05000315/LER-1999-005, :on 940512,determined That RT Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed

:on 940512,determined That RT Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed

ML17325B474
Person / Time
Site:	Cook
Issue date:	03/18/1999
From:	Pogue B INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17325B473	List: 05000315/LER-1999-005, :on 940512,determined That RT Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
References
LER-99-005, LER-99-5, NUDOCS 9903250371
Download: ML17325B474 (2)

LER-1999-005, on 940512,determined That RT Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2) 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
3151999005R00 - NRC Website

text

NRC Form 366 U.S. NUCLEAR REGULATORYCOMMISSION (6-1998)

.LICENSEE EVENT REPORT (LER)

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

APPROVED BV OMB No. 31504)t04 EXPIRES 06130/200t KSTBLATKD BURDEN PER

RESPONSE

TO COMPLY WITH THIS MANDATORY INFORMATIONCOLLECTIONREGUEST: 50.0 HRS. RKPORTKD IESSONS LEARNEDARE WCORPORATED PITO THE LCENNSNG PROCESS ANO FED BACK TO INDUSTRY.

FORWARD COMMENTS REGARDBIG BURDEN ESTSLATE TO THE IIPORMATIONANO RECORDS IMNACEAIENT BRANCH IT4 FST),

U S.

NUCLEAR REGLRATORY COMMiSSION, WASIBNGTCN. OC 205554001, AIK5 TO THE PAPERWORK REDUCTION PROIKCT IM500104>, OFFICE OF MANAGEMENT AND BUDGET. WASHNGTON, OC 20500 FACILITYNAME(I)

TITLE(4)

Cook Nuclear Plant Unit 1 DOCKET NUMBER(2) 05000-315 PAGE (5) 1 of1 Reactor Trip B(eaker Manual Actuations During Rod Drop Testing Not Previously Reported MONTH DAY YEAR EVENT DATE (5)

YEAR LER NUMBER (6)

SEQUENTIAL NUMBER REVISION NUMBER REPORT DATE (7)

MONTH DAY YEAR A ILI NAM Cook Unit 2 NUMB 05000-316 OTHER FACILITIESINVOLVED(8) 05 1994 1999 005 00 03 18 1999 A ILITYHAM D

NUM OPERATING, MODE (9)

POWER LEVEL(10) 00 THIS REPORT IS SUBMITTEDPURSUANT TO THE REQUIREMENTS OF 10 CFR li: (Check one or mo 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) 50.73(a)(2)(i) 50.73(a)(2)(ii) 50.73(a)(2)(ili) re) (11) 50.73(a)(2)(viii) 50.73(a)(2)(x) 73.71 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 Speoty BIAbelreol below or n NRC Form 366A Mr. Brent D. Pogue, Licensing TELEPHONE NUMBER (Inolude Aree Code)

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

CAUSE

SYSTEM COMPONENT MANUFACTURER REPORTABLE TO EPIX JS

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

'AY 12 1999 Abstract (Limitto 1400 spaces, i e., approximately 15 single-spaced typewritten lines) (16)

On February 11, 1999, during a review of Licensee Event Reports (LER) that had been submitted by other utilities for actuations of the Reactor Protection System (RPS) during rod drop surveillance testing, engineering personnel questioned the reportability of past D. C. Cook RPS actuations during rod drop surveillance testing.

In the course of performing rod drop testing, manual actuation of the reactor trip breaker had been utilized when unplanned problems have occurred during the surveillance.

Upon further review, on February 16, 1999, it was determined that there were cases identified in which the manual actuation of the reactor trip breakers was not proceduralized, and therefore not pre-planned.

In accordance with the reportability requirements under 10CFR50.72 (b)(2)(ii) and 10CFR50.73 (a)(2)(iv), these RPS actuations should have been reported, but were not. Based on this determination, an ENS notification was made on February 16, 1999, at 1808 hours0.0209 days <br />0.502 hours <br />0.00299 weeks <br />6.87944e-4 months <br /> in accordance with 10CFR50.72 {b){2)(ii).

Preliminary investigation indicates that the cause of this event is lack of training on NRC reportability requirements that led to surveillance procedure inadequacies.

Personnel involved in the surveillance did not question the reportability aspects of a manual actuation of the RPS.

Immediate corrective actions willinclude a discussion with engineering personnel on the requirements of 10CFR50.72 and 10CFR50.73 as it applies to pre-planned manual actuation of the reactor trip breakers.

Rod drop surveillance procedures willbe revised to allow the trip breakers to be opened whe'n unplanned problems occur during testing.

It has been determined that there is no safety signiTicance due to these manual actuations of the RPS or the delay in reporting the events.

When unplanned problems were encountered during the rod drop surveillance, opening of the reactor trip breakers was a conservative action and was not in response to adverse plant conditions.

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

Additional corrective actions, including preventive actions, may be developed based on the results of the root cause investigation.

Supplemental information willbe provided when completed.

9903250371 9903ia PDR ADOCK 050003l5 8

PDR