ML20235U343
| ML20235U343 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/20/1987 |
| From: | Bowling M, Harrell E, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20235U321 | List: |
| References | |
| FOIA-87-461 NUDOCS 8710140044 | |
| Download: ML20235U343 (49) | |
Text
{{#Wiki_filter:_ - _ _ _ _ - _ _ _ - - _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - t*. 't $kjt J%' E,,%ogen, -Q VIRGINI A POWER NORTH ANNA POWER STATION
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, EMERGENCY PROCEDURE rs j .y; .i,,N umber, Procedure Title Revm on
$ kt' " 1,00
, , '1 ES-3.1 ,
POST-SGTR C00LDOWN Page
. USING BACKFILL i
r Oi ti. (WITH NO ATTACHMENTS) 1 of 6 _,,,, f, r 7' Purpose c To provide guidance for operations personnel to cooldown and depressurize the RCS to CSD conditions following a SGTR. This recovery method deprespurizes the ruptured SG(s) by draining through the ruptured SG(s) tube (s) 'into the + l
. RCS. -.
J . User . p nv ut.Q
, NAPS Operations Personnel DOCUMENT l , :, c G$l .: - '
Entry Conditions l
's Ny;gssARILY T5 b -
TEST REVt@ON This procedure is entered from: l 1)Y1-EP-3, . STEAM GENERATOR TUBE RUPTURE, or i r -
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a
- 2) 1-ES .l.2, POST-SGTR COOLDOWN USING BLOWDOWN,', '*"
*ac rr.orty of
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' ccr.!..alned in tilic J Mument SAE Y REATED: l j- 8710140044 871000 5
PDR FOIA BAUMANB7-461 PDR Revision Record E '6
, KREV. 1.01 PAGES (S): 2&5 DATE: 06-12-87 fu. 'NJ
.; REV. PAGES(S): DATE:
sr.57" REV. PAGES(S): DATE: SI4"D~95 iliy.If '/- REY. PAGES(S): DATE: f . - REV. PAGES(S): DATE: g/jY
.'? 'c REV. PAGES(S): DATE:
Approval Recommended Approved Date U h Yj Chairman Station Nuclear Safety 06-12-87 h and Operating Committee
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_ . . . FOLDOUT FOR EP-3 AND ES-3 PROCEDURES - f f;, .ww. . (, g rg. vo,'
.n l'.2.i IFREINITIATION CRITERIA ll Itally operate.. Charging /SI pumps and align BIT as required and GO TO
.ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBC00 LED RECOVERT DESIRED,
,y, ,
.p.. Step J,, if either condition listed below occurs:
. .x
- RCS subcooling based on Core Exit TCs - LESS TRAN 30*F [80'F).
4
~
OR '. i i ,
- PRZR level - CANNOT BE MAINTAINED GREATER THAN 15% [50%). .
a *
- 2. . RED PATH
SUMMARY
f -l.. a) SUBCRITICALITY - Nuclear power greater than 5% b) CORE COOLIN,G - Core Fa:it TCs greater than 1200'F ,
. i 'I ! OR ..
g .. . r . f ; , Core E: tit TCs greater than 700*F AND RVLIS full range j- -
' T '. , less than 46% with no RCPs running #s
? I c) HEAT SINK - Narrow Range level in all SGs less than 10% [32%) AND total feedwater flow less than 340 gpm V l
[ l!.
; d) INTEGRITY - Cold leg temperature decrease greater than 100*F in last
( ,' 60 minutes AND RCS cold leg temperature less than 285'F
; e) CONTAINMENT - Containment pressure greater than 60 FSIA
- l. !
{~l 3. SECONDARY INTEGRITY CRITERIA l^ ' , , 50 'TO EP-2, FAULTED STEAM GENERATOR ISOLATION, Step J,, if any SG pressure
!- Q/ .3".is*
.- df;N, 'and has decreasing not been in an uncontrolled isolated, manner unless needed or cooldown.
for RCS has completely depressurized, N ' l ... ..
. '. b COLD LEG RECIRCULATION SWITCHOVER CRITERION
. GO TO ES-1,3, TRANSFER TO C07.D LEG RECIRCULATION, Step J_, if RWST level i
I. ,
.. decreases to les.s than 29%.
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- f
- 5. ECST LEVEL CRITERIA
' Nake-up to the ECST from the CST or provide alternate sources for AFW l1 ,,,,. suction (SW or FP) when ECST level decreases to 40%.
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c , 2 .,_ , l}' ml;NUMBER , t..l PROCEDURE TITLE Reft 5fN'
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r '; ,, ci'. 1-ES-3.1 t. . 'P%tMGTN COOLDCV ' PA05 y :i,f,J , h* s
'USINGBACKFILL[ -2 of 6-3..a Db .
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,.l't _ STEF . AI,5UN/;XPSCT&u RESPONSE RESPONSE NOT OBTAINED (c .. .. y -
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x'* N,0TE : Setpointsinbreckets[]are.foradversecontginment
'y s, atmcephere (M psia containment pressure or 10 R/HR
! containment radiation.)
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- 3. - TURN ON PRZR HEN /ERS AS j 2 I
NECESSARY TO SATURATE PRZR
.3: ' WATER AT RUPTURED SG(s)
\/
.?RESSURE 4
T 2 .' CHECK IF SI ACCUMULdCRS " i SHOULD BE UCC.ATED:. ,: -
. l E \
. ' a)' Check the following: , a) JF, either conditionpjil l
<7s. 3 f , satisfied, TftEN, CO TO ,
3.F
$ C RCS subc.coling b'ased '
1-ECA-3.1, SGTR VITE LOSS a
onCoreExitTCi*\'i 0F REACTOR COOLANT i SUB-n'OREATF3 THAN 30% \l30*F] COOLED RECOVERY DESIRU), l
[ s !* . 1
' Step 1. l
- PRZR level-GREATER !
'?!HAN 15% [50%]
\\
b) 'Ac'cumulator discharge b) Restore power to discharge NOVs -(ENERGIZh.D MOVs.
' s )) !
3 c) CIVse alf; SI accumulator c) Vent any accumulator that' dia'thar3e MOVs can NOT be isolated as per l y 1-OP-7.3. ' s 3. VERIFY ADEQUATE SHUTDOWN t MARGIN AS PER 1-PT-10: ' i a) y Sample ruptured SGfs)
.,1
b){ \ Sample RCS T c) Shutdown Margin-c) Borate as required.
d ,/
, f ADEQUATE ,
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pee, etserst) - t g_ Y r*: .' gygggy PROCEDURE TITLE REVISION pq _ 1.00
'M I1-ES-3.1 POST-SGTR C00LDOWN' pADE
', : -USING BACKFILL 3 of 6-h' n . . 1 .. STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED $.~!): t ., is l. 9 .
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~
s 3 . ;. L't., ! . CAUTION: Alternate water sources (CST or 1-AP-22.7) to prevent loss of AFW pump suction pressure will be necessary if.ECST decreases to 40%. - I.'
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[. Y CHECK INTACT SG(s) LEVEL:
~
a) Narrow Range level - a) Maintain total feed flow GREATER THAN 10% [32%] greater than 340 gpm until
' NR icvel 1n at least one SG is greater than 10% [32%).
, b) Control feed flow to b) IF NR level 1% any ,
r maintain Narrow Range intact SG continues.,to level between increase in an uncontrolled 10% (32%) and 50% manner, THE_N GO TO 1-EP-3, STEAM GENERATOR TUBE RUPTURE, Step 1,. NOTE: Since ruptured SG(s) may continue to depressurite to less than the minimum RCS pressure required for RCP operation, cooldown to CSD should be completed as quiekly as possible within Tech Spec cooldown restrictions.
- 5. INITIATE RCS COOLDOWN TO COLD SHUTDOWN:
. a) Maintain cooldown rate in RCS cold Icgs - LESS TRAN 100*F/HR b) Use RHR system if in service j (STEP 5 CONTINUED ON NEXT PAGE)
M.: pe.. w est:13 . { . .. - {. . . - NUMBEM PROCEDURE TITLE. REVISION 1.00 1-ES-3.1 POST-SGTR C00LDOWN PAGE USING BACKFILL 4 of 6
)
(: - STEP ACTION / EXPECTED RESPONSE RESPONSENOTORTAINED >, 5. INITIATE RCS COOLDOWN TO COLD SHUTDOWN: (CONTINUED) c) Dump steam to c) Manually or locally dump condenser from intact steam from intact SG(s): SG(s)
- SG PORV(s) ". !
[ :. 9A Decay heat release valve. , IF no intact SG available, THEN perform the following: Use faulted SG , i J 9R f l GO TO 1-ECA-3.1, SGTR J WITH LOSS OF REACTOR l COOLANT - SUBC00 LED { RECOVERY DESIRED, Step ,1,. .-
- 6. CHECK RUPTURED SG(s) Refill ruptured SG to NARROW RANGE LEVEL - 75% [60%] using feed flow.
GREATER THAN 10% [32%) IF either of the following occurs, THEN stop feed flow to the ruptured SG: Ruptured SG pressure I, decreases in an : uncontrolled smanner I p_R i i Ruptured SG pressure i increases to 1000 psig. I i Y
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!{ ' ' -NUMBEM PROCEDURE TITLE
}.. RE ISfN
, ~.
f ES-3.1: POST-SGTR C00LDOWN MGE I
; .USING BACKFILL --5 of 6 I 1 j t
y
-(
. 1 S:' ~ STEP I ACTION / EXPECTED RESPONSE .. RESPONSENOTO8TAINED 1-)
,7.
1* ' . CONTROL RCS MAKEUP FLOW- {A TO. MAINTAIN.PRZR LEVEL:
'a) PRZR level.- GREATER 's)? Increase RCS makeup flow as
[l1 i THAN 30%.[55%) required. . GO TO.'4tep 8_. - b b) PRZR level LESS b) . Decrease RCS makeup flow as - gj, t; THAN 70% [65%)' required. GO T0,8tep 9_.. O T NOTE: The upper head region may void during RCS depressurization-if
, RCPa are not running. This may result in a rapidly ~ increasingly PRZR level.
~~"
- Si. DEPRESSURIZE RCS TO BACK -
.. : FILL FROM RUPTURED SG(s):-
s , a) . :Use normal PRZR spray IF letdown in service THEN
<D' ' a)
He auxiliary spray.),E NOT, THEN use one PRZR-PORV. b) Turn on PRZR heaters as necessary c) Maintain RCS subcooling based on Core Exit TCs - GREATER THAN 30 'F [80 *F]
- 9. CHECK IF RHR CAN BE PLACED IN~ SERVICE: \
I a) Check the following: a) GO TO Step 0 1,0,. ;
- RCS WR T 1 LESSTHAN350'F 1 4
- RCS pressure -
LESS THAN 400 PSIG J {225 PSIG) b) Place RER in service g as per 1-OP-14.1 I
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NUMBER PROCEDURE TITLE REVISION . , ,:, 1.00 ! t .,
- I 1-ES-3.1
~'
' POST-SGTR C00LDOWN l{
USING BACKFILL 6 of 6 f.!
?
>L - STEP ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED
- j,'1 l7 -
T 10. CHECK IF RCPs MUST BE STOPPED: ? .- .
$. a)' Monitor.the following: a) _
GO TO Step H. } - Number .' seal differ- -
- p. ential pressure -
. ' LESS THAN 210. PSID
(. . _OR
- j. Number 1 seal leakoff '
flow - LESS THAN 0.3'GPP
, b) Stop affected RCP(s)
I
- s. ,
- 11. CHECK RCS WR T -
Return to Step 3. LESS '111AN 200'h
- 12. EVALUATE LONG TERM PLANT. STATUS:
i a) Maintain cold shutdown b) Consult TSC personnel M END
- V I
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.. NORTH ANNA POWER ST
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.x. ,A.u;. , O S y REACTOR TR.I? OR SAFL ~ INJEF d' i M ' /rX f-f f. b j q'"'.y ; ~G . ..
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i g 'ACil0,$ EXPECTED RESPONSE -- ~ $ RESFCNSEN0iCBT,bi f fD.R4f&
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OTE:. .' Bra 'eted [ ] numbers show imm diste a'ction' tI ' '* l NOTE:l'
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.. M Q 4 .7 ime 7.' Satpgintsinbrackets[]are'foradverse$
at=osphers (20 psia containment?pressuYe4 cent ' a conO1nment radiation). . ! 4 J.- ) M5tfALLY ' IP REACTOR *: : .,
) Ope och reactor trip breakers ? ., .. "h
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$Yb' N %&$$
L' - 5' -
. b) Verify reactor - TRIPPED 4...' b'")' ' 'G0 TO'l-FRP-5.1.T RESPONSE
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6 g 3 TO$ NUCLEAR Po d ?
;V; ' - GENERATION /ATWS .'6t'
- Rgetor trip and bypass '
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' T /. ' bhakers-OPEN l, "
/II
- N(utron Flux - 'j . .'JM H #
- ., DECREASING TO LESS T
.- TRAN 5%.
MANUALLT& TRIP TUPJINE:
$ 3 N:,5 }
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.; Deprgse both turbin'e trip -
pushbuttons 92 -
'
- Verify all turbine stop 7 ;~P ace" s val's - CLOSED g , _P-T-L d-F... IFftur ' et
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W .tripp~ed $THEN nuall
,',t ,hT',IFAturbinacan i f runbackj'turb[ NO -
'U t .* -runbackKTHEN' se.MSTV -
- i and! b*y'p*as
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's,. C1, rehe$ter inlet valves .). .i gy by depressing reset -lg
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4:- a . 7.- we sE , VERIFY POWER TO AC '
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!,I QEMERGENCY}* BUSSES: ... Y;( I l y '
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. 'f}) AC emergency busses - AT ate re ower '
J.E , LEAST ONE ENERGIZED ', tb$t eas _ _ _ ___ j. . y, ca E
'g f restored, 1 THEN GO'.T*, 1 ECA'O'.0, L0SS '0
$ ALL.AC.' POWER,* Step 3? % -
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"4.b) AC emergency busses - b) tog store powerjto *p p ALL ENERGIZED deenergized'AC; emergency'y* 4
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s buiI,1,. , .M' 3 i Qu^l&D-l. O ,. D.5. . ' 1,*.
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.. CHECK IF SI IS ACTUATED: Verif nonecofItheMg.5- A
,d'h .f.ollovi nditio E ' iirink
-M$
l ~7*(Charging /SI pumps - RUNNING
. haveToccur c ed:, 5,,,, , j
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'I;* LHSI pumps - RUNNING Emergency Diesel Generators -
~ .' 41kIf % .
Low PRZRpressu e j '[' 'g f '. , i t '
' RUNNING .
HighlEentairIneE ressure .,.
- Any SI First-Out Annunciator 1 Steaml'ini fd 'tTal "'
tLIT -> . pressiuii. . High team ov:. ,
- 1. Tavg r... v
'p*High s team. f.1
- s. team: % ressur 7 .g., g .
[' h ~ f-1 I'requ 5 ,.THEN q ~ 34 / Step]5.4
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IF NOT requ THEN GO.TO . L
'9 MCTO RESPONSE; l
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, PROCEDURE TITLE gr ;.
REACTOR TRIP OR SAFETY INJECTIO ,, Y ' h., (3,, , ga- f CE' '; hp g $ kh DN@ ! n 1 z P ACTION /EXPECTE0 RESPONSE RESPONSEN0TORJfiNEQMJ
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0 f..~.?).s.;lc..N,Q $ n . 2 ' MANUALLY INITIATE BOTH . hD,f' A ' d
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, TRAINS OF SI c..- ..
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's CHECK CHARCING/SI , C i. .r -
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,ggP,UMPALIGNMENT: ,
, c; '
, (f l a) RWST Suction - OPEN a) /'
's '
Manuallyopen.valfes.N-3 W 44 *
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- MOV-1115B "i %.l'j I;g[,..
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- MOV-1115D
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, . ;;b) VCT Suction - CLOSED b) Maisally close'valv7es!-hl .. .,.
- MOV-11150 -
f /' 1., *
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- MOV-1115E ' i
~
iv, f ,, J. 4I' I(A ,';, i c) Normal charging - CLOSED c)
,gT- .
Manually closa"jalves. A, V 1,,5.' If([ .f
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- M07-1289A i .m -
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- MOV-1289B b -
'N DM: '"* d4-V,"f.i ~ '
{,' g d) , Letdown isolation - CLOSED 'd) Manua y,.close a ves. Ef 3 -
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[f*HCV-1200A'
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. PROCEDURE TITl,EM t iREVISION.
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E REACTOR TRIP OR SAFETY INJE O - e. f.)@@lti.M
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.;, ACTION / EXPECTED RESPONSE RESP,0NSE NOTCI]LINE0 ?&
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-VERIFY CHARGING /SI FLOW: ' 7; M
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" a) Two Charging /SI pumps - a) Manually s: art' ppmps. ' ?',' .,
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't,',- RUNNING 0 . h. ' -
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g
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j 4^ valves:
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- MOV-1867C t-J' L l' .* MOV-1867D -
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?.N 3)Q,7 Open BIT inlet valves:l-{6. .
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g
..... e
*INdV-1.87K I i t' MOV 4 . .
. ,,, f 7
'~ IFY FW ISOLATION: W: '\ . .
~. 'yk S& y. . ,
in FW flow control ' N M'anu'allyeclose a ves
.. iilyas - CLOSED !'4 ,WiV + i. y s
.y )@ :,-;e(. ; . ..,j
'T - gh.
FW
, y# p y, isolation MOVs - CLOSED
- Manualif.,close~,.valves. u , .>-
f. { . 'IQ.
- n' %.
