ML20117M663
| ML20117M663 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Crane |
| Issue date: | 09/22/1983 |
| From: | Conner E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Keimig R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20114G054 | List:
|
| References | |
| FOIA-84-616 NUDOCS 8505170154 | |
| Download: ML20117M663 (4) | |
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.. f UNITED STATES ep razy g
jo, NUCLEAR REGULATORY COMMIS$10N 1
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' REGION i
,y 631 P Am er. A V E N UE f
KING of PRUSSI A, PE NNsv t.V ANI A 194D6
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.c Le Septc=ber 22, 19E3
- MEMORANDUM.FOR:
R. R. Keitig, Chief, Projects Branch No. 3 Division of Proj ect and Eesident Progra=s (DPKP)
E. L. Conner, Chief Project Section 33, DPP.P
- FKOM:
SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE
- SUEJECT:
(SALP) INPUTS (TMI-1) q in acccrdance with Region 1 Instruction 0501.5, dated October 8, 1982, this is
- notification of the trigger date (board date cinus 60 days - September 29, 1983) to start the writing of inputs for the TMI-1 SALP.
By copy of the.
memorandum, responsible (lead) section chiefs are requested to provide inputs for the SALP to Mr. E. L. Conner (at the Region 1 Of fice) by November 3,1982, (re: NRC Manual Chapter 0516).
Lead sections for the various SALP functienal areas are annotated on the enciesure_along with support sections or offices that may be required to provide a f eeder on a verk activity conducted during the SALP period (10/1/82 to 9/30/83).
I will keep.you appraised of any delays in preparing the SALP input per schedule.
-Q J
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E. L. Cenner, Chief Proj e ct Section 35, LPRP Cen' tact:
Enclosure:
As' stated 4
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- S:ptsmb:r 22,.1983
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21 C. Andersen, RI
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W. Crocker, RI'-
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Davis,;NMSS--
-:J. Durr,~RI S. Ebneteri RI
~A. Fascno,--K12
' J. ' Jastisan, -- RI J.fJoyner, RI~
E., Nicholas, RI.. >
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Starostecki, RI-
'M.'Shanb'ky. RI-a J. Stolz, NRR F ' Young :RI lJ.:Vanvliet, NRR-f s
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ENCLOS"RE SALP INPUT RESPONSIEILITY TM1-1 (Period 10/1/62 to 9/30/S?)
TMI-l Functienal Area lead Support 1.
Plant Operatiens (PLT)
Z/U LPM 6 AEOD (Shutdovn) 4 a.
QA/QC (QAC)
M/F Z/U Training (TRN)
M/F Z/U Corredtive Action Syste:
M/P Z/U Management Info /
Records M/P Z/U Procedure Support /
Drawing Software M/P Z/U
'b.
Engineering Analysis P/S 2/U Engineering Resciution P/S 2/U Design Change /
Modificaticns (DCM)
P/S Z/U S
c.
Housekeeping /
Cleanliness Z/U M/P d.
Licensee Violatien P cJ.1:va; Z/U ALL e.
Ccr.tracter Use and Centrel I/U ALL C
[2.) Radielegical Centrols
(~Z/R NA Prctectict (7,CP)
Waste Manage:ent (RCW)
Transpertatien (RCT)
Effluent Centrol 6 Monitoring (RCE)
S 3.
Maintenance (MdT)
M/F Z/U G
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Su rveillanc e (I.:1/IST Preep Test).
T /P Z/t "l?
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Pire Protecticn (TDP)
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g/P NA 7
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Esergency Prentredness D
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Punctienal Area Lead Surpert S
7.
Security /Sofeguards (SPP)
S/S NMSS 6.
Refueling (RET)
Not Reviewed c.
9.
Licensing Activities (LCA)
LPF' 2/U Other NRK Branches 10.
Tabular Su== aries ADM 2/U Violatiens vs Severity Inspectien Reports vs Modules vs Hours LER FiJe (1982-83) 01 Pile by Functional Area (Opened and Closed in 1982-1953)
Respensibility Codes D/P Emergency Preparedness Section, DETP LPM Licensing Project Manager, NRR M/P Management Progra s Section DETF P/S Plant Syste: Section, DETP T/P Test Programs Section, DETP 2/R Onsite Radiation Specialist. DPRP (Support frem DETP) 2/U Resident Inspectors, DPRP S/S Security / Safeguards Sectien. DETF NM55 Office ef Nuclear Material Safety and Safeguards AIOD Office fer Analyris and Evaluatien ef Orcratienti Data (if verk activity a;;11ed te ~M:-: during S Ali ;c ri:d)
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September 29, 1983 I
e James C. Keppler Reglonal Administ rator Region Ill D. 5. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn,'IL 60137
Dear Sir:
Reportable Occurrence Report f_83 M L-0 Docket #050-373 is being submitted to your of fice in accordance with LaSalle County Nuclear Power Station Technl-cal Spect fIcation 6.6.E.2. (b), condit tons leading to operation in a degraded rode permitted by a limiting condition for operation or plant shutdown reculred by a Iimit Ing condition for operetlon.
