05000395/LER-1993-003

LER 93-003-00:on 930628,purge Sys Discovered Outside Provisions of Ts.Caused by Personnel Error.Operations Mgt Communicated Importance of Proper Procedural Usage & Stressed Usage Level requirements.W/930830 Ltr

ML20056H353
Person / Time
Site:	Summer
Issue date:	07/28/1993
From:	Proper J, Skolds J SOUTH CAROLINA ELECTRIC & GAS CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-003-01, LER-93-3-1, RC-93-0233, RC-93-233, NUDOCS 9309090184
Download: ML20056H353 (4)

LER-2093-003,

Event date:
Report date:
3952093003R00 - NRC Website

text

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John A.

&_ 2A Couth Carolma Dettlic & Gas Company gglggsCmes 3 ko s Nuc

• one'a'ons SCE&G  !

August 30, 1993 L Refer to: RC-93-0233 l

Document Control Desk U. S. Nuclear Regulatory Commission  ;

Washington, DC 20555 Gentlemen:

Subject:

VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)

DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 i RESPONSE TO NOTICE OF VIOLATION NRC INSPECTION REPORT 93-19 Attached is the South Carolina Electric & Gas Company (SCE&G) Licensee Event Report No.93-003 which responds to the violation addressed in Enclosure 1 of NRC Inspection Report 50-395/93-19. SCE&G is in agreement with the alleged i violation, and the enclosed response addresses the reason for the violation and corrr:ctive actions being taken to prevent recurrence. Additional corrective action items 1 and 2 have been completed.

If you should have any questions, please call at your convenience.

Very truly yours, M

John L. Skolds DCH:lcd Attachment c: 0. W. Dixon (w/o attachment)

R. R. Mahan (w/o attachment)

R. J. White S. D. Ebneter i NRC Resident Inspector 1 J. B. Knotts Jr. '

J. I. Byrd  !

NSRC '

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'"" M u~n M ," 19"#3, aI0l 65 To*urs, approval was granted by the control room to remove At e spheric Radiation Monitor RMA-2 from service to allow the performance of pn entive maintenance. A Removal and Restoration Checklist (R&R) was entered and logged in the control room documenting that RMA-2 was out of service. The status of RMA-2 was discussed and included as part of turnover to the oncoming shift which was completed at approximately 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />.

Soon after turnover was completed, the Reactor Building pressure alarm annunciated indicating the pressure was approaching the low pressure limit allowed by Technical Specifications. At 0745, the control building operator c .!ned purge supply valves PVG-6056 and 6057 and started purge supply fan XFN-95 to increase reactor building pressure without consulting System Operating Procedure (SOP) 114, Reactor Building Ventilation System. Shortly after the valves were opened, another control room operator noticed the valves were open and pointed out that the valves should be closed due to RMA-2 being out of service. The fan was stopped and the valves were closed at 0748. Action 17 of Table 3.3-3 states that plant operation may continue provided the containment purge and exhaust valves are maintained closed. Opening the valves with RMA-2 out of service constitutes operation outside the provisions of Technical Specifications.

Radiation levels inside containment were normal and remained steady during the three minutes the valves were opened. Therefore, this event resulted ir: no safety consequences.

Operations management has communicated to all operations personnel the importance of proper procedural usage and stressed the usage level requirements defined in Station Administrative Procedure (SAP) 123, Procedural Use and Adherence (Revision - 1).

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Virgil C. Summer Nuclear Jtation o is Io lo 10 t 31915 91 3 _ - 01013 -

010 012 or O! 3 j vw - ~ _ c o , w., m, PLANT IDENTIFICATION:  ;

L Westinghouse - Pressurized Water Reactor j i

EQUIPMENT IDENTIFICATION:

Contaicment Isolation Valve EIIS - JM i

IDENTIFICATION OF EVENT: -

A personnel error in performing a plant evolution without proper procedural adherence I led to operations outside the provisions of Technical Specifications (T.S.). l 1

i EVENT TIME AND DATE* t June 28, 1993, at 0745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br />. l REPORT DATE: i July 28, 1993  ;

I' This report was initiated by Off-Normal Occurrence report 93-046.

CCNDITIONS PRIOR TO EVENT: i Mode 1, 100% power DESCRIPTION OF EVENT:

On June 28, 1993, at 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> approval was granted by the control room to remove  ;

Atmospheric Radiation Monitor RMA-2 from service to allow the performance of preventive j maintenance. 'A Removal and Restoration Checklist (R&R) was entered and logged in the j control room documenting that RMA-2 was out of service. (The R&R logs are part of the configuration control process used to aid operations personnel in tracking the status of out-of-service' equipment and any associated alternate actions.) The status of RMA-2 was discussed and included as part of turnover to the oncoming _ shift which was completed at approximately 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />.

Soon after turnover was completed, the Reactor Building pressure alarm annunciated indicating the pressure was approaching the low pressure limit allowed by Technical Specifications. At 0745, the control building' operator opened purge supply valves PVG-6056 and 6057 and started purge supply fan XFN-95 to increase reactor building pressure without consulting System Operating Procedure (SOP) 114, Reactor Building Ventilation System. Shortly after the valves were opened, another control room operator noticed

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001 013 or 0l3 the valves were open and pointed out that the valves should be closed due to RMA-2 being out of service. The fan was stopped and the valves were closed at 0748. Action 17 of Table 3.3-3 states that plant operation may continue provided the containment purge and exhaust valves are maintained closed. 50P-114, Section-N, Reactor Building Normal Pressure Control, lists the following statement; "RMA-2 Atmosphere Gaseous Iodine - RB sample line is in service," as an initial condition to procedure performance. Opening the valves with RMA-2 out of service constitutes operation outside the provisions of Technical Specifications.

CAUSE OF EVENT:

A non-licensed, control building operator made a personnel error by performing an evolution without consulting the governing procedure which contained the control to prevent the opening of the purge supply valves if RMA-2 is out of service.

2 ANALYSIS OF EVENT:

Radiation levels inside containment were normal and remained steady during the three

j. minutes the valves were open. Also, due to this event involving only the Reactor l Building supply portion of the system, no release of Reactor Building Atmosphere occurred. Therefore, this event resulted in no safety consequences.

4 IMMEDIATE CORRECTIVE ACTION:

1

The Reactor Building purge supply valves were closed as required by Technical

Specification 3.3.2.

ADDITIONAL CORRECTIVE ACTIONS:

(1) Operations management has communicated to all operations personnel the importance t

of proper procedural usage and stressed the usage level requirements defined in l Station Administrative Procedure (SAP) 123, Procedural Use and Adherence (Rev-1).

j (2) This event was included in a meeting of the Management Review Board on July 13, 1 1993, and again on July 20, 1993, to insure adequate management attention was

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given to this matter.

l PRIOR EVENTS:

J None.

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