ML19296C594
| ML19296C594 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 02/15/1980 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| P-80026, NUDOCS 8002260687 | |
| Download: ML19296C594 (16) | |
Text
1.
l pubue service company =e cdondo E
(,_
16805 Weld County Road 19 1/2, Platteville, Colorade 80651 ha-J Feb ruary 15, 1980 Fort St. Vrain Unit No. 1 P-80026 Mr. Karl V. Seyfrit, Director Nuclear Regulatory Comission Region IV Of fice of Inspection and Enforcement 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 Re ference: Facility Operating License No. DPR-34 Docket No. 50-267
Dear Mr. Seyfrit:
Enclosed please find two copies of the Report of Changes, Tests, and Experiments Not Requiring Prior Comission Approval in accordance with Part 50.59(b) of Title 10, Code of Federal Regulations, for the period of January 1,1979 through December 31, 1979.
If you have any questions concerning this report, please contact thii o f fice.
Very truly yours,
$Md Don Ware = bourg Manager, Nuclear Production DW/cis Enclosure.
V O
cc: Director, I & E O *p\\ Ii\\
I
( Y]
~
"co2260 1
b
PUBLIC SERVICE COMPA!.T 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, 1979, through December 31, 1979 5
i:
TABLE OF CONTENTS Page Introduction -------------------------------
3 1.0 Public Service Company Change Notices 5
2.0 General Atomic Company Field Change Notices 6
3.0 General Atomic Cocpany Requests for Test 8
4.0 Public Se rvice Company Tes ts - - - - - - - - - - - - - - - - - - - - - 10 5.0 Table of Abbreviations - - - - - - - - - - - - - - - - - - - - - - - - 12 6.0 Sys tem Numbe r Identification - - - - - - - - - - - - - - - - - - - - - 14 m
2 Ii
. INTRODUCTION This report is submitted to comply with the requirements of Part 50.59(b) of Titic 10, Code of Federal Regulations as they apply to Fort S t.
Vrain Nuclear Generating S tation, Unit No.1.
It includes the period of January 1,1979, through December 31, 1979.
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.
Field Change Notice - Documents modification work proposed and installed by contractor.
"T" Tests - Documents tests proposed and conducted by Public Service Comp any.
"RT" Tests - Documents tests proposed and conducted as requested by contractor.
In this report, the Safety Evaluation for the changes and tests listed is sum-marized. The terrinology used in these summaries is defined as follows:
Safety-Related Facilities - Those plant systecs, structures, equipment, and components which include the following features:
a) Seismic Class I per the Final Safety Analysis Report.
b) Safe Shutdown as described in the Final Safety Analysis Report, cl Engineered Safeguards as described in the Final Safety Analysis Report, d). Portions of radioactive waste systems whose failure would result in release of radioactive gas or liquid in excess of maximum permissible con >ent ra tion.
S afe ty Significant Change a) Changes to the facility, systecs, components, or structures described in the Safety Analysis Report, that may affect the capability to pre-vent or mitigate the consequences of accident situations that could endanger the health and safety of the public or could result in ex-posures to plant personnel in excess of occupational limits.
bl Changes in nuclear safety related systems which involve the addition, deletion, or rework of components, structures, equipment, or systems such that the original design intent is changed.
c). Any change that would result in an unreviewed safety question or require a Technical Specification change.
1
. Unreviewed Safety Question - Any plant modification or activity is deemed to involve an unreviewed safety question when:
a) The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in l
the Final Safety Analysis Report may be increased.
b) The possibility for an accident or malfunction of a different type than any evaluated previously in the Final Safety Analysis Report may be created.
c) The margin of safety as defined in the basis for any Technical Speci-fication 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.
E I
l l 1.0 PUBLIC SERVICE COMPANY CHANGE NOTICES Change, Test, or Experiment System /
Description of Change, Summary of Safety Nu=ber Component Test, or Experiment Evaluation CN 230 21/RT-21251 Install new sample sup-Not safety significant.
ply to RT-21251 in Not an unreviewed safety order to delete the question.
need for a pu=p on the RT.
CN 315 93 Design, procure materi-Not safety significant.
al, and arrange for re-Not an unreviewed safety build of both manifolds question.
of fast gas and iodine samplers (panels I-74 and I-75).
CN 454 21 Provide interlocks on Safety significant. Not circulator water tur-an unreviewed safety bine inlet and outlet question.
valves to prevent manu-al opening when circu-lator is operating on steam turbine drives.
CN 517 45 Seal cable floor pene-Not safety significant.
trations between Con-Not an unreviewed safety trol Room and Auxiliary q ues tion.
Electrical Equipment Room with three-hour fire-rated firestop s ealan t.
