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{{#Wiki_filter:. | {{#Wiki_filter:. | ||
public service company =e c 2:2s:10 4 16805 ROAD 19% - | public service company =e c 2:2s:10 4 16805 ROAD 19% - | ||
I',7,'23 PLATTEVILLE, CO .OR ADO'80651 - - | I',7,'23 PLATTEVILLE, CO .OR ADO'80651 - - | ||
:J .','". ~j :. | :J .','". ~j :. | ||
25' | 25' | ||
.:.S November 5, 1980 Fort St. Vrain Unit No. 1 P-30393 Mr. Karl V. Seyf rit, Director Nuclear Regulatory Coc=ission Region IV Office of Inspection and Enforcement 611 Ryan Pla::a Drive Suite 1000 Arlington, Texas 76012 | .:.S November 5, 1980 Fort St. Vrain Unit No. 1 P-30393 Mr. Karl V. Seyf rit, Director Nuclear Regulatory Coc=ission Region IV Office of Inspection and Enforcement 611 Ryan Pla::a Drive Suite 1000 Arlington, Texas 76012 | ||
Line 39: | Line 33: | ||
Very truly yours , | Very truly yours , | ||
: d. >v .! c- .kg?/ -, | : d. >v .! c- .kg?/ -, | ||
Don W. Ware = bourg - | Don W. Ware = bourg - | ||
Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station DWW/alk OO} | Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station DWW/alk OO} | ||
Line 46: | Line 39: | ||
~~ | ~~ | ||
REPORT DATE: November 5, 1980 REPORTABLE OCCURRENCE 80-62 Determined ISSUE O OCCURRENCE DATE: Oc tober 22, 1980 Page 1 of 7 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE CC'4PANY OF COLORADO 16805 UEIJ COU:ITY ROAD 191/2 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/80-62/03-L-0 Preliminary IDENTIFICATION OF OCCURRENCE: | REPORT DATE: November 5, 1980 REPORTABLE OCCURRENCE 80-62 Determined ISSUE O OCCURRENCE DATE: Oc tober 22, 1980 Page 1 of 7 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE CC'4PANY OF COLORADO 16805 UEIJ COU:ITY ROAD 191/2 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/80-62/03-L-0 Preliminary IDENTIFICATION OF OCCURRENCE: | ||
On Thursday, October 21,1980, at 2300 hours, while the plant was operating at 47'; thermal power and 144 lNe, it was determined that the isolation valve for the A purification train (HV-2301) would not close either electrically or by the handjack and was theref ore considered inoperable at that time. The valve was closed manually using the handjack on October 22, 1980, at 0830 hours. | On Thursday, October 21,1980, at 2300 hours, while the plant was operating at 47'; thermal power and 144 lNe, it was determined that the isolation valve for the A purification train (HV-2301) would not close either electrically or by the handjack and was theref ore considered inoperable at that time. The valve was closed manually using the handjack on October 22, 1980, at 0830 hours. | ||
Line 60: | Line 49: | ||
Secondary Coolant Pressure 2,440 psig Temperature 970*F Flow 1,060 Kib/hr, 46% | Secondary Coolant Pressure 2,440 psig Temperature 970*F Flow 1,060 Kib/hr, 46% | ||
Electrical Power 144 We, 42*; | Electrical Power 144 We, 42*; | ||
. .~ -. _. - _ _ - . | . .~ -. _. - _ _ - . | ||
REPORTABLE OCCURRENCE S0-62 ISSUE O Page 2 of 7 DESCRIPTION OF OCCURRENCE: | REPORTABLE OCCURRENCE S0-62 ISSUE O Page 2 of 7 DESCRIPTION OF OCCURRENCE: | ||
