ML20041F808
| ML20041F808 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 03/01/1982 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20041F804 | List: |
| References | |
| NUDOCS 8203170433 | |
| Download: ML20041F808 (14) | |
Text
.
PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION 4
4 REPORT OF CHANGES, TESTS, AND EXPERIMENTS NOT REQUIRING PRIOR COMMISSION APPROVAL PURSUANT TO 10CFR50.59(a)
January 1,1981 through December 31, 1981 i
5 8203170433 820301 PDR AD0cn 05000267 j
2 R
. TABLE OF CONTENTS 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....
.......................... 9 5.0 Tabl e o f Abb rev i at i o n s.................................... 11 6.0 System Number Identification Table......................... 13 i
i 3
l 0
2 L_
. INTRODUCTICN 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 1,1981, through December 31, 1981.
Some definitions of major terms used in this report may be helpful:
Modification work proposed and installed by Change Notice Public Service Company.
Field Change Not,{ce - Modification work proposed and installed by contractor.
Tests proposed and conducted by Public Service "T"
Tests Company.
"RT" Tests Tasts proposed and conducted as requested by contractor.
In this report, the Safety Evaluation for the changes and tests listed is summarized. The terminology used in these. summaries is defined as follows, Safety Related Items Those plant systems, structures, equipment, and comoonents which are identified in the FSAR, and are 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).
I b)
Safe shutdown components per the FSAR, Table 1.4-2, l
Amendments 16 and 25 (Table 5.9-1), Amencments 25, 26, and 29 (Table 6.1-1).
c)
Engineered safeguards per the FSAR, Amendments 18 and 19 (pages 7.7-1 thrcugh 7.7-4).
d)
General Atomic Company specification 90-SR-6-1 and 90-SR-6-2 series drawings.
e 3
4_
m Safety Sionificant Chance Changes to the facility, systems, components, or structures as described in the Final Safety Analysis Report (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)
Could result in exposures to plant personnel in excess of occupational -limits.
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, safety shutdown, accident analysis, or any change that would result in an 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 10CFR50.59 if any of the following apply:
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 i
Technical Specification 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 Number Identifications used, i
e 3
i
, 1.0 PUBLIC SERVICE COMPANY CHANGE NOTICES Change, Test, or Experiment System /
Description of Change, Summary of Safety Number Comoonent Test, or Exoeriment Evaluation CN-120A 11 Install double isolation Not safety significant.
valves on reactor pene-Not an unreviewed trations.
safety question.
CN-351A 92/1C Bat-Installation of test Not safety significant, tery equipment for battery IC. Not an unreviewed safety question.
CN-868 73/F-7301, Installation of a carbon Not safety significant.
7302, 7302S test cannister housing Not an unreviewed assembly in exhaust safety question.
filters.
CN-1110 21/ Buffer-Replace Loop 1 and Not safety significant.
d mid-buffer Loop 2 PDIS's with PDT's. Not an unreviewed safety question.
CN-1123 42/P-4201 Replace all three service Not safety significant.
P-4202 water pumps.
Not an unreviewed P-42025 safety question.
CN-1193 93/PT-3S Modify analog test signal Not safety significant.
of PT-35 to follow the Not an unreviewed same path as the normal safety question.
voltage.
CN-1246 11/NR-1199 Changes recorder to a Not safety significant, and more accurate recorder Not an unreviewed i
XR-11262 for SL 3.1 safety question.
I CN-1276 11 Replace ultra sonic test Not safety significant.
well plug with one Not an unreviewed containing boronated safety question.
l graphite balls.
l CN-1299 62/ oil Install bypass line Not safety significant.
separator and associated valves to Not an unreviewed avoid accumulation of safety question.
radioactive liquid in the separator.
3 3
L
. Change, Test, or Experiment System /
Description of Change, Summary of Safety Number Component Test, or Exceriment Evaluation CN-1302 93/
Interchange components Not safety significant.
RT-93251-1 to have the high range Not an unreviewed RT-93250-14 monitor placed by the safety question.
reactor exhaust filters.
CN-1411 18/ fuel Addition of a new neutron Not safety significant.
assemblies source in region 15, Not an unreviewed column 7, layer 4.
safety question.
CN-1422 21/SV-2105 Changes internal seal Not safety significant.
materials.
Not an unreviewed safety question.
CN-179A 21/ PDC /
Controllers to remain Safety significant.
HC-21185 in manual while circ-Not an unreviewed through ulators are running.
safety question.
PDC /
HC-21188 CN-1292 93 Installation of a buffer Not safety significant.
amplifier in front of Not an unreviewed input to reduce the safety question.
loading effect.
CN-1305 and 21/T-2104 Addition of relief Not safety significant.
CN-1305A T-2105 valves for overpressure Not an unreviewed protection.
safety question.
CN-1427 11/B.2.3 Modification to B.2.3 Safety Significant.
interspace for internal helium Not an unreviewed piping leakage.
safety question.
CN-1427A 11/B.2.3 Removes relief valve Safety significant.
interspace V-1139 from original Not an unreviewed piping position to B.2.3 safety question.
CN-1427B 11/B.2.3 Addition of tailpipe to Safety significant.
interspace V-1139 in modification Not an unreviewed piping safety question.
