ML20237F979
| ML20237F979 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 06/30/1987 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20237F977 | List: |
| References | |
| NUDOCS 8709020054 | |
| Download: ML20237F979 (13) | |
Text
__ __-_
1 ATTACHMENT i
Consumers Power Company Palisades Plant Docket 50-255 1
i 1
SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT JANUARY THROUGH JUNE 1987 August 28, 1987 8709020054g{0 55 PDR ADOCK ppg R
11 Pages ATT0887-0137-NLO2
t a
o 1
Palisades Nuclear Plant Semiannual Radioactive Effluent Release Report January
' June 1987 This report provides information relating to radioactive effluent releases and solid radioactive waste disposal operations of the Palisades Plant during the period of January through June 1987 in the format contained in Plant Technical
^
Specification 6.9.3.la.
Due to continuation of the May 19, 1986 outage,'the first quarter 1987 gaseous effluent releases reflect only residual activity levels. Palisades returned to service on April 16, 1987.
1.
Supplemental Information 1
A.
. Batch Releases I
Information relating to batch releases of liquid and gaseous effluents is provided in Table HP 10.5-1.
B.
Abnormal Releases None.
C.
Radioactive Caseous Effluent Monitoring Instrumentation Technical Specification 3.24.2.1(B) requires that when the radio-active gaseous effluent monitor becomes unoperable, best efforts must be made to return the instrument to operable status _within 30 days and if unsuccessful, report the incident in the next Semiannual Radioactive Effluent Report. Technical Specification Table 2.42-2(1b) further stipulates that radioactive gaseous effluent releases may continue to be made with less than the required amount of operable channels (in the gaseous effluent monitor) providing that the flow rate is estimated at least once per 24. hours for continuous releases or once per every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for batch releases.
On June 4, 1987, Waste Cas Decay Tank T-68C (batch #87-018-C) was scheduled for release, however due to poor communications during shift turn-over and the lower than usual release rate, the T-68C Waste Cas Decay Tank (batch #87-018-C) flow ' rate estimate was not perf o rmed. The radioactive gaseous effluent monitor had originally been declared inoperable on March 5, 1987. Due to an extended time period in troubleshooting the problem and in obtaining parts (12 i
weeks) plus an additional lead time (8 weeks) for repair, work completion was estimated for August 7, 1987.
Corrective action was initiated on the above incident and reported to the USNRC. This evaluation is to be incorporated into the j
continuing training sessions of Operations and Health Physics personnel. A copy of the Licensee Event Report 87-017 is being submitted as ar. attachment to the January - June 1987 Semiannual Radioactive Effluent Release Report.
IC0887-0197A-HP01
.o 2
2.
Caseous Effluents Table HP 10.5-2 lists and sumarizes all gaseous radioactive' effluents released during the reporting period. The unidentified beta was 7.37E-06% of the total release.
3.
Liquid' Effluents Table HP 10.5-3 lists and summarizes all liquid radioactive effluents released during the reporting period. The unidentified beta was 1.37E-02% of the total release.
4.
Solid Waste Solid radwaste classification, sources, volume shipped, curie and nuclide content are detailed in Table HP 10.5-4.
All.radwaste shipments were made to either Barnwell, South Carolina or Richland, Washington'for burial.
5.
Summary of Radiological Impact on Man j
Potential doses to individuals and populations were calculated using CASPAR and LADTAP computer program codes. The first and second quarter values for curies released were input for each nuclide and summarized as follows:
A.
The maximum offsite air dose at the site boundary due to noble gases was 0.00 millirad beta and gama for the first quarter; and 2.99E-02 millirads beta and 1.01E-02 millirads gamma for the second quarter.
B.
The most restrictive organ dose to an individual in an unrestricted area (based on identified critical receptors) from gaseous effluents (tritium, particulate.and iodine) was the child bone.
Doses were 1.68E-03 and 1.68E-02 millirem for the first and second quarters, respectively.
C.
The maximum total body dose to individuals (adult) in unrestricted water-related exposure pathways was 3.59E-03 millirem for the first quarter and 6.24E-03 millirem for the second quarter. The maximum organ dose was 5.72E-03 and 1.10E-02 millirem for the first (teen liver) and second (teen bone) quarters, respectively.
D.