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4/ t'LE G. J. Dicderich Superintendent LaSalle County Station CJD/CW/rg Enclosure cc:
[>1 rector of Inspection & Enforcenent Director of Hanegernent Inforrr.ation (, T rogram Cont rol U. 5. NRC Docurent Managerent branch lNPO-Records Ceriter File /NRC
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ilmit of 0.6La(231.45CrH) was exceeded.
Valves 1Bf1-T01DMf, IE21-F032 A/1 for feed g
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for the c'u:Loerd W check velvet failed.
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LER NUMBERt 63-107/03L-0
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LASALLE COUNTY STATION: Unit 1 lit.
DOCKET NUMBER: D50-373 IV.
EVENT DESCRIPTION:
On September 1 1983 with the unit shutdo for a planned outage, it was determined that the Technical Specification 3.6.1.2 limit of 0.6 La (231.4 scfh) was exceeded.
The inboard feedwater check valve,1B21-F010B, was leaking in excess of 3900 scfh.
Various valves for the feedwater penetrations, as well as for the RCIC 3
steam lines, the main steam drain line, the RCIC turbine exhaust line and the Primary Cont ainment "A" chilled water line also had leakage which was considered.
excessive.
The associated valves are 1B21-F010A, 1 B 2.1 - F032 A, 1521 - F032 E,
1B21-F016, IVP063A 1E51-F06E and 1E51-F006.
Several valves associated with the "A" feedwater penetration, the RCIC vacuum breaker line, and the Instrument Nitrogen line had leakege rates which exceeded the leakage guideline as stated in the procedures.
These valves were IB21-F065A, 1E51-F050, 1 E51-F056,11N074, l lN075,1E51-F063,1E51-F064 and 1E51-F076.
V.
FROEABLE CONSEQUENCES OF THE OCCUhrsENCE:
Those va,1ves which 1 caked slightly in excess of the procedure guidelines, valves 1 B21 -F015 A,1E51-F050,1E 51-F056,11N074, l lN075,1E51-F063,1E51-F064 and 1E51-F076, were considered to have acceptable Icatage.
I r-nil e - e# _e thare wee at least one tenistinn ~ 1"*
" * -inin-Staa "hirh The plant was maintained in a safe condition
_had an accepteble Icakape rate.
at all 1irnes.
VI.
CAUSE:
cause of the inboard check valves,1B21-F010A/E 1cakape has not The exact been determined as of 25 September 1983. Vnen the valves we re opened for inspection the sof t seat shwed damage around the pressure relieving vent grooves, some wear on the soft seat face, and slight wear on the body seat.
The out board feedwater check valve 1821-r032A/B 1eaked because the valves -
would not s eat properly. The valve was seated loosely when the piston scals failed to seal the area around the pistons. This caused alr gesket to Icak past the piston which then failed to seat the valve.
1E51-F066, es well as valves 1B21-F010A,1B21-Valves 1 B21-F016, IVP063 A, F010B, and 1B21-F032A/B sho ed some wear on the valve seats which probably cont ribut ed to the excessive leakage found.
The main cont ributor of le.akage f rom the four valves IE51-F005, IE51-F063, IE51-F064 and 1E51-F076 which are tested together, was f rom the pa: king of t he 1E51-F006 valve.
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LER NUP.EEh; E3-107/03t-o
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No cause for the leakage from valves 1E21-F065A, ilN074, ilN075,1E51-F0B0 and 1E51-F086 has been dete rmined as they we re considered to have an accept-able leakage.
Vll.
CORRECTIVE ACTION:
Valves 1521-F010A,1521-F010E,1E21-F032 A/E,1 E21-F016, I VP063 A and 1E51-F068 had their seats lapped. The soft seats on the 1E21-F010A/B disk were re-placed by Commonwealth Edison Nuclear Engineer Department, the Station and the Anchor / Darling Valve Company.
It was determined that like for like seal rep l ac e ne nt was proper es long as any shaving on the soft seat was done by grinding under the supervision of Anchor / Darling and any burrs or cuts in the vent groove where filed to a smooth finish.
A supplemental LER will be issued if additional corrective action is determined to be reovired. The piston gasket seals on valves 1B21-F032A/E were replaced and the packing on valve 1E51-F005 was repai red.
The leakage f rom the rest of the valves in combination with the Icakage f rom the repai red valves were acceptable and below the Technical Specification limit of 0.6 La.
No work was therefore done on the llN074, 11N075,1E51-F050, and 1 E51-F0E6 valves. The leakage from valve 1E21-F065A was accepted as it was pbobably leaking past renual valve 1 E21 - F011 A.
(Normally cpen test boundary)
Frepared by:
Kermit C. Vittenburc I
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