ML18082A647

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Supplemental LER 78-070/01X-1:on 781021,during Mode 4 Operation,While Heating Up to Enter Mode 3,high Flow Through RCP Seals & Other Alarms Indicating RCS Leakage Were Observed.Cause Undetermined.Instructions Have Been Revised
ML18082A647
Person / Time
Site: Salem PSEG icon.png
Issue date: 06/23/1980
From: KAPPLE A W
Public Service Enterprise Group
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18082A646 List:
References
LER-78-070-01X, LER-78-70-1X, NUDOCS 8006300465
Download: ML18082A647 (1)


Text

NRC FORM 366 UPDATE REPORT -LAST REPORT DATED 11/2/78 U.S. NUCLEAR REGULATORY COMMISSION e LICENSEE EVENT REPORT BLOCK: I I ' I 18 1 6 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 7 8 IN] JI s I G Is 11 l@I 01 0 1-I 0 I 01 0 I 0 I 0 1-I 0 I 0 1014 11 11 11 11 101 9 ,LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE :30 57 I 10 CAT 58 CON'T 7 8 W©I o I 5 Io Io Io 12 17 12 101 ll 012 I 1 I 1 I a l©ln.....1 6 '2 I 1 ls Io 10 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 ITTIJ EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

I During Mode 4 operation, while heating up to enter Mode 3, the control room IIill operator observed high flow through No. 13 RCP seals and other alarms indicating

[QJI] RCS leakage. The plant was cooled down and depressurized to Mode 5. All 3 RCP [ill] seals had failed, causing approximately 15,000 gallons of primary water leakage to []li] the containment sump. This is the first occurrence of this type. ITTIJ [£JIJ 7 8 9 [ill]. 7 8 SYSTEM CAUSE CAUSE CODE CODE SU8COOE COMPONENT COOE le IBI@ L!J@ L!J@ I x I xi x I x I XI xi@ 9 10 . 11 12 13 18 SEQUENTIAL OCCURRENCE

@ LER/RO LVENTYEl>.R REPORT NO. CODE REPORT 17 1 a I l=.J 10 17 10 I 1.....-1 I 0 I 1 I NUM8ER 21 22 23 24 26 27 28 29 COMP. SUBCODE l.2.J 19 REPORT TYPE 30 VALVE SUBCODE w@ 20 L=l 31 REVISION NO. l2J 32 TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM $US. SUPPL! ER MANUFACTURER 80 ACTION FUTURE EFFECT SHUTDOWN @ ATTACHMENT NPRD-4 PRIME COMP. COMPONENT 1° 1° 1° I* I l.:.J@ L::.I@ I w1 1 1 2 1°1@ 33 34 35 36 3 7 40 41 42 43 44 4 7 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ [J]::£J I Investigation by Public Service has not conclusively determined the cause of this occurrence.

The instruction for RCP operation has been revised to require a 200 psig minimum differential pressure across the No. 1 seal during RCP operation.

A o::IIJ I check valve has been installed in each RCP No. 1 seal leakoff line to prevent []JI] I backflow from the Volume Control Tank. 7 8 9 80 FACILITY f:iO\ STATUS % POWER OTHER STATUS METHOD OF A ITill L£.J@ 01 o I ol@)._I __ N __ /_A __ __. DISCOVERY DISCOVERY DESCRIPTION (31

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__ O_b_s __ e_r_v_a_t_i_o_n

________________

__. 8 9 10 12 11 ACTIVITY CONTENT Q\ RELEASED OF RELEASE AMOUNT OF ACTIVITY N/A 7 8 9 10 11 PERSONNEL EXPOSURES

(;;:;\ 44 45 46 44 45 LOCATION OF RELEASE @ N/A 80 80 NUMBER

[Q2J I 0 I 0 I

___ N_7A _____________________

__.. 7 8 9 11 12 13 80 PERSONNEL INJURIES f,;".;\ NUMBER DESCRIPTION6 I 0 I 0 I 0 l@.___ _____ N...:..../_A

_____________________

__. 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY f43\ TYPE DESCRIPTION i.::::J C:J2J w@ . N/A 8 9 10 PUBLICITY Q\ NRC USE ONLY ISSUEDQ

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__. I I I I I I I I I I I 8 9 10 68 69 A. W. Kapple NAMEOFPREPARER-----.------------------------------

/f( r 8006800 PHONE:

Salem Ext. 628 80 80 "' I 80 ;;; 0 a. (!)