ML20141H619
| ML20141H619 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 07/23/1997 |
| From: | Tehan T RHODE ISLAND, STATE OF |
| To: | Mendonca M NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9707310263 | |
| Download: ML20141H619 (22) | |
Text
..
TATE OF RHODE ISLAND AND PROVIDENCE PLANTATIONS RHODE ISLAND ATOMIC ENERGY COMMISSION Nuclear Science Center South Ferry Road Narragansett, R.I. 02882-1197 July 23,1997 Docket No. 50-193 Mr. Marvin Mendonca, Senior Project Manager Non-Power Reactors, Decommissioning and Environmental Project Directorate Division of Reactor Projects - III/IV/V.
U.S. Nuclear Regulatory Commission (NRC)
Washington, D.C. 20555
Dear Mr. Mendonca,
This letter and enclosures constitute the annual report required by Technical Specifications (Section 6.8.4). Enclosure 1 provides reactor operating statistics. provides information pertaining to inadvertent reactor shutdowns or scrams. discusses maintenance operations performed during the reporting period. describes changes to the facility carried out under the conditions of Section 50.59 of 10CFR50. Lastly, enclosure 5 summarizes the radiological controk information.
If there are any questions regarding this information, please call me at 401-789-9391.
Sincerely,
/
Te ehan Director i
DhO I
Enclosures (5)
Copy to:
T. Dragoun, Region One H. Knickle, Chairman NRSC fffkfkfkffllf.flfff.fflllflllllll 9707310263 970723 PDR ADOCK 05000193 6
Technical Specifications Section 6.8.4.a. (96-7) 1 Reactor Energy Energy Critical Generated Generated Month
- (hours)
(MWh)
(mwd)
July-96 3.00 0.30 0.01 August-96 0.20 0.10 0.00 September-96 31.48 29.06 1.21 October-96 92.22 155.00 6.46 November-96 44.97 75.93 3.16 December-96 53.93 91.34 3.81-January-97 34.75 61.34 2.56 l
February-97 105.17 177.34 7.39
?
March-97 82.40 141.56 5.90 April-97 113.05 189.04 7.88 4
May-97 88.90-145.91 6.08 June-97 47.52 79.37 3.31 1996-97 Totals:
697.59 1,146.29 47.76 Total Energy Output since initial Criticality:
55,025.76 2,292.82 9
g i
- - o v--,
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3.--
t ENCLOSURE 2 EMERGENCY SHUTDOWNS AND INADVERTENT SCRAMS The following is a listing of the emergency shutdowns and inadvertent scrams, including the reasons, which occurred during the 1996-97 reporting period. This information is required by Technical Specification 6.8.4.b.
DATE RUN#
LOGBOOK /PAGE REASON 8/29/96 6917 45/101 Reactor shutdown after high conductivity reading on the delay tank and lab sample of the primary coolant. The suspected cause was entrained air in the water after the system was opened for upgrade. The entrained air would ionize and conductivity would increase. The reactor was run at low power to gradually heat the water and drive off any remaining air. Conductivity readings returned to normal.
12/4/96 6948 45/136 Inadvertent reactor scram caused by Log N high period.
Instrument malfunction (noise) due to high humidity. The reactor was not near criticality. Light in cabinet turned on to dry out instrument.
12/5/96 6949/50 45/137 Inadvertent reactor seismic scram. He reactor was re-started and the reactor experienced another seismic scram two hours later. There was no seismic activity. The problem being a bent support wire which occurred during performance of the monthly reactor system tests. The -
seismic switch (pendulum) was adjusted and the problem was corrected.
12/30/96 6957 45/145 Inadvertent reactor scram caused by Log N high period.
Instrument malfunction (noise) due to high humidity. The reactor was not near criticality. Light in cabinet turned on to dry out instrument.
12/31/96 6958 45/146 Reactor shutdown after receiving a high stack reading.
The cause was determined to be hose which detached from the rabbit system.
1/2/97 6960 45/147 Inadvertent reactor scram caused by Log N high period.
Instrument malfunction (noise) due to high humidity. The reactor was not near criticality. Light in cabinet turned on to dry out instrument.
1/28/97 6963 46/7 Inadvertent reactor scram on a loss of power to the #2 wide range (PICO) power instrument. The cause of the i
failure was a tripped circuit breaker on the main floor.
