ML20204H496
| ML20204H496 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 01/22/1986 |
| From: | Rey H PUBLIC SERVICE CO. OF COLORADO |
| To: | Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| P-86454, TAC-62126, NUDOCS 8608080129 | |
| Download: ML20204H496 (31) | |
Text
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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION i
ANNUAL REPORT OF CHANGES, TESTS, AND EXPERIMENTS NOT REQUIRING PRIOR COMMISSION APPROVAL PURSUANT TO 10CFR50.59 January 23, 1985, through January 22, 1986 Y )'\\
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h 2-TABLE OF CONTENTS i
i Section Title Page Introduction......................................................
3 1.0 Public Service Company Change Notices (CN).....................
6 2.0 Public Service Company Tes ts (T-Tests)........................ 22 3.0 GA Technologies Requests for Test (RT-Tests)..................
30 4.0 Procedures.................................................... 31 1
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1 m INTRODUCTION This report is submitted to comply with the requirements of Part 50.59 of Title 10, Code of Federal Regulations (10CFR50.59) as they apply to Fort St. Vrain Nuclear Generating Station, Unit No. 1.
It includes the period of January 23, 1985, through January 22, 1986.
The following definitions of major terms used in this report may be helpful:
Change Notice - A document containing installation, inspection and testing requirements, design background information, and design document updating requirements which specify the design control requirements applicable to a plant modification and authorizes changes to "as-built" plant design documentation.
"T" Tests - Tests proposed and conducted by Public Service Company of Colorado.
"RT" Tests - Tests proposed by GA Technologies and conducted by Public Service Company of Colorado.
In this report, the safety evaluation for the changes, tests, and experiments is summarized.
The terminology used in these summaries is defined as follows:
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-. Safety Related Items Those plant systems, structures, equipment, and components which are identified in the FSAR, as detailed and supplemented by applicable P & I, IB and IC diagrams, E and E-1203 schematic diagrams, the Cable Tab and SR-6-2 and SR-6-8 lists to include the following:
a)
Class 1 per the updated FSAR, Table 1.4-1.
b)
Safe shutdown components per the updated FSAR, Table 1.4-2.
c)
Alternate cooling method (ACM) equipment.
Safety Significant Change Changes to the facility, systems, components, or structures as described in the FSAR that may do any one of the following:
a)
Affect their capability to prevent or mitigate the consequences of accidents described in the FSAR, b)
Result in exposures to plant personnel in excess of occupational limits, or c)
Changes in the safety related systems which involve the addition, deletion, or repair of components, structures, equipment, or systems such that the original design intent is changed (i.e.,
changes in redundancy, performance characteristics, separation, circuitry logic, control, margins of safety, safe shutdown, accident analysis, or any change that would result in an unreviewed safety question or l
require a Technical Specification change).
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. Unreviewed Safety Question Any plant modification or activity is deemed to involve an unreviewed safety question as defined in 10CFR50.59 if:
a)
The ' probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR may be increased, or b)
The possibility of an accident or malfunction of a different type than any evaluated previously in the FSAR may be created, or c)
The margin of safety as defined in the basis for any Technical Specification is reduced.
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. 1.0 PUBLIC SERVICE COMPANY CHANGE NOTICES All CN's will be listed in the following order:
First - CN number.
Second - system /ccr anent number.
Third - descript' of the change.
Fourth - summa,y of safety evaluation.
CN-1272A, B System 92/ Electrical Power System This modification established separate power sources to the two (2) computer power distribution panels (N-9296 and N-9297) located in Building 10.
N-9296 will be powered from battery charger / inverter N-9255 located in the 480 Volt Room, and N-9297 will be established by replacing the existing Data Logger Power Inverter, I-93107, with inverter N-9234 (formerly Instrument Power Inverter 1A, which was removed from service during the 1984 refueling outage).
FSAR Figures 8.2-14 and 8.2-20 of the FSAR have been updated to indicate these changes. This modification was safety related but does not alter the operation or function of the electrical power system, therefore, it was determined not to be safety significant and did not involve or create an unreviewed safety question.
