ML19319D260
| ML19319D260 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/29/1975 |
| From: | Engle L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003130899 | |
| Download: ML19319D260 (6) | |
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.1 E O 0 975 Docket No.:
50-302 1_
m, APPLICMiT:
FLORIIA POWER CORPORATION FACILITI:
CRYSTAL RIVER, INIT 3 SUM \\RY OF METING WITH FLORIIA F0WER WRPORATION (FPC) CONCERNING 'i1IE CRYSTAL RIVER, INIT 3 (CR-3) FACILITY Pepresentatives of the NRC and FPC ret in Bethesda, 3hrf and on Au3ust 19,1975 l
and discussed the itens as surnrized bel.x. !An atteniince list is pmvided in Attachnent 1.
RESUGTION OF MAXUGt C0iEICCTION AND NE;l ESTIMATED FUEL IllG EATE FPC smred that rulti-utill7 mmership sidch occtired on July 31 19M 7
muld 111cv recteth of #"n ccnst". -im retivities for the 969 ca.mpleted CR-3 facility and their rm fuel load date has been improved from my,1976 to Februarf 7,1975.
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.m a-FPC stated six mnths ci raw data (Janux y to June,1975) has been co11ceted frew their nw Mot Retreival Systen myl their consult:mt, 'the NW Corporation, had infomed the this data could be processed and muty for sdnittal to -
NRC on Novenber 15, 1975.. NRC staff review wilk follow with~SER Supplemen't' 2 input conceming these ratters to bedissued to LE! c'n Ibrier@er 15, 1975.s
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- DiPLDIENTATION OF REGULA'IORY GUIDE 1.79, PREOPERATIOML TESTING OF_ _
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6' c r:plete: test procedure lfor
%_ ; verifying:the' capability. to heirculate; coolantifran.the stuptto the~ rea 1 f additional ~ calculation'ar]aresis-for PPCahich may-require bottitesting and/
coolant system.} Problem e;Not'PositiveTSuction. Head'.and To'rtexingT dbi C
. NRC staff. informed ~FPCithatitWfaciliticsnbiaver. Valley'and Tro#nihra ti, recently presented a complete: procedure for; implementing-Reg Cuide 1.79 and-w PPC was advised to. discuss?these matters wi.th the' applicant's forithese1TWw,.
. e facilities. > PPC wil14cep.m.C. _inf.ui.d... of_..their.ic_5nthb effv. 2 i.s. tor *A NR
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PLANS FOR TESTING PROPER DRAhTOhN TEES mR BCr3 K\\1ER STOPJE T.M (i%T)
Purs6 ant to the possible generic deficiency of proper drawdom times for BWST as reported by the Babcock 4 Wilcox Company on M1y 8,1975 to D. Knuth, Director, Office of Inspectirn and D1forcement, the appliamt presented their pieceduros for testing to verify ccrrect drawdoim times (see ).
FPC will notify ISE of test procedures and results and submit a copy of test results to DRR for review and evaluaticn.
POTENTIAL DIPACT C?i FIEL LCAD PATE IXE 10 LATE DELP.ERY OF VALVES RFCJIRED LN AUXILI!sY FEI1WG'iR SihtS 91'5)
Imc stated icliverf prob 1' ens conccaing two feedmter rives (FW-101 el D.V-162 shmm in fig.10-2 of CT.-3 FSAF) would prccently igret the fuel load am af Tcbm../ 7, ITS.
In order Oc evoid auitic:c.1 delay
-in completien of CR-3 tu 1 subseqwnt fuel 10ading, rPC requested they be allc ced to install substitute valves as an interin undificaricn of the AFS.
The neo substicule valves (Fishcr Qni.cols Co.) are 6" globe valves ala carben steel hiies rated at 600 psi and are testable to a muinun pressure 0
of 1300 psi. Design tq,erature of the valve body is ~30 F..'1ho actuatien is a pn2=stic fail closed cen;'.Tuction uith provlsiens for rrote ep : tion frcan the control roo;a 1:y a 120 volt AC scicnoid valva.
FPC stated they would continue to eyedite the procurement of the origiral feedt;ater valves for subsequent istallation and testing dring the first refuchng outage of CR-3.
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'Iho NRC staff requested that the. applicant evaluate the time frame required
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for installation and testing of valves,FW-161 and FhV-162 and notify NRC
-by letter that the original-valves will befinstalled at the earliest sintdem. < -
available with sufficient time-to ' envelope the time framo pii'o~ r~ to first J
1 refueling outage. The applicant was further requested to detonnine the-AT for design valve body temperature an.1 maximun operating te perature for theprttiliary Feedrarer Systen.
1 JFPC will inform NRC by lettor to the above requests and also provide the qualification. testing to be ~:mpleted for the two 'interin valves.
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CLASS Ih IUJBENT.
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m FPC requested the scaff to explore the possibility of issuing their.
Scoping Doctants-for Test Procedures as a formal suinittal to staff
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](rsquests kr addiriar*infbraationbyd to applicsnt on Angast 11, 1975., j_fg.,
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, "Itc staff will-detemine if. "PC's proposal is adeg. ate and notif the
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f lapplicante i.is.e ::ms by w
L. Engle, P.ceject Manager Light Water Reactors Branch 2-3 Division of Reactor Licensing, Attachracnts:
1.
List of Attendees.
2.
Outline of BWST Dnredc'.m Test m
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f ATTAGEENT 1
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j MEETING HELD JULY 7, 1975 WITH FLORIDA P0;iER CORPORATION CRYSTAL RIVER, UNIT 3 LIST OF ATfENDEES NRC F. A11enspach D. Bridges J. Fairobant L. Engle G. Ma:etis W. Pasedae A. Sch'.;ence FPC J. Rodgers B. Simpson I
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3 ATTAGEETr 2
~' s BRIEF OIITLINE OF DRANDOWN TEST I.
The HP1, LPI and BS pumps will be set up individually for their rated flows.
II.
Field wiring to the ES cabinets for the required ES equip:aent
'will be terminated.
III.
BST-1 and BST-2 will be pressurized to approximately 3 PSIG to simulate actual solution specific gravities.
IV.
The train "A6B" HPI, LPI and RBI ES Bypasses will be activated.
V.
All train "A6B" HPI, LPI and RBI ES Test Switches will be in the "Off" position.
VI.
A train "A" RBI signal will be initiated using the RBI test switches.
The subsequent ES train "A" equipment drawdown of the B'IST, BST-1 and BST-2 will be allowed to centinue for approximately 15 minutes.
VII.
A train "B" RBI signal uill be initiated using the RBI test switches.
The subsequent ES train "B" equipment drawdown o f the BW5T, BST-; and BST-2 will be allowed to continue for approximately 15 ninutes.
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VIII.
With chemical tracer in the NACH tank, a train "A5B" RBI siguc1 vill be initiated using the RBI test switches.
The train "A6B" drawdown will continue until the BWST reaches the "Lo Level" alarm or the chemical tanks reach the zero level point.
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