05000281/LER-1988-014-02, :on 880528,RCS PORV PCV-2455C Cycled Open & Closed,Simultaneous W/Rcs Venting & Filling.Caused by Failure to Revise RCS Venting Procedure.Operating Procedures Revised

:on 880528,RCS PORV PCV-2455C Cycled Open & Closed,Simultaneous W/Rcs Venting & Filling.Caused by Failure to Revise RCS Venting Procedure.Operating Procedures Revised

ML18152B177
Person / Time
Site:	Surry
Issue date:	06/27/1988
From:	Benson D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-030, 88-30, LER-88-014-02, LER-88-14-2, NUDOCS 8807010450
Download: ML18152B177 (4)

LER-1988-014, on 880528,RCS PORV PCV-2455C Cycled Open & Closed,Simultaneous W/Rcs Venting & Filling.Caused by Failure to Revise RCS Venting Procedure.Operating Procedures Revised

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(o)(2)(vii)
2811988014R02 - NRC Website

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NflC Form 366 (9-83)

FACILITY l'IAME (1)

Surry Power Station, Unit 2 POW 28~06-01-01 U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 3160-0104 El<PIRES: 0/31/llS DOCKET NUMBER (2)

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TITLE (1)

Lifting of Power Operated Relief Valve Due To Procedural Inadequacy

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LER NUr,113ER (6)

Rtl:PORT DATE (7)

OTHER FACILITl!:S INVOLVED (8)

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LICENSEE CONTACT FOR THIS LEA (12)

NAME TELEPHONE NUMBER AREA COOE D. L Benson, Station Manager 8 I O I 4 31 5 I 71 -I ~ I 1 IR I U CAUSE SYSTEM COMPONENT I

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.MlSTRACT./Limit to 1400 spscas, i.e.* opproximot*ly fiftsen singl*-spsce typewritten lin*sl (16)

On May 28, 1988 at 0228 hours0.00264 days <br />0.0633 hours <br />3.769841e-4 weeks <br />8.6754e-5 months <br />, with Unit 2 in cold shutdown, a Reactor Coolant System (RCS) {EIIS-AB} Power Operated Relief Valve (PORV), PCV-2455C {EIIS-PCV} cycled open and then closed.

At the time of the event, RCS venting and filling was in progress and a Reactor Coolant Pump (RCP) {EIIS-P} had just been started" The pressure transient, caused by the start of the RCP with a solid water plant condition, created a pressure rise and lifted the PORV which was set to open at 375 psig.

The PORV immediately closed and the RCS pressure stabilized at approximately 340 psig.

This event is reportable pursuant to Technical Specification (T.S.) 3.1.G.3 and 6.6.C.

The cause of the event was failure to revise the RCS venting procedure when the PORV lift setpoints were reduced.

The administrative procedure which provides the instructions for processing setpoint change requests requires that documents affected by the setpoint change be reviewed.

However, there was no mechanism to ensure that these documents were revised.

The operating procedures for both units are being revised to reduce the required RCS pressure band for operating a RCP when venting the RCSo The administrative procedure will be revised to provide a mechanism to ensure that documents affected by the setpoint change will be revised in a timely manner.

8807010450 880627 PDR ADOC~ 05000281 S

DCD NRC Form 366 (9-83)

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'NRC FORM 366A CS-831 1.0 Descri_Etion of the Event On May 28v 1988 at 0228 hour0.00264 days <br />0.0633 hours <br />3.769841e-4 weeks <br />8.6754e-5 months <br />su with Unit 2 in cold shutdown, a Reactor Coolant System (RCS) {EIIS=AB}

Power Operated Relief Valve (PORV), PCV-2455C

{EIIS-PCV} cycled open and then closedo At the time of the eventu RCS venting and filling was in progress and a Reactor Coolant Pump (RCP) {EIIS=P} had just been started.

The pressure transient, caused by the start of the RCP with a solid water plant conditionr created a pressure rise and lifted the PORV which was set to open at 375 psigo The PORV irrunediately closed and the RCS pressure stabilized at approximately 340 psigo This event is reportable pursuant to Technical Specification (T.S.) 3.1.G.3 and 6.6oC.

2.0 Safety Conseguences and Implications The operability of two PORVs or the RCS vented through an opened PORV ensures that the reactor vessel will be protected from pressure transients which could exceed the limits of Appendix G of 10CFR Part 50, when the RCS temperature is less than or equal to 350 degrees Fahrenheit and the reactor vessel head is bolted.

During the event, PCV-2455C performed as required to maintain RCS pressure within T.S. limits.

Therefore 1 the health and safety of the public were not affected.

3.0

Cause

The cause of the event was failure to revise the RCS venting procedure when the PORV lift setpoints were reduced.

The setpoints were changed in April, 1988 following an analysis from the reactor vessel material surveillance program, which revised the heatup and cooldown curves currently in Technical Specifications.

The administrative procedure which provides the instructions for processing setpoint change requests requires that documents affected by the setpoint change be reviewed.

However, there was no mechanism to ensure that these documents were revised.

• • U.S.GP0.19B6-0-624-538/455

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Immediate Corrective Action(s)

The PORV was verified shut and RCS pressure was verified below the PORV setpointo 5.0 Additional Corrective Action(s) 6.0 7.0 8.0 The PORV setpoint was verified to be 375 psig.

The PORV was cycled open and closed to verify operabilit*y.

Action(s) Taken to Prevent Recurrence The operating procedures for both units are being revised to reduce the required RCS pressure band for operating a RCP when venting the RCS.

This will increase the available pressure operating band prior to reaching the PORV setpointso The administrative procedure will be revised to provide a mechanism to ensure that documents affected by the setpoint change will be revised in a timely manner.

Similar Events

None.

Manufacturer/Model Number N/A

• U.S.GP0.1966*0*624 538/455

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June 27s, 1988 U.S. N~clear Regulatory Commission Documa~t Control Desk 016 Phillips Building Washington, D.C.

20555 Gentlemen:

Vl~Gll\\llA ~l.!fC'filllC ANO POWER COMPANY

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• Serial No.:

Docket No.:

Licensee No.:

88-030 50-281 DPR-37 Pursuant to Surry Power Station Technical Specifications 9 Virginia Electric and Power Company hereby submits the following Licensee Event Report for Surry Unit 2.

REPORT NUMBER 88-014-00 This report bas been reviewed by the Station Nuclear Safety and Operating Cotmnittee 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 9 Georgia 30323