05000315/LER-1999-006, :on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold

:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold

ML17325B558
Person / Time
Site:	Cook
Issue date:	04/16/1999
From:	Orourke B INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17325B557	List: 05000315/LER-1999-006, :on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
References
LER-99-006, LER-99-6, NUDOCS 9904290046
Download: ML17325B558 (1)

LER-1999-006, on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
3151999006R00 - NRC Website

text

r(RC Form 366 U.S. NUCLEAR REGULATORY COMMISSION (6-1998)

LICENSEE EVENT REPORT (LER)

(See reverse for required number of digits/characters for each block)

APPROVED BY OMB No: 3150.0104 EXPIRES 06)30/2001 ESTSIIATED BURDEN PER

RESPONSE

TO CONIPLY WITH THIS MANDATORY INFORMATIONCOLLECTION REOVFST: 50 0 HRS. REPORTED LESSONS LEARNED ARE VICORPORATED INTO THE LICENSSIG PROCESS ANO FED BACK TO INDVSTRY.

FORWARD COMMENTS RECARDING BVRDEN ESTSIATE TO THE INFORMATIONAND RECORDS MANAGEMENT BRANCH (f4 Fss)

VS NVCLEAR F 'GVIATORY COMMISSON. WASHINGTON. DC 205554001. AND TO THE PAPERWORK REDUCTION PROJECT

($150410I). OFFICE OF MANAGEMENT AND BVOGET, WASIeNGTON. DC 2050$

FACILITYNAME(5)

Cook Nuclear Plant Unit 1 DOCKET NUMBER(2) 05000-315 PAGE ($)

1 of1 TITLE(4)

Fuel Crane Loads Lifted Over Spent Fuel Pool Could Impart Impact Energies Greater Than Technical Specification Limits EVENT DATE (5)

LER NUMBER (6)

REPORT DATE (7)

OTHER FACILITIES INVOLVED(8)

MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REVISION NUMBER MONTH DAY YEAR ACILI N

D.C. Cook, Unit 2 DOC NUMB R 05000-316 01 15 1999 1999

006 00 04 16 1999 ACILITYNAM DOCKET'UMB R OPERATING MODE (9)

POWER LEVEL(10) 00 20.2201 (b) 20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(v) 20.2203(a)(3)(i) 20.2203(a)(3)(ii) 5o.73(a)(2)(i) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(viii) 50.73(a)(2)(x) 73.71 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR (I: (Check one or more) (11) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(4) 50.36(c)(1) 50.36(c)(2)

LICENSEE CONTACT FOR THIS LER (12) 50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii)

OTHER Specrr)r in Absrract Below or nNRCForn)366A NAME Ms. Brenda W. O'ourke, Licensing Engineer TELEPHONE NUMBER(Inc)Jde Area Code)

(616) 465-5901, x2604 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE

SYSTEM COMPONENT MANUFACTURER REPORTABLE To EPIX

CAUSE

SYSTEM COMPONENT MANUFACTURER REPORTABLE TO EPIX SUPPLEMENTAL REPORT EXPECTED (14)

X YES (IfYes, complete EXPECTED SUBMISSION DATE)

NO EXPECTED SUBMISSION DATE (15)

MONTH 05 DAY 28 1999 Abstract (Limitto 1400 spaces, i.e., approximately 15 single-spaced typewritten tines) (16)

On January 15, 1999, Operations identified a discrepancy between the Unit 1/2 Technical Specification (TS) 3.9.7 impact energy limitand procedure 12 OHP 4030.STP.046, "New and Spent Fuel Crane Operability Verification and Functional Tests." A preliminary review completed on February 23, 1999, indicated that in the event the fuel crane dropped its load from the maximum height of 15 inches above the spent fuel racks, with a current maximum fuel assembly weight of 1465 pounds (Ibs) and a Rod Cluster Control Assembly weight of 165 Ibs, a calculated impact energy of 24,450 inch-pounds (in-Ibs) could be imparted to the top of the spent fuel pool racks. This resultant impact energy is greater than the TS limit of 24,240 in-lbs, which was based on previous fuel assembly weights and.previously installed Exxon spent fuel racks. The currently installed Holtec fuel racks can withstand a calculated impact energy of 55,800 in-lbs. Due to untimely evaluation of the identified condition, information necessary to determine whether this condition was reportable was delayed.

On February 23, 1999, in accordance with 10 CFR 50.73(a)(2)(i)(B), this condition was determined to be reportable for a condition prohibited by plant TS.

Preliminary investigation indicates that the cause was lack of design basis control for the Spent Fuel Pool system and attendant equipment, and its interface with Technical Specification requirements.

As immediate corrective action, 12 OHP 4030.STP.046 was placed on administrative hold, and a clearance was placed on the spent fuel crane to preclude fuel movement.

The root cause investigation for this event has not been completed.

Based on the results, information regarding the safety significance of this condition, including additional corrective and preventive actions, willbe provided in an update to this LER when the investigation is complete.

9904290046 9904i6 PDR ADQCK 050003i5