s Fort St. Vrain has two parallel helium purification trains which remove the impurities f rom the primary coolant on a continuous basis. These trains are alternated as required with one train being in service while the other is shutdown to allow activity to decay and the train to be regenerated. | s Fort St. Vrain has two parallel helium purification trains which remove the impurities f rom the primary coolant on a continuous basis. These trains are alternated as required with one train being in service while the other is shutdown to allow activity to decay and the train to be regenerated. | ||
Line 78: | Line 61: | ||
ANALYSIS OF GCCURRENCE: | ANALYSIS OF GCCURRENCE: | ||
From the electrical analysis of the valve, it appears that the valve operator motor is running but is not engaged. This indicates possible j amming or in-cerference with the manual operators. The valve has not been tested since it was closed manually, so it cannot be determined if the manual operation has corrected the problem. | From the electrical analysis of the valve, it appears that the valve operator motor is running but is not engaged. This indicates possible j amming or in-cerference with the manual operators. The valve has not been tested since it was closed manually, so it cannot be determined if the manual operation has corrected the problem. | ||
See Figure 1. The failure of HV-2301 or HV-2302 to operate must be ansty:ed for~two condicions. One condition is the postulated permanent loss of forced cooling where one of the two intet isolation valves, HV-2301 for train A or | See Figure 1. The failure of HV-2301 or HV-2302 to operate must be ansty:ed for~two condicions. One condition is the postulated permanent loss of forced cooling where one of the two intet isolation valves, HV-2301 for train A or HV-2302 f or train 3, must be open so that a depressurization path is available. | ||
HV-2302 f or train 3, must be open so that a depressurization path is available. | |||
The second condition is the postulated maximum credible accident which requires that the intet isolation valve, HV-2301 for train A or HV-2302 for train 3, be closed and remain closed if a leak to the purification regeneration system occurs. | The second condition is the postulated maximum credible accident which requires that the intet isolation valve, HV-2301 for train A or HV-2302 for train 3, be closed and remain closed if a leak to the purification regeneration system occurs. | ||
, REPORTA3LE OCCURRENCE 80-62 ISSUE D Page 3 of 7 ANALYSIS GF OCCURRENCE (continued): | , REPORTA3LE OCCURRENCE 80-62 ISSUE D Page 3 of 7 ANALYSIS GF OCCURRENCE (continued): | ||
The depressuriration path required by LCO 4.2.18 is based on the accident analysis of the Final Safety Analysis Report (7SAR) which requires that in the event of a permanent loss of forced cooling, the PCRV must be vented via the purification train. This depressurization path f rom the primary coolant , | The depressuriration path required by LCO 4.2.18 is based on the accident analysis of the Final Safety Analysis Report (7SAR) which requires that in the event of a permanent loss of forced cooling, the PCRV must be vented via the purification train. This depressurization path f rom the primary coolant , | ||
