ML18152A790

LER 88-007-00:on 880224,control/relay Room Chiller Tripped. Caused by Insufficient Svc Water Flow.Throttled Svc Water Valves Fully Opened & Correct Outlet Valve Throttled to Obtain Proper Svc Water flow.W/880317 Ltr

ML18152A790
Person / Time
Site:	Surry
Issue date:	03/17/1988
From:	BENSON D L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-009, 88-9, LER-88-007-01, LER-88-7-1, NUDOCS 8803290277
Download: ML18152A790 (4)

Text

I . POW 28-06-01 NRC Form 366 (9-83) LICENSEE EVENT REPORT (LER) U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31/88 FACILITY NAME (1) Surry Power Station, Unit 1 1 DOCKET NUMBER (2) PAGE 131 O I 5 I O I O I O 12 I 8 1-0 1 I OF O I 3 TITLE l'l Control /Relay Room Chillers Inoperable Due To Inadequate Service Water Flow EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) MONTH DAY YEAR YEAR }tt tr MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(Sl 01s1010101 I I OPERATING MODE (9) THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: {Cht1ek on* or mar* of th* follo"(ing}

(11) I t\l 20.402(b) 20.406(c) 50,73(o)(2)(iv)

-,_ -20.406(0)(1

)(I) 50.31(cl(1) 50.73(oll2lM

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,__ 20.406(0)(1 Hill 50.31(c)(2) 50.73(0)(2) (vii) LEVEL 1--73.71(b) 73.71 (cl OTHER {Spt1cify in Abstr*ct -----b*low and In T*xt, NRC Form POWER I (10) 11 nl n tltl\ii= 20.406(01(1

)(Ill) 60.73(o)(2)(1J 50,73(a)(2)(vlll)(A) 366A} 1--20.406(0)(1

)(Iv) IS0.73(1)(21(11)

IS0.73(1)(2)(vlll)(B)

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20.406(1)(1)(¥1 60.73(1)(21(111) 50.73(11(21(x)

LICENSEE CONTACT FOR THIS LER (12) NAME TELEPHONE NUMBER AREA CODE D. L. Benson, Station Manager 8 I O r 4 3 I 5 I 71 -1 3 I 1 I 8 I 4 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) SYSTEM COMPONENT MANUFAC-TURER CAUSE SYSTEM COMPONENT MANUFAC. TUAER R~~o~~tg~E ililili!i!1li!ilili!1!1!il1!1!1lil1!ili!ili!ili!i!1Ji CAUSE 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 '!ll!:l!l!lll::!/!l!l!l!l!!!l!lll:lllll!l!l!l!)Jjjjj SUPPLEMENTAL REPORT EXPECTED 11,) MONTH DAY YEAR EXPECTED SUBMISSION DATE 115) * , YES {If y*s, complot11 EXPECTED SUBMISSION DATE/ I I ABSTRACT /Limit to 1400 spaco,, I.*., *pproximat11/y flftHn 1/ng/a-spaco typt1writt11n

/inn/ (111) On February 24, 1988 at 1005 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.824025e-4 months <br />, with Unit 1 and Unit 2 at 100% power, one of the three control room/relay room (CR/RR) chillers (l-VS-E-4C)

{EIIS-CHU}

tripped on high condenser discharge pressure.

The 'B' chiller unit had previously been removed from service for cleaning of its service water (SW) {EIIS-BI}

strainer {EIIS-STR}.

This condition is contrary to Technical Specification 3.14 which requires one CR/RR chiller to be operating and another to be operable.

After the 'C' chiller tripped, the 'A' chiller was imrned.fately started. The 1 C' chiller was returned to service at 1110 hours0.0128 days <br />0.308 hours <br />0.00184 weeks <br />4.22355e-4 months <br /> and the 'A' chiller was secured. The chiller tripped due to insufficient SW flow. SW flow to the chiller was being controlled manually because the normal pressure control valves (1-SW-PCV-lOOC

& 1-SW-PCV-lOlC)

{EIIS-PCV}

were out of service. In addition, a manual inlet and outlet valve to the 'C' chiller which should have been fully open, were found throttled.

The throttled SW valves were fully opened, and the correct outlet valve was throttled to obtain proper SW flow. The normal chiller pressure control valves will be repaired.

