ML19247B295
| ML19247B295 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/20/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Berry G POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| References | |
| NUDOCS 7908080329 | |
| Download: ML19247B295 (4) | |
Text
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j NUCLEAR REGULATORY COMMISSION
,o, UNITED STATES 74 y
WASHINGTON, D C. 20555 f
JULY 2 0 1979 Decket No. 50-333 Mr. George T. Berry General Manager and Chief Engineer Power Authority of the State of New York 10 Columbus Circle New York, New York 10019 09ar Mr. Berry:
RE: JAMES A. FITZPATRICK NUCLEAR POWER PLANT We are reviewing your su5mittal dated April 25, 1979 in response to IE Bulletin 79-08. We have detemined that the additional infomation requested in the enclosure is necessary in order to complete our 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.
Si ncerel v, Thomas A. Ippolit, C ief Operating Reactors Branch #3 Division of Operating Reactors
Enclosure:
Request for Additional Infomation
- a/ enclosure:
See rext page f)()
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Mr. George T. Berry Pcwer Authority of the State
' JULY 20579 ef New York 2_
cc:
"ito J. Cassan Assistant General Counsel Power Authority of the State of New York 10 Col umbus Circle New York, New York 10019 Mr. Peter W. Lyon Managcr - Nuclear Operations Punet Authority of the State rf New York 10 Columbus Circle Nc.4 York, New York 10019 J. L. Leonard, Jr.
.....;en-Manager James A. FitzPatrick Nuclear Power Plant P. O. Box 41 tyuusirig, New York 13093 Director, Techr ical Developmer,t Prog rams State of New York Energy Offict Agency Building 2 E Oire State Plaza Albany, New York 12223 Oswego County Office Building 46 E. Bridge Street Oswego, New York 13126 George M. Wilverding, Licensing Supervisor Power Authority of the State of New York 10 Columbus Circle Naw York, New York 10019
Enclosure FITZPATRICK REQUESTS FOR ADDITIONAL INFORMATION IEB 79-08 Item No. 1 1.
Confirm that all licensed operators, plant management and supervisors with operational responsibilities have completed the review of TMI-2 events as required by item 1 of IEB 79-08 and that their participation has been documented in plant records.
Item No. 2 1.
Your response is incomplete in that it does not indicate that you haJe reviewed procedures to assure initintion of containment isolation is in conformance with Item 2 of IEB 79-u3.
Verify that you have reviewed the required procedures or provide the schedule for completion of that review.
Item No. 4 1.
DescH be other instrumentation which the operator mi ht have to determine changes in reactor coolant inventory, e.g., drywell high pressure, radioactivity levels, suppression pool high temperature, containment sump operation, etc.
2.
Clarify your response to indicate whether operators have been instructed to utilize other available informatica to initiate safety systems. Pro-vide your schedule for completion of this action.
Item No. 5 1.
Your response to items 5a and 5b does not address training instructions.
Amend your response to address this matter.
2.
Your response to item Sa does not address the matter of unsafe plant conditions. Amend your response to address this matter.
3.
It is not clear from your response whether your review of pracedures with respect.to the actions directed by item Eb included dll apolicable operating procedures and training instructions.
Amend your response to clarity this point.
4.
Provide a schedule for any actions on item 5 that have not been compl M:ad.
419 25I
FliZPATRICK Iten No. 6 1.
Please augment your response to indicate the extent to which position and locking device checks are performed for lecked safety system valves; i.e., clari fy monthly surveillance of "certain critical valves".
2.
It is not clear from your response that positive administrative controls have been implemented to assure that systems requiring retest are in fact retested prior to the need for their operability.
Please clarify your response to provide assurance that safety related valves are returned to their correct positions following necessary manipulations.
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 su,,plement your response to provide this information.
Item No. 7 1.
Provide your schedule for nodification of procedures to prevent inadvertent transfer of radioactive liquids through the Reactor Coolant Sample Line on resetting of engineered safety features instrumentation.
Item No. 8 1.
We understand from your response that operability tests are perforned on redunaant safety related systems prior to removal of any scfety 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 supple-ment 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 311 involved reactor operationai 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.
Your response is unacceptable.
NRC notification is required whenever "the reactor is not in a controlled or expected condition of operation".
Serious accidents may not be the only events which warrant notification.
Further, you must commit to notification within one hour and to the establishment of an open continuous communications channel.
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