ML19327B306: Difference between revisions
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O W Powin COMpar ? | O W Powin COMpar ? | ||
, 231 w. MICHIGAN.F.o BOX 2046. MILWAUKEE.WI63201 914;pri.2345 plp | , 231 w. MICHIGAN.F.o BOX 2046. MILWAUKEE.WI63201 914;pri.2345 plp | ||
^' | ^' | ||
VPNPD-89-550 10 CFR 50.73 ; | VPNPD-89-550 10 CFR 50.73 ; | ||
NRC-89-130 l | NRC-89-130 l October 19, 1989 ; | ||
October 19, 1989 ; | |||
tc l U. S. NUCLEAR REGULATORY COMMISSION - | tc l U. S. NUCLEAR REGULATORY COMMISSION - | ||
g ' | g ' | ||
Document Control Desk Mail Station P1-137 Washington, D. C. 20555 Gentlemen: | Document Control Desk Mail Station P1-137 Washington, D. C. 20555 Gentlemen: | ||
DOCKET 50-266 LICENSE EVENT REPORT 89-008-00 s AMSAC NOT ENABLED AS REQUIRED ' | DOCKET 50-266 LICENSE EVENT REPORT 89-008-00 s AMSAC NOT ENABLED AS REQUIRED ' | ||
BY TECHNICAL SPECIFICATIONS ! | BY TECHNICAL SPECIFICATIONS ! | ||
POINT BEACH NUCLEAR PLANT, UNIT 1 j | POINT BEACH NUCLEAR PLANT, UNIT 1 j Enclosed is Licensee Event Report 89-008-00 for Point Beach ! | ||
~ Nuclear Plant, Unit.1. This report is provided in accordance with i 10 CFR 50.73(a)(2)(1)(B), "Any operation or condition prohibited l by the plant's Technical Specifications." ; | |||
Enclosed is Licensee Event Report 89-008-00 for Point Beach ! | |||
~ Nuclear Plant, Unit.1. This report is provided in accordance with i 10 CFR 50.73(a)(2)(1)(B), "Any operation or condition prohibited l | |||
by the plant's Technical Specifications." ; | |||
r This report describes an event in which the ATWS mitigating system ' | r This report describes an event in which the ATWS mitigating system ' | ||
actuation circuitry (AMSAC) was automatically bypassed at a power ! | actuation circuitry (AMSAC) was automatically bypassed at a power ! | ||
level greater than t'ne 40% power level required by the Technical Specifications. A supplement to this report will be submitted at a ; | |||
; | ; | ||
later date. | later date. | ||
Line 59: | Line 47: | ||
1 L Enclosure l Copies to NRC Regional Administrator, Region III > | 1 L Enclosure l Copies to NRC Regional Administrator, Region III > | ||
NRC Resident Inspector , | NRC Resident Inspector , | ||
l' f.gogic( 'O 'p i i | l' f.gogic( 'O 'p i i u | ||
u | |||
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. 3y,,.== su e e .a 6 .. e===T vee ea.e s.w | . 3y,,.== su e e .a 6 .. e===T vee ea.e s.w UCENSEE EVENT REPORT ILARI 6,,, n' ees e, mane. e. - | ||
UCENSEE EVENT REPORT ILARI | |||
6,,, n' ees e, mane. e. - | |||
Point Beach Nuclear Plant, Unit 1 e is i o io l e 121616 1 loF}0 11 | Point Beach Nuclear Plant, Unit 1 e is i o io l e 121616 1 loF}0 11 | ||
.- m AMSAC Not Enabled as Required by Technical Specifications evem en e, up. .u . ., n , u n i,i ., . . .. ..u 6v.. ., | .- m AMSAC Not Enabled as Required by Technical Specifications evem en e, up. .u . ., n , u n i,i ., . . .. ..u 6v.. ., | ||
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,, t=e ,eem m. so ,v., w mmew wc,.i,e | ,, t=e ,eem m. so ,v., w mmew wc,.i,e | ||
.= m au g ,8' tm a esseni se eeni.i m tensieHei _ | |||
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Line 96: | Line 66: | ||
i s | i s | ||
