ML19341D300
| ML19341D300 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/31/1980 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| References | |
| NUDOCS 8103050303 | |
| Download: ML19341D300 (57) | |
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g PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION REPORT OF CHANGES, TESTS, AND EXPERIMENTS NOT REQUIRING PRIOR COMMISSION APPROVAL PURSUANT TO 10CFR50.59(a)
January 1, 1980, through December 31, 1980
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TABLE OF CONTENTS Page Introduction ------------------ ------ ---- 3 1.0 Public Service Company Change Notices ---------------- 5
- 2. 0 General Atomic Company Field Change Notices ------------- 7
- 3. 0 General Atomic Company Requests for Tests -------------- 8 4.0 Public Service Company Tests - - - - - - - - - - - - - - - - - - - - - 11 5.0 Table of Abbreviations - - - - - - - - - - - - - - - - - - - - - - - - 16
- 6. 0 System Number Identification Table - - - - - - - - - - - - - - - - - - 18 j
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o INTRODUCTION This report is submitted to comply with the requirements of Part 50.59(b) of Title 10, Code of Federal Regulations as they apply to Fort St. Vrain Nuclear Generating Station, Unit No. 1. It includes the period of January 1,1980, through December 31, 1980. ,
Some definitions of major terms used in this report may also be helpful:
Change Notice - Documents modification work proposed and installed by Public Service Company.
Fie: d Change Notice - Documents modification work proposed and installed by cont;ractor.
"T" Tests - Documents tests proposed and conducted by Public Service Com-pany.
4 l "RT" Tests - Documents tests proposed and conducted as aequested by con-
! tractor.
In this report, the Safety Evaluation for the changes and tests listed is sum-marized. The terminology used in these summaries is defined as follows, Safety-Related Items Those plant systems, structures, equipment, and compnnents which are iden-tified in the FSAR and as detailed and supplemented by special safety-related lists and drawings to include the following:
a) Class I per the FSAR, Table 1.4-1, Amendments 16 and 25 (Table 5.9-1),
Amendments 16 and 24 (Table 5.11-2),
b) Safe shutdown components per the FSAR, Table 1.4-2, Amendments 16 and 25 (Table 5.9-1), Amendments 25, 26, and 29 (Table 6.1-1),
c) Engineered safeguards per the FSAR, Amendments 18 and 19 (pages 7.7-1 through 7.7-4),
d) General Atomic Company specification 90-SR-6-1 and 90-SR-6-2 series drawings.
Safety Significant Change Changes to the facility, systems, components, or structures as L .,cribed in the Final Safety Analysis Report (FSAR) that may do any one of the fol-lowing:
a) Affect their capability to prevent or mitigate the consequences of ac-
{ cidents described in the FSAR.
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b) Could result in exposures to plant personnel in excoss of occupational limits.
Changes in the safety-related systecs 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, safety shutdown, accident analysis, or any change that would result in ar.
unreviewed safety question or require a Technical Specification change. .
Unreviewed Safety Question Any plant modification or activity is deemed to involve an unreviewed safety question as defined in 10CFP50.59.
a) The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased.
b) The possibility of an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created.
c) The margin of safety as defined in the basis for any Technical Specifi-cation is reduced.
To reduce the size of this report, many repetitive terms have been abbreviated.
The reader is referred to Section 5.0 for this listing. Certain systems are identified by their generic numbers; Section 6.0 contains a list of System Num-ber Identifications used.
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1.0 PUBLIC SERVICE COMPANY CHANGE NOTICES Change, Test, or Experiment System / Description of Change, Summary of Safety Number Component Test, or Experiment Evaluation CN 101 63 Replaced hard seated Not safety significant.
check valves with soft seated check valves.
CN 420 11/ Valves added for future Not safety significant.
V-111140, instrument taps for re-V-111141, actor. primary coolant V-111142, pressure.
V-111143 g'
CN 469 21/Circula- CN 469 removed the Not safety significant.
lators Mar- Marmon flanges aad re- Not an unreviewed safety mon Flange placed them with solid question.
piping. This will re-duce the leakage prob-lem at these joints.
CN 471 93 Installed are sup- Not safety significant.
pressors on various re- Not an unreviewed safety lays. q ues tion.
CN 473 21 Installed manual iso- Not safety significant.
lation valve upstream Not an unreviewed safety
' of the pelton whec1 question.
water supply lines.
CN-653 73/RIS-7312 Install bypass switch Not safety significant.
for RIS-7312 to facil- Not an unreviewed safety itate surveillance question.
testing.
CN ',28 93 Wired plant protective Safety significant. Not service logic module an unreviewed safety inputs to test points question.
on module front.
CN-990 21 General upgrade of Safety significant. Not helium circulator aux- an unreviewed safety iliaries, buffer sys- question.