Main FW pumps - TRIPPED
- Manually, trip pumps. g *
.g y
;.{,- - , g' t
- Bypass flow control valves -
- Manually cloagalves. , .,. ,
r 3, : CLOSED 4* ~ A. 6 ..~r - -
- . f.'%
10 -.. . ; ,.
- ,g *..E-T-LStandby Main FW pump (s) in -
- Place in.P-T-L 7*,'nM . ., .
..r . - , .. v -
' .,,;. s .
.My,& >,a "., c. t 1
%:'id ' : r~4 .
,,. w..., :{ z.
.?. .
. ..v..a .. .
.. .f.
- .. g ,. 7, g h N P
.,J h.- .
i'
\
.n. . . _ - ,
.. 4 4
~
.9 PROCEDURE TITLE 4*? .
U. ;' ..r
>>< T REACTOR TRIP OR SAFETT INJE' Tge$fRg@.y ~ '
* * .s ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED . fi, eq-g(,, - . .,
.t; ;
, f' e ..
-Q
- 3. .
s ,a r -
' ' VERIFY AFW PUMPS - RUNNING: .'-
((a)
- g. .
Motor-driven AFW a) Manu' ally start pumps.- ff, 5
- m. .,;
pumps - RUNNING .
.'L.,,., ,.g...., y
.t.
ye-c. : tu ,. a, u, . . . , . , 5 .,.
.b)- Turbine-driven AFW pump - b) Man:u..r <aii en: steam supply. *g 46 RUNNING , . ,.,v .
' r. ..
Yh[(.' re
. VERIFY CONTAINMENT ISOLATION , .i 77'. PHASE A: .E ' e.A.
t' ,1
.\ .:,.sgeY .z.'.A a: 1, -
>% a) Phase A - ACTUATED 'a) -Man (,ually initiat'.bo _
e . [ 4, tra' ins ' of . Phas("A. lid 7 ' ' .- G mm f.. . . - :. 9." -lt s . ,
..i' b) Initiate Attachment 2 sO * '
l- *
~.
I '.,) VERIFY LHSI PUMPS STATUS: #
- vr. .
l
., j 4..,. a) Two LHSI pumps - RUNNING a) Manually start. pumps.
. !M.: -W2,v:2: 4'+- f ?. ,h . .. j F b) RCS pressure - LESS THAN b) GO,TO Step 12.'* , . n.
O 175 PSIG ' . c7 6 ,-
,, f {
$8.:F
Q,c p) LHSI pump flov - INDICATED c nua ly'op HSI val'ves ' J. -
') ' ,i $ )*,v w. h7 MAfe] %4' * . ]
[~ '
- FI-1945
- FI-1946 N* ", .*W~r.MOVc .1864A'
[,;r.! M *.- A~~ I
- MOV-1864B' - j e ; .. **' *.
- MOV01890Cp
- MOV-1890D w '.S*:
[/
%;y; { & .
. VERIFY SERVICE WATER PUMPS - Manually sta'rt'. pumps.as aY
';, RUNNING: required. q, .
.. . 3 ,,
?'y
i*.'
- 1-SW-P-1A - RUNNING i v ,> p E , .
~. .i ),L i e.s . . .. p. '
' '. k s i, ' 0,,, R
.jg;a ,
,y,g;f_;, . }} ,
.' 1-SW-P RUNNING . . 4r
- 1-SW-P-1B - RUNNING ',.~:-
. :. .N . . 3 r; . ., ~ .N 1.
.s
- x. . -
1 ; *
- g. . ; p- .
1 .:, , ' l _ - _ _ J
r-
. . - . . . . = . .
_:n... o
,s ,:, PROCEDURE TITLE .
pr REACTOR TRIP OR SAFETY.INJECTI .
- ?- .- f ,
i g- a
.a - s
' o.5{'
? 'ty S , ,s.4 .a "R.
ACTION / EXPECTED RESPONSE RESP 0 HSE NOT08TAINED ' , ~'
*T,.1
. "' 5'
..- e. ,
N - [.'.eI
~.
- g. ,g' {.
";y r i, : J.
ECK IF MAIN.STEAMLINES ., <
, . n.f- -
,.,- f 4
SHOULD BE ISOLATED: .
.g dy f f.9.
s -. . . , ' . , '- [&% , :
. L.,
' ' ' g..
f Annunciator 2D-E3 - , a) GO TO Step 14'. .,. , 7 LIT ^
;. r
~ .
O
@f' s b) , Verify MSTVs and pg. .. .- ,. . 6 b) Manually cibsevalvess - -
y'e bypass valves - CLOSED ,V'; W ~3 .
-;',[.~ 4 [1
,~ .- 4.. s r. ,
.)k CHECK CONTAINMENT PRESSURE: Wi r.N '
M- ' F..
- .Y'.
+ >. . .'9.. . 1*C.'.'. ',t - -
Containment pressure - .a) Perfor.n the following: I ;- '
'J'
' k. h. a) HAS REMAINED LESS THAN
.A.M. ,
) ' -
'h. i
.J W 28 PSIA ON P-LM-110B .., 's:n'all ctu. ate BOTH D <
21
.:, . trains o quenth ' ' '
,-f ,% ' spray. , c;.4 - p. cl.
W v ,
+ :.:-:'/ t. N f' 2) ;'i,,Initisie?;Atitachment. I.Q 1,~}
f . Q)p* ~'r '
.t,
. . .~
1.bg
,.ff-
- c. 3)p: Terify CCW pumps
'I ^ ', ' ' "
W1.. tripped. r. 'a - , f4 r-
,;q.
l'* : * ';%k 9 T,: X' . l 4)i Stop alf'.RCPs. J,
>. - s
},
, . . w . .4 , .
u..;':.< n'; ,- . 7T
' '.WMN - i.- i Mb) Containment pressure - . b)
VeY1"f7MSTVs :[ pass M EAS REMAINED LESS THAN vaiv'es' clos'~ed,fIF NOT L. Ei? 4.
- gj?yW,
'- 17.8 PSIA ON P-LM-110B THEN manually 'close valves."j s '[ s , s
.. ,' , l. t
,e * *
.v ,
,n r .
.'hhl. 4,k~ I**
. .y y-
, , ., . .* ;di. -
y i ":" ' ' .; *--
]j' & '
'.,. I' A ,_
- (./:,' *4:.%
.- #j
.., , s.. >
.i.... . . , . .. .-
,y* <
.i.,'
+ ".. -
f
.gy*
A.-
+
f ' I
f. 4. e . t _. PROCEDURE.TITLE i.: .. Y Q'u. '- C ~ 7^~ REVis10N}MM ^ pl$00
- E'.'
REACTOR TRIP OR SAFETY INJECTIO e, s .- - i
- f. f*' ! AGE .', y i
$d:,_ gp,8 of 16 M
.g. .'
g.. -
-y; '" - , ;y .)
' ACTION / EXPECTED RESPONSE RESPONSENOTCDTAINEO
. g Q~*
~
n, - . J. y
'j e. r
- 3. ,
'. VERIFY AFW FLOW: 9 M . . .; ?.' 7'..
< ..:
- h' 'h.': .'{.W' '
7 ga) AFW flow - INDICATED a) Handally, sligg',p . valves3-ed,9 ? 4 . .. ,"
- N,"
1r .gs - E- K+
- FI-FW-100A '4 s : 7@D
..OR*u s
~
h '; 4 h.9ks~
-'
- FI-FW-100B .
"rd .-.I
j!.
- FI-FW-100C Maridally st,ai,t pumps, 1 L.
f h.L .
'y:/. . b) Verify total ' flow - b)
IF SC UR level' greater y rW - -
-4f W 3
\
GREATER THAN 340 GPM than 10% [32%) in any- SG, .}.*e'.'.
..J f@.d THEN control fepd flov'to F )J:j h' .'.
TF maintain NR level?- ;.f + l E: , .;.f W _ l W ;_, . . h. gl." .;
, level'dfess than 10% .
IF ..
s J, ....i
. ' .e j
h. u..
, .]
,c g
. X , _ ., . ,
. .z. .
+
*(..,
U x .a
- p. .
9 s
, . -s
+or ,
,,. Ii
.!*g
; t
_____. e. ' i
.. = . _ --
f G,- ' PROCEDURE TITLE
' R Q if. V'.
M.'REVIS10N ) , b' ~
, .00 j-REACTOR TRIP OR SAFETY INJECTION.C,--$ dk E'~
.'h:: ' .8,. &,w PAGE p
~
. , e, 9 of 16 r 1.# ir +.'
ACTION / EXPECTED RESPONCE RESPONSENOTOBTAINED
-h&,-
1 g 5:
. f,* *
.s.
y
~ .
. . . .s ? .
tZ %% ,' ~ 4
- 7. CHECK RCS TEMPERATURE - _IF, temperature less than 547'F,'y. g.
' STABLE AT OR TRENDING TO THEN stop dumping steam.
,, ; a 6
- 547*F .
.i IF cooldown c.. ,. w ,.ontinu.e6. ' THEN:
4 ,, i t e . e ( SG NR level.is greater than" p. rl ' . 10%.[32%)'. -df" p J
~
i-. b) e IFcooldowncontinuesTH T1'oaeMSTVs'andbypass.i 7 h. di 4; s; -
' valves.V # ~ k .5 i, 2$1. f.c& ,
- ,W Q'.'
." IF temperature 9..grea
~
an 5 > 'f' 547'Fand1ncrEas'iEg{;THEN:'
.&,$t'*2f,
] t f, 7, 7
Dump steam to the co_ndenser j ', p W. ,
< i. A #- OR s
l-Mi . Du.sp ateam using SG PORVs. Ir
,b. .. J . , '
e
> /s '
ja .* 95 v
.n .
, '. : t .
g 4 %y
. ^:
.6 :. - .
0 e
.i 2 .
V .... j .v.*: ,', . _ _ . _ . , _ _ _ _ _ _ . _ _ _ _ _ _ _ - - - - - -- -- - -^
,3 -l. : '
* *n :
r PROCEDURE TITLE REVISION - 6 k. 'R a R'-{ft
~ .
1*00 l g3 ,-'
~
REACTOR TRIP OR SAFETY INJECT w ' PAGE 3- .r. : " r
. . . v-yp~,'.F - *C .. . 10 of 16 .*
.s py 4"
- r* y. >
ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED , b r
. , . =;;; -
, .. r~
y
? e y
;c- ;T '
. CHECK PRZR PORVs AND SPRAY VALVES: *
. b a) Haster controller, a) Take manual control of f M ., PC-1 444J - NOT FAILED
~
PC-1-444J. >
%r . .
.... ? -
f b) PORVs - CLOSED , b) ,IF PRZR.preEs'p((g) Ass,than - E' 2335 psig, THEN manually . D- '* PCV-1455C close PORVs..o* .- M b
- PCV-1456 . . u. .
~
.fF IF,;'any.'.PORV cad NOT be j .
?, '
4 closed, THEN ally.] . 5 d.' close its block MOV.- 3 L c-j.*~. .e .' g ,y. y . s. , el.
'e .
- i. I block % 0V can NOT be s Eos'ed," THEN Gy.'.TO 1,-EP-1, ,)
~
g,6 LOSS OF REACTOR OR y- g.. SECONDARY COOLANT, Step ~1. q;. ., ~. . r.. : ,. l- g c) PRZR spray valves - CLOSED c) IF,PR2R' F pressure ~less than 1 h a 2260 psig, THEN manually 1 9
- PCV-1455A -
close valves. 1f r; i
- PCV-1455B
. . IF valves can NOT be
- f. f .~- , Hosed. THEN stop RCP(s) 5I,i. supplyingfailedspray
~
. ,;;g -
valve (s): L: 4 ~>
' "A".RCP - PCV-1455A c ;
"C". RCP - PCV-1455B ',
, ', 4.g-
[. i *
- 9. s ' '
4, . 9 %
.\
., z. R :- . [. a.' .
%" .l e*. d%. #
4 9
'g y,, . y'.
(
.k 9"j h' ' ' _ _
i is f . 'y.
.y - .
*. PROCEDURE TITLE .&: M ,, ' REVISION M{f,'*.
E, k-F. REACTORTRIPORSAFETYINJECTIONp14 p'..,i*00 M'
*r,
,~.,n . ,,, , p, gg 7,
.;+. ...' ,
<. . it.h.Ih*! h.3.1.4 ?I 10 'I (
.a =
4 r 'o'MlW- Q )2f M f. . ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINEO t,E , ..
.g >
a
*0d M.
* * * * * *~* * * * * * * * * * * * * * * *
- a * * * * * * * * * *
- w ,
I' CAUTION: To prevent Emergency Diesel Generator overload, th ef1 or #4 PR2R heater banks should not be re-energized untif*the - .. c' * , respective Emergency Diesel Generator load'is.less7.than 2750
- L .
}-?, ,
N[J ,
* * * * * * * * * * *
- 6 m * * * * * * * * * * ** * * * * * * * *.* j g. '
?!, , E '. ?1 .
q.c
.w. e J 3 N0'TE: Loss of seal injection flow can cause RCP 's'eal - . ,
,p;. degradation. .g ;-j ' ,'y .jk" - ' ;${ '
, c \
g ..'I* CHECK IF RCPs SHOULD BE STOPPED: 4 ' a h ' >. V.,
' {
f Charging /SI pumps -
~
.2 -
a) a) GO TO Step _2,1,. ' ., f AT LEAST ONE RUNNING l (. ,'r.9;:. s ~. s kc. C
'fbj.,
; b) RCS subcooling based on b) GO TO Step g i o- r Core Exit TCs - LESS ?A .
h'i THAN 25'F (70'F) 'b'.g. f; -
- Ei,
.. c) Stop all RCPs 5
^*) gl f.,, .
- *d.*Qg.. re*********************************** '
l - rz . . . t. . , .
.,;. CAUTION: Charging /SI pump recire valve must be open . -at 2000 psig RCS s 1
- 7. pressure to prevent possible pump damage. 1 M /* ' .*************************************
Y, 1 l 4 ' . :- ,.
. l t .. '.# k ' 2 0. ' *J CHECK IF CHARGING /SI o uF. PUMP RECIRC MOV(s)
'. N SHOULD BE CLOSED:
P
< y i - a) rcd pressure - a) GO TO Step 2J1,.9
. . . LESS THAN 1275 ,.
; [1575 PSIG) .
j, C b) Close Charging /SI pump t . . n. - .
. recire MOV(s): ,
j
- MOV-1275A 1-CH-P-1A g ,e
- MOV-1275B 1-CH-P-1B
- b. ., ,
- MOV-1275C 1-CH-P-1C
.P Y ', e we
~
L'
w j 7s10 1',
- PROCEDURE TITLE ,
'r
= . "
MEVISION
.00 *.5 E,s.'! h ,
' REACTOR TRIP OR SAFETY INJECT Of 1
, lY. j# !, o.
, Q:. PAGE
. 'A.g,ke
...s i'aC.12, of 16 I
f ,f. ,,,, i W'[C . W - '*
* ~I ACTION / EXPECTED RESPONSE RESPONSE NOT087AINE0 a:/ ,f -.1
.. e u. '
_ y . r . 3.F'. lib. VERIFY NOTIFICATIONS:
,[N
( a) STA - NOTIFIED - r i C e :. , i b) EPIP - INITIATED - i.. g.., k. a "
.m CHECK THAT SGs ARE NOT FAULTED:
GO TO 1,EP ~2F
' n, , g, ".M s -
g pf,,NO SG PRESSURE DECREASING GENERATOR',' ISOLATION,, Step 1. S-
- f' Yj' r','" 'i
~ . .
IN AN UNCONTROLLED MANNER # '
?
!~ . '.
/ ,; ' '
- NO SG COMPLETELY
* $ DEPRESSURIZED
, W' -
t ,
"x' " CHECK THAT SG TCBES ARE NOT GO TO 1-EP-3, STEAM GENERATOR '
,,.. RUPTURED: TUBE RUPTURE, Step 1,.
1.' ^
"l gh"
- Condenser air ejector l'?
. "h radiation - NORMAL .
[r~- N. T p' :
+;j ly
'* SG main steamline I'[".'
~, '.
. ,5
, radiation - NORMAL h.fs , "
*; ?
s h.. - g f0 Z M ~ /* SG blowdown radiation -
.s -
-s
;y,. Qf= ~ l? NORMAL
'~* * * *
~
- 24. CHECK THAT RCS IS INTACT: GO TO 1-EP-1, LOSS OF REACTOR d[8,, '. '.t[?
OR SECONDARY COOLANT, Step 1. 3 ' .s'"
- Containment radiation -
4 NORMAL
; .,' ., 'Aj s
- Containment pressure -
C 4'/3JNORMAL u . e:+ - u si c .-
- Containment Recirculation 'n -
y' Spray sump level - NORMAL , i,.' . I..
.y).-
[ -l. *
~
'"k. 41. ,
y
* *y J. '. -. g ,
.1 - '
y .< , ; . ;._y., . -' : ~{&. s H
. ,g-M , ,?g,
- ee 'c.
[- ..
~
PROCEDURE TITLE f. :,. . .g REVISION
.gg- or,
- .00
~
.- REACTOR TRIP OR SAFETY INJECTIONg..
,? .-
.,D 3 , PAGE s.
, .g ':.*
**tb. +
13 of 16
~~ . 41 g ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINEO
)
- - CHECK IF SI CAN BE TERMINATED:
a) RCS subcooling based on a) DO,NOT STOP SI PUMPS. N' Core Exit TCs - GREATER g, THAN 30*F. GO TO Step 2J7,..;,ns 7, ,,H : ,
'k.b) Secondary heat sink: b) IFne[therIddition n - I Etisfi'ed',$fsE$6ddN'OT'STOP,j ,,
Total AFW flow t'o SGs -
- w. ..t ' - GREATER THAN 340 GPM SI PUMPS:G0;TO Step ,2],.