Integrated total body doses to the general population and average doses to individuals within the population from liquid effluent i
releases within a distance of 50 miles from the site boundary were:
1.19E-02 manRem and 1.13E-05 millirem for the first quarter; and 2.05E-02 manRem and 1.95E-05 millire. for the second quarter.
E.
Integrated total body doses to the general population and average j
doses to individuals (adults) within the population from gaseous effluent releases within a distance of 50 miles from the site boundary were: 2.04E-03 manRem and 1.94E-06 millirem for the first IC0887-0197A-HP01 1
3 I
quarter; and 1.95E-02 manRem and 1.86E-05 millirem for the second quarter.
F.
'The Selenium-75 Design Basis Quantity f ractions in gaseous ef fluent
)
releases (first quarter only) were not significant in either whole-body or organ doses. Entrained noble gases were present in the second quarter liquid releases only (Xe-133 and Xe-135).
6.
There are no changes to the PCP during this reporting period.
7.
Offsite Dose Calculation Manual (ODCM)
There are no changes to the ODCM during this reporting period.
8.
Correction of the June - December 1986 Semiannual Radioactive Effluent Release Report The Palisades Nuclear Plant Semiannual Radioactive Effluent Release Report, July - December 1986 is being submitted as an attachment (in its entirety) for the'following revisions:
A.
Page 2, item 2, Caseous Effluents: the unidentified beta is changed from 9.67E-03% to 9.30E-03% of the total release, B.
Page 6, Table HP 10.5-1, Batch Releases, item B, Liquid: change 1st quarter and 2nd quarter column designations to 3rd and 4th quarters, respectively.
C.
Page 7, Table HP 10.5-2, Caseous Effluents - Summation of Releraes, item C, Particulate:
change 4th quarter percent of annual average limit MPC from 4.78E-06 to 4.89E-06.
D.
Page 9, Table HP 10.5-2, Caseous Effluents (isotopic Ci listings),
item 3, Particulate:
change the 4th quarter reported isotopic values for:
Sr-89 from 2.89E-06 Ci to 2.69E-06 Ci Sr-90 from 2.13E-06 Ci to 2.51E-06 Ci Net unidentified beta from 4.70E-06 Ci to 4.52E-06 Ci E.
Page 10, Table 10.5-3, Liquid Effluents - Summation of Releases; item D - Cross Alpha Radioactivity and item E - Volume of Waste Released:
1.
Change 3rd and 4th quarter Cross Alpha Radioactivity (total release) i 3rd quarter from 4.05E-06 Ci to 4.09E-06 Ci l
4th quarter from 3.45E-06 Ci to 4.08E-06 C1 IC0887-0197A-HP01 i
l
l 4
1
)
I 2.
Change 3rd and 4th quarter Volume of Waste Released (Prior to Dilution):
3rd quarter from 8.49E+05 L to 8.50E+05 L i
4th quarter from 5.55E+04 L to 5.55E+05 L i
F.
Page 11, Table 10.5-3, Liquid Effluents (isotopic Ci listings), item 1, Nuclides Released:
I 1.
Change 3rd quarter Sr-89, Sr-90 reported isotopic values:
1 Sr-89 from 8.75E-06 Ci to 1.21E-05 Ci Sr-90 from 1.97E-05 Ci to 1.70E-05 Ci
\\
2.
Change 4th quarter Sr-89, Sr-90 and net unidentified beta reported isotopic values:
l l
l Sr-89 from 4.61E-05 Ci to 2.82E-05 Ci Sr-90 from 1.90E-05 Ci to 1.07E-05 Ci Net unidentified beta from 5.76E-04 Ci to 6.02E-04 Ci Reasons for the above data revisions to the Palisades Nuclear Plant i
Semiannual radioactive Effluent Release Report, July - December 1986 l
was that the calculated Sr-89 and Sr-90 release quantities (for both I
gaseous and liquid effluents) were based on estimated values for the month of December. Teledyne Isotopes Midwest Laboratory had not yet completed the actual sample analyses prior to the Technical Specifi-cation Semiannual report due date. Also there were errors / mis-transfers of data from the draft work sheets. All data corrections are indicated by '#' in the right-hand margins.
There were no reportable changes in doses to the public.
l l
l 1
s 1
l l
l l
l IC0887-0197A-HP01
- v.,
f-i f
i t
1 TABLE HP 10.5-1:
i PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE i
EFFLUENT RELEASE REPORT y
)
\\.
