ML19276E473
| ML19276E473 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 03/01/1979 |
| From: | Groce R YANKEE ATOMIC ELECTRIC CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| WYR-79-25, NUDOCS 7903140252 | |
| Download: ML19276E473 (15) | |
Text
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Totophone 617 366-9011 rwx 780 3 9 3.c739 YAl!KEE A703!C ELECTRIC C0h1 pally s.4.1.1
.n ?.'1 20 Turnpoko Road Woubt c;h, Massachusetts 01581
.YAmxes WR 79-25 March 1, 1979 United States Nuclear Regulatory Cor=ission Office of Inspection and Enforectent Region I 631 Park Avcnue Ring of Prussia, Pennsylvania 19406 Attention: Mr. Boyce H. Grier, Director
Reference:
License No. DPR-3 (Docket No. 50-29)
Dear Sir:
Subj ec.t:
Yankee Rove 1978 Annua 1 Report Enclosed hercuith please find two (2) copies of the Yankee Rove Annual Report, which descri*oes.the facility changes, tests and experiments conducted without prior ERC approval during the year 1978.
This report is submitted in accordance with 10 CFR 50.59(b) and Yankee Rowe Technical Specification 6.9.2b requirements.
We trust this inf ormation is acceptable to you; however, should I
you have any questions, please contact us.
Very truly yours, 1*J.Lc. tuwm r.LECTRIC COMPANY M
Robert H. Groce Licensing Engineer RTT/cm Enclosurc 790314025&7-
l YANKE-A10:11C ELECTRIC COMPANY YMI:EE ATOMIC ELECTRIC NUCLEAR STATION AWUAL REPORT i
1978 i
Prepared By Yankee Atomic Electric Company i
Technical Assistant to the Plant Superintendent's Department Star Route Rowe,llassachusetts 01367
e 1978 ANNUAL REPORT Table of Centents TITLE
_PAGE_
.1 Title Page.
Table of Content
.2
.Introduct on.
.3 i
Other Changes, Tests and Experiments:
A.
Engineering Design Changes.
.4 B.
Plant Design Changes
.5 C.
Plant Alterations
. 11 D.
Test.
. 14 E.
Experiments.
. 14
INTRODUCTION i
The Yankee Atomic Electric Nuclear Power Station is a Pres-surized Water Reactor (Pb"il) of 175 !!W electrical, maximum dependable capacity (!IDC).
The nuclear steam supply system is a Westinghouse 4 loop reactor.
The architect / engineer and constructor for this project was Stone & Webster Engineering Corporation, Boston.
The condenser cooling is once through using the Deerfield River as a cooling medium.
The plant is operated in accordance with license DPR-3, issued July 19, 1960, pursuant to Docket Number 50-59.
The date of initial reactor criticality was August 19, 1960 and commercial operation began July 1, 1961.
This annual report represents the first of a series and is submitted in accordance with Technical Specifications, Section 6.9.2.
t f
4 f
Other Changes, Tests, and Experiments A.
Engineering Design Changes 1.
The following is a list of those fully approved Engineering Design Changes that were implemented during the year 1978.
a.
Engineering Design Change No. 76-13 EDCR 76-13, On Site Meteorological Program Upgrading, was completed during this report period.
This change allows for the accumulation of data required by the NRC for reporting requirements.
This change does not impose any unreviewed safety question in that the plant will operate in the same manner as that covered in the existing Safety Hazard Report.
b.
Engineering Design Change 77-20 EDCR 77-20, Ground Datection Alarms for 480 and 2400 V Switch Gear, was completed during this report period.
This change consisted of replacing the existing ground detectors on the 480 and 2400 volt buses with ground detcetors with alarm function and an alarm in the Control Room.
This change was designed to enhance equipment safety and reliability ard does not impose any unreviewed safety question in that effected systems will operate in the same manner as covered in the existing Safety Hazard Report.
c.
Engineering Design Change No. 77-26 EDCR 77-26, Diesel Generator Alarm Modification was completed during the report period.
This change consisted of clarifying the EDG alarms and adding new alarms to make the operators more aware of any diesel malfunction.
The modification does not impose any unreviewed safety questiot. in that it will operate in the same manner as that covered in the existing Safety Hazard Report.
d.
Engineering Design Change No. 78-1 EDCR 78-1, Alterations to Post - LOCA Recirculation System, was completed during this report period.
This change involved the addition of piping and valves to provide a flow path from the vapor container sump through the safety injection pumps and back to the reactor. The reason for the modification is to improve the long term cooling capabilitics of the Emergency Core Cooling System.