' .yi k?-
dd OR v .? At least one SG Narrow (.
..J . . .~ -Range level - GREATER
", TRAN 10% ,
, s- -
RCS pressure - STABLE c) DO NOT STOP SI PUMPS. g%: c) OR INCREASING GO TO Step E.,
~
4 . c& - d) PRZR level - GREATER d) DO$5TSTOP'SI/ PUMPS.
- '-%* j;i .
~
THAN 15% Try to stabi1~ii:e RCS v pressure with normal PRZR
;- spray. Retu'rn'To Step 25a.
'$ 6. GO TO 1-ES-1.1, .. .;da
' ' ~
SI TERMINATION, Step ~1
% ,- h f)7 .
,9 , 27. INITIATE MONITORING OF Monitor CSF Status Trees with T. CRITICAL SAFETY FUNCTION F-Series procedures.
,hg.
,'. STATUS TREES ON SPDS
- j r.
} "*,**************************************
yp .j n T. A l N 'CAUTION: Alternate water sources (CST or 1-AP-22.7) to prevent loss of AFW lM 1
, . g. - pump suction pressure will be necessary if ECST decreases to 40%.
!:/
***********************************e*
2 ,p. -
, .- CHECK SG LEVELS: .- ,
a I" '3,: [$U *
' a) Narrow Range level - a) Maintain total feed flow j GREATER THAN 10% greater than 340 gpm until '
,g .
NR level is greater than q u. ; 10%. .
- b. ;
j.',' - S,TEP'28 CONTINUED ON NEXT PAGE) T
I-
~
I . . ae k 3,T'. PROCEDURE TITLE REVISION
-def8EQ
. EVP - -
1.00 4 EP-0 REACTOR TRIP OR SAFETY INJECTION
)4 PAGE 1/' -
14 of 16 Y(A fgj iSTEP,( , ACTION / EXPECTED RESPONSE l RESPONSE NOTOBTAINEO
;~
D.I CHECK SG LEVELS: (CONTINUED)
~
' r~ .
b) Control feed flow to b) IF,NR F level in any.SG con- ' maintain Narrow Range tinuos to increase in an J
^
' ' 'M level between 10% uncontrolled miiinner, THEN
.- and 50% GO TO 1-EP-3,ST'EAM.GENER- > i g ATOR TUBE RUPTURE, Step ~1.
hESET SI [ % ~';g@t g N. ?
. ^
J; # 0.;.
.y RESET CONTAINMENT ISOLATION f%
[A '
. r$ . .. PHASE A AND PHASE B
,. t ~
. VERIFY CONTAINMENT Manually,open ralves.
INSTRUMENT AIR VALVES - OPEN
'. .TV-IA-102A W
-k. i . .. .. -
l
.5 TV-IA-102B ' *-..
- < ' i CHECK SECONDARY RADIATION: .+
ttI,
?. a) Reset SI and align systems i e,'s, - '.i i for sampling as required '
4'd. i .
'#! . 3.,2.; . ' '
b) Seconcary radiation- b) GO TO 1-EP-3,' - i j 'E 4 NORMAL , STEAM GENERATOR j
' g.s TUBE RUPTURE, Step J,. 1
.4
- Condenser air ejector i f .. radiation - NORMAL i
. .e . n ;. .i
- u. :_ ry. u -- i t.- g' . -
- SG main steamline
- V radiation - NORMAL
, N;
'A 1 -
- SG blowdown radiation -
,. . ..g. c- nognxt . _'; .v.
p,, ; ., n v.. o. U.
- De ' b j
s ._ M'.,A.-; c
,c
' k. .; .
1
. i, h - !
'w. j
' Ar ?.'
- _=- ,
l
~
n'
.&, #h[' . M.J. 'd
.C;
- ~ ' '
's.
PROCEDURE TITLE REVISI:M
' ~
T 1
- 0"*
w.f '.. REACTOR TRIP OR SAFETY INJECTION i' r. g 1-PAGE
.4 g, b ; ',, 15 of 16
.'%) . :** ~ T ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED c
)
l CHECK FOR OUTSIDE CONTAINMENT Evaluate fause of abnormal'
,3" INVENTORY LOSS: conditions %
IF cause is 'a loss of RCS ^
'C
/
a) Safeguard sump inventory outside conta".nment. level annunciators - THEN GO TO ,1,-ECA-1.'~ 2,,LOCA L-
.?.a .- NOT LIT OUISIDE CONTAINMENT; ' Step ~1.
, x. ~< -
. ., . r ' ' , * "E" Panel F-8 ,
* "A" Panel C-1 i g .,,g g g ,
g.p. #' '
*W . . .
;W 2
E.7 b) Safeguards radiation - '$
. Nb. NORMAL
~ m !
" \
. . 1 CHECK PRT CONDITIONS - NOPE.AL Evaluate abnormal co,nditions as -
D,./ a possible source of RCS ' a
)
,. 2nventory. loss: F/
g( Y
%,.yp ,::, b _ 5
./z ,
- Letdown relief valve
- e
- Sealvater return relief valve
,/ -
- Excess letdown relief valve
.i ' when sligned to VCT
- RER relief valve (Intersysten
.r.j LOCA).
'T re P.
m 3 r. at.. 4, u.. :.
. ..0
.. a
.g; t. l
~ . *.
\
1
'i.
W'- g . < '-
.7 2.f' d ;
i wk ,h.' . w -
.f D '
f ,, 6., P* [f UN y PROCEDURE TITLE V ' ,; Q ^ REVISION s k- .s ' 1*oo >
- REACTOR TRIP OR SAFETY INJECTION l
. ,.. k PAGE l
'((k'.h' 16 of 16
.. : d -
i.( ! _ N$* Y.'
*:5 STEP' ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 3 3, '
s #
*********************** * * * * +.,< * * * * *
, h;M -
!st
*i;
, CAUTION,: If RCS pressure decreases to less than 250 psig en the LHSI pupps must be manually restarted to supply water to t.he RCS.~-
,; @f************************Mi.-I-****.**,*'P...,
e CIECKIFLHSIPUMPSSHOULD .g g,9
, BE STOPPED: ' ' '
- 7
, ~ [. ,'
a) Check RCS pressure: h[ '
. n. .~. ,
- ,. ,. i
- 1) Pressure - GREATER 1) GO TO l-EP 1, LOSS OF ' '
. ,. THAN 250 PSIG REACTOR OR SECONDARY gg g.,.
COOLANT, Step 1. .g g.
- e ;._ .
): ,' 2) Pressure - STABLE OR *
- 2) 'GOTOSteE.3,6,a, E i p r., . , .
INCREASING b) Stop LHSI pumps and place " j I in Auto-Standby 5-CHECK IF DIESEL GENERATORS SHOULD BE STOPPED:
'j,C ,
., {
a) Verify AC emergency busses - a) Initiate 1-AP-10.1 to
< ENERGIZED BY OFFSITE POWER restore offsite power. ;
6 I db). Stop any unloaded diesel Ji - j 3 generator as per 1-0P-6.1
- '.p and/or 1-OP-6.2 {
-l:
C.bp'k, c ': J I r j l.- 37. '; ~ RETURN TO STEP -17 I n,.y , , . l
?. .{
i
',.e.
d END
- j. is op ad ~
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O .: w - A TTACHMENT TITLE k.
<. sir; .
REVISION
~
~ ^
1.00
. VERIFICATION OF C##f#I '
.- PHASE B ISOLATION c; '-
, e ., , ., 1 ef 4 T 99-i.
. . k i.,[.V5RIFTORMANUALLYPERFORM'IHEFOLLOWINGAUTOMATICOPERATIONSON"H" @ ; .! SAFEGUARDS PANEL: 6 dl* e .-- H 4'
lllps * *-
- a) Verify Phase "B" isolation valves - CLOSED (lo'c ated on the lover
, f.
4 E, q. right corner of the panel) 5; - e; ,y , j b '
'I. TRIP VALVES (TV) - CLOSED (GREEN) #', ' 'y CC- CC-CC-CC-
.ge.,y,g .,. ggy
~(,7" 105A 102A 104A-1 101A y: *
;, i.
, ' ' 'CC--
CC- ':C- CC-
*/
105B 102C 1043-1 103A y - v- . r CC- CC- CC- , 1A- .. .. .g -
'105C 102E 104C-1 102A F yae - N, q ..4; - ,.
h.j ))' Verify Quench Spray - ALIGNED AND RUNNING '
';R_UNNING (RED) OPEN (RED)
- f
- . Vt
)'-
VI
,1-QS-P-1A MOV-QS101A '
MOV-QS100A
,' ,' Verify SW - ISOLATED TO CCW HEAT EXCHANGERS CLOSED (GREEN)
.I i :F -
C
- t' MOV-SW-108A*F
'u l.
s ..
.. Verify SW - ALIGNED TO RS EXs
[ 'k '
-$,)l
'i '
hO Y. OPEN (RED) OPEN (RED) OPEN (RED) OPEN (RED) d.N - M07-SW-103A MOV-SW-103D MOV-SW-104A M07-SW-104D
- f :: '
[.f
- =
MOV-SW-101A MOV-SW-101C MOV-SW-105A M07-SW-105C
- j. .* .s e) Verify Recirc Spray - ALIGNED AND RUNNING (Note time delays)
. L:*,.:y .
- g. RUNNING (RED) RUNNING (RED) OPEN (RED)
- n. .
y ,j.
..,L.<
MOV-RS156A [ A MT(I'RS-P-1A (3k min. T.D.) 1-RS-P-2A (3 min. T.D.) MOV-RS155A
,.? ' ?: __
l
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A TTACHMENT TITLE :*- . REVISION VERIFICATION OF # .M 6
####I '
C :
' PEASE B ISOLATION '
*: A'
*. . . + - UI ( -
2 of 4
- Q . .
NT
=
- y. .
uf 2I[kERITTORMANUALLYPERFORMTHEFOLLOWINGAUTOMATICOPERATIONSON"J"
,"'*QSAFEGUARDSPANEL:
a - 7 . . .,, n. e. . 0+ ) Verify Phase "B" isolation valves - CLOSE (located on the lower l 4I ' .. . right corner of the panel) zf I
;v t
?:,l . TRIP VALVES (TV) - CLOSED (GREEN) j "; .
..t-
,,.(
e , hs ii CC- CC- CC- CC- ;; y* ...
"- 00A 102B 104A-2 101B T ,
- -[
4" ,: .: .' 4 ' - r- ;,- R.. .
'.CC- CC- CC- .CC- ' -
. G, g-4 1005 _ _ 102D 104B-2 103B :. ..
v. CC- CC- CC- IA- 4 . G. ,
.1000 102F 104C-2 102B #
..'r/ ' ') ' .
,q q: ,
[,,' Verify Quench Spray - ALIGNED AND RUNNING l' l 2 RUNNING (RED) OPEN (RED) y 1pS-P-1B MOV-QS101B
~ ' MOV-QS100B ". ,
l Q
' ' l
erify SW - ISOLATED TO CCW HEAT EXCHANGERS I r, k [+.
; CLOSED (GREEN) g.
$ i-a .y , . w.
, MOV-SW-108i , ;'
m ', .--
,- x,i <
s 2.. Verify SW - ALIGNED TO RS HXs A l'. l
,P. OPEN (RED) OPEN (RED) OPEN (RED) OPEN (RED) ,
,t ., .- g.. t
'1 N MOV-SW-103B MOV-SW-103C MOV-SW-104B MOV-SW-104C t .'.
.l
,'I,f
'i.
. MOV-SW-101B MOV-SW-101D MOV-SW-105B MOV-SW-105D 3 ; ) Verify Recire Spray - ALIGNED AND RUNNING (Note time delays),
; ' RUNNING (RED) RUNNING (RED) OPEN (RED)
N 't-
$.-[..
).v
- h. C ~,
MOV-RS156B
. g; 'a '
E. ' h l-RS-P-1B (3k min. T.D.) 1-RS-P-2B (3\ min. T.D.) MOV-RS155B hl,.<k '
~- 1
. . . . . 1 oe A*'
9' ' y,, ~ A TTACHMENT TITLE
;;? REVISION
'I"
, ,J 1.00 VERIFICATION OF F CN,NENT FHASE B ISOLATION 10'Y! ;
3 of 4 35 . C,
,4.,
,o p
- e c.
., .: . , g. g5 -
/P'? ^3. VERIFY _0_R MANUALLY PERFORM THE FOLLOWING AUTOMATIC OPERATIONS ON THE UNIT 1 VENTILATION PANEL:
y
. c y. ' .. a )
. Verify all Containment Air Recire Fans TRIPPED (AMBER) OR OFF
' ~ . "$. ..., (GREEN) ,
I[ : .
- r. .a g en.f 1-HV-F-1A
~
.,fr d 1-HV-F-1C 1-HV-F-1B 1-HV-F-1C.
,.~~
- Verify all shroud cooling fans OFF (GREEN) . . ,, Y
;43 E r
-HV-F-37A 1-HV-F-37B 1-HV-F-37C 1-HV-F-37D 1-HV-F-37E 1-HV-F-37F
;;t. ; , .
' Verify Air Cirs Emer Supply Valves - CLOSED '(GREEN)
,, CLOSED (GREEN) CLOSED (GREEN)
((. SW-TV-101A-1 SW-TV-101A-2 0 H-W , , SW-TV-101B-1 SW-TV-101B-2 2
. : Verify that the following filters - DIVERTED TO THE 10DINI FILTER
,g_.,,- ' v.
t f.
.: . jFILTER (RED) , FILTER (RE555;fr.,
, .c , .rc; A0D-HV-107A1,2,3,4 A0D-HV-107B1,2,3,4
,- s. .
A0D-HV-128-1,2,3,4 A0D-HV-128-1,2,3,4 h
."*, .~
p
. ' 4'
- 5 8n.;. e. ;-
55. s-s l
><s
- ('S pt
'7 .ij 7 35 g '
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I
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*.' ' . , A TTACHMENT TITLE - %** Y ': s - u REVIS10N! ' '
. p* -
. $.5 * .g.
.f ~, g,. : 1.00 -
. . - VERIFICATION OF a .4 -
IId##8f#I< PHASE B ISOLATION % , *I 7;$,.. 4..
~
FAGE g,
.f. , S.Wm
- 4 of 4.2' 9
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ys _ _
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'n VERIFT O_R_ MANUALLY PERFORM THE FOLLOWTNG AUTOMATIC OPERATIONS ON THE
- g. IT 1 RADIATION MONITORING PANEL: , 7
'v p . . . {. T iVerify the following sample pump's RED " Low Flow"' light - NOT LIT 1 7(Notes 2 minute Time Deley) ..
~ f)gigg,a,. --
M' .. % N'OT LIT NOT LIT NOT LIT- NOT LIT' - Q : ~. p'.f '
;. , . y.P 1-SW-P-5 1-SW-P-8 T-SV-P-6 1-SW-P-7 0 3
' ^**
a._._ . , .. , ., s . .. 2fb.';; if1 "; - "
, GIFT ,0R,MA1 WALLY PERFORM THE FOLLOWING AUTOMATIC OPERATIONS ON THE ,
j T 1 CASING COOLING PANEL LOCATED PL' HIND THE UNIT 1 BACKBOARDS: 1
. .k.Q. , W .,< - -
lw ' Verify Casing Cooling Pumps - ALIGNED AND RUNNING _ i
'?., .
"H" PANEL (left) 1 Y- ..
', OPEN (RED) OPEN (RED) RUNNING (RED) iff ', i# M' MOV-RS101B MOV-RS100A 1 PRS-P '3A - i' - .J i.
. si. M .
. j,, . "J" PANEL (Right) ~t .
c
...p*i y ..,
~-<:.. ,
..' AOPEN (RED)_ OPEN (RED) . RUNNING (RED) -.
.r.' '%
4 ' E MOV-RS101A MOV-RS100B ~1-RS-P-3B i.:,A ?'. l ky;. ),. *
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.. 6 V# #
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1 [*4 f.f A TTACHMENT TITLE :p's. AEVISION l
~ . j';.[,%
l~
-0.#7 1. 00'- I
. ~'
#f#I VERIFICATION OF PRASE A i'i ' O I
ISOLATION l v. v-k..! .s, WW5l. p .. .m . . . C' .
? -
[k l' . . VERIFY OR MANUALLY PERFORM THE FOLLOWING AUTOMATIC ~ 0PERATIONS O Y 'i , %{; ,
"B" SAFE 6UARDS PANEL:
* ? DS
- 4a -
,, CLOSED (GREEN) OPEN (RED) i
~.
' t,, fs JhdTV-1884C ,MOV-1867C , OPEN (RED) OPEN (RED)
- g4 CLOSED (GREEN) t vgy'TV-1884-A f: :d MOV-1867A MOV-SW-121A
> p.. .:, .
<.. . " . .n. . MOV-SW-122A MOV-SW-123A ".4 0FF (GREEN) CLOSED (GREEN 1.
ll 1-CV-P-3A ' MOV-1380
.; <F~ r f'? -a c T.:
s. p Trip Valve (TV) - CLOSED (GREEN) ., ' ? 'l a .':' . .
, w .nz, ..
; c CV- DA- LM- '
, . , LM- RM- SI- SS SS- S S,-
A- ) gy - 150A - 100A - 100C - 101A&C- 100A - 100A - 100A - 103A - 112A l
\
f,h!