systen is as follows: A-2301 or A-2302, high cenperature filter /adsorbers; HV-2301 or HV-2302, purifica tion inlet isolatier, valves; E-2301 or E-2332, helium purification coolers; A-2303 or A-2304, helium purification dryers; E-2303 or E-2304, low temperature gas to gas exchangers; A-2305 or A-2306, low temperature adsorbers: E-2303 or E-2304, low temperature gas to gas ex-F-2302, purified helium filters; then at mon pump down line to the ventilation or This exhau(}s)t depressuritation system. | systen is as follows: A-2301 or A-2302, high cenperature filter /adsorbers; HV-2301 or HV-2302, purifica tion inlet isolatier, valves; E-2301 or E-2332, helium purification coolers; A-2303 or A-2304, helium purification dryers; E-2303 or E-2304, low temperature gas to gas exchangers; A-2305 or A-2306, low temperature adsorbers: E-2303 or E-2304, low temperature gas to gas ex-F-2302, purified helium filters; then at mon pump down line to the ventilation or This exhau(}s)t depressuritation system. | ||
path requirement can be met with either of the purification trains. At the time of this occurrence, both inlet isolation valves were open and depressuri- | path requirement can be met with either of the purification trains. At the time of this occurrence, both inlet isolation valves were open and depressuri-zation could have been accomplished satisfying the requirements of LCO 4.2.18. | ||
zation could have been accomplished satisfying the requirements of LCO 4.2.18. | |||
The Maximum Credible Accident (Case 6) cescribed in Section 14.8 of the Final Saf ety Analysis Report consists of the largest credible identifiable accidental leakage frem the primary coolant system, resulting f rom a multiple f ailure accident involving the helium purification system regeneratien piping. | The Maximum Credible Accident (Case 6) cescribed in Section 14.8 of the Final Saf ety Analysis Report consists of the largest credible identifiable accidental leakage frem the primary coolant system, resulting f rom a multiple f ailure accident involving the helium purification system regeneratien piping. | ||
See Figure 2. Primary Coolant Leakage Potential. Leakage of the normally | See Figure 2. Primary Coolant Leakage Potential. Leakage of the normally | ||
Line 104: | Line 77: | ||
ACTION: ' | ACTION: ' | ||
The valve was manually closed and is now considered operable on the handjack. ! | The valve was manually closed and is now considered operable on the handjack. ! | ||
A determination of remote-manual operability will be made when plant condi- | A determination of remote-manual operability will be made when plant condi-tions permit. The results of this determination vill be included in a future supplemental report. | ||
tions permit. The results of this determination vill be included in a future supplemental report. | |||
**g 4 | |||
REPORTABLE OCCURRE CE 80-62 ISSUE O Page !. of 7 CORRECTIVE ACTION (continue d: | |||
**g | |||
, In addition the Nuclear Projects Department will be asked to investigate pos-sible further eodifications to lessen chances of valve inoperability. | , In addition the Nuclear Projects Department will be asked to investigate pos-sible further eodifications to lessen chances of valve inoperability. | ||
FAILURE DATA /SIMILAR REPORTED OCCURRENCES: . | FAILURE DATA /SIMILAR REPORTED OCCURRENCES: . | ||
Line 124: | Line 86: | ||
None CODE I?! PACT: | None CODE I?! PACT: | ||
Nons l | Nons l | ||
l | l 1 | ||
l J | |||
1 | |||
l | |||
J | |||
,- _ ,_ _ - , . _.4- - _ | ,- _ ,_ _ - , . _.4- - _ | ||
- i D, l I 1[th'je | |||
- i | |||
D, l I 1[th'je | |||
. 'I !, i I; s | . 'I !, i I; s | ||
*I ! 111 53 !!! | *I ! 111 53 !!! | ||
! l$$j ! !.ii !Elh 5 h'0If0 !h no 80-62 | ! l$$j ! !.ii !Elh 5 h'0If0 !h no 80-62 l.I h! !?!Es Qi fi it l,ni$ !!E i ~8 - ' | ||