1/30/97 6965 46/10 Unplanned reactor shutdown due to a loss of secondary system flow. Upon investigation, the secondary system blowdown timer had failed in the blowdown mode and the i
makeup could not keep up with the blowdown.
Subsequently, the secondary pump lost suction and automaticaly tripped to prevent running pump without water.
1 l
1 l
ENCLOSURE 2 (conQ l
EMERGENCY SHUTDOWNS AND INADVERTENT SCRAMS J
DATE RUN#
LOGHOOK/PAGE REASON 2/21/97 6979 46/25 Reactor scram by reactor operator upon hearing the evacuation alarm. He evacuation system was initiated as part of an unplanned emergency drill.
3/14/97 6987 46/36 The reactor was being operated with the new primary and secondary systems (#1 system) when the high inlet temperature alarm for the primary system annunciated.
The senior operator was notified and it was discovered that the reactor operator was operating the new (#1) primary system in conjunction with the old (#2) secondary system.
1 The two loops are unable to communicate and therefore the primary inlet temperature continued to rise, he operator placed the old (#2) primary in service and the reactor scrammed on low primary system flow. The l
momentary decrease in primary system flow was a result i
of starting a second pump which drew water away from the operating loop. The root cause was determined to be operator error and lack of attention to detail. Additionally, this was a new system being operated for the first time i
which also led to the problem. The operator was counseled and re4 rained to minimize the possibility of reoccurrence.
3/18/97 6989 46/37 Inadvertent reactor scram on a momentary loss of AC power. Associated with curren; weather conditions.
3/31/97 6997 46/46 Inadve l power.rtent reactor scram on a momentary loss of AC Associated with current weather conditions.
1
a ENCLOSURE 3 MAJOR MAINTENANCE OPERATIONS The following is a listing of the major maintenance operations performed in the 1996-97 reporting period which includes impact upon the safe operation of the reactor and the reasons for the corrective maintenance. This information is required by Technical Specification 6.8.4.c.
- 1. Primary Coolant Channel Gate Repair On January 13,1997 the primary system delay tank was drained for the primary pump suction diaphragm valve replacement. An inspection of the delay tank was s; kduled for that time also because a clanging sound could be heard by the staff when testing the primary pumps in parallel operation (3600 gpm). The staff hypothesized that a delay tank baffle had come loose from the inside of the tank and would be thrown about at high flow rates (two pump operation). The tank was isolated from the pool, drained, and inspected. The staff discovered that one of the primary system coolant channel gate vanes had bent and broken off of the coolant gate.
The coolant channel gates are an integral part of the coolant channel and must be closed during forced convection to direct the primary flow down to the core and must be open during natural convection to allow the pool water to circulate through the core. The vane is attached to the coolant gate and extends into the coolant channel. During forced convection, the vane is acted upon by the force of the water and holds the coolant gate closed. During natural convection, the vane acts as a counter-weight and causes the gate to fall open.
On January 17,1997 the fuel was unloaded from the core and placed in the fuel storage racks in preparation for draining the high power section of the pool. On January 21,1997 the high power section of the pool was isolated and drained / pumped to a level below the 10" primary pipes and the location of the coolant channel gates. A new vane was fabricated as a replacement, but the design was slightly altered. The new vane surface area was reduced by half so as to reduce the force applied to the vane shaft by the flow of primary coolant.
Although the surface area of the vane was decreased, the weight proportion remained constant and therefore the counterweight moment remained the same.
Once the pool level was at the desired location, dose rates were checked by Health Physics personnel. The dose rates were negligible and a staff member donned protective clothing and was lowered down to the coolant channel gate. The vane was replaced and tested for proper operation. The repair resulted in no contamination or exposure to the individual lowered into the pool.
l I
l P
l l
ENCLOSURE 3 (cont) l' l
MAJOR MAINTENANCE OPERATIONS j
i Although the vane had separated from the coolant channel gate, the operation of the gate during forced convection was satisfactory. The gate remained closed during forced convection due to both the loss of the counter weight and the flow of the coolant. Had the gate failed to remain closed in the forced convection mode, a scram would have occurred. However, during the natural circulation mode the gate is supposed to open to allow communication between the pool water and the water in the primary coolant channel. The staff believes that even if l
the gate did not open there would have been ample cooling provided by the pool water since the core cover plates are not installed. Without the core cover plates installed, the water being heated by the core during natural convection can freely l
rise and mix with the pool water.
l l
- 2. Primary Suction Valve Replacement On January 14,1997, the primary pump suction diaphragm valves were replaced.
