ML20055C402
| ML20055C402 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 12/31/1989 |
| From: | Cockfield D PORTLAND GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| PGE-1015-89, NUDOCS 9003080407 | |
| Download: ML20055C402 (176) | |
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David W. Cockfield Vice President, Nuclear 1
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l Febsmary 28, 1990 1
Trojan Nuclear Plant Docket 50-344 License NPF-1 l
U.S. Nuclear Regulatory Commission l
ATTN:
Document Control Desk i
Washington DC 20555 Dear Sir Annual Report Enclosed is one copy of Portland General Electric Company's Annual Report for the Trojan Nuclear Plant for the calendar year 1989.
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Sincerely,
,/
,4 W
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Enclosure c
Mr. David Stewart-Smith (2)
State of Ore 5on l
Department of Energy Mr. John B. Martin (1)
Regional Administrator, Region V i
U.S. Nuclear Regulatory Commission Nr. R. C. Barr (1)
NRC Resident Inspector Trojan Nuclear Plant q
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AddlB. bro 0K' (BR'*Ree8&ggggg;,v gs47 va 121 S.W. Salmon Street, Portland, Oregon 97204,503/464,8897
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l PGE 1015-89
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j ANNUAL REPORT i
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l TROJAN NUCLEAR PLANT u
FOR 1989 l O l
Docket 50-344 License NPF-1 n
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PORTLAND GENERAL ELECTRIC COMPANY 121 S. W. Salmon street Portland. Oregon 97204 s
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n IABLE OF CONTENTS CA&R s
INTRODUCTION.
i 1.
Radiour.tive Effluent Release Report.
1 A.
Effluent and Weste Disposal Report.
3 B.
Offsite Radiation Doses........
36 C.
Meteorological Data.
81 D.
Changes to the Offsite Dose Calculation Manual (CDCM) 82 E.
Reactor Coolant System (RCS) Specific Activity.
83 2.
Annual personnel Exposure and Monitoring Report.
44 3.
Staum Generator Tube Inspections and Maintenance.
88 4.
Relief Valve Challenges.-.........
109 S.
Emergency Core Cooling System Performance.
110 6.
Changes. Tests, and Experiments.
112 A.
Plant Modifications and Design Changes.
113 B.
License Amendments.
130 C.
Licensing Document Change Requests (LDCRs Approved During 1989) 142.
D.
Plant Tests....
157 E.
Changes to Procedures.........
161 F.
Setpoint Changes.......
162
INTRODVOTION The Annual Report of the Trojan Nuclear plant for 1989 is submitted in accordance with the requirements of Federal Regulations and Facility Operating License NpF-1, and as a supplement to the Monthly Operating Reports.
Other required reports are included for ease of reference and completeness.
FWt%ARY OF OPERATING EEptRIENCE IN 1989 The Trojan Nuclear plant began the year operating at full power.
On January 26 dredging of the area outside the intake structure was completed. An estimated 4.000 cubic yards of material was removed and pumped to the barge landing area and repairs were made to the trash racks and los boom.
The extensive program of reconstitution and repair of fuel elements, which had begun in mid-November of 1988, was completed on February 8.
power was reduced to 85 percent on February 19 for approximately fifteen hours to perform ex-core /in-core cross-calibration of nuclear instrumentation.
A small intemittent circulating water leak on the A-train of the "A" condenser had begun in early December 1988 and continued to be noticed.
Steam generator conductivity was maintained below the limits for unrestricted power operation.
On February 25, power was reduced to 55 percent and the A-train circulating water system was drained to perform maintenance activities to eliminate the leak. The A-train circulating water system was placed back in service with the leak indication still present but greatly reduced. Power was returned to 100 percent on February 26.
Resealing of the condenser water box bolts temporarily eliminated the remainder of the leak indication.
By late March, the periodic condenser leak indication returned causing the Steam Generator chemistry levels to enter the seven day action statement on several occasions.
Interim efforts successfully reduced the leak until it could be fully investigated and repairs accomplished during the refueling outage.
The 1989 refueling shutdown began with the reduction of power on April 5.
Significant outage activities were as follows:
- Inspection of the main turbino and generator began on April 11.
Examination of the main generator rotor bars revealed an unacceptable amount of copper dust and flakes. The generator was cleaned and reassembled with new slot insulation and separators between bars to correct the copper dusting problem.
Inspection of the high pressure O
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- During inspections of the containment recirculation sump, debris was found which apparently was present during the last power operation cycle. Additionally, it was discovered that the required screen on the top of the sump was not installed and installed portions of the i
screen were damaged. The debris was removed, the required screens l
were installed and/or repaired, and stricter controls were established for Containment cleanliness. The sump and Containment were successfully reinspected in accordance with the new requirements.
plant startup was delsyed by two unrelated problems with the rod l
control. system:
On July 29. a rod dropped due to a blown fuse. The Containment electrical penetration had experienced a ground that caused the.
1 failure of the fuse. The grounding problem was repaired and other circuits associated with the electrical penetration were verified i
to be good and/or were repaired and the system returned to service.
on July 31. as a rod was being withdrawn, it became mispositioned with respect to other rods. A team congrised of various Nuclear Division and NSSS vendor personnel resolved the cause of the
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mispositioned rod, which appeared to be mechanical interference with rod movement from a small piece of material which had become caught between a rodlet and guide tube.
Rod cycling and drop testing was performed to assure that the material had cleared.
The Plant was taken critical on August 1.
On August 2. during testing of the main turbine, excessive vibration caused a turbine trip. Investigation showed the problem to be a deflection in a coupling due to a small pin being lodged between the coupling and its cover. The coupling was reassembled and the turbine l
successfully retested.
By August 3. the turbine generator was brought up to 185 MWe for approximately three hours and it ran smoothly with low vibration.
The electrical overspeed trip of the turbine was successful, but the mechanical overspeed trip did not function. Adjustments were made and the mechanical overspeed trip test was successfully. completed.-
The plant tripped on over temperature delta-temperature (OTAT) on August 9.
The bistables for one channel of OTAT had been tripped for routine surveillance. A spurious signal on a second OTAT channel completed the two-out-of-four logic to cause the reactor trip. All safety systems functioned normally after the trip.
The reactor was restarted on August 14 and the plant was synchronized with the grid on August 15.
After plant startup on August 29, the Loop 4 OTAT began to experience additional spurious alarm signals.
Extensive testing and I
troubleshooting was conducted to locate the source of the spurious 111
INTRODUCTION O-The Annual Report of the Trojan Nuclear Plant for 1989 is submitted in accordance with the requirements of Federal Regulations and Facility Operating License NPF-1, and as a supplement to the Monthly Operating Reports.
Other required reports are included for ease of reference and completeness.
SUMMARY
OF OPERATING EXPERIENCE IN 1989 The Trojan Nuclear plant began the year operating at full power.
On January 26, dredging of the area outside the intake structure was completed. An estimated 4,000 cubic yards of material was removed and pumped to the barge landing area and repairs were made to the trash racks and log boom.
The extensive program of reconstitution and repair of fuel elements, which had begun in mid-November of 1988, was completed on February 8.
Power was reduced to 85 percent on February 19 for approximately fifteen hours to perform ex-core /in-core cross-calibration of nuclear instrumentation.
A small intermittent circulating water leak on the A-train of the "A" condenser had begun in early December 1988 and continued to be noticed.
Steam generator co,nductivity was maintained below the limits for unrestricted power operation.
On February 25, power was reduced to 55 percent and the A-train circulating water system was drained to perform maintenance activities to eliminate the leak. The A-train circulating water system was placed back in service with the leak indication still present but greatly reduced. Power was returned to 100 percent on February 26.
Resealing of the condenser water box bolts temporarily eliminated the remainder of the leak indication.
By late March, the periodic condenser leak indication returned causing the Steam Generator chemistry levels to enter the seven day action statement on several occasions. Interim efforts successfully reduced the leak until it could be fully investigated and repairs accomplished during the refueling outage.
The 1989 refueling shutdown began with the reduction of power on April 5.
Significant outage activities were as follows:
- Inspection of the main turbine and generator began on April 11.
Examination of the main generator rotor bars revealed an unacceptable amount of copper dust and flakes.
The generator was cleaned and reassembled with new slot insulation and separator) between bars to correct the copper dusting problem.
Inspection of the high pressure O
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I turbine identified the need for extensive repairs of the diaphragms i
due to erosion at the blade roots.
The repairs to the diaphragms were completed and reassembly of the turbine continued through the end of the month.
l Sludge lancing was performed on the four Steam Generators from
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April 13 to April 19.
l In-service inspection of the reactor vessel was accomplished between i
April 25 and May 8.
An indication was discovered in the A-loop nozzle to vessel weld: however, after examination this was determined i
to be within code allowable limits.
The Nuclear steam supply system (NSSS) vendor later provided an analysis for additional assurance that the flaw was acceptable.
Reactor coolant pump flange bolt work conunenced on April 19 and was concluded in June.
Testing of electrical penetration connections began on May 3.
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number of electrical cable wires had pulled loose from a containment 1
electrical penetration assembly during seal replacement.
Several more connections pulled loose during testing and the scope of the work was increased to test more connections.
Fuel reload consnenced on May 11 and was completed on May 16.
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Flux thimble testing, begun May 21, revealed that several thimbles had unacceptable amounts of thinning in the walls which resulted in the plugging of nine thimble tubes.
4 A minor fire (smoke only) occurred on June 7 due to a rub between the rotor and stator in the "B" circulating water pump.
The rub had damaged several windings in the pump and required that the pump be sent offsite for repair.
Eddy current testing performed on June 12 revealed twelve unexpected tube flaws in the "B" Steam Generator consisting of circumferential 1
1 cracks from the inside diameter of the tube, just below the top of the tube sheet. This resulted in the need for additional testing of all Steam Generator tubes, on the hotleg side.
Tubes with significant circumferential cracking were plugged.
Some of these tubes were also stabilized to prevent them from damaging adjacent tubes if the crack should propagate to failure during the next cycle. On July 16 special flushing and soaking with boric acid was done in an attempt to arrest the tube cracking.
j During inspections of supports for the control room ventilation and l
emergency diesel generator ventilation systems, it was discovered
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that certain supports did not meet the design requirements. The.
j supports of concern were replaced or repaired to meet specifications, i
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- During inspections of the containment recirculation sump, debris was found which apparently was present during the last power operation cycle. Additionally, it was discovered that the required screen on the top of the sump was not installed and installed portions of the screen were damaged. The debris was removed, the required screens were installed and/or repaired, and stricter controls were established for Containment cleanliness. The sump and Containment were successfully reinspected in accordance with the new requirements, plant startup was delayed by two unrelated problems with the rod control-system:
On July 29 a rod dropped due to a blown fuse. The Containment' electrical penetration had experienced a ground that caused the failure of the fuse. The grounding problem was repaired and other circuits associated with the electrical penetration were verified to be good and/or were repaired and the system returned to service.
On July 31 as a rod was being withdrawn, it became mispositioned with respect to other rods. A team comprised of various Nuclear Division and NSSS vendor personnel resolved the cause of the mispositioned rod, which appeared to be mechanical interference with rod movement from a small piece of material which had become caught between a rodlet and guide tube. Rod cycling and drop testing was performed to assure that the material had cleared.
The plant was taken critical on August 1.
On August 2 during testing of the main turbine, excessive vibration caused a turbine trip. Investigation showed the problem to be a deflection in a coupling due to a small pin being lodged between the coupling and its cover. The coupling was reassembled and the turbine successfully retested.
By August 3, the turbine generator was brought up to 185 MWe for approximately three hours and it ran smoothly with low vibration.
The electrical overspeed trip of the turbine was successful, but the mechanical overspeed trip did not function. Adjustments were made and the mechanical overspeed trip test was successfully completed.
The plant tripped on over temperature delta-temperature (OTAT) on August 9.
The bistables for one channel of OTAT had been tripped for routine surveillance. A spurious signal on a second OTAT channel completed the two-out-of-four logic. to cause the reactor trip. All safety systems functioned normally after the trip.
The reactor was restarted on August 14 and the plant was synchronized with the grid on August 15.
After plant startup on August 29, the Loop 4 OTAT began to experience additional spurious alarm signals.
Extensive testing and troubleshooting was conducted to locate the source of the spurious 1
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.t signals. The probable source of the spurious signal was isolated as a loose connection in a lead / lag module for the 1,oop 4 OTAT. On August 30, the lead /las module was replaced and the system sucessfully j
retested.
While performing a periodic Operating Test, a problem was discovered with the rod control system.
Shutdown Bank "C" would not drive in by I
rod control. The rod control system was placed in the manual mode of operation and troubleshooting comenced. The problem was isolated to a failed Rod Control System logic card which was then replaced. The system was retested and restored to normal operation.
In early September, the frequency of draining and cooling the i
pressurizer relief tank (PRT) had increased with time. The source of leakage into the PRT was from one leaking pressurizer safety valve and a leaking relief valve on the let-down line. Due to increasing i
leakage, the decision was made to shut the plant'down for repair on
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September 16.
t Anomalous (inconsistent) rod movement was observed on September 9 during a surveillance test of power range nuclear instrumentation.
l Troubleshooting revealed the problem to be dirty contacts in a nuclear instrumentation bypass switch. The contacts were cleaned, retested, l
and the system restored to service.
The switch was replaced during the September 16 outage.
On September 16, the press.urizer safety valve lif t setpoints were tested. This was done in response to new industry infomation that l
indicated the old method of testing without loop seals could introduce an excessive error. One valve did not lift at the required pressure.
The valve was reset and tested satisfactorily.
An inspection of the screens around the Containment recirculation sump l
on September 18 revealed some openings (gaps) that were slightly j
i outside the acceptance criteria. The gaps were evaluated and repairs j
conducted.
The OTAT setpoints were changed on October 1 to reflect a new understanding of required average temperature input for each Reactor Coolant System loop.
This information resulted from the investigation into recent problems with the OTAT portion of the protection system.
I Heatup comenced on October 1, but was halted when a pressuriser safety j
valve began experiencing leakage. Troubleshooting was conducted, the i
pressure lift setpoint was increased, and the valve successfully.
ratested. No additional leakage has occurred.
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The reactor was taken critical on October 3 with the plant reaching i
l 97 percent power on October 4.
The 97 percent level was maintained as a result of the change made to the Reactor Coolant System maximum average temperature (Tave) during O;
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the setroint changes previously referenced for OT&T. The plant remained at that level until an engineering analysis was completed supporting an increase to 100 percent.
On November 8, a spurious high alarm en the Containment radiation monitor caused an automatic closure of the hydrogen vent Containment isolation valvot.
The source of the spurious signal was not determined. The effected monitor and other associated monitors were satisfactorily retssted. The Containment radiation monitor was restored to service snd a noise suppression circuit was installed to reduce spurious signa.'s.
The "C" main steam isolation valve bypass failed to close during the performance of testing on November 13.
The valve was.then isolated in accordance with the Trojan Technical specifications.
The Number 1 seal water leak off flow indicator for reactor coolant pump Number 2 failed on November 30.
The failure was identified as a loose fuse clip.
The problem was fixed and verified not to exist on any other seal water leak off flow indicators.
The pressuriser power-operated relief valves (p0RV) were declared inoperable on December 6.
The channel calibration testing methods were not adequately testing all required electrical relays that actuated the PORVs. Appropriate actions were insnediately taken in accordance with the Trojan Technical Specifications. A Temporary plant Test was successfully completed on December 15 to test the required relays, and O
the p0RVs were restored to service.
On December 12 a review of the basis for chlorine toxic gas limits revealed that the installed monitors could not respond within the analyzed time requirement.
The chlorine analysis assumes a total 6-second delay time prior to isolation of dampers upon a monitor setpoint of 5 ppm being reached. The 6 seconds are based on 3 seconds for the monitor to actuate and 3 seconds for the damper to close upon generation of the isolation signal. Recent vendor information showed the detectors could not be relied upon to react within the required 3 seconds. The control room was placed on recirculation and an emergency change to the Trojan Technical specifications was obtained.
The toxic gas analysis was revised and new detectors are being procured.
A Containment entry was made on December 21 to investigate a suspected small steam leak. The steam leak was isolated to a "D" steam generator secondary side upper manway and on December 26, the plant reduced power to 30 percent to effect repairs. Repairs were completed and power was restored to 97 percent on December 29.
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The monthly and overall capacity factors for the year are as follows:-
Month Capacity Factor January 101.2 I
February 99.3 1
March 100.9 April 15.8 May
- 0.4
.l June
- 0.4 July
- 1.5 August
$4.5 September 48.2 October 46.7 November 97.7 December 91,4 Overall 57.6 t
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RADI0 ACTIVE EFFLUENT RELEASE REPORT Recuirement 4
Trojan Facility Operating License NPF-1 Appendix A Technical Specifica-tions 6.9.1.5.3 and 6.9.1.5.4, " Semiannual Radioactive Effluent Release Report", require:
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" Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.
j "The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid l
waste released from the unit as outlined in Regulatory Guide 1,21 (Rev. 1), ' Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Ef fluents f rom Light-Water-Cooled Nuclear power Plant',
with data summarized on a quarterly basis following the format of l
Appendix B thereof.
"The Radioactive Effluent Release Reports may include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in R*gulatory Guide 1.21 (Rev. 1), with data summarized on a quarterly basis following the l
format of Appendix B thereof.
If the summary of the meteorological data is not included in the radioactive effluent release reports, it O
will be available for review at PGE's Corporate Office.
"The Radioactive Effluent Release Reports shall include an assessment l
of the radiation doses from radioactive effluents to' individuals due to their activities inside the unrestricted area boundary (Figure 5.1-1) during the report period. All assumptions used in i
making these assessments (e.g., specific activity, exposure time and location) shall be included in these reports.
"The Radioactive Effluent Release Reports shall include a copy of all licensee event reports required by Specification 3.11.1.1 and 3.11.2.1.
"The Radioactive Effluent Release Reports shall include an assessment of radiation doses from the radioactive liquid and gaseous effluents-released from the unit during each calendar quarter as outlined in Regulatory Guide 1.21.
In addition, the unrestricted area boundary maximum noble gas samma air and beta air doses shall be evaluated.
The meteorological conditions concurrent with the releases of afflu-ents shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the Offsite Dose Calculation Manual (ODCM).
"The Radioactive Effluent Release Reports shall include any changes to the PROCESS CONTROL PROGRAM or to the Offsite Dose Calculation Manual (ODCM) made during the reporting period, as provided in Speci-O fications 6.13 and 6.14".
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4 Report Complete data for the year 1989 have been included, although the data for the first six months (January through, June) have been previcusly reported.
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1.A EFFLUENT AND WASTE DISPOSAL REPORT O
This section contains a sumary of the liquid and gaseous release limits; a list of the maximum pomissible concentrations of the isotopes released; a sumary of batch and abnormal release data; a sumary of total liquid and gaseous releases; listings of isotopes released classified by path-way, gaseous or liquid, and type, continuous or batch; and a sumary of solid radioactive waste shipments. This section represents all releases during the period January 1, 1989 through December 31, 1989.
Data for January 1, 1989 through June 30, 1989 have been previously reported.
The "ND" notation used in the following data tables indicates that no detectable activity was found when samples were analyzed using counting techniques which ensure compliance with the " Lower Limit of Detection" (LLD) values of Technical Specification Tables 4.11-1, " Radioactive Liquid Waste Sampling and Analysis program", and 4.11-2, " Radioactive Caseous Waste Sampling and Analysis program". The referenced "LLD" specifications are not used as limiting values for reporting activity; all measurable activity is reported.
For sama-omitting isotopes, all isotopes with measurable activity, together with those isotopes specified in Technical Specification Tables 4.11-1 and 4.11-2 are reported.
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In November 1989, it was discovered that the setpoint for the Noble Gas Activity Monitor of the Condenser Air Ejector Monitoring System (paM-6A) was not set as conservatively as calculated by the offsite Dose Calculation Manual (ODCM) to ensure that the limits of Technical l
O-Specification 3.11.2.1 were not exceeded.
Once discovered, the setpoint was imediately changed to the correct setting.
The cause of the incorrect setpoint was the installation of a los ratemeter for the instrument which was not as specified in either the Technical Manual or the Final Safety Analysis Report (FSAR), and failure to verify the as-built condition of the monitor when replaced.
The following terms are used:
K = Average total body doce factor due to gama emissions, y
Ly = Average skin dose factor due to beta emissions, l
i My = Average air dose factor due to beta emissions.
N = Average air dose factor due to gama emissions, i
y Ri = Average dose factor for nuclides other than noble gases at the controlling exposure locations, i
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TA8LE 1.A-1 SUPPLEMERTAL INFORMATION January 1. 1989 through June 30, 1989 REGULATORY LIMITS First Second Fission and Activation Gas Release Rate Linlig
_ Unit guarter Quarter 1.
Tech Spec 3.11.2.1(a), instantaneous QTv <
1 Ci/sec 1.50E-1 1.85E-1 2.0 Ky QTv <
1 Ci/sec 3.82E-1 4.48E-1 0.33 (L 4 1.1 N )
y y
2.
Tech Spec 3.11.2.2, Quarterly Average O
QTv <
1 CL/sec 5.05E-3 6.08E-3 50 Ny QTV <
1 C1/sec 3.77E-3 3.92E-3 i
25 My 3.
Tech Spec 3.11.2.4(1), Quarterly Average Requiring Use of the Gaseous Radwaste Treatment System QTv <
1 C1/see 2.53E-3 3.04E-3 100 Ny QTV <
1 Ci/sec 1.89E-3 1.96E-3 50 My O
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l TABLE 1. A-2 9i SUPPLEMENTAL INFORMATION January 1, 1989 through June 30, 1989 j
i REGULATORY LIMITS Gaseous Iodine 131. Tritium, and Particulates First Second-2 With > 8 Day T1/2 Limits
- Unit Duarter Quarter 1.
Tech Spec 3.11.2.1(b), Instantaneous QTv <
1 CL/sec 3.81E-2 7.58E-3
-i 67 R1 l
2.
Tech Spec 3.11.2.3, Quarterly Average QTv <
1 C1/sec 2.55E-4 5.08E-5 i
100 Ri s
3.
Tech Spec 3.11.2.4(2), Quarterly Average Requiring Use of the Ventilation Exhaust Treatment System QTv <
1 Ci/sec 1.28E-4 2.54E-5 200 Ri f
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TABLE 1.A-3 SUPPLEMENTAL INFORMATION i
January 1, 1989 through June 30, 1989 i
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REGULATORY LIMITS Liould Effluent Limits 1.
Tech Spec 3.11.1.1 Instantaneous discharge concentrations Instantaneous less than the maximum permissible concentrations listed in 10 CFR part l
- 20. Appendix B. Table II, Column 2, for radionuclides other than dissolved or entrained noble gases.- For i
dissolved or entrained noble gases.
the concentration is limited to 2 x 10-4 pCi/ml total activity.
2.
Tech Spec 3.11.1.2 Cross release limit of 2.5 Ci per Quarterly Average quarter excluding tritium and dissolved noble gases.
If this limit-
'l is exceeded, cumulative dose due to i
O liquid effluents will be limited.to 1.5 mrom to the whole body and to 2.5 mrom to any organ, using isotope specific methodology in the plant offsite dose calculation manual (0DCN).
3.
Tech Spec 3.11.1.3 The liquid radweste treatment system Quarterly Average Requiring shall be maintained and used when Use of the Liquid Radwaste activity discharged (excluding tritium Treatment System and dissolved noble gas) would exceed 1.25 Ci/Qtr.
4.
Tech Spec 3.11.1.4 The quantity of radioactive material Temporary Storage Tank contained in temporary radwaste storage Activity Limit tanks is limited to 1 10 Ci excluding tritium and dissolved noble gases.
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l TABLE 1.A-4 SUPPLEMENTAL INFORMATION I
January 1, 1989 through June 30, 1989 i
MAXINUM PERMISSIBLE CONCENTRATIONS Lieuld j
(10 CFR 20. Appendix B. Table 11. Col. 2)
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MPC MPC
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Isotope luci/cc)
Isotope (uC1/cc) q Fluorine 18 8 x 10-4 Iodine 131 3 x 10-7 Chromium 51 2 x 10-3 Iodine 132 8 x 10-6 Manganese 54 1 x 10-4 Tellurium 132 2 x 10-5 Iron 55 8 x 10-4 Iodine 133 1 x 10-6 Cobalt 57 4 x 10-4 Cesium 134 9 x 10-6 i
Cobalt 58 9 x 10-5 Cesium 137 2 x 10-5 Iron 59 5 x 10-5 Cesium 138 3 x 10-6 Cobalt 60 3 x 10-5 Barium 140 2 x 10-5 Rubidium 88 3 x 10-6 Lanthanum 140 2 x 10-5 Strontium 89 3 x 10-6 Cerium 141 9 x 10-5 Strontium 90 3 x 10-7 Cerium 144 1 x 10-5 Zirconium 95 6 x 10-5 Tungsten 187 6 x 10-5 Niobium 95 1 x 10-4 Alpha 3 x 10-8
_t Molybdenum 99 4 x 10-5 Unidentified 3 x 10-8
'l Technetium 99m 3 x 10-3 Tritium 3 x 10-3 r
Ruthenium 103 8 x 10-5 Krypton 85m 2 x 10-4 Ruthenium 106 1 x 10-5
. Krypton 87 2 x 10-4 Silver 110m 3 x 10-5 Krypton 88 2 x 10-4 Tin 113' 8 x 10-5 Ionon 131m 2 x 10 {
Antimony 124 2 x 10-5 Kenon 133 2 x 10-4 Antimony 125 1 x 10-4 Kenon 133m 2 x 10-4 Antimony 127 3 x 10-6 Kenon 135 2 x 10-4 l
Ionon 135m 2 x 10-4 Oaseous Gaseous MPCs are not used in calculating technical specifications at
- Trojan, l
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- l TABLE 1.A-5 SUPPLEMENTAL INFORMATION January 1, 1989 through June 30, 1989 I
AVERAGE ENERGY EffluentreleaselimitsarenotbaseduponE,hence,reportingEisnot required.
MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Gaseous Releases Fission and Activation Gases: Cansna spectrometric analysis of gaseous grab samples define radionuclide distribution at least monthly on monitored gaseous release points. Using the known-nuclide distributions and process radiation monitor readings, the actual quantities of gaseous releases are calculated.
Iodines and Particulates: Weekly composite filter and iodine cartridge samples are analyzed by gamma spectroscopy to determine the concentration of particulate and iodine isotopes. Weekly composite.
l samples are analped for alpha-omitting isotopes by counting with a gas flow proportional counter.- Quarterly composite filters are analyzed for Sr-89/90 using gas proportional beta counting and chemical separation techniques when necessary.
Tritium: Tritium is collected on dry silica sel in monthly composite samples and counted using liquid scintillation spectroscopy..
Liculd Releases Fission and Activation Products:. Gansna spectrometric analysis of each batch is performed. Weekly composite samples are maintained for continuous releases, and the composites are analyzed for specific nuclides as required. Monthly and quarterly composites are prepared for both batch and continuous releases for specified activity determinations.
Tritium: Monthly composite samples are distilled and deionized as necessary to remove contamination and counted by liquid scintillation techniques.
Dissolved and Entrained Gases: Gaseous isotopes are determined by gamma spectrometric analysis of each batch and'on a minimum frequency of once per month for continuous releases.
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l TABLE 1.A-6 SUPPLEMENTAL INFORMATION i
January 1, 1989 through June 30, 1989 1
i BATCH RELEASES l
Enli Lievid Gateous l
Number of Batch Releases 27 61 j
Total time period for Batch Releases Hours 144.0 2047.6 i
Maximum time period for Batch Releases Hours 12.5 435.4 Aversta time period for Batch Releases Hours 5.3 33.6 Minimum time period for Batch Releases Hours 0.6 0.3 Average dilution flow during Batch Releases GPM 32512 NA*
t ABNORMAL RELEASES l
Number of Abnormal Releases 0
3 Total Activity Released Ci NA*
4.91 9!
- NA = Not Applicable 9
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)
t TABLE 1.A-7 Sheet 1 of 2 j
GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES January 1, 1989 through June 30, 1989 l
First Second Rettmated EISSION AND ACTIVATION CASES Unit Quarter Quarter Error (%)
Total Activity Released C1 1.43E+1 2.28E+2 13.5El Average Release Rate for Quarter pCi/sec 1.84E+1 2.90E+1 Percent of Limit:
1 Tech. Spec. 3.11.2.1 (a) -
3.44E-2 1.49E-1 Instantaneous Tech Spec. 3.11.2.2 -
4.89E-1 7.35E-1 Quarterly Average Tech. Spec. 3.11.2.4.(1) -
9.79E-1 1.47E-0 t
Quarterly Average Requiring I
g processing l
IODINE 131 Total Iodine 131 Released Ci 9.13E-5 3.83E-3 13.581 Average Release Rate for Quarter pCi/sec 1.17E-5 4.87E-4 pARTICULATES Total with Half-lives > 8 days Ci 4.77E-7 6.01E-5 13.551-l l
Average Release Rate for Quarter pCi/sec 6.13E-8 7.65E-6 Total Gross Alpha Released Ci 6.185-8 2.31E-7 1
TRITIUM Total Released Ci 6.38E0 2.58E+1 13.0E1 Average Release Rate for Quarter pC1/sec 8.20E-1 3.28E0 l'
4 10 i
?