3 k
i:
2.0 GENERAL ATOMIC COMPANY FIELD CHANGE NOTICES Change, Test, or Experiment System /
Description of Change, Summary of Safety Numb er Cocoonent Test, or Experiment Evaluation GA FCN 2876A 92 Add 20 amp breaker pro-Not safety significant.
tection to secondary Not an unreviewed safety side of 480/120V AC CRD question.
MCC transformers and lower size of primary breakers f rom 20 amps to 15 amps. This will provide more adequate breaker protection.
GA FCN 2906A 46/HV-4669, Revise electrical Not safety significant.
HV-4670 wiring such that Not an unreviewed safety HV-4669 /4670 fail open question.
rather than closed on loss of either air or
< ctrical.
GA FCN 2919 21
. 41fy backup bearing Not safety significant.
water gas side charging Not an unreviewed safety valves.
question.
GA FCN 3086B 21/TR-Add time delay relays Not safety significant.
21285, TR-to prevent backup Not an unreviewed safety 21286 bearing water accumula-question.
tors from interacting with emergency shutdown accumulators on helium circulators.
GA FCN 3597A Ebisture Make changes required Not safety significant.
Monitors in panel I-10 to imple-Not an unreviewed safety ment moisture monitor q ues tion.
sample flow alarm sys-tem modification noted in FCN 3610 and FCN 3611.
GA FCN 3610 11/XC-1115 Revise wiring on XC-Not safety significant.
thru 1122 1115 thru 1122 modules Not an unreviewed safety to permit connection of question.
=oisture monitor sacple flow alar =s to local annunciator panel.
?
3 I
. 2.0 GENERAL ATOMIC COMPANY FIELD CHANGE NOTICES (Cont'd)
Change, Test, or Experiment System /
Description of Change, Summary of Safety Number Cocponent Test, or Experiment Es alua tion GA FCN 3956 Plant Pro-Modify linear power Safety significant. Not tective range channel drawers an unreviewed safety System to provide a manual question.
reset of 30% power bi-stables.
GA FCN 3968 Plant Pro-Rewire CS-1 modules, Safety significant. Not tective I-10 bins and I-10 an unreviewed safety System board connectors of the question.
plant protective system in order to allow by-passing low main steam temperature loop trip on reactor scram.
GA FCN 4102 93/TR-Set a time delay relay Not safety significant.
93163A & B/ of 200 to 1000 mil-Not an unreviewed safety TR-9 3164A & liseconds into relays question.
B TR-93163A & B/TR-93164A
& B.
GA FCN 4143 Plant Pro-Reset modifiers which Safety significant. Not tective set the low feedwater an unreviewed safety System flow program trip under q ues tion.
one circulator opera-tion in a loop.
GA FCN 4268 Plant Pro-Provide a mechanism for Safety significant. Not tective removing high water an unreviewed safety System turbine speed input to q ues tion.
the helium circulator single channel trip alarm system.
GA FCN 4544 Co re Provide for instal-Not safety significant.
lation of 84 region Not an unreviewed safety ccastraint devices.
question.
I b
5 3.0 GENERAL ATOMIC COMPANY REQUESTS FOR TESTS Ch ange, Tes t,
or Experiment System /
Description of Change, Summary of Safety Number Component Test, or Experiment Evaluation RT-416 12/18/22 Demonstrate capability Not safety significant.
of core orifices to Not an unreviewed safety equalize steam gener-question.
ator module inlet heli-um temperature and of feedwater trim valves to equalize main steam temperature when module inlet helium tempera-tures are not equal.
RT-427 21 Observe and document Not safety significant.
performance of helium Not an unreviewed safety circulators on condea-question.
sate drive at reduced PCRV pressures.
RT-428 21 Determine effect of in-Not safety significant.
creased cold helium Not an unreviewed safety temperature on "A",
question.
"B ", " C", and " D" circulator penetration primary closures.
De-termine leak rate for all helium circulator interspaces.
RT-436 12 Determine effective Data taking only.
" full-closed" position of core-flow orifice valves.
Determine flow characteristics at near-closed orifice po-sitions. Characterize time response of region outlet temp eratures,
following orifice move-ments at near-closed positions.
RT-439 12 Measure core power Data taking only.
distribution each time a rod bank is fully withdrawn and compare with calculated power dis trib ution.
I f
. 3.0 GENERAL ATOMIC COMPA'TY REQUESTS FOR TESTS (Cont'd)
Ch ange, Tes t,
or Experiment System /
Description of Change, Summary of Safety Number Cocoonent Test, or Experiment Evaluation RT-486 12 Collect data and com-Data taking only, pare data associated with instrumented con-trol rod drives to data f rom calibrated plant ins truments.
RT-505 13/ Fuel Demonstrated and quali-Not safety significant.