l.I h! !?!Es Qi fi it l,ni$ !!E i ~8 - ' | |||
ISSUE O g | ISSUE O g | ||
X,l X, | |||
^ | ^ | ||
: % y " j 0 | : % y " j 0 | ||
* Page 5 j ''i | * Page 5 j ''i E; | ||
j!) Ys Y ' M + 6N : | |||
E; j!) Ys Y ' M + 6N : | d7 5 | ||
d7 | ce g. | ||
. is,. u> | . is,. u> | ||
t ; - | t ; - | ||
ga3 e , -- - | ga3 e , -- - | ||
1 | 1 | ||
Line 170: | Line 113: | ||
]n a%- g n. e g e-c g | ]n a%- g n. e g e-c g | ||
i * ' - | i * ' - | ||
* rA e.---- ,i 1 ha e | * rA e.---- ,i 1 ha e co sh I a g$ | ||
co sh I a | |||
g$ | |||
j Y)! '------ | j Y)! '------ | ||
-*O ie G3 | -*O ie G3 CD e i G jy~ A | ||
CD e i G jy~ A | |||
.p -e? | .p -e? | ||
n | |||
= | = | ||
,* 4 ( #,-s | ,* 4 ( #,-s | ||
@L S | @L S | ||
-O O r cc | -O O r cc | ||
~* , 4F $ | ~* , 4F $ | ||
i!" ./s iii _. _eI * 's @ . | i!" ./s iii _. _eI * 's @ . | ||
u "h _ n !! s e as ses \- | u "h _ n !! s e as ses \- | ||
I o, T | I o, T | ||
n, Y | n, Y | ||
Line 199: | Line 131: | ||
-sx ' 3-[ | -sx ' 3-[ | ||
a | a | ||
- : la TI | - : la TI sq u, | ||
sq u, | |||
y . z_ s~ . | y . z_ s~ . | ||
s .v | s .v | ||
~ | ~ | ||
i_{ | i_{ | ||
eg,b*e , | eg,b*e , | ||
m- ,- | m- ,- | ||
.i | .i | ||
( 1 . .. .- ;- . > j = | ( 1 . .. .- ;- . > j = | ||
2 :- . y:- is | 2 :- . y:- is | ||
Line 222: | Line 145: | ||
;3 = 1s /. = | ;3 = 1s /. = | ||
y q 3R | y q 3R | ||
,t E | ,t E i | ||
o o . a e | |||
"2 9 g | "2 9 g | ||
; .9... | ; .9... | ||
3 | 3 | ||
-~g ~ | -~g ~ | ||
3 I.e - | 3 I.e - | ||
O T I'r /\ C3 - ( T, / l f ,,fp7 j= 0fa IS* | O T I'r /\ C3 - ( T, / l f ,,fp7 j= 0fa IS* | ||
a . - | a . - | ||
*a Q. qe N si'- : | *a Q. qe N si'- : | ||
Ed e !;i:. } | Ed e !;i:. } | ||
. o | . o im.g ei. a .- e ar slg 2&y _ | ||
im.g ei. a .- e ar slg 2&y _ | |||
*6$' | *6$' | ||
9 i | 9 i | ||
g | g e | ||
g o -@ | |||
:e . | :e . | ||
*i)- | *i)- | ||
( | ( | ||
c? te | c? te | ||
('. | ('. | ||
ija | ija | ||
>s | >s | ||
* 3 a | * 3 a | ||
@!i e | @!i e | ||
@ 8 | @ 8 | ||
~s a ~ | ~s a ~ | ||
W @.e - | W @.e - | ||
23 UwE $ ' | 23 UwE $ ' | ||
1 Q h . mi | 1 Q h . mi | ||
Line 273: | Line 179: | ||
! ' -h - | ! ' -h - | ||
5! l' | 5! l' | ||
( llw 'c .-i | ( llw 'c .-i "h Euf.ce .; | ||
y m o | |||
v i | v i | ||
e | e | ||
+ !I | + !I p~ .4 is k ?! !$ g , @- *i | ||
p~ .4 is k ?! !$ g , @- *i | |||
!!g! | !!g! | ||
24 b) mW NcP - | 24 b) mW NcP - | ||
Line 293: | Line 194: | ||
e s - | e s - | ||
re p!!a- ;i 1,, | re p!!a- ;i 1,, | ||
b> t U I!! | b> t U I!! | ||
** * 'N - | ** * 'N - | ||
j ,y , PURIFICATION WE LLS | j ,y , PURIFICATION WE LLS | ||
// *s & | // *s & | ||
Qd 7[# y S % | Qd 7[# y S % | ||
// \ Q ,G // \t // \j ll | // \ Q ,G // \t // \j ll | ||
\\\ | \\\ | ||
A 2301 y | A 2301 y | ||
$ E-2301 | $ E-2301 Jf'B\\\ | ||
Jf'B\\\ | |||
; A 2303 3)// | ; A 2303 3)// | ||
jj l\ ' | jj l\ ' | ||
E 2303 | E 2303 | ||
-M | -M n, | ||
n, | |||
? | ? | ||
n ^'2305 | n ^'2305 | ||
)) | |||
8 ' | 8 ' | ||
\[t[ \ | \[t[ \ | ||
g 1- _ W | g 1- _ W | ||
// | // | ||
A | A WM | ||
WM | |||
// | // | ||
\s V L # | \s V L # | ||
Line 337: | Line 221: | ||
[/ | [/ | ||
M | M | ||
/ r M A TP PCflV | / r M A TP PCflV A)p3 ' | ||
A)p3 ' | |||
1 1 7 A PENETilAll0N 8 I : J k 8 L__ _ _.1_ _n. __ ___ _ .3 TilEllMAL SLEEVE . PURIFIED llEllUM h | 1 1 7 A PENETilAll0N 8 I : J k 8 L__ _ _.1_ _n. __ ___ _ .3 TilEllMAL SLEEVE . PURIFIED llEllUM h | ||
C WELL !!OUND Ally (TYPICAL) | C WELL !!OUND Ally (TYPICAL) | ||
