05000263/LER-1980-022-03, /03L-0:on 800529,primary Containment Oxygen Concentration Exceeded 5% by Weight Tech Spec Limit.Caused by Open Svc Air Isolation Valve to Drywell.Procedures Have Been Revised to Assure Proper Valve Positioning
| ML112900754 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 06/26/1980 |
| From: | Shurts S Northern States Power Co |
| To: | NRC/OI/RGN-III/FO |
| Shared Package | |
| ML112900755 | List: |
| References | |
| LER-80-022-03L, LER-80-22-3L, NUDOCS 8007010542 | |
| Download: ML112900754 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| 2631980022R03 - NRC Website | |
text
REGULATORY &FORMATION DISTRIBUTION S *EM (RIDS)
ACCESSION NBR:8007010542 DOCeDATE: 80/06/26 NOTARIZED: NO FACIL:50-263 Monticello Nuclear Generating Plant, Northern States AUTH.NAME AUTHOR AFFILIATION SHURTSS.J.
Northern States Power Co.
RECIPNAME RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director DOCKET #
05000263 SUBJECT; LER 80-022/03L-0:on 800529,primary containment oxygen concentration exceeded 5% by weight Tech Spec limitCaused by open svc air isolation valve to drywell,Procedures have been revised to assure proper valve positioning.
DISTRIBUTION CODE: A002S COPIES RECEIVED:LTR -1 ENCL SIZE:..Lt..
TITLE: Incident Reports NO T E S :----
RECIPIENT ID CODE/NAME ACTION:
BC WPbfL/TO,T0o5 COPIES LTTR ENCL 1
1 RECIPIENT ID CODE/NAME PM COPIES LTTR ENCL 06 2
2
- A/D CORE & CS A/D REACT SYS AEOD CHEM ENG BR CORE PERF BR EQUIP QUAL BR I&C SYS BR JORDANE,/IE MPA 11 OP EX EVAL BR TR AC TERAC BR ACRS NSIC 1
1 10 1
1 1
1 1
3 3
1 1
1 16 04 1
1 1
10 1
1 1
1 1
3 3
1 1
1 16 1
A/D RAD PROT 1
A/D TECHNOLOGY 1
AUX SYS BR 1
CONT SYS BR 1
EMERG PREP 1
HANAUERS.
1 I&E 09 2
- MOOREV, 1
NRC PDR 02 1
OR ASSESS BR 1
QA BR 1
SIT ANAL BR 1
TERA:DOUG MAY 1
LPOR 03 1
1 j? ~
TOTAL NUMBER OF COPIES REQUIRED; LTTR INTERNAL EXTERNAL:
61 ENCL 61
A NORTHERN STATES POWER COMPANY MINNEAPOLIS. MINNESOTA 55401 June 26, 1980 Mr J G Keppler Office of Inspection & Enforcement U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
Dear Mr Keppler:
MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Excessive Oxygen in Containment The Licensee Event Report for this occurrence is reproduced on the back of this letter. Enclosed are three copies.
This event 6.7.B.2.b.
mode for a Conditions is reported in compliance with Technical Specification in that it represents operation in a degraded short period of time as allowed by the Limiting for Operation.
Yours very truly, 0-I Zea L 0 Mayer, PE Manager of Nuclear Support Services LOM/DMM/jh cc:
Director, MIPC, USNRC (3)
MPCA Attn:
J W Ferman
- - over-80070 1o 5i3/
I/fC)
NIIC FOIIM.i166 (7.77) 7 8
CON'T 7
8 0672 OB0 LU.
S. NIJCII.All il GII.Alan1Y C(OMMISSION 17-771 0
80 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE
'SUBCODE COMPONENT CODE SUBCODE SUBCODE I ]
IS JA] 3 Z1 L
jV A jIL IV JE IX I
[ (JQ 7
8 9
10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION
~.LER/RO rEVENT YEAR REPORT NO.
CODE TYPE NO.
8 REPORT 18 1810 [J
102 12 1 Li_
L[
L--
L0 NUMBER I i
L-Q 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP.
COMPONENT TAKEN ACTION ON PLANT METHOD HOURS.
22 SUBMITTED FORM SUB.
SUPPLIER MANUFACTURER LXJ@LG_
Z_
WO 10 010101 [NJ 2N3 AC 1616 IS 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Upon discovery, actions taken to reduce 02 to less than 5% (accomplished within 8 hrs.
ITE1 I Service air isolation valve to drvwell found open. Leakage at drywell air stations I
1 caused gradual increase in 0, over several week period. Procedures and checklists have [T ] jbeen revised to assure proper positioning of service air isolation valve during opera-I l tion and assure that greater margins to 02 limit are maintained.