'i
' D-CV-1500 DG-100A LM-100E VG-100A RM-100B MS-109A SS 101A
.. SS-104A
)
jh Dj SI- LM- LM- MS- TV- Tv- SS-SS- TV-k E 101 100A 1000 110A 1204A 1859 102A 106A 1519A l y[.. > SV- SV-
l -
102-1 102-2
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. ATTACHMENT TITLE c., . ' '-9 . - REV!$10N
-rr-O'.'[ Q
,f 1.00
' VERIFICATION OF PHASE A I
ISOLATION #68 y ' d, . I " +. **
? - ;.~ VERIFY OR MANUALLY PERFORM THE FOLLOWING AUTOMATIC OPERATIONS ON THE
. L.-
;; UNIT 1 5" SAFEGUARDS PANEL: ,. 1
... CI.0' SED (GREEN) OPEN (RED)
.6 OPEN (RED) OPEN (RED) EIMED (GREINJ
. s*5 , ..-
4 V.
,, a;, , MOV-1867D SW-MOV-121B SW-MOV-122B SW-MOV-1233
- n. .,.
i.
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)
,, k ' ' '
OFF (GREEN) CLOSED (GREEN) W. . h.,. .. , ([/ I fytf,%.;. 1-CV-P-3B MOV-1381,, l
%.7
.' U;. .,
),}e-[ 'y- Trip Valves (TV) - CLOSED (GREEN) ,,,
y, [, 1.. ., 3
, }.p j. '-
,7. BD- CV- DA- LM- LM- RM- SI- SS ' SS- SS- I
",I "100B- 150B 100B 100D 101B&D~ 100C 100B %
'100B 103B 1123
- .M "'"- ~ ~
7M h. ;.
,4 9 ,
D' CV- DG- LM- VG- RM- MS -f' 'SS- SS- ' F .h.s '00D ~ 150D 100B 100F 100B 100D 109 101B 104B ) v6 i
', '.jfi ,jD: ' HCV- LM- LM- MS- TV- TV- SS- SS-1936 1003 '100H 110 1204B 1842 102B 1063
,,, = .,
.- SV-
',... ;c g$ . .
103 l
-Q >n- .
;~ !
.I . A iFY CLOSED OR MANUALLY CLOSE THE FOLLOWING VALVES ON THE POST ACCIDENT i). f 4 ONITORING (PAM) PANEL: .
JJ . 3
^
M.1.7 -@ CLOSED ' (GREEN). CLOSED (GREEN) 5 - TV-DA103B TV-DA103A r:
,. f.'.ep Y" bk,' $.
A** . , ,gd<f
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- 7. .e.= 9 Y
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. :[ f A TTACHMENT TITLE 6. -
REVIS10N 1.00 ENT VERIFICATION OF PHASE A . ISOLATION #A## 3 of 4:'
..F
, 4,./
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t.>
$'k '
y.. L ' D' 4.
' VERIFY OR PEEFORM THE FOLLOWING AUTOMATIC OPERATIONS LOCATED AT THE BOTTOM W THE WIT 1 VENTILATION PANEL: ~
..)f '
, [,;-
CLOSED GREEN) 0FF (GREEN) CLOSED (GREEN) k ~ HV-AOD-160-1 1-HV-F-15 15510D-161-1
. a %4 -
- f' f ,
-k$w[5[
r' I- , yz*i ,,,
' Secure Waste Gas Releases:
( ii," ,, jIN-f ,. d., [.i '",'?': a) FCV-GW 101 - CLOSED e 'iy
, n. , ~ # ?. ):
Q b)
' Inf:ra unaf fected unit to secure contain::en. ..t purge or hogging n
1 r ope:ations. W -
-[ ' _. VERIFY OR, MA!CALLY PERFORM THE FOLLOWING AUTOMATIC OPERATIONS LOCATED
[; , 'AT THE BOTTOM OF THE UNIT 2 VENTILATION PANEL: A. , : Y : CLOSED (CEEEN) CLOSED (GREEN) 4 HV-AOD-160-2 HV-AOD-161-2 g, MOD MOD
]... v .. ] ,.
T
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b I e$ i
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T A TTACHMENT TITLE .' PEVISION ' ' j/ . 'I ' ' i ,. 'et
..- s ir r? 9
. 1.CO
, s
.(
p' e .1 i7.RITICATION OF, PHASE A
. ISO,'.ATION r
, pg ,, -
;, . , , FACE-4 of 4,,,
L*. ' ,,
. s<. ' ~
y i ' s
- y w , .s . -
) w.L RIFF OR MANUALLY PCPIORM TEE F01 LOWING AUTOMATIC OPERATIONS ON THE %' .. 67p!,
'" "j0 NIT,i2 SAFEGUARDS PANELS:
' M, q. h i.;.: , , 'T
~,
'~
a_, "H" Panel "J" Panel
%, [.', g. RUNNING (RED). RUNNING (RED) ,,- , ;g.,,
.n .... . .
,3-
.q 2 FW-P-1A 2-SW-P-1B .4 -
l '- 'V N : W
- N
.f-i v . 2-SW-P-4 C -
- k. e i (
t
' ON (RED) (S^ min T D.) .ON (RED) (5 minsT.D.) ; y; . +
f.'.;f M^, , ,_ _ H, Analyzer Heat H, Analyzer Heat
- g. TPacing Train A
} TPacing Train B - ( r,-
- c. .
>7. VERIFY AUTOMATIC INITIATION OF BOTTLED IW2SH AIR ' SUPPLY TO THE .
h >
, ' CONTROL ROOM: ,
7 -. ,
,.. x f . :z :
#fy. ' '
x? ,
. PI-HV-1311 *
- ig :9 C ,'
_ PI-HT-2311 , li . L'. t,A (Located behind the Unit 1 Post Accident Monitoring (PAM) Panel). I .? >
* , , M. E ,e ',, $ y-* . , .
t~".7, f __. VERIFY O_R PLACE HYDROGEN ANALUEA IN SERVICE AS PER 1-OP-63.2.
. ., ! . >. s y NOTIFY THE STA TO REVIEW 1.97 ViRIABLES ON GROUPS 36 AND 37 0F TEE SPDS.
[ % o .
' .g.+f . .
".y
..y- . . .
4 sp _ _ _ _ . . _
V it9 , w .. c -i" INSPECTION AND REPAIR HISTORY
' *Unit Start-up in 1978
. *1979 Refueling.Outsge r
- Tubes Inspected Leakage Tubes Plutted
. S/G A - 440 None - S/G A - 94 S/G B - 133 None S/G B - 94 S/G C - 480 2 leaks in S/G C S/G C - 96 '
Comunents : Resin intrusion during cycle. How 1's preventively plugged. 2
'other tubes plugged due to denting. Denting first ' observed, Boric
- acid treatment initiated. Leakage rate barely detectable. -
to e d m %,- u .tu c o . ~ ~ . s. cog %
*1982 Refustie.g Outage .
. Tubes Inspected Leakage Tubes Plugged S/G A - 107 None None S/G B - 1165 None None S/C C - 243 None None Comments: Partial tube end repair due to split pin damage in S/G's A and C.
\
*191. Forced Gutage i Tubes Inspected Leakaze Tubes Plugayd S/G B - 579 3 Icaks in S/G B S/G S - 4 i S/G C - 552 2 leaks in S/G C S/G C - 5 j i
comunents : No progressiva in tube denting observed. Row 1 leaking explosive I plugs repaired. Partial tube end repair performed. Distorted indications at support pistes first noticed. Leakage rate 396 GFD. i l Fox A %l l
% 1
___ J
4
, c. t l
Pago 2- , 07/21/87 t
'I
*1984 Refueling Ontage l '
Tubes Inspected Leak g Tubes Plugged S/G A - 100%.available None S/G A - 10 S/G B - 100% available S/G B - 1 S/G C - 100% available $ S/G C - 5 .T i Profilometry in all 3 S/G's. Comunents : Partial tube end repair performed. Attempted tube removal in A S/G. Distorted indications observed. Foreign object located and removed 1 in S/G ~ C. 2 tubes plugged preventively. Leakage rates ~2.3 GPD in 'l A, and 10.8 GPD in C. ( , ,, ,7 g g,g 4 gad m q !W,.1. h u..<, , uA.i p .s f 4 wy up .a
*1985 Outage - i Tubes Inspected Leakage Tubes Pluned S/G A - 830 3 leaking tubes S/G A - 13 !
Casaments : Distorted indications observed. Leakage rate 213 GPD.
- i
*1985 Refueling Outage Tubes Inspected Leakaze Tubes Plunged -
S/G A - 100% available None S/G A - 9 S/G B - 100% available 2 leaks in B S/G B - 17
\
S/G C - 100% available 4 leaks in C S/G C - 47 Commsents : 'No tubes removed with 4 support plate intersections, 30 tubes from the three steam generators were plugged due to " strong" distorted indications. Sample specialized NDE applied in S/G C. Leakage rate 90 GPD. I i I; l
. p, ' ..' f ( - [j( ,1[ #
'b s e < +
-o
*/;
- f" C Pags 3 l.1 r 07/21/87 L . . <
11 ,' *0ther Events During 1986 thru Narch 1987
<r.
~
-Extensive examination of tubing and materials with EPRI and Westinghouse'.
-Preparati.on and submission of WCAP to NRC.
-Reque'sted and held meeting with NRC. staf f 12.' March,1987.
i L-Developed oddy current rule base for April 1987 Refueling..
/
*1987 Refueling Outage .
~
Tubes Inspected Leakage Tubes Plunged S/G A - 100% available None S/G A - 83 \ l S/G B - 100% 'available 2 tubes in B S/G B - 62 i S/G C'
.100% available 4 tubes in C. S/G C - 118 i
Cosaments: Extensive additional NDE performed included: v"
-Profilometry of more than 100 tubes in each S/G. .,, ,
-8 X.'1 probing of nesrly 100% of available tubes.
d
-Rotating pancake prcbing of all idsntified tubenheet indications and a sample of support plate intersections.
-AVB indications first noted primarily All indications
.less than 40% and no tubes plugged. I b u,in t- B S/G. MM .- .e36%
J Tube end repair completed. U-bend. stress relief performed on all ; available Raw 2 tubes in all 3 steam generators. Support plate' stress relief demonstration performed in S/G B. Two tubes removed from S/G A containing 2 tubesheet ' indications and one . support plate intersection. Leakage rate: 11.5 GPD in B and 14.6 GPD in C. 3 l ______m_.____ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ k
.1
;4 '
; il ll '.g )
. , ' C ; , l.'< :- ', !_ f,-
-1
-# -Pago 4- t
,. l 3}.. . c.
07/21/87 ll a
' ' 4 4 ,
j
' - NORTH ANNA UNIT 1 (
i,. i.
. TUBE PLUGGING
SUMMARY
1 .. f I V l , ' ,
- a. . . -
TOTAL .-)
.'0UTAGE DATE - STEAM GENERATOR ~ TUBES A B 'C '}
l s ', .V , '!
. . SEPTEMBER ~'79 ' 94 94- 96- 284-4 i #
-' JANUARY '84 0 4 5. 9
. MAY '84 10 1 5 16 ,
AUGUST '85 13 0 0 13 h - ' n' . E NOVEMBER '85 9
< 17 47 73-1 1
<o-y- APRIL '87 83. 62 118--
<263. ,
- a. , , ,.. - '-
TOTAL 209 178 271 658 ' (6.2%)(S'.3%) (840%) (6.5%)
-r.
l l \ l' L l' 1 t
.J j
l t . y .4 j !' i, I i.- 1 l: i 1 i _ _ _________________________._._m_ _ . _ _ _ _ _ _ _
1 i,
,- . . up ' : , I 'M 'D'ocument Name:
N. ANNA STEAM GEN TUBE RUPTURE
' Requestor's IDi BET 1T Author sN'ame: i Document Comments:
I 1 FoT. 8 4 61 b)7 l
L c. L - UNIT 1 STEAM GENERATOR TUBE RUPTURE EVENT ON JULY 15, 1987 At approximately 6:35 a.m. on July 15, 1987, North Anna Unit 1 was manually tripped from 100% power due to indications of. a steam generator tube rupture in the'"C" steam generator. Approximately twenty seconds later, the safety i
'njectionsystemautomaticallyinitiated.
At 6:39 a.m. , a " Notification of Unusual E.ent" was ceciarec after indications of the tube rupture (primary to secondary leakage exceeding ore gallon per minute) in "C" Steam Generator were evaluated by centrol roon personnel. Initial notifications to NRC and offsite agencies were completed by 6:51 a.m. By 6: 54 a.m. , the event 33 upgraded to an " Alert" class'fication at the direction of the Interim Station Emergency Manager Notifications to the NRC and offsite agencies trat aere reauirec si a res :: :- tre utgradec classification were complete b;. 7: C2 a. +. 4.- 3fu :'an: ecuipment functionec properly, anc t + .n : <. 3 5 3.a:' ':e: i ' 1::: 1 ce .".o 5tatic" Emergency Operating Proce:; es. I a: cit : . E e ge :. 'la- Implementor; Procedures respecti.e t: a- We . class:3:#:n se e 4 :'eme te: to augme,* tre onshif t staff. Ej 7: 25 3.- a 5:::. :a:.; ; .. ;' 5' static perscene nad t)een conductec. E:. .5 3- :+ ~+:--ica' !..::: *. Ce :+- ac Operational Support Cente ere f ' 3 mance; a : a::i.5.e: E n3a. .1+ iccal Emergency Doerations Fa:ilig t 3s f.:' , ~2"ec 5,: a:t ste:. Tre initial i. dica:i ,s a.5 i t :e t: ire c:sc5:: 3 ee + 'r:- : e m3 ir steamline radiation meni 0 5 .hicn ent into aler't at c:roxima:ely 6:30 a.m. on July 15, 1987. Subsequently, cressari:er pressure 3 c level regan to decrease rapidly. Pressuri:er pressure decreased (a'ter tr.e manual reactor
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" trip) to:approxhnately.-1730 psig which is below the safety injection setpoint
~ c of approximately 65% to offscale low prior to recovery. The maximum primary M
' to secondary , leak rate has been estimated to. be 637 gpm. The re-establishment-of. pressurizer L level and isolation 1 of the ' ruptured "C" steam generator was
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,, completed L under Station . Emergency Operating Procedures. (EP-0 and EP-3,
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Revision 1). t < Cocidewn and depressuri:5 tion cf the RCS -as ir.itiate: s *. 7 : 10 a . m. in accordance with Station Emergency- Operating Procecure E5-3.1, Resision 1 anc. proceeded routinely, At - 11: 09 a.m. , the RCS was cooled acwn to below 350 l
, y degrees F and.Onit I was placed in Mode 4, Hot Shutdown. At 1:33 p.m. , the RCS was cooled down to less than 200 ' degrees F and tne. unit was placed in
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Mode 5, Cold ' Shutocwn. Plant conditions were staDi e a : . e emergency was . terminated at 1:36 p.m. , at' which time termination notif # cations were made tt ! I
~ t.,e NRC ar.: of fsite agencies.
1 kri g the ::urse :f ve e,ert. e'fluenu eleases f :- '-
'Stea- Generat; Deice't0 'its isciaticr .c:currec through tne Concense- U- Ejector and
. Auxiliary Feedwater Pumo I.:rbine exhaust. Howeser, t e reiesse was determired )
to ce s er,, SIail . Isotopi; analyses performea or 53 0165 :* awn f ect these
- sth.3ys s'e as #:llows: hrtricu.icn fr:- Concerse -
Eject: gasec..! a:t'eity was 0.44% of Tecnnical 5:ecificatic- limits 3 : :::ine atti."ty .35 Iess than cetectaDie. Contribution f rom tre Auxiliar. see:.,3te- Fum: TurMN
.as 0.17% f Te:rnicai 5:e:ification lim ts. for a t:t3 i
<eiease ;f 0.6T. c' Tecnnicai iceci#ics.i:- li-'is.
Informatica Contacts: M. L. Bowling ( 7C3-894-5151) er i. J. HardaiCk (804-273-2908). 1
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State. Manager ' Manager NRC 3 I Command-l Center 1 Maintenance Tech-ical Nuclear Industry Health and E.i .ni n Safety and I r.te-f a c e Physics Repair' Licensing l 1
.# .c - b q 4, h) UNIT 1, STEAM GENERATOR TUBE RUP"'URE SEQUENCE OF EVENTS July 15, 1987 l l 0630 'C' Steam Generator Feedflow begins to decrease slightly (compared toA' and 'B') Steam flow remained relatively ) constant -l 0630 Pressurizer Pressure began decreasing I { 0630 Pressurizer Level began decreasing i 0630
- Received and 'B' Annunciator alarm.on Main Steam Rad Monitors. Main 'A'
. Steamline NRC Rad Monitors were in Alert and the "C" t Steam line NRC Rad Monitor was in High ' alarm (i.e. , HI-HI alarm)'
0633 '
' Letdown isolated and charging pump suction realigned to Refueling Water Storage Tank. A unit ramp down of ~2%/ minute was <
initiated. { 0635:04 Manual Reactor Trip
'0635:06 Manual. Turbine Trip
0635:07 Pressurizer Low Pressure Reactor Trip Signal 0635 Auxiliary Feed Water Pump 3A, 3B Breakers closed
-0635:24 Pressurizer Low Pressure Safety Injection
('B' Charging Pump, A,B Low Head Safety Injection Pump breakers closed). 0635:24 Feed Water Pump Breakers Open 0635:25 Feed Water Pump Breakers Open 0644 Low Head Safety Injection Pumps Shut Down 0650 Feed to 'C' Steam Generator isolated and level still increasing 0654 'C' Steam Generator completely isolated 0657 Plant Conditions 'C' Steam Generator Level '60% NR
'A' Steam Generator Level 'O NR
'B' Steam Generator Level 'O NR Pressurizer Level '5%
Pressurizer Pressure Increasing Fox)t wot D/t j
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D, . h) 0701' Secured Pressurizer Heater (Pressurire pressure increasi ng and~ Pressurizer' Level 10-15%) ' e 0704 B' Charging Pump Shut Down 0704' p Open 1 Pressurizer Power Operated Relief Valve etopressure reduc _IAWRelief EP-3. Pressurizer Valve Closed. Pressure reduced 40 PSIG and Power 0710
'C'-Steam Generator level increase stopped COOLDOWN USING BACKFILL"Transitioned to E
.0713:21 Reactor Cooling Pump 'C' Shut Down 0713:22 Reactor Cooling Pump 'B' Shut Down- '
0715
' Supt. Operations and SRO-ON-Cc11 arrived in Control m Roo 0720 Station Manager arrived in Control Room 0730 Aast. Station Manager arrived in Control Room 0739 Station Manager assumes Station Emergency Manager on Positi
'0757 TSC activated 0915 .Y LEOF activated .