This change does not present significant hazaris not described or implicit in the Sa ety Analys b Report.
f e.
Engineering Design Change No. 78-14 EDCR 78-14, Containment Electrical Penetration MI Cable End Seal Modification was completed during the rep o rt.
period.
The change consisted of modifying certain mineral insulated (llI) cable end seals of containnent electrical penetration to ensure operability for post LOCA service.
The modification was performed to enhance the safety of the facility and does not impose any un-reviewed safety question in that effected systems will operate in the same manner as covered in the existing Safety Hazard Report.
f.
Engineering Design Change No. 78-20 EDCR 78-20, Alternate Emergency Steam Generator Feed was 9
completed during this report period.
This change pro-j vides a mechanism for supplying feed flow to the steam i
generators which will be independent of the effects of a fire in the turbine building.
This change does not present significant hazards not described or implicit in i
the safety Analysis Report and does not involve an un-i reviewed safety question.
j B.
Plant Design Changes i
1.
The following is a listing of those fully approved Plant j
Design Changes that were implemented during the year 1978.
a.
Plant Design Change 76-4, Replacement of a Component Cooling Heat Exchanger, was completed during this report j
period. This change consisted of replacing one component j
heat exchanger with a new heat exchanger designed' for j
service water through the tubes and component cooling I
water through the shell. This change would permit clean-ing of the service water side by plant personnel instead of chemical cleaning by contractors.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner i
as covered in the existing Safety Hazard Report.
r b.
Plant Design Change 76-17, Eupl. #2, V.C. Type C Testing l
Modification on the Neutron Shield Tank Tell Tale and Air Charging Line was completed @ ring the report period.
The change consisted of adding test taps and isolation valves to a Row testing to 10 CFR 50, Appendix J cri-teria.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
i c.
Plant Design Change 76-20, Installation of a Spare Bat-tery Charger was completed during the report period. The change consisted of adding a fourth battery charger which would replace any one of the three existing chargers in the event of a failure.
This change increases the relia-bility of the DC distribution system.
This change does not impose any unreviewed safety ques-tien in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
d.
Plant Design Change 76-30, Addition of a Pulsation Damp-ener on the No.
I Charging Pump Discharge Header was completed during the report period.
The change consisted in adding the dampener and large sweeping elbows to the discharge of the pump.
This change will reduce the intensity of vibration on the charging line; thus, mini-mizing fatigue failures.
This change does not imposs any unreviewed safety ques-tion in that the sy;, tem will operate in the same manner as covered in the existing Safety Hazard Report.
c.
Plant Design Change 76-34, Primary Seal Tank Level Ind-icaticn Modification was completed during the report period.
The change consisted of adding a level trans-mitter and level indicator to the seal water tank and adding two test valves for the low level switch.
This change will aid in monitoring and maintaining the tank level.
It will also facilitate calibration and testing of the low level switch.
This change does not impose any unreviewed safety ques-tica in that the systera will operate ia the same manner as covered in the existing Safety Hazard Report.
(
f.
Plant Design Change 76-38, Replacement cf the Diesel Day Tanks Level Contro: was completed during the.:epo r t period.
The change consisted of replacing GEMS level controls on the diesel day tanks with more recent state of the art GEMS level controls. This change provides for easier adjustment of makeup and alarm setpsints.
1 This change does not impose any unreviewed safety ques-tion in that the system will bperate in the samc manner as covered in the existing Safety Hazard Report. I
g.
Plant Design Change 77-6, Emergency Boiler Feed Pump Modifications was completed during the report period.
The change consisted of replacing the emergency boiler feed pump relief valve with a flanged type relief valve and in adding a bypass between the ccadensate makeup and the emergency boiler feed pump suction. This change will facilitate inspections and repairs to the relief valve.
The additian of the bypass will provide direct suction of the condensate makeup system to the emergency boiler feed pump.
This change does not impose any unreviewed safety ques-tion in that the systea will operate in the same manner as covered in the existing Safety IIazard Report.
h.
Plant Design Change 77-11, Change of Emergency Lighting From the No. 3 Station Battery to the No. 2 Station Battery was completed during the report period.
The change consisted of relocating the emergency lighting load from No. 3 Station Battery to the No. 2 Station Battery to equalize load requirements for the station batteries.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
i.
Plant Design Change 77-12, Capping of Defective In-Core Flux Mapping Paths J4 and D3 was completed during the report period.
The change consisted in plugging two pret.surized flux tubes.
Technical Specification limits reactor operations to two pressurized flux tubes.