I i
BATCH RELEASES d
i
~
l JANUARY 1987 to JUNE 19tC s
\\
s i
l f
A.
CASEOUS Units 1st Quarter 2nd Quaxter t
I Nutber of Releases 8
3
{
i Total Release Time Minutes 1.07[+03 1.10E+03
._g Maximum Release Time Minutes 2.55E+02 5.50E+02 I
i.
Average Release Time Minutes
- 1. 3i.E+ 02 3.67E+02 i
l Minimum Release Time Minutes 3.80E+01 2.60E+02 i
i
\\
~
B.
LIQUID Units 1st Quarter 2nd[arter Number of Releases 17 1
Total Release Time Minutes 2.13E+03 3.10E+03 i
Maximum Release T. ire Minutes 7.25E+02 1.22E+03 Average Release Time Mi[otes 1.25E+02 2.81E+02 Minimum Release Time Minutes 3.70E+01 5.20E+01 s
k N
s r
s MIO 88 7-005 3 A-HI'01
9 TABLE HP 10.5-2 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CASE 0VS EFFLUENTS - SUMMATION OF RELEASES JAUNARY 1987 to JUNE 1987 F
Est Total A.
FISSION AND ACTIVATION CASES UNITS 1st QUARTER 2nd QUARTER Error %
j 1.
Total release Ci None 6.27E+02 2.
Average release rate for period l
uCi/sec None 7.98E+01 4.22 3.
Percent of annual avg MPC None 3.81E-02 B.
IGDINFF 1.
TU. 1 Iodine Ci Non'e 6.59E-03 2.
Average. release rate for period
- uCi/sec None 8.38E-04 4.17*
3.
Percent of annual avg MPC None 1 6.86E-04 C.
P ARTI CULATES 1.
P4r;,iculates with half-lite >
8 !ays Ci 1.74E-05 4.38E-05 2.
AveraRe release rate for period uCi/sec 2.24E-06 5.57E-06 3.
Percent of annual avg limit MPC 2.52E-06 2.62E-05 51.0**
4 Cross alpha radioactivity Ci 2.50E-06 2.31E-06 5.
Gross alpha average release rate for period uCi/Sec 3.21E-07 2.94E-07 D.
TRITIUM 1.
Total release Ci 6.64E-01 9.59E-01 2.
Average release rate for period uCi/sec 8.53E-02 1.22E-01 3.
Percent of annual avg MPC 6.10E-05 8.72E-05 E.
1.
Beta air dose at site boundary due to Noble Cases (TS 3.24.5.2a) mRads None 2.99E-02 l
2.
Percent limit None 2.99E-01 3.
Camnm air dose at site boundary due to Noble Cases (TS 3.24.5.21) mRads None 1.01E-02 4.
Percent limir None 2.02E-01 F.
1.
Maximum organ dose to public based based on critical receptors (TS 3.24.5.3) mrem 1.68E-03 1.68E-02
{
2.
Percent cf limit 2.24E-02 2.24E-01
- Note: Data is reported for I-131 and I-133 only.
- o Note:
Large error factor due to very small amount of particulate present in gaseous effluents.
MIO887-005?A-HP01
I TABLE HP 10.5-2 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CASEOUS EFFLUENTS JANUARY 1987 to JUNE 1987 10 FISSION CASES Units 1st QUARTER 2nd QUARTER l
i Krypton-85 Ci None 7.46E-03 i
1 Krypton-85m Ci None l
3.31E-02 i
Krypton-87 Ci None 3.14E-02 l
Krypton-88 Ci i
None 3.76E-02
{
J Xenon-131m Ci None 1.30E-03 t
Xenon-133 Ci None 6.26E+02 Xenon-133m Ci None 3.84E-01 Xenon-135 Ci None 2.73E-01 Xenon-135m Ci I
None 1.42E-01 I
1 i
Xenon-138 Ci I
~
i Argon-41 Ci None 1.38E-02 l
l Total for Period Ci None 6.27E+02 l 2.
10 DINES l
Ci None 2.84E-03
{
Iodine-132 Ci None None l
I l
Iodine 133 Ci None 1
3.75E-03 l
Iodine-135 Ci None None I
Total for Period Ci None 1
6.59E-03 i
MIC887-0053A-HP01
9 TABLE HP 10.5-2 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT.
CASEOUE EFFLUENTS JANUARY 1987 to JUNE 1987 3.