1108 Entered Mode 4 1218 Placed RHR in service 1330 Enter Mode 5 1335 Terminated Emergency t ( I l 1
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PRELIM 1NnRY NOTIFICnlION OF EVt.Ni ilk UNuGUAt.. UC.Cl)RfdiNCE i
'lh a st4futyprel or ipublli!
mi nney hot 19 f' *61 i ntercett t at aQnion ft ieFir.t.i cesitct'. t itteth hAl:t Y notice of eve =nts of POSS11!LI Ths inf ormat ion i ss ars InitjaJ1y rtev etel ve J wi t htaut verri fi ca ti the heut on J i istaf f. tatt t h i s t$4 t.o.on *:r evaluatAun. nnd in becocally #11 that is k'i} F ACIL11 Y. Virgins e Electrie 64 Power Compcny t a rensee litner gency Classi fication: North Cana Urit t 1 Notification A'icrt of Unuuual Event
- Dciclwt Nc: bO-330 ria ner 41. Viruanta ~
Sito Area Emergericy Gantrr al Emerglency
/. Not Applicable ,,
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- va c a.l e,l ien, l ht- ur pcF sti on liitt ur'on t*t .4Wnms lu v t+> t r of.rh un d r, wanA one ar.d V _ 'r M L inch the 1 1 t. :. iv..eo i n p r r,.'p..ir i n g t i, pt.r t o: *ii t he erf dy rui rc it t es;L f or all tubes un List- t.c) f: ie q .'. t' rJ c::ptte i s. *fdMA 7WA&t').
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4 ' ' 9 '. ' 1 MINERAL.,'VA. (APr -- A LEAX OF RADI0 ACTIVE NATER FORCG'TH T00AY OF R REACTOR AT THE NORTH ANNA NUCLE1 AMOUNT OF RADIOACTIVE " ' ' GASMAS. RELEASED TO UTILITV :THE ATNOSPE! ' 0FFICIALS SAID. . /> I' J-j VIRGINIA PONER DECLARED. M' ALERT .THE2.SECOND-L /
.' REACTORS.
EMERGENCY CLASSIFICATIONS,gAF.TER* : - THE. ACCIDENT. AT OM
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THE UTILITV SAID:IT APPEAREDf,THATiTHf RELEASE OF.' GAS " CON ' ABOUT H HOUR AN A HALF.AND HS NELL'.BELON;THE STATION!S TECHN l SPECIFICATION 'LINITS.' UTiWr0&
"NO STAT 10N.ENPLOVEES'NERE INJUREDii AND'THE RADj RELEASED POSES NO THREAT. T0'THE HEALTHJORESAF ~
EMPLOYEESs" IT SAID. :
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KEN CLARKi SP0tESN8N AT THE NUCLEAR REG DFFICE IN' ATLANTA: SAID ST.ILIT.V.' MONITORS 'NERE U RADICACTIVTV IN* THE. ATM0 SPHERE 0UTSIDE.THE. PLA VENTED. '
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. THE SOURCE OF THE LEAK NAS NOT'.IMEDIATELY 307:1T DETERMINE -
APPARENTLY WAS IN PIPES. RUNNING BETNEEN :TN0' STE RONALD H. LEASBUREs THE UTILITY'S SENIOR.'VICE PR RND CONSTRUCTION. - ' - ii 3. " .
"THE MOST. PROBABLE'CAUSE'IS THAT ONELOF THESE LARGE LEAKS."iLEASBURO SAID AT A: NEWS CONFERENCE
. HE SAID. THE US VENTED T0 THE 'ATNOSPHERE' CONTAINED 1.2,9 PI FEDERALLY THE NAKEUP of:ALLOWED TNE GAS.' - ' '" DISCHARGE LINITS..FOR.RADI0 A 0F. /',J W A <
r OLEASBUR6 SAID UTILITY OFFICIALS NON'T KNOWi UNTIL>THE SYSTEN.CM BE C00LEDe' A, PROCESS' EXPECTED TO ' HOURS.* a- -
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RSKE0 MV THE GAS LEAK LAST FOR ABOU.T.198 MINUTES, LEAsBU {
"THE PRIMARY CONCERN IS TO ISOLATE THAT P8IMARY S CERTAINLY TAKEN IN A SITMTION COULD LIKE THIS."s TAKE S0~ HINUTES TO TAKE ALL. T "
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'DEBBY CLARKs A LOUISA COUNTY SHERIFF's 0FFICE WARNING SIRENSec!NSTALLED IN THE. AREA *TO NARN., RESIDENTS 7tCCIDENTS: NERE NOT SOUNDED.s . -
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- July.15,.1987:
', 4
,Mr. Addison,E. Slayton State Coordinator State Department of Emergency Services
' 310 Turner Road-
- Richmond, Virginia- 23225-6491 bearMr.Slayton:
SUMMARY
OF " ALERT" EMERCENCY .) NORTH ANNA POWER STATION UNIT 1 "C" STEAM GENERATOR -TUBE RUPTURE q .-
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Enclosed is a . copy ,of the Summary Report of'the " Alert" emergency'which occurred at North Anna Power Station on July 15,.1987. '
' Very truly yours, W. L. Stewart.
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' Enclosure t cc: Mr. M. M. Cline Mr. G. O'N. Urquhart
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NORTH ANNA POWER STATION
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SUMMARY
REPORT: ALERT Initiated: July 15, 1987 at 6:54 a.m. Te rminated: July 15, 1987 at 1:36 p.m. EVENT: Unit No. I "C" Steam Generator Tube Rupture ; DESCRIPTION OF EVENT: ' At approximately 6:35 a.m. on July 15, 1987, North Anna Unit I was manually tripped from in the "C" steam100% power due to indications of a steam generator tube rupture generator. .Approximately twenty seconds later, the safety inj ection (RCS) system automatically initiated due to low Reactor Coolant System pressure. At'6:39 a.m., a " Notification of Unusual Event" was declared in accordance with EPIP-1.01, Tab "B", Item 7, after indications of the tube rupture (primary to secondary leakage exceeding one gallon per minute) were evaluated by control room personnel. compinted by 6:51 a.m. Initial notifications to offsite authorities
/
were By 6:54 a.m., the event was upgraded to an " Alert" classification at lirection the I of the Station fab "B", Item 8,." Gross Emergency Manager, and in accordance with EPIP-1.0l, Primary to Secondary leakage". Notifications to offsite authorities- that were required as a result of the escalated ) classification were completed by 7:02 a.m. i Plant response to the event progressed as expected. "C" Steam Generator was l completely isolated at 6:54 a.m. properly and the unit was stabilized All major plant equipment functioned 1 Procedures. in accordance with Station Emergency In addition, Emergency Plan Implementing Procedures respective to , an " Alert" classification were implemented to sugment the onshift emergency response staff. By 7:28 a.m., been conducted, an accountability of all station personnel had j j At 7:57 a.m., i were fully manned bothand the activated. Technical Support Center and Operational Support Center At 9:15 a.m., the Local Emergency Operations l Facility was fully manned and activated. Cooldown and depressurization of the RCS was initiated in accordance with Station Emergency Procedures and proceeded routinely throughout the event. At 11:09 a.m., the RCS was cooled down to below 350 degrees F. and Unit I was placed in Mode 4. Hot Shutdown. At 1:33 p.m., than 200 degrees F. and the unit was placed in Mode the RCS was cooled down to less 5, Cold Shutdown. conditions were stable and the emergency was terminated at 1:36 p.m., at which Plant time termination notifications were made to offsite authorities. During the course of the event, effluents released from "C" Steam Generator prior to its isolation occurred through the Condenser Air Ejector and w - ___ _.
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t..'y Auxiliary Feedwater Pump Turbine exhaust. However, the release was determined to be very small. ; Isotopic, analyses performed on samples drawn.from these pathways are as followst: Contribution. from Condenser Air Ejector ' gaseous activity was 0.44%. Technical Specification limits and' Iodine ectivity was less than detectable. Contribution from the Auxiliary Feedwater Pump Turbine was 0.175% Technical Specification limits, for a total release of 0.62% Technical Specification 11mits'. Unit I will' remain shutdown.'until the. problem is evaluated and corrected.- No further: correspondence concerning this event is anticipated.
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l' - l l' ' l bc:- Mr..J. L. Wiloon Mr. E. W.'Hatrell'
'Mr. G. E. Kane Mr.-M. L. Bowling i Ms. N. E. Clark
'Mr. G. L. Pannell l Mr. F. M. Cox Mr. D. J. Vandewalle i Mr. S. A. Harrison Mr. J. P. Smith '
E.P. File NOD Tech Library (bc original) i
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(804) 771-6725 t YOR I!91EDIATE RELEASE July 15, 1987 '
- Release No. 1 ,. 8;00 a.m.
t VIRGINIA POWER DECLARES ALERT AT NORT;i ANNA
- i Virginia Power today declared an alert at its North Anna Power station at 6:54 a.m. .
The alert was ditolared because the stations unit I reactor cooling system was experiencing a primary to secondary system leak .in the "c" steam generator. 11 nit 2. was shut down by 'l;l.h 3.' 1 station personnel and is being cooled down. .There appears to have been no significant release of radioactive material to the atmosphere. 9 Virginia Power has established a special phone number to provide information regarding the alert. Collect calls will be
, accepted at this nurnbar. The number is (804) 771-6725. b 4 - &7- N /
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} $7 :1 iO2 ~ -08047713042 VIRGilllfP0ER y:.
13001/001 ! (.c 1< l r . One radiation. monitor on the air ejector pipe was found to be ineperacive during the . event. If it had been operating, it would have detected ; the sma.: amounts of radiatiou:that were released, but the levele were l sufficiently low that it would not have isolated the release. No injuries occurred, and there was no 'tbreat to- the' health or safety of station ' employees or the _ public. l IIIII t 1 i
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- UgwnIfl 21:D 38047713042 VIR0lNIAP0H
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ff-l. 1 O lin /Ininer//ule kc/va.4' (804) 771-6725 Wesm M Por:ct GM'I., FOR IF01EDIATE RELEASE July 15, 1987 Release No. 2 9:00 a.m. ALERT STATUS CONTINUES AT NORTH ANNA POWER STATION virginia I Power reports that the alert status declared earlier today continues at its North Anna Power Station. 1 . The alert was declared because the station's unit 1 reactor cooling system was experiencing a primary to secondary system leak in the "C" steam generator. Unit 1 was shut down by station personnel and is being cooled down. This shutdown was followed by an automatic initiation of the safety injection system, which injects cooling water into the reactor cooling system. The primary system leak was isolated and station
, , shutdown continued. The unit should be in cold shutdown by 11s00 a.m.
SZ4-8?-K O/ftf A small { amount of radioactive gas was released to the I atmosphora t.hrough the secondary ayatom air ejector. Initial indications are that the releaso continued for about an hourad d and was well below the station's technical specification limits. No station employees were injured, and the amount of !
; 07/14/87 21:25 08047713042 VIRGINIAP0H 1
@ 001/001 radioactive gas released poses no threat to the health or sataty.of the public or employees.
Virginia Power has established a special phone number to provide information' regarding the alert. collect calls will be accepted at this number. The number is (804) 771-6725. l All further public statements will be issued from the l Public News Center at Ons James River Plaza, Richmond, Vai The Public News Center is located in the auditorium of One James River Plaza, corner of eth and Cary streets, Richmon.d. Virginia Power also is establishing a Local Hedia center { at Hineral Volunteer Fire Department, Hineral, Va. However, all "i official company statements regarding the emergency will be I provided at' the Public News Center in Richmond. 4
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.' t.icensce/ Facility' Notification / Subject VEPCO/ North Anna 1 HQ Duty Of ficer Steam Generator Tube Leak Event /
Event No. N/A North Anna 1 experienced a steam generator tube leak of unknown magnitude while at 100% power. ' An alert was declared at 0654. The plant was manually tripped at 6:35 a.m. safety injection (SI) auto initialert at 6:36 a.m. and initialindications are that all equipment functioned as requ'/ed. .The SI was terminated at 7:05 a.m.
.The Resident inspector was in the contiol room during the event. The Regional incloent Response Team was activated and a site team dispatched.
Regional Action: Region to followup, PN issued. i 4* l J
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Licensee / Facility Notification / Subject VEPCO/ North Anna.1 Upda te of Reactor Trie c- on Ju1Y 15 I Event- Event No. Tho'resional team which was sent to the site on July 15 developed into an AIT. os of. July.16. The primary to secondary leakase . cal culatiorP is preliminary and is between'2OOL '600 sem. The FSAR assumed a 735 rem steam senerator tube leak. Tho. licensee is preparins to visually inspect the steam senerator on July 19. M3dia interest has increased after the declaration of the AIT. The licensee is 'l1 nodeline the event on the site simulator. The licensee conducted plant tours vosterday.for the Press and'is conductins tours today for the local officials.
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.Rocional Actions .A PN will be issued..
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' PRIORITY TTENTION REQUIRED . MORNING REPORT - REGION III JULY 17, 1987 FACILITY / LICENSE NOTIFICATION / SUBJECT
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MOBILE INSPECTION S VICES, INC. 2104 RIVE 9 RD. SOURCE CONTAINER FOUND ALONG SIDE l ROADWAY IN CHIO FARMINGTON. NEW MEXICO j EVENT " EVENT NO.
-RIII WAT INFORMED BY OHIO DIS *TER SERVICES AGENCY . (ODSA) THAT A SOURCE CONTAINER WAS FOUND ALONO SIDE ROUTE 95 NEAR MANSFIELD, OHIO. THE SHIPPING
-PAPERS INDICATED THAT IT WAS OWN- BY MOBIL INSFECTION SERVICES, INC. AND WAS
-BEING SHIPPED TO AMERSHAM TECHNICAL SERVICES, BERLINGTON, MASSACHUSETTS VIA ANR
,TRUCKINO COMPANY. APPARENTLY THE SH PINO COMPANY, (ANR) LOST THE CONTAINER )
DURINO TRANSIT. ODSA TOOK POSSESSION l THE DEVICE AND WILL RETURN IT. THE CONTAINER CONTAINED 24.7 CURIES OF IRIDI -192. . ! REGIONAL ACTION : NOTIFY U.S. D.O.T.'AND NEW MEXICO RADIATION CONTR BUREAU AND LICENSEE f l L? Forg-P7- f'/
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, (804);771-6725 -
JOR IMMEDIATELRELEASE' July 15, 1987 Release No."3 ALEr.t STATUS' CONTINUES AT NORTil ' ANNA' AS C00LDOWN CONTINUES The' alert. status declared at North Anna Power Station's' Unit 1 I continued this morning as .the unit headed toward cold shutdown in a routine 1 1 .., manner.
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' The. alert was called because of a primary to. secondary system leak in' cone oflthe unit's three steam generators.
- An extremely small.-release of radioactivity occurred during the incident, but it was 'less than two percent of the allowable limits set by.the NRC and
- posed no threat' to the. safety..or. health of station employees or the. public.
The total- release, 'which . occurred over about 'an hour and a half,, was 1 less'than.the amount of'one6 chest x-ray and was undetectable above normal background r'adiation levels at the b'oundary of the plant, at'6:39 a.m.. the , The event.'at. Unit 1-occurred at 6i36 a.m.'and atxtkaxmanax11maxtka lowest ) lev 1.of emergency' status, an unusual event, wasideclared. The next level, an l alert, was' declared at 6:54_a.m..
.h Aga#nd "s"hs%"tl'&.* emu'4Tfeted t b achined latu this aftunoon.
J. team from the NRC is expected ko reach the plant in early afternoon. 4 L-j r f j_ Form-77 'M b//7 _.-.i_x _2_m--.__----m_= - - - - - - - - - - - - - - - - - - - - - -
?' 0804 Til 3042 07l15/8714:57 VIRGifHAPOER
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m ._ n>r immedktte Releasc C<mtact (804) 771-6725 For Ic=ediate Release July 15.1987 . I Release No. 4 2:00 p.m. ' I ALE 3T ENDED AT NORTE ANNA PC'WER STATION
, Virginia Power officiale announced the ecd of the alert status at t North Anna Power Station at 1:36 p.m. today. I The alert, ubich was declared at 6:54 a.m. today, was terminated af ter l Unit I was brought to a cold shutdown (cold ebutdown meant, the pri=ary eyetem j coolant was less than 200 degrees Fahrenheit). Cold shutdovu had been project-ed to occur by about 11 \
a.c., but the rate of cooldave was intentionally sloved I as plant conditions quickly improved. The neretely small amount of radiation released from: one of Unit l's three steam generators was even less than originally calculated. An initial calculation of the a:cuot of radioactive 5as rele.ased ind1-cated a level of less than 2 percent of the .a=ount allowed by the U.S. Nuclear Regulatory Co= mission--an amount lese chao a chest x-ray and undetectable at the plant's boundaries. Such a email a= cunt is dLfficult to monitor and calculate with perfect accuracy, but additdocal, more precise calculaticos s h ow t F.a t the level was lees than 1 percent of the allevable limit-ao amount eq uivalen t to what would Fo.14 -fr 7-Y4 / be received on a roundtrip flight across the country.
