ML19290E344
| ML19290E344 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/31/1979 |
| From: | JERSEY CENTRAL POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19290E343 | List: |
| References | |
| NUDOCS 8003110005 | |
| Download: ML19290E344 (6) | |
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OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE DPR-16 ANNUAL REPORT STATION tiODIFICATIONS 1979 6
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- PRE ACE -
In accordance with 10 CFR 50.59 (b), this report includes those facility changes, tests, and experiments conducted at the Oyster Creek Nucicar Gen-erating Station without prior NRC approval during the period January 1,1979 through December 31, 1979.
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D 0YSTER CREEK NUCLEAR GENERATING STATION STATION MODIFICATIONS 1979
- 1. Sa'fety Related Electrical Equipment Seismic Supports As part of the Systematic Evaluation Program's review of the seismic adequacy of safety related electrical components, JCP&L performed a '
systematic inspection of these components. As a result of these inspections, actions were taken tc upgrade the seismic capability of the safety related 125V DC Battery B and several safety related panels.
Conclusion of Safety Evaluation:
The purpose of this modification is to provide additional hold down capability to the safety related equipment as dictated by calcu-lations and analysis with respect to the furnished hold down criteria.
The proposed modifications do not affect the safety function of these equipments; but, it will provide more safety margin in case of earth-quake. Therefore, this modification does not involve an unreviewed safety question.
- 2. Containment Spray System Undervoltage Modification As a part of the ECCS modification which was conducted in 1975, 1976, and 1977, it was desirable that the automatic starting sequence of containment ; pray pumps 1-1 and 1-3 terminate if an undervoltage condition existed on 4160V switchgear busses 1C and 1D. This would prevent a core spray pump and a containment spray pump powered from the same diesel generator from simultaneously starting and possibly overloading the diesels. This modification created a time window of approximately two to three mirutes during which the automatic start of the Containment Spray System would have been impossible during a LOCA with loss of offsite power.
ET 333-70 corrected this problem in addition to satisfying the original intent of ;he ECCS modification. This modification was installed while the plant was shut down in April 1979.
Conclusion of Safety Evaluation:
The proposed modification insures operability of at least one Containment Spray System. The design has been reviewed to insure that this modification does not degrade any safety function. The modification satisfies single failure criteria in that any single failure occurring within the modification itself will not prevent one of the Containment Spray Systems from operating. It is not intended at this time to upgrade the system to satisfy present day regulatory requirements.
Existing equipment will be used to implement this modification. This modification does not involve any unreviewed safety questions.
Oyster Creek Nuclear Generating Station Station Modifications - 1979
- 3. Diesel Generator Annunciator Systems The purpose of this chance was to separate diesel generator alarms in the control room annunciator panel, such that the operators would recognize the distinction between alarms that prevent automatic emergency starts and alarms which only indicate abnormal but not disabling conditions.
The modification was reviewed by PORC and was concluded that the change did not involve an unreviewed safety question. The panels involved were 8F/9F and 9XF in the control room.
Conclusion of Safety Evaluation:
The emergency diesel generator annunciator system is designed to '
provide the control room operator with an accurate status of the condition of the diesel generator. Presently, there is the possibility of some misinterpretation as to v 5at the status of the diesel is prior to or af ter automatic or manual ommands. The proposed modification will eliminate such misinterpre itions and will increase system reliability.
It is, therefore, concluded that this modification does not constitute an unreviewed safety question as defined in 10CFR50.59.
- 4. Diesel Generator Louver Modification The purpose of this modification was to provide a reliable diesel generator louver control system. This was required in order to prevent unnecessary hot engine shutdowns due to failure of louver actuator temper-ature switch. The change involved the addition cf a time delay relay, a new annunciator window in the control room and replacing a single relay with two time delay relays. The change was reviewed and approved by PORC as not involving an unreviewed safety question.
Conclusion of Safety Evaluation:
The introduction of a new time delay relay in the diesel louver control circuitry will provide a means of bypassing the existing hot engine switch in case this switch should fail as it has done ir, the past. This backup component will increase system reliability during surveillance testing and throughout normal operation. By installing a new annunciator window in the control room, the operator will have more precise knowledge of the alarm sequence when the hot engine switch fails and when the backup relay takes over.
In addition, the segregation of the double action time relay
. (provides 2 second circuit at 15 second intervals to switch "TB") into a circuit with two (2) separate relays will ensure more reliable service.
Based on the above, the diesel louver control system will be more reliable than at present and, therefore, it is concluded that this modification does not constitute an unreviewed safety question as defined in 10CFR50-59.
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Oyster Creek Nuclear Generating Station Station Modifications - 1979
- 5. EFCV V-130-1 Open Verification Monitor Upon completion of surveillance testing of RK01, the excess flow check valve (V-130-1) must be verified to be in the open position. This was normally performed by valving in a pressure gauge and comparing it to reactor pressure. Performing this action can produce a pressure spike in the instrumentation sensing line and cause an unnecessary reactor scram.
Installation of a pressure transmitter allows verification to be performed by observing normal reactor pressure trans'ents and valving of the pressure gauge was eliminated.
Conclusion of Safety Evaluation: ,
The proposed modification does not adversely affect nuclear safety since no safety related equipment or safety functions will be affected by the installation and since the modification will be seis-mically designed and installed to assure no compromise of the functioning of the reactor protection instrumentation will exist.
The proposed modification does not involve an unreviewed safety question.
- 6. Spent Fuel Racks As part of the overall expansion program for the Oyster Creek spent fuel storage pool as defined in Amendment 78 to the FDSAR, the spent fuel storage capacity of the fuel pool was increased from 1176 storage locations to 1400 storage locations. This was accomplished by removing the old racks from the third row from the west wall and installing the higher density spent fuel racks and bases. As a result of previous difficulties encountered with the fuel rack base during the installation of rows one and two, the base was redesigned to facilitate ease of installation.
This redesign of the fuel rack base was reviewed by the PORC and determined not to involve an unreviewed safety question as defined in 10CFR50.59.
The spent fuel pool capacity expansion was approved by the NRC in License Amendment 22, issued March 30,19/7.
Conclusion of Safety Evaluation:
Based upon the discussion in the Safety Evaluation, it was concluded that the proposed modification will not create an unreviewed safety question as defined in 10CFR50.59.
- 7. Remote Manual Operation of Offgas Valves V-7-29 and 0G-SV-0016 The purpose of this modification is to provide the capability of selectively closing V-7-29 and OG-SV-0016 from the main control room upon an indication of a hydrogen detonation within the original Offgas System (i.e. excluding the A0G) in response to IE Bulletin 78-03.
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C,,;ter Creet da: lear Generating Station Ett:icn Modifications - 1979 Conclusion of Safety Evaluation:
The proposed modification, when implemented togethe with plar.:
procedure changes. will reduce the potential for the development of an explosive hydrogen mixture due to the loss of sump water seals. This by itself serves to increase safety. In addition, the proposed modi-fication does not adversely affect the ability of the Offgas System to perform its intended design function and does not, therefore, constitute an unreviewed safety question as defined in 10CFR50.59.
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