, m M Ht H.I _ | , m M Ht H.I _ | ||
, Igj _ | , Igj _ | ||
m eninHtitel gelteniguel 30 ,6.iW He.14l v m e. in H.i e n. .H n a n.ien.i | m eninHtitel gelteniguel 30 ,6.iW He.14l v m e. in H.i e n. .H n a n.ien.i | ||
Line 106: | Line 75: | ||
uom ......, .. o 13;;c- atr,A1;* c v.. . . . . . , c- n, 13;te atr,Ay;a - . | uom ......, .. o 13;;c- atr,A1;* c v.. . . . . . , c- n, 13;te atr,Ay;a - . | ||
B , , , , , , , , , , , , , , , | B , , , , , , , , , , , , , , , | ||
I l l I I I I i 1 l 1 i i 1 wmewmu .. , ceeo n.. i.e.,- o., ,p. | I l l I I I I i 1 l 1 i i 1 wmewmu .. , ceeo n.. i.e.,- o., ,p. | ||
~~') ,n t,,,. - e m cree si ,u,a u re, 7one, 112 013 81 9 awe e, ,6 . . ... .- ,, . .i On September 10, 1989, Point Beach Nuclear Plant Unit 1 was decreasing power from greater than 40% to less than 40%. At somewhat less than 40% power, the ATWS mitigating actuation circuitry (AMSAC) is designed l | |||
~~') ,n t,,,. - e m cree si ,u,a u re, 7one, 112 013 81 9 awe e, ,6 . . ... .- ,, . .i On September 10, 1989, Point Beach Nuclear Plant Unit 1 was decreasing power from greater than 40% to less than 40%. At somewhat less than 40% power, the ATWS mitigating actuation circuitry (AMSAC) is designed | to be bypassed automatically based upon first-stage turbine pressure. | ||
Power as indicated by first-stage pressure at this power level during power decreases is less than reactor power. In fact, the AMSAC was cutomatical).y bypassed at about 42% reactor power. Technical Specificati ms require the AMSAC system to be enabled at greater than 40% reactol Dower. Power was reduced to 38% and held until the bistable cc.t .d be reset. The enable / disable bistable setpoint was reset to 300 to ensure the operation of the system at less than 40% | Power as indicated by first-stage pressure at this power level during power decreases is less than reactor power. In fact, the AMSAC was cutomatical).y bypassed at about 42% reactor power. Technical Specificati ms require the AMSAC system to be enabled at greater than 40% reactol Dower. Power was reduced to 38% and held until the bistable cc.t .d be reset. The enable / disable bistable setpoint was reset to 300 to ensure the operation of the system at less than 40% | ||
reactor power. A revision to the Technical Specifications will be oubmitted to the NRC to clarify that turbine power of greater than 40% | reactor power. A revision to the Technical Specifications will be oubmitted to the NRC to clarify that turbine power of greater than 40% |
Revision as of 23:22, 31 January 2020
ML19327B306 | |
Person / Time | |
---|---|
Site: | Point Beach |
Issue date: | 10/19/1989 |
From: | Fay C WISCONSIN ELECTRIC POWER CO. |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
CON-NRC-89-130 LER-89-008, LER-89-8, VPNPD-89-550, NUDOCS 8910300134 | |
Download: ML19327B306 (2) | |
Text
.
e
'O
- 3 ,
O W Powin COMpar ?
, 231 w. MICHIGAN.F.o BOX 2046. MILWAUKEE.WI63201 914;pri.2345 plp
^'
VPNPD-89-550 10 CFR 50.73 ;
NRC-89-130 l October 19, 1989 ;
tc l U. S. NUCLEAR REGULATORY COMMISSION -
g '
Document Control Desk Mail Station P1-137 Washington, D. C. 20555 Gentlemen:
DOCKET 50-266 LICENSE EVENT REPORT 89-008-00 s AMSAC NOT ENABLED AS REQUIRED '
BY TECHNICAL SPECIFICATIONS !