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ey 3 g4 _ JULY 16,1987 - 1600 MEETING
- 1. Plant Status:
V I. -On RHR - 120*
- Bubble in pressurizer 40// and 275* - 260'
-C S/G at 22(/
-N n VCT' 2
-Cold Shutdown Xe Free Boron
-Containment Atmospheric
- 2. . Task Group S :atus:
Maintenance and Repair Preliminary Outage schedule developed which assumes no special tes ting.
, Activities for completion overnight:
- s. Containment on Purge and surveyed and posted for general entry.
- b. Fill 'C' S/G Secondary side and then drain 'C' loop primary and determine height of break.
Goal is to set up work area and be ready to remove diaphragms by Saturday morning. Technical Collected initial version of S/G maintenance history. Will review with NRC following this meeting.
-Initial Inspection plan to be completed by mid-day tomorrow (7/17/87).
-Contacted Ginna and discussed their event and lessons learned.
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e;g 47. u ..L.o. ; . , [/; ,.+ , , :-Post trip interviews complete's ' g ,.
, %j . _ _ ,
ly ? Eg.c:-Manual- Leak rate' calculation completedL- Maximum Leak 627 gpe. . , tW ,,g,fohm[tionfprovided D to NRCJincludAd . copiesf of/ EPIP's, Post trip
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" T data, copy. of leak rate calculations,. control: room logs, and EP's.
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-SPDS data will be provided.to NRC later.
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1 V-Detaile'd ? Sequence -of ? Events. should be completed on L7/17/87 with" ( ' A ' analysis to follow for. lessons learned. b~ '
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- j. Rad monitor, and.ssvaple ' data supplied to HP. '
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.e entry has been prepared ~ for. release.
l 7,-
-Reviewed INPO SOER's' 82-03 on S/G tube ruptures - have complied with ~
f 'its: requirements. Also reviewed' W analysis...and found, nothing. unusual.~
-Working on ' an outline for ' a . detailed report with' o,ther group leaders.' Should Le available by 7/18/87'(Saturday).
-W111'obtain data for studying the event on the simulater'. ,
Health Physics
-All sample analyses reviewed have been normal . - including vegetation 4 . and soil samples.
..-Process and vent vent charts all appear normal.
y
-Still looking - at. Terry Turbine and plan ' to examine Kasan Monitor
. data.
-Question raised about Air Ejector flow path to vent stack and how it is monitored. Tiow path and monitoring will be confirmed and
; reported - tomorrow. 'Also the operability status of vent-vent Kasan monitor at the time of the accident will be checked.
i 1 1
Rs .Paga 3
- i. 07/17/87
- Industry Interface- i f S Conducted four (4). TV interviews at North Anna and one (1) in Richmond
- ,. with Power Supply ,(L. Ellis).
-Standby st,atement developed for use by PA 'in answering questions.
1
-Most frequently ' asked question has been about how cost. will effect-customers. j l
!' -SCC seems satisfied with information supplied to date (copy of report
~ given to State DES given to SCC).
-INPO sending two people to arrive tomorrow to work with us on. developing
~
an SER or SOER. "
-0DEC provided information for use with an upcoming board meeting.
t
-Louisa County officials were invited to tour plant. The tour was conducted and officials were satisfied with Emergency Plan implementation.
-Plan to invite other surrounding counties for similar tours tomo, trow.
NRC' s
-Raised question about the preliminary outage schedule.
The question concerned the online data shown when the NRC Region II had only been briefed and accepted schedule. activities through setting up for eddy current work. Virginia Power stressed that the schedule was preliminary and subject to change based on the results of 'C' steam generator inspection. The preliminary schedule includes no special testing or repairs.
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% OUTAL;E DAY ~;
if 1 I, . NOR Ti l ANMA POWPR STATION l} ilN a f 1 FORCED OUTAGE y' 'C' S/G TO: MR.G.KANE FROM: D.HAHN ,
. J.DEMARCO '
UNIT 1 OUTAGE STATUS ' l. ,
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- n > < 4 o 4 + + *
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- RCS TEMP 115 : PRESS 29 PSIG *
"C" 5/G GAS SAMPl d KESUL T3: 4.4% HYDROGjiN
- 16% OXYGEN *
= *
' 76% N(TROGEN
- 9330 MPC'sXENON *
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- 46 e > + + + + + W k * + 4 + * * *
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13 GFERAFIONS: CONTAINMENT PURGE COMPLETE - CA M d o ~ PERSONNEL I(ATCH UPEN
. + "C" LOOP 3 TOP VALVE CLOSED
+
DISC PRESSURIZATION ON "C" LOOP STOP s INSTAI.LATION WORKING 23 MECHANICAL:
** 90 SPOOL PIECF.S INSTALLE.D ON A.B.C S/G'O INSTALLED 0[EC PRESSURIZATION ON "C" L t'.'O P STOP VALVE WORKING ADJUSTED PACKING ON UNIT 2 "A&B" FHED REG VALVES. I W-:'4 78 N FW-2488
- 3) HP:
- HP SUR'/F r' 1 i! 11 i i CONTAINMENT CU!1Pl. E 7 i '
- G AMPLU:n "C" a L, 43 CHEM (GTf-Y:
- PERFORMCD GAfi SAMPl.ES ON "C" R/G
*** UNI 7 2 8m. 5 5 ^ 9..j
. NO MAJOR lROf!LEMS a**
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ETnDIK IEPWri IMIT 1 SMAN MISthTGt "C" OLTTME pgg LUL 3 SWtfepr START 02 : 07/17/37
- e.
-!.. J GIG REM LM.2 P EMLY -EME.Y LATE LAR ft , m. m ACTIVITY MERIPT11BI M5t DIAt DPT SYS CD R STMtf FINISt START: FINISI FL ' .10000'0001 1 REACTtst TRIP & SI 1.0 0 0 (P RC 00002 A07/15/06 ~ A07/15/07 : ACT M TY CGPLETE 10002 10003 Cott. Dthat TO 350 3.0 0.0 OP !RC 00002- A07/15/07 A07/15/10 ACT M TY COSM.ETE 10034 10037 . T15ts!E WIN Dinst & ON GENT 2.0 0.0 OP.'TM 00004 A07/15/07 407/15/09 ACT M TY CGWi.ETE 10038 10039 7tatBIE CtII. Dinal 24.0 0.0 OP TM 00004 A07/15/09 A07/1 & 09 ACT M TVJ CtR9LETE I 10004 10005 Mst EARP 10.0 0.0 (P RH A07/15/10 A07/15/10 ACT M TY. CGFLETE 10006 10007 COtL Dtnat TO 200 3.0 0.0 F RC 00002 A07/15/10 A07/25/14 ACT M TV CG9 TETE 10024 10025 SIEAK CGESWt UACLAAI 10 0.0 OP CN ' A07/15/13 A07/15/1'4 - ACT M TV COWLEE 100 3 10029 IEttstE & TAS FU2nl4TER SYS 9.0 0.0 OP FW 407/15/14 07/17/15 07/25/17 07/25/17 19d !
10040 10041 TlftBIE C0tL Dinet GT GEAR . 24.0 0.0 OP TM 00004 A07/1&O9 A07/17/09 ACT M TY CGPLETE 21002 21003- SAMLINB W EIDSNtY PLANT 40.0 23.0 CH' 00012 A07/1&14 07/10/14 07/2&O5 07/27/04 206 MTnELL,W WTR BRAIN TLFW EATERS 14042 1A043 GAS SAWLE C I/O 2.0 . 0.0 CH MS A07/1&15 A07/1#17 ACT M TY Ct39 TETE
.19042 19043 LIQUID Sapp 11 C S/6 '20 0.0 CH MS A07/1&15 A07/1u17 ACT M TY CSFLETE 10000 10009 3REAK CtNTADDENT VACLAff 2.0 0.0 CP E 00010 G'21.2 A07/1&15 A07/1u16' ACT ' M TY. CGFLETE 10010 10011 PtsitE (XNTAD0ENT 6.0 0.0 OP K 00010 F-21.2 A07/1&14 A07/1 u22 ACT M TY CG9 TETE s
1003410035. W St5tVEY & POST CONT. 6.0 0.0 W G A07/1&16 A07/1&21 ACT M TV CGPLEM 10010 10019 12.0GE C LotP 1rTIP W.V 2.0 0.0 OP RC A07/1&19 A07/1u21 PEP-5.90 ACTIVITY COPPLETE 1
.10020 10021 1*BJ -PP -ABC WD6 M 2722 6.0 0.0 E BD- A07/1&19 A07/17/00 ACTIVITY COPPLETE WD0062723/M272419F-Cf-4 INSTL BLOWDolN SPL PCS 10032 10033 ISG. ATE C S/9 !ECOGNtY 4.0 0.0 OP MS W-33 2 A07/17/00 A07/17/04 ACT M TY CorLETE I ~ 10022 10023 1-itC - -4.0tPC WO4 062740 3.0 0.0 E RC A07/17/M A07/17/12 ACT M TY C019 TITE MtP-5.90d9P-C-P-4 INSTL DISC PflES6 RIG -
10042 10043 ECt#E TtstBIE & TAG 0.0 2.0 (P TM 00004 A07/17/09 07/17/17 07/22/09 07/22/11 114. l 14018 1A019. DE0A88 PftIMARY 400 40.0CP RC 00014 07/17/15 07/19/15 07/23/11 07/25/11 140. 1C042 1C043 1-$8 4P -44NT 150 062034 20 2.0 OP PS 07/17/15 07/17/17 07/17/19 07/17/21 4. P-115 (DEV) W & PtslE C S/9 ECONDNtY 10052 10053 1-CE -EH -1 nW6 062777 4.0 4.0 E E 07/17/15 07/17/19 07/18/20 07/19/00 29. PDP-C-CE-3 Rft/ EECAPE TRL80( HATDi i 10058 10069 1-WT PP -AB niDe 062714 2.0 2.0 E WT I 07/17/15 07/17/17 07/20/11 07/20/13 68. WO9062717 PDP-C-P-4 INSTL ET LAYtP SPL PCS 10N010H1 NtAIN D S/G 6.0 4.0 GP MS F-33 2 07/17/15 07/17/21 07/17/15 07/17/21 0. ! 15016 15017 1 CI -C8 -31CCM 486 062902 30 3.0 IN EI 00016 07/17/15 07/17/18 07/24/22 07/25/01 175. ICP-P-I-ICOH1,DP-C flISC-02 ERRATIC READING '15020 15021 1 896 -2R' -101A 606 062910 40 4.0 IN pel 00012 DP-C-MISC-05,2R-406101FSR-4M-101,DP-C-ENV-2 INSP/ REPAIR 07/17/15 07/17/19 07/27/00 07/27/04 225. ! l2000420005 1-4tc -E -1C 40 { j 4.0 W E 00010 07/17/15 07/17/19 07/18/03 07/18/07 12. INSTALL LPPER PLATTORM & REMOVE IN9ULATION 1 Fe2:4-F 7- W/ { \ - b/ a39
;4 ETIENBC 8tE*0RT (MIT 1 STEAM E)DAT(5t "C" OUTAE pg
- .LE. 3 SWtf BY START $2 07/17/87 1 J Gts REM LVL2 P EMILY EAm Y LATE LATE- T M le0E ACTIVITY DE90tIPTIE DLft DUR DPT SYS CD R STNtf FINI54 START -FINISH F'i 10054 20055 ' 1-E 4H : -1 lee 062777 2.0 2.0 E CE 07/17/19 -07/17/21 79P-C-CE-3 IMTALA. PEETilATI(N FLME 07/19/00 07/19/02 2 .
20006 20007 1 4tc 4 - -1C' * - 6.0 6.0 W E 000'10 07/17/19- 07/18/01 07/18/07- 07/18/13 1-KT1P STEP-OFF PAD /W COmtm. BOLMDARY 1ST FILA. C S/0 6.0 4.0 F MS 07/17/21 07/18/03 07/17/21 .07/1b/03 1004410046 ' F-33 2 10056 10057 1- E 1 WOG 062777 1.0 1.0 E E 07/17/21 07/17/22 07/19/02 07/19/03 79P-C-CE-3 INTL CAR.ES & lees & EA. PENETRATIONS 2 20012 20013 1 4tC 4 -1C - WO4 2.0 2.0 W E 00010 PERF(NIM PRIMARY W PLATFORM W RftVEYS 07/18/01'. 07/18/03 07/18/13' 07/18/15 1-; 10026 10027 ' DRAIN C S/G PRIMARY 4.0 . 4.0 (P RC 07/18/03 MOP-5.90 07/18/07 47/18/03 07/18/07 10046 10047 1ST DRAIN C S/0 6.0 6.0 & MG F-33 2 07/18/03 07/18/09 07/20/13 07/20/19 $ 10062 10063 ' FILL B S/0 FWt ET LAYtF - 6.0 6.0 W M6 07/18/03 OP-33 2 07/18/09 07/20/13 07/20/19 S 15012 15013 1-SV -RM -121 WO4 062639 4.0 4.0 IN 9V 00016 N07/19/07 07/18/11 RP6-1-SU-121,19-C-MISC 45 INIP/IEPAIR 07/24/21 07/25/01 15 15014 15015 1-VG -RM -179-2 WD4 062778 3.0 3.0 IN VG 00016 N07/19/07 IF,-C-MISC-05 RERACE LID 07/18/10 07/24/22 07/25/01 15' 15018 15019 1-N1 - -404190 WO6 062778 4.0 4.0 IN N!.00016 N07/18/07 I P -C-MISC-02 FAILED HIGH 07/18/11 97/24/21 07/!5/01 15I 20008 20009 1-4tC -E -1C WO4 9.0 6.0 E RC 00016 07/18/07 07/18/15 07/18/07 07/18/15 ( T10P4:-RC-2A RENOW PRIMARY M4NWAY CDVERS 10048 10049 2ND FILL C S/G 6.0 60& MB OP-33.2 07/18/09 07/18/15 07/20/19 07/21/01 5l 10064 10065 15tAIN A S/G 6.0 6 0 (P M6 F-33 2 07/18/09 07/18/15 07/20/19 07/21/01 5E 10050 10061 22 DRAIN C S/G ' 6.0 6.0 (P M6 (F-33.2 07/18/15 07/18/21 07/22/23 07/23/05 10d 10066 10067 FygS/0 FOR E7 LARP 6.0 6.0 (P W 07/18/15 07/18/21 07/21/01 07/21/07 SE 20010 20011 1-ftC 4 -1C nel 12 0 12.0 W RC 00016 07/18/15 07/19/03 07/18/15 07/19/03 C TP9P-C-AC-2A IEEVE W DIAPlftML/IETALL IGZ2LE cwt 20068 10069 S/0 A & 8 IN ET LAYLP 100.0100.0 OP MS 07/18/21 07/23/01 07/21/07 07/25/11 SE 20024 20025 1-ftC 4 -1C WD6 24.0 24.0 nM RC 00016 ET (P FGt EDDY CL51 RENT 07/19/03 07/20/03 07/19/03 07/20/03 0 20036 20027 14tC -E -1C - WO4 24.0 24.0 WH RC 00016 07/20/03 07/21/03 07/20/03 07/21/03 0 TF-C-ftC-3A PERFORM EDDY CURRENT 21000 21001 1-FW - -110 WOG 062582 8.0 8.0 E FW 00012 07/20/03 07/20/11 07/26/20 PRESSLNE SEAL LEAK (@ SLAtVEY REQUIRED) 07/27/04 141 10030 10031 ECLflE & TAG CtNDENSATE SYS 8.0 8.0 OP CN M07/20/07 07/20/15 07/25/09 07/25/17 122 2002 20029 1-fic -E -1C - WO4 DATA AN4 LYSIS 12.0 12.0 nM RC 00016 07/21/03 07/21/15 07/21/03 07/21/15 0 15004 15005 1 M8 -ftSV -1D WO4 062809 24.0 24.0 SM MS 00006 M07/21/08 PDP-C-GWfSR-1 REMACE/ REPAIR ACTUATWt LEW3t 07/23/14 07/25/11 07/28/11 35
[.
, IETWINIK ftEPGti
; LE 3 9(ItJ SY STitRT . 82 l#dIT 1 STEAM GDERATOR "C" 2/TAE 07/17/97 PAGE
I. J GtG REM M MOE ACTIVITY KSCRIPT!WI Lw2 P EARLY EM1.Y DLR ItJR IPT SYS CD R LATE LATE START ' FIN 194
- START FINISI 15006 15007 1-+E -fisV -it WD0 M2815 24.0 24 0 SM MS 0000s 79P-C-0V-+ER-1 ftEPLAMAIEPAIR ACTUATOR LEVER M07/21/08 0743/16- 07/25/11 07/ 3 '11 15000 15009 1-45 -T -tP2 WO4 062700 20.0 20.0 SM TM 00006 M07/21/00 07/23/12 79P-C-+G-NER-6 INSP/ REPAIR STEAN GLAND k 07/23/15 07/3u11
;20030 20031: 1-ftC -E -1C WO4 38.0 38.0 W RC 00016 07/21/15 07/23/05 TPP-C-flC-3A MAft( & #ECH PLl4 07/21/15 07/23/06
.'30014 30015' 1-4fT -PP - -A8 WO4 M 2719 6.0 6.0 E WT WD006272019P-C-P-4 RMV 6ET LAYLP GFt. PCS 07/23/01 07/23/07 07/25/11 07/25/17 1 20032 20033 ftEFTLL C S/G IECGGARY SIN 4.0 4.0 F MS 00016 P-33.2 07/23/05 07/23/09 07/23/05 07/23/09
,20036 20037 1-ftC { -1C .