{
TABLE 1.A-7 sheet 2 of 2 l
i IODINE 131. PARTICULATES WITH First Second Estimated-l
> 8 DAY T1/2 AND TRITIUM Unit Quarter Quarter Error (t) i Total Released Ci 6.38E0 2.58E+1 13.5El Average Release Rate for Quarter yCi/sec 8.20E-1 3.28E0 l
Percent of Limitt Tech. Spec. 3.11.2.1 (b) 3.99E-3 1.66E-1 Instantaneous Tech. Spec. 3.11.2.3 3.22E-1 6.49E0 Quarterly Average Tech. Spec. 3.11.2.4(2) 6.44E-1 1.30E+1 Quarterly Average Requiring Processing O'
i O
11 w
y
TABLE 1.A-8 Sheet 1 of 2 GASEOUS EFFLUENTS GROUND LEVEL RELEASES January 1, 1989 through June 30, 1989 NUCLIDES RELEASED Continuous Mode Batch Mode l!D.11 let Quarter inhph 1st Quarts 2nd. Quarter FISSION GASES Krypton 85m Ci 5.46E-2 4.03E-3 1.62E-2 3.72E-3 Krypton 85 Ci WD ND 1.9250 3.90E0 Krypton 87 Ci 9.23E-2 7.23E-3 9.28E-3 1.21E-3 Krypton 88 Ci 1.21E-1 9.185-3 1.42E-2 4.87E-3 Xenon 131m Ci WD ND 1.3980 1.64E0 Xenon 133m C1 4.97E-1 1.57E 3 3.09E-1 8.938-1 Xenon 133 Ci 9.72E+1 8.56E41 3.86E+1 1.36E+2 Xenon 135m Ci 5.23E-1 3.39E-2 1.75E-2 ND Xenon 135 C1 1.4250 3.98E-2 3.385-1 3.908-1 Xenon 137 C1 1.77E-1 9.78E-3 ND ND Xenon 138 C1 2.55E-1 1.96E-2 ND ND ArEon 41 Ci 9.67E-3 4.20E-4 1.59E-1 2.28E-2 TOTAL FOR QUARTER C1 1.00E+2 8.57E+1 4.28E+1 1.43E+2 O
12 i
I e
IARLE 1.A-8 Sheet 2 of 2 4
9; i
Continuous Mode hatch Mode Unit let Quarter 2nd Quarter let Duarter 2nd Duarter i
5 I0 DINES I
Iodine 131 C1 8.99E-5
- 1. 9 2 E 1.41E-6 1.90E-3 Iodine 132 Ci 1.10E-7 ND ND ND Iodine 133 C1 3.59E-5 5.79E-4 3.37E-7 3.29E-5
+
Iodine 135 C1 2.79E-7 ND ND ND r
TOTAL FOR QUARTER C1 1.26E-4 2.50E-3 1.75E-6 1.93E-3 PARTICULATES > 8 DAY T-1/2 AND TECHNICAL EPECIFICATION REQUIRED ISOTOPES Nanganese $4 Ci ND ND ND ND Cobalt $8 Ci ND ND ND ND Iron 59 Ci ND ND ND ND Cobalt 60 Ci ND ND ND ND Zinc 65 Ci ND ND ND ND Strontium 89 C1 4.32E-7 1.26E-7 ND 2.953-5 Strontium 90 Ci 3.128-8 1.11E-7 ND 1.675-5 Wlobium 95 C1 ND ND ND 1.355-5 l
Molybdenum 99 Ci ND ND ND ND Cesium 134 Ci ND ND ND ND Cesium 137 C1 1.36E-8 2.10E-7 ND ND Barium 140 Ci ND ND ND ND i
Cerium 144 Ci ND ND ND ED Neodymium 147 Ci ND ND ND ND TOTAL FOR QUARTER C1 4.77E-7 4.475-7 0.00E0 5.97E-5 O,
t 13
1&]LLE 1. A-9 O-GASEOUS EFFWENTS ELEVATED RELEASES January 1, 1989 through June 30, 1989 No Elevated Release Points O
O 14
~. -
l i
TABLE 1.A-10 1
9 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES January 1, 1989 through June 30, 1989 i
FISSION AND ACTIVATION PRODUCTS First Second Estimated Unit Duarter Quarter Error %
Total Activity Released (excluding Ci 3.08E-2 4.6EE-2 13.5E+1 gases, tritium, and alpha)
Average Diluted Concentration pCi/ml 1.97E-9 3.39E-9 Percent of Limit Tech Spec 3.11.1.1 - Instantaneous 2.375-1 1.6950 Tech Spec 3.11.1.2 - Quarterly Limit 1.23E0 1.8750 i
Tech spec 3.11.1.3_- Quarterly Limit 2.47E0 3.7430 Requiring Processing j
TRITIUM Total Released Ci 5.29E+1 5.39E+1 13.0E+1 Average Diluted Concentration pCi/ml 3.39E-6 3.91E-6 Fraction of NPC 1.13E-1 1.30E-1 DISSOLVED AND ENTRAINED CASES l
Total Activity Released Ci 4.38E-3 2.90E-4 13.5E+1 Average Diluted Concentration pCi/mi 2.80E-10 2.105-11 I
Fraction of NPC 5-1.40E-4 1.055-5 9ROSS ALPHA RADI0 ACTIVITY Total Activity Released C1 1.38E-5 1.91E-5 13.0B+1 UNDILUTED VOLUME OF WAST @ MRED, Liters 1.17E+7 6.03E+6 15.0E0 i
VOLUME OF DILUTION WATER Liters 1.56E+10 1.38E+10' 11.5E+1 i
15 1
TABLE 1.A-13 Sheet 1 of 2 LIQUID EFFLUENTS January 1, 1989 through June 30, 1989 NUCLIDES RELEASED Continuous Mode Batch Mode 2Djd.
let Ouarter 2nd Duarter-1st Quarter 2nd Quarter Chromium 51 Ci ND ND 5.25E-4 5.53E-3 Manganese 54 C1 ND ND 2.415-4
.3.488-4 Iron 55 Ci 5.99E-3 9.13E-4 1.15E-2 1.225-2 Cobalt 57 Ci WD ND 4.53E-6
- 8. 70E-6 Cobalt 58 Ci WD ND 1.26E-3 9.20E-3 Iron 59 Ci ND ND 2.92E-5 1.285-4 Cobalt 60 Ci ND ND 5.25E-3 6.055-3 Zinc 65 Ci ND ND ND ND Strontium 89 C1 1.60E-4 2.03E-5 8.61E-6 ND Strontium 90 Ci 1.43E-6 3.935-5 3.10E-6 2.275-5 Zirconium 95 Ci ND ND 1.67E-4 1.10F-3 Niobium 95 Ci ND ND 5.33E-4 1.758-3 Molybdenum 99 Ci ND ND 4.725-6 7.765-6 Technitium 99m Ci ND ND 4.80E-6 7.90E-6 Ruthenium 103 Cl ND ND 2.178-5 8.85E-4 Ruthenium 106 Cl ND ND 3.26E-3 3.365-3 Silver 110m Ci ND ND 6.175-4 1.61843 Tin 113 Ci ND ND 3.02E-5 8.495-5 Antimony 125 Ci ND ND 3.135-4 4.188-4 Iodine 131 Ci 7.83E-6 9.56E-5 3.01E-4 2.228-4 Iodine 133 Ci ND ND 6.788-6 ND Cesium 134 C1 ND 3.33E-5 2.74E-5 3.80E-4 P
Cesium 137 Ci ND 7.925-5 7.398-5
16 I
TABLE 1.A-11 Sheet 2 of 2-NUCLTDES RELEASED.
-j Continuous Mode Batch Mode jo gg[L 1st Quarter 2nd Quarter.lst Quarter 2nd Duarter Cerium 141 Ci ND ND ND
- 2. 08E-4 '
Cerium 144 Ci ND ND
'4.565-4 1.355-3 TunEsten 187 Ci ND ND ND-6.315-5 Unidentified Ci ND ND ND-ND TOTAL FOR QUARTER Ci 6.16E-3
'1.18E-3 2.46E-2 4.56E-2 DISSOLVED AND ENTRAINED GASES
{
Continuous Mode-Batch Mode l
{~
gp_Q 1st Ouarter 2nd Quarter let Quarter 2nd Quarter Krypton 87' Ci ND ND ND ND Krypton 88 Ci ND ND ND ND Kenon 131m-Ci ND ND ND ND Ionon 133m Ci ND ND ND ND Xenon 133 Cl ND-ND 6.63E-4 2.90E-4 Kenon 135 Ci ND ND 3.72E-3 ND 1
-l Renon 138 Ci ND ND
-ND ND TOTAL FOR QUARTER Cl ND ND 4.38E-3 2'90E-4 l
1 17
+
~!
TABLE 1.A Sheet. 1 of 1 O
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January 1, 1989 through June 30. 1989 i
SOLID WASTE' SHIPPED OFFSITE FOR Activity.
Volume-Estimate BURIAL OR DISPOSAL (Not Irradiated During.
During Total Fuel) - Type of Waste Six Months Six Months ~
Brror %
j 1.
Spent Resin, Filters, Sludges, 437.9 Ci 70.63 m3 25%
Evaporator Bottoms, etc.
2.
Dry Compressible Waste, Contam-3.2 C1 116.E8 m3 25%
insted Equipment, etc.
l t
3.
Irradiated Components, Control'
.0.000 0.00
-i Rods, etc.
4.
Other 0.000 0.00-ESTIMATE 0? MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE
()
Nuclide 1.
See attached sheet.
2.
See attached sheet.
3.
4.
SOLID WASTE DISPOSITION i
Number of Shioments Mode of Transcortation Destination 9
Exclusive Truck U.S. Ecology,-Inc.=
1 P. O. Box 638
'Richland WA ~99352 5
Exclusive Truck Allied Nuclear, Inc.
2025.Battelle Blvd.
Richland WA 99352 V
4 18 l
...u
- [
TABLE 1.A-12 Sheet'2 of 2 JRRADIATED FUEL SHIPMENTS DISPOSITION Humber of Shipments Mode of Transportation Destination 0
N/A*
N/A*
BSTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE 1.
Nuclide El Nuclide El '
H-3 3.236 Ru-106 1.121 C 0.370 As-110m 0.013 Cr-51 0.021 Sn-113 0.000 Mn-54 4.133 Sb-125 1.761 Fe-55 43.884 I-131 0.001 Co-57 1.200 Cs-134 17.972; Co-58 76.038 Cs-137 40.798 j
Fe-59 0.002 Ba-140 0.000 1
Co-60 123.809 Co-141 0.000-i Ni-63 111.790' Co-144 0.387 Sr-89 0.001 U-235
-0.000
=I Sr-90 10.081 Pu-238 0.016 Nb-95 0.012 Pu-239 0.018 4
Zr-95 0.013 Pu-241 1.206 Ru-103 0.003 Cm-242 0.000
'37.886 Total 4
2.
Nuclide El Nuclide G1 j
H-3 1.302 Ru-106 0.058 C-14 0.426 Ag-110m.
0.004 Cr-51
'0.043 Sn-113 0.000 Mn-54 0.088 Sb-125 0.002 Fe-55 0.468 I-131 0.000 Co-57 0.000 Cs-134 0.012 Co-58 0.134
.Co-137 0.018 Fe-59 0.000 Ba-140 0.000 Co-60 0.183 Co-141 0.000 N1-63 0.082 Co-144 0.031 Sr-89 0.237 U-235 0.000
'g Sr-90 0.000 Pu-238 0.000 Nb-95 0.037 Pu-239-0.000 Zr-95 0.029 Pu-241 0.044-Ru-103 0.014 Cm-242 0.000 Total
.3.212
- N/A = Not Applicable 19
TABLE 1.A-13 Sheet 1 of 2 SUPPLEMENTAL IN ORMATION July 1, 1989 through December 31, 1989 l
l REGULATORY LIMITS Third Fourth Fission and Activation Gas Release Rate Limits Unit Quarter Quarter 1.
Tech Spec 3.11.2.1(a), Instantaneous QTv <
1 Ci/sec 1.74E-1 1.53E-1 2.0 Ky QTv <
1 Ci/sec 4.27E-1.
4.07E-1 0.33 (Ly + 1.1 ' N )
y I
2.
Tech Spec 3.13.2.2, Quarterly Average QTv <
1 Ci/sec 5.78E-3 5.16E-3 J) 50 Ny QTv <
1 Ci/sec 3.85E-3 3.8BE-3 4
25 My 3.
Tech Spec 3.11.2.4(1), Quarterly Average 1
Requiring Use of the Gaseous Radweste-Treatment System l
l QTv <
1 Ci/sec 2.89E-3 2.58E-3 100 Ny j
i QTV <
1 C1/sec 1.92E-3 ?
1.94E-3l 1
.1 50 My 1
20
TABLE 1.A-13 sheet 2 of 2 O
REGULATORY LIMITS Gaseous lodine 131. Tritium, and Particult.tes Third Fourth With > 8 Day T1/2 Limits Unit Quarter Quarter
- 1. ' Tech Spec 3.11.2.1(b), Instantaneous
_QTv <
1 Ci/sec 4.20E 5.55E-2
.67 Ri 2.
Tech Spec 3.11.2.3, Qusrterly Average QTv <
1 Ci/sec 2.82E-4 3.72E-4 100 Ri 3.
Tech Spec 3.11.2.4(2), Qusrterly Average Requiring Use of the Ventilation Exhaust Treatment System QTv <
1 Ci/sec 1.41E-4 1.86E-4 200 Ri c
9 21
i 1
TABLE 1.A-14
)
SUPPLEMENTAL.INFORMATION July 1, 1989 through December 31, 1989
'I REGULATORY LIMITS-I Liould Effluent Limits 1.
Tech Spec 3.11.1.1 Instantaneous discharge concentrations Instantaneous less than the _ maximum permissible '
concentrations listed-in 10 CFR Part 20,.
j Appendix B. Table II, Coluan 2, for
{
radionuclides other than dissolved or i
entrained noble gases. For dissolved or entrained noble' gases, the concentration:
is limited to 2-x 10-4 pCi/mi total activity.
2.
Tech Spec 3.11.1.2 Gross' release limit of 2.5 Ci per Quarterly Average quarter excluding tritium and dissolved.
noble gases.
If this limit is exceeded.
cumulative dose due to liquid effluents will;be limitedito 1.5 mrom to the whole-body and to 2.5 mram to any organ,~using i,
l
\\-
isotope specific methodology in the plant offsite dose calculation' manual (ODCM).
-I 3.
Tech Spec 3.11.1.3 The liquidcredwaste treatment. system-Quarterly Average Requiring shall be maintained and used when_
4 Use of the Liquid Radweste activity discharged (excluding tritium-i Treatment System and dissolved noble gas) would exceed.
(
1.25 Ci/Qtr.
1 I
4.
Tech Spec 3.11.1.4 The quantity _of radioactive material l
Temporary Storage Tank contained in temporary radweste storage y
Activity Limit tanks is limited to s 10 C1.exc1rding tritium and dissolved noble gases.
d 4
i O
d 1
22 i
TABLE 1.A-15 SUPPLEMENTAL INFORMATION July 1, 1989 through December 31, 1989 MAXIMUM PERMISSIBLE CONCENTRATIONS Liould MPC~
MPC Isotope (uCi/ce)
Isotope (uCi/cc)
Fluorine 18 8 x 10-4 Iodine 131 3 x 10-7 Chromium 51 2 x-10-3' Iodine 132 8 x 10-6 Manganese 54 1 x 10-4 Tellurium 132 2 x 10-5J Iron 55 8 x 10-4 Iodine 133 1 x 10-6 Cobalt 57 4'x 10-4 Cesium 134 9 x 10-6:
Cobalt 58 9 x 10-5 Cesium 137 2 x 10-5' Iron 59-5 x 10-5 Cesium ~138 3 x-10-6 Cobalt 60 3 x 10-5 BariumLi40 2 x 10-5 Rubidium 88 3 x 10-6 Lanthanum 140 2 x 10 Strontium 89 3 x 10-6 Cerium 141 9 x 10-5 Strontium 90 3 x 10-7 Cerium 144 1 x 10-5 Zirconium 95 6 x 10-5.
rungsten 187 6 x 10-5 Wiobium 95 1 x 10-4 Alpha-3 x 10-8 Molybdenum 99 4 x 10-5 Unidentified
. 3 x 10-8 Technetium 99m 3 x 10-3 Tritium 3 x 10-3 Ruthenium 103 8 x 10-5~
-Krypton 85m 2 x 10-4 Ruthenium 106 1 x 10-5 Krypton 87 2 x-10-4' Silver 110m 3 x 10-5 Krypton 88.
2 x-10-4 Tin 113 8 x 10 Xenon-131m 2 x-10-4 Antimony 124 2 x 10 Xenon 133 2 x 10-4 Antimony 125-1 x 10-4 Xenon 133m 2 x 10-4 Antimony 127 3 x 10-6 Xenon 135 2 x 10-4 Xenon 135m 2 x 10-4 Gaseous Caseous MPCs are not used in calculating technical specifications at Trojan.
e 23
a i
TABLE 1.A-16 O
SUPPLEMENTAL INFORMATION July 1, 1989 through December 31, 1989 f
e I
AVERAGE ENERGY J
Effluent release limits are not based upon E, hence, reporting E is not required.
i MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY
'l s
Gaseous Releases
- l s
Fission and Activation Gases: Germa spectrometric analysis of gaseous d
grab samples define radionuclide distribution at least monthly on monitored gaseous release points.
Using the known nuclide distributions-and process radiation monitor readings, the actual. quantities-~of gaseous releases are calculated, i
Iodines and Particulates: Weekly composite filter and iodine cartridge samples are analyzed by gamma spectroscopy to determine the concentration of particulate and iodine isotopes. Weekly composite l
samples are analyzed for alpha emitting isotopes by counting with a gas flow proportional counter. Quarterly composite filters are analyzed for l
Sr-89/90 using gas proportional beta counting:and chemical separation techniques when'necessary.
I i
Tritium: Tritium is collected on dry silica gel in monthly _ composite i
samples and counted using liquid scintillation spectroscopy.-
Liould Releases
~e Fission and Activation Products:
Gamma spectrometric analysis of each batch is performed. Weekly compcsite samples are maintained for continuous releases, and the composites.are analyzed for specific nuclides as required. Monthly and quarterly composites are prepared for both batch and continuous releases for specified activity determinations.
Tritium: Monthly composite samples are distilled and deionized as-necessary to remove contamination and counted by liquid. scintillation techniques.
Dissolved and Entrained' Gases:
Gaseous isotopes are determined by gamma spectrometric analysis of each batch and on a minimum frequency of once l
per month for continuous releases.
lh
\\
(_ /
I 24 L
L
TABLE 1.A-17
.l SUPPLEMENTAL INFORMATION July 1, 1989 through December 31,'1989 BATCH RELEASES Unit Lieuld Gaseous Number of Batch Releases 49' 68 Total time period for Batch Releases Hours-273.3 1318.1_
j Maximum time period for Batch Releases 1:ours 44.3 202.8
{
Average time period for Batch Releases' Hours 5.6
_19.4 l
Minimum time period for Betch-Releases Hours 0.1 0.4 Average dilution flow during Batch Releases-GPM 35910 NA a
ABNORMAL RLEASES i
Number of Abnormal Releases 1
1 Total Activity Released.
Ci 7'68E-7.
3.05E-3 0;a l
l i
O 25-e
l l
i 1
\\
l
+
TABLE 1.A-18 Sheet 1 of 2
.j GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES-I July 1, 1989 through December 31, 1989-Third Fourth Estimated-FISSION AND ACTIVATION GASES Unit Quarter Quarter Error Total Activity Reisased Ci 1.79E+2 4.24E+1 13'. 5 El I
Average Release Rate for Quarter pCi/sec 2.26E+1 5.33E+0-Percent of Limit:
Tech. Spec. 3.11.2.1 (a) -
1.02E-1 8.47E-3 Instantaneous.
Tech Spec. 3.11.2.2 -
5.84E-1 1.37E-1 Quarterly Average-1 Tech. Spec. 3.11.2.4.(1) -
1.17E-0 2.74E-1 Quarterly Average Requiring-Processing IODINE 131 Total Iodine 131 Released Ci 3.14E-4 3.18E-5 13.5E1 -
Average Release Rate for Quarter pCi/sec 3 '. 95 E-5 4.00E-6 PARTICULATES a
Total with Ralf-lives > 8 days Ci 1.2SE-7 3.22E-8 3.5El Average Release Rate for Quarter' pCi/see 1.58E 4.05E-9
-Total Gross Alpha. Released C1 1.10E-7 6.88E-8 TRITIUM 1
Total Released Ci 2.87E+1 1.22E+1-
+3.0E1 Average Release Rate for Quarter pCi/sec 3.61E0 1.53E0 o
26
s TABLE 1.A-18 Sheet 2 of 2' O
IODINE 131. PARTICULATES WITH Third.
Fourth Estimated
> B DAY T1/2 AND TRITIUM Unit Ouarter Quarter Error
-Total Released Ci 2.87E+1-1.22E+1 13.5El Average Release Rate for Quarter pCi/sec 3.61EO 1.53E0 Percent of Limit:
i Tech. Spec. 3.11.2.1 (b) 2.73E-2 3.62E-3 Instantaneous Tech. Spec. 3.11.2.3 1.30E0
'4.14E-1 Quarterly Average l
Tech. Spec.~3.11.2.4(2) 2.60E0 8.275-1 Quarterly Average Requiring Processing Q;
O' 27
~..-... _.
e i
i TABLE 1.A-19 Sheet l'of 2 L
CASEOUS EFFLUENTS CROUND LEVEL RELEASES July 1, 1989 through December 31,-1989 NUCLIDES RELEASED
.f Unit.
' Continuous Node
' Batch Node
-)
3rd Quarter 4th Quarter 3rd Duarter 4th Quarter t
f FISSION GASES Krypton 85m Ci 9.77E-05 1.07E-03 2.14E-02 7.42E-031 Krypton 85 Ci ND
. ND -
3.40E+00-2.75E '
q Krypton 87 Ci 1.55E-04
-2.71E-03 ND 1.29E-03 Krypton.88 Ci 4.35E-04 9.55E-04 ND
'1.12E-02
.i Xenon 131m Ci ND
.ND.
5.30E-01 5.60E-02 Xenon 133m Ci ND ND 1.74E+00 3.01E-02 Xenon 133 Ci' 3.92E+01 3.70E+01-
-1.33E+02 4.62E+00 Zenon'135m Ci 1.19E-03 9.96E-03 ND
-3.62E-04
' O' Ienon 135 Ci 2.93E-03
.9.99E-03 1.46E+00 1.17E-01L t
Xenon 137 Ci ND ND ND
= ND Xenon 138 Ci ND 4.59E-03 ND 2 '. '25 E-02 Argon 41 Ci ND ND 2.36E-01 2.29E TOTAL FOR QUARTER Ci 3.92E+01 3.70E+01:
1.40E+02 5.37E+00 t
t
(
d f
I 4
6 28 h
TABLE 1.A-19 Sheet 2.of 2 O
I NUCLIDES' RELEASED Continuous Node Batch Mode-Unit 3rd Duarter 4th Quarter 3rd Duarter 4th Quarter i
10 DINES Iodine 131 C1' 2.12E-04 3.16E-05 1.02E-04 2.45E-07 Iodine 132 Ci ND ND ND ND Iodine 133 Ci ND 1.18E-08
- ND
~ ND Iodine 135 Ci ND ND ND ND l
TOTAL FOR QUARTER C1 2.12E-04 3.16E-05 1.02E-04 2.45E I i
l PARTICULATES > 8 DAY T-1/2 AND TECHNICAL SPECIFICATION REOUIRED ISOTOPES 1
Nanganese 54 Ci ND ND-ND ND q
Cobalt 58 Ci 3.86E-09 ND ND:
ND-Iron 59 Ci ND WD ND-ND
.i Cobalt 60 Cl ND ND ND ND Zinc 65 Ci ND ND ND ND Strontium 89 Ci 6.08E-08
'2.00E-08
'ND ND-
-j Strontium 90 Ci 6.08E-0E
'1.22E-08 ND ND l
Niobium 95 Ci WD ND WDE ND j
Nolybdenum 99 Ci ND ND=
ND ND-Il Cesium 134 Ci
-ND ND NDL ND Cesium 137 Ci ND ND.
-ND-ND Barium 140 Ci WD ND ND ND Cerium 141 Ci MD ND ND ND-Cerium 144 Ci ND ND ND ND Neodymium 147 Ci ND ND ND WD TOTAL FOR QUARTER Ci 1.25E-07 3.22E-08 0.00E+00 0.00E+00 s
a i
l i
29
TABLE 1.A-20 CASEOUS EFFLUENTS ELEVATED RELEASES
-July l'. 1989 through December 31, 1989
~
No Elevated Release Points-O O
30
TABLE 1.A-21 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES July 1, 1989 through December'31, 1989 FISSION AND ACTIVATION PRODUCTS Third--
Fourth'-
' Estimated Unit Ouarter-
= Quarter Error %
Total Activity Released (excluding Ci 6.84E-2 1.56E-2 13.5E+1:
gases, tritium, and alpha)
Average Diluted Concentration WCi/ml 4.78E-9
- 8. 5 7 E-10,
Percent of Limit Tech Spec 3.11.1.1 - Instantaneous 1.17E+0
~1.27E-1.
Tech Spec 3.11.1.2 - Quarterly Limit
-2.73E+0 6.23E-1 Tech spec 3.11.1.3 - Quarterly Limit 5.47E+0 1.25E+0 Requiring Processing TRITIUM Total Released Ci' 1.93E+2 1.8SE+1
~3.0E+1
+
Average Diluted Concentration WC1/ml 1.' 35 E-5 1.02E-6 Fraction of MPC 4.50E-1 3.40E-2 DISSOLVED AND ENTRAINED CASES Total Activity Released C1 2.68E 7.24E-4 13.5E+1-Average Diluted Concentration pCi/mi
.1.87E-8 3.98E-11 Fraction of MPC 9.37E-3 1.99E-5 GROSS ALPHA RADIOACTIVITY Total Activity Released Ci 4.63E 6.34E-6 13.0E+1 UNDILUTED VOLUME OF WASTE RELEASED Liters 2.09E+7 1.70E+7 15.0E0 VOLUME OF DILUTION WATER Liters 1.43E+10 1.82E+10 1.5E+1 O
31
TABLE 1.A-22 Sheet 1 of 2 LIQUID EFFLUENTS July 1, 1989 through December 31, 1989 NUCLIDES RELEASED s
- t Continuous Node Batch Mode
- [
Unit 3rd Ouarter 4th Ouarter 3rd Duarter 4th Ouarter, Chromium 51 Ci~
ND ND 3.72E-03 1.07E-04 Nanganese 54 Ci ND.
ND
-6.50E-04 1.64E-04 Iron 55 Ci 2.40E-03 ND 1~.20E-02
-6.22E-03 Cobalt 57 Ci ND ND 7.13E-05
'2.07E-05 Cobalt 58 Ci-ND.
ND-1.68E-02 2.22E-03 Iron 59 Ci ND ND-6.80E ND Cobalt 60 Ci ND WD 1.08E-02 2~.85E-03 Zine 65 Ci ND ND ND WD
'f Strontium 89-C1 1.92E-03 2.62E-04
-5.49E-04 2.17E-05 Strontium 90 Ci 1.30E-04 1.002-04 1.33E-05 1.76E-06
~ Zirconium 95 Ci ND ND 1.58E-03 1.97E-04 Niobium 95 Ci ND ND 3.17E-03 4.90E-04 i
Nolybdenum 99 Ci ND ND ND ND Technitium 99m Ci-ND ND ND.
ND i
O.
Ruthenium 103 Ci ND ND 9.74E-04 4.752 j Ruthenium 106 Ci ND WD 6.66E-03 1.37E-03 i
Silver 110m Cl ND ND 1.99E-03' 4.09E-04 Tin 113 Ci ND' ND 1.42E-04 1.01E-05 Antimony 124 Ci ND ND 2.71E-05 ND Antimony 125 Ci ND ND 9.69E-04 3.11E,
Iodine 131 Ci-ND ND 3.03E-05
'5.73E-05 1
lodine 133 Cl ND ND 1.56E-05 ND Cesium 134 Ci ND ND 4.90E-04 1.18E Cesium 137 Ci ND ND 7.56E-04 5.61E-05 Lanthanum 140 Cl ND ND 9.23E-05
'2.87E-05 Cerium 141 Ci ND ND 1.16E-04 WD
. Cerium 144 Ci ND ND 2.08E-03 5.74E-04 Tungsten 187 Ci ND WD 1.06E-04 ND Unidentified Ci ND ND ND 2.46E-05 i
-1, TOTAL FOR QUARTER Ci 4.45E-03 3.62E-04 6.38E-02 1.52E-02 i
1 32 q
l
l TABLE 1.A-22 Sheet 2 of.2 NUCLIDES RELEASE _D DISSOLVED AND ENTRAINED GASES I
Continuous Mode Batch Mode Unit 3rd Quarter 4th Quarter 3rd Duarter-4th Ouarter Krypton 85 Ci ND ND 1.07E ND Krypton 88.
Ci ND ND ND-ND' Xenon 131m Ci ND ND 1.39E-03
.2.19E Xenon 133m-Ci ND ND 3.72E-03 ND t
Xenon 133 Ci ND ND
.2.61E-01 6.98E-04 l
Xenon 135 Ci WD ND 1.23E-03
- 4. 05 E-0(.
Xenon 138 Ci ND-ND.
ND ND
't TOTAL FOR QUARTER Ci.
ND ND 2.68E-01 7.24E-04 hN b -
I:
i 1
t 1.
L i
n i
33
3 TABLE 1.A-23 Sheet 1 of 2
)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS l
July 1, 1989 through December. 31, 1989 l
l' i
SOLID WASTE SHIPPED OFFSITE FOR Activity Volume Estimmte BURIAL OR DISPOSAL (Not Irradiated During During Total l
Fuel) - Type of Weste
. Six Months.
Six~ Months Error %
l' 1.
Spent Resin Filter Sludges, 3.175 Ci 11.33 m3 25%
Evaporator Bottoms, etc.
i 2.
Dry Compressible Waste, 2.663 Ci 60.41 m3 25%
Contaminated Equipment, etc.
3.
Irradiated Components, Control 0.000-0.00 j
Rods, etc.
t 4.
Other 0.000 0.00 l
l-ESTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE Nuclide 1.
See attached sheet.
2.
See attached sheet.
i i
3.
4.
i SOLID WASTE DISPOSITION i
Number of Shipments Mode of Transportation Destination 2
Exclusive Truck U.S. Ecology, Inc.
PO Box 638-Richland WA 99352 5
2 Exclusive Truck Allied Nuclear, Inc.
2025 Battelle Blvd.
Richland WA 99352 4
i u
34
'l
-]
TABLE 1.A-23 Sheet 2 of 2 0\\
l IRRADIATED FUEL SHIPMENTS DISPOSITION l
Number of Shipments Mode of Transportation Destination 0
N/A*
N/A*-
i ESTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE 1.
Nuclide gi Nuclide gi-H-3 1.637 Ru-103 0.001
-C-14 0.014 Ru-106 0.051' Cr-51 0.003-As-110m 0.003 Mn-54
-0.018 Sb-125 0.013 Fe-55 0.592-Cs-134 0.079
Co-58 0.191 Co-144 0.026 Co-60 0.294 Pu-238 0.001 I
.0.001 Sr-89 0.157 Pu-240 0.001 l
Sr-90 0.002 Pu-241 0.072 l
Nb-95 0.008 cm-242 0.001 f
l Zr-95 0.015 l
Total' 3.175-2.
Nuclide ci Nuclide Ci H-3 0.439 Ru-106 0.076 C-14 0.145 As-110m 0.000 Cr-51 0.083 Sn-113 0.000 Mn-54 0.026 Sb-125 0.007 Fe-55 0.753 Cs-134 0.000 Co-58 0.270 Cs-137 0.011 Co-60 0.269
'Co-144 0.053 Ni-63 0.124 Pu-238 0.001 Sr-89 0.153 Pu-239 0.001 Sr-90 0.000.
.Pu-240 0.001.
Nb-95 0.099 Pu-241 0.074 Zr-95 0.065 cm-242 0.000 i
Ru-103 0.012 Total 2.663
- N/A = Not Applicable el 35
1.B 0FFSITE RADIATION DOSES-Offsite radiation doses from gaseous and liquid effluents for 1989 are presented in this section.. Included are quarterly doses to individuals at locations of maximum actual exposure and quarterly doses to the 50-mile
~ population.
Doses are presented separately for batch and continuous releases and for noble gas, gaseous iodine, and particulate and liquid effluents.
Exposure locations _are based on the land-use survey presented in the Final Safety Analysis Report and the 1988 annual survey of agricultural production.
Models and assumptions used in performing the dose analyses for 1989 are presented in Sections 11.2, "L4. quid Waste Management < Systems", and 11.3,
" Gaseous Waste Management Systems", of the Trojan Final Safety Analysis Report.