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. CN-1354 System 53/ Extraction Steam System This modification removed the valves which provided the building heating system with extraction steam.
The building heating system will continue to be supplied by the 150 psig steam header which is su) plied by either the auxiliary boiler, cold reheat steam, or tie bypass flash tank depending on plant conditions.
FSAR Section 9.10.1 has been updated to reflect this change.
This modification was non-safety related and was determined not to be safety significant and did not involve or create an unreviewed safety question.
CN-1368 Systems 73/ Reactor Plant Ventilation System This modification was done in an attempt to enhance the cooling below the PCRV, changing ducting and installing fans.
This ventilation system is not required for safe shutdown.
FSAR Section 6.2.3.2.5 'of the FSAR has been updated to reflect the modification of the reactor plant ventilation system.
This activity was safety related -because of attachment to building steel, but it was determined not to be safety significant and did not. involve or create an unreviewed safety c4uestion.
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. CN-1502 Various Plant Systems This change notice updates documents to indicate those items required for safe shutdown, adds relays to the safety related data base and establishes environmental certification sheets.
Tagging of instrumentation is the only installation work associated with this activity.
FSAR Sections:
1.4.5.4, 1.4.6, B.5.2.7, and I.6.2 have been updated to reflect the documentation changes. This activity was safety related but was determined not to be safety significant and did not involve or create an unreviewed safety question.
CN-1603 System 75/ Turbine Building (Vents and Drains)
The modification replaces the control room emergency makeup filter (F-7502) with a new filter which meets or exceeds the standards of the existing filter.
FSAR Section 7.4.1 has been revised to more accurately describe s.
the control room makeup filter. Therefore, this modification was safety
- related, but it was determined not to be safety significant and did not involve or create an unreviewed safety question.
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. CN-1624 System 11/ Reactor Vessel and Internal Components This modification rerouted moisture monitor tubing within penetrations B-1 and B-6.
The operation of the moisture monitors is unchanged by this modification.
FSAR Figures 7.3-21 and 5.8-14 have been updated to show compression fittings and capping of the moisture monitor test facility line.
This activity was safety related but was detern-:ned not be safety significant and did not involve or create an unreviewed safety question.
CN-1629A System 92/ Electrical Power System - Current Limiting Reactors This modification installed current limiting reactors on the power feed of each of the eight (8) 480 volt motor control centers (MCCs) powered by an essential 480 volt bus. These l
current limiting reactors will increase the reliability of the MCCs.
FSAR Figure 1.2-6 has been updated to show the location of the current limiting reactors within the plant.
This modification r
was safety related but was determined not to be safety i
significant and did not involve or create an unreviewed safety l
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. CN-1639 System 61, 62, 23/ Decontamination System, Liquid Waste System, Helium Purification System This modification installs new lines to allow the decontamination system to receive, store and process liquid waste from the helium purification
- system, specifically the helium purification coolers, and from the liquid waste system. Each of these systems will continue to function as designed.
FSAR Sections 11.1.1.2, 11.1.2.2, 11.1.3.2, 9.3, 9.4 and Figure 11.1-1 have been updated to reflect this change.
This modification was safety related because of its effect on class 1 walls, but it was determined not to be safety significant and did not involve or create an unreviewed safety question.
CN-1697 System 72/ Reactor Building (Vents and Drains)
This modification isolates the reactor building sump upon detection of a high gamma radiation level in the reactor building sump pump discharge line. RIS-6212 and RIS-6213 monitor the gamma radiation levels in thie, line.
FSAR Sections 11.1 and 11.2 have been updated to state that the reactor building sump pumps are automatically shut off upon detection of high gamma radiation. This activity was non-safety related and was determined not to be safety significant and did not involve or create an unreviewed safety question.
. CN-1707 System 21/ Primary Coolant System This modification was authorized to help reduce problems associated with the primary coolant circulator control systems.
The change installed separate drain lines from the high pressure separators and the circulator main drains to the bearing water surge tanks.
The individual lines (originally comon lines) allowed for better drain control of each subsystem.
