ML19331D393
| ML19331D393 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/22/1980 |
| From: | Murray T TOLEDO EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML19331D394 | List: |
| References | |
| L80-1052, NUDOCS 8009020333 | |
| Download: ML19331D393 (1) | |
Text
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C TDL EDO e EDISON August 22, 1980 L80-1052 FILE: RR 2 (NP-33-80-69 NP-33-80-70 Docket No. 50-346 NP-33-80-71 License No. NPF-3 NP-32-80-12)
Mr. James G. Keppler R;gional Director, Region III Office of Inspection and Enforcement
.U. S. Nucicar Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Mr. Keppler:
Attached are three copies of Licensee Event Reports (NRC Form 366)80-055, 80-056,80-057 and 80-058 which have been corrected to include the NPRD-4 Form Code which vis omitted in block 24 of the LER form when the report was initially submitted.
The report date in block 9, which was also omitted, has now been entered on each form.
There has been no change to the supplemental information sheet for each of these Licensee Event Reports.
Please destroy your previous copies of these LERs an'd replace with the attached, corrected copics.
Yours truly,
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T rry D. Murray Station Superintendent Dsvis-Besse Nuclear Power Station TDM/1jk Attachments cc:
Mr. Victor Stello, Jr., Director Office of Inspection and Enforcement Enc 1:
30 copies LERs80-055, 80-056,80-057 40 copics LER 80-058 Mr. Norman Haller, Director Office of Management Program Analysis Enc 1: 3 copies cach LER THE TOLEDO ED:SCN COWANY EDISON F'LAZA 300 MAD:5CN AVENUE TCLEDO. OH;O 13652 80 0 9 0 2 033J
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U. S. NUCLEAR REGULATt RY COMMISSION 9 11)
LICENSEE EVENT REPORT g
CONTROL BLOC'K: l l
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(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI I
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lg 8 9 LICENSEE CODE 14 15 LICENSE NVMSER 25 26 LICENSE TYPE JG
$7 CAT 68 CC'4"T l0I1l
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8 60 61 DOCKET NUYBER 68 63 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h lo 121 l (NP-33-80-69) On 7/9/80 at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />, the control room operator observed that posi-l
.l c l 3 l l tion indication for the eC ergency core cooling system room ventilation exhaust damper l lll o 14 l lHAS441 had been lost. Attempts to move the damper were unsuccessful, and it was de-l ll c I sj l clared inoperable. The unit entered the action sta.tement of T.S. 3.3.2.1.
Tnere was l l-l C ls ] l no danger to the public or station personnel.
It would only be needed during a Safety l l c l 7 l l Features Actuation System incident concurrent with a seismic event that would damage l
lj c i,3 ; l this ventilation piping in the decay heat cooler room.
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8 9 80 SYSTE M CAUSE CAUSE CONIP.
VALVE CODE CODE SU8 CODE COMPONENT CODE SUBCODE SUBCODE o 9 i SI "I@ W@ L7J@ l zl zl zl zl zl ZI@ LZJ@ W @
7 8
9 to 11 17 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REV!SION LE RJRO EVENT YEAR REPORT No.
CODE TYPE No.
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JJ 34 35 36 31 40 41 42 43 44 47 CAUSE OESCRIPTION AND CORRECTIVE ACTIONS h Ltj,0,J lThe cause is unknown at this time.
The damper was manually closed and power to the l
it li j l motor operatt,r removed within one hour. thus conn 1 vine with the action sentecent-I g l Maintenance Work Order 80-2837 was issued to troubleshoot and repair. The reninen of!!
l11i31lthe investination were inconclusive.