Thus the failure of a third flux tube will result in only one pressurized flux tube which is not capped and will not require a reactor shutdown for repair.
This change does not impose any unreviewed safety ques-tion in that the system will i.perate in the same manner as covered in the existing Safety Hazard Report.
j.
Plant Design Change 77-13, LPSI Pump Mechanical Seals was completed during the report. period. The change consisted of replacing the packing with a mechanical seal on Number 2 and 3 pumps.
This change greatly reduces non-running leakage without effecting the operation of the pumps.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
k.
Plant Design Change 77-14, Removal of Perry Water Filters From Diesel Generato~..was completed during.the report period.
The change tviaisted of removing the filter and plagging the filter line which is a small bypass line.
The change was recommended by the manufacturer to mini-mize a build-up of contaminents in the cooling system caused by the old type water filter which could contri-bute to overheating prob 1ces.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
1.
Plant Design Change 77-15, Replacement of the Charging and Volume E/P Converter and Replacement of Pressurizer Indicator Channel was completed during the report per-iod. The change consisted of replacing the converter and indicator with a state-of-the-art converter.
This change increases reliability and accuracy of the system. More-I over, it facilitates obtaining of spare parts.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
Plant Design Change 78-3, Installation of plug connectors n.
on motor and control leads for safety injection motor I
operated valve contactors on Emergency Motor Control center No.
2.
This change consisted of adding pit. and socket connectors to SI-MOV-22, 23, 24 and 25 motor a.'d
{
control leads.
This change will allow personnel to make I
those valves operational quickly with little change af error.
This change does not impose any unreviewed safety ques-j tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
i Plant Design Change 78-04, Replacement of the Power Range o.
Gain Control was completed during the report period.
The change consisted of replacing the gain controls with i
state-of-the-art controls.
This change increases relia-bility, reduces maintenance time and facilitate adjust-ments by the operators.
j This change does not impose any areviewed safety ques-tion in that the system will ope:.te in the same manner as covered in the existing Safety Hazard Report. i
p.
Plant Design Change 78-6, Replacement of V.C.
Terninal j
completed during the report period.
This Boards was change consisted of replacing those terminal blocks that would be required to be operational under accident condi-I tions.
This change will insure the operation of safety related equipment during an accident condition.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
g.
Plant Design Change 78-7, Rerouting Charging Pump Relief completed during the report period.
Valve Discharge was The change consisted of routing thc discharge piping from the suction side of the pumps to the floor.
A splash guard was provided.
The discharge will drian ultimately to the gravity drain tank.
l l
This change does not impose any unreviewed safety ques-Lion in that the system will operate in the sane manner as covered in the existing Safety Hazard Report.
Plant Design Change 78-8, Emergency Cooling Supply to No.
r.
2 C.C.
Heat Exchanger was completed during the report period.
The change consisted of providing a valve and a capped hose connection at the inlet to the heat exchanger service water side.
This. change allows cooling of No. 2 component cooler with fire protection water.
s This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
s.
Plant Design Change 78-9, Replacement of Level and Pres-r sure Transmitters was completcd during the report period.
The change consisted of replacing the level transmitter on the component cooling surge tank and the safety injec-tion tank, and the replacement of the pressure trans-mitter on the Boric Acid Mixing Tank transfer pump.
This change is part of the plant continuing program to update instrumentation to ensure availability of repair parts and/or improve reliability.
This change does not impose any unreviewed safety ques-tion in that the system willtoperate in the same manner as covered in the existing Safety Hazard Report.
9.
t.
Plant Design Change 78-10, Addition of Emergency Diesel Generator Voltage Controls and Watt meters on the Safety Injection Panel was completed during this report period.
This change consisted of, replacing the local voltage control with a remotely operated rheestat and the addi-tion of Watt meters taounted on the safety injection panel.
This change will enable the diesel operator in the Control Room to regulate the voltage and to verify loading requirements.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
Plant Design Change 78-12, Permanent Service Air for the u.
V.C. Personnel Hatch Pressure Test, was completed during this report period.
This change consisted of installing permanent service air piping to the V.C. personnel hatch for air pressure testing requirements.
Due to the test-ing frequency permanent piping is considered necessary.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
v.
Plant Design Change 78-13, Installation of Gauges on Safety Injection Nitrogen System was completed during the report period. The change consisted in adding a gauge on the 500 psi and 100 psi nitrogen system that can be read more easily and that can be calibrated.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
w.
Plant Design Change 78-15, Relocation / Replacement of Heise Line (SIAS) Pressure Switch was completed during the report period.