PARTICULATE
- Units 1st QUARTER 2nd QUARTER Chromium-51 Ci None None
'l Hanganese-54 Ci None l
None Cobalt-58 Ci None None Coba?t-60 Ci 1.22E-06 9.63E-08 I
l Cesium-134 Ci None l-None l
ci I
4.37E-06 None i
Selenium-75 l
Ci 7.51E-06 None l
Strontium-89**
Ci 6.7E-07 3.2E-07 i
i i
i i
Strontium-90**
Ci i
5.6E-07 2.8E-07 Net unidentified I
i l
beta Ci 3.06E-06 4.31E-05 i
Total Ci 1.74E-05 4.38E-05
- Particulate with half-lives >8 days.
- Calculated n r.a vendor analysis of monthly stack gas filters.
i Mote: Reported net beta and vendor analyzed Sr-89/90 results were input to CASPAR code l
as Sr-90 to yield conservative dose estimates.
l l
)
i i
)
MIO887-0053A-HP01 l
_ _. _ _ _ _ - - - - _. - -. _ - _ = _ _ - - - - _ - -. -
1
)
\\
i l
TABLE HP 10.5-3 PALISADES NUCLEAR PLANT SEMIANNUAL RADIOACTIVE i
EFFLUENT RELEASE REPORT i
LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES
{
l JANUARY 1987 to JUNE 1987 Est Total' A.
FISSION AND ACTIVATION CASES UNITS let QUARTER 2nd QUARTER Error %
l 1.
Total release (not including j
tritium, gases, alpha)
Ci 3.61E-03 1.11E-02 2.
Average diluted concentration i
during period uCi/e1 1.09E-10 3.40E-10 9.55
,I 3.
Percent of MPC 5.16E-03 2.31E-02 i
B.
TRITI UM 1.
Total release ci 5.85E+00 1.16E+01
{
2.
Average diluted concentration l 3.55E-7
)
during period uCi/ml 1.77E-07 18'.8 l
3.
Percent of MPC 5.91E-03 1.18E-02 C.
DISSOLVED AND ENTRAINED CASES 1.
Total Release Ci None 1 6.24E-03 2.
Average diluted concentration during period uCi/ml None 1.91E-10 18.8 3.
Percent of MPC None 1 9.55E-05 D,
CROSS ALPHA RADI0 ACTIVITY I
I (Total Release) **
Ci 4.1E-06 1.6E-05 1.
Cross alpha average diluted l
concentration during period uCi/ml 1.2E-13 1 4.9E-13 E.
VOLUME OF WASiE RELEASED (Prior to Dilution)
Liters 4.38E+05 i 4.76E+05 l
i i
F.
VOLUME OF DILUTION WATER USED DURING PERIOD Liters 3.30E+10 1 3.27E+10 C.
MAXIMUM DOSE COMMITMENT - WHOLEBODY mrem 3.59E-03
! 6.24E-03 Percent of TS 3.24.4.la limit 2.39E-01
! 4.16E-01 H.
MAXIMUM DOSE COMMITMENT - ORCAN l
mrem 4.73E-03 1.10E-02 Percent of TS 3.24.4.la limit
. _,1 9.46E-02 2.20E-01
- Note: Calculated from vendor analysis or monthly radwaste composite samples.
MIO887-0053A-HP01
TA8LE HP 10.5-3 PA_LISADES NUCLEAR PLANT SEMTANNUAL RADIOACTIVE EFFLUENT RELEA3E REPORT IIQUID EFFLUENTS JANUARY 1987 to J_UNE 1987
- 1.. NUCLIDES RELEASED Units 1st QUARTER 2nd QUARTER Ces'um-137 Ci 1.43E-03 2.44E-03 Cobalt-58 Ci 2.60E-04 9.81E-05 Hanganese-54 Ci 1.55E-04 6.31E-04 Cobalt-60 Ci 9.88E-04 5.58E-03 Cesium-134 Ci 3.04E-04 2.75E-04 Strontium-89**
Ci 5.6E-06 5. 4 E-0 5 ***
t Strontium-90**
Ci 4.8E-06 9.1E-OS***
Net Unidentified Beta Ci 4.61E-04 1.93E-03 Fission & Activation Product Total (Above)
Ci 3.61E-03 1.11E-02 Xenon-133 Ci None 6.12E-03 Xenon-135 Ci None 1.22E-04 Tri t i um Ci 5.85E+00 1.16E+01 Crand Total Ci 5.85E+00 1.16E+01 Calculated f rom vendor analysis of monthly radwaste composite samples.