- tem.
CN-1016 17 Installed modified Safety significant. Not transition reflector an unreviewed safety ,
! elements containing PGX question.
- graphite surveillance I
- specimen.
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, t" 1.0 - PUBLIC SERVICE COMPANY CHANGE NOTICES (Cont'd)
Change, Test or Experiment System / Description of Change, Summary of Safety Number Component Test, or Experiment Evaluation CN 1079 93 Modify plant protective Not safety significant.
system modules to allow Not an unreviewed safety better test of inhibit question.
circuit between main feedwater low pressure and emergency feedwater flow low.
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2.0 GENERAL ATOMIC COMPANY FIELD CHANGE NOTICES Change, Test or Experiment System / Description of Change, Summary of Safety Numbe r Component Test, or Experiment Evaluation GA FCN 4251 23 Installed manual oper- Not sal:ety significant.
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ator capability for Not an unreviewed safety purification train in- q ues tion.
let valves.
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3.0 CENERAL ATOMIC COMPANY REQUESTS FOR TESTS
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Change, Test, or Experiment System / Description of Change, Summary of Safety Number Component Test, or Experiment Evaluation
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RT-322 11/ Reactor Determine magnitude of Data collection only.
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Power Indi- difference between cation power indicated on nuclear channels and heat balance power over various power levels from zero to full power.
RT-350 46 Determine degree of Not safety significant.
perturbation on PCRV liner cooling system flow balance due to flow rate changes caused by the varia-tions in heat exchanger flows and combinations of pump service.
RT-429 Evaluate particulate Not safety significant.
loading rate for the Not an unreviewed safety bearing water MU filter question.
elements and the normal bearing water filter elements when using fire water for bearing water makeup.
RT-437 21/ Relief Determine the flexi- Not safety signicant.
Valves bility of System 21 Not an unreviewed safety relief valve tail question.
piping.
RT-477 21/ Bypass Record helium temp- Not safety significant.
Helium Flow eratures along 3 T/C Not an unreviewed safety at 30% to 50% power. question.
This is information ac-cumulation for temp-erature analysis.
RT-491 12/ Reactor Determine if increase Not safety significant.
2 Core in core pressure drop Not an unreviewed safety has influence on power cuestion.
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! level at which temp-l erature/ power oscil-lations occur.
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t 3.0 GENERAL ATOMIC COMPANY REQUESTS FOR TESTS (Cont'd)
Change, Test, or Experiment System / Description of Change, Summary of Safety Numbe r Component Test, or Experiment Evaluation RT-495 12/ Core Or- Open most closed ori- Not safety significant.
ifices fices to minimum po- Not an unreviewed safety sition to determine in- question.
fluence on core power level at which oscil-lations occur.
RT-498 12 Determine influence of Not safety significant.
core flow distribution Not an unreviewed safety on threshold for core question.
oscillations.
RT-500(H), 12/ Reactor Provide for fluctu- Not safety significant.
Revision 4 Core ation testing with Not an unreviewed safety RCD's installed. question.
RT-507 13 Installs and tests a Not safety significant, bowed element handling Not an unreviewed safety kit on the fuel question.
handling machine.
RT-509 21 This test collects pri- Not safety significant.
mary system data at Not an unreviewed safety
, various power levels, question.
RT-Sil 12/ Reactor Determine correctness Not safety significant.
Core of measured region out- Not an unreviewed safety let temperature in question.
region #20.
RT-515A 12 Provide data regarding Not safety significant.
temperature retro-grade Not an unreviewed safety effect in region #34. question.
RT-516 11/PCRV Obtain DAS-PCRV struc- Not safety significant.
tural data during re- Not an unreviewed safety pressurization of PCRV question.
commencing at approxi-mately 0 psig.
r RT-520 13, 18/FHM Determine characteris- Not safety significant.
tics of handling a Not an unreviewed safety region constraint de- question.
s vice (RCD) with the i fuel handling machine.
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s 3.0 GENERAL ATOMIC COMPANY REQUESTS FOR TESTS (Cont'd)
Change, Test, or Experiment System / Description of Change, Summary of Safety Number Component Test, or Experiment Evaluation RT-522 13 Obtain gamma dose rate Not safety significant.
measurements during and No danger to health and af ter unloading of core safety of the general region 27. public. Not an unre-viewed safety question.
.RT-525 18 Determine by measure- Not safety significant.
ment dimensional Not an unreviewed safety changes occurring in question.
irradiated fuel and re-flector elements.
RT-526A 18 Ship one irradiated Not safety significant.
fuel element to Gener- Not an unreviewed safety al Atomic Company in question.
San Diego for post ir-radiation examination.