The change consisted of relocating the heise line pressure switch sensing point from the pressurizer to loop 2 and/or loop 3, and replacing the heise line pressure switch.
The pressure switch was replaced because of its low temperature limitation.
The relocation is to improve response time and provide for three loop cperations.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
x.
Plant Design Change 78-16, Diesel Genera t.or l'uel oil supply Modifications was completed during this report period.
The change consisted of rerouting the fuel oil supply line for the E.D.G. 's and increasing the fuel oil day tank supports.
This change is for system upgrading I
for fire protection.
t This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
y.
Plant Design Change 78-18, Addition of a Root Valve for the Hogger Jets was completed during the report period.
The change consisted of adding a second isolation valve between the auxiliary steam header and the hogger jets.
This change will help ensure the hoggers are not over-pressured due to seat leakage.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
C.
Plant Alteration 1.
The following is a listing of those fully approved Plant Alterations which required a safety evaluation that were impleme:.cd during the year 1978.
a.
Plant Alteration 77-14, Instalation of a check valve up stream of SW-V-875, to prevent service water f r. m by-passing the coagulator.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered i.t the existing Safety Hazard Report.
b.
Plant Alteration 77-15, Instalation of nitrogen cylinder charging connections in the Safety Injection Accumulator Cubicle for filling the 1/4 size nitrogen cylinders.
This change will eliminate the need to transfer nitrogen cylinders up and down stairs, therefore it will eliminate a safety hazard.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report. h
c.
Plant Alteration 77-16, Installation of a condensate return sump pump to the PCA storage building heating system.
This char will increase the condensate return u
s rate from the PCA storage to the vaste disposal building to allow better heating.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
d.
Plant Alteration 77-17, Installation of a small puri-fication ion exchanger in conjunction with the existing filter on the waste disposal evaporator effluant piping.
This change is designed to aid in reducing radioactive constitucnts which are discharged to the environment to a minimum.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
e.
Plant Alteration 77-22, Relocation of the Heater Drain pump cooling water connection to the service water system.
This change will reduce the possibility of contaminating the potable water system supply with nonpotable water.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
f.
Plant Alteration 77-25, Rerouting the gland steam dump line directly to the condenser.
This change will in-crease the efficiency of the gland steam dump line and decrease the possibility of a pipe rupture.
This change does net impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
g.
Plant Alteration 78-04, Removal of the Steam Generator Blowdown Tank Effluent Neptune meter and installation of a pressure switch and timer on the pneumatic control lines to LCV-408.
This timer will conitor the total time fluid is discharged to the river.
From this time, the total quantity of water discharge from the blowdown tank may be calculated.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
12 -
6 h.
Plant Alteration 78-10, re-routing the gravity drain tank vent to the filtered ventilation exhaust system.
This change will reduce the potential for radioactive dis-charge to the enviroraent.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
i.
Plant Alteration 78-12, replacement of No. I feedwater heater with a new unit.
This change will increase the plant efficiency and decrease the chances of shutdown for tube trouble.
This change does not impose any unreviewed safety ques-tion in that the system will cperate in the same manner as covered in the existing Safety Hazard Report.
j.
P1.. Alteration 78-19, install: tion of an isolation vam.e for the top hat drain trap. This change will allow more efficient steam drain system operation and increase reliability by providing an inservice maintenance capabi-lity.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
k.
Plant Alteration 78-20, replacement of feedwater, con-densate, service water, seal oil and makeup water in-strument transmitters, with addition of test connections and drain valves to the sensing and air lines.
This alteration will increase the overall accuracy and system reliability.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
1.
Plant Alteration 78-25, installation of a high level alarm on the prima ry drain collecting tank sump.
The addition of this alarm is to warn the operator of a possible flooding condition.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
13 -
m.
Plant Alteration 78-27, installation of a filter in the air supply line to tha N2 booster pump.
'Ihis change is to reduce pump maalanance, down time and expense by reducing the oil carry-over to the air motor which, according to the manufacturer, requires no lubricant in the air supply.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
n.
Plant Alteration 78-37, addition of curbs at the aux-iliary boiler room door, diesel generator cubicle doors, cubicle inter-connecting doors, and drains from the transformer oil coolers and iorn horse to the main transformer sump.
This change is to comply with commit-ments made for fire protection.
This change does not impose any unreviewed safety ques-tion in that the system will operate in the same manner as covered in the existing Safety Hazard Report.
D.
Tests 1.
There were no special tests performed during the reporting period, 1978.
E.
Experiments 1.
There were no experiments as defined in 10 CFR 50.59.a (2).
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