05000315/LER-1980-005-03, /03L-0:on 800321,discovered That Unit 1 Axial Power Distribution Monitoring Sys & P-250 Axial Power Distribution Monitoring Sys Limits Were Incorrect.Caused by Personnel Using Unit 2 Fq & K(Z) Limits in Computer Program

/03L-0:on 800321,discovered That Unit 1 Axial Power Distribution Monitoring Sys & P-250 Axial Power Distribution Monitoring Sys Limits Were Incorrect.Caused by Personnel Using Unit 2 Fq & K(Z) Limits in Computer Program

ML17326A672
Person / Time
Site:	Cook
Issue date:	04/18/1980
From:	Delong S INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17326A671	List: 05000315/LER-1980-005-03, /03L-0:on 800321,discovered That Unit 1 Axial Power Distribution Monitoring Sys & P-250 Axial Power Distribution Monitoring Sys Limits Were Incorrect.Caused by Personnel Using Unit 2 Fq & K(Z) Limits in Computer Program 05000315/LER-1980-006-03, /03L-0:on 800324,during Surveillance Test,Unit 1 650-ft Elevation Airlock Door Leakage of 130CFH Was Found.No Cause for Leak Found.Retest Performed W/Satisfactory Results ML17326A670
References
LER-80-005-03L-01, LER-80-5-3L-1, NUDOCS 8004230444
Download: ML17326A672 (2)

LER-1980-005, /03L-0:on 800321,discovered That Unit 1 Axial Power Distribution Monitoring Sys & P-250 Axial Power Distribution Monitoring Sys Limits Were Incorrect.Caused by Personnel Using Unit 2 Fq & K(Z) Limits in Computer Program

Event date:
Report date:
3151980005R03 - NRC Website

text

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION tCENSEE EVENT REPORT CONTROL BLOCK:

Qi

{PLEASE PRINT OR TYPE ALLREQUIRED INFORMATION)

I 6

N I 0CC IQ200000000000041111QE~QE 7

8 9

LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T RE o

~LQR 0

5 0

0 0

3 1

5 QT 0

3 2

1 8

0 Qs 0

4 I s

9 0 Q 7

8 SOURCE 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES +10 ON MARCH 21 i 1 980 2 IT WAS DISCOVERE6 THAT THE UNIT 1

APDMS AND P 250 APDMS

~O3

~O4 LIMITS INSTALLED SINCE THE PREVIOUS SURVEILLANCE, WERE INCORRECT.

THIS EVENT WAS NON-CONSERVATIVE WITH RESPECT TO T.S. 3. 2. 6.

PREVIOUS EVENT OF A SIMILAR NATURE WAS RO-315/79-043.

~OB

~OB 7

8 7

6 80 SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE Q11

~~Q72

~~Q13 I

N S

T R

U Qw

~XQEE

~Z Qs 9

10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION EVENT VEAR REPORT NO.

CODE TYPE NO.

Q17 REPORT

~~"

U ~

L~l LU~

LiJ 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDQ PRIME COMP.

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.

SUPPLIER MANUFACTURER L~II&8019

~Q29 &6 0

0 0

0 I

Q23

~~Q24

~NQ25 Il 1

2 0

Qss 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 THE CAUSE OF THIS EVENT NAS OUE TO NUCLEAR SECTION PERSONNEL USING THE UNIT 2 F

AND K(z) LIMITS IN THE COMPUTER

PROGRAM, WHICH CALCULATES THE APDMS AND P250 APDMS SETPOINTS, INSTEAD OF THE UNIT 1 LIMITS.

THE INCORRECT LIMITS WERE 3

4 INSTALLED FOR A TOTAL OF 28

DAYS, FROM 2-22-80 TO 3-21-80.

THE APDMS AND P250 SCANS FOR THIS TIME PERIOD HAVE BEEN REVIEWED (SEE ATTACHED SUPPLEMENT) 7 8

9 FACILITY STATUS 55POWER OTHER STATUS Qso E

1 0

0 NA 44 METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32

~QER ~Q29

~BQsi SURVEILLANCE TEST 7

8 9

10 12 13 44 45 46 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITYQ LOCATIONOF RELEASE Q36 6

~Z Qss

~ZQ34 NA NA 7

8 9

10 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 0 Q37 2 Q39 NA 7

8 9

11 12 13 PERSONNEL INJURIES

~

~0 "V'"O Q'"'"'""""

80 80 80 80 7

8 7

8 O

,7 8

9 11 12 LOSS OF OR DAMAGETO FACILITYQ43 9

10 PUBLICITY ISSUED DESCRIPTION~

Me 9

10 NAME OF PREPARER S.

D.

DeLong PHONE:

80 80 NRC USE ONLY PE Es 80 ER 0

68 69 616-465-5901 goo $ 2.3o $V.g

ATTACHMENT TO LER >so-oos/o3r,-o SUPPLEMENT TO CAUSE DESCRIPTION AND THERE WAS SUFFICIENT MARGIN SO THAT THERE WOULD HAVE BEEN NO F

IOLATIONS WITH THE PROPER LIMITS INSTALLED.

WHEN THE ERROR WAS FOUND THE CORRECT VALUES WERE INSTALLED IN BOTH THE APDMS AND P250 COMPUTER.

TO PREVENT THIS FROM REOCCURRING THE NUCLEAR SECTION PERSONNEL RECEIVED ADDITIONAL TRAINING COVERING THE USE OF PROPER LIMITS.

A CHANGE TO THE CORE POWER DISTRIBUTION LIMITS SURVEILLANCE PROCEDURE (UNITS 1

AND 2)

WAS ALSO '.INITI'ATED.

THIS CHANGE WILL REQUIRE BOTH THE ENGINEER PER-FORMING THE PROCEDURE AND THE ENGINEER REVIEWING THE PROCEDURE TO CHECK AND SIGN THAT THE CORRECT INPUT DATA WAS USED IN THE COMPUTER PROGRAM WHICH DERIVES THESE LIMITS.