ML18153C703

LER 91-012-00:on 910720,discovered That Pressurizer Level Channel Not Declared Inoperable,Per Acceptance Criteria Due to Personnel Error.Personnel Involved Reinstructed in Review of Recorded Data & Supervision of trainees.W/910816 Ltr

ML18153C703
Person / Time
Site:	Surry
Issue date:	08/16/1991
From:	Kansler M VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
91-465, LER-91-012-01, LER-91-12-1, NUDOCS 9108220178
Download: ML18153C703 (5)

Text

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.. , Virginia Electric and Power Company Surry Power Station P. 0. Box315 Surry, Virginia 23883 August 16, 1991 U. S. Nuclear Regulatory Commission Serial No.: 91-465 Document Control Desk Docket No.: 50-280 Washington, D. C. 20555 License No.: DPR-32 Gentlemen:

Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report for Unit 1.

REPORT NUMBER 91-012-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by the Corporate Management Safety Review Committee.

Very truly yours, Enclosure cc: Regional Administrator Suite2900 101 Marietta Street, NW Atlanta, Georgia 30323

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• J NRC FORM366 (6-891 e U.S. NUCLEAR REGULATORY COMMISSION e APPROVED 0MB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-5301, U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-01041, OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME 111 DOCKET NUMBER (21 I PAuE 131 Surry Power Station, Unit 1 I0 I5 I O IO I O ,2 I 81 0 I 1 OF O 14 TITLE C41 Pressurizer Level Channel Not Placed in Trip Within Six Hours Due to Personnel Error EVENT DATE C&I LER NUMBER 161 REPORT DATE (71 OTHER FACILITIES INVOLVED CII MONTH DAY YEAR YEAR ]f SE~~~~~~AL () ~~"1~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(SI o17 21 o 9 1 9 11 - ol 1 12 - olo oIs I 1 6 9 I1 OPERATING THIii REPORT IS SUBMITTED PURSUANT TO THE Rt;QUIREMENTS OF 10 CFR §: (Ch,clr on* or motY of th* following) (111 MODE CII I

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20.40IIC1IC110111 II0.73C11121CII II0.73(111211vllllCAI 366AI 20.40IIC1111 lllvl 20.40IIC1111 IM - 'II0,73(111211111 II0.73(1112lCIIII LICENSEE CONTACT FOR THIS LER 1121 II0.7311lC2lCvllilCBI II0.731111211*1 NAME TELEPHONE NUMBER AREA CODE M. R. Kansler, Station Manager 8 10 I 4 3 I 5171- I 311 18 I 4 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC- MANUFAC-CAUSE SYSTEM COMPONENT TURER TURER I I I I I I I I I I I I I I I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED (141 MONTH DAY YEAR EXPECTED n YES (If v*1, compt*ro EXPECTED SUBMISSION DATE/ hi NO SUBMISSION DATE 1151 I I I On July 20. 1991 at 0635, with Unit 1 at 100% power, it was discovered that pressurizer level indicator 1-RC-LI-1461 had exceeded channel check acceptance criteria specified in a surveillance procedure for greater than six hours and had not been declared inoperable. Consequently, the channel was not placed in trip as required by Technical Specification 3.7 Table 3.7-1. Following this discovery, the channel was declared inoperable and placed in trip. An emergency work order was initiated which checked channel calibration and vented the transmitter to resolve the problem. No safety implications were posed by this event. This event occurred as the result of cognitive personnel errors in failing to recognize an out of specification condition, and failure to properly supervise a trainee. Personnel involved were reinstructed in the review of recorded data and the supervision of trainees. This occurrence was considered to be a violation of Technical Specification 3.7 and is being reported pursuant to 10CFR50.73(a)(2)(i)(B).

NRC Form 366 C6-891

NRC FORM 388A U.S. NUCLEAR REGULATORY COMMISSION

(~9) APPROVEO 0MB NO. 3160.()104 EXPIRES: 4/30/92 LICENSEE EVE' REPORT (LER) ES ATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS, FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20565, AND TO 1'HE PAPERWORK REDUCTION PROJECT (3160.()104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME 11) DOCKET NUMBER (2) LEA NUMBER (ti) PAGE (3)

Surry Power Station, Unit 1 TEXT fH - - le ,equirwl, ,_ Ndirlotw NRC Fann .mA'aJ 1171

1.0 DESCRIPTION

OF THE EVENT On July 19, 1991, at approximately 1000, with Unit 1 at 100% power, procedure 1-PT-36, "Instrument Surveillance" was being performed by a reactor operator trainee. During the performance of this procedure, the trainee recorded pressurizer levels which differed by 4% and thus exceeded acceptance criteria by 1%. At this point the reactor operator trainee should have red circled the readings, informed the reactor operator of this condition, and informed the shift supervisor. Because the trainee did not recognize the out of specification condition, these required actions were not taken. At approximately 1600, the trainee recorded a second set of pressurizer level readings which also exceeded acceptance criteria by 1% without recognizing that an out of specification condition existed.

