ML14097A176
| ML14097A176 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/11/1979 |
| From: | Baskin K Southern California Edison Co |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7901190120 | |
| Download: ML14097A176 (5) | |
Text
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 K. P. BASKIN TELEPHONE
- MANAGER, GENERATION ENGINEERING January 11, 1979 213-572-1401 Director, Office of Nuclear Reactor Regulation Attn: Mr. D. L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
Subject:
Docket No. 50-206, Provisional Operating License No. DPR-13 Fire Protection Program Review San Onofre Nuclear Generating Station Unit 1 The purpose of this letter is to provide the additional informa tion requested by the NRC staff concerning the status of the Fire Protection Program Review at San Onofre Unit 1. The information presented below has been discussed with the NRC staff during meetings or has been submitted to the NRC formally by letter.
- 1. Interim Shutdown Modifications As described in Enclosure 3 of our letter dated October 18, 1978, the modifications to allow for safe shutdown of the station following a fire in the 4160 volt switchgear room or the lube oil reservoir area were to be completed by the end of the outage for refueling for Cycle 7 operation. These modifications have been completed.
- 2. Air Supply Modifications As described in our letter dated November 22, 1978, the modifications to the air supply system for equipment required for safe shutdown following a fire in the 4160 volt Switchgear room or the lube oil reservoir area were to be completed by December 31, 1978.
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Mr. D.
January 11, 1979 modifications have been completed.
- 3. Deletion of Jockey Pump In accordance with agreements reached with the NRC staff during a meeting held on August 29, 1978 in Bethesda, Maryland, the crosstie between the San Onofre Unit 1 fire water system and the San Onofre Units 2 & 3 fire water system will be modified to allow for automatic water supply to San Onofre Unit 1. Since the San Onofre Units 2 & 3 fire water system currently includes an operating jockey pump which is adequate to maintain pressure on both fire water systems, the proposed jockey pump for San Onofre Unit 1 will be deleted from the design.
- 4. North Wall of Turbine Building Lube Oil Reservoir Area As described in Enclosure 2 of our letter dated October 18, 1978, the final modifications to the lube oil reservoir area will include (1) an upgrade of the north wall of the turbine building to a three hour fite rating with appropriate penetration seals, and (2) a fusable link wet pipe sprinkler system to provide protection to the 480 volt switchgear room walls and turbine building structural steel. As described in.our letter dated November 22, 1978, we plan to expand the coverage of the fusable link wet pipe sprinkler system to also protect the north wall of the turbine building. Consequently, the north wall of the turbine building including penetrations and discontinuities, will be upgraded to provide at least a one hour fire rating. This fire rating in combination with the water curtain protection results in a heat removal capacity in excess of a three hour fire rating.
- 5. Fire Barrier Penetration Seals for the 4160 Volt Switchgear As described in our letter dated November 22, 1978, the penetration seals for the 4160 volt switchgear room will have a three hour fire rating. Penetration seals with a three hour fire rating will not result in cable derating problems.
- 6. Reactor Coolant Pump Oil Splash Shields During the site.visit at San Onofre Unit 1 on October 19, 1978, the NRC staff requested additional information on the oil splash shields to be installed to prevent reactor coolant pump lubricating oil from impinging on reactor coolant piping. Accordingly, the following information is provided in response to the NRC staff request:
The reactor coolant pump lubrication system will be equipped with a containment/drip pan subsystem which will prevent oil leakage from contacting hot reactor coolant piping which could ignite the oil.
Mr. D.
January 11, 1979 The pressurized portions of the lubrication system will be completely enclosed in a metal housing.
The portions of the system which are essentially nonpressurized will have drip pans and drain lines to a drain funnel.
- 7. Safe Shutdown Capability As described in our letter dated October 18, 1978, a conceptual proposal describing the alternate method to bring San Onofre Unit 1 to a safe shutdown condition which does not rely on the Chemical Volume and Control System Test Pump for reactor coolant system inventory makeup will be submitted to the NRC by January 15, 1979.
