ML19247B299
| ML19247B299 | |
| Person / Time | |
|---|---|
| Site: | Humboldt Bay |
| Issue date: | 07/20/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Morrissey J PACIFIC GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7908080336 | |
| Download: ML19247B299 (4) | |
Text
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JULY 2 0 1973 Decket No. 50-133
.'?. Jchn C. Morrissey Vica President and General Counsel Pacific Gas and Electric Company 77 Beale Street San Francisco, California 94106
Dear Mr. Morrissey:
nu HUMBOLDT BAY NUCLEAR POWER PLANT We are reviewing your submittal dated May 1,1979 in response to IE Bulletin 79-08.
We have detemined that the additional infomation requested in the enclosure is necessary in order to caiplete cur safety evaluation.
We request that responses to the items in the enclosure be forwarded to this office within two weeks of your receipt of the enclosure, which was previously transmitted to you by telecopy.
Please contact William F. Kane at (301) 492-7745 if you require additional discussions or clarification regarding the infomation requested.
Sincerely, Thomas A. Ippolito, C 'ef Operating Reactors Branch 3 Division of Operating Reactors
Enclosure:
Request for Additional Infomation cc w/ enclosure:
Cae next page
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Mr. John C. Morrissey JULY 2 0 1979 Pacific Gas & Electric Company cc:
Philip A. Crane, Jr.
Sist Floor Pacific Gas and Electric Company 77 Beale Street San Francisco, California 94106 Mr. James Hanchett
?ublic Information Officer Regicn V - IE U. S. Nuclear Regulatory Commission 1990 N. California Boulevard
'n'ainut Creek, California 94596 Humboldt Cour ty Library 636 F Street Eureka, California 95501 David E. Pesonen, Esquire Garry, Dryfus, McTernan, Brotsky, Herdon & Pesonen, Inc.
12So Market Street San Francisco, California 94102 Linda J. Brown, Esquire
.Dononew, Jones, Brown & Clifford 100 Van Ness Avenue, 19th Floor San Francisco, California 94102 Dr. Perry Aminoto Department of Conservation Division of Mines & Geology 1416 9th Street, Room 1341 Sacramento, California 95814 f, j t uUU j
Enclosure HUMBOLDT BAY REQUESTS FOR ADDITIONAL INFORMATION IEB 79-03 Item No. 2 1.
Your response is incomplete in that it does not indicate that you have reviewed all applicable procedures to assure that containment isolation initiation is in conformance with Item No. 2 of IES 79-03.
Verify that you have reviewed all applicable procedures and confirm that containment isolation of all lines (including those designed to transfer radioactive liquids and gases) is initiated on all automatic initiations of safety injection.
2.
State whether you have prepared and implemented procedures required for manual isolation of closed cooling water lines to the drywell air coolers.
3.
Provide a schedule for any action on Item No. 2 that has not yet been completed.
Item No. 4 1.
Your response is incomplete.
Describe all uses and types of vessel level indication for both automatic and manual initiation of safety systems.
2.
Describe other instrumentation which the operator might have to determine changes in reactor coolant inventory, e.g., radioactivity levels, contain-ment high temperature, containment sump pump operation, etc.
Item No. 5 l.
Provide a schedule for any actions on item 5 that have not yet been completed.
Item No. 6 1.
It is not clear f om your response that safety-related valve positioning requirements wer; reviewed to ensure proper operatior of engineered safety features. Please supplement your response to provide a commitment to concutt this review and a schedule for completion.
2.
Please augment your response to indicate the extent to which position and locking device checks are performed for locked safety system valves.
3.
Your response did not clearly indicate that all accessible safety-related valves had been inspected to verify proper position.
Nor was a schedule for performing the position verification for all safety-related valves provided.
Please supplement your response to provide this information.
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-HUMBOLDT BAY Item No. 7 1.
Provide a complete list of systems designed to transfer radioactive gases or liquids outside of containment and indicate whether these systems are isolated by the containment isolation signal.
2.
Provide assurance that resetting of engineered safety features instrumentation will not result in inadvertent transfer of radioactive gases and liquids outside of containment.
3.
Discuss the basis upon which continued operability is assured of the features designed to prevent inadvertent transfer of radioactive gases and liquias outs'de of containment.
d.
Provide a schedule for completion of the study regarding an alternate vent path for the emergency condenser and for implementation of any system modifi-cations resulting from that study. Confirm that these actions will comply with the requirements of Item No. 7 of IEB 79-08.
Item No. 3 1.
We understand from your response that operability is verified for redundant safety-related systems prior to removal of any safety-related system from service. Since you may be relying on prior operability verification within the current technical specification surveillance interval, operability should be further verified by at least a visual check of the system status to the extent practicable, prior to removing the redundant equipment from service.
Please supplement your response to provide a commitment that you will revise your maintenance and test procedures to adopt this position.
2.
It is not clear from your response that all involved reactor uperational personnel in the oncoming shift are explicitly notified about the status of systems removed from or returned to service.
Please indicate how this information is transferred at shift turnover.
Item No. 9 1.
Provide assurance that your procedures stipulate NRC notification any time the reactor is not in a controlled or expected condition of operation.
In adcition, provide the schedule for completion of these procedural revisions.
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