ML20246G920
| ML20246G920 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/30/1989 |
| From: | Fitzpatrick E GENERAL PUBLIC UTILITIES CORP. |
| To: | Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8907140279 | |
| Download: ML20246G920 (4) | |
Text
-
l 1
GPU Nuclear Corporation
~ Nuclear
- g = 888 Forked River,New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number
June 30,1989 Mr. William T. Russell, Administrator Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
Dear Mr. Russell:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 10CFR50.59(b) Reporting Requirements Pursuant to the provisions of 10CFR50.59(b), erclosed is a brief description of changes made to the Oyster Creek Nuclear Generating Station as authorized under 10CFR50.59(a)(2) for the calender year 1988. The report includes those modifications / changes that were put into service before the end of 1988. The remainder of the chates that occurred during the 12R refueling outage will be included in the rnt annual submittal.
In each case, the corresponding safety evaluation concluded that there was nc unreviewed safety question involved.
Should you have any questions concerning this submittal, please contact Mr.
George Busch, Oyster Creek :icensing Manager at (609)971-4643.
Very truly yours, E.E.Fitzp}atrick?W Vice President and Director Oyster Creek EEF/KFB/dmd (0780A)
Enclosure cc: Mr. Alexander W. Dromerick, Project Manager U.S. Nuclear Reg >1atory Commission Division of Reactor Projects I/II Washington, DC 20555 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731
\\ \\
8907140279 890630
)
PDR ADOCK 05000219 1
R PNV l
GPU Nuclear Corporation is a subsidiary of the General Pubhc Utihties Corporation J
l
^
e 1
u BA 402558-INTAKE STRUCTURE MODIFICATIONS The modification consisted of. installation of a new trash rake and cart, l
removable covers for the traveling water screen troughs, and rails for the trash rake.. Also, condition of concrete was inspected and necessary upgrading was done by removing the deteriorated concrete and building up the damaged portion'with new concrete.
This modification was implemented in response to general. deterioration of the intake structure and related equipment primarily due to salt water corrosion, replace existing equipment, and make minor modifications to the intake structure.
This modification has no adverse impact on plant safety and does not constitute an unreviewed safety question as defined in 10CFR50.59.
BA 402804-LIQUID POISON TANK LEVEL INSTRUMENTATION UPGRADE This modification included the replacement of the existing inoperable level transmitter and difficult to calibrate level switches with a new ultrasonic.
level detection system. The overall operation of the Liquid Poison system was not affected..
This modification has no adverse impact on plant safety and does not constitute an unreviewed safety question as defined in 10CFR50.59.
BA 402807-CONTROL ROOM PANEL 3F CRT REPLACEMENT The purpose of this modification is to replace the existing Sigma cathode ray tube (CRT) monitor located over control room panel 3F with a new high resolution CRT compatible with the Plant Computer System. The new CRT provides SPDS displays, E0P support displays, alarm information, multi-parameter trends, and historical data. Providing the operators at panel 3F with the above information enhances nuclear safety and safe plant s hutdown.
This modification has no adverse impact on plant safety and does not constitute an unreviewed safety question as defined in 10CFR50.59.
(..
L BA 402850-REPLACEMENT OF BUILT-UP ROOF 0F THE REACTOR BUILDING The purpose of this modification is to replace the deteriorated built-up roof of the Reactor Building with new class 1 (considered non-combustible) roof.
After removing the old built-up roof, the metal roof-deck was inspected and the damaged areas were repaired or reinforced without cutting or opening the existing deck. As a result, the existing function of secondary containment was not affected.
This modification has no adverse impact on plant safety and does not constitute an unreviewed safety question as defined in 10CFR50.59.
BA 402853-1El UNIT SUBSTATION POWER SUPPLY The lEl Unit Substation receives power from a 44.5 kV distribution line supplied by the JCP&L 34.5 kV Oyster Creek substation. This distribution line had frequent outages, one of which resulted in an unmonitored release.
The modification provided an additional source of power to the 1El substation supplying New Radwaste/ Package Boiler House /0ffgas Building, and a pair of circuit breakers to shift to an alternate source of power if the primary source fails.
This modification improves the availability of power supply to the 1El substation, has no adverse effect on plant safety, and does not constitute an unreviewed safety question as defined in 10CFR50.59.
BA 402882-REACTOR WATER CLEAN-UP (RWCU) SYSTEM FILL / START-UP LINE A bypass line around outboard containment isolation valve V-16-14 was installed. This line provides a means to fill the RWCU system prior to system restart after an inadvertent trip during power operation.
Operators previously throttled containment isolation valve V-16-14 which caused water hammer and wear. - The bypass will enable operators to fill and pressurize the line upstream of system control valve ND-11 during RWCU system startup.
The affected portion of the RWCU system does not perform a safety function, and therefore the modification does not adversely affect nuclear safety and does not constitute an unreviewed safety question as defined in 10CFR50.59.
BA 402902-EXTENDED LIFE CONTROL R0D PROCUREMENT During the 12R outage, seventeen (17) extended life control rods were installed at Oyster Creek. This change reduces outage critical path time as these control rods will only require replacement every third outage instead of every outage.
1 This modification has no impact on plant safety and does not constitute an
)
unreviewed safety question as defined in 10CFR50.59.
l 1 1