ML18153B532

LER 88-021-00:on 880908,required Test Frequency for B Low Head Safety Injection Pump Exceeded.Caused by Inability of Operator to Obtain Required Vibration Test W/Test Equipment Used.Formal Training of Equipment administered.W/881006 Ltr

ML18153B532
Person / Time
Site:	Surry
Issue date:	10/06/1988
From:	Benson D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-050, 88-50, LER-88-021-01, LER-88-21-1, NUDOCS 8810170157
Download: ML18153B532 (4)

Text

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

APPROVED DMB. NO. 3160-0104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31/88 FACILITY NAME (1) DOCKET NUMBER (2) PAGE 131 11 Surry Power Station, Unit 2 IO I 5 I O I O I O I 2 I 81 1 1 OF O I 3 I TITLE 14) 8 11 LHS I Pump Not Tested Within Required 8 Hour Interval Due To Inoperable Test Equipment EVENT DATE 15) LER NUMBER 16) REPORT DATE 171 OTHER FACILITIES INVOLVED IB)

MONTH DAY YEAR YEAR *]t SE~~~~~~AL tt ~~t~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERIS) o I 9 oIs a a aI a - oI 2 I 1 .:.... ob 1 I o o 16 s Is THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Chock on* or more of th* follo"(ing/ (11)

OPERATING MODE C9)

N I

20.4021b) 20.405(*111 )II) 20.405(cl 60.381c)(11 ---

50.73(a)l2)1iv) 50.73lall21M

.__ 73.711b) 73.71(c)

POWER .

1--

L~~~L O I 7 I 2 ..- 20.405(*1111111) .___ 60.38lc)(2) 60.731*11211vll) .__ OTHER (Spocify in Abstnct al'IJ=

20.4051*11111111) 20.40611111 lllvl 20.405(a)(11M

---" };.. *60,73la)(2)11) 60,73(1112lliil 60.73(111210111

&0.7311112)(vllll(AI 50.7311)(211vlll)(BI 50,73(1)(211xl IH/ow and In ToKt, NRC Form 366A}

LICENSEE CONTACT FOR THIS LER 1121 NAME TELEPHONE NUMBER AREA CODE D. L. Benson, Station Manager 810 14 315171-1 31 11814 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC- MANUFAC-CAUSE SYSTEM COMPONENT SYSTEM COMPONENT TURER TURER R~O~lt8iE  :!!1:i!i:iiiii:iiii!lil!iiiii!l!lii!l!l!!il!i!!!lijjj CAUSE I I I I I I I I I I I I I I I .I I I I I I :jj!jl!l!!il!l!!ili!i!ilili!i!!!llil!!il!!ili!i!!/jjj I I I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR EXPECTED

~

SUBMISSION I YES (If v**. comp/or. EXPECTED SUBMISSION DA TEI NO DATE 1151 I I I ABSTRACT (Limit to 1400 spoc*s. i.*.* *pproxim*t*ly fifto*n sing/B-spoc* typ*writrBn lin*sl 1161 On September 7, 1988 at 1750 hours0.0203 days <br />0.486 hours <br />0.00289 weeks <br />6.65875e-4 months <br />, with Unit 2 at 72% power, the "A" Low Head Safety Injection (LHSI) pump was removed from service to facilitate maintenance activities. Prior to this, at 1611 hours0.0186 days <br />0.448 hours <br />0.00266 weeks <br />6.129855e-4 months <br />, the "B" LHSI pump had been satisfactorily tested per the requirements of Technical Specification (T. s.) 3.3.B.3. At 2326 hours0.0269 days <br />0.646 hours <br />0.00385 weeks <br />8.85043e-4 months <br />, a second test was conunenced on the "B" pump per the eight hour test frequency required by T. s. The test was not completed satisfactorily until September 8, at 0050 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />, exceeding the required test frequency by 39 minutes. The delay of completing the test on the "B" p'ump was due to the inability of the operator performing the test to obtain the required vibration data with the test equipment .being used. Another vibration test instrument of a different type was obtained and the test was completed satisfactorily. Formal training on use of*

the vibration test equipment used during the event will be administered to the non-licensed operators.

