ML18096A921

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LER 92-012-00:on 920724,discovered That semi-annual Surveillance of Rtb 2A Position Exceeded on 920615.Caused by Personnel Error.Surveillance Successfully Completed on 920731 & Event Reviewed W/Maint Dept mgt.W/920824 Ltr
ML18096A921
Person / Time
Site: Salem PSEG icon.png
Issue date: 08/24/1992
From: Pollack M, Vondra C
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-92-012-01, LER-92-12-1, NUDOCS 9209010068
Download: ML18096A921 (5)


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PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station Augus.t 24, 1992 U. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT NO. 2 LICENSEE EVENT REPORT 92-012-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR

50. 73 (a) (2) (i) (B) .. This report is required to be issued within thirty (30) days of event discovery.

Sincerely yours,

c. A. Vondra Gen~ral Manager -

Salem Operations MJP:pc

  • Distribution re::i..2 I/ /

9209010068 920824. 95-2189i10~*1 12-89 .

PDR ADOCK 05000311

I NRC FORM,'366 U.S. NUCLEAR REGULATORY COMMISSION (6-89) APPROVEO OMB NO. 3150*0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICEN.SEE EVENT REPORT (LERI COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555. AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104). OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) * ,DOCKET NUMBER (2) I PAGE (31 Salem Generating Station - Unit 2 O I5 I o IO I o I 3 I 1 I 1 1 OF oI 4 TITLE (4)

Missed Tech Spec semiannual surveillance of 2A Reactor Trip Breaker due to personnel error EVENT DATE (5) LEA NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR  ::::::::::: SEQUENTIAL :::::::::: REVISION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI

            • NUMBER  :::::::::: NUMBER 9 2 91 2 - ol 1 l2 - o I o o :*s OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE R~OUIREMENTS OF* 10 CFR §: {Ch*ck one or more of the fol/owing) (11)

MODE (9) 1 t-----.------1-=.+..--l POWER I 20.402(b) 20.405(*)(1 )(i) 20.405(c)

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.....__ OTHER {SfJ'lcify in Abstr*ct b8/ow and in T~xt. NRC Form x

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50.73(o)(2Jlil 50.73(o)(:i)(viiillAI 366A)

&0.73(*112lliil 50.73(ol(2)(viiillBI 50.73(*112lliiil 50.73(*112ll*I LICENSEE CONTACT FOR THIS LEA (121 NAME TELEPHONE NUMBER AREA CODE M.J. Pollack - LER Coordinator e:: In la -:i 1-:i I q I -12 I Ol 2 12 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 MANUFAC* MANUFAC* REPORT AB LE '": :::::;.: *:*:*:-:*:*: :*:**:*:*:*:

CAUSE SYSTEM COMPONENT CAUSE SYSTEM COMPONENT *TO NP RDS ,;*:* :;::::-:  ::::::::  :*:-:

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DAY YEAR SUPPLEMENTAL REPORT EXPECTED (141 I YES (If yes. comp/ere EXPECTED SUBMISSION D,O.TEJ ABSTRACT (Limit to 1400 spaces, i.a., approximately fifteen single-space typ~written lines) (16) rn NO EXPECTED SUBMISSION DATE 1151 I I I On July 24, 1992, during normal power operation, it was discovered that the semi-annual surveillance of 2A Reactor Trip Breaker (RTB) serial number {S/N) 02YN219-3, in the 2A RTB position, had been exceeded. The surveillance was last ~ucc~ssfully completed on November 1, 1991, and was required to be performed by June 15, 1992. The root cause of this

  • event is personnel error due to inattention to detail. A Maintenance bepartment Planner did not update the surveillance schedule for the 2A RTB position (in January 1992) in accordance with Station Maintenance Procedure, SC.MD-AP.ZZ-0202, "Work Package Closeout Process" resulting in the semiannual surveillance being missed and a semiannual surveillance being completed twice, on a different breaker, during this period. On July 31, 1992, the semiannual surveillance was successfully completed for breaker S/N 02YN219-3. The breaker would hav*e functioned per design had it been required to do so since its last surveillance (November 1, 1992). Therefore, the health arid safety of the public was not affected by this event. This event has been reviewed by Maintenance Department management. Appropriate corrective disciplinary action with the individual(s) involved in this event has been completed. The circumstances surrounding this event will be reviewed with applicable Maintenance Department personnel. The RTB and RTBB surveillance work orders will be revised to require stoppage of the surveillance work activity should the breaker S/N on the work order not match the breaker S/N in the RTB/RTBB enclosure.

NRC Form 366 (6-89)

  • LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 92-012-00 2 of 4 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse - Pressurized Waier Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx}

IDENTIFICATION OF OCCURRENCE:

Missed Techriical Specification semiannual surveillance of 2A Reacto~

Trip Breaker (RTB) due to personnel error Discovery Date: 7/44/92 Event bate: 6/15/92 Report Date: 8/24/92 This report was initiated by Incident Report No.92-453.

  • CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 Reactor Power 90% - Unit Load 960 MWe DESCRIPTION OF OCCURRENCE:

On July 24, 1992, during normal power operation, it was discovered that the semi-annual surveillance of 2A Reactor Trip Breaker (RTB) serial number (S/N) 02YN219-3,* in the 2A RTB position, had been exceeded. The surveillance was last successfully completed on November .1, 1_991, and was required to be performed by June 15, 1992.

