ML19350B034
| ML19350B034 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 03/02/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19350B035 | List: |
| References | |
| NUDOCS 8103190216 | |
| Download: ML19350B034 (10) | |
Text
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UNITED STATES c2eteaa secutaroav commission
- Q;.C,..;2 WASHINGTON. D. C. 2CS$5 M...../
VERMONT YANKEE NUCLEAR POWER CORPORATION, DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 63 License No. DPR-28 l
1.
The Nuclear Regulatory Comission (the Commissio.7) has found that:
t A.
The apolication by Vemont Yankee Nuclear Power Corporation (the I
licen.e:a)datedSeptember 12, 1980, as supplemented January 5, 1981, complies with the 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; 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 i
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon i
defense and security or to the health and safety of the public; l
and E.
The issuance of this amendment is in accordance with 10 CFR Part l
51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the_ license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and l
paragraph 3.B of Facility License No. DPR-28 is hereby amended to read as follows:
1810319O N
. 8.
Technical Specifications-The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 63, are hereby incorporated in ' the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendrent is effective as of the date of its issuance.
FG;t THE NUCLEAR REGULATORY C0!9tISSION
/t
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AM Thomas A.
ppolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 2,1981
_ _- _.. -.. _.._. _ - _. _. _, _.. _. -_ _ - ~. _ _. _. _
ATTACHMENT TO LICENSE AMENDMENT NO.63 FACILITY OPERATING LICENSE NO. OPR-28 i
j DOCKET NO. 50-271 Revise Appendix A as follows:
1 Remove Insert 49 49 49a 1
60 60 61 61 190a 190a i
193 193 215 215 4
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JL VYNPS TABLE 3.2.6 POST-ACCII)ENT INSTRtiffENTATION
. Minimum Number of.
Instrument Operable Instrument Channels ~
Parameter Type of Indication Range
-2 Drywell Atmospheric Temperature Recorder #16-19-45 0-300'F (Note 1)
Recorder #TR-1-149 0-300*F 2
Drywell Pressure (Note 1)
Recorder #16-19-44 0-80 psis Torus Pressure (Note 1) 0-80 psia
~2 Torus Water Level (Note.3)
Meter #16-19-46.\\
0-3 fr.
Meter #16-19-4611 0-3 ft.
Torus Water Temperature Meter #16-19-48 60-180 F
-2 2
Reactor Pressure (Note 1)
Recorder #6-97 0-1200 psig Heter #6-90A 0-1200 psin Meter #6-90B 0-1200 psig 2
Reactpr Vessel Water Level Meter #2-3-91A
(-150)-0-(+150)"It 0 (Note 1)
Meter #2-3-9111
(-150)-0-( t 150) "l1 0 1
Control Rod Position (Note 1, 2)
Meter 0-48" RPIS 1
Ne<neca Monitor (Note 1, 2)
Heter 0-125% Rated Flux 1
Torus Air Temperature (Note 1)
Recorder #TR-16-19-45 0-300*F 2/ valve Safety / Relief Valve Position Lights (SRV 2-71-A through D)
Closed - Open from pressure switches (Note 4) 1/ valve Safety J 1ve Position f rom Meter Z1-2-1A/B Closed - Open Acoustic Monitor (Note 5)
Note 1 - From and af ter the date that one of these-parameters is not indicated in the control room, continued reactor operation is permissible during the next seven days.
If reduced to one indication of a parainct e i.p. iat inn 1:
permissible for 30 days.
Note 2 - Control rod position and neutron monitor instruments are considered to be redundant to eacle ottier.
^
Auendment No. 63 w
TABLE 3.2.6 NOTES Note 3 - From and af ter the date that this parameter is reduced to one indication in the control room, continucil reactor operation is permissible during the next thirty days.
If both channels are inoperable und indication cannot be restored in six hours, an orderly shutdown shall be initiated and the reactor shall be in a hot shutdown condition in six houra cud a cold shutdown condition in the following 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.
Ilote 4 - From and af ter the date that safety / relief valve position from pressure switches is unavailab,Te, reactor operation may continue provided safety / relief valve position can be slotermined f rom recorder '!-166 (theim...ouple.
0-6000F) and meter 16-19-48 (torus water temperature.60-180 F).
If both indications are not avullable, the reactor shall be In a hot shutdown et.Jition n six hours and a cold shutdown condition in tho f ollouing 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.
Note 5 - From and af ter the date that oafety valve position f rom the acoustic monitor is unavailable, reactor operation may continue provided safety valve position can be determined f rom recorder 2-166 (therinocouple. 0-60001:
and recordc.- 16-19-44 (drywell pressure 0 80 psia).
If both indications are not available, the reactor shall be in a hot shutdown condition in six hours and in a cold shutdown condition in the following 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.