8:::0:3290.._*?77 8 PDR ~80317 s ADOCK osooo2eo NRC Form 3811 (9-83) DCD I NRC Form 369A 19-831 FACILITY NAME (1) LICENSEE EVENT REPORT (LERI TEXT CONTINUATION DOCKET NUMBER (21 U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31/88 LER NUMBER (61 PAGE (JI Surry Power Station, Unit 1 o 1s101010121810 818 -01011 -01 o 012 oF ol3 TEXT (If mot9 -io ,equl,ed, -.,,_,. NRC Fann .Jllll;4'1J f 171 NAC FOAM 366A (9-831 1.0 Description of the Event On February 24, 1988 at 1005 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.824025e-4 months <br />, with Unit 1 and Unit 2 at 100% power, one of the three control room/relay room (CR/RR) chillers (1-VS-E-4C)

{EIIS-CHU}

tripped on high condenser discharge pressure.

The 'B' chiller unit had previously been removed from service for cleaning of its service water (SW) {EIIS-BI}

strainer {EIIS-STR}.

This condition is contrary to Technical Specification 3.14 which requires one CR/RR chiller to be operating and another to be operable.

After the 'C' -chiller tripped, the 'A' chiller was immediately started. The 'C' chiller was returned to service at 1110 hours0.0128 days <br />0.308 hours <br />0.00184 weeks <br />4.22355e-4 months <br /> and the 'A' chiller was secured. 2.0 Safety Consequences and Implications The CR/RR air conditioning system consists of three air conditioning chiller units. The design temperatur~

of the CR/RR spaces is from 40 degrees Fahrenheit to 120 degrees Fahrenheit.

During this event, the CR/RR air handling Units remained operable or operating.

In addition, there was no noticeable increase in ambient temperature of the CR/RR areas. Therefore, the health and safety of the public were not affected by this event. 3.0 Cause The cause of the chiller trip was insufficient SW flow which resulted in insufficient heat transfer from refrigerant to SW causing the high condenser discharge pressure trip. SW flow to the chiller was being controlled manually'because the normal pressure control valves (1-SW-PCV-lOOC

& 1-SW-PCV-lOlC)

{EIIS-PCV}

were out of service. Increased SW flow to 'C' chiller was required when the 'B' chiller was shut down for maintenance.

Since the SW flow to the 'C' chiller was being controlled manually, flow did not automatically increase to meet the higher demand. In addition, a manual inlet and outlet valve to the 'C' chiller which should have been fully open, were found throttled.

• U.S.GPO: 1986-0-624*536/455 NRC Form JeeA (9-83) FACILITY NAME (1) LICENSEE EVENT REPORT (LERI TEXT CONTINUATION DOCKET NUMBER (21 POW 28-06-01 U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 31 50-0104 EXPIRES: 8/31 /88 LER NUMBER (6) PAGE (3) Surry Power Station, Unit 1 0 5 0 0 0 TEXT (If"'°"' _.,. ia -,und, u* eddltiaMI NRC Fam, .-.C'*J 1171 4.0 Immediate Corrective Action(s)

The throttled SW valves were fully opened, and the correct outlet valve was throttled to obtain proper SW flow. The 'C' chiller was returned to service with no further problems.

5.0 Additional

Corrective Action(s)

Service water pressure to the CR/RR chillers is checked at least every four hours. 6.0 Action(s)

Taken to Prevent Recurrence The normal chiller pressure control valves will be repaired.

Design work is proceeding on upgrading the service water supply to the CR/RR chillers.

The operations training program includes training on proper operation of heat exchanger inlet and outlet valves; *and this event will be included in future retraining sessions.

7.0 Similar

Events Although this specific event has not occurred before, previous incidents of inadequate SW flow to the CR/RR chillers have been reported.

8.0 Manufacturer/Model Number N/A . . NRC FOAM 3158A (9-83)

• U.S.GPO: 1988*0-824-538/455 e March 17, 1988 U.S. Nuclear Regulatory Commission Document Control Desk 016 Phillips Building Washington, D.C. 20555 Gentlemen:

e VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station P. 0. Box 315 Surry, Virginie 23883 Serial No.: Docket No.: Licensee No. : 88-009 50-280 DPR-32 Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Coapany hereby submits the following Licensee Event Report for Surry Unit 1. REPORT NUMBER 88-007-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by Safety-Evaluation and Control. Very tTIIly yours, David L. Benson Station Manager Enclosure cc: Dr. J. Nelson Grace Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323