ML20133E103

Forwards Record of Telcon Between NRC Staff & Maine Yankee Atomic Staff Re Emergency Diesel Generator on 961223-24

ML20133E103
Person / Time
Site:	Maine Yankee
Issue date:	01/07/1997
From:	Eaton R NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
TAC-M96589, NUDOCS 9701100198
Download: ML20133E103 (3)

Text

i January 7, 1997

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MEMORANDUM T0:

• File FROM: Ronald 'B. Eaton, Senior Project Manager (Original Signed By) 4 Project Directorate ~I-2 '

4 Division of Reactor Projects I/II SUBJECTi TELEPHONE CALLS BETWEEN NRC STAFF AND MAINE YANKEE ATOMIC STAFF REGARDING THE' EMERGENCY DIESEL GENERATOR (TAC NO.

M96589).

Please place the. attached record of the subject conversations which took place on December 23 and 24, 1996 on Docket file 50-309.

Docket No. 50-309

Attachment:

As stated DISTRIBUTION w/ attach.

Docket file PUBLIC PDI-3 RF Reaton DDorman ETomlinson DISTRIBUTION w/o attach, CJamerson JStolz PMcKee DOCUMENT NAME: G:\EATON\M96589.MYA Ta seceive a copy of this document. Indicate in the boa: "C" e Copy without ettechmentleylosure "E" = Copy with attachment / enclosure "N* e No copy 0FFICE PM: PD1h3 lE LA:PDIII-3 l C. D:PM JSy / l l l NAME REafgly// CJamerson ofk JSigli /F V 6 01/j/97 DATE 01///97 '

01/ 7 /97 0FFICIAL RECORD COPY l

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The post LOCA loads at Maine Yankee are calculated to be 2842 KW. These loads are applied to EDGs with the following ratings: 2597 KW continuous j duty, 2850 KW for 2000 hrs., 2950 KW for 168 hrs, and 3050 KW for 30 min.

. The EDGs at Maine Yankee should be able to handle the post LOCA loads with no i j trouble for the following reasons: (1) The load of 2842 KW will be reduced by l

280 KW at about I hr. into the accident. At that point, the loads will be within the continuous duty rating of the EDGs. One hour at the 2000 hr.

j, rating is not a concern with these EMD engines. (2) The calculated loads include approximately 100 KW for runout on the LPSI and EFW pumps. It is questionable how these pumps would get into a runout condition and, i consequently, the inclusion of this additional 100 KW is also questionable.

! (3) The loads were calculated using name plate data. These data are

, conservative: 1.e., the actual loads will be lower.

4 The above conservative values removed from the load calculations, it is very 4

likely that the post LOCA loads will be within the continuous duty rating of the EDGs. However, even if the loads remained at 2842 KW, the time at this value is not sufficient to cause any measurable degradation. Therefore, there is no safety concern.

In the attached draft, " Time After DG-1B Breaker Closed" profile, it shows a i valve of 430 KW for the decrease in load after 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, which. is significantly l' below the continuous load rating for the EDG.

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71 KU kb 3.000 168 HR RATING - 2.950 KW

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- _R_R_AT_I N_G _ _2_. 8_5 0_K_W.

-- 2. 842 KW  ? o" I

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166 KW r MANUAL LOAD SHEDDING STEP 4 2.642 KW 430 KW r-2.605 KW gp p 441 KW STEP 3 MOV OPERATION *N" E $ 5$

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2.246,KW m o 2.201 KW 37 KW DECREASE I ar- r- o MANUAL LOAD !

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SHEDDING 2.000 - 166 KW

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957 KW STEP 2

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1.118 KW 5)

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qO g 2 RANDOM LOADS 126 KW ,, ,, ,, ,, g g ,

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5 MIN *p f. ,

TIhE AFTER DG-18 BREAKER CLOSED q q g i

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