FSAR Section 4.2.2.3.4 and Figure 4.2-5 have been revised to reflect this change. This modification was safety related, but it was determined not to be safety significant and did not involve or create an unreviewed safety question.
CN-1709 System 12/ Control Rod Drive and Orifice Assembly System This modification authorized the installation of temperature sensors and an associated monitoring system for the Control Rod Drive and Orificing Assemblies (CRD0A).
The installation included three Resistance Temperature Devices (RTDs) on each CRDOA and output multiplexers. The system is expected to be used to analyze the CRD0A operating conditions at all power levels.
This change notice authorized installation of RTDs on each CRD0A.
FSAR Section 3.8.1.1.2 has been updated to reflect the installation of these RTDs. This activity was safety related but was determined not to be safety significant and did not involve or create an unreviewed safety question.
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. CN-1800 System 45/ Fire Protection System This modification replaces the dry chemical extinguishers in Building 10 with either C02 or Halon extinguishers depending on the area fire hazards.
FSAR SEction 9.12.2.3 has been updated to reflect the installation of these portable extinguishers. This activity was non-safety related and was determined not to be safety significant and did not involve or create an unreviewed safety question.
CN-1876 System 12/ Control Rod Drive and Orificing Assembly This modification allows the continuous movement of the orifice valve over its allowable range of motion. Previously, interlocks prevented this by requiring the hand switch to be reactivated every 0.0125 inches of valve travel.
This modification will reduce the time required to reorifice the core.
FSAR Sections: 3.6.5.1, 3.9.1, 7.2.3.1, 7.2.3.2, and 7.2.3.3 have been revised to reflect this change. The safety evaluation of this modification determined it to be safety related and safety significant, but it did not involve or create an unreviewed safety question.
. CN-1889 System 11/ Reactor Vessel and Internal Component This modification relocates several differential pressure elements from within PCRV penetrations C1 and C3 to outside the penetrations. The pressure differential elements are being moved for ease of calibration and maintenance, and they will continue to function as designed.
FSAR Section 14.7 and Table 14.7-1 have been updated to reflect this change. This modification was safety related but was determined not to be safety significant and did not involve or create an unreviewed safety question.
CN-1923 System 12/ Control Rod Drive and Orificing Assembly This modification installs recorders to record the control rod drive motor temperatures and control rod drive purge flows.
The operation of the control rod drives is not altered by this modification.
FSAR Sections 3.8.1.1.1, 3.8.1, and 3.8.4 have been revised to reflect the installation of these recorders. This activity was safety related but was determined not to be safety significant and did not involve or create an unreviewed safety question.
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CN-1933 System 12/ Control Rod Drive and Orifice Assembly This modification changes control rod cable material from AISI 347 stainless steel to Inconel 625.
It also changes the material for other bolts, tubing and fittings to avoid stress corrosion problems. These new materials will not alter the designed performance of the control rod drives.
FSAR Sections 3.8.1.1.1, 3.8.1.2, 3.8.2, and Figure 3.0-11 have been revised to reflect the change in control rod cable naterial.
This activity was safety related but was determined riot to be safety significant and did not involve or create an unreviewed safety question.
CN-1943 System 45/ Fire Protection System This modification changes the G and J wall fire sprinkler system from a dry spray system to a closed head water spray system. The fixed spray systems in the Auxiliary Electrical Room and the 480 Volt Room are unchanged.
FSAR Sections 9.12 and Appendix C Criterion 3 and Figures 9.12-2 and 9.12-5 have been updated to indicate the change.
This activity was safety related but was determined not to be safety significant and did not involve or create an unreviewed safety question.
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. CN-1960A System 11/ Reactor Vessel and Internal Components This modification taps and installs 0-rings and 0-ring retainers on longitudinal and accessible bottom crosshead PCRV tendon end caps.
The function of the end caps and PCRV tendon is not altered by this modification.
FSAR Section 5.6.2.5 has been updated to indicate the changes to the end caps. This activity was non-safety related and was determined not to be safety significant and did not involve or create an unreviewed safety question.
