ML18026A826
| ML18026A826 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/16/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Tennessee Valley Authority |
| Shared Package | |
| ML18026A827 | List: |
| References | |
| DPR-33-A-093 NUDOCS 8401120528 | |
| Download: ML18026A826 (9) | |
Text
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UNITED STATES NUCLEAR R EG ULATORY COMMISSION WASHINGTON, O. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROlINS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
93 License No.
DPR-33 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated July 13,
- 1983, as supplemented by letters dated October 20, 1983 and November 17, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission '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 Commission; 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the common 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 Commission's regulations'nd 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 paragraph 2.C(2) of Facility License No.
DPR-33 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical specifications contained in Appendices A and 8, as revised through Amendment No.
93, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
840ii20528 83i2i6 PDR. ADaCV 05000259' PDR
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3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 16, 1983 Domenic B. Vassallo, Chief Operating Reactors Branch 02 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
93 FACILITY OPERATING LICENSE NO.
DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages:
38 39 41 85 2.
The marginal lines on the above pages indicate the revised area.
3.
Add the following new page:
110a
TABLE 4.l.h (Coat fnued)
Hain Stean Lint Isolation Valve Closure Turbine Control Valve Past Closure or turbine trip
~Garou (2l Trip Channel and Alam Trip Chanael aad Alarm HinteLuu Fre uenc Once/Month (1)
Once/Month (l)
Turbine First Stage Pressure Permissive (PT-1-81A and B, PT-1-91A and B)
Turbine Stop Valve Closure A
Trip Channel and hlara (7)
Trip Channel and Aleph Every
> Months Oace/Month (1)
NOTFS FOR TARLE 4.1.A l.
Initially thc minimum frequency For thc indicated tests shall be once pcr month.
2.
A description rif the three groups is i ncl>>dcd in thc Pases of this speci fica tion.
3.
Functional tests nrc not required when thc systems arn not req>>ired to hc opcrablc or arc operating (L.c., sl.ready tripped).
Tf tests are
- missed, they shall be performed prior'to rcturninr, thc systems to an operable status, 4.
This'nstrumentation is exempted from thc instrument channel test definition.
This instrument channel functional test will. consist of injcctinr a simulated electrical signal into the mens>>rcment channels
~
5e The w The water'evel in the reactor vessel will be perturbed and the corres-ponding level indi.cator changes will be monitored.
Thi b
te.,t will bee performed every month after complctinn of the monthly f inctional test program.
6.
The functional test of the flow bias network is performed in accordance with Table 4.2.C.
7.
Functional test'onsists of the in5ection of a simulated signal into the electronic trip circuitry in place of the sensor signal to verify operability of the trip 'end alarm functions.
Amendment No.
93
HATI:S FOR TAIILE 4.1
~ II 1.
h description of three groups is inc'udcd in the bases of this specification.
Calibrations are not required when the systems arc not required to be operable. or az'e tripped.
Xf calibrations are missed, they shall bc performed prior to returninII the system to an operablc status.
4.
The current souzce provides an instr<<ment channel alinnmcnt.
Cali-bration using a radiation so<<rcc shall bc made each refueling outage.
Required frequency is initial staz'tup folio in@ each refueling outage.
pt>ysical inspection a>>>l art>>ation oc these positio<<switches will be pcrI'o>mcd once pcr opcrat.inn cyc3e
~
On controlled startups, overlap between the IIQI's and AI>RN's will.
be verified.
The Flow Bias Signal Calibz'ation will consist of calibrating the sensoz's, flow convcrtezs, and siI:nal offset networks during each opczatinp, cyc3c.
The instrumentation is an analog type with zedun-d
'low si~nals that can be compared.
The flow 'comparator trip 4
~ C and upscale will bc functionally tested accozdinn to Taole
.2.
to ens<<rc the propez operating during the. operatinz: cycle.
Refer to 4.1 IIascs Cor further explanation of, calibz'ation frequency.
A co>np'lcte tip system traverse cal.ibrntcs the LPP>< sipnnl.. to the process computrg.
Thc in<livid<<el I.PIIH n>uter rcadinI's will bc adjusted as a minimum at thc bcqinninI: of each opcratin cyc'e before zeachinq 100Z power.
9.
Calibration consists of the adjustment of the primary sensor and associated'omponents so that they correspond within acceptable range and accuracy to known values of the parameter which the channel
- monitors, including adjustment of the electronic trip circuitry, so that its output relay changes state at or more conservatively than the analog equivalent of the trip level setting.
41 Amendment No 93
TABLE t I h SORVEILLAHCS REQDIRZHIHTS FOR PRIlCARZ COHTAIHHXHT AHD REACTOR SOILDIHO ISOLATIOV IHSTRUHIHTATIOH tunction Instrusent Channel-Reactor Lov Qatar Level (LIS-3-303A-Di SH 3-3)
Instrument Channel Reactor Bfqh Pressure Instranent Chaanel "
Reactor Lov Qatar Level
[LI8 3-54A-Dg SQ 41)
Iastrusent Channel-Siqh Drywall tressure fPs da-54A-0$
Instrusent Channel Siqh Radiation Hain Stean Ltae Tunnel Inetrusent Channel-Line IPL'-V-8,-'N,-b2,-86)
Functional Test l1) (27) calibration Frequency CS) once/3 nonths once/3 nonth tS) 15)
Once/operating cycle (28)
Instrusent Chec'k once/day none once/day H/A once/day
- 11) (27)
Inst rusent Channel Biqh tlov Hain Stean Line (cPZ 1 13A D 25A D g 36A D g 50A D)
Inetrunent Channel l1)
Hain Stean Line Tunnel Siqh Tesperature once/opecatiny cycle none
. OnCe/Operating CyCle (28) once/day Inetreent Channel Reactor but ldinq Ventilation Biqh Radiation - Reactor tone 11)11<) 13>)
once/) nonths once/day 14)
NOTES FOR TABLES 4.2.A THROUGH 4.2.H Continued 27.
Functional test consists of the in3ection of a simulated signal into the electronic trip circuitry in place of the sensor signal to verify operability of the trip and alarm functions.
28..
Calibration consists of the adjustment of the primary sensor and associated components so that they correspond within acceptable range and accuracy to known values of the parameter which the channel monitors, including adjustment of the electronic trip circuitry, so that'ts output relay changes state at or more conservatively than the analog equivalent of the trip -level setting.
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Amendment No.
93