F'h C 10112GETTEfl UNIT M q r - - - - -- ---7 E | |||
F'h C | |||
10112GETTEfl UNIT M q r - - - - -- ---7 E | |||
, w A-2301 - | , w A-2301 - | ||
Dg D2 e | Dg D2 e | ||
lilGil TEMPEll ATUllE ' L e ' L 1 | lilGil TEMPEll ATUllE ' L e ' L 1 FILTEll ADS 6llBEll flEGENEll ail 0N SECTION E 2301 IIEllUM PUllIFICATION ---> E 2305 : C-2302 : T-2301 : A-2307 : E 230S - | ||
FILTEll ADS 6llBEll flEGENEll ail 0N SECTION E 2301 IIEllUM PUllIFICATION ---> E 2305 : C-2302 : T-2301 : A-2307 : E 230S - | |||
COULEll A 2303 ? Un $ | COULEll A 2303 ? Un $ | ||
mmm llELIUM PUlilFICAT10tJ B flAD10 ACTIVE *gg IlllYEll -I HAD10 ACTIVE | mmm llELIUM PUlilFICAT10tJ B flAD10 ACTIVE *gg IlllYEll -I HAD10 ACTIVE | ||
-C> - GAS WASTE | -C> - GAS WASTE | ||
* oy | * oy A 2305 LIQUID WASTE LOW T EMPEll AT UIlE SYSTEM o ADS 0!!BEH @ | ||
A 2305 LIQUID WASTE | |||
LOW T EMPEll AT UIlE SYSTEM o ADS 0!!BEH @ | |||
A 2307 C-2302 E-2303 E 2305 T 2301 E-2306 M | A 2307 C-2302 E-2303 E 2305 T 2301 E-2306 M | ||
gn llEGENEllAll0N llEGENEllATION LOW TEMPEllATullE flEGENEllATION ilEGENEllATION flEGENETIATION y DilYEll COMPilESSOft GAS TO GAS EXCllANGEll C00LEll KNOCK UUT DflUM llEATEll m w | gn llEGENEllAll0N llEGENEllATION LOW TEMPEllATullE flEGENEllATION ilEGENEllATION flEGENETIATION y DilYEll COMPilESSOft GAS TO GAS EXCllANGEll C00LEll KNOCK UUT DflUM llEATEll m w | ||
Fig. 14.8-1-S i mpl i f ied 1rocess flow diagram of the helium purification system for the ''' | Fig. 14.8-1-S i mpl i f ied 1rocess flow diagram of the helium purification system for the ''' | ||
maximum credible accident discussion (valves shown positioned for the regeneration of helium purification dryer) Amendme n t 26 | maximum credible accident discussion (valves shown positioned for the regeneration of helium purification dryer) Amendme n t 26 | ||
.. .- - .. - . .- .-. .-. =. | .. .- - .. - . .- .-. .-. =. | ||
1 REPORTABLE OCCURRENCE 80-62 | 1 REPORTABLE OCCURRENCE 80-62 | ||
, ISSUE O l Page 7 of 7 | , ISSUE O l Page 7 of 7 E | ||
i Prepared by: MM ' | |||
Prepared by: MM ' | |||
W | W | ||
- Asa 3. 9.ded Technical Services Technician 4 | - Asa 3. 9.ded Technical Services Technician 4 | ||
Reviewed by: O/ h7 /h d (6 _ /[n? | Reviewed by: O/ h7 /h d (6 _ /[n? | ||
l J. W. Gahm / ' | l J. W. Gahm / ' | ||
Technical Services Supervisor l | Technical Services Supervisor l | ||
/ h'' , ,9 | / h'' , ,9 Reviewed by: \ | ||
Reviewed by: \ | |||
Frank M. :tathie i Operations-Manager t | Frank M. :tathie i Operations-Manager t | ||
( | ( | ||
Line 395: | Line 252: | ||
: f. Approved by: /'b.''. ' | : f. Approved by: /'b.''. ' | ||
w~ d-4c l.O ' ,'frn j Don W. Ware =courg (. | w~ d-4c l.O ' ,'frn j Don W. Ware =courg (. | ||
1 Manager, Nuclear Production | 1 Manager, Nuclear Production j | ||
j | |||
l l | l l | ||
I | I W | ||
4 ' l l | |||
+ | + | ||
i e | i e | ||
4 | 4 | ||
.-}} | .-}} |
Latest revision as of 21:36, 15 March 2020
ML19340B890 | |
Person / Time | |
---|---|
Site: | Fort Saint Vrain ![]() |
Issue date: | 11/05/1980 |
From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
To: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
Shared Package | |
ML19340B891 | List: |
References | |
P-80393, NUDOCS 8011120523 | |
Download: ML19340B890 (8) | |
Text
.
public service company =e c 2:2s:10 4 16805 ROAD 19% -
I',7,'23 PLATTEVILLE, CO .OR ADO'80651 - -
- J .','". ~j :.
