ML20085N508

Staff Exhibit A-37,consisting of Plant Review Board Meeting Minutes

ML20085N508
Person / Time
Site:	Vogtle
Issue date:	05/17/1995
From:	GEORGIA POWER CO.
To:
References
OLA-3-A-037, OLA-3-A-37, NUDOCS 9506300223
Download: ML20085N508 (4)

Text

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VEGP PLANT REVIEW BOARD MEETING MINUTES

L66nciin -

j MEETING NO. 90-66 DATZ 5/8/90 PAG OF 2 i .

EETING CONVENED 9:15 AM/PM; IEETING AMO

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• VIA TELECON)

D gi iS3 0h2 :36 ^"/"

THIS MEETING CHAIRED BY: .

( ) C11A7RMAN (X) VICE CHAIRMAN A. rFICE OF SECRETARY L. Mosbau13CKETIE A SERVICE VOTINC NIMB G */ RESENT: J. G. Aufdenkampe J E.N$ N htzwelder I H. Handfinger M. W. Horton j PRB SECRETARY W. C. Gabbard l

NON-VOTI'G MEMBERS PRESENT: G. R. Frederick 1

1 M VOTING ALTERNATES PRESENT:

i 4 I. A. Kochery FOR R. L. LeGrand FOR 1

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NON-VOTING ALTERNATES PRESENT:

FOR FOR 1

i FOR i

i FOR FOR i

i GUESTS / TECHNICAL ADVISORS:

W. K. Smith T. E. Webb j T. V. Greene l

1 PRB ACTION ITEMS OPENED: 90-66-01 j PRB ACTION ITEMS CI4 SED: None PRB MINUTES APPROVID  : None 8 '

- N 92 PROJECT 060257 PRB SECRETARY PRS CHAIRMAN

! CC: NRC RESIDENT INSPECTOR (FORM NAME=PRBAGEND)

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• O PRB 90-66 Page 2 of 2 PRE NEETING NINUTES CONTINUATION SEEET A. The following items were unanimously recommended for approval with comment. No unreviewed safety question involved.

LER 1-90-11 " Manual Reactor Trip Due to i Inadvertant Closure of Main l Feed Regulating Valve". ) Sections D E F (Cause and j Corrective Actions) - Remove ' rsfarences to labeling and i lecking device. l l . HQIE: PRB Action Item 90-66-01 issued to T*;1p 2 Reduction Committee to re-evaluate ", rip Hazards j y and Single Point Trips (Ref. review of LER l J 1-90-11). Report results to PRB.

                                                                     " Loss of Offsite Power Leads LER l-90-6, Rev. 1

to Site Area Emergency".

}                                                                    Section D (Cause of Event)                                   -

! clarify what Comprehensive

 !                                                                   Test Program means.

I  ! ! Comment to PRB minutes of 5-8-90 by G. R. Frederick: l Do not concur that 11 diesel starts "r,ubsequent to the 1 test programa as stated in last paragraph of Section E, i page 6 of 8, for DGlA is accurate. d 'ased on the { information presented to the board start #39 completed , the program using T-ENG-90-016 which makes 11 an ) incorrect value. Without further review I would agree

. 6 successful starts were made starting on 4/6/90 at

! 2347. 1 1 1 i i 4 l l 1 j 92 PROJECT C80258 i .- . _ . . . - - . . . - . . . . . . . - . . . . - - . - - - . - . . . . . . - . - - . - . . . . - . . . .

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                  '""-""" ! **'"* '" "*90E ft2 ??WJ% S E R V I C E N         g b            During the NbIkent test run of the DG on 3-30-90, one of the                                                                                                                                 a dq4             C             switches (TS-19111) tripped and would not reset. This appeared to be an intermittent fatlure. humu .it. subsequently mechanically reset.

1.g . 0% ( This switch and the leaking switch (T5-19112) were replaced with new [yl i:: N, 4 g 4 switches. All subsequent testing was conducted with no additional e problems. i sh E

                               ,     hi           A test of the jacket water system temperature transient during engine starts was conducted. The purpose of this test was to determine the i          4 s g 5            actual jacket water temperature at the switch locations with the engine e?

y$% in a nor341 standby lineup, and then followed by a series of starts o .g 'r without air rolling the engine to replicate the starts of 3-20-90. The test showed that jacket water temperature at the switch location j Ya q 3 decreased from a standby temperature of 163 degrees F to approximately jg 156 degrees F and remained steady. Numerous sensor talibrations ,(including jacket water temperatures), special pneumatic leak testing, and mu' tiple engine starts and runs j were performed under various _condi After the 3-20-90 event, the

           ,                 k               J:ontrol systems of both engines 5:g!qs._r subjected to a comprehensive                                                               .

test progrant Subsequent to this test program, DGIA and DG18 have been startedtt M3 lt tir :::5 and no failures or problems have sfAsie. occurred during any of these starts. t. :ffitw 4n undervoltage . W ed start test without air rollawas conducted on 4-6-90 and DGIA started i and loaded properly. Ls4h4

                    'n h.es coch Ghr. 4 as-so)                                                                                                                            .

Based on the above factri it is concluded that the jacket water high j temperature switches were the most probable cause of both trips on j 34 W .

E. ANALYSl r W DfT l

i The loss of offsite power to Class IE bus 18A03 and the failure of DGIA to

start and operate successfully, coupled with DG18 and RAT 18 being out of

! service for maintenance, resulted in Unit I being without AC power to both j Class IE busses. With both Class 1E busses deenergized, the RHR Systes , ! could not perform its required safety function. Based on a noted rate of l

rise in the RCS temperature of 46 degrees F in 36 minutues, the RCS water

would not have been expected to begin boiling until approximately I how and j 36 minutes a'fter the beginning of the event.

                                                                                                                                                                        .a Restoration of RHR and closure .of the containment equipment hatch were completed well within the estimated 'I hour and 36 minutes for the projected
                  <'                    onset of boiling tir the RCS'.'- A-review of information obtained from the Process and Efr i                                        analysis indicated                                                     uent                allRadiation       normal values. Monitoring      System As a result   of (PERMS)is th                   event, noand grab         -

l increase in radioactive releases to either the containment or the ! enyironnent occurred..  ; 94 - j ' -g 92 PRCMECT 057503 l o i

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