1 shall be demonstrated OPERABLE at least semi-annually by a CHANNEL TEST.
4.18.1.2 Fire detection instruments inaccessible during power operation shall be demonstrated OPERABLE by performing specification 4'.18.1.1 during each refueling interval.
4.18.1.3 The circuitry associated with the sprinkler water flow detector alarms in Section 3.14.31 shall be demonstrated OPERABLE at least semi-annually.
4.18.2 The FIRE SUPPRESSION WATER SYSTEM shall be demonstrated OPERABLE:
a.
Weekly by verifying the water supply volume.
b.
Monthly on a STAGGERED TEST BASIS by starting each pump and operating it for at least fif teen (15) minutes on recirculation fIow.
Annually by cycling each testable valve through'one complete c.
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 sequenca and verifying that each automatic valve in the flow path actuates to its correct position.
2.
By verifying that each pump will develoo a flow of at least 2000 gpm 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 Section 11, Chapter 5, of Fire Protection Handbook, lath Edition published by National Fire Protection Association.
g.
tienthly by verifying t tat ea..h valve (manual, power-operated or automatic) in the flow pa.h is in its correct position as indicated by position instrum atation.
Amendment No. 18 4-58
A RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS
. Surveillance Standards 4.18.2 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 ambient 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 recommendations for the class of service, and b.
Verifying the diesel starts from ambient conditions on the auto-start signal and operates for > 20 minutes
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while loaded with.the 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-0975-74 with respect to viscosity, water content and sediment.
i.
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 >' 24 volts.
2.
Quarterly by verifying that the specific gravity is appro-priate for continued service of the battery.
3 At least onc per refueling interval by verifying that:
a.
The batteries and battery racks show no visual indica-tion of physical damage or abnormal deterioration, and
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The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-
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corrosion material.
i Amendment No, 18 4 39
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS
.s Surveillance Standards 4.18.3 The spray and/or sprinkler systems specified in Section 3 14.3 1 shall be demonstrated to be OPERABLE:
a.
Annually by cycling each testable valve through one complete cycle.
b.
Each REFUELING INTERVAL:
1.
By performing a system functional test which includes simu-lated automatic actuation of the system and verifying that the automatic valves in the flow path actuate to their correct positions; and 2.
By inspection of spray and/or sprinkler headers to verify their integrity; and c.
By inspection of each nozzle and/or sprinkler to verify no blockage.
4.18.4 The CO2 system shall be demonstrated OPERABLE:
a.
Weekly by verifying the CO2 storage tank level and pressure.
b.
Each refueling inte. val by verifying the system electro manual pilot valves and associated ventilation dampers actuate automati-cally and manually to a simulated actuation signal.
A flow test shall be made te verify flow f rom each nozzle.
4.18.5 Each fire hose station shall be verified to be OPERABLE:
a.
Monthly by visual inspection of the station to assure all equip-ment is available.
b.
Each refueling interval iispect and replace 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 valve blockage.
c.
Once per three (3) years by removing and replacing all hose with equivalent NFPA tested and approved hose.
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 eenetration seal functional following repairs or maintenance.
Amendment No.
18 4-40
ry 6.0...
ADMINISTRATIVE LONTROLS 4
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.
6.2 ORGANI ZATION OFFSITE 6.2.1 The offsite orcanization for facility management and technical support shall be as shown on Figure 6.2-1.
FACILITY STAFF 6.2.2 The facility organization shall be as shown on Figure 6.2-2 and:
a.
Each on duty shif t shall be composed of at least the min mum shift crew composit.lon shown in Table 6.2-1.
b.
At lea'st one licensed Operator shall be in the Control Room when fuel is in the reactor.
c.
At least two licensed Operators shall be present in the Control Room during reactor startup, scheduled reactor shutdown and during recovery from reactor trips.
d.
An Individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
e.
ALL CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator limited to Fuel Handling who has no other concurrent respons Lilities during this operation.
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A Fire Brigade of 3 members shall be maintained on the site at all times. This excludes 2 members of the minimum shift crew necessary for ' safe shutdown of the plant and any personnel required for other essential functions during a fire emergency.
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Amendment No. 18 0"I
30ARD OF DIRECTORS
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SECRETARY TREASURER ATTORNEY ACCOUNTANT INDEPENDENT CONSULTANTS MANAGEMENT rERIODIC SAF*TY AUDIT GENERAL MANAGER SAFETY REVIEW OF RANCHO SECO OPERATIONS COMMITTEE l
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CONSUMER PERSONNEL LEGAL STAFF RELATIONS DEPARTMENT DEPARTMENT AGM*
AGM*
AGM* (**)
l CONTROLLER OPERATIONS CHIEF ENGINEER SYSTEMS & PROCEDURES QUALITY
^
INTERNAL AUDITING ASSURANCE t
l TRIBUTION ACCOUNTING ENGINEERING
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DEPARTMENT DEPARTMENT E
r DATA DISTRIBUTION HYDRO OPERATIONS PROCESSING P LAFNING DEPARTMENT DEPAATMENT DEPARTMENT GENERAL DISTRIBUTION NUCLEAR SERVICES OPERATION OPERATIONS DEPARTMENT DEPARTMENT DEPARTMENT PURCHASES CUSTOMER GENERATION SERVICES ENGINEERING
& STORES DEPARTMENT DEPARTMENT DEPARTMENT
- AGM - Assistant General Manager
- Aesponsible for Fire Protection Program l
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,y SMUD ORGANIZATION CHART RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Amendment No. g, 18
D O
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.s PLANT **
SUPERINTENDENT d
ADMIN'STRATIVE TECHNICAL STAFF ASSISTANT
- ASST.S M.
