ML112900754

LER 80-022/03L-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: 05000263/LER-1980-022, Forwards LER 80-022/03L-0 ML112900754
References
LER-80-022-03L, LER-80-22-3L, NUDOCS 8007010542
Download: ML112900754 (4)

Text

REGULATORY &FORMATION DISTRIBUTION S *EM (RIDS)

ACCESSION NBR:8007010542 DOCeDATE: 80/06/26 NOTARIZED: NO DOCKET #

FACIL:50-263 Monticello Nuclear Generating Plant, Northern States 05000263 AUTH.NAME AUTHOR AFFILIATION SHURTSS.J. Northern States Power Co.

RECIPNAME RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director 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 TE S :----

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL ACTION: BC WPbfL/TO,T0o5 1 1 PM 06 2 2 INTERNAL : A/D CORE & CS 1 1 A/D RAD PROT 1 A/D REACT SYS 1 1 A/D TECHNOLOGY 1 AEOD 10 10 AUX SYS BR 1 CHEM ENG BR 1 1 CONT SYS BR 1 CORE PERF BR 1 1 EMERG PREP 1 EQUIP QUAL BR 1 1 HANAUERS. 1 I&C SYS BR 1 1 I&E 09 2 JORDANE,/IE 1 1 MOOREV, 1 MPA 11 3 3 NRC PDR 02 1 OP EX EVAL BR 3 3 OR ASSESS BR 1 1 1 QA BR 1 TR; AC 1 1 SIT ANAL BR 1 TERAC BR 1 1 TERA:DOUG MAY 1 EXTERNAL: ACRS 16 16 LPOR 03 1 1 NSIC 04 1 1 j?~

TOTAL NUMBER OF COPIES REQUIRED; LTTR 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 is reported in compliance with Technical Specification 6.7.B.2.b. in that it represents operation in a degraded mode for a short period of time as allowed by the Limiting Conditions for Operation.

Yours very truly, 0-I Zea L 0 Mayer, PE Manager of Nuclear Support Services LOM/DMM/jh cc: Director, IE, USNRC (30)

Director, MIPC, USNRC (3)

MPCA Attn: J W Ferman I/fC)

-over-80070 1o 5i3/

NIIC FOIIM .i166 LU.S. NIJCII.All il GII.Alan1Y C(OMMISSION .

(7.77)17-771 LICENSEE EVENI BEPOHT CONTROL BLOCK: I (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

M1 NI M NI P1 1(02 0 01-0 100 101.0 l - 1010 1 26 4 11 11 1111 1 1 LICENSE TYPE 30 57 CAT 58 (D

7 8 9 LICENSEE CODE 14 15 LICENSE NUMIJER 25 CON'T

_L] l0j5j0 0 0l2l613 (0l5j2l98 0 @ 016 2 21 6 LLJ 81 0l REPORT 7 8 SOURCE 60 j6I050001163~I 61 DOCKET NUMBER 68 69 5I 1980KI16 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES 0672 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.

OB0 80 0

SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE 'SUBCODE COMPONENT CODE SUBCODE SUBCODE I ] 8 IS JA] 3 9 10 11 LZ1 12 jV 13 A jIL IVJE IX I 18

[ (JQ 19 20 7

SEQUENTIAL OCCURRENCE REPORT REVISION

~.LER/RO L[ CODE TYPE L-- NO.

L0 8 REPORT NUMBER I rEVENT YEAR 18 1810 [J REPORT NO.

102 12 1 Li_ 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_

33 34 35 Z_ WO 36 10 01010140 37

[NJ 41 2N3 42 AC 43 44 1616 IS 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 I1 I0 0 @l NA I 1BJ0 Operator Observation 80 7 8 9 10 12 13 44 45 46 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE 7

EE L zI ( .Z 1 NA 8 9 10 11 44 45 80 1

PERSONNEL EXPOSURES NUMBER TYPE C)~LRIPTION 0 7 8 101 1T 9

10 13 11 12 zLI 13 NA 80 PERSONNEL INJURIES NUMBER DESCRIPTION 8

[0 101l0 (1 NA 1 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION 7

I 8 IZ11 NA 9 10 PUBLICITY 80 ISSUED DESCRIPTION N 11] OIN II NA 68 80 7 8 9 10 69 80 5MTiHiOO 0F h~sz SAL Surts E 61 G NAME OF PREPARER

NIIC FOi M13C SE-I E.IS.. NiCI.IAll Ill GI I.A IOItY COMMISSION (7-77) 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- 1010(4 lI 25 26 11j11 TYPE LICENSE 11l 30

) 1 57 CAT 58 (D

7 8 9 LICENSEE CODE 14 tB LICENSE NUMUEn CONT REPORT LLJIj 0l 50300 2j6L3J 101512 t9l8l0 j10 16 21 6! 81 01G 7 8 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 60 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.

78 80 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 REPORT NO. CODE TYPE NO.

LER/RO EVENTYEAR SREPORT NUMBER 18 21 JJ 22 L-J 23 10 1212126 24 27 fj 10..J.11 28 29 L.LJ 30 L-J 31 00_

32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD.4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT' METHOD HOURS SUBMITTED FORM SUB. SUPPLIER MANUFACTURER 33 U@L GJ134 LzJ@

35 36 U Lo1010101 37 . 40 41 WOJ@ 42 LL 43 I lC16 16 15 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 DISCOVERY DESCRIPTION LLJI STATUS  % POWER OTHERSTATUS DISCOVERY 7

I 8

LE 9

Il 10 0I0 12 11 NA 44 45 46 operator ObservationI 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY S LOCATION OF RELEASE 1 1 L6OZ @ IUZel9 NA I1N 7 89 11 44 45 PERSONNEL EXPOSURES NUMIER (DTYPE DSCRIPTION DI~~]

7 8 9 lo 10 10 11lLzlRI 12 13 NA PERSONNEL INJURIES NUMBER DESCRIPTION TI 10 10 10 1DI NA 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION NA I9 Z 1@110so 7 8 PUO NRC USE ONLY ISSUED DESCRIPTION I LJj83 NA 6869 I IIIIITIIi 80 7 89 10 0

80 NAME OF PREPARER S. J. Shurts% PHONE: 612/29s - s 1; 7 08