CN-1967 System 11/ Reactor Vessel and Internal Components This modification installs knock-out pots on the helium purge lines to the steam generator and helium circulator penetration interspaces.
This modification reduces the possibility of moisture entering the control rod drive and orifice assembly interspaces via the helium purge system.
FSAR Sections 3.8.4 and 5.8.2 have been updated to indicate the installation of these knock-out pots. This activity was safety related but was determined not to be safety significant and did not involve or create an unreviewed safety question.
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. CN-1977 System 92/ Electrical Power System This modification installs new 480 volt p(ower cables to the water jacket heaters on the standby diesels K-9203-X, K-9204-X, K-9205-X, K-9206-X). -These cables will be classified as essential electrical cables. The operation of the water jacket heaters and the standby diesels is not altered by this modification.
FSAR Section 8.2.3.3 has been updated to include a description of the standby diesels' water jacket heaters.
This activity was safety related but was determined not to be safety significant and did not involve or create an unreviewed safety question.
CN-1979 System 92/ Electrical Power System This modification changes the power source for Building 10 emergency lighting and fire detection / suppression power circuits from N-9296 and N-9297 to instrument power bus IC-1 and fire panel XC-45316, respectively. The emergency lighting and fire detection / suppression systens in Building 10 will operate more reliably as a result of this modification.
FSAR Section 8.2.6, Figure 8.2-19 and Table 8.2-8 have been updated to include emergency lighting in Building 10.
This activity was safety related but was determined not to be safety significant and did not involve or create an unreviewed safety question.
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.. CN-1982 System 12/ Control Rod Drive and Orifice Assembly This modification revises Specification RL-1-1 to bring it up to current industry standards. RL-1-1 covers the lubrication and cleaning of the control rod drive motors.
FSAR Sections 3.8.3 and A.9.2 have been revised to indicate the name change of the lubricant used. This is a manufacturer name change only; the chemical composition of the lubricant is unchanged. This activity was safety related but was determined not to be safety significant and did not involve or create an unreviewed cafety question.
CN-1983 4
Systems 21 and 22/ Primary Coolant System and Secondary Cooling System.
This Change Notice modifies the helium circulator control system to avoid the trip of a second circulator in a loop, on overspeed, following the trip of the first circulator, at power levels in excess of 70 percent. The function of the helium circulators is unchanged, and their reliability is improved.
FSAR Section 7.1.2.6 will be revised in Revision 5 to indicate the modification done to avoid unnecessary circulatory trips.
This activity was safety related but was determined not to be safety significant and did not involve or create an unreviewed safety questions.
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. t CN-1986 System 12/ Control Rod Drive and Orifice Assembly This Change Notice updates the control cod drive and orifice assembly drawings which were affected by non-conformance reports during the refurbishment program. The function of the control rod drive and orifice assemblies is not altered by this modification.
FSAR Figures 3.8-10 and 3.9-2 have has been updated to reflect the changes made to drawing D1201-200. This activity was safety related but determined not to be safety significant and did not i
involve or create an unreviewed safety question.
CN-1996 System 92/ Electrical Power System This modification installs fused disconnect safety switches in the Building 10 circuit breaker test facility, that are to be used as a power supply when testing the circuit breakers. This modification will not alter the function or operation of the 480 volt system.
FSAR Figure 8.2-17 will be updated in Revision 5 to add the circuit breaker test facility to the 480 volt load center switchgear.
This activity was safety related but was determined not to be safety significant and did not involve or creata an unreviewed safety question.
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. CN-2017 System 48/ Alternate Cooling Method (ACM)
This modification reroutes ACM fuel oil transfer pump cables to be in compliance with 10CFR50 Appendix R.
The function and operation of the ACM and the fuel oil transfer pumps are not altered.
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FSAR Figure 8.2-30 will be revised in Revision 5 to indicate the new numbers on the ACM fuel oil transfer pump cables.
This activity was safety related but was determined not to be safety significant and did not involve or create an unreviewed safety question.
CN-2038 System 21/ Primary Coolant System This modification removes the welded-in check valves from the discharge line of each bearing water pump.