The staff decided that the valves should be replaced because of the apparent i
excessive suction head losses across the existing valves. The old diaphragm valves were replaced with new stainless steel butterfly valves which did reduce the differential pressure across the valves.
I The valve replacement had no impact on the safe operation of the reactor.
- 3. Emergency Generator Water Pump On March 6,1997, during the weekly run of the emergency generator, a staff member noticed that the radiator fan was rotating asymmetrically. The senior j
reactor operator was notified and the reactor operator was told to stop the normal reactor startup (Technical Specifications requires the emergency generator to be operable). The emergency generator was stopped and locked out to investigate. It l
was quickly discovered that the water pump assembly had a failed bearing. The radiator fan is part of the water pump assembly which is belt driven off of the crankshaft of the engine. The water pump assembly and fan were removed and the water pump assembly was replaced with one in stock. The generator was subsequently run and determined to be operating properly.
i
ENCLOSURE 3 (cont)
MAJOR MAINTENANCE OPERATIONS i
- 4. Start-up Counter L
On March 20,1997, the reactor operator on duty notified the senior reactor operator that the start-up counter (SUC) was experiencing erratic counts and period indication. The reactor start-up was stopped and the SUC housing was pulled from the pool. Upon disassembly, the housing was found to be partially filled with water. It was determined that the water was causing the detector to short and give erroneous readings. The detector, associated wiring, and housing was replaced and reinserted into the pool. On April 3,1997, similar problems with the SUC occurred. Again, the housing was pulled, inspected, and dried out.
SUC problems occurred approximately every two weeks for various reasons.
Each time the detector and associated wiring was inspected and dried out and the staff would work to make small changes to better the SUC. The SUC is now working and has not failed in approximately two months. The primary cause for the failures is unknown, however a new SUC housing was fabricated for a spare if the need arises.
1 l
4 i.
i 1
ENCLOSURE 4 FACILITY CHANGES - 10CFR50.59 REVIEW The following is a listing and description of 10CFR50.59 evaluations conducted during the 1996-97 reporting period. This information is required by Technical Specification 6.8.4.d.
- 1. Primary Pump Suction Valves Pursuant to 10CFR50.59, a committee was formed to evaluate the replacement of f
the primary pump suction diaphragm valves with butterfly type valves to increase the net positive suction head at the pumps. The butterfly valves will reduce the pressure drop across the valve with only a smooth plate in the center of the flow.
The valves are constructed of stainless steel and will provide the same isolation capability as the diaphragm valves. This change did not require a change in the Technical Specifications nor did it create an unresolved safety question.
- 2. Reactor Scram and Alarm Circuits r
Pursuant to 10CFR50.59, a committee was formed to evaluate the change of the primary system flow alarm and scram circuits. With the new primary and secondary systems in place, the alarm and scram circuits were reviewed and determined to be inadequate for operation with the new systems and future operation above 2MW. The alarm circuit contacts for operation below 2MW should be placed in series and for operation above 2MW the contacts should be in l
parallel. The scram circuitry, being fail safe, should be in parallel for operations i
below 2MW and in series for operations above 2MW. This circuitry allows for operation of either primary / secondary loop at the licensed power level.
Additionally, the circuitry has been modified, with the exception of a jumper wire, to allow operation above 2MW in the future.
The changes do not alter the operation of the reactor at power levels at or below i
2MW and continue to cause a scram if the 5MW position is selected on the power schedule switch. This change did not require a change in the Technical Specifications nor did it create an unresolved safety question.
2
s.
ENCLOSURE 5 RADIOLOGICAL CONTROLS
- 1. Environmental Surveys Outside Facility - Technical Specification 6.8.4.e Quarterly TLD badges are deployed outside the reactor building in three separate locations. These locations are not frequented by the general public and therefore occupancy factors may be used to approximate the annual dose. The allowable external dose rates must be below 50 mrem. The doses are shown in the table below.