ASST. SUPT.
M UNTEN ANCE UN I AL NUCLEAR PLANT SUPERVISO R*
SUPPO RT*
OPERATIONS (SL)
- SHIFT MAINTENANCE SUPERVISOR (SL)
PERSONNEL SR. CONTROL ROOM OPERATORS (L)
SR. POWER PLANT CHEMICAL. RADIATION INSTRUMENT CONTROL SUPERVISOR
- SUPERYtSOR (NUCL R/MEC ICAL)
CONTROL ROOM OPERATORS (L)
CHEMISTRY.R ADIATION INSTRUMENT CONTROL PERSONNEL PERSONNEL AUXILIARY OPERATORS SL. SENIOR O' ERATOR LICENSE r
EQUIPMENT L. OPERATOR LICENSE
- . ROUTINE REPORTING REQUIRE.
ATTENDENTS MENTS ON PERSONNEL CHANGES
- -Responsible for Fire Protection Progra:::
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.e FIGURE 6.2-2 PLANT ORGANIZATION CHART RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Amendment No. 18
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AM'IN TRATIVE CONTROLE 6.3 FACillTY STAFF QUALIFICATIONS 6.3.1 Each member of the operating staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions.
6.3.2 The Chemical-Radiation Supervisor shall meet or exceed the minimum qualifications of NRC Guide 1.8 September 1975.
6.4 TRAINING 6.4.1 A retra'ning and replacement training program for the operating staff shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and recommenda-tions of Section 5.5 of ANSI N18.l-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2
'A training program for the Fire Brigade shall be maintained under the direction of the Safety Technician and shall meet or exceed the requirements of Section 27 of the NFPA Code - 1975, except refresher. classroom training shall be on a quarterly schedule.
6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRC)
FUNCTION 6.5.1.1 The Plant Review Committee shall function to advise the Plant Superintendent on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The Plant Review Committee shall be composed of the:
1 Chai rman: Technical Assistant Member:
Assistant Superintendent Nuclear Plant Operations Member:
Assistant Superintendent Technical Support 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.,k#7 18 6-3
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ADMINIST,RATIVE CCNTROLS
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. AUDITS 6.5 2'.8 Audits of facIIIty 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 IIcense conditions at least once per year.
b.
The performance, training and qualifications of the entire facility staff at least once per year.
c.
The result of all actions taken to correct deficiencies occurring In facility equipment, structures, systems or method of operatien that affect nuclear safety at least once per six months,
d.
The performance of all activities required by the 0.uality.4ssurance' Program to meet the criteria of Appendix "B",10 CFR 50, at least i
once per two years.
j The Fa'cIlity Emergency Plan and implementing procedures at least e.
once per two years.
f.
The Facility Security Plan and implementing procedures at least once per two years, g.
Any other area of facility operation considered appropriate by by the MSRC or the General Manager.
h.
Compliance with fire protection requirements and implementing procedures at least once per two (2) years.
1.
An Independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.
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.
AUTHOR I TY 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.
Amendment No. 18 6-9
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, ADMINISTRATIVE CONTROLS l
6.7' SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated.
The provisions of 10 CFR 50.36 (c) (1) (i) shall be complied
)
a.
i with immediately.
b.
The Safety Limit violation shall be reported to the Plant Supe rintendent, the Chairman of the MSRC and to the Commission immediately, 1
A Safety Limit Violation Report shall be prepared. The report c.
shall be reviewed by the PRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facili ty components, systems or structures, and (3) torrective 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 Written procedures shall be established, implemented and maintained covering the activities referenced below:
The applicable procedures recommended in Appendix "A" of a.
Regulatory Guide 1.33, November 1972.
b.
Refueling operations.
Surveillance and test activities of safety related equipment, c.
d.
Securi ty Plan Implementation.
Emergency Plan implementation.
e.
f.
Fi re Protection Procedures imp.lementat.Lon.
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 set forth in each document.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
The intent of the original procedure is not altered.
a.
Amendment No.
18 6-11
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SPECIAL REPOR15
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6.9.5 special reports shall be submitted to the Director of the Regulatory Operations f:egional Of fire within the time period'specified for each report. 1hese reports shall be subraitted covering the activities identified belou pursuant to the requirement,s of the applicable reference. specification:
A.
A one-t ite only, "Itarrat ive. Sumary of Operat ing ExperIcnce" teill be submittpd to cover 'the transition period (calendar year 1977).
7 8.
A Reactor Building ciructural integrity report shall be submitted within ninety (90) days of completion of each of th 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
.2 Tendon Stress S$rveillance 3
End Anchorage Concrctc Surveillance
.4 Line'r Plate Surveillance C.
Inservice Inspu. tion Program.
D.
Reserved fo,- Proposed %endment ilo. 43 E.
Status of Inoperable Fire Protection Equipment l
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6-12d Amendment No.
18 e