05000255/LER-1979-028-03, /03L-0 on 790623:conductivity & Sodium Concentration in Steam Generator a Exceeded Tech Spec Limits.Caused by Combination of Condenser Tube in Leakage & Chemical Hideout Return as Result of Power Reduction

/03L-0 on 790623:conductivity & Sodium Concentration in Steam Generator a Exceeded Tech Spec Limits.Caused by Combination of Condenser Tube in Leakage & Chemical Hideout Return as Result of Power Reduction

ML18043A857
Person / Time
Site:	Palisades
Issue date:	07/24/1979
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML18043A856	List: 05000255/LER-1979-028, Forwards LER 79-028/03L-0 05000255/LER-1979-028-03, /03L-0 on 790623:conductivity & Sodium Concentration in Steam Generator a Exceeded Tech Spec Limits.Caused by Combination of Condenser Tube in Leakage & Chemical Hideout Return as Result of Power Reduction
References
LER-79-028-03L, LER-79-28-3L, NUDOCS 7907300398
Download: ML18043A857 (2)

LER-1979-028, /03L-0 on 790623:conductivity & Sodium Concentration in Steam Generator a Exceeded Tech Spec Limits.Caused by Combination of Condenser Tube in Leakage & Chemical Hideout Return as Result of Power Reduction

Event date:
Report date:
2551979028R03 - NRC Website

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P.ALIS.fl.DES NRC FOrlM 366 (7*77)

U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: !-j _.....__.__...._...._~~I 8 1

6 (PLEASE PRiNT OR TYPE ALL REQUIRED INFORMATION)

~

I Ml r I PI Al LI 1101 o I o Io I o lo I o I o Io I o I ol o 10! 4 I 1 I l I 1 I 110! I 10 7

8 9

LICENSEE CODE 14

,5 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT SS CON'T C£::DJ 7

8

~~~~~; L!:J© I o I 51 o I o I o I 2 15 I 5 101 o I 6 I 21 3 I 7 I 9 I© Io I 7 I 21 4 I 71 9 I G) 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

[EJ2J I Dliring load reduction in preparation for repairs of main condenser tuoe

~

I leaks, the conductivity and sodium concentration in the A steam generator

~

I increased to 25.6 micro-mho/cm and 1.58 ppm.

(B S/G: 22.9 micro-mho/cm

~I and 1.01 ppm).

These valves exceeded the limits of TS 3.18.1. Chemistry

(())] 1was returned to within specifications within the time limits of TS 3.18.~

ITJ:2J I and 3.18. 5.

No threat to public health or safety existed.

Occurrence*

[IT[] similar to LER 79- 02 7 7

8 9 IT:ITl 7

8 SYSTEM CODE I RIB I@

9 10

(.:;"\\

LERiRO CVENT YEAR

~

REPORT I 7 19 I NUMBER 21 22

CAUSE

CAUSE COMP:

CODE SU BC ODE COMPONENT CODE SUBCODE

~@ @J@ IH ITI EIX ICI HI@ L!J@)

11 12 13 18 19 SEQUENTIAL OCCUR REN CE REPORT REPORT NO

• CODE TYPE VALVE SUBCODE

~@

20 I I 1° 12 1 81

~ Io I 31

~ l.=l 23 24 26 2 7 28 29 30 31 ACTION FUTURE EFFECT SHUTDOWN C::::-.

ATTACHMENT NPRD-4

• PRIME COMP.

REVISION NO,

~

32 COMPONENT MANUFACTURER 80 TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM ~UB.

SUPPLIER LLl@lzJ@ Lzl@ LzJ Io I olo I nl W@ W§ W@

33 34 35 36 37 40 41 42 43 le l!.t I 9lo I CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

44 47

!The out of spec condition resulted from a combination of condenser tube l in leakage and chemical hideout return as a result of the power [ill].

ITIIJ 1reduction.

The condition was corrected through S/G blowdowns and

!plugging of leaking main condenser tubes.

[QI].

[ill]

7 8

9 OTHER STATUS @

80 FACILITY METHOD OF DISCOVERY DESCRIPTION @

STATUS

%POWER DISCOVERY filD L!J@ 1° I 71 51@1 NA l!_l@I Chemistry Sample 8

9 10 12 13 44 45 46 80 ACTIVITY CONTENT AMOUNT OFN'.ATIVITY@

LOCATION OF RELEASE@

RELiz-seo OF R~LEASE QJIJ ~@~@I NA 7

8 9

10 11 44 45 60 02]

PERSONNEL EXPOSURES NUMBEP.

@TYPE DESCRIPTION 39 I 0 I 0 I 0 I 37 ~@)

NA a 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION 41

~

I 01 010 I@

NA 8

9 11 12 80 LOSS O* OR DAMAGE TO FACILITY@

TYPE

DESCRIPTION

Em ~@

NA 7

a 9 10 GO PUBLICITY NRC USE ONLY ISSUED@ DESCRIPTION 45 ITTIJ lJ:!J 44 I I I I I II I I I I I I 8

9 10 68 69 80

consumers Power company General Offices: 212 West Michigan Avenue,.Jackson, Michigan 49201

• Area Code 517 788-0550 July 24, 1979 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen EllYn, IL 60137 DOCKET 50-255 - LICENSE pP*R PALISADES PLANT - LICENSEE EVENT REPORT 79-028 On the reverse side is Licensee Event Report 79-028 which is reportable under Technical Specification 6.9.2.b.(2).

David P Hoffman (Signed)

David P Hoffman Assistant Nuclear Licensing Administrator CC:

Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement