ML19319D911
| ML19319D911 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/01/1977 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML19319D910 | List: |
| References | |
| NUDOCS 8003270579 | |
| Download: ML19319D911 (16) | |
Text
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l' RANCHO SECO UNIT I 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.
1.9.5 Quarterly - A time period of three calendar months spaced to occur 4 times a year.
l.9.6 Semi-Annual - A time period from January I and July I covering the suosequent six months.
l.9.7 Biannually - A time period of 24 calendar months spaced to occur once in two years.
1.10 SAFETY Safety as used in these Technical Specifications shall mean nuclear safety and shall encenpass all systems and components that hase or may have an ef fect on the health and safety of the general public.
1.11 FIRE SUPPRESSION SYSTEMS 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.
Such valves include yard hydrant valves ar.d 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.
47 1.11.2 The FIRE SUPPRESSION CARBON DIOXIDE SYSTEM shall consist of a CO2 source and distribution piping with sectionalizing control valves which protect nuclear safety components.
Proposed Amendment No. 47 Rev. 1 8003 270 g
[p 1-6
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ment.
The _ fire barrier penetration seals are a passive element in the facility fire protectioni program' and are subject to periodic inspections.
During periods of time when the seals are not' functional, a continual fire watch
?Is required to.be maintained in the vicinity of the affected seal until the seal is restored to -functional stogaco
r RANCHO SECO UNIT'l 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; and a.
b.
At least annually by performance of a channel calibration.
4.18.1.2 Instruments inaccessible during. power operation shall be demonstrated OPERABLE by performing specification 4.18.1.1 a and b at each refueling.
4.18.1 3 The circuitry associated with the detector alarms shall be demonstrated OPERABLE at least once every two (2) months for all NFPA Code 72D Class A supervised circuits.
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 fifteen (15) minutes on recirculation flow.
c.
Quarterly 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 sequence and verifying that each automatic valve in the flow path actuates to its correct position.
2.
By verifying that each pump will develop 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 wi th -Chapter 5, Section Il of Fire Protection Handbook, 14th Edition pubitsbed by National Fire Protection Association.
Proposed Amendment No. 47 Rev. 1 4-57 3
/
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.18.3.
The spray and/or sprinkler systems shall be demonstrated to be OPFRABLE:
Quarterly by cycling each inspection test station valve through one a.
complete' cycle.
b.
Each RETUELING INTERVAL:
1.
By performing a system functicnal 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 inspection 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:
Weekly by verifying the CO2 storage tank level and pressure.
a.
b.
Each refueling interval by verifying the system electro manual s.
pliot valves and associated ventilation dempers actuate automati-cally and manually 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:
Monthly by visual' inspection of the station to assure all equip-a.
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.
Once per three (3) years, partially open hose station valves to c.
verify valve operability and no blockage.
4.18.6 Penetration fire barriers shall be verified to be functional by a visual inspection:
At -least once each refueling interval; and a.
Prior to ' declaring a fire penetration seal functional following b.
repairs or maintenance.
.4.18.7 Penetration fire barriers that perform a pressure ' sealing function shall be
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verified to be functional by performance of a local leakage test prior to declaring a penetration fire barrier functional following repairs or
- maintenance.
Proposed Amendment Ns. 47L2GL_Jl
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7, 6.0 ADMINI,STRATIVE C I *RO LS'
- 6. I' RESPONSIBILITY 6.1.1
.The Plant Superintendent shall be responsible for overall fac;lity operation and shall delegate in writing the succession to this responsibility during his absence.
6.2 ORGANIZATION OFFSITE' 6.2.1 The offsite organization 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 minimum shift cre.< composition.shown in Table 6.2-1.
b.
At least 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 Juring recovery from reactor trips, d.
An Individual quali fied in radiation protection procedures shall b on site when fuel is in the reactor.
ALL CORE ALTERATIONS af ter the initial fuel loading shall be e.
directly supervised by either a IIcensed Senior Reactor Operator c-Senior. Reactor 10perator limited to Fuel Handling who has no other concurrent responsibilities during this operation.
f.
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 47 essential functions during a fire _ emergency.
4 Proposed Amendment No. 47 Rev. 1 6-1
PLANT
+
SUPERINTENDENT
- ADMINISTRATIVE TECHNICAL STAFF ASSISTANT
- ASST. SUPT.
ASST. SUPT.