O O
36
l L
L Sheet 1 of 2, l( )
' TABLE 1.5-1 PARAMETERS USED IN CALCULATINC' DOSES FROM CASEOUS KFFLURNTS (First Half 1989)
Parameter-Value Accumulation and Decay Times (days)
. 1.0 Harvest of leafy vegetables'to consumption by man f
Harvest of pasture grass'to consumption by animals 0.0 Harvest of stored feed to consumption by-animals 90.0 4
Harvest of produce to consumption by man 60.0 Animal butchering to consumption 20.0 Food ingestion by animal to milking 2.0 Accumulation time on ground 7,300.0 Human Consumption Rates (kg/yr)
Leafy vegetables by adult 64.0 Produce by~ adult
.456.0 Meat by adult 110.0 Milk by adult 310.0 Milk by infant 330.0 3
Breathing ~ Rates (m /yr)
/
Adult 8,000.0
\\
Infant 1.400.0 Animal Consumption Rates-(kg/ day)
~
Animal feed by meat animal 50.0 Animal feed by milk cow 50.0 Animal feed by milk goat-6.0 Exposure Periods During Growing Season _(days)-
.j Leafy vegetables 60.0-Pasture vegetation 30.0 Produce 60.0 Residential Structure Shielding Factor 0.7 Fraction of Particulates Initially Deposited on Leafy Vegetation-0.2-Fraction of Particulates Initially Deposited on Produce 0.2 Fraction of Iodine Deposited on Leafy Vegetation 1.0 Fraction of Iodine Deposited on Produce 1.0 2
Surface Density of Soil'for Root Zone (kg/m )
240.0 Field Decay Half Life (days) 14.0 37
4
- 1 TABLE 1.B-1 Sheet 2 of-2
- . O j
Parameter Value 2
Agricultural Productivity (kg/m )
y Leafy vegetables 2.0-
-l Pasture grass 0.7' Produce 2.0 Period of Long-Term Buildup for Activity in Soil (days) 7,300.0
~
Fraction of Leafy Vegetables Crown in Garden of Interest-1.0 Fraction-of Produce Crown in Garden of-Interest 0.76 Fraction of Year Animal Graces on Pasture 0.5 1
Fraction of Daily Feed that is Pasture Crass when Animal Grazos 1.0
,I e
I y
l t
e l
38
-TABLE 1.B-2 Sheet 1 of 2:
PARAMETERS'USED IN CALCULATING DOSES FROM LIQUID EFFLURNTS a
Value-Parameter let Otr. 1989 2nd Otr. 1989 Plant Dilution Flow Rate (spm) 31,800.
27,800, j
Columbia River Flow Rate (cfs)
.130,997.
370,900.
.i Dilution FactorsL Drinking water 1,846.
6,111.
Swimming water 406.
1,344.
Aquatic biota 406.
1,344..
t Shoreline sediment
- 406, 1,344.-
l Irrigation water
.1, 84 8.-
6,111.'
Milk and meat animal water 1,848.
6,111.
Decay Times (days)'
. _..0.59 Discharge to drinking water 0.76 Discharge to swimming water 0.0 0.0 Discharge to aquatic biota consumption 1.0 1.0 Discharge to deposition on shoreline sediment 0.0 0.0 Discharge to irrigation water withdrawal
-0.76 0.59 l
Discharge to milk and meat animal water 0.76 0.59 withdrawal Leafy vegetable harvest to consumption by man 1.
Produce harvest to consumption by man'
-60.=
Stored feed harvest to consumption by animals.
90.
Pasture grass to consumption by animals
- O.
Animal butchering to consumption ~
20.
Food-and water ingestion by cow / goat'to 2.
milking Accumulation Times (days)
Shoreline sediment 7,300.
Irrigated soil-7,300.
l Irrigated vegetables 60.
I Pasture grass 30.
l l
Adult Consumption Rates (kg/yr)
Drinking water 730.
Fish 21.
Invertebrates (crayfish) 5.
Irrigated leafy vegetables 64.
s Irrigated produce 456.
Cow's milk from irrigated pastureland 310.
Goat's milk from irrigated pastureland 310.
Meat from irrigated pastureland 110.
-f
\\
\\
\\
39 h
/
TABLE 1.B-2 Sheet 2 of 2 O Value Parameter let Otr. 1989 2nd Otr. 1989 Annual Exposure Times (hr/yr)
Swimming and boating 12.
Shoreline activities 12.
1 Irrigated pasture 2,190.
Infant Consumption Rates (kg/yr)
Drinking water 330.
Cow's milk from irrigated pastureland 330..
Fraction of Year Animals Graze on Pasture 0.5 Fraction of Year Crops are Irrigated 0.5 Field (Weathering). Half-Life (days) 14.
j 2
Irrigation Rate (liters /m -hr) 0.104 Fractional Concentration of Water in Soil (3/s) 0.2 Fraction of Leafy Vegetables Grown in Garden of-1.
Interest 4
j Fraction of Produce Crown in Garden of-Interest
-0.76 j
Irrigated Soil Self-Shielding Factor 2.5 l
Fraction of Isotope in Irrigation Water That is 0.25 Initially Retained by Leafy Vegetables l!
Fraction of Isotope in Irrigation Water That is 0.25 Initially Retained by Produce Pasture Grass Yield (kg/m2) 0.7-q Vegetable Yield (kg/m2) 2.
Surface Density of Soil (kg/m2) 240.
Animal Consumption Rates (kg/ day).
Water by milk cow 60.
Water by milk goat 8.
Water by beef 50.
Pasture vegetation by milk cow 50.
Pasture vegetation by milk goat 6.
Pasture vegetation by beef 50.
O 40
.._m w
TABLE 1.B-3 0 1 QUARTER 1989 DOSES FROM LIQUID EFFLUENTS (MREM) l TOTAL OTHER
~
ADULT INFANT INTERNAL EXPOSURE PATHWAY 00DY SKIN LUNG SONE THYROID THYR 01D ORGANS AQUATIC AT MAXIMUM LOCATION DRINKING WATER 3.5E-05 3.5E-05 3.5E-05 3.6E-05 3.9E 5.8E-05 4.IE-05 i
FISH CONSUMPTION 2.0E-05 2.0E-05 9.3E-06 2.4E-05 2.7E-05 0.0E400 2.9E-04 INVERTE0 RATE CONSUMPTION 1.2E-05 1.2E-05 1.8E-05 3.9E-05 1.3E-05 0.0E*00 1.4E-04 EXPOSURE TO SHORELINE SEDIMENT 1.6E-06 1.9E 1.6E-06 1.6E-06 1.6E-06' O.0E*00 1.6E-06 SWIMMING AND 00ATING 1.7E-08 1.5E-07_
1.7E-08 1.7E-08 1.7E-08 0.0E*00 1.7E-08 AQUATIC TOTAL 6.9E-05 7.0E-05 6.4E-05 1.0E-04 8.0E-05 5.8E-05 4.7E-04
~
AQUATIC AT AGRICULTURAL LOCATION DRINKING WATER 3.5E-05 3.5E-05 3.5E-05 3.6E-05 3.9E-05 5.8E-05 4.lE-05 FISH CONSUMPTION 4.5E-06 4.5E-06 2.0E-06 5.4E-06 5.9E-06 0.0E*00 6.4E-05 INVERTE0 RATE CONSUMPTION 2.8E-06 2.8E 3.9E-06 8.7E-06 2.9E-06 0.0E+00 3.0E-05 EXPOSURE TO $NORELINE SEDIMENT 3.4E-07 4.0E-07 3.4E-07 3.4E-07' 3.4E-07 0.0E*00 3.4E-07 SWIMMING AND 00ATING 3.8E-09 3.3E-08 3.8E-09 3.8E-09 3.8E-09 0.0E+00 3.0E-09 IRRIGATION AND LIVESTOCK WATERING EXPOSURE TO AGRICULTURAL SOIL 4.5E-06 5.3E-06 4.5E-06 4.5E-06 4.5E-06 0.0E+00 4.5E-06 LEAFY VEGETABLE CONSUdPTION 3.2E-06 3.2E-06 3.2E-06 3.6E-06 5.8E-06 0.0E+00 6.1E-06 PRODUCE CONSUMPTION 1.6E-05 1.6E-05 1.6E-05 1.8E-05 1.4E-05 0.0E+00 2.9E-05 MEAT CONSUMPTION 7.2E-06 0.0E+00 1.5E-04' i
MILK CONSUMPTION (COW)
, 7.0E-06 7.0E-06 1.1E-05 1.0E-05
' 2.2E-05 9.1E-05 2.0E-05 1.6E-05 1.6E-05 1.6E-05 1.7E-05 MILK CONSUMPTION (GOAT) 3.6E-05 3.6E-05 3.5E-05 3.6E-05 4.2E-05 1.4E-04
-3.5E-05 AGRICULTURAL TOTAL
- 1.1E-04 1.1E-04 1.1E-04 1.2E-04 1.2E-04 2.2E-04 3.6E-04 EXCLUDING COW MILK CONSUMPTION EXCLUDING GOAT MILK CONSUMPTION 9.0E-05 9.1E-05_
9.3E-05 1.0E-04
. 1.0E-04 1.5E-04 3.5E-04 i
l.
...m________...____________****************************"****"***************"**********************
,m.
y..
2%
g.
~7-e p
sw.
q
-w
,, q%q r
w 3
b TABLE 1.B-4 FIRST 00ARTER 1989 POPULATION DOSE (59-MILE) FROM LIQUID EFFLUENTS (MAN-REM)
EXPOSURE PATHWAY TOTAL SODY THYROID AGUATIC DRIKING WATER I.4E-04 I.6E-94 FISH CONStNFTION I.9E-93 2.6E-93 INVERTEBRATE CONSUMPTION 5.5E-96 5.7E-94 EXPOSURE'TO CONTAMINATED SEDIMENT 7.8E-96 7.8E-96 SWIMMING AND BOATING 4.4E-98 4.4E-98 IRRIGATION AND LIVESTOCK WATERING-LEAFY WEDETABLE CONSUMPTION 2.5E-97 4.5E-97 PRODUCE CONSUMPTION
'1.2E-96 I.2E-96 MEAT CONSUMPTION 9.7E-96 9.9E-96 MILK CONSUMPTION 8.4E-95 I.2E-94 EXPOSURE TO CONTAMINATE 9 SOIL 6.6E-97 6.6E-97 TOTAL
-2.2E-93 2.9E-93 AVERAGE DOSE (MREM / PERSON)
I.IE-96 I.4E-96 O
. O O
=
i s
t IA.B E 3-1
\\
FIRST QUARTER 1989 BATCH RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION
. 5 i
Site
-'i Boundaryl*I -
Residence (b)
~
Beta Air Dose (mrad) 2.3E-2 1.3E-2.
f Cama Air Dose (mrad) 7.8E-3
'3.18-3 Beta + Gama Skin Dose (mrem) 7.8E-3 Gama Total Body Dose (mrom)
-2,6E-3 i
i
[a] NNW sector at 674 meters.
(b) NWW sector at 1000 meters, ll l
4 I
I 1
4 4
- n V
43-5-
z
oj i
TABLE 1.B-6 i
FIRhT QUARTER 1939 CONTINUOUS RELEA3dS i
DOSES FROM NOBLE GASES AT-SITE BOUNDARY AND RESIDENCE OF
+
HIGHEST CONCENTRATION i
r I
Site Boundary [a]
Residence [b]
Beta Air Dose (mead) 5.3E-2 3.0E-2' f
Gamma Air Dose (mrad) 2.1E-2 8.2E-3' i
1.9E-2 Beta'+ Gamma Skin Dose (mrem) c
'I Gamma Total Body Dose (mrom) 7.1E-3 t
t
[a] NNW sector at 674 meters.
-l
[b] NNW sector at 1000 meters.
'L l
I
(
t 4
i 1
l I
l 1
s
.i 44
- i
?
I f
TABf,E 1,5-7 i
FIRST QUARTER 1989 BATCH + CONT 1WUOUS RKLKASES D0sts FROM WOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION i
I Site boundaryla) posidenc,[b]
[
t Beta Air Dose (mrad) 7.6E-2 4.28-2 Gkmma Air Dose (mrad) 2.9E-2 1.1E-2 t
2.75-2 Beta + Camma Skin Dose (mrom) 9.7E-3
[
Camma Total Body Dose (mrom) 4 (a) Maximum site boundary location.
(b) Maximum residence location.
(
6 s
f i
[
1 s
a i
I i
l.
l 45 9
- + - - -, --
TABLE 1.B-8 9I SUARTER 1999 SATCM RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLUDING N09tE GASES) AT MAXIMUM 0FFSITE EXPOSURE LOCATIONS (NREN)
STNER TOTAL ASULT INFANT INTE9NAL EXPOSURE LOCATION AND PATHWAY 909Y SKIN LUNG SONE THYROID TMYROID ORGANS GARDEN (N W SECTOR AT 1999. METERS)
AIR INMALATION 8.59E-97 8.59E-97 8.59E-97 8.52E-07 5.28E-96 4.93E-96 8.56E-97
. EXPOSURE TO SOIL 4.61E-98 5.49E-88 4.6tE-98 4.61E-98 4.61E-98 4.61E-98 4.61E-98 LEAFY VEGETA9tE CONSUMPTION 3.17E-97 3.17E-97 3.17E-97 3.3SE-97 4.79E-95 0.99E*89
- 3. 79E-9 7 PRODUCE CONSUMPTION 1.29E-06 1.29E-96 1.28E-96 1.28E-96 2.83E-96 9.99E*09 1.29E-96 TOTAL 2.49E-06 2.59E-96 2.49E-96 2.53E-96 5.51E-95 4.97E-06 Z.56E-96 MEAT ANIMAL (NW SECTOR AT 3299. METERS)
AIR INNALATION 1.49E-97 1.49E-97 1.49E-97 1.59E-07 9.62E-97 1.19E-96 1.59E - 0 7 e-EXPOSURE TO SOIL 6.36E-99 7.73E-99 4.36E-C9 6.36E-99 4.36E-99 6.36E-99 6.36E-99 LEAFY VEGETA9tE CONSUMPTION 5.61E-98 5.61E-98 5.61E-98 5.86E-98 6.49E-96 9.99E*99 6.46E-98 PRODUCE CONSUMPTION 2.43E-97 2.43E-07 2.43E-97 2.43E-97 4.58E-97 9.99E*09 2.4 3E-9 7 t
MEAT CONSUMPTION 4.69E-98 4.6?E-98 4.69E-98 4.79E-98 4.83E-97 9.99E*99 4.74E-98 TOTAL 5.92E-37 5.93E-97 5.92E-97 5.95E-97 8.49E-96 1.IIE-96 5.12E-87 MILK COW (NNW SECTOR AT 8994. METERS)
AIR INNALATION 3.38E-98 3.38E-98 3.38E-98 3.38E-98 2.28E-97 2.43E-97 3.49E-98 EXPOSURE TO SOIL 3.IIE-99 I.35E-99 I.IIE-99 I.IIE-99 I.IIE-99 1.IIE-99 1.IIE-99 LEAFY WEGETASLE CONSUMPTION 1.32E-98 1.32E-88 1.32E-98 1.36E-08 1.14E-96 9.99E*SS I.4FE-98 PRODUCE CONSUMPTION 6.98E-98 6.98E-98 4.99E-98 4.99E-98 9.83E-98 9.99E*89 6.99E-98 MEAT CONSUMPTION 1.17E-98 1.17E-98 1.17E-98 1.17E-98 8.89E-98 9.99E*89 E.18E-08 COW MILK CONSUMPTION 3.98E-98 3.99E-98 3.99E-98 3.16E-98
- 2. IGE-96 3.43E-95 3.36E-98 TOTAL 1.53E-97 f1.52E-97 1.51E-97 I.53E-07 3.69E-96 1.64E-95 1.54E-97 MILK GOAT (NNW SECTOR AT 9999. METERS)
EXPOSURE T8 SOIL 3.IIE-99 1.35E-99 2.IIE-99 3.IIE-99 I.IIE-99 I.IIE-99 3.IIE-99 LEAFY WEGETAGLE CONSUMPTION 1.32E-98 1.32E-98 1.32E-98 I.36E-98 1.14E-96 9.99E*99 I.47E-98 PRODUCE CONSUNPTION 6.98E-98 6.98E-98 6.98E-98 6.99E-98 9.93E-98 9.99E*99 6.08E-98 MEAT CONSINFTION 1.17E-98 I.17E-98 1.17E-08 1.17E-98 8.99E-98 9.99E*09 1.18E-98 GOAT MILK CONSUMPTION 5.99E-98 5.99E-98 5.99E-98 6.98E-98 2.59E-06 1.94E-85 6.3IE-98 TOTAL 1.89E-97 1.89E-97 1.09E-97 1.82E-ST 4.I4E-96 1.96E-95 1.8 5E-9 7 9
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TABLE 1.B-12 j
9 2 OUARTER 1999 DOSES FROM LIOUID EFFLUENTS (MREM) l OTHER TOTAL ADULT INFANT INTERNAL EXPOSURE PATHWAY 90DY SKIN LUNG SONE THYROID TNYROID ORGANS AGUATIC AT MAXIMUM LOCATION DRINKING WATER 1.3E-95 1.3E-05 1.3E-95 1.4E-95 1.4E-95 2.1E-95 1.5E-95 FISH CONSUMPTION 5.6E-95 5.6E-95 1.2E-95 5.9E-95 5.8E-95 9.9E+99
- 3. 2E-94 INVERTE9 RATE CONSUMPTION 1.1E-95 1.1E-95 7.6E-96 1.9E-95 1.1E-05 9.9E*89
- 7. 3E-95 t
EXPOSURE TO SHORELINE SEBIMENT 6.9E-97 8.1E-97 6.9E-97 6.9E-97 6.9E-97
- 9. 9E
- 9 9 -
6.9E-97 SWIMMING ANO 90ATING 1.1E-88 5.3E-98 1.1E-98 1.1E-88 1.1E-98 9.9E*00 1.IE-98 t
AGUATIC TOTAL 8.IE-95 8.1E-95 3.2E"95 8.3E-95 8.5E-95 2.1E-95 4.1E-94 f
u, O
i AGUATIC AT AGRICULTURAL LOCATION l
t DRINKING WATER 1.3E-95 1.3E-95 1.3E-95 1.4E-95 1.4E-95 2.1E-05 1.5E-85 FISH CONSUMPTION 1.2E-05
-1.2E-95 2.5E-96 1.1E-95 1.3E-95 0.9E*99
- 7. 9E-95 INVERTE9 RATE CONSUMPTION 2.5E-96 2.5E-96 1.7E-96 4.2E-96 2.5E-96 9.9E*99 3.6E-95 EXPOSURE TO SMORELINE SEBIMENT I.5E-97 1.8E-97 1.5E-97 1.5E-97 1.5E-07 9.9E*99 1.5E-97 SWIMMING ANO 90ATING 2.5E 1.2E-98 2.5E-99 2.5E-99 2.5E-99 9.9E*09 2.5E-99 IRRIGATION AND LIVESTOMC WATERING j
I EXPCSURE TO AGRICULTURAL SOIL 2.9E-96 2.35-96 2.9E-96 2.9E-96 2.9E-96 9.9E*99 2.9E-96 LEAFY VEGETA9tE CONSUMPTION 1.4E-96 1.4E-96 1.3E-96 1.8E-96 2.3E-96 9.9E*90 2.6E-96 PRODUCE CONSUMPTION 6.9E-96 6.8E-96 6.4E-96 9.9E-96 6.8E-94 9.9E*00 1.2E-95 MEAT CONSUMPTION 2.6E-94 2.6E-96 4.9E-94 3.6E-96 2.7E-96 9.9E+99 5.6E-95 MILR CONSUMPTION (COW) 4.6E-96 6.6E-96 5.9E-96 6.6E-96 8.5E-06 3.3E *5 9.9E-96 MILE CONSUMPTION (GOAT) 1.5E-95 1.5E-95 1.3E-95 1.5E-95 1.7E-95 5.9E-05 1.3E-95
!~
AGRICULTURAL TOTAL EXCLUDING COW MILE CONSUMPTION 5.5E-95 5.6E-85 4.3E-95 6.8E-95 4.9E-95 7.9E-95 I.9E-94 EXCLUDING GOAT MILK CONSUMPTION 4.7E-95 4.7E-95 3.7E-95 5.2E-95 5.2E-95 5.4E-95 1.8E-04 i
.... _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. - -... - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ ~ ~ - -
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TABLE 1.5-14 i
SECOND QUARTER 1989 BATCH RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF 1
HIGHEST CONCENTRATION q
l 1
site Boundary (a)
Residene,1b)
J 4
Beta Air Dose (mrad) 4.9E-2 1.9E-2 Camma Air Dose (mrad) 1.6E-2 4.2E-3 1.1E-2 j
Beta + Camma Skin Dose (mrom) 3.5E-3 Camma Total Body Dose (mesm) s
[a] East sector at 677 meters, c
lh
[b) North sector at 1000 meters.
k s
e I
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TABLE 1.5-15 SECOND QUARTER 1989 CONTINUOUS RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site poundaryl'I Residenc,[b]
Beta Air Dose (mrad) 2.6E-2 1.1E-2 Gamma Air Dose (mrad) 8.9E-3 2.7E-3 a
Beta + Cama Skin Dose (mrom) 6.4E-3 Gamma Total Body Dose (mrom) 2.38-3
[a] tast sector at 677 meters.
[b] North sector at 1000 meters.
O O
53
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l
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l TABLE 1,3-16 O
l SECOND QUARTER 1989 BATCH + CONTINUOUS RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF
. HIGHEST CONCENTRATION i
l l
site Boundary [a]
Residence (b)
Beta Air Dose (mrad) 7.5E-2 3.05-2 Gamma Air Dose (mrad) 2.5E-2 6'.9E-3 Beta + Gamma Skin Dose (mrom) 1.7E-2 Garema Total Body Dose (mrom) 5.8E-3 r
(a) Maximum site boundary location.
(b) Maximum residence location.
G l
f
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54
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4 TABLE 1.B-17 82 00ARTER 1989 DATCM RELEASES DOSES FROM GASEGUS EFFLUENTS (EXCLUSING N00LE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREN) i 9YNER TOTAL ADUti INFANT INTERNAL j
EXPOSURE LOCATION AND PATNWAY 90DY SKIN LUNG DONE TNYROID TNYRDID ORGANS g
CARDEN l'
(NNW SECTOR AT 1999. METERS)
AIR INHALATION 5.35E-94 5.35E-94 5.45E-04 4.83E-84 2.79E-93 3.98E-83 5.38E-94 l
EXPOSURE TO Soft 2.2GE-85 2.46E-05 2.29E-85 2.20E-95 2.29E-95 2.20E-05 2.20E-85 LEAFY VEGETA9tE CONSUMPTION 4.35E-84 4.35E-04 4.35E-94 1.26E-93 2.29E-02 0.00E*00 4.43E-04 PRODUCE CONSUMPTION 2.14E-03 2.14E-03 2.14E-93 6.39E-93 2.86E-83 0.00E*89 2.14E-03 TOTAL 3.13E-03 3.14E-93 3.14E-83 8.36E-93 2.77E-92 3.11E-03 3.16E-03 i
MEAT ANIMAL (SSW SECTOR AT 1600. METERS)
- t
[
AIR INNALATION 1.34E-94 1.34E-04 1.39E-94 1.74E-84 7.17E-94 7.95E-04 1.37E-94 i
EXPOSURE TO S0tt 5.38E-96 4.52E-96 5.38E-96 5.38E-96 5.38E-06 5.38E-96 5.38E-06 i
LEAFY VEGETABLE CONS'JMPTION 1.09E-04 1.99E-94 1.99E-94 3.10E-94 5.49E-93 0.00E*90 1.16E-04 PRODUCE CONSUMPTION 5.37E-94 5.37E-04 5.37E-94 1.58E-93 7.14E-04 0.00E*99 5.37E-84 MEAT CONSUMPTION 4.63E-95 4.63E-95 4.63E-95 6.74E-85 4.06E-94 0.89E*99 4.d7E-85 TOTAL 8.35E-94 8.34E-94 8.36E-04 2.14E-93 7.24E-93 8.99E-84 8.42E-94 i
MILK COW (SOUTH SECTOR AT 8998. METERS) 9.39E-95 1.5eE-95 AIR INNALATION 1.49E-95 1.49E-95 1.51E-95 1.90E-05 8.4IE-95 EXPOSURE TO SOIL 7.58E-97 9.18E-07 7.58E-07 7.58E 7.58E-87 7.58E-87 7.58E-97 4
LEAFY WEGETABLE CONSUMPTION 1.48E-95 2.48E-SS 1.49E-95 4.32E-05 7.69E-04 0.99E*88 1.58E-95 PRODUCE CONSUMPTION 7.29E-05 7.29E-t-7.29E-95
- 2.29E-94 9.78E-05 S.98E*08 7.29E-05
[
MEAT CONSUMPTION 6.01E-96 4.91E-96 6.91E-96' 8.90E-06 5.67E-05 8.etE*00 6.99E-06
' COW MILK CONSUMPTION 1.77E-95 1.77E-95 1.77E-05
. 2.95E-95 1.41E-93 1.07E-82 1.95E-05 i
. TOTAL 1.27E-94 1.27E-94 1.27E-94 3.21E-94 2.41E-83 1.98E-82 1.39E-04 l
l MILK GOAT-(SSW SECTOR AT 4299. METERS)
{
AIR INNALATION 2.92E-e5 2.92E-95 2.97E-95 3.73E-85 1.59E-94 1.77E-04
- 2.93E-e5 EXPOSURE 70 SOIL 1.SIE-96 1.22E-96 1.91E 1.9tE-06 1.01E-06 1.81E-86 1.91E-06 LEAFY WEGETABLE CONSUMPTION 2.21E-05
- 2.2EE-05 2.21E-95 6.99E-95 1.92E-93 9.89E*00 2.34E-95 PRODUCE CONSUMPTION 1.19E-94 1.10E-94 1.19E-94 3.96E-04 1.43E-04 9.90E*89 1.10E-84 MEAT CONSUMPTION 1.94E-95 1.04E-95 1.94E-95 1.44E-05 7.81E-95 9.00E*99 1.95E-05; GOAT MILK CONSUMPTION.
5.73E-95 5.73E-05 5.73E-95
. 8.96E-95 2.29E-03 1.71E-02 6.02E-05 i
TOTAL 2.30E-94 2.30E-94 2.31E-94 5.08E'-04 3.69E-93 1.73E-02 2.35E l
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56 1
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1 TABLE 1.B-19 92 OUARTER 1989 BATCM + CONTINUOUS RELEASES 1~
DOSES FROM GASEOUS EFFLUENTS (EXCLUDING MOSLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM)
.____e_______.e.....
_____......................e-e.
i OTNER TOTAL AOULT INFANT INTERNAL EXPOSURE LOCATION AND PATHWAY 90DY SKIN LUNG SOME THYROID THYRDID ORGANS
...._____me
...e._e..
.e._
..e GARDEN MAXIMUM LOCATION
_____.......e_................
AIR INHALATION 3.99E-93 3.99E-03 3.1DE-93 3.23E-83 7.74E-03 7.42E-83 3.99E-93 EXPOSURE TO SOIL 4.28E-85 5.18E-95 4.28E-95 4.28E-95 4.28E-85 4.28E-05 4.28E-95 LEAFY VEGETABLE CONSUMPTION 1.18E-83 1.18E-83 1.18E-93 2.82E-03 4.36E-92 8.99E*00
- 1. 24E-8 3 i
PRODUCE CONSUMPTION 6.90E-03 6.00E-83 6.98E-83 1.93E-92 7.42E-53 8.99E+00 6.91E-83 TOTAL 1.93E-92 1.93E-92 1.93E-02 1.54E-82 5.88E-82 7.47E-03 1.94E-92 MEAT ANIMAL MAXIMUM LOCATION
._____..__.e...._...._.
I AIR INHALATIow 7.48E-94 7.48E-94 7.51E-94 7.87E-94 1.91E-83 1.85E-03 7.59E-84 EXPOSURE TO SOIL 1.04E-95 1.26E-05 1.04E-95 1.94E-95 1.94E-95 1.e4E-95 1.94E-85 LEAFY VEGETABLE CONSUMPTION 2.93E-04 2.93E-94 2.93E-84 4.97E-94 1.96E-SZ 0.00E*06 3.87E-84 5
PRODUCE CCNSUMPTION 1.49E-03 1.49E-93 1.48E-93 2.53E-93 1.83E-83 9.90E+89 1.49E-03 MEAT CONSUMPTION 2.26E-04 2.26E-04 2.26E-84 2.48E-84 9.28E-94 9.98E*00 2.28E-84 l
TOTAL 2.76E-03 2.76E-93 2.77E-03 4.98E-83 1.53E-82 1.84E-83 2.78E-83 MILK COW MAXIMUM LOCATION J
_.........____.e.e...........
AIR INHALATION 8.58E-95
'8.58E-85 8.49E-95 8.99E-95 2.28E-94 2.23E-94 8.40E-95 EXPOSURE TO SDIL 1.52E-06 1.85E-06
~1.52E-96 1.52E-96 1.52E-96 1.52E-96 1.52E-06 LEAFY VEGETABLE CONSUMPTION 3.99E-95 3.99E-95 3.99E-95 4.88E-85 1.55E-03 9.00E+98 4.19E-85 PRODUCE CONSUMPTION 2.02E-94 2.02E-04 2.82E-04 3.59E-04 2.52E-94 0.00E*00 2.92E-94 3.95E-95 3.95E-95 3.95E-95 3.35E-85 1.33E-94 9.09E+0e 3.07E-95 MEAT CONSUMPTION 7.77E-95 7.77E-05 7.77E-05 9.91E-05 2.90E-83 2.18E-82 8.14E-05 COW MILK CONSUMPTION TOTAL 4.37E-94 4.37E-94 4.37E-94 6.35E-84 5.87E-03 2.29E-92 4.43E-04 l
l MILK GOAT MAXIMUM LOCATION i
......e.......e AIR INHALATION.
1.41E-94 1.6IE-94 1.62E-94 1.49E-94 4.23E-04 4.11E-84 1.4tE-94 EXPOSURE TO SOIL 1.95E-96 2.36E-36 1.95E-06 1.95E-06 1.95E-96 1.95E-86 1.95E-96 LEAFY VEGETABLE CONSUMPTION 6.48E-SS 6.48E-05 6.48E-95 1.93E-94
- 2. ele-93 9.99E*e8 6.74E-85 PRODUCE CONSUMPTION 3.32E-04 3.32E-94 3.32E-94 5.39E 3.97E-94 9.SSE*8e 3.32E-94 MEAT CONSUMPTION 5.27E-95 5.27E-95 5.27E-05 5.67E-95 1.84E-94 0.00E+es 5.28E-95 GOAT MILK CONSUMPTION 2.63E-04 2.63E-04 2.63E-94 2.97E-94 4.61E-93 3.38E-92 2.69E-04 TOTAL 8.77E-94 8.77E-94.
8.78E-94 1.16E'-93 7.62E-83 3.42E-92 8.96E-94 O
.e.
ee-ee......Oe....e_........-...e.e....e......e-eee....>eee.....m....ee.e..eee e..eee..e.e..ge.ge...
6.