When electrical maintenance checked. ir van l
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[i14Iloperable.
l 7
8 9 80 S
% POWER oTHER STATUS IS O 4 DISCOVERY DESCRIPTION l' 151 [Hj@ l 0 l 0 l 0 l@l NA l
l Al@l Control Room Indication l
ACTivlTY CONTENT RELE ASED OF RELE ASE AVOUNT OF ACTivlTY LOCATION OF RELE ASE
,1 l6 l [2,j @ LZj@l NA l
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to 13 44 45 80 PERSONNEL EXPOSUHES NUYGER TYPE DESCRIPTION l t l 7 l l 0 l 0 l 0 l@W@l NA l
PE RSONN E L INJun t CS NUMBER DESCRIPTION l-l l 0l 0 l 0 l@l NA l
1 E 9 11 12 80 LOSS OF OR D AVAGE TO F ACILITY TYFE DE SCR!P TION l 9 l [,ZJ@l NA l
M 9,
to 80 PUO L ICITY NRC USE ONLY l 'l LuJ@ DESCRIPTION l
lllllllIIllllI ttSUEp l NA e 9 10 68 69 80 E DVR 80-11 N VE OF PRCPAltER KCViU H"INIUd PHONE-RDn2 OG ^A t
URC FORM 56 U. S. NUCLEAR REGULATORY COMMISSION l'
7-77)
LICENSEE EVENT REPORT e
CONTROL BLOCK: l l
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8 9 LICENSEE CODE 14 15 LICENSE NUMdEH 26 26 LICENSE TYPE 40
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8 60 61 DOCKET NUYBER 68 b3 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l o ( 21 l (NP-33-80-70) On 7/9/80 at 2325 hours0.0269 days <br />0.646 hours <br />0.00384 weeks <br />8.846625e-4 months <br /> while performing ST 5030.09 in Reactor Protec-l 1
[ol3l l tion System (RPS) Channel 3, an insulated alligator clip slipped off the terminal studl 19141 l causing a short circuit between terminals 3 and 4.
This resulted in a loss of Y3 l
l l o 1 s ] [ which caused a loss of Safety Features Actuation System (SFAS) Channel 3 containment l l
lo ls i [ radiation, placiTr the unit in violation of T.S.
- 3.,3.2.1.Y3 was switched to an alter-l l o l 7 ] [ nate power supply and SFAS Channel 3 was operable within minutes.
RPS and SFAS Chan-l l
[otsii nels 1, 2, and 4 were continuously available.
I 80 7
8 9 SYSTEM CAUSE CAUSE COYP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SU8 CODE lE lB lh yh l C lh l C l K l T l B l R l K lh l A l@ l Zl @
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10 11 12 13 18 19 70 SEQUENTI AL OCCURRENCE REPORT REVISION LE R/RO EVENTVEAR REPORT NO.
CODE TYPE N O.
O"Ngnat 18101 1-1 1 01 Si c4 l-l 10 13 I l Ll l-l 10 I a
,_ 21 22 23 24 26 27 28 29 30 31 32 SU!PLIE TAKE4 ACT ON O PL T
T4 HOQRS 22 S B IT D F
1 UB.
MAN FACTURER
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33 34 JS 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS li 1 o l l The cause was a personnel error in that the technician used the wrong type of insulatep l
li li ] l alligator clips.
Under Mb'O 80-2821, F101 was replaced.
At 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br /> on 7/10/80, Y3 l l
[il7l l was powered from its normal source.
A memo was written by the Lead I6C Engineer, l
{ i l 3 l l cautioning the technicians on the importance of using the correct style insulated l
l alligator clips.
l i - 4 80 8 9 ST S
% POWE H OTHER STATUS bl5 OV R DISCOVERY DESCRIPTION m Lilij@ l 0 I o I o 181 N^
l i B 181 Surveillance Test Sr 5030.09 l
AEtiviiv COOTENT
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Av0aNTO,ACuviiv @ l LOCADON OF RELU5E @
Ruusto 0, nE LE Au I NA I
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i c li 8 9 10 11 44 45 80 PEHSONNEL F *' DES NUYPE R TYPE DESCHIPTION I 7 I I 01 01 d@L ;@L N^
l I1 PE HSONNE L INJU ES NUve[H OESCR!PitCN NA l
li l-l 1 01 01 01@l l?