CN-1427C 11/B.2.3 Returns interspace Safety significant.
interspace piping to normal.
Not an unreviewed piping safety question.
5 I
e w-
. 2.0 GENERAL ATOMIC COM?ANY FIELO CHANGE NOTICES No Field Change Notices were reportable during this period.
2 2
L
-.)
~
. 3.0 GENERAL ATOMIC COMPANY REQUESTS FOR TESTS Change, Test, or Experiment System /
Description of Change, Summary of Safety Number Component Test. or Experiment Evaluation RT-499 21 Attempt to produce fluc-Not safety significant.
tuations by step changes Not an unreviewed in circulator speed.
safety question.
O i
i e
3 I
.g.
4.0 PUBLIC SERVICE COMPANY TESTS Change, Test, or Experiment System /
Description of Change, Summary of Safety
-Number Component Test. or Exoeriment Evaluation T-118 93/ Nuclear Determine magnitude of Not safety significant.
Instrument difference between the Not an unreviewed power range nuclear safety question.
detectors indication and manual calculation by heat balance.
T-150 22/ Loop 2 Determine which steam Not safety significant.
Steam generator module inter-Not an unreviewed Generator space is leaking helium.
safety question.
T-154 N/A Determine any point in-Not safety significant.
plant which can not be Not an unreviewed reached by portable radio safety question.
from the control room.
T-162 21/C-2102 Monitor the shutdown seal Not safety si:nificant.
leak rate on "1B" Not an unreviewed circulator.
safety question.
T-165 22 Test operation of Not safety significant.
FSH-2206-5, PV-22167, and Not an unreviewed PV-22168.
safety question.
T-168 62/A-6201 Modify the liquid waste Not safety significant.
A-62015 system for increased flow, Not an unreviewed and ease of resin change.
safety question.
T-170 12/re-Determine condition of Not safety significant.
1 flector reflector block in region Not an unreviewed element 36, layer 3, column 3.
safety question.
36.03.R03 T-172 21/C-2103 Test circulator seal Not safety significant.
bellows for leakage.
Not an unreviewed safety question.
T-173 92/N-9255 Induce load related Not safety significant.
transients and observe Not an unreviewed effects on Bus 1C safety question.
(N-9255) charger-inverter trip circuitry.
i
r g
l Change, Test, or Experiment t System /
Description of Change, Summary of Safety Number Component Test, or Exoeriment Evaluation T-176 21/C-2102 Measure the penetration Not safety significant.
pressure decay after Not an unreviewed isolating from the puri-safety question.
T-177 45/P-4501 Connect time meter to Not safety significant.
determine yearly run Not an unreviewed time of P-4501.
safety question.
T-173 92 Determine the system Not safety significant.
power factors and loads Not an unreviewed on various 480 V buses.
safety question.
)
T-186 21 Obtain operating data on Not safety significant.
proper circulator steam /
Not an unreviewed water drain valve safety cuestion.
po5
' versus cold re-h' sure.
t 6
5 4
l 3
s 0
1
. 5.0 TABLE OF ABBREVIATIONS I
ACM Alteranate Cooling Method ANSI American National Standards Institute ASCO Automatic Switch Conpany ASTM American Society for Testing and Materials
' 3-C, Compressor CFM Cubic Feet / Minute CN Change Notice (Public Service Company)
CO c, Carbon Dioxide 2
E Exchange (Heat)
F Filter FCN Field Change Notice (Non-Public Service Company Initiated Change)
FE Flow Element FIS Flow Indicator /Switen FSAR Final Safety Analysis Report GAC General Atomic' Company HSV Hand Solenoid Valve HV Hand Valve HVAC Heating, Ventilating, and Air Conditioning i
K Engine (Diesel or Gasuline)
L Line A
LCV Level Control Valve N
Nitrogen (Gas) i 5
NRC Nuclear Regulatory Commission P
Pump
. 9 i
PCRV Prestressed Concrete Reactor Vessel PDIb Pressure Differential Indicating Switch PDT Pressure Differential Transmitter PDV Pressure Differential Valve 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 i
V Valve I
i
. }
1' 6.0 SYSTEM NUMBER IDENTIFICATION TABLE 11 Reactor Vessel and Internal Components 12 Control Rods and Drives 13 Fuel Handling Equipment 14 Fuel Starage 15 Fuel Shipping Equipment 16 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 44 Domestic Water System 45 Fire Protection System 46 Reactor Plant Cooling Water System 47 Purification Cooling Water System 48 Alternate Cooling Method 3
51 Turbine Generator and Auxiliaries i
2
r $
52 Turbine Staam l
53 Extraction Steam 54 Turbine Lube Oil Purification 55 Turbine Vents and Drains 61 Decontamination System 62 Radioactive Liquid Waste System 63 Radioactive Gas Waste System 72 Reactor Building (Vents and Orains) 73 Reactor Plant Ventilation System 75 Turbine Building (Vents and Drains, HVAC) 32 Instrement and Service Air 83 Communication System I
84 Auxiliary Boiler and Heating System 91 Hydraulic Power 92 Electrical Power
]
93 Controls and Instrumentation 98 Hydraulic Piping Snubbers I
i i
i 4
l i
I
.