LOCATION 3RD QTR 1996 4TH QTR 1996 IST QTR 1997 2ND QTR 1997 Northeast Wall 380 mrem 470 mrem 350 mrem 370 mrem Demin Door 10 mrem 180 mrem 160 mrem 150 mrem Heat Exchanger 0 mrem 70 mrem 60 mrem 20 mrem Door The northeast wall area is in a location where access is limited. Consequently, the general public will not frequent this area and appropriate occupancy factors can be used to approximate the annual dose. The dose in this area is due to storage in the reactor room and is present regardless of reactor operation. Assuming that the j
maximum time a member of the general public would be present in this location is 15 minutes / day. An occupancy factor of 0.01 can be used to obtain an annual dose of 15.7 mrem.
The demineralizer and heat exchanger doors are restricted areas as well. Access to these two areas is limited and posted with a chain across the driveway.
Assuming that the maximum time a member of the general public would be present in this location is 15 minutes / day. This dose is only present when the i
reactor is in operation (approx. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> / day). An occupancy factor of 0.04 can be used to obtain an annual dose of 26.8 mrem (demineralizer door) and 8.8 mrem (heat exchanger door).
- 2. Annual Exposures Exceeding 500 mrem - Technical Specification 6.8.4.f There were no personnel exposures greater than the above limit.
- 3. Radioactive Effluents - Technical Specification 6.8.4.g A.
Gaseous effluent concentrations are documented on the Monthly Information Sheets (Form NSC-78) enclosed. The gaseous effluents,
I s.
t primarily Argon-41, are about 3-4% of the maximum permissible concentrations.
B.
Liquid effluent concentrations released to the sewer are documented on the Sewer Disposal Record (Form NSC-52) and/or the Liquid Release (Form NSC-17). The concentrations are well below the monthly sewer limits.
The liquid effluent releases have been reduced considerably because the pool leak water is now being collected and returned to the pool. Below is a summary of the liquid effluents released.
1 DATE VOJUME ACTIVITY 87c OF LIMIT ORIGIN 10/1/96 900 gal
< 500 pCi 2%
Pool 1/10/97 4000 gal 1.85 mci 8%
Delay Tank 1/15/97 10.000 gal 4.66 mci 10.4 %
Pool i
- Note: The water contains a mixture ofisotopes, the principal ones being Co-60, Cs-137, Sb-122, Sb-124, and H.
3 9
l i
- - ~ _ -.. -. - _ - _ - _ - _ -. - _ - _ _ _ - _ - _ _ - - - _ _ _ - - - - -. -.
1 1
Monthly information Sheet NSC-78 l Month:
Jul-96 l
l Revised 5/18/95 _ l Cumulative MWH's l Start:
4183.46 l l
End:
4183.76 l 3
Run Ave Power Start S/D Operating Todays Stack Stack No.
Day Level Time Time Time total Monitor
% EC (1-31)
(MW)
(hhmm)
(hhmm)
(hrs)
MWH max CPM noteased 6915 3
0.10 1133 1340 2.12 0.21 2,000 0.1 %
6916 24 0.10 1452 1545 0.88 0.09 1,000 0.0%
4 o
L Totals:
3.00 0.30
SUMMARY
Max.
Actual Max.
Actual Operating Hours:
154 3.00 M W H's:
308.00 0.30 Operating Percent:
2%
0%
4 m
~
+
.w-
t i
Monthly information Sheet NSC-78 i Month:
Aug-96 l
l Revised 5/18/95 l Cumulative MWH's l Start:
4183.76 l l
End:
4183.86 l Run Ave Power Start S/D Operating Todays Stack Stack -
No.
Day Level Time Time Time total Monitor
% EC (1-31)
(MW)
(hhmm)
(hhmm)
(hrs)
MWH max CPM Released 6917 29 0.50 1344 1356 020 0.10 2,000 0.0%
1 I
u d
Totals:
0.20 0.10
SUMMARY
Max.
Actual Max.
Actual Operating Hours:
154 020 M W H's:
308.00 0.10 Operating Percent:
0%
0%
O e
9 e
4
1 i
Monthly Information Sheet NSC-78 l Month:
Sep-96 l
l Revised S/18/95 l Cumulative MWH's l Start:
4183.86 l l
End:
4212.92 l Run Ave Power Start S/D Operating Todays Stack Stack No.