June Sr-89/90 sample results were unavailable from vendor; 2nd quarter Sr-89/90 calculation incorporated a June estimate.
]
l NOTE: Reported net beta and vendor analyzed Sr-89/90 results were input to LADTAP code as Sr-90 to yield conservative dose estimates, i
.)
l J
l MIO887-0053A-HP01 f
j 1
1 s
TABLE HP 10.5-4 PALISADES NUCLEAR PLAdT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SOLID RADIOACTIVE WASTE JANUARY 1987 to JUNE 1987 Waste Source of Solidification Connainer Volume Total
- Principal Class Waste Agent Type (Cu.ft.)
Curies Radionuclides A
DAW N/A B-25 Box-LSA 980.0-1.1 H,Mn-54,Fe-55,Co-57, 3
Co-58,Co-60,Ni-63; Cs-134,Cs-137~
A Concentrates Asphalt Metal drum 30.0 1.8 Co-57,Co-58,Co-60, LSA C s-13 7, H,3, C r-51, Mn-54,Nb-95,Ni-63 C-Resins N/A HIC-14-195H 193.0 59.8 Mn-54,co-58,Co-60, co-57,Cs-134,Cs-137, Ni-63,Tc-99,H3 Total Shipped 1203.0 62.7
- Note:
Camma Isotopes are measured quantities, all other isotopes are estimated.
i I
4
)
MIO887-0053A-HP01
L i
o l
i i
ATTACHMENT 1
Consuuers Power Company Palisades Plant Docket 50-255 l
i LICENSEE EVENT REPORT 87-017 Failure to Estimate Waste Gas Release Flow Rate Results in Technical Specification Violation jl i
i i
i August 28, 1987 5 Pages ATT0887-0137-NLO2
@powERas Consumers Power MKHeGAN's PltOGRE55 l
c.n.r.i orrie : $e4s w..
e.<n.is no.a. a.cu.on, ui 492ot. <sta 7ss-osso July 6, 1987
]
l I
Nuclear Regulatory Commission Document Control Desk l
Washington, DC 20555 1
l DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
LICENSEE EVENT REPORT 87-017 - FAILURE TO ESTIMATE WASTE GAS l
RELEASE FLOW RATE RESULTS IN TECHNICAL SPECIFICATION VIOLATION l
l Licensee Event Report (LER)87-017, (Failure to Estimate Waste Gas Release Flow Rate Results in Technical Specification Violation) is attached. This event is reportable to the NRC per 10CFR50.73(a)(2)(1).
)
l l
I l
Brian D Johnson (Signed) l 4
l Brian D Johnson l
Staff Licensing Engineer l
CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment pm(m5%Sgf-OC0787-0096-NLO2 l
l l
_-_--_-____a
1 e
m.
u s. auc6 as muu roav ca.a a asseoveo one no atgiaion
)
LICENSEE EVENT REPORT (LERI ene.urt name m ensart muussa m PALISADES NUCLEAR PLANT o Ie 1 0 10 i e 1 2 15 15 1 lopl0 g.
i I
rirse a Failure To Estimate Waste Gas Release Flev Rate Results In Tech S::ec Vielstien event ears a tea mummen a me car oareiri ofwen eeute ave 6 vee e esoesta oav vena vean
"'*Nn' 6 esoserm oav ve&a eacsutv =anses ooCast asunseenian N/A 0 isl0 lo g o; ; 9 i
8l?
0l1l7 Cl C 0 l7 0l6 8l 7 NA Cl 6 0lL 8
7
~
0 isto1 0 tof I rwe nepoet a aumerereo runsuant to two acousnes. eve os se can e osw
.<.= awe===w itis mees a N
.,s.,
re.,,,
m.assemne es.m w m m.rewsw.e rs riw y
nm 11010 m.mmmm se.mwe, en.rowmeni vuonrem-g a, g messe uinas 1
en tswown es tamenieuw maar m.mmm m es im.em es.rewen.=>m m mesHiHet m r91slailull m rSteleMal Laceasse Coeff acT Poa ft,as L3a rigs name rete,.o :.u,me.
assa caos CSKozup, Technical Engineer, Palisades 611 16 716 I L l-t 8I o n n comesses one une,oa saca consoment eas6uas essenione in two mesent ne cause avsta=
consoasar
"'%,', h?",;.'j!'
