ML19312D938
| ML19312D938 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/05/1980 |
| From: | Jay Collins Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Snyder B Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-TMI-80-080, CON-NRC-TMI-80-80 NUDOCS 8005230033 | |
| Download: ML19312D938 (8) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMisslON 3
S WASHINGTON, D. C. 20555 E
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May 5, 1980 NRC/TMI-80-080 0
MEMEORANDUM FOR:
H. R. Denton, Director, Office of Nuclear Reactor Regulation
- b. J. Snyder, Program Director, TMI Program Office FROM:
J. T. Collins, Deputy Program Director, TMI Program Office
SUBJECT:
NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Enclosed is the status report for the week of April 26 - May 2,1980.
- -f$e< ?fr!dN
. ohn T. Collins Deputy Program Director TMI Program Office
Enclosure:
As stated cc:
ED0 OGC Office Directors Commissioner's Technical Assistants NRR Division Directors THIS DOCUMtiiT CONTAINS i4RR A/D's P00R QUALITY PAGES Regional Directors IE Division Directors X00S X0MA HEW EPA Public Affairs, RI T. Elsasser TMI Program Staff l
8005230033
NPC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT Week of:
April 26 - May 2,1980 Plant Status Core Cooling Mode:
Cyclic natural circulation in the "A" reactor coolant system (RCS) loop via the "A" once through steam generator V
(OTSG), steaming to the main condenser, and RCS loop-A and B cyclic natural circulation to reactor building ambient.
Available Core Cooling Modes: 0TSG "B" to the main condenser; long term cooling "B" (OTSG-B); decay heat removal.
RCS Pressure Control Mode:
Standby Pressure Control (SPC) System.
Backup Pressure Control Mode: Makeup system in conjunction with letdown flow (Emergency use only due to suspected leaks in the seal injection system).
Major Parameters (As of 0400, May 2,1980) (approximate values)
Average Incore Thermocouples: 141 F Maximum Incore Thermocouple:
182 F RCS Loop Temperatures:
A B
Hot Leg 145 f 148 F Cold Leg (1) 106 F 96 F (2) 123 F 99 F RCS Pressure:
135psig(Heise)
Pressurizer Temperature:
302 F (Saturation Pressure 54 psig)
Reactor Building:
Temperature:
78 F Pressure:
.64 psig (Heise)
Water level: Elevation 290.6 ft. (8.1 ft. from floor) via decay heat system Elevation 290.2 ft. via penetration 401 manometer Environmental & Effluent Information 1.
Liquid effluents from TMI-l released to'the Susquehanna River, after processing, were within the limits specified in Technical Specifications.
2.
No 11guld effluents were discharged from TMI-2.
ei 3.
Results from EPA monitoring of the environment around the TMI site were:
EPA environmental stations registered background levels for air particulate and water samples.
I
2 Gas air sample results (Kr-85) for the period April 19-25, 1980, were: Bainbridge - 18 pCi/m3, Goldsboro - 23 pCi/m3, Middletown -
20 pCi/m3, and TMI Observation Center - 26 pCi/m3 EPA states that samples collected in the vicinity of TMI in recent months show background levels of Kr-85 to be in the range of 20-40 pCi/m3 of air.
For the period April 25-30, 1980, direct radiation (gamma) v readings showed no levels above background.
4.
Radioactive material shipments off site were as follows:
On Monday, April 28,1980, a Unit 2 reactor coolant sample was sent to the B&W Lynchburg Research' Center, Lynchburg, Virginia.
On Tuesday, April 29, 1980, a shipment consisting of 152 drums of low level baled waste from Unit 1 was shipped to Richland, Washington.
~
On Friday, May 2, 1980, a shipment of 11 wooden LSA boxes of low M el waste from Unit I was sent to Richland, Washington.
S.
EPICOR II processing status:
(Auxiliary building approximate quantities)
Amount processed this week:
22,000 gallons Amount processed to date:
247,000 gallons Amount to be processed:
198,000 gallons Major Activities (Past and Present) 1.
Reactor Coolant System (RCS) Pressure Reduction. On April 15, 1980, RCS pressure was reduced from 300 psig to 190 psig.
The pressure was further reduced to 135 psig on April 29, 1980.
It is planned j
to reduce pressure to 100 psig on May 7, 1980.
The primary system responded predictably to the pressure reductions.
Water samples drawn from the letdown system indicate that dissolved gas concentrations in the RCS will remain below saturation at 100 psig.
However, due to limited water circulation, it is assumed that gas saturated water and gas pockets do exist in portions of the P.CS.
The following gas pocket volumes versus primary pressure have been calculated:
RCS pressure Gas volume 300 psig 50 cubic feet 190 psig 57 cubic feet 136 psig 106 cubic feet 100 psig 138 cubic feet The above pressure / volume relations have been verified during-several pressure changes by comparing the amount of makeup / letdown to the resultant RCS pressure changes.
The RCS pressure reductions have not produced a noticeable effect on the secondary system. Both A and B loops continue-to " burp" periodically. The A loop " burp" interval _ increased from 21 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The'B loop " burps" sporadically every 80 to 110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br />.
3 The decreased " burp" frequency in the A loop is attributed to higher heat loses to the reactor building atmosphere.
The reactor building evaporative cooling system was activated on April 15, 1980, to reduce the reactor building pressure.
The " burp" frequency decreased after the reactor building cooling system was activated.
The RCS leak rate appears to have decreased as a result of the pressure reductions. Quantitative leak rate data will be provided after additional leak / makeup volumes are compiled.
Pressurizer heaters will not be used after pressure is reduced to 100 psig. The cycling of the heaters is producing pressure fluctuations.