WO4 10 1.0 QC RC 00016 GC TISE PLLEGIPE VERIFICATION 07/23/05 07/23/06 07/24/00 07/24/01- 1
-20034 20035 C S/G POGT PLUG PRESS 4.0 7-33.2 4 0 OP MS 00016 07/23/09 07/23/13 07/25/09 07/25/13 4; 20030 20039 1-4tc -C -1C WD0 4.0 4.0 W RC 00016 07/23/09 VIDEO SCAN-P06T PLUG LEAK C*. 07/23/13 07/23/09 07/23/13 (
15010 15011 1-96 -IV -1D WD0 M2911 16.0 16.0 SM MS 00006 07/23/12 79P-C-GV-NGR-1 INSP/ REPAIR 07/25/12 07/2u11 07/28/11 22 ' ;0040 20041 1-itC -E -1C Woe 12.0 12.0 W RC 00016 '07/23/13 fiEMOVE EEIPtENT & CLEAN BOLTHOLES 07/24/01 07/23/13 07/24/91 0 20048 20049 1-fic -E ,,
-1C 4.0 4.0 OP M6 00016 DftAIN SEC(NDMtY TD GPERATING LEVEL 07/23/13 07/23/17 07/25/13 07/2$/17 48 30022 30023 1-BD ABC WO4 M2725 6.0 6.0 ME BD WOOM272&M2727 NP-C-P-4 RNV BLOWD0hel SPL PCS07/23/17 07/23/23 07/26/22 07/27/04 77 20044 20045 1-fic -E -1C WD6 12.0 '12.0 W RC 00016 07/24/01 07/24/13 99P-C-fC-2B REMOVE N0ZZLE CVR/ INSTALL MW DIAPEAGM 07/24/01 07/24/13 0-30024 30025- 1-G -Di -1 Woe M2636 2.0 2.0 E CE ItP-C-E-3 Rit/ PEETRATION FLAN (E 07/24/01 07/24/03 07/28/08 07/29/10 103.
30026 30027 1 CE 1 WD4 M2834 2.0 2.0 E CE 79P-C-E-3 REPLACE ESCAPE TRLp0( HATCH 07/2443 0744/05 07/29/10 07/28/12 103. 20046 20047 1-NC -E -1C Woe M2742 12 0 12.0 E RC 00016 07/24/13 79P-C-AC-2B INB7ALL PRIMARY MMAY COVERS 07/25/01 07/24/13 07/25/01 0.. 30020 30021 Flit & VDfT PRIMARY 6.0 6.0 OP RC 00018 07/25/01 07/25/07 07/25/01 10016 30017 - WGl DISC PRESS AIS 07/25/97 0.- 40 40E RC 00018 07/25/07 07/25/11 07/25/07 10012 30013 OPDf LOF STOP WVE C LO(P 07/25/11 0.i 2.0 2.0 OP RC 00018 07/25/11 07/25/13 07/25/11 $1440015 START LUBE OIL & ON GEAR 10 1.0 OP TM 00020 07/25/13 0.t $1030011 07/25/12 07/25/13 07/28/11 1-ftC - - WD4 4.0 07/28/12 71.( REMOVE PRIMARY SPL PCS 4.0 E RC 00018 07/25/13 07/25/17 07/25/13 07/25/17 0.C 0000 40001 EAT TO 195 24 0 24.0 OP RC 00018 07/25/17 204 40006 DRAW 3L54LE 07/2u17 07/25/17 07/2u17 0.0 90 8.0 GP RC 00018 07/2u17 07/27/01 07/26/17 216 40017 ESTABLISH MAIN CO2 VACLAM 2.0 2.0 OP CN 00020 07/27/01 0.0 07/2u17 07/2u19 07/29/12 202 40003 P-13 WALX D0let WITH SEC3.0 07/29/14 43.0 3.0 OP CE 00018 07/27/01 07/27/04 07/27/01 07/27/04 406 40007 ESTABLISH CSfTADOENT 6.0 VAC 6 0 OP CE 00020 0.0 07/27/04 07/27/10 000 40009 (P-1E INTEG LIST 8.0 07/27/04 07/27/10 0.0 9.0 OP CE 00020 07/27/10 07/27/18 07/27/18 07/29/02 8.0
ETicutiqEPtRt-WIT 1 STEM GDetATOR "C" OUTAGE PE' t.W. 3 3Gli BY START 42 ' . 07/17/87
.I J GIS REM LM2 P - EARLY EAft.Y
. MIE . MK LATE LATE T ACTIVITY DEE3tIPT191 DLR DlJt DPT SYS CD R STNtf FINI!N START FINI91 F 40010 40011 TEST CWif PtAE & D04 M.V8 16.0 16 0 OP CE 00020 07/27/10 07/28/02 07/27/10 07/28/02 40012 40013 E AT TO 350- 6.0 6.0 OP RC 00020
' ~
07/28/02 07/28/08 07/28/02 07/28/08 40018 40019 EAT TO 547 60 6.0 CP RC 00020 07/28/08 07/23/14 07/28/08 07/28/14 40020 40021 BWl0N DILUTI(DI' ' 5.0 5.0 @ RC 00020 07/28/14 07/23/19 07/28/14- 07/2S/19 ' 40022 40023 Pft! SYSTDI LEM CEOC 4.0 4.0 OP RC 00020 07/28/14 07/28/18 07/28/15 07/28/19 l 40024 40025 CRITICALITY 1.0 1.0 OP RC 00020 07/28/19 07/28/20 07/28/19 07/28/20 40024 40027 P0let TO 5X & ROLL tut 91E . 4.0 4.0 @ TM 00022 07/28/20 , 07/29/90 '07/28/20' 07/29/00 40028 40029 REACTWt TO 25X poler 6.0 6.0 OP AC 00022 07/29/00 ' 07/29/06 07/29/00 07/29/06 40030 40031 30X BGt0N SOAK 20.0 20.0 OP RC 00022 07/29/06 07/30/02 07/29/06 07/30/02. i. 40032 40033 , TERRY TLRBIE RLDi 4.0 4.0 OP AF 00022 07/30/02 07/30/06 07/30/02 07/30/06 ( 40034 4002 BORON ACC0WTABILITY 8.0 8.0 OP RC 00022 07/30/06 07/30/14 07/30/06 07/30/14 ( 40034 40037 CEM HCLD & BORON CLEAN LP 4.0 4.0 CP RC 00022 07/30/14 07/30/18 07/30/14 07/30/18 ( 4003 40039 DLoli DolM 10.0 10.0 @ 90 00022 07/30/18 07/31/04 07/30/18 07/31/04 ( 40040 40041 TO 100X P0llER 24.0 24.0 OP RC 00022 07/31/04 08/01/04 " 07/31/04 08/01/04 ( a i
., 4 1 JULY 17,1987 - 1600 MEETING
\
l i,W' 9 .3' .'
- 1. Plant Status ased on results of samples from Hotwell and S/G f ".'U --
'A' and 'B',
? '+ discharg~es will be handled via norma 1' release forms.. i Draining of 'B' S/G had _ started, but water temperature was
, determined to be too high - S/G will be filled before draining.
Procedure for "a.nting 'C' S/G was reviewed by SNSOC and approved with changes. Jumper evaluation will be performed for hoses to be used. 5 Venting of 'C' S/G and purging with nitrogen will be done in a staggered f ashion vs concurrently. i :. - Cables and air lines through Equipment Hatch will be in ple.ca . tonight and penetrations sealed. Sequence of operations for 'C' S/G: T* Venting and purging of S/G secondary [ ' d* Fill S/G secondary ~* ~ ' t >
", <
- Drain S/G primary
,V -i
- Start first drain of S/G secondary
-. l
'C' S/G Manway removal most likely early on 7/19. NRC to be
. notified prior to removal.
- 2. Technical Task Group Alternative inspection /NDE techniques have been developed for range 7, of conditions.
, l Equipment and technical support personnel will be on site shortly !
for tube inspections. j
- l A IS Sample plan (per T.S. Table 4.4-2) is being prepared.
. ]
- 1 Repair / corrective action plans under development with Westinghouse.
$ valuation of S/G ' A' and 'B' response is underway.)
Videotape confirming previous plugging will be available for review. l l FoI 4-F7- W / l b/.ttf
1 Pass 2 07/18/87
. .. g
, l' 3. NS&L s
L f.
.h[hh, w- -
Detailed Sequence of Events (SOE) is being finalized and will be compared to Control Room recorders. Evaluation of implementation of Emergency Plan during event in progress.
. SOE information is being used to model event on simuistor.
Westinghouse has also requested data for modeling on their
, simulator.
IN?O team was briefed on event. NAPS and Surry Check Operators will be interviewing the?operatore
, iho were on duty during the event.
- 4. Indus try Interface See-through model of primary plant loop will be on site and set up in Electric Shop of Training Building.
. u--
Completed tour for Bill Vakos (Virginia Senate candidate). Surrounding county officials have been contacted % d extended invitations for tours / meetings. 9' - Richmond Times Dispatch reporter was walked through the event using the simulator. W News conference is tentatively scheduled for 1500 on 7/20/87 at NAPS. INPO team plans to talk to operators who were on duty during event. A " Town Meeting" for Louisa County citizens is being planned to be held at NAPS within next 2 weeks.
- 5. Health Physics Results of environmental samples analyzed by independent contractor
.:q- will be available on 7/18/87.
Started review of SPDS radiation monitor data.
- 6. NRC The meaning of "100% inspection" of S/G tubes during Unit i refueling outage was clarified. All tubes were inspected from the hot leg end, but 16% of the tubes were inspected full length. This scope was discussed during the June '87 meetings with NRC.
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.'J, JULY 18,1987 - 0830 MEETING p u , .3 3 f.Mi.y
>. *e l '1. . Plant Status ( Plant Conditions: Pressurizer Level 50%; RCS Pressure 40 PSIG, RCS N, . - Temp.115'F, 'C' S/G Secondary Pressure 8 PSIG. +. 9 , pesults of 'C' S/G Air' Sample taken at 1440 on 7/17/87: H215%, d?. - .- y , ; 0 13%, 2 N 77%, 2 Xe 10,000. times HPC.
- 4.
O D 1. -
' A' and . 'B' S/Gs have been filled and are being drained. ' Hotwel>l
'O Ta's been drained. Copies of all release forms will be asallable for.
.NRC review. ,
layup system spool pieces have been installe'd for 'A' and 'B' ~g (gWetS/Gs. h,, .1h~ # 'Gt ~ Decision was made to use the installed Process Vent radiationd 1 monitors for accountability and tracking of releas&during venting
*of 'C' S/G' secondary. The monitors will automatically isolate flow
, , ' path if levels reach setpoint.
;n;.
, c pe point of connection for venting .the 'C' S/G , secondary was s
thanged from a vent valve (1-MS-80) to valve on FT-1494'. ,
.c Q
M r'. Westinghouse to set up breathing air inside containment today. - - j
%',- . 2. Technical I
Virginia Power and Westinghouse have finalized inspection 4 a kh . jg alternatives. Will discuss plans with NRC today. d)ff A Westinghouse has modeled event on their simulator and will refine as additional data is available. s MM' gg ( ,,, - NDE will review plugging tapes today and should complete by 1600 gtfji@jee meeting. N . Mtation Chemistry department is evaluating conditions seen in S/Gs f C %'and'B'. All. groups were cautioned to fully document any irregular conditions .
+ '
found during entry and inspection of any of the S/Gs. { Full QC t Teoverage will be available. J > Forn-tr~4G,7
. . , . bla6
- l. l,
- v. Pags 2 h4 '
07/18/87 e p? 13. NS&L _ l
- b. ,C -
E,17 - Detailed Sequence of Events (SOE) has been completed and is in LN' typing. NRC review of SOE to start today. ?
' SPDS, Pl.ots of various plant parameters are being created. So far, only the recovered. data - recorded on the first tape (0629 to .0845) has been I
e,* 9. - -
) , .t . gheck Operator interviews with on-duty operators will start today.
?c! ,
- 4. Industry Interface
.!1
- 1 An article appeared in today's Richmond Times Dispafch. The.
Superintendent was presented. of Operations was interviewed, and a positive image INPO team will cover the following areas today: S[G maintenance history, inspection plans for 'C' S/G, operator interviews, and review of chemistry data.
-5. Health Physics r 1 1
i.;~ Will be checking with Teledyne on results of environment %1 sampling.
.( , fi -
Plots of radiological data will be generated from SPDS. >} w nMpf -
'Qatus of . Air ',jI .<
f Tdatermined. Ejector Monitor (RM-SV-121) repairs will bd Tech Services was requested to review I. , monitors relied upon. during the event. calibration data for all
+- -
First draft of radiological SOE will be completed today.
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f 4.- l t," JULY 18, 1987 - 1600 MEETING j, '
,, , 1. Plant Status b;
- Plant Conditions: RCS Temperature 120*F, RCS Pressure 40 PSIG,
,' Pressurize'r Level 40%, . 'C' S/G Secondary Pressure 6 PSIG, 'C' S/G Level 63%.(NR)
I'
' -DB S/G has been drained and refill is in progress. draining of ' A' (S/G to start after 'B' is complete.
-gVgnting of 'C' S/G secondary is in progress with a flow rate of )'
.30 ft*/ min. No significant change seen~1n process vent radiation monitors.
(
~
NOTE: concentration is diluted by makeup air before reaching monitors.
'; . . . w . u.
- Discussion was held on lineup to be used during N2 purge and filling of n . "- 'C' S/G secondary. . It was decided to use flowpath through process
!. # *g ',
. vents to vent gas when S/G secondary is being filled.
i
-{silth Physics needs to establish criteria for terminating vent;ing ind'?
ptFrging of 'C' S/G secondary (i.e. , H2 5 4% and activity levels 5 some . i r ,,, .%rcentage of MPC).
; . .i .9 4
',J.. -
e OP's used to control the evolutions on secondary side of the , , .** f * (; C' S/G will need to be revised to reflect the above decisions. s a 3
;'+
' - - Westinghouse will be provided access to Auxiliary Building to stage 7 equipment for movecent into containment. . Westinghouse and Health Physics to decide on availability of staging area in Auxiliary Building. P Technical
'- Was been verified that tube stabilizers are available.g v
. f. - Briefed NRC on inspection options.
. ,&; - Optic probe is available to explore a damaged tube prior to using E/C y4%J- probe if needed.
..[l'QS y
' , i.e.L
. y, 4TDE completed review of plugging tapes and found no discrepancies.j ,
- Correlation of S/G VR level to elevation of S/G components was generated.
,,...,u...
f'
'b 1S Inspection plan has been prepared - it includes 306 tubes, most of z,
ghfch are outside row 10. t kn - eg'eived information from Northeast Utilities on their tube leak event ' P,>.b. K' 'ich will be reviewed tomorrow.
.i ., r.
- f. ..-. . i ' .
F02,8-9746) L b/a 7 fa 1
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- g. 7/19/87 i.
{
)
.,3. NS&L
- l e, )
l.I
.I
. Distributed detailed chronology of event and package of plots (from SPDS) of various plant parameters.
.- / - Westinghouse was asked not to perform any additional analysis of event J until formally asked. l
. ! ,,, G 1 j
'.% (Evaluation of implementation of Emergency Plan is in progress.; I 4 : <C .p - NRC Project Manager, Leon Engle, will be on site July 21, 1987, w ,4 ..
- i. '4. Industry Interface
- An interview was conducted for Channel 9 TV (Washington, D. C.) . " . " . ~.'*',n. INFO has exited. They will be getting additional information as.it.
f becomes available. )S r.,n 2 . [ a 'l , ? 5. Health Physics c- a Pa.T jkN' g y:'.', .
- Results from Teledyne will be available on Monday. a. .
' - Continuing to review data and prepare chronclogy of 9tiological
- g. '- , events. #v
- u. .a -
?. $ - Expect to interview Health Physics' personnel on duty during the eve'nt l".'
g .) (.V Honday. Al Stafford and Ed Schnell will conduct the interviews. l I
- f. '
$ .,e-.N.' '
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( q[p g - aq i , gp })g l - gm. h - t 1 j5 1: , _ CHRONOLOGY-4 ' STEAM CENERATOR TUBE RUPTURE EVENT
@ NORTH ANNA POWER STATION UNIT 1-JULY 15. 1987 f ,
- 1. E
'following chronology vas~ reconstructed from alarm the print ou typewriter" attached to the Control Room P-250 process-Events. Recorder -(Dranetz)l driven by the Hathaway ~ annun. computer, . the Sequence ciator. system, the data
' Support Center, RO.and SRO logs and interviews,
. Room recorders.
Selectedof.each
.explicitly significance data was transmitted datum'as.it from identified a the various sub-event or records base demonstrated, chronology cantor~ implicitly, a sub-event in the sequence.-
accuracy,and effectiveness of the measures applied to .