Day Level Time Time Dme total Monitor
% EC (1-31)
(MW)
(hhmm)
(hhmm)
(hrs)
MWH max CPM Released 6918 3
0.50 1004 1046 0.70 0.35 1,000 0.0%
6920 5
1.00 0942 0952 0.17 0.17 1,000 0.0%
{
6921-6 0.10 0949 1500 5.18 0.52 2,000 0.4%
6923 10 0.10 0935 1600 6.42 0.64 1,100 0.2%
6924 11 1.00 0922 1600 6.63 6.63 11,000 2.5%
6925 12 1.75 0947 1600 6.22 10.88 19,000 4.0%
6926 30 1.60 0950 1600 6.17 9.87 17,000 3.6%
4 Totals:
31.48 29.06
SUMMARY
Max.
Actual Max.
Actual Operating Hours:
140 31.48 MWH's:
280.00 29.06 Operating Percent:
22 %
10%
4 4
4 4
4 w.g.
y s
gp
Monthly information Sheet NSC-78 l Month:
Oct-96 l
l Revised 5/18/95 l Cumulative MWH's l Start:
53910.93 l l
End:
54065.93 l
- added HEU=49698.01 Run Ave Power Start S/D Operating Todays Stack Stack No.
Day Level Time Time Time total Monitor
% EC (1-31)
(MW)
(hhmm)
(hhmm)
(hrs)
MWH max CPM Released 6927 1
1.60 0930 1600 6.50 10.40 17,000 3.8%
6928 2
1.66 0941 1600 6.32 10.49 18,000 3.9%
6929 3
1.60 0941 1600 6.32 10.11 19,000 4.1 %
6930 8
1.75 0915 1600 6.75 11.81 20,000 4.6%
6931 9
1.70 0903 1600 6.95 11.82 19,000 4.5%
6932 10 1.65 0915 1600 6.75 11.14 18,000 4.1 %
6933 15 1.73 0911 1600 6.82 11.79 20,000 4.7%
6934 17 1.75 0916 1600 6.73 11.78 20,000 4.6%
6935 22 1.75 0930 1600 6.50 11.38 20,000 4.4 %
6936 23 1.65 0910 1600 6.83 11.28 20,000 4.7%
6937 24 1.55 0947 1550 6.05 9.38 19,000 3.9%
6938 29 1.75 0914 1600 6.77 11.84 20.000 4.6%
6939 30 1.63 0904 1600 6.93 11.30 18,000 4.3%
6940 31 1.75 1000 1600 6.00 10.50 18.000 3.7%
Totals:
92.22 155.00
SUMMARY
Max.
Actual Max.
Actual Operating Hours:
154 92.22 M W H's:
308.00 155.00 Operating Percent:1 60 %
50 %
e k
h 9
g m-m y
,m,
~-
Monthly Information Sheet NSC-78 l Month:
Nov-96 l
l Revised 5/18/95 l 4
Cumulative MWH's l Start:
54065.93 l l
End:
54141.86 l
- added HEU=49698.01 Run Ave Power Start S/D Operating Todays Stack Stack No.
Day Level Time Time Time total Monitor
% EC (1-31)
(MW)
(hhmm)
(hhmm)
(hrs)
MWH maxCPM Released 6941 4
1.75 0922 1600 6.63 11.61 20,000 4.5%
6942 6
1.70 0925 1500 5.58 9.49 19,000 3.6 %
6943 7
1.65 0935 1600 6.42 10.59 19,000 4.2%
6944 13 1.65 0903 1600 6.95 11.47 20,000 4.7%
6945 14 1.70 0921 1600 6.65 11.31 20,000 4.5%
6946 19 1.70 0917 1600 6.72 11.42 18,000 4.1 %
6947 27 1.67 0959 1600 6.02 10.05 -
18,000 3.7%
Totals:
44.97 75.93
SUMMARY
Max.
Actual Max.
Actual Operating Hours:
126 44.97 M W H's:
252.00 75.93 Operating Percent:
36 %
30 %
S 4
.k-
4 1
Monthly Information Sheet NSC-78 l Month:
Dec-96 l
l Revised 5/18/95 l Cumulative MWH s l Start:
54141.86 l l
End:
54233.20 l
- added HEU=49698.01 Run Ave Power Start S/D Operating Todays Stack Stack No.