In addition, our October 18, 1978 letter stated that an implementation schedule for the conceptual proposal will be submitted by January 15, 1979. Our letters dated October 18, 1978 and December 1, 1978 outlined the criteria being considered in the investigation of the alternate methods for safe shutdown not dependent on the test pump_.
- 8.
Insitu Smoke Tests As described in our letter dated June 5, 1978 and in accordance with the agreements reached with the NRC staff during the August 29, 1978 meeting, in-situ tests will be performed in areas where smoke detectors exist or will be installed. These tests will take into account the ventilation air flow patterns in the areas and will include the use of a suitable smoke generation device. Bench tests to ensure adequate sensitivity will also be performed on smoke detectors which exist or will be installed. The tests will be performed following the installation of the new smoke detectors (refer to Enclosure 1 of this letter) and appropriate modifications will be implemented if any fire detection systems are found to be inadequate.
- 9. Hydrogen Seal Oil Area Fire In accordance with the agreements reached with the NRC staff during the August 29, 1978 meeting, an evaluation will be performed to determine the potential for damaging the structural steel of the turbine building in the vicinity of the hydrogen sal oil unit should a fire occur in this area. The evaluation will also determine the potential for damaging safe shutdown equipment located within or near the turbine building should the structural steel in the vicinity of the hydrogen seal oil unit be damaged.
The evaluation will be performed assuming that the oil from the turbine lube oil system is feeding the fire and will be completed by February 15, 1979.
Mr. D.
January 11, 1979
- 10.
Schedule of Plant Modifications The summary implementation schedule included as Enclosure 1 to this letter, is consistent with the schedular information presented to the NRC staff during the meetings held on August 29, 1978 and September 15, 1978 in Bethesda, Maryland. All modifications, except those impacted by the Systematic Evaluation Program, are shown to be completed by the end of the outage for refueling for Cycle 8 operation.
Following completion of final engineering, as detailed quantities and construction unit rates become available, we will update the milestones in the implementation schedule and will advise you if the identified modifications cannot be accomplished prior to the end of the outage for refueling for Cycle 8 operation.
If you have any questions or desire additional information concerning the information discussed above, please contact me.
Very truly yours, Enclosure Schedule of Final Modifications Fire Protection Program Item Schedule
- 1. Fire Detection Systems Refueling Outage for Cycle 8 Operation (1) (2)
- 2. Fire Water Supply Refueling Outage for Cycle 8 Operation (1)
- 3. Yard Hydrants Refueling Outage for Cycle 8 Operation
- 4. Hose Stations Refueling Outage for Cycle 8 Operation
- 5. Water Suppression Systems Refueling Outage for Cycle 8 Operation (1)
- 6. Foam Suppression Systems Refueling Outage for Cycle 8 Operation
- 7. Gas Suppression Systems Refueling Outage for Cycle 8 Operation (1)
- 8. Portable Extinguishers Completed
- 9. Fire Doors Refueling Outage for Cycle 8 Operation (1)
- 10.
Supervision of Fire Doors 4/79
- 11.
Fire Barriers Refueling Outage for Cycle 8 Operation (1)
- 12.
Fire Dampers Impacted by Systematic Evaluation Program
- 13.
Fire Barrier Penetrations Refueling Outage for Cycle 8 Operation (1)
- 14.
Water Damage Protection Impacted by Systematic Evaluation Program
- 15.
Control of Combustibles Refueling Outage for Cycle 8 Operation (1)
- 16.
Isolation Devices Refueling Outage for Cycle 8 Operation
- 17.
Emergency Lighting Refueling Outage for Cycle 8 Operation Notes:
(1) Schedule completion dates are only applicable to those modifications identified as not impacted by future work (i.e., Systematic Evaluation Program).
Cate gorization of modifications (i.e., items not impacted by future work versus items impacted by future work) were presented to NRC staff during meeting held on August 29, 1978 and September 15, 1978.
(2) Modifications to be completed prior to the end of the outage for refueling for Cycle 8 operation currently scheduled to commence March, 1980.