05000316/LER-2076-020, Opening of Reactor Coolant System

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Opening of Reactor Coolant System
ML18219C356
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 05/24/1976
From: Jurgensen R
American Electric Power Service Corp, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To: James Keppler
NRC/IE, NRC/RGN-III
References
LER-1976-020-00
Download: ML18219C356 (5)


LER-2076-020, Opening of Reactor Coolant System
Event date:
Report date:
3162076020R00 - NRC Website

text

NRC FDAM 195 lU.S. NUCLCAAAFGULATOAY MISSION I2.'IS I P NRC DISTRIBUTION FDA PART 50 DOCKET MATERIAL DOCKCT NUMBEA 50-315 FILF. NUMGEA XNCXDENT REPORT To: J.G.

Keppler FRoM: Indiana 8 Michigan Power Co.

Bridgman, Michigan R.W. Jurgensen DATC OF DOCUMFNT 5-24-76 DATE AECEIVED 5-27-76 QLETTEA 5 0 A IG INAL 0 COPY 0 NOTOAIZE D

@UNCLASSIFIED DESCAIPTION Ltr. trans the following.......

P AOP INPUT FOAM NUMDEA OF COPIES AECEIVED 30 ENCLOSUAE Licensee Event Rpt.

(R.O. 0'6-20) on 5-1-76 Concerning the diesel generator supplying the emergency bus associated with the east charging pump was tagged out for maintence.....

PLANT NAW.:

Cook g 1

(30 Carbon Cys.

Received)

DO NOT REMOVE ACKNOWLEDGED NOTE:

XF PERSONNEL EXPOSURE XS INVOLVED SEND DXRECTLY TO KREGER/J ~ COLLINS SAFETY BRANCH CHIEF:

W 3 CYS FOR ACTION Kniel FOR ACTION/INFORMATION ENVIRO LXC ~ ASST:

V/

CYS ACRS CYS Service ENT TO LA Fv NRC PDR I &E 2

INTERNALD ISTR I BUTION SCHROEDER/IPPOLITO

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NOVAK CHECK V

RES Wm Er MH TEDESCO MACCA ELLE BAER SHAO VOLL>li:R/BUNCii KREGEIIJ

(~OLL~NS LPDR:

TXC NSXC EXTERN'AL DISTR IBUTION CONTROL NUMBER 5314 1i. P) 7

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INDIANAG MICHIGANPDIIIIEB GDMPAII!Y DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 0/

DQcxgrfa May 24, 1976 Mr. J.

G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, I.L 60137 5l87gy 3

~+> ATION AAg CINE Operating License DPR-58 Docket No. 50-315

Dear Mr. Keppler:

Pursuant to the requirements of Appendix A Technical Specifications and the United States Nuclear Regulatory Commission Regulatory Guide 1. 16, Revision 4, Section 2.b, the following report is submitted:

RO 50-315/76-20 rA Sine ly,

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Plant nag cc:

R.

S. Hunter J.

E.

Dolan G.

E. Lien R. Kilburn R. J. Vollen BPI R.

C. Callen MPSC K.

R. Baker RO: III P.

W. Steketee, Esq.

R. Walsh, Esq.

G. Charnoff, Esq.

G. Olson J.

M. Hennigan PNSRC R.

S. Keith Dir., IE (30 copies)

Dir., MIPC (3 copies) p

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89 CONTROL BLOCK:

LICENSEE NAME I

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14 15 LICENSE NUMBER 0 0 0

0 0

0 0

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LICENSE EVENT TYPE 25 26 30 31 32

'lCENSEE EVENT REPORT f

EASE PRINT. AU.,REOUIRED INFORMATION) 6 REPORT REPORT 7

8 57 58 59 60 EVENT OESCRIPTION [oa~]

r was in Col 7

8 9 OOCKET NIIMDEII EVENT OATE REPORT OATE p

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5 2

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6 61 68 69 74 75 80 d Shutdown condition, Node 5, with a shutdown margin of 14.4Ã

,80

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and the reactor coolant system opened.

Technical 7

8 9 [oO~3 80 be o erable.and ca able of being powered from an operable emergency bus 7 89 [oom st char in um was designated as the operable charging (Cont'd on attached she6

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7 8 9 SYSTEM

CAUSE

COOE COOE COMPONENT CODE fp~

A Z

Z Z

Z Z

7 8 9 10 11 12.

CAUSE OESCRIPTION tool The ermi ss (RO 50-315/76-20)

VIOLATION N

48 PRME COMPONENT SUPPLIER 80 COMPONENT MANUFACTURER Z

Z ZZZZ 17 43 44 47 diesel generator had been given due to the fact that son to ta out the 80 w re such that removin the diesel generator associated with the 7

89 Qoj9 7

8 9 Q~ 0

'east centrifu al char in pump from service and complying with-(Con't on attached sheeP 89

~

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~ 0 80 [004]

S ecification 3.1.2.3 requi res that at least one charging pump in the boron injection OTHER STATUS NA 7

8 9 LOSS OR OAMAGE TO FACILITY 7

'8 9 10 PUBLICITY NA 7

89 7

89 FACILITY STATUS 5 POWER Q~g LsJ Loaoog

- 7 8

9 10

'2 13 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY

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~z NA

.7 8' 10 11 PERSONNEL EXPOSURES NUMBER-TYPE OESCRIPTION

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NA 7 89'1 12 13 PEAS'ONNEL INJURIES K4I ~LOJ 7

89 11 12 PROBABEE CONSEQUENCES

'l None METHOO OF OISCOVERY B

44 45 46 44 45 DISCOVERY DESCRIPTION LOCATtON OF RELEASE 80 80 80 80 80 80 80

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80 7

89 AOOITIONAL FACTORS K'1 L13~xen.

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8 9 matter has been discussed with the operators involved to prevent a reoccurrence.

~19 NAME:

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EVENT DESCRIPTION

Con' pump with the west pump tagged out for maintenance.

When performing operability tests on the east charging

~ -that the die sel generator supplying the emergency bus charging pump had been tagged out for maintenance thus for the operable charging pump.to be capable of being emergency bus.

(RO 5O-~1517~-2o).

pump it was discovered associated with the east violating the requirement powered from an operable CAUSE DESCRIPTION Con' the Action Statement of Technical Specification 3.1.2.3 did not place the reactor in a less safe condition.

The action statement requires that operations involving core alterations or positive reactivity changes be suspended until one charging pump is restored to operable status.

Since neither of these operations were planned permission to take the diesel generator out of service was granted.