These check valves serve no useful parpose in the existing system configuration. No detrimental effects on the bearing water system will occur as a result of this modification.
FSAR Figure 4.2-12 has been updated to indicate the removal of these check valves. This activity was safety related but was determined not to be safety significant and did not involve or create an unreviewed safety question.
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- CN-2125 System 78/ Security System This modification extends the storage pond vital area fence around the circulating water makeup pump house and valve pit. No alteration of the overall Security System or circulating water makeup system occurs as a result of this modification.
FSAR Figure 1.2-4 will be updated in Revision 5 to show the extension of this fence. This activity was safety related but determined not to be safety significant and did not involve or create an unreviewed safety question.
CN-2201 Systems 92 and 93/ Electrical Power System and Plant Protective System This modification authorizes the use of Flamemastic 77 in place of Flamemastic 71A for a retardant coating.
Flamemastic 71A contains asbestos, and in order to minimize personnel exposure, non-asbestos Flamemastic 77 will be used instead.
The fire retarding capabilities of Flamemastic 77 are as good as or better than Flamemastic 71A.
FSAR Sections 8.2.7.1 and 9.12.3.4 have been updated to reflect the use of Flamemastic 77. This activity was non-safety related and was determined not to be safety significant and did not involve or create an unreviewed safety question.
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,-.. o CN-2205 System 21/ Primary Coolant System This modification provides a manual actnation station for the helium circulator brake and seal system fran outside the Reactor Building. This station is being established due to environmental qualification requirements.
The circulator brake and seal system, whether. manually or automatically actuated, will continue to function as designed. This system has been incorporated into the Appendix R Fire Protection Evaluation.
FSAR Section 4.2.2.3.4 has been updated to include the capability to manually actuate the helium circulator brake and seal system.
This activity was safety related but was determined not to be safety significant and did not involve or create an unreviewed safety question.
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.- 2.0 PUBLIC SERVICE COMPANY TESTS (T-TESTS)
T-214 System 12/ Control Rod Drive and Orificing Assembly To determine the wattege input to the shim motor during control rod movements.
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This test involved acquiring data from an operating shim motor on a control rod drive.
No more than two (2) control rod pairs were withdrawn at any time.
It was determined that typical power values were 46 watts for rod-in movements and 90 watts for rod-out movements.
This test was determined to be safety related, but it was not safety significant and did not involve or create an unreviewed safety question.
T-232 System 12/ Control Rod Drive and Orificing Assembly (CRD0A)
To investigate the effects of possible debris in shim motor bearings and to determine if exercising the motor will loosen this possible debris.
This test checked the torque of a shim motor removed from a CRD0A before and after exercising.
It was found that a noticeable reduction in torque occurred in every shim motor exercised, indicating frictional loads can be reduced by exercising.
This test was safety related.
It was determined not to be safety significant and did not involve or create an unreviewed safety question.
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- T-252 System 72/ Reactor Building Vents and Drains To determine the flow path of equipment and floor drains in the Reactor Building.
The test sent dye through the drains in the Reactor Building to discover whether they went to the liquid waste sump or the reactor building sump.
The flow paths have been mapped. This test was not safety related, and was determined not to be safety significant and did not involve or create an unreviewed safety question.
T-259,T-271,andT-]73 System 21/ Primary Coolant System To collect data on the helium circulator main drain control system during transient conditions.
This test induced perturbations in the bearing water supply to "A", "B", and "D" helium circulators. Through this test it has been determined a fixed setpoint is favored over the existing modulated setpoint.
This test was safety related.
It was determined not to be safety significant and did not involve or create an unreviewed safety question.
T-265 System 11/ Reactor Vessel and Internal Components To determine the pressure integrity of bottom crosshead tendon tubes following refurbishment of the end cap 0-ring seals.
It was determined that the leak rates were significant, especially from the tendons with a load cell.
It was recommended as a result of this test to maintain a low pressure (0.25 psi) in order to conserve nitrogen. This test was not safety related.
It was also determined not to be safety significant and did not involve or create an unreviewed safety question.