8.*-----*
l
-.. ?. _-..,. _ -,,
d 4
I 3~
1 l
i TABLE 1.B-20 l
t SECOND OUARTER 1999 BATCH + CONTINUOUS RELEASES i
I i
POPULATION DOSE (59-MILE) FROM l
1 GASEOUS EFFLUENTS (MAN-REM) i EXPOSURE PATNWAY TOTAL BODY THYROIB
- AIR SUOfERSION 2.9E-92 2.9E-92 AIR INNALATION I.7E-92 4.3E-92 EXPOSURE TO SOIL 1.1E-94 1.3E-94 i
w LEAFY WE9ETABLE CONSUfFTION 1.8E-94 3.7E-93 PR000CE CONSupFTION 9.6E-94 1.lE-93 MEAT CONSupFTION 1.3E-93 3.2E-93 MILR CONSUMPTI000 1.3E-92 2.5E-91 l
t
- TOTAL 5.3E-92 3.2E-91 AVERe0E DOSE (INEM/PERSSII) 2.6E-95 1.6E-94
.I i
L f
9 O
O
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g%
p-V'.-
vw..wg-.r-@ege-g
,, -.w.*_wy.
ym__
_en___,_
__i_____,,,______q, g
,_m
, =
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u
,- he sw-d-
we'
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-sw W-kW'D- DNht---
. --a s e v- - 2e-@
Sheet 1 of 2 TABLE 1.5-21 PARANETERS USED IN CALCULATING DOSES FROM OASEOUS EFFLUENTS (Second Half 1989)
Parameter Value Accumulation and becay Times (days)
Harvest of leafy vegetables to consumption by man 1.0 Harvest of pasture grass to consumption by animals 0.0 Harvest of stored feed to consumption by animals 90.0 Harvest of produce to consumption by man 60.0 Animal butchering to consumption 20.0 Food ingestion by animal to milking 2.0 Accumulation time on ground 7,300.0 Human Consumption Rates (kg/yr)
Leafy vegetables by adult 64.0 Produce by adult 456.0 Meat by adult 110.0 Milk by adult 310.0 Milk by infant 330.0 Breathing Rates (m3/yr)
Adult 8,000.0 Infant 1,400.0 Animal Consumption Rates (kg/ day) j Animal feed by meat animal 50.0 Animal feed by milk cow 50.0 Animal feed by milk goat 6.0 Exposure Periods During Growing Season (days)
Leafy vegetables 60.0 Pasture vegetation 30.0 Produce 60.0 Residential Structure Shielding Factor 0.7 i
Fraction of Particulates Initially Deposited on Leafy Vegetation 0.2 Fraction of Particulates Initially Deposited on Produce 0.2 Fraction of Iodine Deposited on Leafy Vegetation 1.0 Fraction of Iodine Deposited on Produce 1.0 Surface Density of Soil for Root Zone (kg/m2) 240.0 Field Decay Half Life (days) 14.0 O
$9
TABLE 1.B-21 sheet 2 of 2 Parameter Value I
Agricultural Productivity (ks/m2) i Leafy vegetables 2.0 l'
Pasture grass 0.7 Produce 2.0 Period of Long-Term Buildup for Activity in Soil (days) 7,300.0 i
Fraction of Leafy Vegetables Crown in Garden of Interest 1.0
[
r Fraction of Produce Crown in Carden of Interest 0.76 Fraction of Year Animal Crares on Pasture 0.5 i
Fraction of Daily Feed that is Pasture Cross when Animal crates 1.0 i
I 9;
h b
I I
O>
60
TABLE 1.5-22 O-Sheet 1 of 2 PARAMETERS USED IN CALCULATING DOSES FROM LIQUID EFFLUgNTS Value Parameter 3rd Otr 1989 eth Otr 1989 Plant Dilution Flow Rate (spm) 28,500.
36,300.
Columbia River Flow Rate (cis) 142,563.
105,390.
Dilution Factors Drinking water 2,245.
1,303.
Swimming' water 494 287.
Aquatic biota 494.
287.
Shoreline sediment 494.
287.
Irrigation water 2,245.
1,303.
Milk and neat animal wster 2,245.
1.303.
Decay Times (days)
Discharge to drinking water 0.74 0.83 Discharge to swinning water 0.0 0.0
+
Discharge to aquatic biota consumption 1.0 1.0 Disc.harge to deposition on shoreline sediment 0.0 0.0 Discharge to irrigation water withdrawal 0.74 0.83 O
Discharge to milk and nest animal water 0.74 0.83 withdrawal Leafy vegetable harvest to consumption by men 1.
Produce harvest to consumption by man 60.
Stored feed harvest to consumption by animals 90.
Pasture grass to consumption by animals 0.
Animal butchering to consumption 20.
Food and water ingestion by cow / goat to 2.
milking Accumulation Times (days)
Shoreline sediment 7,300.
Irrigated soil 7,300.
Irrigated vegetables 60.
Pasture grass 30.
L Adult Consumption Rates (kg/yr)
Drinking water 730.
Fish 21.
Invertebrates (crayfish) 5.
Irrigated leafy vegetables 64.
Irrigated produce 456.
Cow's milk from irrigated pastureland 310.
Goat's milk from irrigated pastureland 310.
Meat from irrigated pastureland 110.
~ !
l 61 4
m
TABLE 1.5-22 Sheet 2 of ^-
Value Parameter 3rd Otr 1989 4th Otr 1969 AAnnual Exposure Times (hr/yr)
Swimming and boating 12.
Shoreline activities 12.
Irrigated pasture 2,190.
2 Infant Consumption Rates (kg/yr)
Drinking water 330.
Cow's milk fron irrigated pastureland 330.
Fraction of Year Animals Craze on Pasture 0.5 Fraction of Year Crops are Irrigated 0.5 Field (Weathering) Half-Life (days) 14.
2 Irrigation Rate (liters /m -hr) 0.104 Fractional Concentration of Water in Soil (g/s) 0.2 Fraction of Leafy Vegetables Crown in Garden of 1.0 Interest Fraction of Produce Grown in Garden of Interest 0.7 Irrigated Soil Self-Shielding Factor 2.5 Fraction of Isotope in Irrigation Water that is 0.25 Initially Retained by Leafy Vegetables i
Fraction of Isotope in Irrigation Water that is 0.25 l
Initially Retained by Produco j
2 Pasture Crass Yield (kg/m )
o,y Vegetable Yield (kg/m2) 2.0 Surface Density of Soil (kg/m2) 240.0 Aninal Consumption Rates (kg/ day)
Water by milk cow 60.
Water by milk goat 8.
Water by beef 50.
Pasture vegetation by milk cow 50.
Pasture vegetation by milk goat 6.
Pasture vegetation by beef 50.
NF 62 i
g TABLE 1.B-23
- 3 QUARTER 1989 DOSES FROM LIQUID EFFLUENTS (MREM)
____ = _ _, _ _ _ _ ___
z_
OTHER TOTAL ADULT INFANT INTERNAL EXPOSURE PATHWAY BODY SKIN LUNG BONE THYROID THYROID ORGANS
=_ _.___
_____ =__
AQUATIC AT MAXlMUM LOCAT104
- - - =-==.-
==-==... ------
DRINKING WATER 1.2E-04 1.2E-04 1.2E-04 1.3E-04 1.2E-04 1.6E-04 1.3E-04 FISH CONSUMPTION 1.9E-04 1.9E-04 5.0E-05 2.0E-04 1.9E-04 0.OE+00 1.5E-03 INVERTEBRATE CONSUMPTION 4.5E-05 4.5E-05 3.2E-05 8.8E-05 ft.5E-05 0.0E+00 3.3E-04 EXPOSURE TO SHORELINE SEDIMENT 3.2E-06 3.8E-06 3.2E-06 3.2E-06 3.2E-06 0.GE+00 3.2E-06 SWIMMING AND BOATING 5.0E-08 5.0E-07 5.0E-08 5.0E-08 5.0E-08 0.0E+00 5.0E-08 AQUATIC TOTAL 3.6E-04 3.6E-04 2.0E-04 4.2E-04 3.6E-04 1.6E-04 2.OE-03 l
- =_
-- _=_=..
......w---
=_==-_.......-------- -
......--.........=-__
b AQUATIC AT AGRICULTURAL LOCATION DRINKING WATER 1.2E-04 1.2E-04 1.2E-04 1.3E-04 1.2E-04 1.6E-04 1.3E-04 FISH CONSUNPTIOff 4.3E-05 4.3E-05 1.1E-05 4.4E-05 4.3E-05 0.0E+00 3.4E-04 INVERTEBRATE CONSUMPTION 9.8E-06 9.8E-06 7.1E-06 1.9E-05 9.8E-06 0.0E+00 7.3E-05 EXPOSURE TO SHORELINE SEDIMENT 7.0E-07 8.3E-07 7.0E-0 T '
7.0E-07 7.0E-07 0.0E+00 7.0E-0 7 SWIMMlleG AND BOATIMG 1.1E-08 1.1E-07 1.1E-08 1.1E-08 1.1E-08 0.OE+00 1.1E-08 IRRIGATION AND LIVESTOCK WATERING EXPOSURE TO AGRICULTURAL Soll
'9.2E-06 1.1E-05 9.2E-06 9.2E-06 9.2E-06 0.0E+00 9.2E-%
LEAFY VEGETABLE CONSUMPTION 1.2E-05 1.2E*05 1.1E-05 1.6E-05 1.2E-05 0.0E+00 1.8E-05 PRODUCE CONSUMPTION 5.8E-05 5.8E-05 5.7E-05 7.5E-05 5.8E-05 0.0E+00 8.3E-05 MEAT CONSUMPTIO98 2.3E-05 2.3E-Oi 3.0E-05 2.8E-05 2.3E-05 0.0E+00 3.0E-04 MILK CONSUMPTION (COW) 5.7E-05 5.7E-05 5.5E-05 5.9E-05 5.8E-05 1.8E-04 6.6E-05 MILK CONSUMPTION (COAT) 1.3E-04 1.3E-04 1.2E-04 1.3E-04 1.3E-04 3.8E-04 1.2E-04 AGRICULTURAL TOTAL EXCLUDING COW MILK CostSUMPTION 4.OE-04 4.0E-04 3.6E-04 4.5E-04 4.0E-04 5.4E-04 1.1E-03 EXCLUDING COAT MILK CONSUMPTION 3.3E-04 3.3E-04 3.0E-04 3.8E-04 3.3E-04 3.4E-04
- 1. 0E-0 3
~.... - -... - -.
g y-s
_%w-mp yv v
-m'p w
9
,ir yag 4mm
,y...%w
_y,,
my y_.
w
=_,%ep y--m y-m y
TABLE 1.B-24 THIRD QUARTER 1989 j
POPULATION DOSE (50-MILE) FROM LIQUID EFFLUENTS (MA88-REM)
F I
EXPOSURE PATHWAY TOTAL BODY THYROIO i
_==..
1 AQUATIC i
URllIKING WATER is.8E-04 4.8E-04 FISH CO8tSUMPTIOes 1.8E-02 1.8E-02 INVERTEBRATE CONSUMPTION 2.0E-05 2.0E-05 EXPOSURE TO CONTAMINATED SEDIMENT 1.6E-05 1.6E-05 E
SWIMMING Afe0 BOATING 1.3E-07 1.3E-07 IRRIGATIOff AND LIVESTOCK WATERING LEAFY VEGETAPLE CONSUMPTION 9.0E-07 9.2E-07 PRODUCE CostSUMPTION 4.5E-06 4.5E-06 MEAT COISSUMPil08i 3.1E-05 3.1E-05 MILK COctSUMPTION 2.9E-04 3.1E-04 EXPOSURE TO CO8tTAMINATED Soll 1.3E-06 1.3E-06 TOTAL 1.9E-02 1.9E-02 AVERAGE DOSE (MREM /PERSost) 9.4E-06
.9.4E-06 i
O.
O O
Table 1.B-25 THIRD QUARTER 1989 BATCH RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a]
Residencelb)
Beta Air Dose (mrad) 4.1E-2 2.18-2 Gamma Air Dose (mrad) 1.4E-2 5.0E-3 Beta + Gamma Skin Dose (mrom) 1.2E-2 i
Gamma Total Body Dose (mrom) 4.2E-3
[a] ESE sector at 805 meters.
0
[b] ESE sector at 1300 meters.
i O
65 1
I i
Table !.B-26 THIRD QUARTER 1989 CCNTINUOUS RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION I
i Site Boundaryla)
Residence [b]
i
.1 Beta Air Dose (mrad) 1.0E-2 5.2E-3 Gamma Air Dose (mrad) 3.4E-3
.1.2E-3 Beta + Gamma Skin Dose (mram) 2.9E-3 Gamma Total Body Dose (mram) 1.0E-3 la) ESE sector at 805 meters.
t
[b] ESE sector at 1300 meters.'
i O-B 9
b i
4 l
a 3
0 66
,--n v
't Table 1.B-27 THIRD QUARTER 1989 O;
BATCH + CONTINUOUS RELEASES i
DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION 9
Site Boundary!a)
Residence [b]
Beta Air Dose (mrad) 5.1E-2 2.6E-2 f
Camma Air Dose (mrad) 1.75-2 6.2E-3 1.5E-2
. Beta + Gamma skin Dose (mrom) t 5.2E-3
)
Camma Total Body Dose (mrom)
I (a) Maximum site boundary location.
(b) Maximum residence location.
t i
f I
67 y
~
+,. -.
TABLE 1.B-28 73 QUARTER 1989 8ATCM RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLU0lleG
- 08tE GASES} AT MAX 1 MUM OFFSITE EXPOSURE LOCAT100tS (MREM)
............=--.-
OTHER TOTAL ADULT IIIF AMT INTERMAL EXPOSURE LOCATION AND PATHWAY 800Y SKIN LUMG 80NE THYROID THYRolo ORGAMS CARDEN (MMW SECTOR AT 1000. METERS)
AIR INHALATION 1.08E-04 1.08E-04 1.08E-04 1.08E-04 1.85E-04 1.51E-04 1.09E-04 EXPOSURE TO Soll 6.12E-07 7.as3 E-07 6.12E-07 6.12E-07 6.12E-07 6.12E-07 6.12E-07 LEAFY VECETABLE CostSUMPTION 3.1tsE-05 3.14E-05 3.18sE-05 3.16E-05 6.69E-04 0.00E+00 3.22E-05 PRODUCE CONSUMPTION 1.6EsE-04 1.64E-Ots 1.64E-04 1.64E-Ott 1.F5E-04 0.00E+00 1.68E-0Es TOTAL.
3.04E-04 3.05E-04 3.04E-Ots 3.05E-04 1.04E-03 1.52E-04 3.05E-04 MEAT ANIMAL (SSW SECTOR AT 1600. METERS)
==
AIR IMHALATION 3.t:3E-05 3.t:3E-05 3.43E-05 3.as3E-05 5.89E-05 as.82E-05 3.44E-05 EXPOSURE TO Soll 2.34E-07 2.84E-07 2.34E-07 2.34E-07
- 2. 31sE-07 2.34E-07 2.34E-07 LEAFY VEGETABLE CONSUMPTION 1.02E-05 1.02E-05 1.02E-05 1.03E-05 2.54E-04 0.00E+00 1.05E-05 PRODUCE C00tSUMPfl04 5.31E-05 5.31E-05 5.31E-05 5.31E-05 6.12E-05 0.00E+00 5.31E-05 MEAT C08tSUMPTIOff 1.01E-05 1.01E-05 1.01E-05 1.01E-05 2.67E-05 0.00E+00 1.01E-05 TOTAL 1.08E-04 1.08E-Oes 1.08E-Ols 1.08E-04 Is.01E-04 Es.85E-05 1.08E-04 MILK COW (SSE SECTOR AT 8000. METERS)
AIR i stHALATIOft 6.89E-06 6.89E-06 6.89E-06 6.89E-06 1.23E 1.02E-05 6.89E-06 EXPOSURE TO Soll to.56E-08 5.SasE-08 Es.56E-08 4.56E-08 4.56E-08 ts.56E-08 as.56E-08 LEAFY VEGETABLE C00tSUMPT1086 2.39E-06 2.39E-06 2.39E-06 2.t:1E-06 as.99E-05 0.00E+00 2.as5E-06 PRODUCE C09tSUMPil0N 1.25E-05 1.25E-05 1.2SE-05 1.25E-05 1.as tE-05 0.00E+00 1.25E-05 MEAT CostSUMPTiom 2.38E-06 2.38E-06 2.38E-06 2.38E-06 5.61E-06 0.00E+00 2.38E-06 COW MILK CoftSUMPTION 5.74E-06 5.74E-06 5.7tsE-06 5.77E-06 9.ts8E-05 6.94E-04 5.86E-06 TOTAL 2.99E-05 2.99E-05 2.99E-05 3.00E-05' 1.77E-04 7.05E-04 3.01E-05 MILK GOAT (SSE SECTOR AT 8000. METERS)
AIR INHALATION 6.89E-06 6.89E-06 6.89E-06 6.89E-06 1.23E-05'.
1.02E-05 6.89E-06
' EXPOSURE TO foll is.56E-08 5.54E-06 as.56E-06 as.56E-08 4.56E-08 4.56E-08 ts.56E-08 LEAFY VEGETABLE C08tSUMPTl088 2.39E-06 2.39E-06 2.39E-06 2.as t E-06 4.99C-05 0.00E+00 2.45E-06 PRODUCE CONSUMPTIOft 1.25E-05 1.25E-05 J.25E-05 1.25E 1.41E-05 0.00E+00 1.25E-05 MEAT CONSUMPTioes 2.38E-06 2.38E-06 2.38E-06 2.38E-06 5.61E-06 0.00E+00 2.38E-06 GOAT MILK COftSUMPTION 1.16E-05 1.16E-05 1.16E-05 1.16E-05 1.18E-04 8.48E-04 1.17E-05 TOTAL 3.58E-05 3.58E-05 3.58E-05 3.58E-05 2.00E-04
.8.58E-04 3.60E-05
................. _........ _... _. ~...
O O
O
m TABLE 1.B-29 F3 QUARTER 1989 CONTINUOUS RELEASES
- i DOSES FROM GASEOUS EFFLUENTS (EXCLUDING NOBLE CASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM)
OTHER TOTAL AOULT INFANT INTERNAL EXPOSURE LOCATION AND PATHWAY BODY SKIN LUNG BONE THYRotD THYRotD ORGANS l
k GAROEM (NNW SECTOR AT 1000. METERS) i
- =.--------------
AIR IMHALATION 1.87E-03 1.87E-03 1.87E-03 1.87E-03 2.02E-03 1.14C-03 1.87E-03 i
EXPOSURE TO Soll 1.09E-06 1.3?E-06 1.09E-06 1.09E-06 1.09E-06 1.09E-06 1.09E-06 LEAFY VEGETABLE CONSUMPTION 5.2SE-04 5.25E-04 5.2SE-04 5.27E-04 1.66E-03 0.00C+00 5.27E-04 PRODUCE CONSUMPTION 2.83E-03 2.83E-03 2.83E-03 2.84E-03 2.87E-03 0.00E+00' 2.03E-03 TOTAL 5.23E-03 5.23E-03 5.23E-03 5.24E-03 6.55E-03 1.14E-03 5.23E-03 MEAT ANIMAL (SSW SECTOR AT 1600. METERS)
AIR INHALATION 7.61E-04 7.61E-04 7.61E-04 7.61E-04 0.20E-04 4.63C-04 7.61E-04 EXPOSURE TO SOIL 5.55E-07 6.74E-07 5.55E-07 5.55E-07 5.55E-07 5.55E-07 5.55E-07 i
LEAFY VEGETA8LE CONSUMPTION 2.19E-04 2.19E-04 2.19E-04 2.20E-04 7.97E-04 0.00E+00 2.19E-04 PRODUCE CONSUMPTION 1.18E-03 1.18E-03 1.18E-03 1.180-03 1.20E-03 0.00E+00 1.18E-03 MEAT CONSUMPTION 2.2hE-04 2.24E-04 2.24E-04 2.24E-04 2.63C-04 0.00E+00 2.24E-04 i
TOTAL 2.38E-03 2.38E-03 2.38E-03 2.39E-03 3.08E-03 4.64E-04 2.38E-03 i
MILM COW (SOUTH SECTOR AT 8000. METERS)
AIR INHALATION 1.31E-04 1.31E-04 1.31E-04 1.31E-04 1.42E-04 8.11E-05 1.31E-04 EXPOSURE TO SOlt 9.84E-08 1.19E-07 9.84E-08 9.84E-08 9.84E-08 9.84E-08 9.84E-08 LEAFY VEGETABLE CollSUMPTION 4.42E-05 4.42E-05 4.42E-05 4.44E-05 1.47E-04 0.00E+00 4.44E-05 PRODUCE CONSUMPTION 2.39E-04 2.39E-04 2.39E-04 2.39E-04 2.42E-04 0.00E+00 2.39E-04 MEAT CONSUMPTION 4.53E-05 4.53E-05 4.53E-05 4.53E-05 5.23E-05 0.00E+00 4.53E-05 COW MILK CONSUMPTION 1.07E-04 1.07E-04 1.07E-04 1.07E-04 2.99E-04 1.79E-03 1.07E-04 TOTAL' 5.67E-04 5.67E-04 5.67E-04 5.67E-04 8.82E-04 1.87E-03 5.67E-04 l
MILM COAT (SSW SECTOR AT 4200. METERS)
AIR INNALATION 1.68E-04 1.68E-04 1.68E-04 1.68E-04 1.82E-04 1.03E-04 1.68E-04 EXPOSURE TO Soll 1.05E-07 1.28E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 LEAFY VECETABLE CONSUMPTION 5.25E-05 5.25E-05 5.25E-05 5.27E-05 1.62E-04 0.00E+00 5.27E-05 PRODUCE CONSUMPTION 2.83E-04 2.83E-04 2.83E-04 2.84E 2.87E-04 0.00E+00 2.83E-04 MEAT CostSUMPTION 5.38E-05 5.38E-05 5.38E-05 5.38E-05 6.12E-05 0.00E+00 5.38E-05 GOAT MILK CONSUMPTION 2.59E-04 2.59E-04 2.59E-04 2.59E-04 5.05E-04 2.68E-01 2.59E-04 TOTAL 8.17E-04 8.17E-04 8.17E-04
- 4.18E-04 1.20E-03 2.78E-03 8.17E-04
-L
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TABLE 1.B-30
- 3 QUARTER 1989 8ATCH + CONTif000US RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLUDING fe0BLE GASES} AT MAXlMUM orFSITE EXPOSURE LOCATIONS (fmEM)
_.--- -- --- -- _=...-
OTHER TOTAL ADULT INFANY INTERfeAL EXPOSURE LOCATION AND PATHWAY 800Y SKIN LUNG 8088E THVROID THYRotD ORGANS
====._
.. _ - - - =
CARDEN MAXIMUM LOCATION
......... - - =.
AIR IIGHALATION 1.98E-03 1.98E-03 1.98E-03 1.98E-03 2.20E-03 1.29E-03 1.98E-03 EXPOSURE TO Soll 1.70E-06 2.06E-06 1.70E-06 1.70E-06 1.70E 1.70E-06 1.70E-06 LEAFY VEGETABLE CONSUMPTION 5.56E-04 5.560-04 5.56E-04 5.59E-04 2.33E-03 0.00E*00 3.59E-04 PRODUCE CONSUMPTION 2.99E-03 2.99E-03 2.99E-03 3.00E-03 3.05E-03 0.00E+00 2.99E-03 TOTAL 5.53E-03 5.53E-03 5.53E-03 5.54E-03 7.59E-03 1.29E-03 5.53E-03 MEAT ANIMAL MAXlMUM LOCATION
__=---
AIR INHALATION 7.95E-Oa 7.95E-04 7.95E-04 7.95E-04 8.79E-04 5.11E-04 7.95E-04 EXPOSURE TO Soll 7.89E-07 9.58E-07 7.89E-07 7.89E-07 7.89E-07 7.89E-07 7.8?E-07 LEAFY VEGETABLE CONSUMPTION 2.29E-04 2.29E-04 2.29E-04 2.30E-04 1.05E-03 0.00E+00 2.29E-04 PRODUCE CONSUMPTION 1.23E-03 1.23E-03 1.23E-03 1.23E-03 1.26E-03 0.00E+00 1.23E-03 yo MEAT CONSUMPTIOff 2.34E-04
- 2. 34E-Ols 2.34E-04 2.3a:E-04 2.90E-04 0.00E+00 2.34E-04 TOTAL 2.49E-03 2.a9E-03 2.49E-03 2.50E-03 3.48E-03 5.12E-04 2.4?E-03 MILK COW MAXIMUM LOCATION AIR litHALATION 1.38E-04 1.38E-Gas 1.38E-04 1.38E-04s 1.54E-04 9.13E-05 1.38E-0s:
EXPOSURE TO SOIL 1.44E-07 1.74E-07 1.44E-07 1.hteE-07 1.44E-07 1.44E-07 1.htsE-0 T LEAFY VEGETABLE C088SUMPTION 4.66E-05 4.66E-05 as.66E-05 4.68E-05 1.97E-04 0.00E+00 4.68E-05 PRODUCE CostSUMPTIOtt 2.51E-04 2.51E-04s 2.51E-04s 2.51E-04 2.56E-04 0.00E*00 2.51E-04 MEAT C08tSUMPTION 4.77E-05 4.77E-05 Es.77E-05 4.77E-05 5.79E-05 0.00E+00 4.77E-05 COW MILK COWSUMPTION 1.13E-04 1.13E-04 1.13E-04 1.13E-04 3.94E-04 2.48E-03 1.13E-04 TOTAL 5.97E-04 5.97E-04 5.97E-04 5.97E-04 1.06E-03 2.58E-03 5.97E-04 MILK GOAT MAXIMUM LOCAT104 i
....-==.
AIR IleHALATIces 1.75E-04 1.75E-04 1.75E-Oes 1.75E-04 1.94E-04 1.13E-04 1.75E-04 EXPOSURE TO Soft 1.51E-07 1.83E-07 1.51E-07 1.51E-07 1.51E-07 1.51E-0 7 1.51E-0T LEAFY VEGETABLE C08tSUMPTION 5.49E-05 5.49E-05 5.49E-05 5.51E-05
-2.12E-04 0.00E+00 5.51E-05 PRODUCE CoelSUMPTION 2.96E-04 2.96E-04 2.96E-04 2.97E-04
3.0 1E-08
0.00E+00 2.96E-04 MEAT C08tSUMPTlost 5.62E-05 5.62E-05 5.62E-05 5.62E-05 6.68E-05 0.00E+00 5.62E-05 GOAT MILK CostSUMPTION 2.71E-04 2.71E-04 2.71E-Oes 2.71E-04 6.23E-04 3.53E-03 2.71E-04 TOTAL 8.53E-04 8.53E-04 8.53E-Oes 8.54E-04 1.le0E-03 3.64E-03 8.53E-04:
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I Table 1.B-33
- l FOURTH QUARTER 1989 POPULATION DOSE (50-MILE) FROM LIQ'JID EFFLUENTS (MAN-REM)
EXPOSURE ?ATHWAY TOTAL BODY-
-THYROID AQUATIC DRINKING WATER 6.7E-05 7.1E-05 FISH CONSUMPTION
.1.9E-03 2.OE-03 1NVERTEBRATE CONSUMPTION 5.5E-06 5.5E-06 EXPOSURE TO CONTAMINATED SEDIMENT 3.3E 5.3E-06I U
SWifMING AND BOATING
-3.6E-08 3.6E-08 IRRIGATION AND Ll";ESTOCK WATERING
. l.EAFY VEGETABLE-CONSUMPTION 1.70-07
.2.2E-07 PRODUCE CONSUMPTION' 8.6E-07 8.6E-07"-
MEAT CONSUMPTION 4.5E-06 4.6E-06 MILK CONSUMPTION.
3.9E-05 4.7E-05 EXPOSURE TO CONTAMINATED SOIL 4.5E-07 :.
4.5E-07 TOTAL 2.OE-03 2.2E-03 AVERAGE DOSE - (MPUt; PERSON) 9.8E-07 1.1E-06 m
w.,,
g mes.4h-e-w++C'"
-4/
W-'l%'
- f
- '"Y'*
Y
Table 1.E-34 FOURTH QUARTER 1989 BATCH RELEASES DOSES FROH NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF
-HIGHEST CONCENTRATION Site Boundaryl*l.
Resideneelb)
Beta Air Dose (mrad) 2.0E-3 1.1E-3
~ l' Gamma Air Dose (mrad) 1.3E-3 5.2E-4 l
Beta + Ganna Skin-Dose (mram) 1.0E-3 Gamma Total Body Dose (mram) 4.7E-4 (a) NNW sector at 674 meters.
[b] NNW sector at 1000 meters.-
e 3
i I
I
' l O
4 74
Table l'. E-3 5 FOURTH QUARTER 1989 CONTINUOUS RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundaryla)
Residence [b]
Beta Air Dose (mrad) 1.6E-2 8.5E-3 a
Gamma Air Dose (mrad)
- 5. 4 E 2.0E-3.
Beta + Gamma-Skin Dose (mram) 4.7E -
Gamma Total Body Dose-(mram) 1.7E-3
[a] North sector at 663 meters.
lb) North sector at 1000 meters.
l
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[
l
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l 1
1 i
a i
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b I
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i Table 1.B-36 FOURTH QUARTER 1989 BATCH + CONTINUOUS RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND' RESIDENCE OF HIGHEST CONCENTRATION ~
Site 4
Boundary [a]
ResidenceIDI i
Beta Air Dose (mrad) 1.BE-2 9.6E-3
.. l Gamma Air Dose (mrad) 6.8E-3 2.5E-3 Beta + Gamma Skin Dose (mram) 5.8E-3 Gamma Total Body Dose (mram)-
2.2E-3
)
la) Maximum site boundary location.
(b) Maximum residence location.
l u
l 1
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3 3
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Table 1.B-37
- 4 QUARTER 1989 8ATCH RELEASES 00$ES FROM GASEOUS EFFLUENTS (EXCLU0lleG N08LE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM)
OTHER TOTAL AOULT INFANT INTERNAL EXPOSURE LOCATION AND PATWAY BODY SKIM LUNG BONE THYROID THYR 010 ORGANS
. I CARDEN
. l (NW SECTOR AT 1000. METERS)
AIR INHALATION 2.57E-07 2.57E-07 2.57E-07 2.57E-07 7.22E-07 7.11E-07 2.58E-07 EXPOSURE TO Soll 4.55E-09 5.52E-09 4.55E-09 4.55E 4.55E-09 4.55E-09 4.55E-09 LEAFY VECETA8LE CONSUMPTION 7.99E-08 7.99E-08 7.99E-08 8.17E-08 4.81E-06 0.00E+00 8.61E-06 PRODUCE CONSUMPTION 3.88E-07 3.88E-07 3.88E-07 3.88E-07 5.46E-07 0.00E+00 3.88E-07 TOTAL 7.29E-07 7.30E-07 7.29E-07 7.31E-07 6.09E-06 7.16E-07 7.36E-07 MEAT ANIMAL (W SECTOR AT -1900. METERS)
AIR IMHALATION 1.03E-07 1.03E-07 1.03E-07 1.03E-07 2.93E-07 2.90E-07 1.03E-07 EXPOSURE TO Soll 8.56E-10 1.04E-09 8.56E-10 8.56E-10 8.56E-10 8.56E-10 8.56E-10 d
LEAFY VEGETA8LE CONSUMPTION 3.13E-08
'3.13E-08 3.13E-08 3.16E-08 9.23E-07 0.00E+00 3.24E-08 PRODUCE CONSUMPTION 1.61E-07 1.61E-07 1.61E-07 1.61E-07 1.91E-07 0.00E+00 1.61E-07 MEAT CONSUMPTION 3.07E-08 3.07E-08 3.07E-08 3.07E-08 9.13E-08 0.00E+00 3.07E-08
(.