8810170157 881006 PDR ADDCR 05000281 S PNU NRC Form 386 19-831

POW 28-06-01-01

\ NRC Form 38BA U.S. NUCLEAR REGULATORY COMMISSION

, (9-83)

LICENSEE EVENT REPORT (LER) TEXT CONTINUA ION APPROVED OMS NO. 3150-0104 EXPIRES: 8/31 /811 FACILITY NAME (11

• DOCKET NUMBER (2) LER NUMBER (61 PAGE (31 Surry Power Station, Unit 2 o Is Io Io I o I 21 s 11 sIs - o I 211 - oIo o 1 2 oF o 13 TEXT /ff more space ls mquirrtd, use addhion11/ NRC Form 366A's/ (171 1.0 Description of the Event on September 7, 1988 at 1750 hours0.0203 days <br />0.486 hours <br />0.00289 weeks <br />6.65875e-4 months <br />, with Unit 2 at 72% power, the "A" Low Head Safety Injection (LHSI) pump {EIIS-PB, P} was removed from service in order to repair a leak on a flow element fitting. Prior to this, at 1611 hours0.0186 days <br />0.448 hours <br />0.00266 weeks <br />6.129855e-4 months <br />, the "B" LHSI pump had been satisfactorily tested, per the requirements of Technical Specification (T. S.) 3.3.B.3, in preparation for the removal of the "A" LHSI pump from service. At 2326 hours0.0269 days <br />0.646 hours <br />0.00385 weeks <br />8.85043e-4 months <br />, a second test was commenced on the "B" LHSI pump, in compliance with the eight hour test frequency required by T. S. However, during this test, operators had difficulty obtaining the vibration data required to complete the test using the vibration test equipment at hand and the test was delayed until another vibration meter could be found. The test was restarted after the other vibration meter was obtained and was completed satisfactorily at 0050 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> on September 8. This exceeded the required eight hour test frequency by 39 minutes.

2.0 Safety Consequences and Implications The LHSI pumps function to provide coolant to the reactor core in the event of a large break loss of coolant accident. One operable LHSI pump is assumed in the safety analysis. Since the "B" LHSI pump remained operable throughout the duration of the event, as verified by satisfactory testing, the plant remained within the bounds of the safety analysis. Therefore, the health and safety of the public were not affected.

3.0 Cause The delay in completing the operability test on the "B" LHSI pump was due to the inability of the operator performing the test to obtain the required vibration data with the test equipment being used.

The data could not be obtained because the test equipment had been damaged and was not operating properly. Also, the operator performing the test did not recognize that the equipment was not operable until the test was already in progress.

NRC FORM 366A *U.S. GPO, 1988-520-589,00070 (9,831

POW 28-06-01-01 U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LERI TEXT CONTINUA ON APPROVED 0MB ND. 3150--0104 EXPIRES: 8/31/88 FACILITY NAME 11)

• OOCKET NUMBER 12) LER NUMBER 16) PAGE 13)

Surry Power Station, Unit 2 o 1s101010121s11 sis -01211 - 010 o 13 oFo 13 TEXT (ff more space is required, use additional NRC Form 366A 's/ 1171 4.0 Immediate Corrective Action(s)

When the operator determined that he was unable to obtain the vibration data with the test equipment at hand, another vibration test instrument, of a different type, was obtained and the test was completed satisfactorily. Additionally, at 0011 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> on September 8, 1988, the time at which the required eight hour test frequency was exceeded, a six hour clock to hot shutdown was commenced per T. s. 3.0.1, and was terminated when the test was completed satisfactorily.

5.0 Additional Corrective Action(s)

The remaining tests on the "B" LHSI pump were performed within the required time intervals and the "A" LHSI pump was returned to service at 1713 hours0.0198 days <br />0.476 hours <br />0.00283 weeks <br />6.517965e-4 months <br /> on September 8, 1988.

6.0 Action(s) Taken to Prevent Recurrence Formal training on use of the vibration test equipment used during the event will be administered to the non-licensed operators. In addition, operators will be reminded to thoroughly inspect test equipment prior to use.

7.0 Similar Events None.

8.0 Manufacturer/Model Number N/A NAC FORM 366A *u.s. GPO, 1988-520-589100070 (9-83)

VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station P. 0. Box 316 Surry, Virginia 23883 October 6, 1988 U.S. Nuclear Regulatory Commission Serial No.: 88-050 Document Control Desk Docket No.: 50-281 016 Phillips Building Licensee No.: DPR-37 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 2.

REPORT NUMBER 88-021-00 This report has been reviewed by the Station Nuclear Safety and Operating Cononittee and will be reviewed by Safety Evaluation and Control.

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

---Cf~,-.

/

. ,.l ,