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. T-266 System 92/ Electrical Power System To determine the capacity of battery "1A" (N-9242)andits ability to supply the required ampere-hours.
This battery performed as designed during this test. The battery was able to supply the required ampere-hours.
This test was safety related.
It was determined not to be safety significant and did not involve or create an unreviewed safety question.
T-268 System 99/ Miscellaneous - Meteorological Tower To demonstrate the reliability of meteorological data recovery system.
The recorders in the control room and the weather shack were examined for one month.
This test found that no two chart recorders monitoring the same parameter were down simultaneously.
Therefore, all the required data was retrievable. This test was not safety related, and it was determined not to be safety significant and did not involve or create an unreviewed safety question.
T-269 System 72/ Reactor Building Vents and Drains To determine the maximum flow rate through V-72320.
The maximum flow was found to be 8-9 gpm. The maximum release rate per ELC0 8.1.3 is 10 gpm. However, the continuous sampler has a maximum flow rate of 2-4 gpm; therefore, the actual release rate will not exceed 10 gpm because the continuous sampler flow is not directly released and should not be added to the release rate. 'Th'is test was not safety related.
It was determined not to be safety significant and did not involve or create an unreviewed safety question.
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T-281 System 62/ Radioactive Liquid Waste System To verify the isolation capability of V-6241, HV-6212, and V-6297.
This test involved dead heading the liquid waste transfer pumps
' against each of these valves individually. No flow was detected i
on FR-6215 which is upstream of these valves. Therefore, it was determined that these valves are capable of _ isolating the radioactive liquid waste system.
This test was not safety
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related, and was determined not to be safety significant and did not involve or create an unreviewed safety question.
T-283 1
System 11/ Reactor Vessel and Internal Components To remove residual material, which is blocking flow, from the refueling penetration interspace pressurizing lines.
High pressure-helium was applied to the refueling interspace pressurizing lines in order to clear any blockage. This test was performed with the reactor shut down and depressurized and the secondary penetration cover removed.
All blocked lines were eventually cleared.
This test was safety related.
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determined not to be safety significant and did not involve or create an unreviewed safety question.
T-286 System 21/ Primary Coolant System To collect data on the helium circulator main drain control system with the main drain control valve acting as a fixed orifice.
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bearing supply side by closing and opening the supply valve. The results of this test were inconclusive due to the limited nature of the test. This test was safety related, but was determined i
not to be safety significant and did not involve or create an unreviewed safety question.
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. T-291 System 12/ Control Rod Drive and Orificing Assembly To functionally test the scram control rod drive bypass system.
This test simulated a scram by interrupting power to the CRD motors and control power to the CRD starters. The bypass system was then tested by inserting a rod from each CRD MCC. The CRD bypass system was functional. This test was safety related.
It was determined not to be safety significant and did not involve or create an unreviewed safety question.
T-293 System 93/ Plant Protective System (PPS)
To verify that the first in with lockout circuits for the loop shutdown logic operate properly.
This test showed that neither loop could be tripped with the other loop shutdown. The first in with lockout circuits operated as designed.
This test was safety related.
It was determined not to be safety significant and did not involve or create an unreviewed safety question.
T-294 System 11/ Reactor Vessel and Internal Components To determine the amount of moisture in the helium circulator and steam generator interspaces and to purge the interspaces of moisture as required.
"A" and "B"
circulator interspaces and Loop 1 steam generator interspaces were found dry. Circulators "C" and "0" were found to have traces of moisture while loop II steam generator interspaces contained about 10 gallons of water (See T-296). All moisture was removed from the interspaces and their supply lines.
While this test was safety related, it was determined not to be safety significant and did not involve or create an unreviewed safety question.
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. l T-296 System 11/ Reactor Vessel and Internal Components To determine the probability that a feedwater leak exists in the loop II steam generator interspaces.
This test was run in two phases.
First, the EES section was isolated but not drained; second, the EES section was isolated and drained.
In both cases, any leaking water was alleved to accumulate for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This test discovered that water found previously had not' accumulated as a result of a feedwater leak, but instead, the water was from the existing cold reheat leak (See LER 85-013).