TOTAL 3.27E-07 3.27E-07 3.27E-07 3.27E-07 1.50E-06 2.91E-07 3.28E-07 MILK COW (NW SECTOR AT 8000. METERS)
AIR IMHALATION 9.29E-09 9.29E-09 9.29E-09 9.30E-09 2.79E-08 2.79E-08 9.32E-09' i
EXPOSURE TO Soll'
'1.12E.1.36E-10 1.12E-10 1.12E-10 1.12E-10 1.12E-10 1.12E-10 LEAFY VEGETA8tE CONSUMPTION 3.31E-09
-3.31E-09 3.31E-09 3.36E-09 1.20E-07' O.00E+00 3.46E-09 i
PRODUCE CONSUMPTION
~1.68E-08 1.68E-08 1.68E-08 1.68E-08 2.07E-08 0.00E+00 1.68E-06 l
MEAT CONSUMPTION 3.21E-09 3.21E-09 3.21E-09 3.21E-09 1.12E-08 0.00E+00 3.22E-09 i-COW MILK CONSUMPTION-
'7.91E-09
- 7.91E-09 7.91E-09 i7.99E-09 2.27E-07 1.69E-06 8.19E-09 l
j TOTAL 4.07E-08 4.07E-08 4.07E-08 4.08E-08
.4.07E-07 1.72E-06l 4.11E-08 i
MILK GOAT (N W SECTOR AT 8000. METERS)
AIR INHALATION 9.29E-09 9.29E-09 9.29E-09 9.30E-09 2.79E-08 2.79E-08 9.320-09 I
EXPOSURE'TO Soll
-1.12E-10 1.36E-10 1.12E-10 1.12E-10
- 1.12E-10 1.12E-10
.1.12E-10 i
LEAFY VECETABLE CONSUMPTION 3.31E-09 3.31E-09 3.31E-09 3.36E-09 1.20E-07 0.00E+00 3.46E-09 PRODUCE CONSUMPTION 1.68E-08 1.68E-08 1.68E-08.
1.68E-06 2.07E-08 0.00E+00 1.68E-08 MEAT CONSUMPTION 3.21E-09 13.21E 3.21E-09 3.21E-09' 1.12E-08 0.00E+00 3.22E-09 J
GOAT MILK CONSUMPTION 1.58E-08 1.58E 1.58E-08' 1.59E-08 2.79E-07 2.05E-06 1.61E-08
~
TOTAL 4.86E-08 4.86E-08
'4.86E-08
" 4.87E-08 4.59E-07
-2.07E-06 4.91E-06
,m
, _~<.
.-,.am._
A,
...m,.
m m
m Table 1.B-38
- 4 QUARTER 1989 CONTINUOUS RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLUDING le0BLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIOplS (MREM)
..-=__ =___-_.-
==.....................--...............-....
OTHER TOTAL ADULT INFANT INTERNAL EXPOSURE LOCATION AND PATHWAY 800Y SKIN LUNG BOttE THYROID THYROID
. ORGANS GARDEN (NNW SECTOR AT 1000. METERS)
~
2.60E-03 AIR IMHALATION 2.60E-03 2.60E-03 2.60E-03 2.60E-03 2.66E-03 1.41E-03 EXPOSURE TO Soll 5.69E-07 6.91E-07 5.69E-07 5.69E-07 5.69E-07 5.69E-07 5.69E-07 LEAFY VEGETABLE CONSUMPTION 7.27E-04 7.27E-04 7.27E 7.28E-04 1.32E-03 0.00E+00 7.28E-04 PRODUCE CONSUMPTION 3.93E-03 3.93E-03 3.93E-03 3.94E-03.
3.95E-03 0.00E+00 3.93E-03 TOTAL 7.25E-03 7.25E-03 7.25E-03 7.26E-03 7.93E-03 1.41E-03 7.25E-03 MEAT ANIMAL (NW SECTOR AT 1900. METERS)
"~"^
"j~R" bTb
-7.23E-04 7.23E-04
'7.23E-04 7.23E-04 7.42E-04 3.94E-04
-7.23E-04 EXPOSURE TO Soll.
1.09E-07 1.32E-07 1.09E-07 1.09E-07 1.09E-07 1.09E-07 1.09E-07 LEAFY VECETABLE CONSUMPTION 2.09E-04 2.09E 2.00E-04 2.10E 04 3.22E-04 0.00E+00 2.09E PRODUCE CONSUMPTION 1.13E-03 1.13E-03 1.13E-03 1.13E-03 1.14E-03 0.00E+00 1.13E-03 ym MEAT CONSUMPTION 2.15E-04 2.15E-04 2.15E-04 2.15E-04 2.23E-04 0.00E+00 2.15E-04 i
TOTAL 2.28E-03
'2.28E-03 2.28E-03 2.28E-03 2.42E-03 3.94E-04 2.28E-03
-l MILK COW (NORTH SECTOR AT 8000. METERS)
AIR INHALATION 1.32E-04 1.32E 1.32E-04
~1.32E-04 1.36E-04 7.22E-05 1.32E-0:
EXPOSURE TO Soll 1.45E-08 1.76E-08
- 1. 2:5E-08
- 1. t:5E-08 1.45E-08 1.45E-08 1.45E-08
'l LEAFY VEGETABLE CONSUMPTION 4.t3E-05 4.43E-05 Is.t:3E-05 is.t:3E-05 5.94E-05 0.00E+00 Is. t:3E-05 PR000CE CONSUMPTION
- 2.40E-Ots 2.40E-Ois 2.t:0E-Ots 2.t:0E-Ota -
2.tsOE-Ots 0.00E+00 2.t:0E-04 MEAT CONSUMPTION-
~4.55E-05 88.55E-05 4.55E-05 ft.55E 4.65E-05 0.00E+00
.Is.55E-05 i
COW MILK CONSUMPTION 1.07E-04 1.07E-Ott
- 1.07E-Ols.
1.07E-Ott 1.35E 5.50E-04 1.07E-04
-l TOTAL 5.69E-04
-5.69E-04 5.69E-04 5.69E-04 6.17E-04 6.22E-04 5.69E-04 MILK COAT'
-(NORTH SECTOR AT 8000. METERS)
...... _ _ = _ -...
AIR IMHALATION 1.32E-01:
- 1. 32E-Ots 1.32E-04 1.32E-Ott 1.36E-04 7.22E-05 1.32E-04 EXPOSURE TO SOIL 1.45E-08 1.76E-08 1.45E-08
'1.45E-08 1.45E-08 1.45E-08
- 1. t:5E.08 LEAFY VEGETA8LE CoelSUMPTION 4.t:3E-05 ts.43E-05.
4.8s3E-05 ts.es3E-05 5.94E-05 0.00E+00 ts.8s3E-05 PRODUCE CONSUMPTION 2.40E-04 2.40E-04 2.40E-04 2.40E-04 2.40E-04 0.00E+00 2.40E-04~
MEAT CONSUMPTION 4.55E-05 4.55E-05
.Es.55E-05 4.55E-05 es.65E 0.00E+00 ts.55E-05
-GOAT MILK C00lSUMPTIO91-2.19E-Ois 2.19E-04 2.19E-04 2.19E-04 2.53E-04 9.41E-04 2.19E-04
' TOTAL 6.80E-04 6.80E-Ois 6.80E-04 6.81E-04 7.35E 1.01E-03 6.80E-Oli
Table 1.B-39
- 4 QUARTER 1989 BATCH + CONTINUOUS RELEASES DOSES FROM CASEOUS EFFLUENTS (EXCLUDIf0C NOBLE CASES) AT PAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM)
-- =-............=_
OTHER TOTAL AOULT INFANT INTERNAL EXPOSURE LOCATION AND PATHWAY BODY SKIN LUNG BONE
. THYR 010 TMYROID ORGAMS
....... - - - - - - - - - - _=.--..
=
CARDEN MAX 1 MUM LOCATION AIR IMHALATION 2.60E-03 2.60E-03 2.60E-03 2.60E-03 2.66E-03 1.41E-03 2.60E-03 EXPOSURE TO Solt 5.74E-07 6.97E-07 5.74E-07 5.74E-07 5.74E-07 5.74E-07 5.74E-07 LEAFY VEGETABLE CONSUMPTION 7.27E-04 7.27E-04 7.27E-04 7.28E-04 1.32E-03 0.00E+00
-7.28E-04 PRODUCE CONSUMPTION 3.93E-03 3.93E-03 3.93E-03 3.94E-03 3.95E-03 0.00E+00 3.93E-03 TOTAL 7.25E-03 7.25E-03 7.25E-03 7.26E-03 7.94E-03 1.41E-03 7.25E-03 MEAT ANIMAL MAX 1 MUM LOCATION
-.............. - _ _ - -. = -
AIR INHALATION.
7.23E-04 7.23E-04 7.23E-04 7.23E-04 7.42E-04 3.94E-04 7.23E-04 EXPOSURE TO Soll 1.10E-07 1.33E-07 1.10E-07 1.10E-07 1.10E 1.10E-07 1.10E-07 y
LEAFY VECETABLE CONSUMPTION 2.09E-04 2.09E-04 2.09E-04 2.10E-04 3.23E-04 0.00E+00 2.09E PRODUCE CONSUMFTION 1.13E-03 1.13E-03 1.13E-03 1.13E-03 1.14E 0.00E+00 1.13E-03 MEAT CONSUMPTION
. 2.15E-04 2.15E-04
'2.15E-04 2.15E-04 2.23E-04 0.00E+00 2.15E-04 TOTAL 2.28E-03 2.28E-03 2.28E-03 2.28E-03 2.42E-03 3.94E 2.28E-03 MILK COW MAXIMUM LOCATION AIR IMHALATION 1.32E-04 1.32E-04 1.32E-04
- 1.32E-04 1.36E-04 7.22E-05 1.32E-04 EXPOSURE TO Soft 1.46E-08 1.77E 1.46E-08 1.46E-08 1.46E-08 1.46E-08 1.46E-08 LEAFY VECETABLE CONSUMPTION 4.43E-05 4.43E-05 4.43E-05 4.43E-05 5.95E-05 0.00E+00 4.a3E-05 PRODUCE COftSUMPTION 2.40E-04 2.40E 2.40E-04 2.40E-04 2.40E-04 0.00E+00 2.40E-04 MEAT CONSUMPTION 4.55E-05
-4.55E 4.55E-05 4.53E-05 4.65E-05 0.00E+00 4.55E-05 COW MtLK CONSUMPTION 1.07E-04 1.07E-04 1.07E-Oes 1.07E-04 1.35E-04 5.52E-04 1.07E-04 TOTAL 5.69E-04 5.69E-04 5.69E-04 5.69E-04 6.17E-04 6.24E-04 5.69E-04 MILM COAT-MAX 1 MUM LOCATION AIR INHALATION 1.32E-04 1.32E 1.32E-04 1.32E-04 1.36E-04 7.22E-05 1.32E-04 EXPOSURE'TO Soll 1.46E-08 1.77E-08 1.46E-08 1.46E-08 1.46E-08 1.46E.1.46E-08 LEAFY YEGETABLE CONSUMPTION 4.43E-05 4.43E-05 4.43E-05 4.43E-05 5.95E-05 0.00E+00 4.43E-05 PRODUCE CONSUMPTION 2.40E-04 2.40E-04 2.40E-04 2.40E-04 2.40E-04 0.00E+00 2.40E-04 MEAT CONSUMPTION
- 4.55E-05 4.55E-05 4.55E-05 4.55E-05 4.65E-05 0.00E+00.
4.55E-05 GOAT MILK CONSUMPTION.
2.19E-04 2.19E-04 2.19E-04
- 2.1$2-04 2.53E-04
.9.43E-04 2.19E-04 TOTAL 6.80E-04 6.80E-04 6.80E-04 6.81E 7.35E-04
.1.01E-03 6.80E-04
.,n~_--
-...eY a ----..A----
=;=-a.--------
i l
l Table 1.B-40 l
FOURTH QUARTER 1969 BATCH + CONTaft000S RELEASES 1
1 1
FOPULATION DOSE (50-MILE) FROM CASEOUS EFFLUENTS (MAN-REM)
- - =.
_ =
_.-----------..------------.==--
EXPOSURE PATHWAY TOTAL BODY THYROID
- - - - - - - - - -. - - -. - - - - = _ - -
-=_
-==-
AIR SUBMERSION 5.1E-03 5.1E-03 A1R~lOfMALATION-
'9.9E-03 1.OE-02 i
EXPOSURE TO Soll 9.OE 9.0E-07 LEAFY VEGETABLE CONSUMPT1ON 7.9E-05
'1.1E-04 PRODUCE CONSUMPflON 4.3E-04 4.3E-04 MEAT CONSUMPTION 6.4E-04 6.5E-04 MILK COftSUMPTION 6.3E-03~
8.5E-03.
TOTAL 2.2E-02 2.5E-02 AVERACE DOSE (pmEM/ PERSON) 1.1E-05 1.2E-05
--- - = = - - -.. - -.. = = - = - - -... - -....... - -........ - -.. - - - - _ = -
i 9
9 9
=
I
/
l-1.C METROROLOGICAL DATA Meteorological data for 1989 are available for-review in the pCE Corporate Office as per Technical Specification 6.9.1.5.4. " Semiannual Radioactive Effluent Release Report". Meteorological models and assumptions used in performing the analyses are presented-in'PGE-1021. "Offsite Dose Calcula--
tion Manual".
O O
81
3.D CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)
,ecui,ement Trojan Facility Operating License.NPF-1, Appendix A. Technical Specification 6.15.2.A for changes to the ODCM requires:
"6.15.2.A Licensee initiated changes:
"1.
Shall be submitted'to the commission by inclusion in the Semiannual Effluent Release Report for the period in which the change (s) was made and shall contain:-
"a.
sufficiently_ detailed information-to totally.
support the rationale for the change without__
i benefit of additional or supplemental informa :
i tion.
Information submitted should consist of a package of those pages.of the ODCM_to be changed with each page numbered and provided with an-
.(
approval and date box, together with appropriate' analyses or evaluations justifying the change (s);
"b.
a determination that the change will not reduce the accuracy or_ reliability of dose calculations or setpoint determinations; and "c.
documentation of the fact that'the change has been reviewed and found acceptable by the PRB."
Report j
In 1989, there were no changes-to the ODCM.
4 O
t 82
-!o 6
i l
1.E REACTOR COOLANT SYSTEM (RCS) SPECIFIC ACTIVITY l\\
j Re.uirement Trojan Facility Operating License NPF-1. Appendix A, Technical' specification 6.9.1.5.d, " Annual Reports", states:
-j Reports required'on an annual basis shall include:
~
"The results of specific activity analysis in which the primary' coolant exceeded the. limits of specification'3.4.8. Tho' following information shall'be included:
(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to the first sample in which the limitJ
]
l was exceeded; (2) Results of-the last; isotopic analysisifor radioiodine performed prior.to exceeding the limit, results of analysis while limit was exceeded and results of one analysis ~-
)
after the radioiodine activity was reduced to less than limit.-
'T Rach result should include date and time of-' sampling.and-the radiolodine concentrations; (3) Clean-up system flow history.
starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the-limit:
was exceeded; (4) Graph of the I-131 concentration and one.
4 I
other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration When-the specific activity of.the primary coolant -exceeded the radiciodine limit."
Technical Specification 3.4.8,." Reactor Coolant System Specific-a Activity Limiting Condition for Operation",-requires:
i "The specific activity of the primary coolant shall be limited to:
I
- a.
1 1.0 pC1/ gram DOSE EQUIVALENT I-131, and "b.
1 100/E pCi/ gram."
pp ort During 1989, the Reactor Coolant System specific. activity'did not' exceed,
-the limits of Specification 3.4.8.
i i
J
]
4 4
- u i
'l 83
~.
s t
2.
ANNUAL PERSONNEL EXPOSURE AND MONITORING REPORT j
Requirement l
l Trojan Facility Operating License NPF-1, Appendix A. Technical Specif1-cation 6.9.1.5 states:
" Reports required on an annual basis shall include:
"a.
A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mesm/yr and their associated man-rem exposure according to work and job functions, e.g., reactor operations and surveillance,.
inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and.
refueling.
The dose assessment to various duty functions may be estimates based on pocket, dosimeter, TLD ' or film badge measurements.- Small exposures totaling less than'20%
of the individual total. dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose.
received from external sources: shall be assigned to specific major work functions."
c Report O-Table 2-1 lists the number of workers receiving exposures greater than 100 mrem per year and the - total exposures' by work and. job function ~ for the year 1989.
Special maintenance in 1989 consisted of fuel reconstitution / repair and electrical penetration testing and repair.
Requirement i
l 10 CFR 20.407(b) requires:
"A statistical summary report of the personnelLaonitoring information
~
recorded by.the licensee for= individuals.for.whom personnel' i
monitoring was either required or provided.
-. indicating the number of individuals whose total whole body' exposure recorded during the previous calendar year was...(in various exposure ranges)."-
Reoort Table 2-2 is the statistical report of radiation exposure required by
[
10 CFR 20.407(b) for the year 1989.
i lO s
4 84
..-w.
e c
e, e
,-,-r
'y
,4 g
.. - ~-..
TABLE 2-1
- Sheet 1 of 2
'{
REPORT'ON NUMBER OF PERSONNEL AND MAN-REMi BY WORK AND JOB FUNCTION j
J 1989 u
Wo. of Personnel (>100 mrom)-
Total Man-Rem-Station Utility-Contract Station Utility- -Contract sI L
- Work and Job Function Employees Employees Workers Employees Employees; Workers i
L REACTOR OPERATIONS & SURVEILLANCE l'
. Maintenance Personnel 3
1 54 1.64-0.19-18.53' Operating Personnel 22 0
0 7.40 0.00 0.00' Chemistry & Radiation 23 0
12 8.03-0.00 L 4.32 ',
Control Personnel Supervisory Personnel 6
2 3
2.06 0.44 1.67.
Engineering Personnel 9
0 2
3.12 0.00 0.52
+
ROUTINE MAINTENANCE & INSERVICE INSPECTION Maintenance Personnel 134 16 289 48.78 6.72 222.09 Operating Personnel 2
0 0
0.62 0.00 0.00-Chemistry & Radiation 40 0
73 21.05 0.00-69.34 Control Personnel 4 -
Supervisory Personnel 12 0
34
'3.77 0.23 12.39 Engineering Personnel 1
-0 25 0.97 0.00.
11.78~
SPECIAL MAINTENANCE 4
Maintenance Personnel 0
0 0-0.01 0.00 0.02 i
Operating Personnel 0
0 0
o0.01.
0.00
- 0.00 Chemistry & Radiation 0
0 0
0.12-0.00 0.03 i
Control Personnel Supervisory Personnel
'O O
O' O.00 0.00 0.00 Engineering Personnel 0
0 0
'O.02 0.00 0.36 WASTE PROCESSING Maintenance Personnel 0
0 4
0.09 0.00 1.14 Operating Personnel 0
0 0
0.66-0.00
'O.00'
{-
Chemistry & Radiation 35 0
'6 14.89 0.00 l'. 83 -
Control Personnel Supervisory Personnel 0
0 0
'O.13 0.00 3.05 Engineering Personnel 0
0 0
0.00 0.00 C.00 85
/
i i
\\
l TABLE 2-1 Sheet 2 of 2
.)
l No. of Personnel (>100 mram)
Total Man-Rem Station Utility Contract Station Utility Contract
~
Work and Job Function Employees Employees Workers Employees Employees-Workers REFUELING 1
Maintenance Personnel 8
0 60 4.15 0.12 L46.80
'l Operating Personnel
~ 2 0-0 1.05 0.00
'O.00 Chemistry & Radiation 10 0
17 3.96-0.00 10.84 j
Control Personnel l
Supervisory Personnel 9
0 13 1.86 0.07 5.41 Engineering Personnel 2
0 5
0.99' O.00 1.10 TOTAL M2intenance Personnel 117 13 359 42.06 5.74 227.23 Operating Personnel 22 0
0 7.23 0.00 0.00 Chemistry & Radiation 72 0
91 37.78 0.00 65.37 Control Personnel Supervisory Personnel 19 2
38 5.03 0.56 15.36 Engineering Personnel 11 0
28 3.29 0.01 11.05 GRAND TOTAL 241 15 516
-95.39' 6.31 319.02 O
.1 86
TABLE 2-2 TROJAN PLANT WHOLE BODY EXPOSURE (REM) 1989 Number'of People With No Exposure = 992 Exposure of at Least 0.001 and Less Than 0.099 Number of People = 559 Exposure of at Least 0.100 and Less Than 0.249 Number of People = 294 Exposure of at Least 'O.250 and Less Than 0.499 Number of People = 214 Exposure of at Least- 0.500 and Less Than 0.749 Number of People = 106 Exposure of at Least 0.750 and L'ss Than 0.999 Number of People =- 73 e
Exposure of at Least 1.000 and'Less Than 1.999 Number of People = 107 Exposure of at Least 2.000 and Less Than 2.999 Number of People =
7' Exposure of at Least 3.000 and Less Than 3.999-Number of People.=
0 Exposure of at Least 4.000 and Less Than 4.999 Number of People =-
0.
Exposure of at Least 5.000 and Less Than 5.999 Number of People =
0 Exposure of at Least 6.000 and Less Than 6.999 Number of People.=
0 Exposure of at Least 7.000 and Less Than 7.999 Number.of People =
0 Exposure of at Least 8.000 and Less Than 8.999 Number.of People =
0 Exposure of at Least 9.000 and Less Than' 9.999 Number of People..=
0 Exposure of at Least 10.000 and Less Than 10.999 Number of People =
0 Exposure of at Least 11.000 and Less Than 11.999 Number of People =
0 Exposure of at Least 12.000 and Less Than 100.999 Number of People =
0.
Total Plant Exposure = 420.715 man-rem O
87
' l l
i 3.
STEAM CENERATOR TUBE INSPECTIONS
- O i
Requirement 1
4 Trojan Facility Operating License NPF-1, Appendix A. Technical Specification 6.9.1.5, " Annual Reports", states:
i Reports required on an annual basis shall include:
b'.
The complete results of steam generator tube inservice l
inspections performed during the report period (reference Specification 4.4.5.5.b).
Technical Specification 4.4.5.5.b.,
"Survr,111ance Requirements, Steam
+
Generator Tube' Sample Selection and Inspection", requires:
The complete result's of.the steam generator-tube inservice inspection shall be reported on an annual basis for the period in which the inspection was completed. This report shall include:
(1) Number and extent of tubes inspected.
(2) Location and percent of well-thickness penetration for'esch indication of an imperfection.
(3)
Identification of tubes plugged.
Report 1.
Pror. ram Summary The 1989 steam generator tube inspection program consisted of the following:
j
~
MIZ-18/SM-10 multifrequency eddy-current examination of all a.
active tubes in Steam Generators A, B, C,-and D throughout their full lengths utilizing standard bobbin coil techniques.
i-a b.
Motorized rotating pancake coil (MRPC) techniques' utilized to further diagnose the bobbin coil reported'indicetions.
c.
The steam generator tube inspection' program was expanded to j
examine all active tubes utilizing the 8x1 probe and/or.MRPC probe techniques at the hotles upper tubesheet interface, following discovery of apparent inside diameter initiated circumferential indications. A corr. elation between the 8x1 and MRPC techniques was performed with the MRPC techniques providing more confidence in detection.
.f*
d.
Eighty-two (82) Westinghouse mechanical tube plugs of Heat NX3962
(
had plus retaining devices installed of the Babcock & Wilcox plug-a-plug (PAP) design.
88 s
e.
Two (2) Babcock & Wilcox rolled tube' plugs of Heat W 592-1 were removed and replaced with rolled j1ugs of a more desirable heat in Steam Generator
'C', Tube Row 2, Column 57.
2.
Results a.
Table 3.1 provides the number of-tubes inspected, the number of tube examination techniques, the number of tube indications plugged, the number of stabilizers installed', the number of PAPS-installed, and the number of tubes plugged-in each steam generator, b.
Tables 3.2 through 3.5 provide the location and percent of wal1~
thickness penetration for.quantifiable indications and the total' -
number of indications for each steam generator examination
- results, c.
Table 3.6 is a listing of tubes plugged and the basis'for plugging as a result of the July-1989 steam generator inspection prograr..
d.
Figures 3.1 through 3.4 show the plugging patterns in each steam generator at the conclusion of the July.1989 outage, Figures 3.5 through 3.7 show the Babcock & Wilcox PAP patterns in e.
each steam generator at the conclusion of_the' July 1989' outage, f.
Eight (8) stabilizers were installed in the steam generators at the upper tubesheet interface as a result of_ Westinghouse analysis and Trojan Nuclear Plant engineering evaluations of the apparent inside diameter initiated circumferential indications.
Figures 3.8 through-3.10 show the stabilizer patterns in each steam generator at the conclusion of.the July 1989 outage.
3.
Classification The overall Inservice Inspection (ISI) classification for the Trojan Nuclear Plant steam generators is Category C-2 based:on Paragraph 4.4.5.2 of the Technical Specifications: one,or-more tubes, but not more than 1 percent of the total tubes inspected are defective or between 5 percent and 10 percent of_the total tubes inspected are degraded tubes.
The individual Steam Generator (S/G)-Inservice Inspection (ISI) classification for the Trojan Nuclear Plant is as follows:
'A' is Category C-1 Steam Generator
'B' is Category C-1 Steam Generator
'C' is Category C-2 Steam Generator
'D' is Category C-2 89 3
O Classification Categories C-1 and C-2 are based on Paragraph 4.4.5.2 of the Technical Specifications:
~
C-1 Less than 5 percent of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
C-2 One or more tubes, but not more then-1 percent of the total tubes inspected are defective, or between 5 percent and~
10 percent of the total tubes inspected are degraded tubes.
t.
A e
O t
I O
90
T
- \\
.i i.
TABLE 3.