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4.0 PUBLIC SERVICE COMPANY TESTS a
Change, Test, or_ Experiment System / Description of Change, Summary of Safety Number Component Test, or Experiment Evaluation T-55 21 Determine by test ef- Not safety significant.
feet of recirculator trips on circulator operation.
T-107 93/ Plant Verify proper logic in- Not safety significant.
Protective put voltages in attempt Not an unreviewed safety System to resolve problems question.
with inadvertent plant protective system trips.
T-113 13 Measure average power Not safety significant.
density in each core Not an unreviewed safety refueling region rela- question.
tive to the average power density in the entire core at a low power level.
T-122 ll/ Region Determine by test if Not safety significant.
Outlet T/C the four installed Not an unreviewed safety Region 34 thermocouples at the question.
outlet of region 3/
indicate the correct temperature.
T-123 Co re/Re- Determine by radiation Not safcty significant.
flector survey quantity and Not an unreviewed safety type of radiation endt- question.
ted by irradiated re-flector blocks.
T-125 48 Verify operability of Not safety significant.
ACM diesel generator Not an unreviewed safety under full load cond!- question.
tions.
T-126 21 Verify position of iso- Not safety significant.
lation valves and brake Not an unreviewed safety I
and seal valves on each question.
circulator shutdown
, when powering plant i protective system logic
- up and down.
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4.0 PUBLIC SERVICE COMPANY TESTS (Cont'd)
Change, Test, or Experiment System / Description of Change, Summary of Safety Number Component Test, or Experiment Evaluation T-127 12/ Inlet Obtain data to deter- Not safety significant. ~
Orifice mine if operating Not an unreviewed safety Valves characteristics for in- question.
let orifice valves have changed as a result of region constraint de- ,
vice installation.
T-128 Reactor Measure core region Not safety significant.
Co re peaking factors at Not an unreviewed safety power following instal- question.
lation of region con-straint devices.
T-129 Reactor Confirm core operating Not safety significant.
Core characteristics fol- Not an unreviewed safety lowing region con- question.
straint device instal-lation and verify oper-ability of test equip-ment prior to conduc-ting RT-500.
T-130 21 Verify operability of Not safety significant.
circulator auxiliary Not an unreviewed safety relay controls ,
question.
T-131 21/ Helium Obtain temperature Not safety significant.
Circulators data of steam / water Not an unreviewed safety drain flow from helium question.
circulators with and without quench water.
T-132 21/ Buffer Determine minimum dif- Nct safety significant.
Helium Re- ferential pressure a- Not an unreviewed safety
! circulators cross buffer helium re- question.
circulators which will maintain seal water flow and keep recircu-(. lator operating. i T-134 21/lB Heli- Determine seal bellows Not safety significant.
, um Circu- status (ruptured or in- Not an unreviewed safety j lator tact) of IB helium cir- question.
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4.0 PUBLIC SERVICE COMPANY TESTS (Cont'd)
Change, Test, or Experiment System / Description of Change, Summary of Safety Number Component Test, or Experiment Evaluation T-135 21/lB Cir- Examine operability of Not safety significant.
4 culato r 1B circulator plant Not an unreviewed safety protective system and question.
relay interlock.
T-136 21/ Helium Determine minimum brake Not safety significant.
Circulators and seal supply re- Not an unreviewed safety quired to hold static question.
seal closed on "B" cir-culator. Determine brake and seal supply use rate.
T-137 93/ Plant Collect data on fixed Not safety significant.
P ro tective low feedwater flow Not an unreviewed safety System trips , programmed cir-culator, and feedwater flow trips to provide data for possible pro-cedure revision.
T-138 21/lB Cir- Functionally test cir- Not safety significant, culator culator 1B brake and Not an unreviewed safety and seal to verify question, operability of re-placement helium cir-culator.
T-139 46 Determine by test the Not safety significant.
accuracy of System 46 Not an unreviewed safety temperature indicators. question.
T-140 92/ Day Tank Determine by test if Not safety significant.
Level Con- diesel day tank makeup Not an unreviewed safety trol level control system question.
can be made to control level at approximately 500 gallons.
T-141 93 Test logic chip input Not safety significant.
voltages using wiring Not an unreviewed safety installed per CN 928. question.
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4.0 PUBLIC SEUICE COMPANY TESTS (Cont'd)
Change, lest, or Experiment System / Description of Change, Summary of Safety Numbe r Componen t Test, or Experiment Evaluation T-145 11/ Loop 2 Checks penetration Not safety significant.
- Steam Gen- interspace leakage Not an unrevieved safety erator using pressure decay question.
Penetration method.
Interspace T-147 ll/ Loop 2 Checks penetration Not safety significant.
Steam Cen- interspace leakage Not an unreviewed safety erator using pressure decay question.