'Once the data was transcribed, a review was performed t o identify the
- synchronism'for time of the various data sources..
y .for' synchronism was the Automatic Pzr Lo-Lo SI. The The principal ite SI action incor,m selected porates several actions including feedwater that make it readily. comparable over all records. isolation and normal charging isolation Recorder logged SI at The. Sequence of Events 06:35:24:805, the alarm typewriter on the P 250 logged SI at 0639. However the earlier Reactor' Manual Trip-has' caused the P-250i
- its scan races. . The P-250 Post Trip review logged SI at'06:35:24 plus e
i cycles, which equates to 06:35:40.86. records full normal charging flow and full power feed flow to'the steamTh { generstors, initiated. Byapproximately-16 seconds after the reactor trip had ybeen manua 06:34:21 . i
. spa'and feed flows are a, bout 600KLBH to 800KLBH.the ERFC data set cha reached a stable but low level . By 06:34:34, all flows had before 06:34:14.'. This. chronology will useIt appears that SI occurred at or slightly 06:34:14.
1
,are Forasautomatic follows: initiation of Safety Injection, the clock comparisons RECORDER TIME Sequence of Events Recorde r (SER)
P-250 Computer (Alarm Typovriter) 06:35:24:805 ERF Computer (ERFC) 06:35:41 M 06:34:14 For Reactor Manual Trip the clock comparisons are as follows: RECORDER TIME Sequence of Events Recorder (SER) P-250 Computer (Alarm Typewriter) 06:35:04:548 ERF Computer (ERFC) 06:35:24 06:33:56 Fot A - f 7-Nl k D/.1g
C.y ,, , . ,
., 1 W, 3 .. n c - , 'l N *
,)
%g CHRONOLOGY g STEAM GENERATOR TUBE RUPTURE EVENT NORTH ANNA POWER STATION UNIT 1-JULY 15, 1987 July 14,21987 I
/ 2238' LtoAir; Ejector.
erratic. Radiation Monitor (RM-RMS-121) was declared inoperable due operation.- LJuly 15, 1987' 0630- ! An alarm was received on the Unit 1 annunciator panel for Main Steam-(High "A" andRange) Radiation-Monitor. When checked by backboard operator,. alarm.
"B" monitors were in " Alert" and "C" monitor was in "High" 0631 !
Unit 1 CR0 observed the pressurizer level decreasing rapidly. 0632 ]
,, U-2 SRO recalled'the Shift Supervisor and.U-1 SRO to the Control Room.
U-1 CR0 took manual control of charging and set FCV-1122 to full open. Received-Pressurizer low pressure. alarm at 2135 psig (Alarme Typewriter).
-0633' l Shift Supervisor entered the Control Room and directed letdown isolation. '
CR0 initiated realignment of charging' pump suction'to RWST and.a 2% per minute. turbine ramp down. Third CR0 (Backboards Operator) assumed BOP duties on Unit 1 Control Board.to assist Unit 1 CRO. ! 20.3%.) (Alarm Typewriter: Make-up' commenced. VCT low level alarm
,0634 STA' arrived.in the Control Room.
i
' Alarm Typewriter: Pressurizer Pressure 2109 psig.
Superintendent manually tripped.of Operations was notified and directed the Unit to be 1 0635 At direction of Shift Supervisor, U-1 CR0 manually tripped the reactor and turbine and initiated EP-0. CR0 observed pressurizer love.1 at ! approximately at 45%manual the time of the and pressurizer trip. pressure at approximately 2100 pois 1 POST TRIP REVIEW: iInitial Event 06:35:24 Rx Manual trip (2) 0.00 sec. 1
. Turbine Trip and P7 0.16 High Flux Rate Trip 0.33 Rx Manual trip (1) 0.60 Par - Lo Press Trip 2.80 ;
Sta Gen B Lo-Lo Trip 4.2 Stm Con C Lo-Lo Trip 4.5 PAGE 1
4
- * ' .s
- 3...
,.M.
,j. i i
It 'is concluded theti the' P-250l led, the SER was within 20 seconds of the P-250 and the ERFC was about one minute behind the P-250.
' The. chronology.that follows is.' annotated by clock time based on the P-250.
~
'All the events.thac occurred within each minute are listed in order of ,
- occurrence as could best be determined,
.i
-l i
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k Sem Gen A Lo-Lo Trip; 4.5' , lm " Par.Lo-Lo SI 16.86L F 5 l Manual SI Train "A".(1)' 43.38 f ' I
' Manual SI Train:"B",(2)- I44.97 seconds I:
e
- p. ' Alarm Typewriter: . Auxiliary Feed Water Pumps Start. . . .VCT: leve1L 22.1% : 1 increasing (indicates that charging pump suction shift to RWST is 'f
'E-completed.)' .. y
.SER: ; Main Feedwater Pumps Trip '(06:35:25) -
0636 t Unit?1 CR0 noted pressurizer pressure less than' 1700 psigLan'd pressurizer' level;1ess.than 5%.. .
. Alarm Typewriters-Pressurizer level 2.7%. Main Feed pump' Breakers g tripped. "B". Charging Pump Start. '"A'? and i"B" ' LHSI pumps start. ~
.0637 AlarmITypewriter G-12' breaker open.
', 0639 'A Notification of Unusual Event was. declared. Unit 2 SRO' assumed. duties as Interim Station Emergency Manager and initiated the EPIP's. (Step 21 of EP-0)'
'0640* Entered EP-3 from Step 23 ofLEP-0. ,..
'0641, Alarm Typewriter: T AVG 1ess than 543*F. P-12 interlock set.
'0642 Alarm Typewriter: "C" Steam Generator level increasing above 18%
narrow range. i 0643* ' Closed "C" Main Steam Trip Valves (Step 4 of EP-3). OpevM Mo^#*"*5 Eln Ws ^ 0644 SI and Phase A reset. LHSI. pumps "A" and "B" shutdown. (Steps 9, 10, and 13, respectively of EP-3) -S C C R " d'" 0645 ' Alarm Typewriter:."C" Steam Generator at.25% narrow range and'
.'inc reasing. . ,
1
.0646*~ Auxiliary Feed Water to "C" Steam Generator isolated.- (Shift Supervisor confirmed Steam Generator Tube Rupture in "C" Steam.
Generator based on "C" Staag Generator level continuing to rise.) 1 040 0 E2FC *, "C " . n%, die % Mu Cloud . , 0647 Alarm Typewriter: "A" Steam Generator at 23% (Narrow Range) and increasing. 0648 ERFC: Graphs of; pressurizer level and RCS pressure reveal increasing j level and. pressure. (Also noted on the strip chart in the Control ] Room.) J 0649 Alarm Typewriter: Pressurizer to Press / Steam Line High Flow SI circuit blocked. (The Note prior to Step 15 of EP-3) Commenced rapid cooldown
, on "A" and "B" steam dump valves. (Step 15 of EP-3) Alarm Typewriter: "B Steam Generator level at 25% (Narrow Range) and increasing. Alarm Typewriter: Pressurizer level 8.5% and decreasinB.
0650 Unit 1 CR0 noted pressurizer level off scale low. PAGE 2
6;
.6 t !s
- 0651 Initial notifications made to the State / Local' Governments (EPIP 2.01)
L and' NRC (EPIP 2.02). 0652 Alarm Typewriter: "A" Te - 509.5'F "B".T, - 509.5'F "C" T c - 523.5'F' 0654' Interim Station Emergency Manager upgraded event classification to
" ALERT".
Alarm Typewriter: "B" Main Feed Pump breakers racked to test and closed.(To provide a flow path for condensate pumps to feed."A" and.
"B" Steam Generators) Steam Generator "A" and "B" pressures at 589
.ps13 0655' Initiated. EPIP-3.01, 5.03, and 5.04 (Call Out, Accountability, and -
Access Control). 0657' ' Strip Chart: RCS Temperature being maintained at 480*F (Step 15 of EP-3). Alarm Typewriter: Pressurizer Spray control at 100% demand. Valves "A" and "B" open (step 18 of EP-3). 0658 . Unit 1 CR0 noted pressurizer level on scale and increasing. 0659 Alarm Typewriter: Source Range Nuclear Instruments manually re-energized. (Intermediate Range Nuclear Instruments were
- undercompensated.)
0700 Alarm Typewriter: Pressurizer low level heater cut off cleared.(level at 15% and increasing). Pressurizer heaters energized (835 KW). 0701 Unit 1 CR0 manually de-energizes pressurizer heaters. 0702 Notifications made to the State / Local Governments and NRC of uograded alert classification. 0704 Opened one Pressurizer PORV to reduce pressure (Step 19 of EP-3). SRO observed pressure reduction of approximately 40 peig and instructed ! CR0 to close PORY and spray valves (Steps 18 and 19.of EP-3). Alarm i
' Typewriter Pressurizer Relief Tank pressure 15 psig.
SRO noted "C" Steam Generator level increase stopped. SI reduction criteria met (Step 21 of EP-3). "B" Charging Pump secured (Step 22 of EP-3). Initiated the isolation of BIT flowpath (Step 24 of EP-3) and established the normal charging flowpath (Step 25 of EP-3). 0706 Shut "A" and "B" pressurizer spray valves. 0709 Alarm Typewriter: Non Regenerative Heat Exchanger outlet flow 47 gpm. (Evaluation of this entry indicates that normal letdown had been i l restored in accordance with Step 29 of EP-3. l 0710 Alann Typewriter: Pressurizer heater breakers closed (Step 31 of EP-3). l ( i y-- PAGE 3
3, y i ~ m;j( , y 14- c )9, t , , ,
'}a l, jf . ,.f N it - <
' + >
l s i~.
"n ,
i
, y. o[11: Alarm Typewriter: Pressurizer heater husker.a closed (Step 31 of -
DA V.. -EP-3).- '! g, .
.g _
? " l Alarm Typewriter: Secured "C" and "B" RCP's-(Step 38.of EP-3).
, d j. dl)0713 ,.
?%j ! f 0714 LAlarm' Typewriter: Spray demand 76%.'(From this time forward RCS t
i 'f, presenre-is maintained by manual e.gntrol' of spray and heaters.) v ; ,
'/ ' i,)4 715 (Superintendent of Operation and/SRO-On-Call arrived in the Control o .g Room.
[071'8' ThansitionedtoES3.1" POST-STEAMGENERATORTUBERUPTURECOOLDOWN
' USING BACKFILL" (Step 42 of EP-3) .
0720I Stat' ion. Manager arrived in the Control Room. 0721 Alarm Typewriter: AFW Feed Pump 3A to "C" D:eam Generator secured. 7 0722 Alaru Typewriter: Pressurizer 1Wel 73% and decreasing.
,.y a 0723 ' Marm Typewriter: L AFW Feed Pump' 3 Leo "B'? Sec.um Generator secured.
(Jabsequently AFW pumps are run intavaittently to ' support Steam Cenerator feed requirements.)
, , o !
0725 oAlaraTypewriciri ' Started "B" Condensate pump-(Both "A" and "B"
, Condendate pumpa now running). 7 !
, J ,.
0727 Began RCS cooldown in accordance with ES 3.1. ' l 0730 Assistant. Station Mana3er arrives in Control Room and initiates
' transition of EPIPs and communications from Control Room to TSC.
3739
) ?? 3
, Station Manager assumes Station Emergency" Manager po$1 tion. ,
J 0745 fl e n Typewrfter: Turbine on the turning gear. i 1 0756 Condenser Air Ejector manually diverted to containment. 0757 Technical Support Center activated. 0810 Alarm Typewriter: Secured"B"condensaftepump. 0820 Corporate Emergency Response Center activatatt. 0845 Started "B" RER pump for system warm-up (Step 9,o1 ES 3.1). l e 1
.0853- Alarm Typewriter: Closed "A" MFE breakers. (Breakers in test to 4
permit opening of pump discharge valve to use Condensate Pumps for a food to Steam Generators.) 0857 Alarm Typewriter: Open "B" MFP lireaktra (To permit isolation of "B" MYP to stop' spraying from "B" pump suction relief valve. 0900* Loose Parts Monitoring System Alarm on "C" Steam Generator. 0915 Local Emer ency Offsite Facility activated. Commenced using auxiliary spray to lement RCS.elepressurization. PAGE 4 !
0949 Containment partial pressure exceeded allowable set point due to Air Ejector exhaust diversion to containment. 1049 Pressurizer PORV Key Switches to "AUT0" for NDTT protection. 1108 Entered Mode 4. 1153 Cycled reactor trip breaker to re-enable automatic Safety Injection. 1200 Placed "A" and "B" charging pumps and "B" LHSI pump in " Pull-to-Lock" in accordance with 1-OP-3.3. 1215 Secured "A" Reactor Coolant Pump. 1219 Placed RHR System in service to continue RCS cooldown (Step 9 of ES 3.1). 1254 . Main Steam System secured in accordance with 1-OP-28.1. 1312 Restored Air Ejector exhaust to normal alignment. 1330 Entered Mode 5 1335 Station Emergency Manager terminated the emergency. 1336 s Notified Nuclear Regulatory Commission, State and Local Governments of - termination of emergency status. 1336 Implemented Recovery Organization.
- Approximate Time Bes a cm ut' , s'c u..J/w srA o bs m>J iu s PAGE 5
~e, l
s . i
, a,& : .
4 1 l q
.]
1 JULY 19,1987 - 0830 MEETING
- 1. Plarit Status'
'l
- Plant Conditions: RCS Temperature 112'F, RCS Pressure 45 PSIG, Pressurizer Level 40%, 'C' S/G Secondary Pressure 3 PSIG, 'C' S/G Leval {
90% (VR) . - L
- }6 - TC' S/G vent complete. Gas space sample results indicate 0% H '
2 1
~
22% 0 , 78% N ' I 2 2 131, 133 - ~ 10 *
- m Ci/m1, Xe 10 s Ci/ml '(both values slightly less than MPC). To complete venting operation, level
, was raised and pressure was increased via N feed.
2 ,
'C' S/G - Today's plan is to drain (via blowdown) to 70% (VR) on ,!
secondary side and stop. The secondary level will be monitored as the j
'C' loop primary drain continues to attempt determing height of the ,
tube failure. E E 'B' S/G fill was completed. Q 'A' S/G drain and fill is proceeding today.
) .
l
'C' S/G Primary manways should come off early tomorrow morn #ing.
QA is prepared to support this activity and the station photographer is-
,. on call to take pictures.
C' S/G should be ready for )( to remove diaphrams during the day tomorrow. l 1
- 2. Technical
- Visual Aids (S/G cutaway and 'C' S/G tube plugging) are on-site for !
Tuesday's press conference. Also working on a sketch of a S/G tube section.
- Length of the optic system probe was determined to be 17 feet.
i
- Work is proceeding on technical sections of the report.
'C' S/G history is being typed today, j
- The S/G Inspection and Repair Iogic is being revised to incorporate the plan for dealing with the potential for a loose part in 'C' S/G. (NRC was told about this change to the plan when they were briefed on it yesterdsy).
l NOTE: During venting of 'C' S/G secondary, a loose parts alarm was received. { S7 4-F 7-W/ )1 l b4 1 l E 1- - 1
[ l(.> Pcg3 2 t 7/19/87
- 3. @ _
- The draft sequence of events and the SPDS displays ere being' reviewed along with the Operator interviews and procedures used during the event.-
- The on Julyinitial loose parts alarm was received at 0900 following the event '
15, 1987. It may be desirable to interview the STA.The STA reported that the noise IThe Operator interviews and INPO exit were completed yesterday Positive feedback procedures was during the received on Operator response and use of event.
- Work is progressing on writing report.
4.- Industry Interface !
"See through" model will arrive this afternoon around 1800.
- NRC will be updated on 'C'
~ schedules. S/G status to allow them to adjust their and H. Conrad to arrive Monday night.NRC current schedule calls for
- 5. . Health Physics '
e
- Draft Health Physics sequence of events is being reviewed today,
- 6. General ,
1
- Morning meetings will be at 0900 rather than 0830.
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1 . h[S k hh[V '//7'('/ ggg l LIST OF FIGURES , Figure 1 - Pressurizer Level, Charging Flow and Letdown Flow Figure 2 - RCS Pre,ssure, RCS Temperature and Pressurizer Level Figure 3 - Steam Generator 'C' Pressure'and Level Figure 4 - Steam Generator 'B' and 'C' Pressures Figure 5 - Steam Generator 'B' and 'C' Levels Figure 6 - RCS Pressure and Steam Generator 'C' Pressure Figure 7 - Pressurizer and Steam Generator 'C' Levels Figure 8 - Main Steam Line Radiation Monitors -(N.R.C.) i Figure 9 - Steam Generator 'C' Feedwater Flow, Steam Flow and Level Figure 10 - Containment Particulate and Area Gas Radiation Monitors Figure 11 - Pressurizer Level Figure 12 - Steam Generator 'C' Pressure . Figure 13 - RCS Loop 1 Pressure Figure 14 - RCS Loop 3 Pressure Figure 15 - Reactor Vessel Level i
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. dissemination 'of 'information (EPRI, . Network) should be rescheduled -
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' until. after the NRC presentation.
y: ' , h
- The Emergency Response Report and the Health Physics' Response Report
) ;- : are nearly ' complete. . i 4.- Health Physics , ew Results of offsite.. samples from Teledyne have beerJreceived. No abnormalities'have been noted' : Sample showed only background levels.
- Interviews of HP personnel (involved with the veersency response:is' ,j.-
1 Cy- nsatjy completed.. .
, - Onsitia radiological samples' are still being ^ processed. b 5.. Industry Interface
'- Press groups have been notified that a cenference wi1Nbe held on--
Wednesday (July 22, 1987) at~11:00f.t. m.. .j 4 5
,< e y e The State' Department' of Emergency Services wehe aldo notified.
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- Town meeting previously scheduled has been out en " hold".
( ., ' - A tour and presentation for . local-governacnts is ' scheduled for Friday l(July 24,'1987). , e o
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