25'
.:.S November 5, 1980 Fort St. Vrain Unit No. 1 P-30393 Mr. Karl V. Seyf rit, Director Nuclear Regulatory Coc=ission Region IV Office of Inspection and Enforcement 611 Ryan Pla::a Drive Suite 1000 Arlington, Texas 76012
REFERENCE:
Facility Cperating License No. DPR-34 Decket No. 50-267
Dear Mr. Seyfrit:
Enclosed please find a copy of Reportable Occurrence Report No. 50-267/S0-62/03-L-0, Preliminary, submitted per the requirenants of Technical Specification AC 7.5.2(a)9.
Also, please find enclosed one copy of the Licensee Event Report for Reportable Cccurrence Report No. 50-267/30-62/0 3-L-0.
Very truly yours ,
- d. >v .! c- .kg?/ -,
Don W. Ware = bourg -
Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station DWW/alk OO}
Enclosure 3 cc: Direc tor, '1IPC /
a801112 O T23 _3
~~
REPORT DATE: November 5, 1980 REPORTABLE OCCURRENCE 80-62 Determined ISSUE O OCCURRENCE DATE: Oc tober 22, 1980 Page 1 of 7 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE CC'4PANY OF COLORADO 16805 UEIJ COU:ITY ROAD 191/2 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/80-62/03-L-0 Preliminary IDENTIFICATION OF OCCURRENCE:
On Thursday, October 21,1980, at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, while the plant was operating at 47'; thermal power and 144 lNe, it was determined that the isolation valve for the A purification train (HV-2301) would not close either electrically or by the handjack and was theref ore considered inoperable at that time. The valve was closed manually using the handjack on October 22, 1980, at 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />.
This is reportable per Fort St. Vrain Technical Specification AC 7.5.2(a)9.
CONDITIONS PRIOR TO OCCURRENCE:
Steady State Power The major plant parameters at the time of the event were as follows:
~
Reactor Power 396:Wth, 47:';
Primary Coolant Pressure 672 psia Temperature 677'F Circulator Inlet Temperature 1,130*F Core Outlet Total Flow 2,430 Kib/hr, 69*.
Secondary Coolant Pressure 2,440 psig Temperature 970*F Flow 1,060 Kib/hr, 46%
Electrical Power 144 We, 42*;
. .~ -. _. - _ _ - .
REPORTABLE OCCURRENCE S0-62 ISSUE O Page 2 of 7 DESCRIPTION OF OCCURRENCE:
s Fort St. Vrain has two parallel helium purification trains which remove the impurities f rom the primary coolant on a continuous basis. These trains are alternated as required with one train being in service while the other is shutdown to allow activity to decay and the train to be regenerated.
On October 21, 1980, it was determined the in service train, A, should be re-i moved from service for regeneration and train 3 placed in service. cperations personnel placed train 3 in service and then removed train A from service.
Train A was isolated f rom the purified helium system by closing HV-2303, the outlet isolation valve. Due to the inability to close HV-2301, train A could not be isolated from the primary coolant system at this time. Operations per-sonnel attempted to close the val"e manually, but could not get the manual operator engaged and therefore declared the valve inoperable at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />.
On October 22,1980, at 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />, Operations personnel and Electrical !!ain-tenance personnel again checked the valva controls and attempted to close the valve. The operator engaged the manual operator with no dif ficulty and closed the valve.
APPARENT CAUSE OI OCCURRENCE:
Design l
The actual cause of the operator f ailure cannot be deternined at this time be-cause the valve is in a penetration in the PCRV top head and is inaccessible during reactor operation.
ANALYSIS OF GCCURRENCE:
From the electrical analysis of the valve, it appears that the valve operator motor is running but is not engaged. This indicates possible j amming or in-cerference with the manual operators. The valve has not been tested since it was closed manually, so it cannot be determined if the manual operation has corrected the problem.
See Figure 1. The failure of HV-2301 or HV-2302 to operate must be ansty:ed for~two condicions. One condition is the postulated permanent loss of forced cooling where one of the two intet isolation valves, HV-2301 for train A or HV-2302 f or train 3, must be open so that a depressurization path is available.
The second condition is the postulated maximum credible accident which requires that the intet isolation valve, HV-2301 for train A or HV-2302 for train 3, be closed and remain closed if a leak to the purification regeneration system occurs.