Day Level Time Time Time total Monitor
% EC (1-31)
(MW)
(hhmm)
(hhmm)
(hrs)
MWH max CPM neleased 6948 4
1.78 1001 1400 3.98 7.09 20,000 2.7%
6949 5
1.75 1007 1140 1.55 2.71 20,000 1.1 %
6950 5
1.72 1227 1600 3.55 6.11 20,000 2.4 %
6951 10 1.70 0959 1600 6.02 10.23 21,000 4.3%
1713 7.68 12.68 20,000 5.2 %
6952 11 1.65 0932 6953 12 1.65 0931 i 1600 6.48 10.70 20,000 4.4%
6954 17 1.72 0934 1600 6.43 11.07 20,000 4.4%
6955 18 1.65 0912 1600 6.80 11.22 17,000 3.9%
6956 23 1.72 1041 1600 5.32 9.14 19,000 3.4 %
6957 30 1.70 0953 1600 6.12 10.40 18,000 3.8%
Totals:
53.93 91.34
SUMMARY
Max.
Actual Max.
Actual Operating Hours:
147 53.93 M W H's:
294.00 91.34 Operating Percent:
37 %
31 %
I e
9
~ e
-.m
Monthly Information Sheet NSC-78 l Month:
Jan-97 l
l Revised 5/18/95 l Cumulative MWH's l
Start:
54,233.20 l l
End:
54,294.54 l
- added HEU=49698.01 -
Run Ave Power Start S/D Operating Todays Stack Stack No.
Day Level Time Time Time total Monitor
% EC (1-31)
(MW)
(hhmm)
(hhmm)
(hrs)
MWH max CPM Released 6960 2
1.80 0957 1600 6.05 10.89 18,000 3.7%
6961 7
0.00 6962 27 1.84 0936 1600 6.40 11.78 18,000 3.9%
6963 28 1.70 0951 1600 6.15 10.46-15,000 3.1 %
6964 29 1.72 0923 1600 6.62 11.38 15,000 3.4 %
6965 30 1.80 0920 1220 3.00 5.40 15,000 1.5 %
6966 31 1.75 0928 1600 6.53 11.43 16,000 3.6%
Totals:
34.75 61.34
SUMMARY
Max.
Actual Max.
Actual Operating Hours:
154 34.75 M W H's:
308.00 61.34 Operating Percent:
23 %
20 %
b o
9
NSC-78 Monthly information Sheet NSC-78 l Month:
Feb-97 l l Revised 2/24/97 l Cumulative MWH's TouL LEU l Start:
54,294.54 l l End: l 54,471.881 4,773.87 l
- added HEU=49698.01 Run Ave PWr Start S/D Operating Todays Stack Stack No.
Day Level Time Time Time total Monitor Ar-41 Released (1-31)
(MW)
(hhmm)
(hhmm)
(hrs)
MWH max CPM uCl/cc Ci/ day 6967 3
1.72 0922 1600 6.63 11.41 15,000 7.35E-05 1.76 6968 4
1.70 0928 1600 6.53 11.11 15,000 7.35E-05 1.73 6969 5
1.60 0917 1600 6.72 10.75 14,000 6.86E-05 1.66 6970 6
1.80 0911 1500 5.82 10.47 14,000 6.86E-05 1.44 6971 7
1.65 0912 1530 6.30 10.40 14,000 6.86E-05 1.56 6972 10 1.80 0913 1600 6.78 12.21 17,000 8.33E-05 2.03 6973 11 1.68 0921 1600 6.65 11.17 14,000 6.86E-05 1.64 6974 12 1.60 0920 1600 6.67 10.67 14,000 6.86E-05 1.65 6975 13 1.60 0920 1600-6.67 10.67 15,000 7.35E-05 1.76 6976 18 1.79 0915 1600 6.75 12.08 15,000 7.35E-05 1.79 6977 19 1.65 0915 1600 6.75 11.14 14,000 6.86E-05 1.67 6978 20 1.63 0915 1600 6.75 11.00 14,000 6.86E-05 1.67 6979 21 1.65 0918 0934 0.27 0.44 12,000 5.88E-05 0.06 6980 21 1.62 1038 1600 5.37 8.69 14,000 6.86E-05 1.33 6981 24 1.82 0913 1600 6.78 12.35 15,000 7.35E-05 1.79 6982 25 1.66 0907 1600 6.88 11.43 14,000 6.86E-05 1.70 6983 27 1.66 0909 1600 6.85 11.37 13,000 6.37E-05 1.57 Totals:
105.17 177.34 26.79
SUMMARY
Operating
. Max.