Penetration method.
Interspace T-148 Portable Experiment with por- Not safety significant.
Radios table radios to deter- Not an unreviewed safety mine which areas of the question.
plant cannot be covered with portable radio equipment and to deter-mine what effect radio transmissions have on various electronic transmitters.
T-149 11/TE-ll74 Determine extent of Not safety significant.
& TE-1178 noise in these thermo- Not an unreviewed safety co uples , question.
T-152 21/HV-21352 Evaluation of hard seat Not safety significant.
for HV-21352. Not an unreviewed safety
- question.
T-153 Startup Collects cata to de- Not safety significant.
Channel De- termine if detectors or Not an unreviewed safety tec to rs pre-amps need to be re- question.
i placed.
T-156 23/V-2392, Test valves V-2392 and Not safety significant.
V-2393 V-2393 for leakage. Not an unreviewed safety question.
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4.0 PUBLIC SERVICE COMPANY TESTS (Cont'd)
Change, Test, or Experiment System / ' ascription of Change, Summary of Safety Number Component Test, or Experiment Evaluation Change System 24/ Increased allowable Based on the information '
T-2401 pressure in T-2401 from in the FSAR, Section 10 psig to 45 psig 9.5.5, and calculations during normal opera- using the equation for tions. Approved by ideal gas. The low PORC #191 on 2-16-77. pressure helium storage bottle pressure can safely be increased from 10 to 45 psig. The cal-culations show that the increased quantity of gas that is available to be pumped into the PCRV will not exceed any LSSS listed is LSSS 3.3 or the operating require-ments of LCO 4.4.1.
Further, there is ample excess weight capacity in the bottles to allow contents of the PCRV to be put into storage at elevated pressure.
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I 5.0 TABLE OF ABBREVIATIONS ACM Alternate Cooling Method ANSI American National Standards Institute ASCO Automatic Switch Company ASTM American Society for Testing and Materials C Compressor CFM Cubic Feet / Minute CN Change Notice (Public Service Company)
CO 2
Carbon Dioxide
-E Exchange (Heat)
F Filter FCN Field Change Notice (Non-Public Service Company Initiated Change)
FE -Flow Element FIS Flow Indicator / Switch FSAR Final Safety Analysis Report
- GAC General Atomic Company HSV Hand Solenoid Valve HV Hand Valve HVAC Heating, Ventilating, and Air Conditioning K Engine (Diesel or Gasoline (
L Line LCV Level Control Valve N Nitrogen (Cas) 2 NRC Nuclear Regulatory Commission P Pump i
PCRV Prestressed Concrete Reactor Vessel 2
4 5.0 TABLE OF ABBREVIATIONS (Cont'd)
PDV Pressure Differential Valve i
PPS Plant Protective System
-PS Pressure Switch PSC Public Service Company of Colorado
-PSI Pounds / Square Inch PV Pressure Valve R Refueling Region (When Followed by a Number)
RIS Radiation Indicator / Switch RT Request for Test (General Atomic Company)
S&L Sargent and Lundy T Tank, Special Test (Public Service Company (
TIG Tungsten Inert Gas TT Temperature Transmitter V Valve l
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6.0 SYSTEM NUMBER IDENTIFICATION TABLE' 11 Reactor Vessel and Internal Components 12 Control Rods and Drives 13 Fuel Handling Equipment _
14 Fuel Storage 15 Fuel Shipping Equipment IT Auxiliary Equipment 17 Reflector 18 Fuel 21 Primary Coolant System (Helium Circulators and Auxiliaries) 22 Secondary Coolant System (Steam Generators) 23 Helium Purification System 24 Helium Storage System ,
25 Liquid Nitrogen System 31 Feedwater and Condensate 32 Feedwater Heater Vents and Drains 33 Water Treatment 41 Circulating Water System 42 Service Water System T
44 Domestic Water System 45 Fire Protection System 46 Reactor Plant Cooling Water System 47 Purification Cooling Water System 48 Alternate Cooling Method
, 51 Turbine Generator and Auxiliaries i <
. 52 Turbine Steam A
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l 6.0 SYSTEM NUMBER IDENTIFICATION TABLE (Cont'd) 53 Extraction Steam 54 Turbine Lube 011 Purification 55 Turbine Vents and Drains 61 Decontaminatien System 62 Radioactive Liquid Waste System 63 Radioactive Gas Waste System 72 Reactor Building (Vents and Drains) 73 Reactor Plant Ventilation System 75 Turbine Building (Vents and Drains, HVAC) 82 Instr nuent and Service Air 83 Communication System 84 Auxiliary Boiler and Heating System 91 Hydraulic Power 92 Electrical Power 93 Controls and Instrumentation 98 Hydraulic Piping Snubbers a
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