The heaters have been used to maintain the water in the pressurizer just below the saturation temperature.
In this condition, the pressurizer was a potential source of pressure for the RCS in the event of an unplanned pressure reduction.
The hazards associated
^
with an unplanned depressurization have decreased with the decrease in thermocouple temperatures below ambient boiling.
2.
Proposal to Open Decay Heat System Valves DH-V-l and DH-V-;11.
The TMI Program Office staff is currently evaluating a licensee procedure to open two decay heat removal system valves (DH-V-1 and DH-V-171) wnich are located inside the reactor building. When opened, the valves will provide a flow path from the RCS to the mini decay heat removal system (MDHR) in the auxiliary building.
Construction of the MDHR is not complete, however, due to the rising water level in the reactor building, it is necessary to open the valves before the valve operators are submerged. At least one of the valves must be opened before the MDHR system can be put into service.
3.
Reactor Building Entry.
The reactor building entry which was scheduled for April 24, 1980, was postponed when the National Institute of Occupational Safety and Health (NIOSH) inspected the Bio Marine Bio Pac 60 breathing units and found that unauthorized modifications had been made.
The Bio Pac 60 has a service life of 60 minutes and was selected to be used by the reactor building entry team, i
The licensee has rescheduled the entry for May 20, 1980, and is l
revising procedures to either use the Bio Pac 60, if NIOSH recertifies the unit, or to use the Mine Safety Appliance Company (MSA) Model 401 breathing apparatus. The MSA unit has a service life of only 30 minutes and as a result, would require shortening the entry to 15 minutes.
The TMI Program Office staff is reviewing the proposed l
changes.
4.
Technical Working Group (TWG) for the TMI Information and Examination Program. Members of the TWG, Task 2.1, (Fission Product Transport and Dispersal'and Environments Characterization) arrived on site to commence data gathering activities.
The objective of Task 2.1 is to improve understanding of nuclear plant accident environments and the phenomona which contribute to those environments.
4 The group obtained reactor builoing gas samples through the R-626 penetration at elevation 347 feet. The samples will be analyzed for radiciosoptic and chemical composition.
Specifically, the gas samples will be analyzed for tritium, hydrogen, oxygen, nitrogen, carbon 14, helium, xenon, krypton, organic iodides, particulate iodine, elemental iodine and toxic gases.
6.
Ground Water Monitoring Program. Water samples were taken from eight ground water monitoring wells on Friday, May 2,1980.
The licensee intends to sample the monitoring wells once per week.
- Split, canposite samples will be sent to two independent laboratories for analysis.
The most current sample analysis results are attached.
Four observation wells have been completed in the vicinity of the borated water storage tank (BWST). Water and soil samples from these wells have been sent for analysis.
Commonwealth of Pennsylvania representatives have expressed concern over the existing practice of pumping approximately 100 gallons of water from each monitoring well to the storm drains during the sampling process. The Commonwealth representatives consider that this constitutes a release of potentially radioactive water through an unmonitored discharge point. As an interim resolution of the Commonwealth's concern, the excess water pumped during sampling on Friday, May 2, 1980, was released to the surface of the ground some distance from the well.
The final resolution of this matter is being pursued by the TMI Program Office staff.
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1
6 Meetings Held with Public Officials and Interested Groups 1.
On April 28, 1980, J. Collins appeared on a talk program on WLBR radio, Lebanon to answer questions from listeners about the cleanup operations.
2.
On April 28, 1980, J. Collins spoke to the Elizabethtown Kiwanis Club on the cleanup operations at TMI.
3.
On April 28, 1980, J. Collins, T. Elsasser and E. Bretthauer, EPA, met with representatives from area school boards at the Middletown High School.
4.
On April 30,1980, at 9:00 a.m., J. Collins, T. Elsasser and E. Bretthauer, EPA, met in Middletown with religious leaders from the Harrisburg area.
5.
On April 30,1980, at 1:30 p.m., J. Collins, T. Elsasser and E. Bretthauer, EPA, met with the York County Commissioners in York.
6.
On April 30,1980, at 4:20 p.m., T. Elsasser met with teachers from Northeastern Senior High School in Manchester.
7.
On May 2,1980, at 9:30 a.m., J. Collins and T. Elsasser met with the Mayor of York.
8.
On May 2,1980, J. Collins and B. Snyder briefed the ACRS on the status of the cleanup operations at TMI and the status of the Programmatic Environmental Impact Statement.
Future Meetings 1.
On May 5,1980, J. Collins will address the 9th grade Civic Classes at East Junior High School, Harrisburg.
2.
On May 5,1980, at 7:00 p.m., J. Collins, T. Elsasser and E. Bretthauer, EPA, will conduct a briefing in Manchester for officials from the following communities:
Conewago Township (West Shore), Dover Township, East Manchester Township, Hellam Township, Manchester, Manchester Township, Mount Wolf, Springettsburg, Warrington Township, and York Haven.
3.
On May 7,1980, J. Collins will appear on a talk program on WAHT radio, Lebanon, called "Two Way Radio" to answer questions from listeners concerning the cleanup operations.
4.
On May 7,1980, at 7:30 p.m., H. Denton, J. Collins, T. Elsasser and an EPA representative will meet in Harrisburg with various leaders of THI Alert to discuss cleanup operations at TMI Unit 2.
5.
On May 8,1980, at 11:00 a.m., J. Collins and T. Elsasser will meet 4
with the Energy Committee of the Pennsylvania Chamber of Commerce.
6.
On May 8,1980, J. Collins will address the Lower Swatara Lions Club at 6:30 p.m. at the Skyways Inn.
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