The out of specification condition pressurizer levels were not detected by the reactor operator responsible for supervision of the trainee, and neither the day shift reactor operator or the shift supervisor completely reviewed the panially completed procedure prior to shift change. When pressurizer levels were recorded at approximately 2200 and 0400 by the night shift, thus completing the procedure, pressurizer levels had returned to within specification.

During shift turnover on the morning of July 20, 1991, it was noted that the pressurizer level channel check was just within specification. The now completed 1-PT-36 was reviewed by the oncoming shift for trends in pressurizer level. During this review, it was discovered that pressurizer level indicator 1-RC-LI-1461 [EIIS-AB,LT] had exceeded channel check acceptance criteria the previous day during their shift.

This was confirmed by reviewing pressurizer level data from the plant computer. Because the channel should have been declared inoperable when the channel check acceptance criteria was exceeded and this condition existed for a period greater than six hours, the channel should have been placed in trip as required by Technical Specification 3.7 Table 3.7-1.

This occurrence was considered to be a violation of Technical Specification 3. 7 and therefore is being reported pursuant to 10CFR50.73(a)(2)(i)(B).

NRC Form 3611A IIM19)

NRC FORM3"A U.S. NUCLEAR REGULATORY COMMISSION (6-89) APPROVED 0MB NO. 3150-0104 EXPIRES: 4/30/92 E* ATEO BURDEN PEA RESPONSE TO COMPLY WTH THIS LICENSEE EVE' REPORT (LER) INFORMATION COLLECTION REQUEST: 50.0 HAS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P-630). 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 11) DOCKET NUMBER (2) LER NUMBER (11) PAGE (3)

Surry Power Station, Unit 1 91 1 - 011 12 - 0 IO O I3 OF OI 4 TEXT (If,,,,.,. - is requited, - NdllJoMI NRC Fann .MA'*I (17)

2. O SIGNIFICANT SAFETY CONSEQUENCES AND IMPLICATIONS No safety implications were posed by this event. Pressurizer level is monitored by three separate channels . which provide a trip signal to the reactor protection system when two of three channels reach the protection setpoint. Channel 1-RC-Ll-1461 can also be selected for performing pressurizer . level control including the functions of isolating letdown and deenergizing pressurizer heaters on low level.

Although the accident analysis does not take credit for this high level reactor trip signal, a channel reading high, as in this instance, would conservatively generate a reactor trip signal earlier than required.

Therefore, the health and safety of the public were not affected.

3.0 CAUSE QF THE EVENT This event was an isolated incident caused by two cognitive personnel errors. First, a reactor operator trainee failed to properly review recorded data and compare it to acceptance criteria. And second, the licensed reactor operator failed to properly supervise a trainee who was taking logs for which the reactor operator was responsible.

4. O IMMEDIATE CORRECTIVE ACTIQNCS>

Channel 1-RC-Ll-1461 was declared inoperable and placed in trip, a station deviation submitted, and an emergency work order initiated to investigate and resolve the problem.

5.0 ADDITIONAL CORRECTIVE ACTIONCS}

The calibration of channel 1-RC-LI-1461 was checked, no adjustment required, and the transmitter was vented. Following venting of the transmitter, level indication returned to normal. The channel was declared operable and returned to service at 1643 on July ~O. 1991.

6.0 ACTIONS TO PREVENT RECURRENCE The licensed reactor operator was counseled on his responsibility for the accuracy of recorded data and for the proper supervision of assigned trainees. This event and lessons learned will be included in Operation's Depanment required reading to reemphasize requirements fo the proper supervision of assigned trainees.

The reactor operator trainee was counseled on his responsibility for comparing recorded data to acceptance criteria and notifying

~RC Form 3611A C&-891

NRC FORM 388A U.S. NUCLEAR REGULATORY COMMISSION (6-89) APPROVED 0MB NO. 3150-0104 EXPIRES: 4/30/92 E* ATEO BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVE' REPORT (LER) INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555. AND TO 1'HE PAPERWORK REDUCTION PROJECT (3150-0104). OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME CU DOCKET NUMBER C2) LER NUMBER C8) PAGE 131 Surry Power Station, Unit 1 TEXT (If tn019 - la,.,....,, .,. HtllrloMI NRC Fann .1151U~J C17l appropriate personnel when an out of specification condition is identified. This event and lessons learned will be reviewed* with the current RO/SRO license course trainees prior to the next inplant training period. Enhanced instructions will also be provided to future RO/SRO trainees prior to beginning . inplant training.

7.0 SIMILAR EVENTS None.

8.0 ADDITIONAL INFORMATION None.

NRC Form 38M. Cll-89)