Handling fy backup method for Not an unreviewed safety Machine fuel handling machine question.
index arm retraction in the event the arm be-comes stuck in extended position.
RT-518A/B Reactor Visually inspect core Not safety significant.
Core components in and Not an unreviewed safety around region 35 for question.
evidence of fluctuation related motion.
RT-519 12 Perform detailed Not safety significant.
functional check of Not an unreviewed safety special instruments in-question.
stalled in modified control rod drives.
RT-523A Core Verify by test that Not safety significant.
region constraint de-Not an unreviewed safety vices can be installed q ues tion.
and removed by the fuel handling machine in a single region.
RT-525 13/18 Inspect and character-No t safety significant.
ize up to 51 irradiated Not an unreviewed safety Fort S t. Vrain segment question.
1 fuel and reflector elements for structural performance.
3 s
4.0 PUBLIC SERVICE COMPANY TESTS Change, Test, or Experiment System /
Description of Change, Summary of Safety Numb er Cocoonent Test, or Experiment Evaluation T-38 93/RIS Functionally test radi-Not safety significant.
Modules ation indication switch Not an unreviewed safety modules upon completion question.
of soldering repair.
T-105 11 Ob tain pressure decay Not safety significant.
data on "C" circulator Not an unreviewed safety interspace penetration question.
to determine interspace leakage.
T-108 Plant Pro-Verify proper operation Not safety significant.
tective of plant protective Not an unreviewed safety System system logic power fast question.
shutdown circuitry.
T-111 22/TE-22101 Verify calibration of Not safety significant.
thru 22106 plant protactive system Not an unreviewed safety superheat thermocouples question, with an RTD as required by Technical Specifi-cations.
T-112 21/P-2109, Verify capability to Not safety significant.
P-2110 maintain core inlet Not an uareviewed safety temperatures less than question.
or equal to 165'F. with one circulator being driven by boosted emer-gency condensate while primary coolant pres-sure is approximately s ubatmospheric.
T-114 48/ACM Die-Determine fuel oil con-Not safety significant, sel Gener-sumption of ACM diesel Not an unreviewed safety ator generator.
question.
T-115 Reactor Verify shutdown margin Not an unreviewed safety Core of 0.01 ao can still be q ues tion.
maintained with instru-mented control rods in regions 5 and 35.
?
3 I
.b
4.0 PUBLIC SERVICE COMPANY TESTS (Cont' d)
Ch an ge, Tes t,
or Experiment System /
Description of Change, Summary of Safety Number Cocoonent Test, or Experiment Evaluation T-116 Plant Pro-Determine by test the Not safety significant.
tective effect of optical iso-Not an unreviewed safety System lator unit on logic question.
chip failure rate.
T-ll 7-Nbisture Determine why moisture Not safety significant.
Monito rs monitors trip when Not an unreviewed safety being powered up af ter question.
recent moisture monitor two-loop dump modifi-ca tions.
T-119 Reactor Collect data for use in Data taking only.
Core analyzing region peaking factors.
T-121 21 Obtain data for System Data taking only.
21 loop split modifi-cation, including per-formance data for buf-fer helium recircu-lators.
T-124 11/SUC-Test startup channels Not safety significant.
1131, 1132 to determine if either Not an unreviewed safety of the detectors or the ques tion.
amplifiers need changed out p rior to region constraint device in-stallation.
3 5
i:
. 5.0 TABLE OF ABBREVIATIONS ACM Alternate Cooling :hthod ANSI American National Standards Institute ASCO Automatic Switch Company ASTM American Society for Testing Material C
Comp ressor CFM Cubic Feet / Minute CN Change Notice (PSC)
Exchanger (Heat)
F Filter FCN Field Change Notice (Non-PSC 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 N2 Nitrogen (_ Gas)
NRC Nuclear Regulatory Commission P
Pump E
PCRV Prestressed Concrete Reactor Vessel b
5.0 TABLE OF ABBREVIATIONS (Cont'd)
PDV Pressure Differential Valve PPS Plant Protec tive 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 Reques t for Test (General Atomic Company)
S&L Sargent and Lundy T
Tank, Special Test (PSC)
TIG Tungsten Inert Gas TT Temperature Transmitter V
Valve r
3
. 6.0 SYSTEM NUMBER IDE'iTIFICATION TABLE 11 Reactor Vessel and Internal Components 12 Control Rods and Drives 13 Fuel Handling Equipment 14 Fuel Storage 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 S torage 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 51 Turbine Generator and Auxiliaries 5
52 Turbine S team I:
t t
..,. 6.0 SYSTEM NUMBER IDENTIFICATION TABLE (Cont'd) 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 Drains) 73 Reactor Plant Ventilation System 75 Turbine Building (Vents and Drains, HVAC) 82 Instrument 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 3
.