Technical Specification 3.3.l Table 4.3-1 semiannual RTB surveillance requirements 12 and 13 state: *

"(12) - Perform periodic maintenance on Reactor Trip Breakers and Reactor Trip Bypass Breakers semiannually as follows:

a. response time testing, (3 times) (visicorder) trend data
b. trip bar lift force measurements
c. u.v. output force measurement
d. dropout voltage check
e. servicing/lubrication/adjustments (see Table 3.1-1 Notation ###)
f. repeat testing steps (a-d) following any necessary actions at step (a)

(13) - Verify operation of Bypass Breakers Shunt Trip function from. local pushbutton while breaker is in the test position prior to placing breaker in service."

LICENSEE EVENT REPORT (-LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER .NUMBER PAGE Unit 2 5000311 *92-012-00 3 of 4 APPARENT CAUSE OF OCCURRENCE:

The root cause of this event is personnel error due to inattention to detail. A Maintenance Department Planner did not update the surveillance schedule for the 2A RTB position in accordance with Station Maintenance Procedure, SC.MD-AP. ZZ-0202, "Work Package *,

Closeout Process" resulting in the semiannual surveillance being missed.

  • surveillance work orders for RTBs are issued against the RTB position, not the S/N of the }:)reaker in that position. *The normal process upon completion of a RTB surveillance_ requires the wo~k order iibrary copy to be updated in accordance with station Mainte~ance Procedure, SC.MD-AP. ZZ-0202. This update. includes date of
  • surveillance completion an(i change of S/N in that RTB position .(if applicable). A new work order can then be generated from the library copy with the "correct information". In this*event, the library copy had not been appropriately updated.

On November 1, 1991, the semiannual surveillance of the RTB in the 2A Reactor Trip Bypass Breaker (RTBB) position was completed. The surveillance work order S/N update line was correctly completed (by the Maintenance Department electrician) to identify that the spare breaker S/N 02YN219-3 was installed in the 2A RTBB position replacing breaker S/N 02YN219-2, which had been removed for refurbishment. A Maintenance Department planner updated the library copy with the correct breaker S/N {02YN219-3) in accordance with Station Maintenance Procedure, SC.MD-AP.ZZ-0202.

on November 22, 1991, the semiannual surveillance of :breaker S/N 324Y7268-B in the 2A RTB position was started. Because of the need for corrective maintenance (CM) on breaker S/N 324Y7268-B, a. CM work order was issued which moved breaker S/N 02YN219-3 from.the 2A RTBB position to the 2A RTB position. The semiannual surveillance of breaker S/N 324Y7268-B was completed January 24, 1992 and the breaker was placed in the 2A RTBB position. Since the breakers were changed, the breaker S/N on the 2A RTB semiannual surveillance work order required updating; therefore, the S/N update line (on the work order) was correctly completed identifying breaker S/N 02YN219-3~ Contrary to the procedure requirements, a Maintenance Department planner did not update the 2A RTB breaker S/N on the semiannual surveillance library copy. This led to the failure to reschedule the next semiannual surveillance date to May 1, 1992 for the 2A RTB position with breaker S/N 02YN219-3 in place (semiannual surveillance of breaker S/N 02YN219-3 was last completed November 1, 1991 as discussed above) .

Maintenance/planning personnel conducted a review of RTB/RTBB surveillances (both Salem units) completed between October 8, 1990, to November 1, 1991. A similar event to this one was not identified.

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER. PAGE Unit 2 5000311 '92-012-00 4 of 4 ANALYSIS OF OCCURRENCE:

There are two (2) reactor trip breakers ("A" and "B"). They are in series which connect the output of the rod drive motor generator sets to the,-rod control power cabinets. In the event of a reactor trip signal, these breakers open, removing power from the control rod drive mechanisms allowing the control rods to drop into the reactor core. The opening of either breaker will cause this to occur. Two (2) RTBBs are provided to allow surveillance testing at power. To ensure proper functioning of the breakers, surveillances are performed as prescribed in the Technical Specifications. These surveillance tests include preventive maintenance. In this event, the required semiannual surveillance was not completed, within the required time This event is reportable to the Nuclear Regulatory Commission per Code of Federal Regulations 10CFR 50.73(a) (2) (i) (B).

The RTB surveillances (on July 14, 1992) required prior to startup by Technical Specification Table 4.3-1 Item 21 were satisfactorily completed. Also; on July 31, 1992, the semiannual surveillance was successfully completed for breaker S/N 02YN219-3. *The as found data*

was satisfactory; therefore, the.breaker would have functioned per design had it been required to do so since its last semiannual *

~urveillance. Therefore, the health and safety of the public was not affected by this event.

CORRECTIVE ACTION:

On July 31, 1992, the semiannual surveillance was successfully completed for breaker S/N 02YN219~3.

This event has been.reviewed by Maintenance Department management.

Appropriate corrective disciplinary action with the individual(s)

, involved in this event has been completed.

The circumstances surrounding this event will be reviewed with applicable Maintenance Department personnel. Attention to detail and procedure compliance, with particular emphasis on Station Maintenance Procedure, SC.MD-AP.ZZ-0202, Work Package Closeout Process will be stressed.

  • The RTB and RTBB surveillance work orders will be revised. to require stoppage of the surveillance work activity should the l;>reaker S/N on the work order not match the breaker S/N in the RTB/RTBB.enclosure.

~eSalem Operations bwl:pc SORC Mtg.92-092