ML19031A547

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LER 1976-017-01 for Salem, Unit 1 Inoperable Personnel Air Lock - Elevation 100'
ML19031A547
Person / Time
Site: Salem  PSEG icon.png
Issue date: 01/04/1977
From: Schneider F
Public Service Electric & Gas Co
To: O'Reilly J
NRC/IE, NRC Region 1
References
LER 1976-017-01
Download: ML19031A547 (4)
v • d • e


Text

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Frederick W. Schneider Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101. 201 /622-7000 Vice President I . *

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January 4, 1977  : .. : ... *- .. .:. *_ :.~"

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Mr. James P .. O'Reilly*

Director of USNRC Office of Inspections and Enforcements Region l 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. O'Reilly:

LICENSE NO. DPR-70 .. *.

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  • DOCKET NO. 50-272 ...

REPORTABLE OCCURRENCE 76-17/3L Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications,* Section 6.9.1, we are submitting Licensee Event Report for Reportable Occurrence 76-l7/3L. This report is required within thirty (30) days of the occurrence.

Sincerely yours, CC: Director, Office of Inspection and Enforcement (30 copies) 81 Director, Office of Management Information and Program Control (3 copies)

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- --76-l 7/3L I_ --

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  • -Report Date: --*08/76'-

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-"----*: Occurrence Date: '12/06/76

- -:- :-. -:*-Facility

  • _salem Generating *station :

_- Public Service Electric & Gas Company

-- _Hancocks Bridge, New Jersey. 08038 '  ! _.:- .-. :-******

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- IDENTIFICATION-OF OCCURRENCE:

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- :Inoperable personnel ~ir_ lock .:... ~ievation 10'() 1 ~- * - "' * *

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--- -  : CONDITIONS PRIOR 'TO OCCURRENCE: *. .__. ...:** ..

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Mode 3 operatiori,-Plant pressure 2235 psig, Plant temperature 532°F.

- : -*I DESCRIPTION OF OCCURRENCE: .-

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DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

Upon entering Mode 4 on li/24/76, the elevation 100' personnel air lock was-inoperable as per Technical. Specifications L.C.O. paragraph 3.6.1.3 due to a calculation error associated with the acceptance value speti-fied in SP(0)4.6.l.3.

ANALYSIS OF OCCURRENCE:

During Mode.4 and Mode 3, the elevation 100' personnel air lock interior-door exceeded the minimum acceptable leakage rate* as specified in S.T.S~

_3._6 .1. 3. - At_ no time during this period did the_ :::::onto.inment pressure exceed th~t specified by Technical Specifications and at no time was there any hazard. to the general public or site personnel*

CORRECTIVE ACTION:

The Maintenance Department replaced the elevation 100' personnel air lock interior door seal, replaced the latch bolts and repositioned the latching mechanism. The Operations Department issued a procedural ~*

chapge to reflect the correct acceptance value and retested the personnel air lock satisfactorily in accordance with SP(0)4.6.l.3. -

FAILURE DATA:

This is the first failure of this type.

Component: Elevation 100' personnel air lock Manufacturer: Chicago Bridge and Iron Company B~ Canfield Manager - Sal'm Generating Station SORC Meeting No. --~~~~~~--

122-76

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. - UCl:PtSCC NAM& - . UC'&NSC NUM8E:R .. . .

@El4N1J:1s1G1s1~1 !1tio101-101010101crr-1 _ 01q~ k411111111~ WJJ-J.

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  • CATEGOAV TV~ SOUAC::E OQC:Kl:T NUM8CR * * . CVIEHT OATIE RE~AT OATC .
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- ... !VENT oesc~IPTION - . -: . - .. . . . .. *' . . - ';:' ; \-->- ._-_ .. . .. * .

  • 10!211 On 12/6/76, the NRC inspector, in-performing' routine inspection of the

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@:§] Operations Department* Surveillance Procedures, 'identified that the 9

. . : *. fo1~j ance value of .::.. 6S% for the -Elev.160' and l.30' personnel air *lock seal

  • 7 i . .  ;
    • _.,_ * [.[!§]I air flow Yas inaccurate as specified in SP(0)4.6.l.3. Subsequent investit 1 89 . . 80

@:]!] 1 gation bv the licensee of the air flow: calculation ind_icated that the r 7 8 9 . . PRIME 80

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  • SVST!:M* C:AU!E COMPONENT COMPONENT .

c:oce: c:oce: C:OMllONUtT c:ooe: SU"9\.IER MANUF ACTUAE:R VI Cl.AT ION

@ID IS I A I Lill l 'X! XI XI Xl XI XI ~ £ I 3 j 11 0 I l!J 1 as 10 11 12 * .. 11 ~ ~ 47 ,48 CAUSE OESCrUPTION

~\Upon entering mode four on 11/24/76, the Elev. 100' personnel air lock .wa¥

@illas inoperable as per .Techn:foal Sp~cification L.C.O. paragraph 3.6.1.3 du~ t~

1 co G:i]I a calculation error in SP(0)4.6.1.3. f 1 as

  • 80 ll'ACll.ITV M~MQQOF STATUS .'!loll:QW£A QTMER STATUS OtSC:CVERV OISC:OVERV OESC:l'IUrr10N rrma 1

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1_gJ 45 I NRC Inspec.tor 80 I

ll'OAMOF .

ACTIVIT'I' C:ONT'ENT IUU..~£0 OF RU:A.5£ AMOUNT OF ACTIVITY 1.0CATION OF A£1...£AS£ GEa 1

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  • -------------.-1soI PERSONNEL EXPOSURES

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7 . 8 9 11 12 13 J PERSONNEL INJUAIES' l'tUM8CA 0SC:Rlll'TIQN.

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. . OFFSITE CONSEQUENCU *,._

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LOSS OA OAMACiE TO FACILITY Jtleit;.J TYtlC CSC:.IUPT10N 1~____........_.____,_.--""µ~/~A=--.....__--..._.__.__.__.______________________-r..1 10 J l'U8\.IC1TY *

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7.19 80 AOOITIONAL FACTORS

(!]!]!EVENT DESCRIPTION (Continued on page_ 2) I 7 8 § . eo

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NAME: _ _ _ _ _ _ _ B_ *._E;...._c_a_n_f__;;;;i;..;e;...l;;;.d.;.;...___ PMONe: (609) 365-7000 Ext.SaleI!l-525

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LER 76-17/JL . '

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EVENT DESCRIPTION (Continued)**

acceptance value should be < 32% versus < 65%. The Operations Department implemented Technical Specification Action Statement 3.6.1.3

  • This is the first occurrence of this type. (76-17/3L).
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