Actual Max.
Actual Hours 140.0 105.2 M W H's:
280.0 177.3 Percentage 75%
63 %
Stack Releases 26.8 curies
. T.
NSC-78 Monthly Information Sheet NSC-78 l Month:
Mar-97 l l Revised 2/24/97 l Cumulative MWH's Tom uu l Start: 54,469.88 l l End: l 54,611.4414,913.43 l
- added HEU=49698.01 Run Ave Pwr Start S/D Operating Todays Stack Ar.41 Released No.
Day Level Time Time Time total Monitor Umit = 1E-3 uC/cc (1-31)
(MW)
(hhmm)
(hhmm)
(hrs)
MWH maxCPM uCi/cc CVday 6984 4
1.80 0921 1600 6.65 11.97 15,000 7.35E-05 1.76 6985 5
1.65 0920 1600 6.67 11.00 14,000 6.86E-05 1.65 6986 12 1.78 0910 1600 6.83 12.16 17,000 8.33E-05 2.05 6987 14 1.81 0934 1007 0.55 1.00 14,000 6.86E-05 0.14 6988 14 1.78 1111 1500 3.82 6.79 16,000 7.84E-05 1.08 6989 18 1.71 0917 1550 6.55 11.20 15,000 7.35E-05 1.73 6990 19 1.65 0913 1600 6.68 11.03 15,000 7.35E-05 1.77 6991 21 1.75 0908 1600 6.87 12.02 16.000 7.84E-05 1.94 6992 24 1.78 0904 1600 6.93 12.34 17.000 8.33E-05 2.08 6993 25 1.70 0907 1600 6.88 11.70 17,000 8.33E-05 2.06 6994 26 1.65 0902 1600 6.97 11.50 15,000 7.35E-05 1.84 6995 27 1.63 0908 1600 6.87 11.19 13,000 6.37E-05 1.57 6996 28 1.65 0909 1530 6.35 10.48 14,000 6.86E-05 1.57 6997 31 1.90 0921 1308 3.78 7.19 13,500 6.62E-05 0.90 Totals:
82.40 141.56 22.14
SUMMARY
Operating Max.
Actual Max.
Actual Hours 140.0 82.4 M W H's:
280.0 141.6 Percentage 59 %
51 %
Stack Releases 22.1 curies t
NSC-78 Monthly information Sheet NSC-78 l Month:
Apr-97 l l Revised 2/24/97 l Cumulative MWH's Tom.
Leu l Start: 54.611.44 l l End: l 54,800.48 I 5,102.47 l
- added HEU=49698.01 Run Ave Pwr Start S/D Operating Todays Stack Ar-41 Released No.
Day Level Time Time Time total Monitor Limit = IE-3 uC/cc (1-31)
(MW)
(hhmm)
(hhmm)
(hrs)
MWH maxCPM uCVcc CUday 6998 2
1.72 0920 1600 6.67 11.47 15,000 7.35E-05 1.76 6999 4
1.71 0903 1600 6.95 11.88 14,000 6.86E-05 1.72-7000 7
1.80 0918 1600 6.70 12.06 15,000 7.35E-05 1.77 7001 8
1.66 0904 1600 6.93 11.51 16,000 7.84E-05 1.96 7002 9
1.62 0917 1600 6.72 10.88 16,000 7.84E-05 1.90 7003 10 1.65 0910 1600 6.83 11.28 17,000 8.33E-05 2.05 7004 14 1.77 0903 1600 6.95 12.30 16,000 7.84E-05 1.96 7005 15 1.65 0907 1600 6.88 11.36 15,000 7.35E-05 1.82 7006 16 1.64 1149 1600 4.18 6.86 15,000 7.35E-05 1.11 7007 18 1.65 0906 1600 6.90 11.39 15,000 7.35E-05 1.83 7008 21 1.75 0947 1600 6.22 10.88 17,000 8.33E-05 1.86 7009 23 1.73 0902 1600 6.97 12.05 16.000 7.84E-05 1.97 7010 24 1.60 0910 1600 6.83 10.93 15,000 7.35E-05 1.81 7011 25 1.57 0906 1600 6.90 10.83 15,000 7.35E-05 1.83 7012 28 1.75 0917 1600 6.72 11.72 15.000 7.35E-05 1.78 7013 29 1.60 0913 1600 6.78 10.85 14,000 6.86E-05 1.68 7014 30 1.56 0905 1600 6.92 10.79 14,000 6.86E-05 1.71 Totals:
113.05 189.04 30.50
SUMMARY
Operating Max.