7 89 so FACILITY METHO OF r _STATUS
% POWER OTHER STATUS&
DICVRDSOEYDSRPTN@
E 5
LEJ I 1 I0 0 @l NA I 1BJ0 Operator Observation 7
8 9
10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE EE L zI (.Z 1 NA 1
7 8
9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE C)~LRIPTION 0
1T 101 10 13 zL I NA 7
8 9
11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION 8 [0 10 1l0 (1 NA 1
7 8
9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE
DESCRIPTION
I IZ 11 NA 7
8 9
10 PUBLICITY 80 ISSUED
DESCRIPTION
N 11]
OIN II NA 7
8 9
10 68 69 80 80 NAME OF PREPARER SAL Surts E
5MTiHiOO 0F 61 G
h~sz LICENSEE EVENI BEPOHT CONTROL BLOCK:
I (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
M1 NI M NI P1 1(02 0 0 1-0 100 101.0 l - 1010 1 4 11 11 1111 1 1 (D
9 LICENSEE CODE 14 15 LICENSE NUMIJER 25 26 LICENSE TYPE 30 57 CAT 58 REPORT
_L]
l0j5j0 0
0l2l613 (0l5j2l98 0
016 2
6 81 0l SOURCE j6I050001163~I 5I 1980KI16 21 LLJ 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES l The oxygen concentration of primary containment was found to exceed the 5% by weight limit specified in Technical Specification 3.7.A.5.a during the weekly surveillance test. The oxygen concentrations in the drywell and suppression chamber were 5.75% and 5.3% respectively. There has been one previous similar occurrence (RO-76-14). This I occurrence had negligible affect on public health and safety.
NIIC FOi (7-77) 7 8
CONT 7
8 78 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 0S JAJ (J
[ZJ jV lA L IV jE IX EJI LJa 7
8 9
10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER/RO EVENTYEAR REPORT NO.
CODE TYPE NO.
SREPORT 18 JJ L-J 10 12121 fj 10..J.11 L.LJ L-J 0
0_
NUMBER 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD.4 PRIME COMP.
COMPONENT TAKEN ACTION ON PLANT' METHOD HOURS SUBMITTED FORM SUB.
SUPPLIER MANUFACTURER U@L GJ1 LzJ@
U Lo1010101 WOJ@
LL I
lC 16 16 15 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS I Upon discovery, actions taken to reduce 02 to less than 5% (accomplished within 8 hrs.)
I Service air isolation valve to drvwell found open. Leakage at drywell air stations I
1 caused gradual increase in 0:, over several week period. Procedures and checklists havp I been revised to assure proper positioning of service air isolation valve during opera-1 I tion and assure that greater margins to 0,, limit are maintained.
7 89 so FACILITY 30 METHO0 OF STATUS
% POWER OTHERSTATUS DISCOVERY DISCOVERY DESCRIPTION I
LE Il 0I0 NA LLJI operator ObservationI 7
8 9
10 12 11 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY S LOCATION OF RELEASE 1 1 L6 O Z IUZel9 NA I
1N 7 8 9 11 44 45 PERSONNEL EXPOSURES NUMIER (DTYPE DSCRIPTION DI~~] lo 10 10 lLzlRI NA 7
8 9
11 12 13 PERSONNEL INJURIES NUMBER
DESCRIPTION
TI 10 10 10 1DI NA 7
8 9
11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE
DESCRIPTION
I Z 1@1 NA 7
8 9
10so PUO NRC USE ONLY ISSUED
DESCRIPTION
I L Jj83 NA I IIIIITIIi 7
89 10 6869 80 0
80 NAME OF PREPARER S.
J. Shurts%
PHONE:
612/29s -s 1; 7
08 M1 3C SE-I E.IS..
NiCI.IAll Ill GI I.A I OItY COMMISSION 0LICENSEE EVENIT EPOHRT CONTROL BLOCK:
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
MI NI MI NI P 1( ()1 0 10 1 - 10 10 10 10 10 1-10 10(4 lI 11j11 11l
)
1 (D
9 LICENSEE CODE 14 tB LICENSE NUMUEn 25 26 LICENSE TYPE 30 57 CAT 58 REPORT LLJIj 0l 50300 2j6L3J 10 1512 t9l8l0 j10 16 21 6! 81 01G 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES I The oxygen concentration of primary containment was found to exceed the 5% by weight limit specified in Technical Specification 3.7.A.5.a during the weekly surveillance test. The oxygen concentrations in the drywell and suppression chamber were 5.75% and 5.3% respectively. There has been one previous similar occurrence (RO-76-14). This occurrence had negligible affect on public health and safety.
80