W3P84-1328, Forwards List of Subgroup Relays Not Testable During Reactor Operation But Testable During Applicable Cold Shutdown Periods.Listing Updates Re Concurrence Reached at 840426 Meeting W/Nrc

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Forwards List of Subgroup Relays Not Testable During Reactor Operation But Testable During Applicable Cold Shutdown Periods.Listing Updates Re Concurrence Reached at 840426 Meeting W/Nrc
ML20084P248
Person / Time
Site: Waterford Entergy icon.png
Issue date: 05/14/1984
From: Cook K
LOUISIANA POWER & LIGHT CO.
To: Knighton G
Office of Nuclear Reactor Regulation
References
W3P84-1328, NUDOCS 8405180062
Download: ML20084P248 (4)


Text

o LOUISIANA 142 otLAnoNoe S1 ster POWER & LIGHT P O BOX 6008. NEW ORLEANS. LOUISIANA 70174. (504) 366-2345

$iu$EysE May 14, 1984 W3P84-1328 3-A1.16.07 4

Director of Nuclear Reactor Regulation Attention:

Mr. G.W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555

SUBJECT:

Waterford SES Unit 3 Docket No. 50-382 Engineered Safety Features Actuation System (ESFAS)

Subgroup Relay Testing Meeting - 4/26/84

REFERENCE:

LP&L Letter W3P83-2273 dated July 21, 1983

Dear Sir:

On Thursday, April 26, 1984, a meeting was held with the Instrumentation and Controls Branch (ICSB) to discuss ESFAS subgroup relay testing. The above referenced letter detailed which subgroup relays could not be tested during reactor operation without adverse and unwarranted impact on plant safety and/or operability. The letter also identified which subgroup relays are tested duri'1g the semi-annual at power Channel Functional Test (Technical Specification 4.3.2.1) and clarified component actuations.

The meeting involved a step-by-step review of'the subgroup relays and resulted in ICSB's concurrence of Waterford 3's ESFAS subgroup relay test program. Please find attached a listing of subgroup relays that are not tested at power but are tested during applicable COLD SHUTDOWN periods. This listing reflects current design and updates the referenced letter as was concurred at the meeting.

Should there be any further concerns, please do not hesitate to contact us.

Yours very truly,

[

K.W. Cook Nuclear Support & Licensing Manager KWC/WW/ch Attachments cc:

E.L. Blake, W.M. Stevenson, J.T. Collins, D.M. Crutchfield, J. Wilson, k

G.L. Constable, R. Stevens, D. Hoffman 8405180062 040514 c

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ESF SUBGROUP RELAYS NOT TESTABLE DURING REACTOR OPERATION i

RELAY NO.

ACTUATED EQUIPMENT Train A Train B K 109 K 109 Trip 3A32 Station SIAS SIAS Service Transformer feeder Breaker K 202 K 202 Letdown Containment Isolation Valve 1CH-F2501 A B RCP Bleedoff Containment Isolation Valve 2CH-F1513 AB i

Fire Water Containment Isolation Valve 2FP-F129 Instrument Air Containment Isolation Valve 21A-F601 A B

- only Train A K

202 Relay N.A.

K 301 Boric Acid Tank A Gravity SIAS Feed Valve 3CH-V106 A (opens) i Boric Acid Tank B Gravity Feed Valve 3CH-V107 B (opens)

Volume Control Tank Dis-charge Valve 2CH-123 A B (shuts)

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RELAY NO.

ACTUATED EQUIPMENT Train A Train B K 305 K305 SG #1 Feedwater Isolation MSIS MSIS Valve 2FW-V823A SG #1 Main Stream Isolation Valve 2MS-V602A SG #1 Feedwater Control Valve 5FW-FM833 SG #1 Feedwater Control Bypass Valve 5FW-FM835 K 308 K 308 Letdown Stop Valve SIAS SIAS 1 CH-F1516 A B Letdown Containment Isolation Valve 1CH-F2501 AB K 313 K 313 SG #2 Feedwater Isola-MSIS MSIS tion Valve 2FW-V824 B SG #2 Main Stream Isola-tion Valve 2MS-V604 B SG #2 Feedwater Control Valve 5FW-FM834 l

l SG #2 Feedwater Control Bypass Valve 5FW-FM836 K 114 K 114 Component Cooling Water CSAS CSAS from RCP's Containment Isolation Valve 2CC-F243 A/B and 2CC-F147 A/B Component Cooling Water I

to RCP's Containment l

Isolation Valve 2CC-F146 A/B 1

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