ML20083K738
| ML20083K738 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/30/1984 |
| From: | Kemper T PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 96, NUDOCS 8404170014 | |
| Download: ML20083K738 (4) | |
Text
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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET I
t P.O. IlOX 8609
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Dr. Thorvis E. Murley, Director Office of Inspection and Enforcement - Region I United States Nuclear Regulatory Commission
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631 Park Avenue King of Prunnia, PA 19406 i
Subject Limerick Cenorating Station. Units 1 1. 2 I
Significant Deficiency Report No. 96 (Attachment 1)
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Hoference Letter - J. S. Keeper /PEco to T. E. Hurley/NRC, l
dated 11/28/H3 l
F11ol QUA!. 2-10-2 (SDR No. 96) l Dear Dr. Hurley j
In compliance with 10CFR50.55(e), we are submitting our Final Significant Deficiency Report concerning loose valve stess anti-rotation devices (SDR No. 96).
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An interim raport (see referenen) was previounty submitted to your 1
i ottice.
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l We trust that this natisfactority resolves the ites.
If further f
information in required, please do not hesitate to contact us.
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l Sincerely,
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f$4C-f Copy tal Director of Inspection and Enforcement l
United States Nuclear Regulatory. Commission Washington, DC 20555 D. Chaudhary, Resident WRC Inapector (Limerich) i l
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LIMERICK GI-II!3%TI?K1 STATIGI, UNITS 1 & 2 SIQ11PICN(r DITICI!2CY RITORT 10. 96 CGXHJ21I?G VAINE ST124 NfrI-IUTATIGl DINICIE NKJIOR DARLI!M CICIJU VNNI'S 1.0 Intrrxtuction Thin in th final report nxjarding the loononing of the not nerew on valvo ntern anti-rotation collarn on Anclor Darling gloin valven.
An initial notification wan given to the USNIC by telephone on Octotor 31, 1983 and an interiin report was rdrnitted on ikmsiirr 28, 1983.
2.0 &ncription of Prrhinrn Tio stavan of nubject Anchor Darling valvon aro provental fran rotating by an anti-rotation collar wh. -h in fantened to tin valvo atun by mann of one (1) or two (2) not scnun depending on valvo riirn. Au loryJ an the ntan in prevent (xl frorn rotating, dio qmrator of tln valvo will drive tho dink through itu full otroko an denirut. birn tho ant.l-rotation collar lxurna loorn, it my nitp out of itu lockiry; ponition, p'nnittirvf tho locking key to drop out. Ulth On dinervjagemnt of On locking arrangemnt, the ntun will rotato winn driven by tho gerator and the dink will no loryJer novo tn ita propar ponition. 1hin nulfunction han Inn chnerval in noveral inntancon durity; ntart-up tenta of varioun nyntrann at
!.frnrick Gonoratintj Stat ion.
3.0 03rr;octivo Act ion (n) to in Taksin An invontigation of tin ptthtrea han toen cceptotni by Ancine Irtrlity; C<rputy, Ilechtol liwr CorToration arv! Philadelphia 1:loctric Catpany. An p1rt of tho inventigation, a prooxluro wan ptcparol for irplernrntation of tin noconnary correctivo actionn. A copy of tho prooxluro in attaciv31.
Sin rearrv rvlol notification wan applint to neweral valves in nyntemn that wro in proconn of ntart-up geration aryl wro krx.un to exp'rienco vibration. Af ter a nuninr of ntartn and extervlal p'ricx!n of qnration, a circk rovealn! that tho not nerewn rotuiryx!
tlyht. Ilo loormnirvJ or rolaxation of tivr not nenvu occurrtxt. An a renuit of tin nuccennful gurtontuneo of tin nixlification, a ptojrarn wan initiatet to lorfonn tin rivxtification on all Anchor Darlir>; notar qcratn1 globo valvon locatel in nafoty syntann.
Thin wrk will in amplotnl prior to fuel load of Unit 1.
' 4.0 Safety Inplications The problem was identified in the Core Spray (CS)' and Pesidual Heat Removal (RHR) systems. However, the potential deficiency also exists in the High Pressure Coolant Injection (HPCI) and the Reactor Core Injection Cooling (RCIC) systems since these_ systems also enploy the type of Anchor Darling globe valve on which the problem has been identified. A reduction in coolant flow to the reactor core could occur in all four (4) systems if the Anchor Darling valves became inoperative in any partial or full open l
position.
l In addition, if the Anchor Darling valves in the steam supply lines to the HPCI and RCIC turbines failed in a closed or partially open position, those systems would becme either inoperable or operable at sme reduced rate.
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Locking Procedure for Stem Clamp Setscrew (s)
A.
Select the proper Allen wrench.
B.
Pcmove the setscrew (s) frcm the clanp.
C.
Hold the clamp in place and nnrk the location of the setscrew hole (s) on the valve stem.
D.
Allow the clamp to drop taking care not to lose the key (s).
E.
Use a drill to make a small indentation (s) in the stem. Dimensions for the indentation are given below.
F.
Peplace the key (s) and lift the stem clamp into place.
G.
Apply lectite No. 580 to setscrew threads.
Replace the setscrew (s) and torque to the value shown below.
H.
I.
Scribe reference mark on setscrew and on stem clamp for future use in assuring no loosening of the setscrew.
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SETSCREN DRIIL MAX. DEPTH TORQUE SIZE SIZE OF INDENTATION (ft-lbs.)
1/4 1/4 3/16 3
5/16 5/16 7/32 6
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3/8 3/8 1/4 12 7/16 7/16 9/32 19 1/2 1/2 5/16 28 9/16 9/16 11/32 40 5/8 5/8 3/8 56 3/4 3/4 7/16 100 h
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