Actual Max.
Actual Hours 154.0 113.1 M W H's:
308.0 189.0 Percentage 73 %
61 %
Stack Releases 30.5 curies
4 k
NSC-78 Monthly Information Sheet NSC-78 l Month:
May-97 l l Revised 5/12/97 l Cumulative MWH's Tout
. Leu l Start: 54,800.48 l l End: l 54,946.39 I 5,248.38 l
- added HEU=49698.01 Run Ave Pwr Start S/D Operating Todays Stack
. Ar-41 Released No.
Day Level Time Time Time total
. Monitor Umit = 4E-4 uC/cc (141)
(MW)
(hhmm)
(hhmm)
(hrs)
MWH max CPM uCUcc CUday 7015 1
1.50 0919 1600 6.68 10.03 14,000 6.86E-05 1.65 7016 5
1.82 0919 1600 6.68 12.16 16,000 7.84E-05 1.89 7017 7
1.73 0903 1600 6.95 12.00 15,000 7.35E-05 1.84 7018 8
1.63 0908 1600 6.87
-11.19 15,000 7.35E-05 1.82 7019 9
1.56 0909 1600 6.85 10.69 14,000 6.86E-05 1.69 7020 12 1.60 0902 1600 6.97 11.15 15,000 7.35E-05 1.84 7021 14 1.70 0907 1600 6.88 11.70 15,000 7.35E-05 1.82 7022 15 1.55 0906 1600 6.90 10.70 14,000 6.86E-05 1.70 7023 19 1.72 0914 1600 6.77 11.64 14,000 6.86E-05 1.67 7024 20 1.55 0910 1600 6.83
-10.59 13,000 6.37E-05 1.57 7025 21 1.55 0914 1600 6.77 10.49 13,000 6.37E-05 1.55 7026 23 1.70 0909 1600 6.85 11.65 15,000 7.35E-05 1.81 7027 27 1.73 0906 1600 6.90 11.94 14,000 6.86E-05 1.70 Totals:
88.90 145.91 22.56
SUMMARY
Operating Max.
Actual Max.
Actual Hours 147.0 88.9 MWH's:
294.0 145.9 Percentage 60 %
50 %
Stack Releases 22.6 Curies
, o e
I i
NSC-78 Monthly information Sheet NSC-78 l Month:
Jun-97 l l Revised 5/12/97 l Cumulative MWH's Torat teu l Start: 54,946.39 l l End: l 55,025.76 i 5.327.75 l
- added HEU=49698.01 Run Ave Pwr Start S/D Operating Todays Stack Ar-41 Released No.
Day Level Time Time Time total Monitor Limit = 4E-4 uC/cc (1-31)
(MW)
(hhmm)
(hhmm)
(hrs)
MWH max CPM uCUcc CUday 7029 18 1.75 0936 1600 6.40 11.20 12,000 5.88E-05 1.35 7030 19 1.63 0919 1600 6.68 10.89 12,000 5.8SE-05 1.41 7031 20 1.65 0901 1550 6.82 11.25 12,000 5.88E-05 1.44 7032 23 1.75 0920 1600 6.67 11.67 13,000 6.37E-05 1.53 7033 24 1.66 0855 1600 7.08 11.76 13,000 6.37E-05 1.62 7034 25 1.65 0901 1600 6.98 11.52 12,000 5.88E-05 1.48 7035 26 1.61 0907 1600 6.88 11.08 12,000 5.88E-05 1.46 Totals:
47.52 79.37 10.30
SUMMARY
Operating Max.
Actual Max.
Actual Hours 147.0 47.5 M W H's:
294.0 79.4 Percentage 32%
27 %
Stack Releases 10.3 curies
- . \\
's
.