ML18152A935

LER 88-008-00:on 880505,reactor Operator Discovered That No Boric Acid Flowpath Existed from Boric Acid Storage Tanks to Charging Pumps.Caused by Personnel Error & Procedural Inadequacy.Procedures Will Be revised.W/880606 Ltr

ML18152A935
Person / Time
Site:	Surry
Issue date:	06/06/1988
From:	Benson D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-023, 88-23, LER-88-008-02, LER-88-8-2, NUDOCS 8806130056
Download: ML18152A935 (4)

Text

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

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

FACILITY NAME (1) DOCKET NUMBER 12) I PAGE 131 Surry Power Station. Unit 2 o I 5 I o I o I o I 21 81 1 , loF nl~

TITLE (4)

Inadequate Boric Acid Flowoaths Due To PersonnAI Error and '

lnadii:>m1~to Prnrorl11r,:,c.

EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR ,{t SE~~~~~~AL tt ~EX.~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(SI oI s ~ s s s s I s - o I o Is - oIo o I 6 oI6 sl s THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Ch*ck on* or mar* of th* folloll(ing) (11)

OPERATING MODE (9)

N ,_ 73.71(b)

I 20.4021b, 20.406(c) 60.73(1)(2)(iv)

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60.38(c)(1) 60.73(1)(2)(v) 73.71(c)

POWER 20.406(1)(1 )(i) ..._

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50.38(c)(2) 60.73(1)(2)(1) 60.73(1)(2) (vii) 60.73(o)(2)(viiil(A)

OTHER (Sp*cify in Abstr*ct bslow and in Tsxt, NRC Form 366A) 11111111111= :::::::~;: - 50.73(o)(2)(ii) 60.73(0)(2)(111)

LICENSEE CONTACT FOR THIS LER (12) 60.73(0) (2) (viii) (Bl 60.73(o)(2llxl NAME TELEPHONE NUMBER AREA CODE D. L. Benson, Station Manager 81014 315171-13111814 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

MANUFAC* MANUFAC*

CAUSE SYSTEM COMPONENT CAUSE SYSTEM COMPONENT TURER TURER I I I I I I I I I -I I I l I i I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED j YES (If v*s, complete EXPECTED SU8/'11SSIDN DA TEI ABSTRACT (Limit to 1400 spoces, I.*.. opproximatBly fiftoon single-spec* tvP*Writton lin*sl (18) rxi NO SUBMISSION DATE 115)

I I I On May 5, 1988 at 1749 hours0.0202 days <br />0.486 hours <br />0.00289 weeks <br />6.654945e-4 months <br />, with Unit 2 at 98% power, the reactor operator discovered that no boric acid flowpath existed from the Boric Acid Storage Tanks (BASTs)

{EIIS-CB TK} to the charging pumps {EIIS-P}. This is in violation of Technical Specification 3.2.B.4.

The loss of the flowpath was due to personnel error and procedural inadequacy in restoring one boric acid transfer pump to service following maintenance. The loss of the flowpath ~isted for seven (7) hours. A second flowpath from the Refueling Water Storage Tank (RWST) to the core existed during this event.

Procedures will be revised to clarify valve alignment in the system for the various possible combinations of tanks and pumps.

8806130056 g~ggg~81 PDR ADOCK PDR s

NRC Form 388 19-83)

NRC Form 3811A (9-83) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE -NT REPORT (LER) TEXT CONTINUA-N APPROVED 0MB NO. 3150,-0104 EXPIRES: 8/31 /88 FACILITY NAME (1) DOCKET NUMBER (21 LER NUMBER (6) PAGE 13)

Surry Power Station, Unit 2 0 15 I O I O IO 12 18 11 8 I 8 - 0 I OIs - 0IO O 12 OF 013

!TIXT 111 lflOtW , , _ . * ,eqund. .,. lltltlltioMI NRC Fann .1fi6A'*I (17) 1.0 Description of the Event on May 5, 1988 at 1749 hours0.0202 days <br />0.486 hours <br />0.00289 weeks <br />6.654945e-4 months <br />, with Unit 2 at 98%

power, the control room operators attempted to perform a blended flow makeup from the Unit 2 Chemical and Volume Control System (CVCS) {EIIS-CB} to the Volume Contra~ Tank (VCT) {EIIS-TK}. However, no boric acid flow was indicated in the control room. Operators verified locally, that the flowpath from the Boric Acid Storage Tank (BAST) {EIIS-TK} to the core was isolated.

