ML20087B507
| ML20087B507 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/03/1992 |
| From: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 C321-91-2324, NUDOCS 9201130152 | |
| Download: ML20087B507 (3) | |
Text
4 GPU Nuclear Corporation arsi pan, Ne Jersey 07054 201 316-7000 TELEX 136-482 Wnter's Direct Dial Nurnber.
January 3 1992 C321-91-2$24 U. S. Nuclear Regulatory Commission Att:
Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Response to NRC Inspection Report No. 50-219/91-23
-Your letter dated September 26, 1991 transmitted NRC Inspection Report No. 50-219/91-23.
The inspection was conducted on July 8-12, 1991 by your staff, Mr. L. Cheung and his consultant, to review GPU Nuclear's implementation pertaining to post-accident monitoring instrumentation.
The inspection report identified one deviation and one unresolved item, and requested GPU Nuclear's response within 30 days of the receipt date of the report. We contacted Mr. L. Cheung in early November and requested an extencion for our response by approximately one month.
Corrective steps taken and/or to be taken to ensure compliance with Regulatory Guide (R. G.) 1.97, Rev. 3 requirements on the deviation and unresolved item are provided below.
EDTICE OF DEVIATION NRC FINDING Contrary to the provisions of R. G. l.97, Rev. 3, no calibration program was specified for the instruments for the status of standby power, and the instruments had not been calibrated since 1986.
(Appendix A to the NRC letter of September 26, 1991).
GPU NUCLEAR RESPONSE The instruments for the status of standby power identified in Notice of I
Deviation include ammeters and voltmeters for 125-VDC batteries B and C, and kilowatt meters for Diesel Generators 1 and 2.
All meters are L
located on Control Room panel 8F/9F. The kilowatt meters were calibrated l
in June 1991 prior to the NRC inspection. The ammeters and voltmeters were calibrated immediately following the NRC inspection in July 1991.
Therefore, corrective steps have been taken by calibrating the jingtrumentsforthestatusofstandbypower.
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C32123?4.tET GPU Nuclear Corporat:or:is a subsidiary of General Pubhc Utihties Corporation i
C321-91-2324 Page 2 To further ensure full compliance with R. G.1.97, Rev. 3 with respect te calibration / testing, the existence of calibration / test programs will be confirmed or new programs will be established if needed for those instruments currently installed and considered as R.G. 1.97 parameters.
It ic projected that this effort will be completed by June 30, 1992.
UNRFSOLVED ITIB NRC FINDING
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The inspectors found several examples where the instrument range in the control room did not match the range identified in the licensee's Regulatory Guide 1.97 submittals or in the Final Safety Analysis Report (FSAR).
(Item 3.10, inspection Report 50-219/91-23).
GPU NUCLEAR RESPONSE Existing Regulatory Guide 1.97 instrument discrepancies have been verified via walkdowns. Any discrepancy between the installed instruments, FSAR description and previous GPU Nuclear submittals will be corrected and submitted with the annual FSAR update.
TAG NUMBERS AND INSTRUMENT IDENTIFICATION NRC FINDING During the physical inspection in the control room, the inspectors noted that many instruments, besides some of those audited for inspection, did not have instrument tag numbers on the control panel or the instrument face.
The licensee agreed to include equipment identification numbers on or adjacent to the instrument face as part of their human factors upgrade.
In addition, there was no unique ider.tification for the subset l
group of instruments-for Regulatory Guide 1.97 (Item 4.2, Inspection Report 50-219/91-23).
GPU NUCLEAR RESPONSI As it was discussed with your staff during the exit interview, GPU Nuclear will provide appropriate tag numbers or labels for those R. G.
1.97 instrument s on the control room panels by the end of the current operating cycle ;.;hich is now projected to be January 14, 1993.
In
-addition, unique 3dentification for the subset group of instruments for Regulatory Guide 1.97'will also be provided by the end of the current operating cycle per the commitment included in our May 1, 1991 letter to the NRC.
In addition, we have noticed the following discrepancies in Inspection Report No. 50-219/91-23.
i C3212324 LET
'C321-91-2324 Page 3 Item 3.2, Reactor pressure vessel water level, describes that "...the fuel zone range instrument is not powered by Class IE Power Sources..."
This is not entirely correct.
Power sources for the fuel zone level instrumentation are 120-VAC Reactor Protection Panels 1 and 2 for microprocessors and recorder, and 120-VAC panels VACP-1 and CIP-3 for transmitters. All these power panels are Class lE. However, the power supply for ine transmitter loops lacks separation. The proposed Reg.
Guide 1.97 modification, as described in our letter dated May 1,1991, will provide two new instrument power supply units for the transmitter
- loops, in addition, the concern regarding the loss of reactor protection system panel power during loss-of-offsite power event will ba resolved by providing two redundant Class IE power sources backed by diesel generators.
Item 3.3, Reactor Pressure Vessel Pressure, describes that "...the Licensee agreed to provide recording capabilities for this variable during the next refueling outage (14R)..."
The recording capabilities will be installed according to our Integrated Schedule.
If you have any questions concerning the above, please contact Mr. Michael 1.aggart, Manager, Corporate Nuclear Licensing at (201) 316-7968.
Sincerely, f
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- arton,
'Vi;e P esident and Director 0 ste Creek JBB/YN/ pip cc: Administrator, Region 1 NRC Resident inspector Oyster Creek NRC Project Manager J. P. Durr - NRC C3212324.LET