ML18024A498

LER 78-017/03L-0:on 781004,drywell Oxygen Concentration Was Not Reduced to 4% within 24 H Period After Placing Reactor in Run Mode.Caused by Personnel Safety Considerations During Repair of Inner Drywell Air Lock Repairs

ML18024A498
Person / Time
Site:	Browns Ferry
Issue date:	10/25/1978
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18024A497	List: ML18024A496 ML18024A498
References
LER-78-017-03L, LER-78-17-3L, NUDOCS 7810300171
Download: ML18024A498 (3)

Text

NRC FORM666 I7 77)

LlCENSEE EVENT REPORT CONTROL BLOCK: Qi IPLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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~O A L B R FE Q7 0 0 - 0 0 0 0 0 - 0 0 Q3 7 1 1 1 1 Q4~QS 7 8 9 LICENSEE CODE 14 i5 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T

~O soUROE L~JQB 0 0 0 0 2 6 0 7 1 0 0 4 8 B 1 0 2 8 QB 60 61 DOCKET NUMBER BB 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DFSCRIPTION AND PROBABLE CONSEQUENCES QIO

~02 The dr ell ox en concentration @as not reduced to 4 within the 24-hour riod

~03 subsequent to plac ing the reactor in the run mode. T. S ~ 3.7.A. 5.b. was not complied

~04 vith. There @as no haiku d. to the public health or safety. Prev'ious occurrences:

Hone,

~06

~O7

~OS 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SVBCODE COMPONENT CODE SUBCODE SUBCODE

~OB ~SA Q77 E Q'7 ~BQ77 P E E E 2 R Q4 ~AQ7> ~E Q7A 7 8 9 10 11 12 13 18 I9 20 SEQUENTIAL OCCURRENCE REPORT REVISION Q77 LERIRO IIEPORT ACTION .FUTURE EVENT YEAR

~R 21 22 EFFECT

~

23 SHUTDOWN

~Q]

24 REPORT NO.

7 26

~~

27

~P3 28 ATTACHMENT CODE 29 NPRDR TYPE

~L 30 PRIME COMP.

~

31 NO.

32 0

COMPONENT TAKEN ACTION ON PLANT METHOD HOVRS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~DQIB 33

~GB 34

~c026 35 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27

~021 36 37 o o o o 40

~r 41 023 ~N024 42

~HQ26 43 44 G 0 8 o 47 0

o Inerting @as delayed, for rsonnel safet durin inner dr e a

("0"-Ring replacement). The reactor was laced in the run mode at 2 10-3-78, Inerting began at 1750 hours0.0203 days <br />0.486 hours <br />0.00289 weeks <br />6.65875e-4 months <br /> 10-4-78. Concentration of less than 4 was 3 reached at 0270 hours0.00313 days <br />0.075 hours <br />4.464286e-4 weeks <br />1.02735e-4 months <br /> 10-5-78. Door sealing surfaces vi1 1 be reexamined dur i t next refueling outage.

7 8 9 80 FACILITY METHOD OF STATUS 3I POWER OTHER STATUS QBO DISCOVERY DISCOVERY DESCRIPTION Q32 S ~CQ77 ~OX Q77 Ld031 7 8 9 10 12 17 44 45 46 80 ACTIVITY CONTENT RELEASEO OF RELEASE AMOUNTOF ACTIVITYQ3 LOCATION OF RELEASE Q36 7

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~zO ~zs ll 9 10 44 45 80 PERSONNEL EXPOSURFS NUMBER TYPE OE5CRIPTION ~39

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~00 0 Q77 ~ZQM 13 EA 7 9 11 12 80 PERSONNEL INJURIES NUMBER OESCRIPTIONQ41 L

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~00 9

0 Q40 HA 7 11 12 80 LOSS OF OR DAMAGE To FACILITY TYPE DESCRIPTION Q43

~19 ~ZQ42 HA 7 8 9 10 80 mB ISSUED WHS PUBLICITY DESCRIPTIO 0 HA NRC USE ONLY O

7 8 9 10 68 69 ~ 80 o 0

NAME OF PREPARER PHONE:

7p./63d o/7 j

0 Form BF-17 BF 15.2 6/09/78 LER SUPPLEMENTAL INFORMATION BFRO 260 / 7817 Technical Specification Involved 3.7.A..b Reported Under Technical Specification 6.2.A.2 Date of Occurrence 10-4-78 Time of Occurrence 2025 Unit 2 Identification and Descri tion of Occurrence:

The drywell 02 concentration vas not reduced. to 4$ vithin the 24-hour period, subsequent to placing the reactor in the run mode.

Conditions Pr ior to Occurrence:

Unit held at 160 hÃe while the dr+ell personnel air lock door seal repairs vere made.

Action specified in the Technical Specification Surveillance Requirements met due to ino erable e ui ment. Describe.

None 1

A arent Cause of Occurrence:

The drywell personnel air lock inner door "0"-Ring sealing surface was leaking.

Anal sis of Occurrence:

None Corrective Action:

The dryvell personnel door sealing "0"-Ring vas replaced and. a silicon type sealer was used. to supplement the "0"-Ring.

Failure Data:

None Tennessee Valley Authority - Brovms" Ferry Nuclear Plant

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