This condition is contrary to Technical Specification 3.2.B.4 which requires two (2) operable boric acid flowpaths to the core; one flowpath from the BASTs and the other from the Refueling Water Storage Tank (RWST)

{EIIS-TK}.

2.0 Safety Consequences and Implications The eves consists of four (4) Boric Acid Transfer Pumps (BATPs) {EIIS-P} and three (3) BASTS. The system is shared between the two units. Normal system lineup is such that one (1) tank and pump are recirculating and in service to each unit while the third tank and one pump are on recirculation only. The BATPs take suction from the BAST and provide boric acid solution to the charging pump suction for reactivity control.

The charging pumps can take suction from the VCT, the BATPs and the RWST. The quantity of boric acid in either the BAST or the RWST is sufficient to achieve cold shutdown condition at any time during core life.

The RWST was available at all times during this event, therefore the health and safety of the public were not affected.

3.0 Cause j\.t 1135 hours0.0131 days <br />0.315 hours <br />0.00188 weeks <br />4.318675e-4 months <br /> on May 5, 1988, following main~nance on the "2D" BATP, a performance test was performed satisfactorily .. The last step in the procedure instructs the operator to align the pump and tanks as desired for plant operation. It was desired to place the "2D" pump in service while recirculating with "C" BAST. The reactor operator instructed a non-licensed operator to accomplish this using an operating procedure. The reactor operator did not review the operating procedure nor did he have a copy of the procedure in the control room.

NAC FOAM 366A (9-83)

U.S.GP0:1986-0-6. 538/455

uw :rn-ua=o1-01 NRC Form 386A U.S. NUCLEAR REGULATORY COMMISSION (9-83)

LICENSEE -NT REPORT (LER) TEXT CONTINU.N APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31 /88 F.t.ClllTY NAME (1) DOCKET NUMBER (2) LEA NUMBER (6) PAGE (3)

SEQUENTIAL

::::::::: REVISION

NUMBER  ::::::::::- NUMBER Surry Power Station, Unit 2 o Is Io Io Io I 21 811 8 I8 - O IO I 8 - O IO oI 3 OF o I3

!fllCT (II - ~ ii,.,,.,,_,, ,_ ~ NRC Farm 31i15A'*) (17)

He did not realize that the operating procedure only placed the "C" BAST on recirculation with the "2D" pump. Following the completion of the OP, the reactor operator verified blended flow of .6 gallons. The blended flow integrator is routinely used to provide additional assurance that a correct flow path exists.

4.0 Immediate Corrective Action(s)

An operator was dispatched to the BATPs to investigate the valve lineup. At 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />, the valves were correctly positioned and the boric acid flowpath was reestablished. The reactor operator verified blended flow of 3 gallons. The flowpath was inoperable for approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

5.0 Additional Corrective Action(s)

None required.

6.0 Action(s) Taken to Prevent Recurrence A Human Performance Evaluation of this event was conducted and contributing factors were identified.

Procedures will be revised to require a blended boric acid flow of sufficient volume to verify a boric acid flowpath.

eves valve lineup procedures will be reviewed and new procedures will be written as necessary to ensure that procedures exist to accomplish the various alignment possibilities that exist in this system.

7.0 Similar Events Unit 1 LER 86-12 dealt with a loss of boric acid flowpcft:h due to valve mispositioning. Following this event, valve labeling was improved. Additionally, procedures were written to accomplish some of the various valve alignment possibilities for the eves, however, no normal operating procedure existed for aligning the "2D" BATP to the "C" BAST.

8.0 Manufacturer/Model Number N/A NRC FORM 366A

• U.S.GPO: 1986-0-6. 1-538/455 (9-83)

i VIRGINIA ELECTRIC ANO POWER COMPANY Surry P~r Station P.O. 11011 31!

Surry, Vlrginl1 23883 June 6, 1988 U.S. Nuclear Regulatory Commission Serial No.: 88-023 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 88-008-00 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, GeA-gia 30323