, REPORTA3LE OCCURRENCE 80-62 ISSUE D Page 3 of 7 ANALYSIS GF OCCURRENCE (continued):
The depressuriration path required by LCO 4.2.18 is based on the accident analysis of the Final Safety Analysis Report (7SAR) which requires that in the event of a permanent loss of forced cooling, the PCRV must be vented via the purification train. This depressurization path f rom the primary coolant ,
systen is as follows: A-2301 or A-2302, high cenperature filter /adsorbers; HV-2301 or HV-2302, purifica tion inlet isolatier, valves; E-2301 or E-2332, helium purification coolers; A-2303 or A-2304, helium purification dryers; E-2303 or E-2304, low temperature gas to gas exchangers; A-2305 or A-2306, low temperature adsorbers: E-2303 or E-2304, low temperature gas to gas ex-F-2302, purified helium filters; then at mon pump down line to the ventilation or This exhau(}s)t depressuritation system.
path requirement can be met with either of the purification trains. At the time of this occurrence, both inlet isolation valves were open and depressuri-zation could have been accomplished satisfying the requirements of LCO 4.2.18.
The Maximum Credible Accident (Case 6) cescribed in Section 14.8 of the Final Saf ety Analysis Report consists of the largest credible identifiable accidental leakage frem the primary coolant system, resulting f rom a multiple f ailure accident involving the helium purification system regeneratien piping.
See Figure 2. Primary Coolant Leakage Potential. Leakage of the normally
, closed valve "A" between a helium purification train and the regeneration equipment could release primary coolant activity to :he gas vaste surge tanks in the radioactive gas waste system, but only if normally closed valve "B" be-tween the regeneration section and the gas waste system also leaks, and if normally closed valves "C", "Dl". or "D2", and "E" in the regeneration section are open. However, this leakage would not lead to uncontrolled release of activity to the atmosphere, and would be terminated with remote-manual closure of the normally open isolation valve "G" between the high temperature filter /ab-sorber and the helium purification cooler of the af f ected train.
Valve "G" described here is HV-2301 for train A and HV-2302 for train 8.
With HV-2301 inoperable this leakage could not be remote-manually terminated as described in the Final Safety Analysis Report.
In the Final Saf ety Analysis Report analysis of a leak f rom a purification train to the regeneration system the entire purification train is considered as doubly contained and a direct release of activity from this equipuent would require at least two unrelated f ailures.
CCRRECTIVE ,
ACTION: '
The valve was manually closed and is now considered operable on the handjack. !
A determination of remote-manual operability will be made when plant condi-tions permit. The results of this determination vill be included in a future supplemental report.
- g 4
REPORTABLE OCCURRE CE 80-62 ISSUE O Page !. of 7 CORRECTIVE ACTION (continue d:
, In addition the Nuclear Projects Department will be asked to investigate pos-sible further eodifications to lessen chances of valve inoperability.
FAILURE DATA /SIMILAR REPORTED OCCURRENCES: .
None PROGRA!C!ATIC IMPACT:
None CODE I?! PACT:
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1 1 7 A PENETilAll0N 8 I : J k 8 L__ _ _.1_ _n. __ ___ _ .3 TilEllMAL SLEEVE . PURIFIED llEllUM h
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mmm llELIUM PUlilFICAT10tJ B flAD10 ACTIVE *gg IlllYEll -I HAD10 ACTIVE
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gn llEGENEllAll0N llEGENEllATION LOW TEMPEllATullE flEGENEllATION ilEGENEllATION flEGENETIATION y DilYEll COMPilESSOft GAS TO GAS EXCllANGEll C00LEll KNOCK UUT DflUM llEATEll m w
Fig. 14.8-1-S i mpl i f ied 1rocess flow diagram of the helium purification system for the
maximum credible accident discussion (valves shown positioned for the regeneration of helium purification dryer) Amendme n t 26
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1 REPORTABLE OCCURRENCE 80-62
, ISSUE O l Page 7 of 7 E
i Prepared by: MM '
W
- Asa 3. 9.ded Technical Services Technician 4
Reviewed by: O/ h7 /h d (6 _ /[n?
l J. W. Gahm / '
Technical Services Supervisor l
/ h , ,9 Reviewed by: \
Frank M. :tathie i Operations-Manager t
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- f. Approved by: /'b.. '
w~ d-4c l.O ' ,'frn j Don W. Ware =courg (.
1 Manager, Nuclear Production j
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