-l
SUMMARY
OF RESULTS JULY 1989 t
IIgg S/G
'A' S/G
'B'
-S/G
'C' 1/G..'D' IgI&k TUBES INSPECTED:
3260 3293 3275 3252
- 13080-9 l
l TUBE EKAMINATION TECHNIQUES:~
'l
- BOBBIN 3260 3293 3275 3252 13080
- 8K1 NONE 3300 2859 1322 7481'
- MRPC 2190 3420}5 3400 }}il), J 5 TUBE INDICATIONS PLUGCED: l NOTE: Some tubes have multiple indications.. ) - CIRCUMFERENTIAL 1 23 25 7 56 () INDICATIONS ? - AKIAL 12 27 77 85 201 INDICATIONS -1.. - PITTING 0 0 2 0 2- ? STABILIZERS INSTALLED: 1 4 3 0. 8 PAPS INSTALLED: 60 0 20 2 82 PLUGS INSTALLED: - PRE-0UTAGE 128 95 113 136 472-3.8% 2.8%- 3.3% 4.1% 3.5% l - 1989 OUTAGE 13 50 91 91 245 - POST-0UTAGE 141 145 204 227 ,717, TOTALS 4.2% 4.3% 6.0% 6.8% 5'3% () c 1-91 i w s-nm e
l-l (: TABLE 3-2
- j STRAM CENERATOR EKAMINATION RESULTS JULY 1989
.) STRAM CENERATOR 'A' l Total Mot Les Cold Leg-I Records Tubes Records Tubes Records Tubes .I i 1 Quantifiable' Indications Total 87 78 65 60 22 21 >=40% 0 0 0 0 .0 0-20-39% 14 14 10 10 4 4 <20% 73 67 55 50 18 18 q Axial Indications Single 13 11 13 -11 0 0 Multiple 1 1 1 1 0 0 circumferential Indications Single 0 0 0 0 0 0-Multiple 1 1 1 1 0- '0 Nonquantifiable Indications -\\ Dents 255 213 162 143 93 88 Inside i Diameter 3 3 3 3 0 0 Variations Pomeability 333 263 175 139 158 135 Variations Copper Indications Total 1387 818 698 558 689-496' Tubesheet 566 388 348 325 218' 178 j let Support 84 82 28 28 56 56 Plate Other 737 472 322 244' 415 316 e 92
TABLE 3-3 STRAM GENERATOR EKAMINATION RESULTS JULY 1989 STEAM GENERATOR 'B' Total Hot Les Cold Les Records Tubes Records Tubes-Records Tubes Quantifiable Indications Total 79 70 35 33 44 40 >.40% 0 0 0 0 0 0 20-39% 19 17 9 9 10 7 <20% 60 57 26 24 34 34 Axial Indications Single 30 30 30 30 0 0 Multiple 11 11 11 11 0 0 Circumferential Indications Single 20 19~ 20 19 0 0 Multiple 4 4 4 ~4 0- .0 Nonquantifiable Indications Dents 572 422 312 303-260 .159 Inside Diameter 13 13 13 13 5 5 Variations Permeability 140 124 81 73~ 59 52 Variations Copper Indications Total 2886 1886 1535' 1399 '1351 1214 .Tubesheet 2392 1713 1321 1294 1071 1069 let Support 85 74 26 26 59 59 Plate Other 409 346 188 169 -221 189 0 93 l l
i / (. TABLE 3-4 j STEAM GENERATOR EEAMINATION RESULTS l JULY 1989 STEAM GENERATOR 'C' Total. Hot Les Cold Leg-Records Tubes Records Tubes Records Tubes Quantifiable Indications Total 88 74 55 48 33 -29 >=40% 2 2 2 2 0 0 20-39% 16 14 10 9 6 5 <20% 70 60 43 60 27 24 Axial Indications Single 69 66 69 66-0 0 Multiple 46 44 46-44 0 -0 Circumferential Indications i Single 22 22 22 22 .0 0 Multiple 3 3 3 3 0 0 -t \\ Nonquantifiable Indications Dents 55 50-33 30 22 21-I Inside Diameter 16 13 12 12' 4 4 Variations Permeability 105 102 42 42 63 61 Variations Copper Indications Total 2947 1894 1830 1429' "1117 .1074 Tubesheet 2271 1702 1224 1212: 1047 1035. 1st Support 57 55 40 40 -17 17~ l Plate other 619 430 566 393 53 48 1
- 1 O
94
=
- t i
16R1.E 3-5 STEAM GENERATOR EKAMINATION RESULTS JULY 1989 + STEAM GENERATOR 'D' Total .liot Les Cold Leg Records _ Tubop.. _ Records Tubes Records Tubes Quantifiable Indications Total 69 62 55 50 '14 13 >=40% 4 4 4 4 0. 0 20-39% 12 10 10 8 2 2 <20% 53 49 41 39 '12 11 Axial Indications Single 63 60 63 60 0 0 Multiple 25 25 25 25 0 0 circumferential Indications Single-7 7 7 7 0 0 l (} Multiple 0 0 0 0 0 0 I Nonquantifiable Indications Dents 69 63 44 42 25 22 Inside Diameter 7 5 5 5 2 2 l Variations Not Fully 1 1 1 1 0 0 i Expanded Permeability 287 197 177-125 110 78 Variations Copper Indications i Total 976 696 670 573 306 269 H l -Tubesheet 772 598 541 497 231 ~216 L 1st Support 47 40 26 25 21 21 L Plate Other 157 138 103 96 54 49' l 1 i i 95
t TABLS 3-6 Sheet 1 of 3 TUBS PLUGCING LIST JULY 1989 Steam-Tube Count Generator Number Basis and Location (Inches)- 1 A R3/C23 Axial Ind at TSH -1.73' 2 A RS/C62 Axial Ind. at H1' O.0. 3 A R7/C52 Axial Ind. at TSH -2.1 + -3.7 4 A R8/C79 Axial Ind.'at TSH -1.1 5 A R10/C50 Axial Ind. at TSH -1.24 6 A R13/C33' Axial Ind, at-TSH -1.67 _1 7 A R14/C63 Circ. Ind at TSH -0.39 l 8 A R19/C39 Axial Ind. at TSH -2.0 9 A R20/C39 Axial Ind at T6H -4.9 10 A R20/C45 Axial Ind, at.TSH -1.2 + -3.0 11 A R21/C41 Axial Ind. at TSH -0.08-12 A R36/C49 Axial Ind 'at TSH -1.89 13 A R37/C54 Axial Ind. at TSH -1.56 14 B R5/C33-Cire. Ind, at TSH -0.84-15 B R8/C15 Axial Ind. at H1 0.0 16 B R8/C31 Circ. Ind st TSH -0.22-17 B 'R9/C36 Circ. Ind. at TSH -0.49 .3 18 B R9/C37 Circ. Ind.-at TSH -0 65' 19 B R9/C38 Circ. Ind. at TSH -0.73 H 20 B R9/C39 Cire. Ind. at TSH -0.67-21 B R9/041 Circ. Ind. at TSH -0.15'
- )
22 B R9/C42 Cire. Ind at TSH -0.59 j 23 B R9/C71 Axial Ind, at TSH -0.49 24 B R9/C72 Axial.Ind, at TSH -0 21 25 B R10/C23 Axial'Ind, at Hi-0.0 l 26' B R10/C37 Cire. Ind. at TSH -0.54 27 B R10/C38 Cire. Ind, at TSH -0.52 28 B R10/C39 Circ. Ind. at TSH -0.72 29 B R10/C43 -Cire. Ind. at'TSH -0.52 l 30 B R10/C74 Axial Ind at TSH -0.74 ~ t 31 B R11/C4 Axial Ind, at'H1 0.0' 32 B R11/C21 Cire. Ind.- at TSH -0.09 33 B R11/C35 Cire. Ind, at TSH -0.18'- 34 B R11/C42 Circ. Ind at TSH -0.48 i 35 B R11/C46 Cire. Ind. at TSH -0.1' 36 B R11/C49 Cire. Ind. at TSH'-0.12. l 37 B R13/C21 Cire. Ind, at TSH -0.13 38 B R13/C34 Cire. Ind at TSH -0.02 39 B R14/C32 Circ. Ind at TSH -0.69 . i 1 96
TABLE 3-6 Sheat 2 of 3 Steam Tube Count Generator Number Basis and Location (Inchas) 40 B R15/C24 Axial Ind. at H1 0.0 41 B R15/C30 Circ. Ind. at TSH -0.08 I 42 B R15/C57 Cire. Ind. at TSH -0.2 43 B 'R16/C59 Axial Ind. at H1 0.0- '44 B R17/C30 Axial Ind. at H3 0.0 45 B R17/C89 Axial Ind. at Hi-0.0= 46 B R23/C10 cire. Ind. at-TSH -1.56 47 B R23/C24-Axial Ind, at TSH~-2.79 I!1 48 B R23/C25 Axial Ind. at TSH -0.51 49 B -R24/C43 Axial Ind. at TSH -0.18 50 B R27/C48 Axial Ind, at TSH -1.49 51 B -R28/C14' Axial Ind at H1' O.0 52 B R33/C25 Axial Ind. at H2 0.0 53 B R34/C19 Axial Ind. at H2 0.0 54 B R36/C34 Axial Ind, at H2 0.0 55 B R36/C35 Axial Ind. at H2 0.0' 56 B R36/C77 Axial Ind, at H1: 0.0~ i 57 B R38/C35 Axial Ind at H2 0.0; 58 B R41/C32 ^ Axial Ind. at H2. 0.0' 59 B R41/C33 Axial Ind. at H2 0.0 l 60 B R41/C37 Axial Ind. at H2 .0.0 -l 61 B R42/C30 Axial ind. at H2 0.0 1 62 B R43/C31 Axial Ind. at H1 0.01 63 B R44/C53' Axial Ind. at H2 0.0 ! 64 C R2/C62 Axial Ind. at H1 +2.36-; 65 C R2/C66 Axial Ind, at H1 0.0 1 66 C R3/C68 Axial Ind, at Hl. '0.0 1 67 C R3/C71 Axial Ind.-at H1 0.0 J' 68 C R3/C88 Axial Ind, at H2 0.0 69 C R4/C85 Axial Ind, at TSH -0.99 70 C RS/C37 Axial Ind. at H2 0.0 1 71 C RS/C40 Axial Ind. at'H2 0.0 1 72 C RS/C50 Axial 'Ind. at H3 0.0 l 73 C R5/C64 Circ. Ind. at TSH -0.14 74 C RS/C69 Axial Ind, at-H1 0.0 75 C R5/C94 Axial Ind. at H1- ~0.0 ( 76 C R6/C62 Axial Ind. at H2 0.0
- i 77 C
R6/C63 Axial Ind. at H1,H2 0.0 - I cire. Ind, at TSH -0.2 1 1 97 y
i O TABLE 3-6 Sheet 3 of 3 Steam Tube Count Generator Busber Basis and Location-(Inches) 78 C R7/C25 ~ Axial Ind. at H2 - 0.0 79 C R7/C51 Axial Ind. at H2-0.0, 80 C R7/C67 Axial Ind. at H1= 0.0 Cire. Ind, at TSH -0.31 81 C R9/C33 ' Axial Ind. at H1 0.0-82 C R9/C67 Axial Ind, at H1 0.0 83 C R10/C28 Axial Ind.Jat TSH -0.05 84 C R10/C65-Cire. Ind, at TSH -0.16 85 C R10/C89 Axial Ind. at H2 0.0 86 C R10/C90 Axial Ind. at H1 0.0' 87 C R11/C62 ' Axial Ind. at Hl. 0.0-88 C R12/C38 Axial Ind. at H2 '0.0 89 C R12/C39 Axial-Ind.1st'His 0.0 90 C R12/C40 Axial Ind. at H1' O.0 91 C R12/C53 Cire. Ind. at TSH~-0.16 92 C R12/C56 Cire. Ind.'at TSH -0.84 93 C R12/C62 Pitting Ind. at TSH +2.5 94 C R12/C65 Axial Ind, at H1 0.0 0 95 C R12/C69 Axial Ind. at H2-0.0- -Cire. Ind.-at TSH -0.37 96 C R12/C71 Axial Ind. at'H2 0.0 97 C R13/C60 Pitting Ind.= at'TSH +3.31 98 C R13/C66 Circ. Ind'.!at TSH -0.09 99 C R13/C72 Axial Ind.'at H2 20.0 100 C R14/C37 Axial Ind at H1 0.0 101-C R14/C52 Cire. Ind.-at TSH -0.57-102 C R14/C73 Circ. Ind..at TSH -0.2 103 C -R15/C10 Circ..Ind. at TSH -0.45 104 C R15/C13 Axial'Ind. at TSH -3.56 105 C R15/C55 Axial Ind.:st H1-0.0 106 C R15/C63 Axial Ind at H1 0.0 107 C R16/C39 Axial Ind. at H1 0.0 108 C R16/C42 Axial Ind. at H2 0.0 109 C R16/C53 Axial Ind. at H1 0.0 110 C R16/C68-Axial Ind.~ at H1 0.0 111 C R17/C39 Axial Ind at H1 0.0 112-C R17/C54 Axial Ind, at H11 0.0 - 113 C R18/C32 Axial Ind.;at'H1 0.0 114-C R19/C56-Axial Ind. at H1 0.0 115 C R20/C39 Axial Ind. at H2 0.0 0 98
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4. RELIEF VALVE CHALLENCES ,e.ui,e.e., Trojan Facility Operating License WPF-1. Appendix A. Technical Specifica. tion 6.9.1.5.c, " Annual Reports", requirest Annual reports shall include..." Documentation of all challenges to the pressurizer power operated relief valves (p0RVs) or safety valves." Boort In 1989, there were no challenges to pressurizer safety valves or power-operated relief valves. O O 109 l
5. EMERGENCY CORE COOLING SYSTEM (RCCS) PERFORMANCE Recuirettent Adaptation of the revised ECCS rule acceptance criteria (10 CFR 50.46) Section (a)(3)(11) requires submittal of annual reports of the nature of changes or errors and the estimated effects on the limiting'BCCS analysis. Report 1989 BCCS MODEL AC APPLICATION CHANGES As provided in a letter dated February 2, 1990, to the NRC Document Control Desk, the following information summarises BCCS changes in 1989: A. Large Break Loss-of-Coolant Accident (LOCA) Temperature Final Safety Analysis Report (FSAR) Limiting Peak Cladding Temperature (PCT): 1983*F Modifications to Evaluation Model 10'F Pressuriser Pressure Trip Setpoint (1) 0'F Reactor Coolant System (RCS) Loop Temperature Imbalance (2) 0*F-I Reduced Residual Heat Removal (RHR) Flow (3) 18'F Total 2011'F O B. Small Break LOCA FSAR Limiting break (3-inch) PCT 1925'F Modifications to Evaluation Model 18'F Pressurizer Pressure Trip Setpoint (1) 4*F RCS Loop
- Temperature Imbalance (2) 40'F i
Reduced RHR Flow (3) 0'F ) Auxiliary Feedwater Water Purge Delay (4) 86*F Total (New Limiting LOCA PCT) 2073'F Wotes: (1) Pressurizer Low Pressure Trip Setpoint in LOCA analysis reduced to' be consistent with transient analysis (1855 + 1825 psia). (2) An evaluation of the worst case RCS loop temperature inibalance, with one loop 4*F hotter than the others, i 110
U i I (3) This change covers the possibility of a miniflow valve remaining j open on an inoperable RKR pump. l (4) Ef f ects of purging hot feedwater f rom feedlines not previously considered for small break LOCA.
Reference:
Letter POR-89-640 to A. N. Roller, PGE, from R. G. Perez, Westinghouse, " Reporting of Emergency Core Cooling System Evaluation Model Revisions", dated December 5, 1989. 1 i i 4 't O' t A f f a p O 111 \\.
l l 6. CHANGES. TESTSuARD_EKERRINRKTE Recuirement Federal Regulation 10 CFR 50.59 and the Trojan Operating License NpF-1 ) require: "(a)(1) The holder of a license... may (i) make changes in the facility as described in the safety analysis report, j (ii) make changes in the procedures as described in the safety analysis report, and (iii) conduct terts or experi- ) ment.s not described in the safety analysis report, without ] prior Commission approval, unless the proposed change, test or experiment involves a change in the technical specifica- ) 8 tions incorporated in the license or an unreviewed safety question. "(b)(2) The licensee shall submit. . a report containing a brief description of any changes, tests, and experiments, includ-ing a summary of the safety evaluation of each... annually. Reoort Section 6 of the Annual Report provides a description of changes, tests, and experiments completed in 1989 in accordance with 10 CFR 50.59, ( including s summary of the safety evaluation for each. Also included in Section 6 is a summary of changes to the Technical Specifications submitted to and approved by the NRC in accordance with 10 CFR 50.59 and 10 CFR 50.90. p 112 l
6.A PLANT MODIFICATIONS AND DESIGN CHANGES The following plant modifications and design changes were completed in 1989 and are being reported in accordance with Title 10 Code of Federal Regulations, part 50.59 (10 CFR 50.59). These modifications were evaluated, and it was determined that they did not: (a) increase the probability of occurrence of an accident or malfunction of the equipment important to safety as praviously evaluated in the Trojan Final Safety Analysis Report (FSAR), (b) create the possibility of an accident or malfunction of a different type previously evaluated in the FSAR, or (c) reduce the margin of safety as defined in the basis for any Trojan Technical specification. Other design changes were partially completed during 1989, some to meet regulatory commitments, and will be reported in future Annual Reports when all portions of the design changes are coiqpleted. 1. plant Design Chante 77-057 Modification of Control Circuits for Heating and Ventilation System Fanft Control circuits of the Containment purge supply fans occasionally allowed both the "A" and "B" Train fans to start simultaneously. The control circuits of the reactor cavity cooling fans were interlocked with auxiliary relays. When one fan was in standby mode and the other fan was started, the standby fan would start and then stop almost instantaneously.. The latter problem also occurred with the hydrosen mixing fans. plant Design Change 77-057 modified the control circuits for eight heating and ventilation system fans to eliminate a design deficiency which caused excessive wear on the equipment. The remote control switch for each fan was replaced to restore the fan circuit breaker interlock in all modes of operation as was intended in the original design. This modification did not involve a change to the Technical Specifications or an unreviewed safety question. 2. plant Desian Chante 77-072 Modification of Boron Injection System Use of the boron injection surge tank to recharge the boron injection tank (BIT) following a safety injection required approximately 20 hours to reach Technical Specification concentration requirements. This imposed costly delays in restarting the plant. O 113
i l Plant Design Change 77-072 installed a cross-tie line from the boron injection tank to the boric acid batching tank to reauce the amount i of time required to drain and refill the boron injection tank. i l This modification did not involve a change to the Technical specifications or an unreviewed safety question. l 3. Plant Design Chante 80-076 Start-up Boiler Steam Piping and Supports 1 To decrease Plant start-up time and to provide steam for radwaste systems operation, the start-up boiler was to be kept permanent for i l maintenance of vacuum after a Plant trip and establishing a vacuum prior to availability of nuclear steam. l Plant Desi,n Change 80-076 modified the start-up boiler steam piping i and supports to be a permanent system. This modification did not involve a change to the Technical j Specifications or an unreviewed safety question. 4. E},ar),,t Desian Chante 81-043 Installation of 1-inch Union in Instrument and Service Air System Particulate Filter Drain 1.ine The service and instrument air particulate filter element was found difficult to change. Plant Design Change 81-043 added a pipe union in the drain line downstream of the service air valve. This modification did not involve a change to the Technical Specifications or an unreviewed safety question. 5. Plant Desian Chante 81-059 Automatic Cas Analyzer Control Panel The automatic gas analyzer did not work as designed or needed. Several minor design changes had been attempted to fix the problems, but had not been successful. The system required weekly maintenance to remain operable. Specific problems included: 1) excessive drain trap leakage causing high gaseous activity; 2) frequent minor gas leaks; 3) detector failures due to moisture in the sample lines; 4) erroneous readings; 5) inability to take grab samples when system was inoperable; and 6) varying conditions (temperature, pressure, moisture) of the 16 sample' points. Plant Design Change 81-059 replaced the automatic gas analyzer with a reliable system that was capable of monitoring the 16 sample 114 i . ~
points with a minimum of maintenance and operational problems. A gas analyzer package, surplused from the Pebble Springs project, was modified for use at Trojan. The control package was replaced with a programmable control package in a separate cabinet. This control package provided the required flexibility of operation and the variability of control required by the 16 sample points, as well as three spare sapple points for future expansion. Th19 modification did not involve a change to the Technical Specifications or an unreviewed safety question. 6. Plant Design Chanae 83-014 Miscellaneous Pipe / Pipe Support problems During the course of normal operation or shutdown, problems with piping and pipe supports are occasionally discovered, and design modification is necessary to correct the problem. Plant Design Change 83-014 was a generic design thange that was initiated to expedite repairs and reduce costs associated with pipe I and pipe supports found to require modification during the calendar year 1984 These modifications consisted oft Service Water Pipe Support in Rmergency Diesel Generator (gDG) Rooms Modifications to Dirty Waste Monitor Tank (DWNT) Pipe RHR Supports Floor Drain New valves on Reactor Coolant System (RCS) Sample [ i Modifications to EDG Exhaust Stack Drain and Air Tank i Instrumentation Improve Access to Small Velves in Turbine Building Reroute Startup Boiler Blowdown Line Auxiliary Feedwater Pump (AFWP) Diesel Cooling Jacket Drain Variable Spring Pipe Support Replacement Relocate Motor / Operator Valve MO-2657, Add Hand-Holes Modify / Reroute Startup Foodwater Recirculation Piping i Install Check Valve, Remote Operator and Root Valve None of these modifications involved a change to the Technical Specifications or an unreviewed safety question, j 115 I
l 7. Plant Design Chante 83-051 Boron Injection Tank (BIT) Batching Modification As a result of high boron concentrations in the BIT, frequent and costly maintenance was required on auxiliary equipment and Plant availability was reduced. Plant Design Change 83-051 disconnected, removed or abandoned in-place those heat tracing circuits, controls, alarms, and annunciators, as well as the BIT recirculation pumps, power supplies, tank heaters, control room indicators, and Hagan rack bistable switches associated with the maintenance of the high BIT boron system temperature. This modification did involve a change to the Trojan Technical Specifications but not an unreviewed safety question. Operating License NPP-1, Amendment 103, dated March 4,1985, provided _ the necessary WRC approval for elimination of the requirement for a source of concentrated boric acid in Modes 1, 2 and 3, thus allowing BIT boron concentration to be reduced. 8. Plant Desian Chante 83-061 Replacement of Manual Valves Unacceptable for Throttling Applications in the Emergency Core Cooling System (ECCS) and the Reactor Coolant System (RCS) Test experience and vendor data indicated that valves used to throttle safety injection flow were not designed for that purpose 3 and valve degradation would occur as a result, J Plant Design Change 83-061 replaced 18 valves for which throttled flow was or might be expected with valves designed specifically for throttling applications. This modification did not involve a change to the Technical Specifications or an unreviewed safety question. i 9. Plant Deslan Chante 84-004 Miscellaneous Pipe / Pipe Support Problems j During the course of notinal operation or shutdown, problems with piping and pipe supports are occasionally discovered, and design i modification is necessary to correct the problem. l Plant Design Change 84-004 was a generic design change that was I initiated to expedite repairs and reduce costs associated with pipe j and pipe supports found to require modification during the calendar year 1985. These modifications consisted of: . f Modification of Main Feedwater Pump Turbine Drain Pipe 1 116 I
l i 1 Modification of Pipe Supports on Systems Inside Containment i i Modify Supports on Auxiliary Feedwater Turbine Steam Line i Pipe and Pipe Support Modifications in Various Radwaste Drains Replacement of Steam Trap Piping and Fittings Replacement of Steam Generator Blowdown Tank Vent Line Installation of Process Steam Line Traps and Drains Relocate Pressurizer Power Operated Relief Valve for the tmergency Air Supply Piping Auxiliary Feodwater Pump Recirculation Line Rerouting and Replacement Replacement of Piping and Fittings of the Steam Driven Auxiliary Foodwater Condenser Drain I Installation of Two Additional Turbine Building Floor Drains Modify Six Pipe Supports on Various Systems outside Containment l t Service Water Pump L:ube Water Flow Indicator Bypass 1 () Correct Press Level Pipe Slope Installation of Isolation Valves on Containment Spray Pump l Suction Valve Drains P Extension of Boric Acid Tank Loop Seals l I l Modification of Three Steam Generator Blowdown Pipe Supports l Relocation of Valve on Pressuriser Safety Valve Drain Lines Modification of Tubing for Steam Generator Hydraulic Snubbers f Modification of Line Near Integrated Leak Rate Test (ILRT) Containment Penetration i None of these modifications involved a change to the Technical Specifications'or an unreviewed safety question. I i i 10. Plant Desian Chanae 84-047 l Diesel Fire Pump Battery Charger i The battery circuit did not provide sufficient load current to keep i O charger's blocking diodes forward-biased and the no-current relay provided nuisance alarms to the. control room. 117 l 1
plant Design Change 84-047 installed a dunusy load across the battery to keep the blocking diodes forward-biased. In addition, space heaters for the electric fire pump were connected to a local power supply. This modification did not involve a change to the Technical specifications or an unreviewed safety question. 11. Plant Design Chante 84-048 Fire Suppression System Modifications The July 1984 Appendix R Review comunitted to the installation of several fire suppression systems in order to meet 10 CFR 50.48 Appendix R Criteria, plant Design Change 84-048 installed five new fire suppression systems including two water curtains in lieu of 3-hour fire barriers and two suppression systems in the Turbine Duilding to separate or protect redundant trains cf safe shutdown equipment. This modification did not involve an unreviewed safety question, and a change to the Technical Specifications was not required. 12. Plant Design Chante 84-067 Stator Cooling Water Flow Control Modifications l The liquid stator cooling circuits that fed the exciter rectifiers j and high voltage bushings did not have adequate flow measurement capabilities. The automatic flow regulators on each circuit could fail in-service and cause the main generator to overheat due to inadequate cooling. This failure of flow regulators would not have brought in a low flow alarm. Plant Design Change 84-067 provided adequate flow measurement capabilities in the stator cooling water system per approved vendor modifications. Manual flow control valves and flow meters were-installed in each stator cooling water line for the exciter rectiflors and high-voltage bushings. Low flow alatins were installed from the flow meters and the high differential pressure alarms were deleted, pressure instrumentation was installed on the supply and return lines to the exciter rectifiers and high-voltage I bushings. An automatic pressure regulating valve was installed to control the high-voltage bushing supply pressure and maintain water pressure below the gas pressure. This modification did not involve a change to the Technical Specifications or an unreviewed safety question. 118-
l \\ i i 13. Plant Design Chante 84-120 Improved Process Radiation Monitor Air Sampling NURgC-0737, " Clarification of TNI Action Plan Requirements", ) l requires representative sampling of iodine and particulates in the Containment purge exhaust, Auxiliary Building vent, and Condenser air ejector exhaust. Process radiation monitors (PRMs) 1, 2, and 6 I are used to sample these effluent streams. j In order to obtain representative samples measures must be taken to l avoid iodine plateout on the walls of the sample acquisition ] piping.. A proven method of limiting plateout is to apply heat trace to the outside of the sample piping. Therefore, to minimize plateout of iodine on the sample lines of PRMs 1, 2, and 6, heat i tracing was installed via Plant Design Change 84-120. i This modification did not involve a change to the Technical Specifications or an unreviewed safety question. 14. plant Design Chante 84-124 ) Transmitter Replacement The qualified life for several instrument transmitters used in the pressurizer pressure. steam generator water level, steam flow, and 1 O Reactor Coolant System wide-range pressure expired after the 1986 j Refueling Outage and the qualified life for pressure transmitters used in the Containment water level' expired after the 1987 ) Refueling Outage. ].i In addition, several transmitters had failed in main steam pressure and main turbine first-stage pressure-sensing applications. Also -l the transmitters used in the auxiliary feedwater flow rate sensing applications exhibited a significant zero shift upon system pressurization. These occurrences raised concerns.of reliability and accuracy. Plant Design Change 84-124 replaced 33 transmitters and also relocated the main turbine first stage pressure transmitters for the 45-foot level of the Turbine Building to the 63-foot level of } the Turbine Building. This modification did not involve a change to the Technical j Specifications or an unreviewed safety. question. I 15. Plant Design Chante 84-128 Correction of Deficiencies Associated with Fuel Handling Equipment j The fuel transfer cart air motor had seized when submerged during l O the last three refuelings, causing delays in refueling, water .j inventory problems, and contributed to Technical Specification violations. 119
The manipulator crane also had several problems which required design modification including: control cabinet overheats, hoist motor overheats. Selsyn indicator inoperability, no means to provide slow-jos movements with mast down (to remove / install bowed fuel assemblies), no fold up seat for the manipulator crane
- operator, plant Design Change 84-128 removed the air motor drive system in its entirety and installed an electric motor drive, mounted on the operating floor to provide replacement motive force. Local fans and hinged waterproof enclosures were provided to preclude overheating of the manipulator crane control cabinet. A shroud and blower were provided to cool the manipulator crane-hoist motor.
