05000483/LER-1997-001, :on 970228,violation Occurred Re Misinterpretation of TS 3.9.6,refueling Machine Trip Limits. TS Interpretation 25 Has Been Deleted

:on 970228,violation Occurred Re Misinterpretation of TS 3.9.6,refueling Machine Trip Limits. TS Interpretation 25 Has Been Deleted

ML20137G657
Person / Time
Site:	Callaway
Issue date:	03/26/1997
From:	Affolter R, Bono H UNION ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-97-001, LER-97-1, ULNRC-03550, ULNRC-3550, NUDOCS 9704010458
Download: ML20137G657 (5)

LER-1997-001, on 970228,violation Occurred Re Misinterpretation of TS 3.9.6,refueling Machine Trip Limits. TS Interpretation 25 Has Been Deleted

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)
4831997001R00 - NRC Website

text

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Calisway Plant Past Office Box 620 fUlIDn, f.fiSSOUn h5251 9

Union Etscrusc g

March 26,1997 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mai! Stop PI-137 Washington, DC 20555-0001 ULNRC-03550 Gentlemen:

DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 FACILITY OPERATING LICENSE NPF-30 LICENSEE EVENT REPORT 97-001-00 i

MISINTERPRETATION OF TECIINICAL SPECIFICATION 3.9.6, REFUELING MACIIINE TRIP I IMITS The enclosed licensee event report is submitted pursuant to 10CFR50.73(a) (2) (i) (B) as I

a condition prohibited by the plant's Technical Specifications.

R. D. Affolter j- }

Manager, Callaway

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l RDA/IIDB/JDN/rjp Enclosure q4' S

t 9704010458 970326 PDR ADOCK 05000483 S

PDR UM lllllfllllllllflkllf!ll

ULNRC-03550 e

March 26,1997 Page 2 cc: Mr. James E. Dyer Regional Administrator U.S. Nuclear Regulatory Commission RegioriIV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 l

1 Senior Resident Inspector i

Callaway Resident Ofrice U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Ms. Kristine M. Thomas (2 copies)

Licensing Project Manager, Callaway Plant

)

Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 13E16 Washington, DC 20555-2738 Manager, Electric Department Missouri Public Service Commission PO Box 360 Jefferson City, MO 65102 Mr. Thomas A. Baxter Shaw, Pittman, Potts, & Trowbridge 2300 N. Street N.W.

Washington, DC 20037 l

t

LICENSEE EVENT REPORT (LER)

F Aclu 1Y NAME (1)

DOCKET NUMBER (2)

PAGE (3)

Callaway Plant Unit 1 0 l5 l0 l0 l0 l4 l8 l3 l OF l 3 l 1

Misinterpretation of Technical Specification 3.9.6 Refueling Machine Trip Limits EVENT DATE (5)

LER NUMBER (6)

REPORT DATE (7)

OTHER F ACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR SEO IAL REV MONTH DAY YEAR FACILITY NAMES OC U B R(S 0l2 2l8 9

7 9l7 0l0l1 0l0 0l3 2l6 9l7 0l510l0l0l l l MO E (

THIS REPORT l$ SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR ; (Checa one or more of the Mowsng)(11) 20 402(D) 20 40Nc) 5013(a)(2)(w) 73 71(b)

POWER 20 405(sX1Xi) 50 36(c)(1) 50.73(aX2Xv) 73 71(c)

EEVEL (10) 0 l0 l0

~

20 405(a)(1)(n)

~

50 36(c)(2)

~

50 73(aX2 Xvii)

~

OTHER (Speerfjrin 20 405(aM1Xm) x 50 73(aX2)(1) 50 73(aX2XvidhA)

Abstreet below andin 20 405(a)(1yw) 50 73(a)(2)(d) 50 73(aX2XvmXia)

Text, NRC Form 366A) 20 405(a)(1Xv) 50 73(aX2Xm) 50 73(a)(2Xx)

L8CENSEE CONTACT FOR THIS LER (12)

NAME T E LEPHONt: NUMBER AsuCOue l

H. D. Bono, Supervising Engineer, Site Licensing 5

7 3

6 7

6 4 4 2

8 COMPLETE ONE LINE FOR EACH COMPONENT F AILURE DESCRIBED IN THIS REPORT (13)

CAUSE

SYSTEM COMPONENT UE TO NPR S

CAUSE

SYSTEM COMPONENT URfR ONPR S I

l l l l ll l

l l l III l

I I I I I I I I

I I

I i 1 l

SUPPLEMENTAL REPORT EXPECTED (14)

MUNTH DAY YEAR i

EXPECTED l

SUBMIS$10N YES fit yes compiete EXPECTED SUBMISSION DATE)

NO DATE (15) l l

l ABSTRACT flimit to 1400 spaces i e approwwnately fifteen sinale-space typewntten IrnesX16) l On 2/28/97 Union Electric discovered Technical Specification (T/S) Interpretation (TSI) 25 resulted in l

the violation of UE FSAR (F/S) Specification 16.9.2.1, REFUELING OPERATIONS-REFUELING MACilINE. F/S Specification 16.9.2.1 replaced T/S 3.9.6. T/S 3.9.6 was violated when TSI 25 was l

used in refuel one, Spring of 1986 through refuel seven, Spring of 1995.