"'gy*-
y,;,'jga cause sverem coneone=t X
- F ;I A 5,0 l N
t i
A I
I I I I I I I
i 1 l l l l mass. sweat ae. oat es,eereo n.
.o.,t.
env same.
""] ves m, - emcreo suen,es,on on m 7"] ~o i
aseramet <u
.,m
,o _
._..,.n.
l OnJune4,1987atapproximately2330$ hours,duringshiftturnover Operations personnel discovered that contrary to Technical Specification (TS) 3.24.2, no flow rate estimation had been performed for eight hours 1
and twenty-five minutes while batching out Waste Gas Decay Tank, T-68C (WE;TK]. TS 3.24.2 states that with flow indicator FI-ll21 (WE;FI]
inoperable, batch waste gas releases may continue provided that the flow rate is estimated at least once per four hours. The reactor was critical with the Plant operating at 100 percent of rated power when the situa-tion was discovered.
At 1425 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.422125e-4 months <br /> on June 4, 1987, a batch release was initiated from Waste Gas Decay Tank T-68C.
Due to F1-ll21 being inoperable, the flow rate for the release was estimated at 1510 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.74555e-4 months <br />. The release was terminated at 2335 hours0.027 days <br />0.649 hours <br />0.00386 weeks <br />8.884675e-4 months <br />. The failure to perform the additional estimates was due to poor communication at a shift turnover. The Radiological Material Control Supervisor failed to turn over the responsibility for additional estimates to the oncoming Shift Supervisor. Appropriate procedures are-being revised to provide direction to Operations personnel in the event of flow indicator inoperability. The feasibility of utilizing addi-tional instrumentation to provide a flow rate indication is also being investigated.
The activity contained in T-68C was a fraction of 10CFR20 Appendix B limits, such that no adverse safety hazard existed.
=
@WM m LER 87-017-NLO2
ne,.,. ma u s wcma novaro2, ca..,..
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION
- aovio oue =o me.o.3 tapings gest ag
,aciuf v maast 11, DOCA t t wussea m 12' Lin av.etR I6i pa04 t3i vsam sa owa =0as
.me.ec=
' ~ ' "
'~"
PALISADES NUCLEAR PLANT 011 l7 0151010101215I5 81 ~'
Ol0 012 0F 0L rat w s
eac w maa enm Description on June 4, 1987 at approximately 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br />, Operations personnel discovered that contrary to Technical Specification (TS) 3.24.2, no flow rate estimation had been performed for cight hours and twenty-five minutes while batching out Waste Gas Decay Tank, T-68C (WE;TK). TS 3.24.2 states that with flow indicator FI-1121 [VE;FI] inoperable, batch waste gas releases may continue provided that the flow rate is estimated at least once per four hours. The reactor was critical with the Plant operating at 100 percent of rated power when the situation was j
discovered.
At 1425 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.422125e-4 months <br /> on June 4. 1987, a batch release from Waste Gas Decay Tank, T-68C was initiated.
We to flow indicator FI-1121 being in-operable, and in conjunction with TS 3.24.2, the flow rate of the release (approximately one cubic foot per minute) vas estimated at 1510 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.74555e-4 months <br />.
From 1510 until 2335 hours0.027 days <br />0.649 hours <br />0.00386 weeks <br />8.884675e-4 months <br /> when the batch release was terminated, two additional flow rate estimates were required, but not performed. This failure was discovered by Operations personnel during shift turnover to the oncoming shift.
The failure to perform the additional required flow rate estimations was attributed to poor communicar. ion between the Radioactive Material Control Supervisor and the oncoming Shift Supervisor. Also contributing to the failure was the low average release rate of approximately one cubic foot per minute. Typical batch releases are discharged at three i
to five cubic feet per minute such that only the initial estimate is needed.
Flow indicator F1-1121 was declared inoperable on March 5, 1987 when questionable flow rates were indicated during a batch release from Waste
{
Gas Decay Tank T-68A.
Five additional waste gas batches have been i
released since the flow indicator was declared inoperable, For each of j
the five batch releases, the required flow rate estimates had been performed, meeting the requirements of TS 3.24.2.