POINT BEACH NUCLEAR PLANT, UNIT 1 j Enclosed is Licensee Event Report 89-008-00 for Point Beach !
~ Nuclear Plant, Unit.1. This report is provided in accordance with i 10 CFR 50.73(a)(2)(1)(B), "Any operation or condition prohibited l by the plant's Technical Specifications." ;
r This report describes an event in which the ATWS mitigating system '
actuation circuitry (AMSAC) was automatically bypassed at a power !
level greater than t'ne 40% power level required by the Technical Specifications. A supplement to this report will be submitted at a ;
later date.
If any further information is needed, please do not hesitate to :
contact us. ,
t Very truly yours, ,
s f ',
/// :
1 C. W. F l Vice President !
Nuclear Power :
1 L Enclosure l Copies to NRC Regional Administrator, Region III >
NRC Resident Inspector ,
l' f.gogic( 'O 'p i i u
s :
- ._ . , _ _ _ _m ---
. 3y,,.== su e e .a 6 .. e===T vee ea.e s.w UCENSEE EVENT REPORT ILARI 6,,, n' ees e, mane. e. -
Point Beach Nuclear Plant, Unit 1 e is i o io l e 121616 1 loF}0 11
.- m AMSAC Not Enabled as Required by Technical Specifications evem en e, up. .u . ., n , u n i,i ., . . .. ..u 6v.. .,
amm. m, .. .. ggt-g, o., u, .... ...6..... noc ei .swe. ..
- illoicisi i i
- ~
0l9 1l0 89 8l9 0l0l8 0l 0 1l0 1l 9 8l 9 0 i lleloict I i
,, t=e ,eem m. so ,v., w mmew wc,.i,e
.= m au g ,8' tm a esseni se eeni.i m tensieHei _
to ttal q as toenmH.i **,t.'
. se ass.inHe en asi.im
= MittH88 m mitiNI . 900Bl lt.e) .et . 8p sn I l l W ,tesip Hu ge ttiniWHessH.I 2,
- ;, - ,
i s
, m M Ht H.I _
, Igj _
m eninHtitel gelteniguel 30 ,6.iW He.14l v m e. in H.i e n. .H n a n.ien.i
- 6. ceases ca. .c, t ,me 6.. nas
,8 6 0 *s >el hs H.
.e.est
..t. c000 C. W. Fay, Vice President - Nuclear Power 4l114 21211 1 - l 218 i 11 1
,6...6..-.-..6u.........,n.,
uom ......, .. o 13;;c- atr,A1;* c v.. . . . . . , c- n, 13;te atr,Ay;a - .
B , , , , , , , , , , , , , , ,
I l l I I I I i 1 l 1 i i 1 wmewmu .. , ceeo n.. i.e.,- o., ,p.
~~') ,n t,,,. - e m cree si ,u,a u re, 7one, 112 013 81 9 awe e, ,6 . . ... .- ,, . .i On September 10, 1989, Point Beach Nuclear Plant Unit 1 was decreasing power from greater than 40% to less than 40%. At somewhat less than 40% power, the ATWS mitigating actuation circuitry (AMSAC) is designed l
to be bypassed automatically based upon first-stage turbine pressure.
Power as indicated by first-stage pressure at this power level during power decreases is less than reactor power. In fact, the AMSAC was cutomatical).y bypassed at about 42% reactor power. Technical Specificati ms require the AMSAC system to be enabled at greater than 40% reactol Dower. Power was reduced to 38% and held until the bistable cc.t .d be reset. The enable / disable bistable setpoint was reset to 300 to ensure the operation of the system at less than 40%
reactor power. A revision to the Technical Specifications will be oubmitted to the NRC to clarify that turbine power of greater than 40%
is the power level at which AMSAC is required.
l l
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