Circuitry was provided for slow-jog movement of the refueling bridge with the manipulator mast down. Modifications were made to the manipulator crane to prevent binding between the inner and outer mast in accordance with manufacturer's recommended instructions. This modification did not involve a change to the Technical Specifications or an unreviewed safety question. 16. Plant Design Chante 84-132 Auxiliary Feedwater Chemical Addition The plant did not have a satisfactory means of adding chemicals to the steam generators especially during startup conditions. The practice for chemical addition required several days for the four generators and post-addition analysis indicated poor results. Cooldown modes showed delays due to this process. The discharge of tho spare chemical injection pump was cross-connected to the discharge header for the shutdown hydrazine pumps. The purpose of the cross-connection was to use the relatively large capacity spare chemical injection pump to inject hydrazine and boric acid into the Auxiliary Feedwater System. Plant Design Change 84-132 replaced.a short section of carbon steel piping and a valve with stainless steel. This piping is exposed to hydrazine and boric acid whenever the spare chemical injection pump is used to inject, or whenever more than one shutdown hydrazine pump is used to inject into a single line. Carbon steel is not suitable for either hydrazine or boric acid. This modification did not involve a change to the Technical Specifications or an unrcviewed safety question. 17. Plant Desien Chante 85-531 Level Control for Condensate Domineralizer Backwash Receiving Tank e The condensate domineralizer backwash receiving tank had an 1 unreliable conductivity-type level indication and control system. 120 6 4
\\ Plant Design Change C5-531 replaced the old level control system O. for the condensate demineralizer backwash receiving tank with a variable resistance type level sensor. This modification did not involve a change to the Technical Specifications or an unreviewed safety question. 18. Plant Design Chante 85-557 Cate Booth and Security Building 120-V ac Power Supply Modifications Extension cords were supplying 120-V ac power to the main gate booth for heating and lighting purposes. Dedicated circuits in the -Security Building could not supply the power required. Plant Design Change 85-557 installed permanent 120-V ac power to the main gate booth and added additional 120-V ac circuits to the Security Building. This modification did not involve a change to the Technical. Specifications or an unreviewed safety question. 19. Plant Design Chant.e 86-023 Noisture Separator Rehester Tube Bundle Replacement The steam generator modifications 5-year plan called for removing copper ion bearing components from the secondary' systems. Plant Design Change 86-023 replacco the moisture separator reheater tube bundles with new tube bundles using stainless steel tubes and incorporating the latest design techniques. The design improvements increased moisture removal from 92 percent to 98 percent. This modification did not involve a change to the Technical { Specifications or an unreviewed safety question. l 20. Plant Design Chante 86-042 Turbine Building High-Energy Line Break (HELB) Modifications Analyses indicated that conditions within the Turbine Building and structures enclosed therein may not remain mild environments under hypothesized HELB accident scenarios. Modifications were required to provide reasonsble assurance that safety-related equipment, relied upon to mitigate HELB effects, remained functional. Plant Design Change 86-042 included several modifications to the O Turbine Building: 121
1 i Installation of a steel plate barrier in front of the l "A" Train Engineered safety Features (ESP) switchgear room roll-up door. j Installation of pressure release fasteners in approximately 2,000 square feet of the Turbine Building siding. I Installation of back-draft dampers on the Auxiliary Foodwater (AFW) pump and remote shutdown panel room Heating, Ventilation. Air Conditioning (HVAC) exhausts. Reinforcement of the AFW pump supply ducts. Relocation of the AFW pump control room ventilation intake from the west to the south wall into the turbine-driven AFW pump room. i Reinforcement of the Turbine Building north entry roll-up door. l Repiscement of Turbine Building railroad bay east roll-up door with a higher-pressure-rated door. l-; Reinforcement of the plaster wall adjacent to one of the 4 doors. Installation of back-draft damper for "A" Train ESF-i switchgear room smoke exhaust system and reinforcement of the duct. This modification did not involve a change to the Technical Specifications or an unreviewed safety question. ( 21. Plant Desian Channe 86-502 ~ Process and Effluent Radiation Monitor (PERM)-10 Flow Indication In 1984 Temporary Plant Test (TPT) 86 was performed (reported in PGs-1015-84) to detemine individual steam generator sample flows to PERM-10 and to determine if pressure control in the steam-l generator blowdown sampling system could be improved. l plant Design Change 86-502 provided sanqple conditioning of the Steam generator blowdown sa1qples. This modification was made as Temporary Modification 83-60 to allow testing per TPT 86. Flow instrumentation was installed, adding individual sample line filters, control valves, and flow indicators to more accurately monitor blowdown activity by assuring greater accuracy of measurements made by the PERM-10 monitors. O 122 l
l 'l p This modification did not involve a change e.o the Technical Specifications or an unreviewed safety question. 22. plant Design Chante 86-533 Installation of Domineralized Water Supply to the Regeneration Sample Sink i There was no available water for the regeneration sample sink resulting in a safety hazard due to the chemicals (caustic and acid) which could not be rinsed from the sink. j Plant Design Change 86-533 installed a domineralised water supply line to the sample sink at the regeneration skid.- i This modification did not involve a change to the Technical Specifications or an unreviewed safety question. ] 23. Plant Design Chante 86-567 Installation of Air Pressure Indication at Discherge of Air Compressors l pressure indication was not adequate to correctly identify O discharge pressure to determine cause while troubleshooting operating problems. 1 Plant Design Change 86-567 installed pressure indication on the discharge pressure switch impulse lines to allow more direct performance testing, evaluation and proper system siljustment, j This modification did not involve a change to the Technical Specifications or an unreviewed safety question. i 24. EJ,3pt Desian Chante 86-573 Electrical Shop Monorail A high potential for injuries existed with maintenance personnel manually liftin6 items. Plant Design Change 86-573 installed a 1-ton electric tuonorsil hoist in the electrical shop of the Maintenance Building. This modification did not involve a change to the Technical Specifications or an unreviewed safety question. 25. Plant Desitn Chante 86-577 .O Air Compressor Cooler Isolation Valve Coupling Addition 123
Maintenance of isolation valves in the bearing cooling water supply lines required removal of 60 feet of downstream piping. Plant Design Change 86-577 installed 2-inch threaded pipe unions in the bearing cooling water supply lines to air compressor-coolers for use during replacement of isolation valves. This modification did not involve a change to the Technical Specifications or an unreviewed safety question. 26. Plant Desien Chante 87-005 Replacement Condensate Domineraliser Air Blower The condensate domineralizer air blower was undersized and resulted in shortened lives of the domineralizer filter elements due to fouling. Plant Design Change 87-005 replaced the condensate domineralizer air blower with a new rotary-lobe type positive displacement blower of required capacity. This modification did not involve a change to the Technical Specifications or an unreviewed safety question. 27. Plant Desian Chante 87-500 Installation of Personnel Screens for the Service Water Intake Structure Temporary personnel screens were frequently used with high costs associated for installation and removal including preparation of Temporary Modifications. The screens were used-for diver protection during Intake Structure underwater surveys. Plant Design Change 87-500 installed two pemanent aluminum personnel screens in the existing stop-log slots in the Intake Structure entrance bay to the "C" service water pump. This modification did not involve a change to the Technical Specifications or an unreviewed safety question. ] 28. Plant Desian Chante 87-501 Removal of Extraneous Tubing from process Sampling System Two pieces of blanked tubing were previously installed in the sampling system from an on-line monitoring system. The tubes servod no functional purpose in the existing system and their removal would help (1) reduce radiation levels in the sampling room, (2) minimize the possibility of a spill due to non-functional { 124 j
pressurized tubing and (3) enable installation of further () improvements to the sample cabinet. Plant Design Change 87-501 allowed for the removal of the two extraneous tubing sections from the process sampling system and the installation of a bypass tubing section with a valve inside the sample rack for the hydrogen sample rig to be used during coolant recirculation. This modification did not involve a change to the Technical Specifications or an unreviewed safety question. 29. Plant Desian Change 87-509 Reactor Coolant Pump (RCP) Motor Lower Bearing 011 Pot Modification Oil level indication problens had been discovered on the RCPs. After the 1986 refueling outage. there was a high oil level alarm on the "C" RCP motor lower bearing reservoir and during the investigation, several other unuous1 indications were noticed. Plant Design Change 87-509 installed vents in the RCP motor lower bearing vent pots to eliminate abnormal oil level fluctuations and spurious high/ low level alarms. O This modification did not involve a change to the Technical l Specifications or an unreviewed safety question. 30. Plant Design Chante 87-521 Counting Room Air Conditioner Condenser Relocation i i Coil cleaning for the counting room air conditioner condenser i required that the unit be removed due to restricted access, r Plant Design Change 87-501 relocated the counting room air conditioner condenser from above the gas bottle storage outside the north wall of the Control Building to a covered area outside the control Room door to facilitate periodic maintenance on the condenser. This modification did not involve a change to the Technical Specific-ans or an unreviewed safety question. 31. Plant Design Chante 87-524 Plant Discharge British Therral Unit (BTU) Recorder / Instrument Replacement () Plant Operations and Maintenance requested upgrade of Plant thermal discharge instrumentation for increased accuracy and reliability. 125
Plant Design Change 87-524 replaced Plant influent and ef fluent temperature and flow instrumentation and recorder with current-technology equipment. The new equipment consists of two-wire Resistance Temperature Detector (RTD) transmitters, a configurable controller, and a microprocessor-based recorder. Use of a moving average feature in the cooling water flow metering instrumentation will smooth out flow epikes which lead to false indications on the Instantaneous Flow and BTUs/ Hour Recorders. This modification did not involve a change to the Technical specifications or an unreviewed safety question. 32. Plant Desian Channe 87-528 Level Transmitter Isolation valves Recalibration of the level transmitters (Dirty Weste Drain Tank) required that a valve on top of the tank be closed for isolation purposes, and the tubing removed from the level transmitter connection for pressure equalisation. Plant Design Change 87-528 installed isolation valves in the instrument tubing for Level Transmitters LT4150 and LT4152 (Dirty Waste Drain Tank) to facilitate periodic calibration and maintenance. This modification did not involve a change to the Technical lh specifications or an unreviewed safety question. 33. Plant Desian Chanae 87-530 Warehouse Loading Dock Modifications Personnel safety problems were identified regarding the Warehouse loading dock. Plant Design Changs 87-530 modified the Warehouse loading dock including the installation of a new hydraulic dock level, a truck locking mechanism and arphalt paving of the dock bottom to reduce the dock height. This modification did not involve a change to the Technical specifications or an unreviewed safety question. 34. Plant Desian Chanae 87-532 Spent Fuel Handling Tool Modification The spent fuel tool would not enter one of the spent fuel rack locations and was tight in a few other locations in the rack bundle. This was because the spent fuel rack bundle was somewhat reduced below envelope tolerance at these locations. 126
._.~ ( Plant Design Change 87-532 removed material from all four sides of the spent fuel handling tool base plate. This modification did not involve a change to the Technical I specifications or an unreviewed safety question. 35. Plant Design Chante 87-536 i Cooling Tower Blowdown Flow Element and Indicator Instruments were not supported as installed. In August 1987, a complete assembly broke off upstream of the instrument root valve t' causing the pit to be flooded. The Cooling Tower had to be drained in order to effect repairs. Plant Design Change 87-536 installed a support for the Cooling Tower blowdown finw element and indicator (located in the pit near the Main Circulating Water Piping, outside of the security fence). I This modification did not involve a change to the Technical j Specifications or an unteviewed safety question. 36. Plant Desien Chante 87-554 J Installation of Remote Operator for Valve Operation of the Treated Weste Monitor Tank (TWMT) discharge valve involved possible personnel safety hazards and ALARA concerns. Plant Design Change 87-554 installed a remote operator for_a valve in the Clean Radweste System to allow the valve to be operated from 6 the common area immediately east of the Dirty Waste Monitor Tank (DWMT) room. This modification did not involve a change to the Technical Specifications or an unreviewed safety question. 37. Plant Desian Chante 88-504 Condensate Receiver Tank Instrument Well Vent Condensate receiver tank instrument well vent released steam and water into the respirator maintenance facility (45-foot Fuel Building) when in operation. plant Design Change 88-504 installed an instrument well vent line-for the level switch on the condensate receiver tank. This modification did not involve a change to the Technical tO Specifications or an unreviewed safety question. 1 b 127
~ 38. Plant Design Change 88-510 0 Steam Generator Blowdown Vent Stack Barrier A vent stack on the Turbine Building was not adequately protected to prevent unauthorized access to a vital area. plant Design Change 88-510 constructed a vent stack barrier (metal enclosure) at elevation 93-foot of the Turbine Building. This modification did not involve a change to the Technical Specifications or an unreviewed safety 9.uestion. 39. plant Design Chante 88-514 Warehouse Mezzanine Modular Office The main warehouse did not have adequate office space. Plant Design Change 88-514 installed a modular office on the mezzanine level of the Main Warehouse. This modification did not involve a chang 6 to'the Technical Specifications or an unreviewed safety question. 40. Plant Design chante 88-525 Fire Pump Flow Indicator and Orifice Plate Replacement The flow indicator sr.d orifice were inconpatible for measuring water flow of the diesel and electric fire pumps and were giving incorrect values. Plant Design Change 88-525 replaced the flow indicator, replaced the flow orifice, and re-routed the sensing lines. This modifiestion did not involve a change to the Technical Specifications or an unreviewed safety question, s 41. Plant Desian Chante 89-006 Repair Ice Damage to Cooling Tower Fill Support Cooling Tower fill support beams were damaged by ice build-up during the freezing weather of February 1989. Two severely damaged beams no longer fulfilled the bracing requirements for the affected' columns and were potential safety hazards to personnel removing silt from the cooling tower basin. Another moderately damaged beam required repair (grout patching) to preclude corrosion of the steel connections and further degradation of the reinforcement steel. 128 l
( plant Design Change 89-006 replaced the two severely. damaged 3 4 Cooling Tower fill support beams and repaired the moderately damaged support beam. This modificat',on did-not' involve a change to the Technical Spscificatiens or an.unreviewed. safety question ~. e I a e 1 1 129 A
i 1 6.B LICENSE AMENDMENTS in 1989, a total of seven licanse amendments were issued by the NRC. . Thirteen requests for license amendments [ License Change Applications (LCAs)) were submitted to the NRC for approval and three resulted in license amendments plus one Temporary Technical specification Change. Of eleven LCAs previously submitted, three received NRC approval and have been issued (one of the previously submitted LCAs was only partially approved). As of December 31, 1989, nineteen LCAs were being reviewed by the NRC. 4 O 9 w I 130
P TABLE 6.B-1 Sheet 1 of 4 AMENDMENTS TO THE TROJAN OPERATING LICENSE ISSUED IN 1989 For the following' amendments,.the NRC has concluded that (1) there is reasonable assurance that the health and safety of the public will not be -endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations. and the issuance of the amendment will not be inimical--to the common defense and. security or the health and safety of the public. Amendment Number Date Subsect t 150 02/28/89 Amendment 150 was issued to reflect the corporate restructuring of Pacific Power and Light Company, one of the licensees for the Trojan Nuclear Plant. - as a result of their merger with Utah Power.and Light Company. The new corporation Pacif1 Corp, plans to continue doing business under the assumed, name of Pacific Power and Light, i This amendment involved only the administration of credit and financial arrangements and antitrust. ( considerations for the Trojan Nuclear Plant, w Accordingly, the amendment met the eligibility criteria for categorical exclusion set forth<in Title 10 Code of Federal Regulations, Part-51.22(c) (10) [10 CFR 51.22(c)(10)). Pursuant to 10 CFR 22 (b), no environmental impact statement. or environmental assessment was. required in connection with the issuance of this amendment. 151 03/17/89 Amendment 151 deleted the 3.5 weight percent Uranium-235 (U-235) fuel. enrichment limit on l reactor fuel. assemblies, and authorized the enrichment limit for the new= fuel storage racks of 4.5 weight percent. j In addition to Amendment 151, PGE distributed a copy of Page 3/4 3-47 which was previously ~l approved with Amendment 93 on September 5, 1984 The NRC requested reissue of this page to correct a clerical error.- 4 Pursuant to 10 CFR 51.21, 51.32 and 5?.35. an environmental assessment was publishedLin the Federal Register. Accordingly, the Commission determined that issuance of this amendment would not result in any environmental impacts other than h those evaluated in the Final Environmental 2 Statement. 131
TABLE 6.B-1 Sheet 2 of 4 Amendment Number Date Subject 152 05/15/89 Issuance of this amendment revised Technical Specification 3/4.3.3.6, " Chlorine Detection Systems", and 3/4.7.6.1, " Control Room Emergency Ventilation System" These changes were initiated as a result of Portland General Elect ric's commitment to resolve Control Room Habitability issues raised during an NRC inspection in 1986. This amendment involved a change in surveillance requirements and in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC determined that the amendment involved no signi-ficant increase in the amounts, and no significant change in the types of any effluents that may be released offsite, and that there was no signifi-cant increase in individual or cumulative occupa-tional radiation exposure. The Commission had previously published a proposed i'inding that the amendment involved no significant hazards con-sideration and there was no public comment on such finding. Accordingly, the amendment met the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment was required in con-nection with the issuance of this amendment. 153 05/24/89 Amendment 153 was issued to provide improved economy with the use of an upgraded fuel design for future Trojan core loadings. Features of the upgraded fuel assembly consist of reconstitutable top nozzle, axial fuel blankets, and the capabi-lity of achieving higher burnups, as well as satisfying higher nuclear peaking factors. Distributed with this amendment was a revised Page 3/4 1-15. With the issue of Amendment 58, dated April 16, 1981, two lines were inadvertently omitted. NRC letter dated May 12, 1989, author-ized reissue of this page to correct the error. Pursuant to 10 CFR 51.21, 51.3?, and 51.35, an environmental assessment and finding of no signi-ficant impact was prepared and published in the Federal Register. Accordingly, based upon the environmental assessment, the Commission 132
TABLE'6.B-1 Sheet 3 of-4 O Amendment Number Date Subject 153 determined that the. issuance of this amendment (cont.) would'not have a-significant effect on the quality. of the human environment. 154 06/20/89 Amendment 154 revised Technical specification 5.7.2.2. The. allowed lateral shear forces on any. story of the Control-Auxiliary-Fuel Building Complex was increased to a not three percent. Pursuant to 10 CFR 51.21,151.32, and 51.35, an environmental assessment.and finding of no significant impact was prepared and published in-the Federal Register. Accordingly, based upon the environmental assessment,1the Commission deter-mined that the issuance of this amendment would 1 not have a significant effect on the quality.of.- _l the human environment. 155 11/06/89 Issuance of Amendment 155 allowed implementation of a recent reorganization within the' Nuclear Division of Portland General Electric Company. These changes reflected.the addition of a third-1 General Manager position and the' formation-of:the Plant Support Group which now includes ~the l Training Department. Also included with the distribution of this l amendment was a; change to the Bases Section of the Trojan Technical Specifications. ~This change provided clarification concerning: assumptions used-in a Containment pressure analysis. In accordance with NRC instructions, changes to the Bases need not be submitted for prior NRC approval. This amendment related to changes-in recordkeeping or administrative procedures or requirements. Accordingly, the amendment met the eligibility criteria for. categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment was required in connection with the issuance of this emendment. 156 12/01/89 Amendment 156 revised the Trojan surveillance requirements for Containment leak testing by specifically stating that provisions of Trojan Technical Specification 4.0.2, " Applicability'?, are not applicable. 133
TABLE 6.B.1 Sheet 4 of 4 -i Amendment Number Date Subject 156 This amendment involved s' change in a-surveillance? (cont.) requirement.- The NRC determined that the amend-ment involved no significant increase in the-amounts, and no significant change in the types, of any effluents that may be released offsite, and that there was no significant increase infindivi-dual or cumulative occupational radiation exposure. The Commission previously published a-4 proposed finding that the amendment. involved no significant hazards consideration and there was no public comment on such finding. Accordingly, the' { amendment met the eligibility criteria for-categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant-to'10 CFR 51.22(b), no environmental impact statement or environmental assessment was required in connection with'the: issuance of this amendment. I 12/28/89 The NRC issued an " Emergency Authorization for 11 Temporary Change to Technical Specification .J 3.3.3.6.b for Trojan Nuclear. Plant". This temp-j orary change allows outside air makeup damper's to: be open for normal and/or amergency. control' room I ventilation systems for up to one hour with both chlorine detectors inoperable. This change is. j effective only until'the chlorine detectors are-returned to operable status, or March 15,'1990, whichever occurs'first. (NOTE: Safety Evaluation Report not yet received from the NRC.) i t i 1 134 ) l v
i .O TABLE 6.B-2 Sheet 1 of 7 STATUS OF LICENSE CHANGE APPLICATIONS (LCAs) SUBMITTED TO AND UNDERGOING REVIEW BY THE NRC AS OF DECEMBER 31, 1989 LCA Date Number-Submitted Subiect and Status 124 07/29/85 Containment Isolation Provisions and Leakage Rate Testing: Revises Containment leakage rate testing. Several changes are also included-to the table listing Containment isolation valves. PGE letters-of December 22, 1986, February 26, 1987, and April 3, 1987 provided. revised pages. URC letter dated February 10, 1988 requested-submittal of a revised Significant Hazards discussion to facilitate NRC review. LCA 124. Revision I was transmitted to the NRC via PGE letter dated March 1, 1988. The NRC O' issued Amendment 147, dated July 11, 1988, to the Trojan Operating License and Appendices approving of a portion of this LCA. -(Note: No changes-have occurred since the submittal of the 1988 Annual Report.) 142 09/30/86 Control Room Habitability: Requests. modifications regarding control room habitability by proposing changes to the (1) Chlorine Detection Systems, (2)-SO2 Detection Systems, and (3) Control Room Emergency Ventila-tion System. PGE letter of November 16,'1987 transmitted Revision 1 of this LCA. On April 14, 1988, revised pages were submitted to the NRC tp incorporate their comments and provide clarifications. The NRC issued Amendment 152, dated May 15, 1989, to the Trojan Operating License and Appendices approving Revision 1 of this LCA, however, a portion of Revision 0 (S02 Detec-O tion System) is still awaiting NRC approval. 135
4 TABLE 6.B-2 Sheet 2 of 7 O LCA Date Number Submitted 5tbject and Status 145 10/28/86 Barton Transmitter Setpoint Changes: Requests changes to reflect the current set-points for Barton transmitters (replaced during-the 1986 outage). The specific setpoints changed are the steam generator low-low level and pressurizer low-pressure reactor trip. Revision 1 of this LCA, incorporating additional-information in the Significant Hazards Deter-mination, was submitted by PCE letter, dated May 19, 1988. PGE lottar, dated December 30, 1988, forwarded LCA 145, Revision 2. This revision removed reference to the pressurizer low-pressuro safety
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injection setpoint as a result of the submittal. of LCA 171 on September 9, 1988. (Note: No changes have occurred.since the submittal of the 1988 Annual Report.) 151 12/24/87 Relocation of Fire Protection Technical Specifications to PCE-1012' i i Removes those, portions of the Trojan ~ Technical Specifications that are related to the Trojan fire protection program and relocates. them to Topical Report PCE-1012, Volume I,'" Trojan i Nuclear Plant Fire Protection Plan - Program Description"..This change would provide additional' flexibility for modifying require-ments within the provisiones of. Title 10 Code'of i Federal Regulations, Part 50.59 (10 CFR 50.59) j and is consistent with NRC guidance provided in . j Generic Letter 86-10, dated April 24, 1986,. i regarding "Itaplementation of Fire Protection Requirements". PGE letter, dated December 15, 1989, forwarded' LCA 151, Revision 1..This revision was sub-i mitted to reflect further NRC guidance as ' I provided in Generic Letter 88-12, dated August' 2, 1988. i 136
TABLE 6.B-2 Sheet 3 af 7 LCA Date Number Submitted Subject and Status 159 11/09/87 Containment Ventilation Isolation System (CVIS): Revises Trojan Technical Specification 3.9.9, " Containment Ventilation Isolation System", to resolve inconsistencies within the Technical Specifications. Technical Specification 3.9.9 currently requires the CVIS to be operable at all times while in Mode 6; however, Technical Specification 3'.9.4 establishes operability requirements >for the i Containment Building penetrations (including Containment ventilation isolation valves) as applicable in Mode 6 only when CORE' ALTERATIONS or fuel movement inside the Containment is in-progress. j Additionally, the ACTION statement is~ revised to specify closing Containment Ventilation penetra-tions if CVIS is inoperable. i NRC letter, dated December 22, 1987, requested re-review and revision of this LCA to address identified NRC concerns. On February 25, 1988, PGE forwarded response to-NRC questions regarding this License Change Application as well as a revised Significant-Hazards Consideration determination to incorpo-rate these responses, j 1 (Note: No changes have occurred since the submittal of the 1988 Annual Report.) 168 07/08/88 Miscellaneous Editorial. Changes: Incorporates various editorial corrections and l clarifications into the Trojan Radiological i Effluent Technical Specifications'(RETS).' i PGE letter, dated January 31, 1989, forwarded Revision 1 of this LCA. This revision incorp-orated a change inadvertently omitted from the original LCA. O 137 2 D +0m,s
TABLE 6.B-2 Sheet 4 of 7 O LCA Date Number Submitted Subject and Status 169 08/12/88 Emergency Core Cooling System (ECCS) Check Valves: Revises the surveillance requirements for the ECCS check valves in the Trojan Technical Specifications. Specifically, thiu change requires adjusting the observed leakage rates through the ECCS check valves when testing at lower-than-maximum differential pressure. PGE letter, dated August 16, 1988, transmitted a replacement page for this LCA, to provide the conclusions of the safety and environmental evaluations performed for this LCA (inadvert-ently omitted from the original submittal). (Note: No changes have occurred since the submittal of the 1988 Annual Report.) 170 10/07/88 Revision to PGE-1017. Trojan Security Plan: Revises the Trojan Nuclear Plant Security Plan by allowing the use of dedicated observers in lieu of security officers to compensate for safeguards degradations pursuant to Nuclear Regulatory Commission (NRC) Regulatory Guide 5.61, Revision 1 (November 1987), " Reporting of Safeguard Events", and NUREG-1045, "Guida', a on the Application of Compensatory Safeguards Measures for Power Reactor Licensees (January 1984)" This LCA also describes the conformance of electrical cable penotrations in thu control room floor to Part 73.55(c)(6) of Title 10, code of Federal Regulations. PGE letter, dated December 23, 1988, submitted an Errata to this LCA which moved the "Significant Hazards Consideration Determination" to an unclassified portion of the LCA. (Note: No changes have occurred since the submittal of the 1988 Annual Report.) 138
I TABLE 6.B-2 Sheet 5 of 7 LCA Date Number Submitted Subject and Status 171 09/09/88 Pressuriser Low-Pressure Safety Injection Setpoint: Revises the pressurizer low-pressure safety injection setpoint.- This new setpoint is nee-essary to accommodate a change to a different. transmitter design used to measure narrow-range 1 pressurizer pressure. (Note: No changes have occurred'since the sub-mittal of the 1988 Annual Report. ) 173 02/10/89 Equipment Hatch Seal / Closure Verification: Clarifies-the surveillance requirements for the-Containment equipment hatch. This LCA requested removal of the verification:of-closure and seal of the equipment hatch statement from the 31-day verification of " Containment Integrity". 177 06/12/89 Steam Line Safety Valves: Requestu a change of the orifice. size of the steam line safety valves shown in Trojan-Technical Specification (TTS) Table 4.7-1, " Steam Line Safety Valves per Loop". This change corrects a discrepancy:between the TTS. and the cetual orifice area. 178 11/13/89 Component Cooling Water (CCW) Technical Speci-fication Changes: Revises the operability and surveillance requirements, and the bases, for the CCW System. Trojan Operating License Amendment 141, dated May 3, 1988, allowed for, split-train operation with spare CCW pump operability until completion of the CCW upgrade. -This request-for change reflects.cumpletion of modifications to seismically upgrade the Seismic category II portion of the CCW System. l 179 07/19/89 Auxiliary Feedwater-(AFW) Steam Supply Valves: Changes the description of the turbine steam supply valves in Trojan Technical Specif1 cation O Table 3.6-1 from motor-operated to air-operated. This change reflects a previous \\ 139 a l 1
/ { l TABLE 6.B-2 Sheet 6 of 7 O LCA Date Number Submitted. Sub3eet and Status 179 modification to the AFW turbine pump design to (cont.)' be independent of alternating current power. The l-design modification ~ included changing the turbine steam supply valves from motor-operated h to air-operated. I 181 10/20/89 Reddction of Operable Incore Thimble: Changes the' minimum requirement for the number of operable in-core detector thimbles from 75 percent to 50 percent for Cycle'12 operation. This change would'be applicable to Cycle 12 only; therefore,~if not requirod during that time, we will' request withdrawal of the LCA. 184 10/20/89 Radiation Protection Manager Qualifications: Updates.the qualification requirements that~the-l Radiation Protection Branch Manager must meet.o This LCA was submitted to reflect current nuclear industry standards' recommendations and NRC Regulatory Guide 1.8, " Personnel Selection and Training," Revision' 2, April.1987 guidance in lieu of that provided in the September,1975 version of the Regulatory-Guide. l 186 11/30/89 Incorporation of Generic Letter 87-09 in.the Trojan Technical Specifications: Revises the Trojan Technical. Specifications to incorporate the recommended changes contained in-Generic Letter 87-09, " Sections-3.0 and\\4.0 of the Standard Technical Specifications-(STS) on the Applicability of. Limiting conditions.for Operation and Surveillance Requirements",' dated: June 4, 1987. 187 11/30/89 Steam Generator Tube Sleeving: Modifies the Technical Specification require-monts for steam generators to allow tube repair by sleeving as an~ alternative to plugging. Plugging tubes reduces reactor coolant flow and is less desirable in some cases than a repair l technique that does not remove the tubec~from service. 140 I b
TABLE 6.B-2 Sheet 7 of 7 O LCA Date Number Submitted Subieet and Status i I 188 12/20/89 Correction to Figure 3.4-2, Reactor Coolant l System (RCS) Pressure-Temperature Limits: Corrects an error contained in Figure 3/4-2', " Reactor Coolant System Pressure - Temperature. 1 0 Limits Versus 60 F/ Hour Heatup Rate - Criti-cality Limit.and Hydrostatic Test Limit"..A corrected curve, received from Westinghouse, shows that the original heatup curve is-conservative.
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'6.C LICENSING DOCUMENT CHANGE REQUESTS (LDCRs) O .I APPRO' Et DURING 1989. Licensing Documents consist of various PCE Topical Reports and the Trojan FSAR. Under Title 10 Code of Federal Regulations, Part 50.54 and Part 50.59 (10 CFR 50.54 and 50.59),. changes are-permitted to-these documents if a change to the operating License or Technical Specifications does not' result, if an unreviewed safety question:is not created, or if there is no i degradation of Plant security, decrease'in effectiveness of the Emergency Plan, or reduction to-the commitments in the QA Program description. The following is a summary of the Licensing Document Change Requests approved in 1989. kQQB: 87-18 Document: Final Safety Analysis Report (FSAR) Status: Approved June 12, 1989 and issued as part'of Amendment 10 on July 31, 1989. Safety Evaluation: Changes were required to the FSAR to reflect completion.of the Steam Generator Blowdown System and i Liquid Radwaste-Ion Exchanger Modification Which-replaced components to increase flow capacity, to recover heat. and to provide for liquid radwaste deionization. The modifications resulted in'a change to the Technical Specifications (Operating License Amenduent 143 approved by the NRC on June 16, 1988). q The changes to the FSAR, however, did not result in a change to the Technical Specifications nor did.they create an unreviewed safety or environmental question.- LDCR: 88-17 Epeument: Modification, Repair. and Replacement Program, PGE-1051 i Status: Approved May 31, 1988 and issued April 27, 1989 as Amendment 1. Safety Evaluation: This LDCR was initiated'to allow purchase'of welding 1 materials from material suppliers as defined in American Society of Mechanical Engineers (ASNE) Code-Interpretation. These changes did not result in a change to the Technical Specifications nor did they' create an unreviewed safety or environmental question. LECE: 88-29 Document: Regulatory Guide Policy Manual (RCPM), PCE-1028 142
i Status: Approved.Nov mber 29,'1988 and issued' Hay 10, 1989 asi Amendment 6. Safety Evaluation: The RCPM establishes PGE's position on WRC Regulatory Guides;which affect the operation, maintenance, refueling., and modifications' of the Trojan Nuclear Plant. The changes to the RCPM. incorporated subsequent comments as well as reflected In-House Positions (IHPs) for new or revised Regulatory Guides. The Safety Evaluation and the INPs were based on full compliance with the Trojan Technical Specifications. Any; conflicts were identified as-exceptions to the Regulatory Guides;-therefore,-no changes to the Technical Specifications were necessary. This LDCR has been determined to involve: no unreviewed safety questions or environmental matters and did not have an effect on any other licensing documents, commitments, or criteria. kECR: 88-30 Document: Trojan Nuclear Plant' Security Plan, PGE-1017 Status: Approved December 30, 1988 and issued January 9, 1989 as Revision 25. Safety Evaluation: Changes made to this document were not_considerec '<. be a degradation of Plant security and were implemented under 10 CFR 50.54(p); therefore, the Trojan Operating License and Technical Specifications. were not affected. LDCR: 88-32 Document: Final Safety Analysis Report (FSAR) Status: Due to the volume of changes involved,;LDCR 88-32 was divided into nine: individual change requests to provide approval by chapter and/or section. 'The last change request was approved April 11, 1989 and Amendment 9 to the FSAR was issued Apr11 28, 1989. Safety Evaluation: Pursuant to 10 CFR 50.71(e), annual revision of the FSAR is required to assure that the' information in the FSAR contains the latest material reflecting the design of the. Plant. All changes initiated with this LDCR were editorial.and/or administrative'in natute-and did not involve a change to the Technical Specifications or any unreviewed safety or environmental quest' ions. Any changes made in the facility, procedures : tests,-or analyses as described in the original FSAR have received prior NRC approval pursuant to 10 CFR-50.59(c) and 50.90, or were effected without NRC' approval based on a separate l 1 143
.....y x 1 t safety / environmental evaluation pursuant to 10 CFR 50.59(a), or were. required by WRC request-pursuant to 10 CFR 50.54(f) or (h). LDCR: 89-01 Document:= Wuclear Division Headquarters Training program,. 3 pGE-8009 Status: Approved February 22,'1989 and issued March 15, 1989 as Amendment 5. 'I Safety Evaluatio.D: This LDCR was initiated to reflect: (1) chen;,es in ' the Nuclear Division; (2) a change in the work location'of the Nuclear Quality Assurance-Department; (3) clarification of responsibilities; (4) editorial-changes-and corrections; (5) management assessment of the Training Program;-and.(6) corrective actions associated with Wonconforming Activity Reports. These. changes were purely; administrative and it was-determined that this LDCR involved ne unreviewed safety questions or environmental matters and:did not have an effect on any other licensing documents, I commitments, or criteria. LDCR: 89.02 Document: Final Safety Analysis Report ~(FSAR)-. 1 Statup_: Due to the volume of changes involved, LDCR 89-02-was divided-into nine individual change requests to provide approval by chapter _and/or'section. The last change request was approved August 25, 1989 and Amendment 10 to the FSAR was issued September 29, 1989. I Safety Evaluation: Pursuant to 10 CFR 50.71(e).. annual revision of the FSAR is required to assure that the information in j the FSAR contains the latest material reflecting the design-of the Plant. All changes initiated with this LDCR were editorial and/or administrative in nature and did not> involve:a change-to the Technical-i Specifications or any unreviewed safety or environmental. questions. Any changes made in the, facility,' procedures, tests, or analyses as described in the original FSAR have received. prior NRC approval pursuant to 10 CFR 50.59(c) and 50.90, or were effected without NRC' approval based on a separate safety / environmental evaluation pursuant to a 10 CFR 50.59(a), or were required by NRC request pursuant to 10 CFR 50.54(f) or (h). i i 144 i
LDCR: 89-03 Document: Regulatory' Guide Policy Manual (RGPM), PGE-1028 ' e' Status: Approved June 27, 1989 and' issued Septembor. 28, 1989 as Amendment 7. Safety Evaluation: The RGPM establishes PGE's position on NRC Regulatory Guides which affect the operation, maintenance, refueling, and modifications of the Trojan Nuclear Plant. The changes to the RGPM incorporated subsequent' comments as well as-reflected In-House' Positions (IHPs) for new or revised Regulatory-l Guides. The Safety Evaluation and the IHPs were a based on full compliance with the; Trojan Technical l Specifications. Any conflicts were identified-as exceptions.to the Regulatory Guides; therefore, no changes to the Technical Specifications werc' necessary. This.LDCR has been determined to involve l} no unreviewed safety questions or environmental I matters and did not have an effect on'any other-licensing documents, commitments, or criteria, j ~ LP.CR: 89-04 Document: Regulatory Guide Policy Manual (RGPM)', PGE-1028 Status: Approved'Harch 8, 1989 and issued as a part of 3 Amendment 6 on May 10, 1989. Safety Evaluatiqn: This.LDCR was initiated to incorporate PGE's In-House i. Position of Regulatory Guide 5.62, " Reporting on Safeguards Events", Revision 1. dated November 1987, into the Regulatory Guide Policy Manual. The Safety Evaluation and the IMPS were based on= full compliance j with the Trojan Technical Specifications. Any conflictss were identified as' exceptions to the-Regulatory Guides; therafore. no changes to the Technical Specifications were necessary. This LDCR has been determined to involve no unreviewed safety. questions or environmental matters and'did-not have an effect on any other licensing documents, commitments, or criteria; LDCR: 89-05 C Document: Trojan Nuclear Plant Security Plan, PGE-1017 Status: Approved February 22, 1989 and issued February 17, 1989 as Revision 26. G: 145 l.