Therefore, this event is considered to be an isolated incident.
I i
Cause Of The Event
]
i The immediate failure to perform the additional two flow rate estimates I
was attributed to poor communications. The batch was initiated shortly before shift turnover and the Radiological Material Control Supervisor j
failed to turn over the responsibility to perform the additional esti-j mates to the oncoming Shift Supervisor. The oncomiag Shift Supervisor
]
and primary side Auxiliary Operator were both aware a release was in progress, however, both thought the Radiological Material Control group was performing required estimates.
\\
%sC 80au Jesa LER 87-017-NLO2 j
1
EC feem see.
U s NuCLt&A REcytavoz, Couuiesiom LICENSEE EVENT REPORT (LER) TEXT CONTINUATION
.**aoveo owe =o sino. eio.
l ex, mis
,2i n
..o e,
..o...,
a i
PALISADES UUCLEAR PLAh
" R'.n."
- '#.i:
015 (0 l0 f 0 l 2l515 8l 7 0l1l 7 0 l0 0l3 05 0 lL An additional contributing factor to the failure to perform the required 1
estimates was the low average release rate for this batch. During this release, the concents of T-68C were being discharged at approximately one cubic foot per minute. Typical waste gas batches are released at three to f M cubic feet per minute and are terminated in five hours i
such that only the initial estimate is.needed to meet the requirements of TS 3.24.2.
l This event would not have occurred had the flow indicator been operable.
l Therefore, the root cause of the event lies with the prolonged flow indicator inoperability.
Corrective Actions of Health Physics Procedure 6.6, Evaluation and Release of Waste Gas Decay Tank, will be revised to include a release rate formula and results area to provide additional guidance to the primary side Auxiliary Operator in the event flow indicator, FI-1121 is inoperable.
Standard Operating Procedure, (SOP) 18A, Radioactive Waste System Gaseous, will also be revised to provide guidance to Operations Personnel.
The feasibility of utilizing additional instrumentation to provide flow rate indications is being investigated and will be implemented if applicable.
The current practice utilized to assign work order priorities for Technical Specification associated equipment with alternate actions other than returning the equipment to service will be reviewed for enhancements such that the potential for events occurring with similar root cause will be minimized.
i l
Operations Department personnel are receiving training on effective I
communication techniques in their continuing training program.
Analysis Of The Event i
l The activity contained in Waate Gas Decay Tank T-68C was a fraction of
{
10CFR20 Appendix B limits, such that no adverse safety consequences were presented to the general public.
Current practice for release of Waste Gas Decay Tanks prohibit the initiation of a release for minimum of fifteen days, for any tank nearing 10CFR20 Appendix B limits for Xe-133, such that if the release rate exceeds anticipated values, no adverse consequences would exist.
j I
This event is being reported per 10CFR50.73 es a condition prohibited by i
Plant Technical Specifications, j
4RC 80au 304a LER 87-017-NLO2 i
g
%1C Sese anta u 4 NUCLE AR A8GULAf 0Av COMw:sseON LICENSEE EVENT REPORT (LER) TEXT CONTINUATION an.ov te eu. No me.oio.
E spists a<31 es f acilli7 NAass igg DOCKET MusetR 121 LSA WyanstAits eact ist l
egan 84 3W8 * Ah : '.tv&C=
PALISADES ITUCLEAR PLMIT 01117 0 Is jo j o jo l21515 81 7 0l0 0 lh or
'l-rmw=
.- wcwanw.nm Additional Information Summary of Waste Gas Batch Releases since FI-1121 was inoperable:
1 Batch Date of Start Time That Flow Batch Number Release Time Rate Estimated Stoo Time 87-008-G 3/23/87 13:46 14:06 17:00 1
87-009-G 3/24/87 12:20 12:40 14:25 87-010-G 3/26/87 15:40 15:40 17:20 87-012-G 4/7/87 12:10 13:40 17:00 q
87-015-G 5/26/87 11:10 11:45 15:20 87-018-G 6/4/87 14:25 15:10 23:35 Flow indicator, FI-1121 is an Ashcroft Gauge model number 1009.
Reference LER 87-010 for an additional report submitted pertaining to the f ailure to return TS arsociated equipttent (with alternate actions) to service in a timely manner.
l l
l i
i i
k i
i 1
LER 87-017-NLO2 i