ML19247B285
| ML19247B285 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 07/20/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Andognini G BOSTON EDISON CO. |
| References | |
| NUDOCS 7908080303 | |
| Download: ML19247B285 (4) | |
Text
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JULY 9 0 1979 Docket No. 50-293 Mr. G. Carl Andognini M/C NUCLEAR Boston Edison Company 800 Boylston Street Boston, Massachusetts 02199 Dear Mr. Andognini RE: PILGRIM NUCLEAR POWER STATION We a' e reviewing your submittal dated April 25, 1979 in response to IE B illetin 79-08. We have detemined that the additional infomation requ2sted in the enclosure is necessary in order to cmplete 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 previcusly 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.
Sincerel Thomas A. Ip hie Operating Reactors Branc #3 Division of Operating Reactors Encl osure:
Request for Additional Informa ticn cc w/ enclosure:
See next page 7908080'p3 500 3'14 e=
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Mr. G. Car 1 Andognini ' JLY 2 0 7379 J'
CC Mr. Paul J. McGuire Pilgrim Station Acting Manager Boston Edison Company "I
el, Rocky 'ill Road Plymouth, Massachusetts 02360 Anthony Z. Roisman Naturai hesources Cefense Council 91715th Street, N. W.
' 'a s P i r.g te n, D. C.
20005 Hanry Herrmann, Esquire Massachusetts Wildlife Federation lEl 'remont Street Boston, Massachusetts 02111 Plymouth Public Library North Street Flpouth, Massac:1usetts 02360 N
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ENCLOSURE PILGRIf1 1 REQUEST FOR ADDITICUAL INFORMATION IEB 79-08 Item No. 1 Provide the date on which you completed the actions required by item 1 of IEB 79-08.
Item No. 2 1.
Your response iridicated that procedures would be develooed to isolt !e the residual Heat Removal to Spent Fuel Pool Demineralizer line and the Toru: Makeup line in the event either was in service on receipt of a containment isolation signal.
Provide your schedule for completion of.his action.
2.
The Main Steam Drain lines and Reactor Water Sample lines are not isolated on high drywell pressure.
Is'lation of these lines on high drywell pressure would not appe?r to result in Jegradation of needed safety features or cooling capability. Therefore provide justification for not isolating these lines or prepare and implement the necessary changes to isolate tbaca lines as required by the Bulletin.
Item No. 4 1.
Describe other redundant instrumentation which the operator might have to determine changes in reactor coolant inventory, e.g., drywell high pressure, radioactivity levels, suppression pool high temperature, containment sumo pump operation, etc.
2.
Clarify your response to indica'te whether operators have been instructed to utilize other available information to initiate safety systei..s.
Provide your schedule for completion of this action.
Item No. 5 1.
Verify that the redundant and diverse instrumentation referred to in your response to item 5b includes instrumentation other than water level instru-mentatior., e.g., drywell high pressure, drywell high radioactivity levels, suppression pool high temperature, etc.
2.
Provide a schedule for any actions on item ; that have not yet been completed.
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_2-Item No. 6 1.
It is not clear from your respotse that safety elated valve positioning requirements were reviewed to ensure proper operation of engineered safety features.
Please supplement your response to provide a commitment to conduct this review and a schedule for completion.
2.
Your response did not clearly indicate that all accessible safety-related valves had been inspected to verify proper Dosition.
Nor was a schedule for performing the position verification for all safety-related valves provided.
Please supplement your response to provide this information.
Item No. 7 1.
Your response regarding inadvertent transfer of radioactive liquids by operation of the containment sume cump on resetting engineered safcty features instrumentation is unclear. Verify that your prcsent procedures require the switch for the sump isolation valves be taken out of the
" auto" position prior to reset in order tr. prevent inadvertent transfer of radioactive liquids out of containment.
In addition provide your schedule for removing the " auto" function trom the switch.
I t s, Ib. 8 We understand from your response that operability tests are performed on redundant safety-related systems prior to removal of any safety-related system from service.
cince 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.
Item No. 9 Your response is unclear as to the extent of commitment to the requirements of item 9 of IEB 79-08.
We require a rewc-ding of your rcsponse to ensure an explicit comni urent to the requirements of item 9 of IEB 79-C8.
Iten No. 10 You stated in your response that you have reviawed only one procedure in connec-tion with this item.
Please orovide a summary description of the operating modes and procedures wh::h you reviewed for adequacy to deal with significant amounts of hydrogen for both transient and accident conditions.
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