This test was safety related.
It was determined the. test was not safety significant and did not involve or create an unreviewed safety question.
T-298 System 21/ Primary Coolant System To investigate suspected static problems and suspected improper automatic valve operation on a circulator trip.
This test found that the automatic actuation of valves was as designed. However, it was learned subsequently that one or both of the helium-water drain block valves appeared to be leaking.
This would explain the suspected automatic valve operation i
problems. The static seal appears to have debris keeping it from j
seating properly. A gas flush is recommended to clear this fouling material (see T-299).
i This test was safety related.
The test was determined to be i
safety significant but did not involve or create an unreviewed 1
i safety question.
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T-299 System 21/ Primary Coolant System l
l To remove the suspected foreign matter fouling the seating surfaces of the "D" helium circulator static seal by means of a gas flush.
This test was unsuccessful due to problems with maintaining the shutdown water seal in the bearing water cartridge.
This is accomplished by flooding the bearing water cartridge. The gas flush was never actually attempted.
It was determined that a gas flush in the reverse direction should be tried (see T-301). This test was safety related.
It was determined not to be safety significant and did not involve or create an unreviewed safety question.
i T-300 System 93/ Plant Protective System (PPS)
To verify the proper operation of the rod group sequence rod withdrawal prohibit (RWP).
With the reactor shutdown, the control rod section switches were placed in various positions to insure that RWPs would be received as required.
The test found that RWPs were indeed actuated as designed. This test was safety related, but it was determined not to be safety significant and did not involve or create an unreviewed safety question.
T-301 i
System 21/ Primary Coolant System To remove foreign matter believed to be fouling the seating surfaces of "D" helium circulator static seal by allowing primary coolant to flow past it at high velocity.
l This test was never performed because the seal seated perfectly
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during preparation to run this test.
Therefore, there was no reason to flush the seating surfaces in this manner. This test was safety related, but it was determined not to be safety significant and did not involve or create an unreviewed safety question.
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. T-305 System 12/ Control Rod Drive and Orificing Assemblies System 93/ Plant Protective System (PPS)
To monitor the output of load current sensor IE-1238 while energizing the "out" contactor coil for several different control rod drive motors to determine the cause of spurious rod withdrawal prohibit (RWP) actuations.
This test showed no abnormal initiation of RWP actuations. The test recommended not changing the existing setpoint and shielding the cable connecting this sensor to the bistable trip module. No rod movement was associated with testing these curcuits.
This test was safety related, but it was determined not to be safety significant and did not involve or create an unreviewed safety question.
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0 3.0 GA TECHNOLOGIES REQUESTS FOR TESTS (RT-TESTS)
None 1
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y 4.0 pggCEDURES None i
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1 f
i OPublic Service ~
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Company of Colorado 2420 W. 26th Avenue, Suite 100D, Denver, Colorado 80211 July 22, 1986 Fort St. Vrain Unit No. 1 P-86454 Regional Administrator T@@@M@M Region IV l
U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000
& 2 31 %
Arlington, Texas 76011 y
ATTN: Mr. J. E. Gagliardo, Chief Reactor Projects Branch Docket No. 50-267
SUBJECT:
10CFR50.59 Annual Report Submittal
REFERENCE:
Facility Operating License No. DPR-34
Dear Mr. Gagliardo:
Enclosed please find forty (40) copies of the Annual Report of Changes, Tests, and Experiments Not Requiring Prior Commission Approval Pursuant to 10CFR50.59, in accordance with Part 50.59(b) of Title 10, Code of Federal Regulations, for the period of January 23, 1985 through January 22, 1986.
If you have any questions concerning this report, please contact Mr.
M. H. Holmes at (303) 480-6960.
Very truly yours, u
H. L. Brey, Manager Nuclear Licensing and Fuels Division l
HLB /SBH/ paw l
l Enclosures cc: Director, Inspection and Enforcement U.S. Nuclear Regulatory Commission (1 copy of the report) g(o-Qb N
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