49.i Anendnent No. 63
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cal.IllitATI(W 11tl7)tilNCIIN IWr-ACCIDINT littrittMNTATlid
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l'arame t er Calibration Instmment Clicck lirywell Atmosphere Temi>crature every 6 months once each < lay Drywell.unt! Toms-Pressure every 6 months once each clay Torus Ifater level every 6 months once each shift Torus it. iter Temperature every 6 months once each clay iteactor l'ressure every 6 months once each clay Itcactor Vessel ifater Level every 6 months' once cach itay Control Itoil'I'osition (note 5) once cach clay Neutron ihnitor T
Same as reactor once cach slay protection systems O
C Torus Air Tenperature every 6 months once each alay N
g Safety /Itelief Valve Position every refueling outage (Note 9) once each day (a Funct.lonal Test to be y
perf onned stuarterly)
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Safety Valve Position every ref ueling outage (Note 9) once cach day (a Funct.lonal Test. to be performed quarterly) 60 Anendnent No. 63
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tat:!.E 4.2 NOTES his type Initially once per month; thereaf ter, a longer interval as deterinined by test results on t 1.
- "*t e-of instrumentation.
l h ll be During each refueling outage, simulated autoinatic actuation which opens all pilot va ves s a redundant cotutterpart.
perforened such that each trip system logic can be verified independent of 100 2.
for proper TtJp system logic calibration chall include'only time delay relays and timero necessary I
.3.
functionfug of the trip cystem.
The functional test will consist
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This inntrumentation is excepted froin functional test definition.
of injecting a simulated electrical signal into the measurement channel.
4.
Check control rod position indication uhile performing the surv :111ance requirement of section 3.3 S.
required when these instruments are not Functional tests, calibrations anil instrument. checks are notFunctional tests shall be performed before cach 6.
to he operable or tripped.
Caltheation shall he performed prior to dr during each neartup or to exceed once per ueck.
to exceed once per week.
Instruw nt checks shall frequency not controlled shutdounu uith a required frequency noticast once per day during those periodii when instrum bu performed at This Instrumentation is excepted f rom the functional test definttlons and shall be calibrated using 7.
nimulated electrical cignals once every three n.ontho.
required when cyctems are not required to be operable.
T Functional tects and calibrations are not 0.
that may be used f or g
The thermocouples associated with Saf ety/ Relief Valves and Safety Valve Position, i
O backup position indication, shall be verified to be operable every operating cycle.
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61 Anendnent No. 63 i
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5.
The Plant itealth Phynici,st shall ' meet or excee.1 the qualifications or.itegulatory ci Ide 1.8, l(ev f ulois 1.(September l')75).
(s.
.The Shif t Technical Advisor - shall have a hachelor's degree or equivalent Jn a scientific or engineerliig ' discipline with upecific training in plant design, and responne and analyuls of the plant. f or transients and accidents.
E.. A l' ire lirigade' of a t least 5.merhers shall'he maintained onsite at.al1~ times. # This excludes 2 members at 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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- Anondnent No. 63 190-a
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'6.9 ENVIRONMENTAL QUALIFICATION.
A.
By no later than June 30, 1982 all safety-rel.iled electrical' equipment in the racility shall be qualified in accordance wit.h the provisions or Division of Operating Heactors "Culdelines f or -
Evaluating Environmental Quall fleation of Cla:sa IM Electrical Equipment. In Operat.ing Heact. ors" (Dolt Guidelines); or, NUltCG-OS8ll " Interim Sta rr posit. ion on Environmental Quall rication of Safety-Helated Elect.rical Equipment.", December 1979 Coples or t.hese document.s are at.t. ached to Order for Hodifloation of License DPil-28 dat.ed Octuber 211, 1980.
D.
By no later than December 1,1980, complete and auditible records must be'available and maintained at a central location which describe the cavironmental qualt rication method used for all safety-related electrical equipment, in sufficient detail to document the degree of compliance with the DDR Guidelines or NUHEG-0588. Therca rt.er, such records should' be updat.ed and maintained carrent as equipment. is replaced, further tested, or otherwise qualirled.
6.10 INTECHITY OF SYSTEMS OUTSIDE CONTAINHENT A program to reduce leakage from systems outside cont.ainment that would or could contain highly radioactive fluids during a serious transient, or accident. to as low as practical levels will be*
Implemen ted. This program shall include the rollowing:
1).
Provisions est.ablishing preventive maint.enance anni periodic visual inspect.lon requirement.s, and 2)
Syst.em leakage' inspections, to the extent. permit.t.ed by system design and radiological conditions, for each system at a frequency not. Lo.excee.1 reruoling cycle intervals. The systems subject to t.his t.csting are (1) Hesidual Hea t. Hensoval, (2) Core Spray, (3) Heaet.or Wa t.cr C. canup, (ii) til'Cl,
(5) HCIC, and (6) sample syst. cms.
6.11 IODINE MONITORING A program which will ensure the capability to accurately determine the airborne lodina concentrat.lon in vital arease under accident condit.lons will be impicmented. This program shall include t.he following:
1)
Training of personnel, 2)
Procedures for monitoring, end 3)
Provisions for maintenance or-nampling and analynis equipment..
Areas requiring rersonnel access for establishing hot shutdown condit. ion.
215 Amendnent No. 63