ML20148N728

Special Rept SR-97-002-00:on 970513,personnel Identified Design Discrepancy for 'B' CCW Train Radiation Monitor. Design Flaw Existed Since Plant Built.Design Change DC-3537 Approved to Reroute Cooling Water Line from Connection

ML20148N728
Person / Time
Site:	Waterford
Issue date:	06/26/1997
From:	Leonard T ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
SR-97-002-00, SR-97-2, W3F1-97-0174, W3F1-97-174, NUDOCS 9706300071
Download: ML20148N728 (4)

Text

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• A O Ent:rgy Operati:ns, Inc.

PO Box B Kiitona. LA 70066-0751 Tel 504 464 3120 T.R. "Ted* Leonard STni$NOT waterford 3 '

W3F1-97-0174 A4.05 PR June 26,1997 U.S. Nuclear Regulatory Commission Attn: Document Control Desk

, Washington, D.C. 20555

Subject:

Waterford 3 SES Docket No. 50-382 License No. NPF-38  :

Reporting of Special Report Gentlemen:

Attached is Special Report SR-97-002-00 for Waterford Steam Electric Station Unit

3. This report provides details of a radiation monitoring instrument having been inoperable for greater than 30 days. This condition is being reported pursuant to Technical Specification Limiting Condition for Operation 3.3.3.1.

Very truly yours, T  !

T.R. Leonard General Manager A19 Plant Operations TRL/JWC/tjs llll0l!!!!!!!!!)$l)lll)$fllllll

, Attachment cc: JE.W. Merschoff (NRC Region IV)l C.P. Patel (NRC-NRR),

A.L. Garibaldi, J.T. Wheelock 'INPO Records Center, J. Smith, N.S. Reynolds, NRC Resident inspectors Office, Administrator - LRPD 9706300071 970626 DR ADOCK 050003 2

," Attachmsnt l W3F1-97-0174 Page 1 of 3 SPECIAL REPORT (SR) 97-00240 RADIATION MONITORING INSTRUMENT ,

! INOPERABLE GREATER THAN 30 DAYS Reportable Occurrence Technical Specification (TS) Limiting Condition for Operation (LCO) 3.3.3.1

" RADIATION MONITORING INSTRUMENTATION" requires that with one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.

l.. The ACTION for Component Cooling Water (CCW) monitors A and B allows for i

continued operation for up to 30 days provided grab samples are taken once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The TS

- further states that if the monitor is not restored to OPERABLE status within 30 days after the failure, continue sampling and prepare and submit a Special Report pursuant to TS 6.9.2 within 14 days. This Special Report is being submitted due to

' CCW monitor 'B' being inoperable for greater than 30 days as of June 12,1997. .

Initial Conditions i

At the time of the discovery, Waterford 3 was in Mode 6, Cold Shutdown, conducting I Refueling Outage 8 activities. Technical Specification LCO 3.3.3.1 was entered May )

13,1997 due to CCW monitor 'B' having been isolated and declared inoperable.

Event Descriptig On May 13,1997, Waten'ord 3 Engineering personnel identified a design )

discrepancy for the 'B' CCW train radiation monitor. The location of the tap for the cooling water to the sample heat exchanger is such that cooling water would be

- isolated by certain accider t actuation signals. Furthermore, a pathway for cross-connection would exist after different actuation signals.

Waterford 3 design provides for two redundant trains of CCW for removing essential and non-essential heat loads from the plant. The two trains are separated by a l header with two isolation valves, CC-200A and CC-200B. Each train has a radiation  ;

monitor designed to detect leakage during normal operation, anticipated operational-occurrences, and certain accident conditions from those components that are cooled by CCW and contain radioactivity. During these conditions the two isolation valves are open, allowing cross flow between the trains. A surge tank with a compartment for each train is provided for level fluctuations and for pump head.

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'Attachm:nt W3F1-97-0174 4

Page 2 of 3 l e .

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' Upon a Safety Injection Actuation Signal (SlAS)in response to a loss of reactor coolant (LOCA) or main steam line break (MSLB) accident, the CC-200B valve a closes to isolate the two trains while allowing continued cooling of some non-I essential heat loads. Upon a Containment Spray Actuation Signal (CSAS)in 4'

conjunction with an SIAS, both CC-200A and CC-200B valves close to isolate the j two trains and to shed all non-essential heat loads.

The limit for the monitors' sample temperature is 130 degrees F. The tap for the l cooling water for the 'A' monitor sample heat exchanger is located outside CC-200A l j

.val ve and is therefore neither isolated nor cross-connected with the 'B' train when i

either or both header isolation valves are closed. However, the tap for the 'B' ,

i monitor cooling water is between the two header isolation valves. This location l provides the path for cross-connection from the 'A' train to the 'B' train when CC- l l 200B closes with an SIAS only, it is also isolated from flow when both CC-200A and {

[ CC-200B close with a CSAS in conjunction with an SIAS. l When this limitation was discovered, Waterford 3 Operations personnel l conservatively declared the 'B' monitor inoperable and isolated it to prevent any cross-connection potential. As required by TS 3.3.3.1, Table 3.3-6, ACTION 28, Chemistry personnel began taking grab samples of CCW once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and ,

analyzing them for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. '

Causal Factors This design flaw has existed since the plant was built. It cannot be determined with certainty if there was a reason for this apparent oversight because of the lapse of time and personnelinvolved.

Corrective Measures To restore CCW radiation monitor 'B' to operable status, design change DC-3537 has been approved to reroute the cooling water line from its current connection point between the CC-200A and CC-200B header valves to the 'B' train side of the CC-200B valve (similar to the current train 'A' configuration). Continuation of modification work related to DC-3537 after June 12,1997 has resulted in radiation monitor 'B' remaining inoperable beyond 30 days, resulting in the requirement for this Special Report in accordance with TS 3.3.3.1, Table 3.3-6, ACTION 28. i Required grab samples from the CCW will continue to be taken by Chemistry personnel while testing and visual examination is completed in accordance with flow j requirements. After completion of required testing, CCW radiation monitor 'B' will be i returned to operable status. j 1

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Att:chmsnt l' W3F1-97-0174 Page 3 of 3

! Safety Significance The CCW radiation monitors provide no safety function under accident conditions.

1 The Waterford 3 Safety Analysis Report and the TS list them as process monitors.

Their monitoring function is not taken credit for in post-LOCA/MSLB safety analyses nor do they directly control the release of radioactive material. Their isolation under

- these conditions is not significant.

l The concern with cross-connection is the loss of cooling water from the 'A' train through the CC-200A header valve and the 'B' monitor sample cooling line to the 'B' train. A low water level in the CCW surge tank is indicative of a leak in the system and interlocks isolate the two CCW trains and line up the pumps for the healthy train.

4 Therefore a cross-connection would result in isolation, which, as described above, is i not significant under accident conditions.

1 While the monitors provide no safety function, their continued reliable operation

} under all conditions is desirable. Therefore the modification described above was.

i implemented.for this purpose.

Similar Events A review of Waterford 3 Licensee Event Reports submitted since 1995 identified no E

similar instances where a design discrepancy could cause a cross-connection l between trains and/or an isolation of a component.

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