F/S 16.9.2.1 requires the refuel machine primary automatic overload cutoff be set at less than or equal to 250 pounds above the indicated weight for wet conditions and the automatic load reduction trip setpoint be set less than or equal to 250 pounds below the suspended weight for wet conditions. TSI 25 allowed the automatic overload cutoff and load reduction trip weights to be set by the heaviest fuel assembly and l

lightest fuel assembly respectively. Differences in fuel assembly weights allowed the automatic overload cutoff 250 pound limit to be exceeded when lighter fuel assemblies than the one used to establish the setpoint were being moved and load reduction 250 pound trip limit to be exceeded when moving fuel assemblies heavier than the one used to establish the limit.

This violation was caused by the incorrect interpretation of T/S 3.9.6.

TSI 25 has been deleted. T/S Section 3.9.6 was relocated to the FSAR during December 1995. The FSAR is being revised to provide appropriate guidance for setting the automatic cutoff and automatic i

load reduction trip. Additional reviews of TSI's are being performed in conjunction with the ongoing T/S conversion process.

I

=

e LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION mun saut ti, oi.sxti nuusta v, tea u

<,o exoe <3, MMIER NO Callaway Plant Unit 1 olslololol4l8l3 9l7

- olol1 olo ol2 3l or TEXT (N more space is requred, use add 4mnal NRC Form 306Ns)(17)

DESCRIPTION OF EVENT

On 2/28/97, it was determined that Technical Specification Interpretation (TSI) 25 allowed Operators to violate UE FSAR specification 16.9.2.1 (formerlyn2) FSAR Technical Specification 3.9.6),

" REFUELING OPERATIONS - REFUELING MACHINE".<

machine primary automatic overload cutoff be set at less than or equal to 250 pounds above the indicated suspended weight for wet conditions. The automatic load reduction trip setpoint must be less than or equal to 250 pounds below the suspended weight for wet conditions. The TSI allowed the heaviest fuel assembly to be used to set the automatic overload cutofflimit and the lightest fuel assembly to be used to set the automatic load reduction trip. The indicated suspended weight consists of the refuel mast weight plus the fuel assembly and assembly insert weight. Due to the difference in fuel assembly and component weights, the automatic overload cutoff would be greater than 250 pounds above the indicated wet suspended weight when fuel assemblies lighter than the one used to establish the setpoint are being moved. The automatic load reduction trip would be greater than 250 pounds below the wet suspended weight of fuel assemblies heavier than the one used to establish the setpoint.

It was determined Technical Specifications were violated when the interpretation was used in refuel i

one, Spring of 1986 and in subsequent 18 month refueling outages through refuel seven in Spring of 1995.

BASIS FOR REPORTAllILITY:

This issue is reportable p r 10CFR50.73 (a) (2) (i) ( B) as a condition prohibited by Technical Specifications.

C_OEDITION AT TIME OF EVENT:

Mode 6, Refueling ROOT CAUSE:

The cause of this violation is the incorrect interpretation of T/S 3.9.6. At the time of the interpretation, Union Electric management believed the method for setting the refuel machine weight limits was appropriate. Discussions with Westinghouse were held to ensure technical merit. Westinghouse concurred.

i

. O LICENSEE EVENT REPORT (LER) 4 TEXT CONTINUATION t

f ACILi[Y NAME (1)

DOLKE T NUMBER (2) tf R NUMBER (6>

PAGE (3)

R NO

]

Callaway Plant Unit i 0lsl0lOl0l4l8l3 9l7

- 0l0l1 0l0 0l3 3l OF

- 5 TEXT (N more space is requred, use adddurial NRC Form 366A's)(17)

CORRECTIVE ACTIONS

Technical Specification Interpretation #25 has been deleted. Technical Specification section 3.9.6.

was moved to the FSAR during December,1995. The FSAR is being revised to provide appropriate guidance for setting the automatic overload cutoff and automatic load reduction trip. Additional reviews of TSI's are being performed in conjunction with the Technical Specification conversion process.

I

- SAFETY SIGNIFICANCE:

At the time of the original interpretation, discussions with Westinghouse were held to ensure technical merit. Westinghouse concurred with the interpretation. During refuels one through eight the use of the automatic overload cutoff trip value or the automatic load reduction trip as specified by TSI 25 did not result in damage to fuel clad or the release of fission products to the environment.

This condition therefore did not pose a threat to public health or safety.

4 J

PREVIOUS OCCURRENCES

None FOOTNOTES:

The system and component codes listed below are from IEEE Standards 805-1984 and 803A-1983 respectively:

1. System-DF, nuclear fuel transfer system

2. Component-FllM, fuel handling machine.

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