MAINTENANCE TECHNICAL NUCLEAR PLANT -
SUPERVISOR
- CPERATIONS (SL)
- SUPPO RT*
SHIFT MAINTENANCE SUPERVISO R (SL)
PERSONNEL SR. CONTROL 47 roost OPERATORS (L)
SR. POWER PLANT CHEMICAL-RADIATION INSTRUMENT CONTROL SUPERVISOR SUPERY!SOR (NUCLEAR / tEC i NICAL)
CONTROL ROOM OPERATORS (L)
CHEMISTRY.R ADI ATION INSTRUMENT CONTI JL PERSONNEL PERSONNEL OPERATORS SL. SENIOR OPER ATOR LICENSE L. OPERATOR LICENSE 47 EQUIP 4 TENT
- - ROUTINE REPORTING REQUIRE-ATTENDENTS MENTS ON PERSONNEL CHANGES
- Member of Fire Brigade FIGURE 6.2 2 PLANT ORGANIZATION CHART RANCHO SECO UNIT 1
' TECHNICAL SPECIFICATIONS Proposed Amendment,No._ 47 Rev. I
[
1:
- 1 ADMINISTRATIVE' CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the operating stafE~shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions.
6.4 TRAINING
~
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6.4.1 A retraining and replacement t.ra_irdrs. program for the operating
~
staf f 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
_Part 55. - - -
__.56.4.2. --- ~~ A training program for~the Fire BFigide sh' ll
- esintained under a
the direction of the Safety Technician and shall meet er exceed the requirements.cf Section 27 of the NFPA Code - 1976.
47 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.
--. COMPOS IT l'ON
~
- --6:5: 1.2-The Plant Review Committee shall be composed of the:
Chairman:
Techni$alAssistant
- Member:
=- Assistant Superintendent Nuclea-' Plant 0perations r
~
Membe r:
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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". ADMittlSTRATIVE' CONTROLS-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 licensed conditions at least once per year.
b.
The performance, training and qualifications the entire facility
~
staff at least once per year, The result of all actions taken to correct deficiencies occurring c.
in facility equipment, structures, systems or method of operation that affect nuclear safety at least once oer six months.
d.
The performance of all activities required by the 0.uality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per two years.
~ ~ ~ ~ ~ ~ ~ ~
~~
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The Facility Emersincy 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 least once per two (2) years.
procedures at is An independent fire protection and loss prevention inspection and audit shall he performed annually utilizing either qualified offsite 47.
IIcensee 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.
Proposed Amendment No. 47 Rev. 1
,6-9
ADMINISTRATIVE CONTROLS 6.7
-SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The provisions of 10 CFR 50.36 (c) (1) (i) shall be complied 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 components, 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 Written procedures shall be established, implemented and maintained covering the activities referenced below:
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.
Fi re Protect ion Procedures implement'at. ion.
47
-6.8.2 Each procedure'and administrative policy of. 6.8.1 above, and changes thereto, shalI 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:
l a.-
'The intent of the original procedure is not altered.
I i
I
-Proposed Amendment No.-47 Rev. 1
- 3. +
.2.
, v.
A_ MIN I ? TRAT I VE ' CONT ROL S*
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 af fected.
c.o "The change is documented, ' reviewed by the PRC, and approved by the Plant Superintendent within 7 days of implementation.
6.9' REPORTING REO.UIREMEtiTS ROUTINE REPORTS AND~ REPORTABLE OCCURRENCES 6.9 1-Information to.be: reported to the Commission, in addition to the reports
- required -by Title 10, Code of Federal Regulations,.shall be in accordance with the Regulatory Position in Revision 4 of Regulatory Cuide 1.16, " Reporting of Operating'Information - Appendix "A" Technical Specliications".
SPECIAL REPORTS 6.9.2 Special reports shall be submi tted to the Director of the. Regulatory
- Operations Regional'Of fice wi thin 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..
Startup Report A summary report of unit startup and power escalation testing and an evaluation of the results from these test programs shall be submi tted wi thin.60 days foilowing commencement of commercial power' operation..The test results-shall be compared with design predictions and specifications.
B.
L A Reactor Building structural integrity report shall be ' submitted within 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.e).
. s
.1 Annual' Inspection
.21 Tendon 1 stress surveillance 3
End anchorage concrete surveillance.
. 4'
- Liner plant surveillance C.
. inservice Inspection Program.
D.
'(Reserv$d for Proposed Amendment No. 43).
47.
E.
-Status of-inoperable fire protection equipment.
V
' Proposed Amendment-No. 47 Rev. 1
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