9 9 11 17 80 l
LOSS OF OH CAVAGE TO T ACILITY l
T4PE DESCFPTION i a NA l
80 ti 9 10 g
gesu ESCRIPTION I: 1 'l Lii91 N^
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ie g s 9
& S0-119 Mn una W4WWM. M. M1 ;
at pggyg _
ECO En o O,&,t P3,,c,,
n, m i u nm avu U S NUCLEAR HEGumiom actilSSlaw (7 77)
LICENSEE EVENT REPORT CONTROL BLOCK: l l
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Jo l1l l OJH lD lB lS l1 l@l 010l 0l 0l 0l 0l 0l 010l 01 Ol@l 4l Il 1l ll 1l@l l
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7 8 9 LICENSEE CODE 14 15 LICENSE Nuvt?ER 2b 26 LICENSE TYPE JO bl CAT bd CON'T lolil soRylL @
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8 60 61 DOCK ET NUYbER 68 69 EVENT D ATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l (NP-33-80-71 ) On 7/10/80 at 1039 hours0.012 days <br />0.289 hours <br />0.00172 weeks <br />3.953395e-4 months <br />, while deenergizing SFAS Channel 2 for I
o a lmaintenance va bus Y2, the control room operator received a Decay Heat Loop 2 high l
l o l 4 l l flow alarm.
It was discovered that DH Cooler 1-2 Discharge Control Valve DH14A had l
l o i s I {niled open.
SFAS Channel 2 was reenergized at 1050 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.99525e-4 months <br />, however, DH14A began l
l o ls l l closing. DH14A Controller HIC DH14A overshot the previous setpoint and reduced decay l lol7][ heat to less than 2800 gpm.
There was no danger to the health and safety of the l
lpublic or unit personnel. A flow of at least 2000 gpm was maintained.
l og 7
8 9 80 DE CODE SLBC E COMPONENT CODE SUBC OE SU E
o 9 IS IF l@ U@ W@ I z I z 17. I z I z I z l@ U@ (z_j @
7 8
9 10 11 12 13 18 19 20 SE QUE NTI AL OCCUR R E N CE REPORT REVISION LER EVENT YEAR REPORT NO.
CODE TYPE NO.
O agg/RO 18101 l-j 1015171
[g_J 10 13 i Lt_J I-1 LLJ s
_2n 22 23 24 26 27 IS 29 30 31 32
<N ATO O PL NT ET HOURS SUD ITT D FO 1 B.
SUPPt s MAN FACTURER (J_J@Lc_J@
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3J 34 35 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION,,ND CORRECTIVE ACTIONS h l i l o l lThe cause wan procedural inadeouecy. Only the AC cortion of SFAS Channel ? needed to l 1 i lhe deenergized.
Decay heat flow was restored to creator rhnn 7 R M o n, nr inst hmore I
1, l 7 l [on 7/10/80.
A temporary modification will be written to ensure that the SFAS DC l
lij3ll Essential Instrument Power is not deenernized when takinc essential busses Y1. Y?.
I li 14 I lY3, and Y4 out of service.
l 7
8 9 80 A US
% POWER oTHER STATUS disco RY DISCOVERY DESCRIPTION
'lil5I d @ l0l010l@l NA l
W @l Control Room Indication l
ACTIV11Y CO TENT q
AMOUNToF ACTIVITY h l l
l R(L E ASED OF RE LE ASE LOCATION OF RELE ASE l116 l d @ l z l@l NA 8 9 10 11 44 45 80 PERSONNEL E APOSURES NUMBER TYPE DESCRtPTION 10101 Ol@LzJ@l NA l
i 7
' PEHSONNEL INJUIES DESCn,PriO.@
NUvee n 1010101@l NA l
p 8 9 11 12 80
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Loss OF 09 DAYAGE To F ACILITV I
T (PE D E SC HIP TION tm] Iz l@l NA I
8 9 10 60 DESCHiPTION issdtE @L NA I
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2 0 8 9 10 68 69 60 %
3 80-120 NwE OF PREPAREH Dave Brown 259-5000 Ext. 296
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