ML18151A084

LER 87-023-00:on 870901,standby Charging Pump Automatically Started on Low Charging Pump Discharge Pressure Signal. Caused by Personnel Error.Pressure Transmitter Drain Valve Closed & Isolation Valve opened.W/870928 Ltr

ML18151A084
Person / Time
Site:	Surry
Issue date:	09/25/1987
From:	Benson D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
87-026, 87-26, LER-87-023, LER-87-23, NUDOCS 8710020137
Download: ML18151A084 (4)

Text

'\.,' POW 28-06-01 NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION (9-83)

APPROVED 0MB. NO. 3150-0104 EXPIRES: 8/31/88 LICENSEE EVENT REPORT (LER)

FACILITY NAME (11. DOCKET NUMBER (2) I PAGE 131 TITLE (4)

Surry Power Station, Unit 1 Io Is I o Io I o I 21 8 Io 1 loF o I 3 Inadvertent Auto Start of Standby Charqinq Pump Due To Personnel Error

'EVENT DATE (51 LER NUMBER (61 REPORT DATE 171 OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR It? SE~~~~~~AL tt ~~~~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(S) oI 9 oI 1 s 7 sI1 - oI 21 3 - ob oI9 2 Is sl 7 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Chock on* or mor* of th* folloV(ing) (11)

MODE (8)

N ,_

I1 20.402(b)

- 20.405(cl X 60.73(1)(2)1iv)

- 73.71(b)

POWER L~~~L I O I O-

. 20.406(1)(1 )II) 60.38(c)l1)

-- 60.73(1)(2)(*)

- 73.71(c) 20.406(1)(1lliil 50.38(c)l2) 60.73(o)(2)1vli) OTHER (Spoclfy in Abstr*ct b*low end in T*xt, NRC Form 111111= -

20.405(1)(1)(111) 50.73(1)12)(1) 60.73(o)l2)(vlll)IA) 366A) 20.406(1)11 )(Iv) 20.405(1)(1 )Iv)

- 50.73(o)(2)1il) 50.73(,)(2)(111) 50.73(o)(2)1vlli)(B) 60.73(o)l2)(x)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER AREA CODE D. L. Benson, Station Manager 8 I nl 4 3 I 51 7 I- I ~11 18 I 4 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

MANUFAC- MANUFAC*

CAUSE SYSTEM COMPONENT SYSTEM COMPONENT TURER R~O~~t~kE i!Ji:jJ!i!i!lil!:!jjj!J!li!!:!iljj!j!iliii!il/\1:ilii CAUSE 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!!l!l!i!!!!!!

I I I I I I I li!i!!!i!i!i!i!!ii!!!ili!i!i!il~i!i!ii!i!i!i!i!i:!jj I I I I I I I SUPPLEMENTAL REPORT EXPECTED (141 MONTH DAY YEAR EXPECTED SUBMISSION DATE 115)

• , YES (If y*s, compl*t* EXPECTED SUBMISSION DATE)

I I I ABSTRACT (Limit to 1400 spoc*s, I.*., *pproximately fift**n singl*-spoc* typ*writton lines) (16)

On September 1, 1987 at 1432 hours0.0166 days <br />0.398 hours <br />0.00237 weeks <br />5.44876e-4 months <br />, with the Unit 1 'B' charging pump in service, the standby charging pump (1-CH-P-lA) {EIIS-P} automatically started on a low charging pump discharge pressure signal. This occurred when an instrument technician inadvertently isolated the charging pump discharge header pressure transmitter {EIIS-PT}. The pressure transmitter was unisolated, and the 'A' charging pump was returned to standby condition at 1441 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.483005e-4 months <br />. At the time of this event, Unit 1 was at 100% power.

A HPES investigation is in progress at the time of this report.

Recommendations anticipated for implementation are increased .

training on instrument mark number designations and increased emphasis on verification of mark numbers.

a1100~0 t37cu e~~tao PDR " 00 "O PDR s

NRC Form 316 (9-83)

.... POW-28-06-01 NRC Form 3661.

e e . U.S. NUCLEAR REGULATORY COMMISSION 19-831 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31 /88 FACILITY NAME (1) DOCKET NUMBER (21 LER NUMBER (61 PAGE (31 VEAR Surry Power Station, Unit 1 o 1s Io Io Io I 2 I al o a I 7- o I2 I ~ - o I n n I ., OF n I ~

TEXT /If mo,w - ;. ,_.,,,..,,, u* additioMI NRC Farm BA'*I (171 1.0 Description of the Event On September 1, 1987 at 1432 hours0.0166 days <br />0.398 hours <br />0.00237 weeks <br />5.44876e-4 months <br />, with the Unit 1 'B' charging pump in service, the standby charging pump (1-CH-P-lA) {EIIS-P} automatically started on a low charging pump discharge pressure signal. This occurred when an instrument technician inadvertently isolated the charging pump discharge header pressure transmitter

{EIIS-PT}. The pressure transmitter was unisolated, and the 'A' charging pump was returned to standby condition at 1441 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.483005e-4 months <br />. At the time of this event, Unit 1 was at 100% power.

2.0 Safety Consequences and Implications The charging pumps provide makeup of borated water to the reactor coolant system and provide seal injection to the reactor coolant pump seals, as well as serving as high head safety injection pumps. The standby charging pump auto started, as designed, when the charging pump discharge header pressure indication failed low.

Throughout this event, the 'B' charging pump was operating and the 'A' charging pump was either operating or in standby. Therefore, this event did not constitute an unreviewed safety question and the health and safety of the public were not affected.

3.0 Cause The 'A' charging pump auto-started on a low charging pump discharge pressure signal. The signal was generated when the associated pressure transmitter (PT-1-121) {EIIS PIT} was isolated and drained in error by an 'instrument technician who thought that he was working on another transmitter (PT-BR-121).

4.0 Immediate Corrective Action The pressure transmitter drain valve was closed and the isolation valve was opened. After ensuring that charging pump discharge pressure was normal, the standby charging pump (1-CH-P-lA) was shutdown and placed in automatic.

NRC FORM 386A (9-83)

• U.S.GPO: 1986*0*824-538/455

. ),

Pow-2s.:..06-0l NRC Form 366t.

e e U.S. NUCLEAR REGULATORY COMMISSION 19-831 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31/88 FACILITY NAME 111 DOCKET NUMBER 121 LEA NUMBER 161 PAGE 131 Surry Power Station, Unit 1 o I5 I o I o I o I 2 I g I n .A i - nI  ?! -:i - nl n rl 2 OF nI 2 TEXT /If_,,.-,,.;. -,und, u* - - NRC Form .-..**J 1171 5.0 Additional Corrective Action None.

6.0 Action Taken to Prevent Recurrence A HPES investigation is in progress at the time of this report. Recommendations anticipated for imple-mentation are increased training on instrument mark number designations and increased emphasis on verification of mark numbers.

7.0 Similar Events N/A 8.0 Manufacturer/Model Number N/A NRC FORM 366A 19-831

• U.S.GPO: 1986*0*824*538/455

},

VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station P. 0. Box 316 Surry, Virginia 23883 September 28, 1987 U.S. Nuclear Regulatory Commission Serial No.: 87-026 Document Control Desk Docket No.: 50-280 016 Phillips Building Licensee No.: DPR-32 Washington, D.C. 20555 Gentlemen:

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

REPORT NUMBER 87-023-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by Safety Evaluation and Control.

Very truly yours, David L. Benson Station Manager Enclosure cc: Dr. J. Nelson Grace Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323