Safety Evaluation: Changes made to this document were not considered to e be a degradation of Plant security and weret implemented under 10 CFR 50.54(p); therefore..the Trojan Operating License and Technical Specifications were not affected, q ggg: 89-06 q Document: Regulatory Guide Policy Manual (RGPM)..PGE-1028 Status: Approved April 12, 1989 and issued as a part of Amendment'6 on:May 10, 1989. l Safety Evaluation: This LDCR was initiated to incorporate PGE's In-House l Position of Regulatory Guide 8.32, " Criteria,for-Establishing a Tritium Bionssay Program",; Revision 0, dated July 1988;:into the Regulatory Culde. Policy.' . Manual. The Safety Evaluation and the IMPS were based on full compliance:with the Trojan Technical Specifications.. Any conflicts were. identified as. exceptions to the Regulatory Guides; therefore, no changes to the' Technical Specifications were i necessary. This LDCR has been determined'to_ involve l no unreviewed safety questions or environmental.. matters and did not have an effect on any other - licensing documents,- comitments, or critesia. -l @CB: 89-07 i Document: Trojan Radiological Emergency Response Plan, PGE-1008-Status _: Approved March 26, 1989 and issued March 31,11989 as Amendment 15. i Safety Evaluation: This LDCR was initiated to incorporate revision'of the Washington State Fixed Nuclear Facility Emergency Response Plan into Trojan-RERP. Changes consisted of-clarification and revision of the information Presented in the Trojan Radiological. Emergency Plan. The Emergency Plan is not referenced in the Technical' Specifications, except for the annual audit of-the-t Plan required by the TNOB; therefore, the Technical. 1 Specifications were not affected by this LDCR. The changes: involve 'no unreviewed safety or environmental. questions and did not affect any'other licensing. documents, comitments, or criteria. The-effectiveness of the Emergency Plan was not' decreased' and remains consistent with the standards of 10 CFR. 50.47(b). O 146 l
j LRp_R: 89-08 R Document: Nuclear Quality Assurance Program, PGE-8010 Status: Approved April 18, 1989 and issued April 26, 1989 as Q Interim Change 188-2. Safety Evaluation: This LDCR was initiated to reflect the reorganization I 'of PGE.into a Generating Division and an Energy _ Services Division, the reorganization of Security into a Nuclear Security Department supporting Trojan,_ updated requirements regarding QA Department review ~ 3 of Licensing Documents and QA Department personnel qualifications, and a clarified definition of " Quality Assurance Record". LRCE: 89-09 Document: Trojan Nuclear Plant, Fire Protection Plan, PGE-1012 Status: Approved June 14, 1989 and issued July 31, 1989 as Amendment 5. Safety Evaluation: This LDCR was initiated to reflect the completion of-Appendix R modifications, incorporate engineering evaluation references, miscellaneous updates, comments and cocrections made since'the last revision of PGE-1012 in October 1988. This'also satisfies the requirements of Title 10 to the Code of: Federal Regulations, Part 50.71(e) [10 CFR 50.71(e)), which n requires periodic update of the Final Safety Analysis-(FSAR)..PCE-1012 is incorporated in its entirety by s reference in Section 9.5.11of the FSAR and serves as the FSAR description of the Fire Protection Program I at Trojan. This change did not involve a change to. j the Technical Specifications nor did it_ involve any-unreviewed safety or environmental questions. LRCR: 89-10 Document: . Regulatory-Guide Policy Manual (RGPM), PGE-1028 1 1 Status: _ Approved July 31, 1989-and issued September 28, 1989 1 as Amendment 7, I 4 -Safety Evaluation: The RGPM establishes PGE's position on NRC Regulatory Guides which affect.the operation, maintenance, refueling, and modifications of the Trojan' Nuclear Plant. The changes to the RGPM incorporated subsequent comments as well as reflected In-House Positions (IHPs) for new or revised Regulatory Guides. The Safety Evaluation and the IHPs were 1 147 i -I
s based on full. compliance 'with the Trojan Technical' l Specifications. Any conflicts were identified as-exceptions to the Regulatory Guides; therefore, no-changes to-theLTechnical Specifications were necessary. 'This LDCR has been determined to involve no unreviewed safety questions or environmental matters and did not have an effect on any.other licensing documents, commitments, or criteria. LDCR: 89-11 Document: Final Safety Analysis Report (FSAR) Status: Approved May 22, 1989 and issued on July. 31, 1989 as part of Amendment 10. Safety Evaluation: This LDCR was initiated to reflect Nuclear Division reorganization required to assure that the-information in-the FSAR contains the latest material reflecting ~the design of the Plant. All changes initiated with this LDCR were editorial-and/or administrative in nature and'did not involve a change to the Technical Specifications or any unreviewed safety or environmental questions. Any changes made in the facility, procedures, tests, or analyses as, described in_the original FSAR'have received prior NRC approval pursuant to 10 CFR 50.59(c) and 50.90,: or were effected without NRC approval based on a separate safety / environmental evaluation pursuant:to 10 CFR 50.59(a), or were required by NRC request. pursuant to 10.CFR 50.54(f) or (h). LDCR: 89-12 Document: Trojan Radiological Emergency Response Plan, PGE-1008 Status: Approved May 17, 1989 and issued May 19, 1989 as-Amendment 16. Safety Evaluation: Change incorporated new procedures for the: Oregon Emergency Operations Center-(Oregon State Plan)~. The Emergency Plan is not-referenced-in the Technical-Specifications, except for the annual. audit of the - Plan required by the TNOB; therefore, the Technical-Specifications were not affected by this LDCR.: The' ~ changes involve no unreviewed safety or environmental questions and did not affect any other' licensing: documents, comitments, or criteria; _The effectiveness of the Emergency Plan was not decreased and remains consistent with the standards'of 10 CFR 50.47(b)'. O 148 1 h
S e LDCR: 89-17 1 Document: Regulatory'Cuide Policy Manual (RGPM), PGE-1028 Status: Approved June 27, 1989 and issued as a part ofE Amendment 7 on September'28, 1989. Safety Evaluation: This LDCR was initiated to revise PGE's.In-House. Position of Regulatory Guide l'.61, " Damping Values for Seismic Design of Nuclear Power Plants",-Revision 0, dated October 1973. The Safety Evaluation and the IHPs were based on full compliance with the Trojan Technical Specifications. Any conflicts were identified as exceptions to the Regulatory Guides; therefore, no changes to the Technical Specifications-1 were necessary. This LDCR has been determined to e involve no unreviewed safety questions or i environmental matters and did not have an effect on any other licensing documents,' commitments, or criteria. LELR: 89-18 Document: Regulatory Guide Policy Manual-(RGPM), PGE-1028' Status: Approved June 26, 1989 and issued as a part of Amendment 7 on September 28, 1989. Safety Evaluation: This LDCR was initiated to incorporate PGE's In-House' Position of Regulatory Guide 3.62, " Standard Format-and Content for.the Safety Analysis. Report for On-Site Storage of Spent Fuel Storage Casks", Revision 0, dated February 1989. The Safety _ Evaluation and the IHPs"were-based on' full: compliance with the Trojan Technical Specifications. Any conflicts were identified as exceptions to the Regulatory Guides; therefore, no changes to the Technical-Specifications were necessary. This LDCR-has been determined to involve no unreviewed' safety questions-or environmental natters and did not have. ~ an effect on any other licensing documents, commitments, or criteria.- LDgR: 89-19 Document: Trojan Nuclear Plant, Fire Protection Plan, PGE-1012 Status: Approved November 27, 1989 and issued December 29, 1989 as Amendment 6. Safety Evaluation: This LDCR was initiated to reflect the completion of Appendix R modifications, the reanalysis of the alternative shutdown methodology, miscellaneous updates, comments and corrections made since the last 149
revision of PCE-1012 in= July 1989. This change-O satisfies a commitment to the NRC to update the description of the Hydrogen Supply = System. This'also satisfies the requirements of Title'10.to the Code of' Federal Regulations, Part 50.71(e) (10 CFR 50.71(e)), which requires periodic update of the Final' Safety : ' Analysis (FSAR). PGE-1012'is incorporated in its entirety by reference in'Section 9.5.1 of the FSAR and serves as the FSAR description of,the Fire. Protection Program at Trojan. This. change did not -1 involve a change to the Technical Specifications nor did it involve any unreviewed safety or environmental- < 3 questions. kp.CB: 89-23 Document: Trojan Radiological Emergency Response Plan, PGE-1008' j Status: Approved August 22, 1989 and' issued July 17,1989 as Amendment 17. Safety Evaluation: This.LDCR was issued to incorporate changes requested by Cowlitz County to the Cowlitz County. Emergency Operations Center procedures. The Emergency Plan is not referenced in the Technical; Specifications, except for the annual audit of the Plan required by-the TNOB; therefore, the Technical. Specifications. i were not affected by this LDCR. The changes involve no unreviewed safety or environmental < questions and 'l did not affect any-other licensing documents,- commitments, or criteria. The effectiveness of the Emergency Plan,was not decreased and. remains = consistent with the standards of.10 CFR 50.47(b). LDCR: 89-24 Document: Trojan Radiological Emergency Response. Plan, PGE-1008 Status: Approved August 31, 1989 and issued October 20, 1989 as Amendment 18.- Safety Evaluation: This LDCR was. issued to~ incorporate 1 changes requested A by Oregon State for:the Oregon State Plan and-Procedures portion of the. Radiological. Emergency
- j Response Plan. The Emergency Plan-is not. referenced in the Technical Specifications, except for the annual audit of the Plan required by the TWOB;.
therafore, the Technical' specifications were nota affected by this LDCR. The changes involve no unreviewed safety or environmental questions-and did not affect any other licensing documents, commitments, or criteria. The effectiveness of the 0-Emergency Plan was not decreased and' remains consistent with the standards of 10 CFR 50.47(b)'. i 150 .q
) LDCR: 89-25 .1 Document: Trojan Radiological Emergency Response Plan, PGE-1008 i Status: . Approved September. 21, 1989_and issued October 27, 1989 as Amendment 19. (1 Safety Evaluation: This LDCR was issued to incorporate changes required as a result of the Nuclear Division move to the Trojan (i.e.' the relocation of the company Support Center to the Trojan North Building). Also included' were changes related to new or revised responsibilities and clarification of information presented in the Trojan Radiological Emergency Plan. The Emergency Plan is not referenced-in.the Technical Specifications, except for the annual audit of the Plan requirsd by the.TNOB; therefore, the Technical Specifications were not affected by this LDCR. the changes involve no unreviewed safety or environmental-questions ard did not affect any other licensing docunents, commitments,-or criteria. -The effectiveness'of the. Emergency Plan was not decreased and remains consistent with the standards of 10 CFR 50.47(b). LDCR: 89-26 Document: Trojan Radiological Emergency' Response Plan, PGE-1009 9 Status: Approved October 24, 1989 and. issued October 25, 1989 as Amendment 20. Safety Evaluation: This LDCR was issued to incorporate changes: requested by Columbia County relating to the Columbia County. Portion of the Radiological Emergency Plan. The -Emergency Plan is not referenced?in the Technical Specifications, except.for the annual audit of the s Plan required by.the TNOB; therefore,Jthe Technical' Specifications were not affected by.this LDCR. The changes involve no unreviewed safety or environmental questions and did not affect any.other licensing documents, commitments, or criteria. The. l I effectiveness of the Emergency Plan was not decreased and remains consistent with the standards of 10 CFR 50.47(b). LDCR: 89-27 i; Document: Inservice Inspection Program for the Second 10-Year Interval, PGE-1049 .r Status: Approved September 29, 1989 and issued October 10, 1989 as Amendment 1. t 151
y 1: Safety Evaluation: This LDCR was initiated to extensively revise and. expand the Inservice Inspection Program to provide additional ciatails and to reflect the 1986 American Society of Mechanical Engineers (ASME).Section XI Criteria for Class 2 Welds. -These changes did not" result in a change to the Technical Specifications. nor did they create an unreviewed safety or environmental question., LDCR: 89-28 = I Document: Trojan Nuclear Plant Security Plan, PCE-1017 1l Status: Approved October 2, 1989 and issued October 17, 1989-as RevisionJ27. .i Safety Evaluation: Changes made to this document were nct considered to' be a degradation of Plant security and were implemented under 10. CFR 50.54(p); therefore, the Trojan: Operating License and. Technical Specifications were not affected, l i LDCR: 89-31 Document: Final-Safety Analysis Report (FSAR) 0.- Status: Approved November 16, 1989 and= issued on December 29, 1989 as part of Amendment 12. j Safety Evaluation: This LDCR was initiated to reflect-Nuclear Division-4 reorganization. :All chant,esLinitiated with this LDCR _were editorial and/or-administrative in' nature and did not involve a' change to the Technical Specifications or any unreviewed safety or 'l environmental questions. Any r.hanges made in the i facility, procedures, tests, or analyses _as described in the original'FSAR have received prior NRC approval ? pursuant to 10 CFR-50~59(c) and'50.90,-or were offected without-NRC approval. based on a separate safety / environmental evaluation pursuant.to ~ 1 10 CFR 50.59(a), or were required by NRC request pursuant to-10 CFR 50.54(f) or (h). J LDCR: 89-32 Document: Inservice Testing Program for Pumps and Valves for the Second 10-Year Interval, PGE-1048 Status: Approved November 16, 1989 and issued November 17, 1989 as Amendment 2. O 152
t Safety Evaluation: Changes consisted of a general' upgrade of the Inservice Testing.(IST) program including editorial L corrections, clarifications 'and additional testing requirements to provide greater assurance of equipment operability. Also included in-this upgrade' 'l was the implementation of guidance provided in i Generic Letter 89-04, " Guidance on Developing Acceptable Inservice Testing Programs", dated April 3, 1989. The changes involved no unreviewed safety or environmental questions nor did they result. in a change to the Technical Specifications. RCR: 89-33 C Document: Final Safety Analysis Report (FSAR) Status: Approved November 16, 1989 and issued on December 23,- i 1989 as part of Amendment 12. l i Safety Evaluation: This LDCR was initiated to reflect the reorganisation i of the Operations and Maintenance Department into two l separate departments.- All changes initiated with this LDCR were editorial and/or administrative in nature and did not involve a change to the Technical Specifications or any unreviewed safety or environmental' questions. Any changes made in the facility, procedures, tests,.or analyses'as described in the original FSAR have received prior NRC approval. pursuant to 10 CFR 50.59(c) and 50.90,;or were y effected without NRC approval based on a separate-safety / environmental' evaluation pursuant.to 10 CFR 50.59(a), or were required by NRC request' I pursuant to 10.CFR 50.54(f) or (h). .j LDCR: 89-35 Document: Final Safety' Analysis Report (FSAR) 1 Status: Due to the volume of' changes involved, LDCR 89-35 was divided into seven individual change requests to provide approval by chapter and/or_section. The last change request was approved. December:15, 1989 and Amendment 12 to the FSAR was issued' December 29, 1989.. Safety Evaluation: Pursuant to 10:CFR 50.71(e), annual revision of.:the-FSAR is required to assure that the information in' the FSAR contains the latest asterial' reflecting the -I design of the Plant. All changes initiated with this LDCR were editorial and/or administrative in nature and did not involve a change to the Technical Specificati.ons or any unreviewed safety or environmental questions. =Any changes made in the i facility, procedures, tests, or analyses as described 153
in the original-FSAR have received prior NRC approval O. . pursuant to 10 CFR 50.59(c) and 50.90, or were effected without NRC approval based on a separate safety / environmental evaluation pursuant to. 10 CFR 50.59(a), or were required by NRC request pursuant to 10 CFR 50.54(f) or'(h). kpg: 89-37 Document: Regulatory Guide Policy Manual (RGPM), PGE-1028 l Status: Approved October 26, 1989 and' issued as a part=of' -Amendment 8 on January 31,-1989. Safety Evaluation: This LDCR was initiated to revise PGE's In-House, Position of Regulatory Guide 1.134 " Medical Evaluation of Nuclear Power. Plant Personnel'. Requiring - i Operator Licenses" Revision 2, dated April 1987... The Safety Evaluation and the IHPs were based.on full I compliance with the Trojan Technical Specifications. Any conflicts were identified as exceptions to thel Regulatory Guides; therefore,-no changes to the Technical. Specifications were necessary. This LDCRL has been determined to involve no unreviewed safety-questions or environmental matters and did not have an effect on any other licensing documents, I commitments, or criteria. LDCR: 89-40 q, Document: Report on Design Modifications for. the Trojan Control j Building, PGE-1020 i i Status: Approved December 6,.1989 and issued December 8, 1989 as Amendment 5. I Safety Evaluation: This LDCR was initiated to correct a referenced-specification.in the Codes and Standards.section of this topical report. The change involved:no unreviewed safety or environmental questions nor did they result in a. change'to the Technical-Specifications. LDCR: 89-43 Document: Trojan Security Force Training and Qualification-Plan, PGE-1024 i Status: Approved December 9, 1989 and issued December 27, 1989 as Amendment 7. O 154
Safety Evaluation: Changes to this document were not considered to be a' degradation'of Plan security'and were implemented under 10 CFR 50.54(p);. theref ore, the Trojan- = operating License and Technical Specifications were not affected, k{tQR: 89-44 Document: Regulatory Guide" Policy Manual (RGPM), PGE-1028' Status: Approved December 10. 1989 anc issued as part of Amendment 8 on January 31, 1990. Safety Evaluation: This LDCR was initiated to establish'PGE's In-House Position of Regulatory Guide l.120. " Fire Protection, Guidelines for. Nuclear Power Plants". Revision.1, dated November'1977. The Safety Evaluation and the IHPs were based on full compliance with the Trojan Technical Specifications. Any conflicts were. identified as exceptions.to.'the Regulatory Guides;.- therefore, no changes to the Technical Specifications.: were necessary.- This LDCR has'been determined to involve no unreviewed safety questions or.. l environmental matters and'did not have an effect on, any other licensing documents, comitments,' or = criteria. l LDCR: 89-45 Document: Operating Experience Review Program, PGE-1044 l Status: Approved November 22, 1989 and' issued December 5, 1989 as Amendment 3. I Safety Evaluation: This LDCR was initiated to incorporate outstanding deviations, coments, and commitments: and to-provide j greater detail. The changes' involved no unreviewed safety or environmental questions nor did they result in a change.to the Technical Specifications'. l LDCR: 89-46 Document: Final Safety Analysis Report (FSAR) Status: Approved December 19, 1989 and issued on December-29.- i 1989 as part of Amendment 12. i Safety Evaluation: This LDCR was initiated'to reflect the reorganizational relocation of the Training j -Department to report directly to the General Manager. All changes initiated with this LDCR were editorial and/or administrative in nature and did not involve any unreviewed safety or environmental. questions or a change to the Technical = 155 i
v; si Specifications.- However, this LDCR is the result of 4 NRC approval and issue of Operating License Amendment' 155, dated November 6, 1989.- Any changes-made in thef facility, procedures,' tests, or analyses as-described in the original FSAR have received prior NRC approval pursuant to 10 CFR 50.59(c) and 50.90, or were-effected without NRC approval-based on a separate -safety / environmental evaluation pursuant to 10 CFR 50.59(a), or were required by NRC request pursuant to 10-CFR 50.54(f) or (h). LDCR: 89-30 Document: Content and Level'of. Detail Criteria for Design Basis Documents, PCE-1055. Status: Approved December 15, 1989 and issued December 15,- '1989 as new document (preliminary issue). Safety Evaluation: This document was initiated to provide detailed guidance for the preparation and revision of Design Basis Documents (DBDs) and established consistent-criteria regarding-the content and level of detail of the DBDs. Contents of this document involved'no unreviewed safety or environmental questions nor did-j they result in a change.to the Technical ]? Specifications. LDCR: '89-51 Document: Technical. Specification Bases Change j Status: Approved December-19, 1989 and issued December 19, 1989. Safety Evaluation: This LDCR was-initiated to define that the phrase ~ " recirculation mode of operation" means stop1 operation of CB-2 and maintain both trains of CB-1 in a lineup capable of responding to a safety injection signal. This change involved no unreviewed safety or environmental questions'nor did it result in a change-to the Technical Specifications. Note: In accordance with NRC letter dated March 23, 1988, " Bases to the Technical Specifications are not considered to be a part of the. Technical-W, Specifications. As such, request for NRC approval of' j proposed revisions to the Bases-which do not 1 necessitate changes.to the. Technical Specifications need not be submitted as an amendment to the Facility. ] Operating License."- 1! 9 156 ..s
l I 6.D Plent Tests i ( I The following plant tests were performed in 1989 and are reported in i accordance with Title 10, Code of Federal Regulations, Part 50.S9. 1. Tomorary Plant Test 175 ) This temporary plant' test (TPT) was perfomed to facilitate termination of monf toring and procedure close-out. This test.did l not involve an unreviewed safety question or a change to the Trojan Technical Specificatione. 2. Tomorary Plant Test 256 { This TPT was perfomed to verify Residual Heat Removal flowrates as 3 calculated by Calculation TM-169, Revision 3. This test did not involve an unreviewed safety question or a change to the Trojan f Technical Specifications. 3. Tomorary Plant Test 261 I This IPT was performed to authorize temporary installation, additional monitoring, update personnel, clarify calibration, and l 4 add as-built drawings (sketches) for pressuriser surge line monitoring. This test did not involve an unreviewed safety question l or a change to the Trojan Technical Specifications. 4. Tomorary Plant Test 263 This TPT was performed to inspect pipe whip restraints and adjacent pipe supports to evaluate potential contacts of the process pipe with the pipe whip restraints. This was originally initiated in la88. In the 1989 Plant Review Board los this entry is listed as a deviation. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. l 5. famoorary Plant Test 270 This TPT was pod ormed because many annunciator points her.< more [ than one wire laid down on each terminal in Panel C21. TLis test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. 6. Tomorgy Plant Test 279 i This TPT was performed to energize and test power sources, power [ distribution and power supplies for the new annunciator system. This test did not involve an unreviewed safety question or a change to the Trojan Technicr1 Specifications. i I V i a 157
f i 7. Temporary Plant Test 280 This TPT was performed to ensure that all components and functions of the new annunciator's microprocessor-based computer subsystem perform correctly. This test did not' involve an unreviewed safety question or a char.se to the Trojan Technical Specifications. 8. Temporary Plant Test 281 4 This TPT was perforned to ensure that all inputs to remote multiplexers are interpreted correctly by the central control unit and the correct alarm messages are output on the alarm CRTs and printers. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. 9. Temporary Plant Test 285 I This TFT was performed to verify the accuracy of a new flowmeter.and orifice plate installed by Plant Configuration Change (PCC) 88-525. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. 10. Temporary Plant Test 292 This TPT was perforned to test changes in Auxiliary Feedwater (AFW) Pump control Room Halon System piping and detection made by Request for Design Change (RDC) 85-052 Design Change Packages (DCPs) 17 and 19. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. 11. Temporary Plant Test 294 This TPT was performed to provide a means to calibrate the reactor coolant system loop narrow range and wide range Resistance Temperature Detectors. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. 12. Temporary Plant Test 295 This TPT was perforwed to test CBH-1 duct / housing leakage as committed to by Licensee Event Report (LER) 88-018,iRevision 1 corrective action. It also performed airflow verification test of CBN-1 as committed to by PGE Nemorandum CAO-391-88, December 8, 1988 L (CB-1 Action Plan). This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. 13. Temporary Plant Test 296 This TPT was performed to leak test check valves 8948 A, B, and D during cooldown prior to the 1989 refueling outage. This test did. not involve an unteviewed safety question or a change to the Trojan. Technical Specifications. 1 4 158 m
i j l f 14 Temporary Plant Test 299 O This TPT was performed to determine if excessive leakage is occurring through the heater drain pump recirculation valves j (CV-2773 A/B). This test did not involve an unreviewed safety l l question or a change to the Trojan Technical Specifications. i I i 15. Temporary Plant Test 300 This TPT was perforned to generate accurate steam generator volume j and level curves for control Room Curves and Tables Reference Manual. This test did not involve an unreviewed safety question or j a chante to the Trojan Technical Specifications. 16. Temporary Plant Test 301 This TPT on collection of containment air temperature and instruments installed under Temporary Modification (TM) 88-071, Revision I was cancelled. 17. Temporary Plant Test 302 This TPT was performed to quantify the flowrate past the CV-3004 i valves While being closed. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. 18. Temporary Plant Test 304 This TPT was performed to test CB-1 duct / housing leakage as committed to by LER 88-018, Revision 1 corrective action. It also performed airflow verification test of CB-1 as committed to by PGE Memorandum CAO-391-88, December 8, 1988 (CB-1 Action plan)..This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. t l 19. Temporary Plant Test 305 This TPT on collection of containment air temperature and instruments installed under TH 88-071, Revision I was cancelled. 20. Temporary Plant Test 306 This TPT was performed to provide base-line test data for rewound east circulating water pump motor, MP-107B (6500 HP $ 12 kW). This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. 21. Temporary Plant Test 307 This TPT was performed to inject helium into pressurizer vapor space sample line to check for system leaks. This test did not involve an unreviewed safety question or a change to the Trojan Technical Ot Specifications. 4 159
~ _-. 22. Temporary Plant Test 308 O1 This TPT was performed to determine if the new after-filter elements (0.3 micron) will operate norina11y in the instrument air system prior to full implementation of Spare Parts Equivalency Evaluation Report (SPEER) 89-023. This test did not involve an unreviewed { safety question or a change to the Trojan Technical Specifications. 23. Temporary Plant Test 309 i This TPT was performed to obtain data during potential steam dump system evolutions during start-up. This test did not involve an i unreviewed safety question or a change to the Trojan Technical Specifications. ] 24 Iemporary Plant Test 312 1 This TPT was performed to test annunciator circuit K20 F.2 " Accumulator tank SI pump or RWS tank valve still not full open." J This test did not involve an unreviewed safety question or a change i to the Trojan Technical. pecifications. l j 25. Temporary Plant Test 313 l -) This TPT was performed to verify the accuracy of a new flowmeter (FI-5953) and to verify the discharge flow and pressure of the electric and diesel fire pumps at shutoff, rated, and peak loads. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. 26. Temporary Plant Test 315 This TPT was performed to verify proper operation of the Positive Displacement Pump (PDP) motor after work is completed by RDC 88-012, DCP 4 which added an alternate power feed to.the PDP motor from ) breaker A112. This test did not involve an unreviewed' safety question or a change to the Trojan Technical. Specifications. 27. Temporary Plant Test 316 r This TPT was performed to add boric acid to the secondary side of the steam generators. This test did not involve an unreviewed L safety question or a change to the Trojan Technical Specifications. l 28. I.glporary Plant Test 321 l This TPT was performed to conduct a normal fast start of ths AFW-i I pump turbine once a day for approximately a one week period. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. 29. Temporary Plant Test 327 e' This TPT was perfor1ned to complete the channel calibration l l requirements for TTS 4.4.3.2.1. .This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. 160 i
I 6.2 CHANGES TO PROCEDURES O + Procedures described in the Trojan Final Safety Analysis Report (FSAR) are used by the Trojan Plant Operating Staff and by various offsite support organizations of Portland General Electric Company. These i procedures are described in the Trojan FSAR Section 13.5, Plant Procedures, and Section 17.0, Quality Assurance. In 1989, the following l organizations made changes to safety-related procedures in accordance with Title 10. Code of Federal Regulations, Part 50.59 (10 Crt 50.59), and concluded that none of the changes involved unreviewed safety questions: Trojan Nuclear Plant muclear Division Wuclear Safety & Regulation Nuclear Plant Engineering Wuclear Quality Assurance Power and Fuels Contracts Nuclear Security Corporate Records I Environmental Services Changes to procedures were generally either administrative or technical in nature. Administrative changes consisted of title, organizational, and editorial changes, while technical changes were the result of system or component modifications, license amendments, or improvements in O j procedural processes, A safety evaluation was conducted for each change, in accordance with l 10 CFR 50.59, and was reviewed and approved by the appropriate personnel. The review concluded that the probability of occurrence or consequences of an accident or equipment malfunction were not increased, j there was no reduction in any Plant safety margins, and the possibility of an accident or malfunction not previously evaluated was not increased. r b
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w. i ( 6.F SETPOINT CHANGES The following setpoint changes were made in 1989 to instruments, alarms, l relief valves, and other control and protective devices whose setpoints are described in the Final Safety Analysis Report (FSAR) and are reported i in accordance with Title 10. Code of Federal Regulations. Part 50.59 1. Plant Setpoint Chante 89-0,91 New flow switch accuracy information was received from Westinghouse that included an evaluation of post-seismic instrument uncertainty. The Residual Heat Removal:(RHR) miniflow switch open setpoint was } changed from 500 gallons per minute (spa) to 750 spm and the close j setpoint was changed from 1000 gpm to 1401 spm. ] This change was made to the minimum flow recirculation setpoints to assure that the safety function of protecting the RHR pumps is retained even with an additional 10 percent uncertainty in the flow j switch setpoints. This setpoint change did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. 2. Plant Setcoint Chante 89-014 O Overtemperature delta temperature setpoints in the reactor protection system were changed in support of Trojan Operating License Amendment 153 relating to upgraded fuel design (see Table 6.B-1 of this report). This setpoint change did not involve a change to the Trojan e Technical Specifications or an unreviewed safety question. i 3. Plant Setpoint Chante 89-016 An inadequate margin existed between the safety analysis limit of 1.38 and the overtemperature delta temperature baseline (K ) 1 value. To account for instrument uncertainty and to stay within the accident analysis, a K1 revision was required. The reactor protection overtemperature delta temperature setpoint was changed to reflect a new Kg value as calculated using e revised safety limit provided by the vendor. This Plant Sotpoint change supersedes the change reported above (Plant Setpoint Change 89-014). This setpoint change did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. 162
4. Plant Setroint Chante 89-019 Nonconformance Report (NCR) 89-293 identified that, "The existing instrument setpoints are not adequate because they do not include the additional sensor drift that can occur in the time period between calibrations." The Residual Heat Removal (RHR) minimum flow valve switch setpoints were evaluated in a PGE in-house calculation that recommended revision of setpoints to account for drift and seismic uncertainty. The RHR miniflow switch open setpoint was changed from 750 gpm to 802 spm and the close setpoint was changed from 1401 spm to 1374 spm. This change was made to the minimum flow recirculation setpoints to assure that the safety function of protecting the RHR pumps is { retained even with an additional 10 percent uncertainty in the flow switch setpoints. This setpoint change did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. 5. Plant Setpoint Chante 89-022 A setpoint change was required by the vendor. This change would ensure that the loop temperature imbalance does not reduce the margin of safety as defined in the basis for any Technical Specification. The effect of this change was to not allow a bonus-to the overtemperature delta temperature (OTAT) setpoint based on a normal average Reactor Coolant System (RCS) temperature (Tay,) in the loops which are below the high loop T ave-Loop "A" OTAT setpaint was changed from 584.7'F to 581*F in i accordance wit.h vendor recommendations. This setpoint change did not involve a change to'the Trojan Technical Specifications or an unreviewed safety question. 6. Plant Setooint Chante 89-023 A setpoint change was required by the vendor. This change would l ensure that the loop temperature imbalance does not reduce the margin of safety as defined in the basis for any Technical Specification. The effect of this change would provide a penalty to the overpower delta temperature (Op4T) setpoint starting at temperatures equal to the particular loop full power T.,,, instead of starting at 584.7'F. Loop "A" OPAT setpoint was changed from 584.7'F to 581*F in accordance with vendor reconsnandations. l This setpoint change did not ' involve a change to the Trojan Technical Specifications or an unreviewed safety question. 163
_~ .l 7. Plant Setooin+ Chante 89-024 [ i A setpoint change was required by the vendor. This change would j ensure that the loop temperature imbalance does not reduce the margin of safety as defined in the basis for any Technical i specification. The effect of this change was to not allow a bonus i to the overtemperature delta tagerature (OTAT) setpoint based on i a normal average Reactor Coolant System (RCS) tagerature (Tave) I in the loops which are below the high loop Tay,. Loop "B" OTAT setpoint was changed from 584.7'F to 582.6*F in accordance with vendor recommendations. 4 This setpoint change did not involve a change to the Trojan Technical Specifications or en unreviewed safety question. 8. plant Setpoint chante 89-025 A setpoint change was required by the vendor. This change would ensure that the loop temperature imbalance does not reduce the margin of safety as defined in the basis for any Technical Specification. The effect of this change would provide a penalty [ to the overpower delta tenerature (0 PAT) setpoint starting at temperatures equal to the particular loop full power Tay,. instead of starting at 584.7'F. Loop "B" OPAT setpoint was changed from 584.7'F to 582.6'F in accordance with vendor recomendations. This setpoint change did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. 9; plant Setpoint Chante 89-026 A setpoint change was required by the vendor. This change would ensure that the loop temperature imbalance does not reduce the margin of safety as defined in the basis for any Technical Specification. The effect of this change was to not allow a bonus to the overtemperature delta temperature (OTAT) setpoint based on a normal average Reactor Coolant System (RCS) temperature (T,y ) in the loops which are below the high loop Tave-10. Plant Setpoint Chante 89-027 1 A setpoint chenge was required by the vendor. This change would ensure that the loop temperature imbalance does not reduce the margin of safety as defined in the basis for any Technical l Specification. The effect of this change would provide a penalty to the overpower delta temperature (0 PAT) setpoint starting at temperatures equal to the particular loop full power T y,, a instead of starting at 584.7'F. O 164
~ Loop "C" OPAT setpoint was changed from 584.7'F to 581.7'F in accordance with the vendor. This setpoint change did not involve a change to the Trojan Technical Specifications or an unreviewed safety question, r n f 1 4 P i e t i t i e: 1 165 .}}