ML19247B301
| ML19247B301 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 07/20/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Groce R YANKEE ATOMIC ELECTRIC CO. |
| References | |
| NUDOCS 7908080340 | |
| Download: ML19247B301 (4) | |
Text
TER/1 f ~s.
+
P, UNITED STATES E, ",-.
NUCLEAR REGULATORY COMMISSION g ' Tl.'h C
WASHINGTON, D. C. 20555 o
JULY 2 0 1979 Docket No. 50-271 Mr. Robert H. Groce Licensing Engineer Yankee Atomic Electric Company 20 Turnpike Road Westboro, Massachusetts 01581
Dear Mr. Groce:
RE:
VERv0NT YANKEE NUCLEAR POWER STA1 ION Ue are reviewing your submittals dated April 27 and May 4.1979, 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 enclosu e be forwarded to this office within two weeks of your receipt of t5e enclosure, which was previo2 sly transmitted to you by telecopy.
Pler.se contact William F. Kane at (301) 492-7745 if you require additional discussions or clarificat#on regarding the infor.mion requested.
Si ncerely, Ip 9polito, 9 h4 'f Thcmas A.
Operating Reactors Branch #3 Division of Operating Reactors
Enclosure:
Raouest for Additional Infomation cc w/ enclosure:
See next page d i) O 00 7908070 T
7 79080803Mh!
Mr. Robert H. Groce JULY 2 0 G79 Yankee Atenic Electric Company
-2 cc:
Ms. J. M. Abbey John R. Stanton, Director
.ermont Yankee Nuclear Power Radiation Control Agency Ccrocration Hazen Drive 77 Grove Street Concord, New Hampshire 03301 Outland Vermont 05701 John W. Stevens Mr. Donald E. Vandenburgh, Conservation Society of Vtce President Southern Vermont Vermont Yankee Nuclear Power P. O. Box 256 Corporation Townshend, Vermont 05353 Turnpike Road, Route 9 Westboro, Massachusetts 01581 Dr. Mars Longley, Director Division Occupational Health John A. Ritsher, Esquire 32 Spaulding Street Rooes & Gray Barre, Vermont 05641 225 Franklin Street Boston, Massachusetts 02110 New Endland Coalition on Nuclear Pollution Laurie Burt Hill and Dale Farm Assistant Attorney, General West Hill - Faraway Road Environmental Protection Division Putney, Vermont 05346 M.torney General's Office One Ashburton Place,19th Floor Public Service Board Boston Massachusetts 02108 State of Vermont 120 State Street Richard E. Ayres, Escuire Montpelier, Vermont 05602 Natural Resources Defense Counsel 917 15th Street, N. W.
W. F. Conway, Plant Superintendent Washington, D. C.
20005 Verment Yankee Nuclear Pcwer Corporation Honorable M. Jerome Diamond P. O. Box 157 Attorney General Vernon, Vermont 05354 State of Vermont 109 State Street Mr. Charles Sheketoff Pavilion Office Building Assistant Director Montpelier, Vermont 05602 Vermont Public Interest Research Group, Inc.
Anthony Z. Roisman 26 State Street Natural Resources Defense Council Montpelier, Vermont 05602 917 15th Street, N. W.
Washington, D. C.
20005 Brooks Memorial Library 224 Main Street Brattleboro, Ver ont 05301 1}O G G {}
Enclosure VERMONT YANKEE REDUESTS FOR ADDITIONAL INFORMATION IE3 79-08 Item No. 2 1.
Your response indicates that containment isolation of the recirculation loco sample line, main steam line drain lines and reactor cleanup system does not comply with the requirements of IE3 79-08. This is because con-tainment isolation of these lines is not initiated on al? automatic inita-tions of safety injection, i.e., containment isolation of these lines is initiated on low-low sater level but not on high drywell pressure.
Please provide justification for not isolating these lines or prepare and implement the necessary changes to isolate these lines as required by the Sulletin.
Provide a schedule for completion of the necessary design and/or procedural changes to comply with the requirements of IES 79-03.
Item No. 4 1.
Your response is incomplete.
Describe all uses and types of vessel level indication for t'oth manual and automatic initiation of safety systems.
2.
Describe other instrumentation which the operator night have to determine changes in reactor coolant inventory, e.g., drywell hign pressure, radio-activity levels, suppression pool high temperature, containment sumo pump operation, etc.
3.
Clarify your response to indicate whether operators have been instructed to utilize other available information to initiate safety systems.
Provide your schedule for completion of this action.
Item No. 5 1.
It is not clear from your response whether your review of procedures, with respect to the actions directed by items 5a and 5b, included all operating procedures and training instructicns. Amend your response to clarify this point.
2.
It is not clear from your response whether your review of operating procedures and training instructions,with respect to the actions directed by item 5b, included additional information and instructions to operators to not rely on vessel level indication alone for manual actions but to also examine other plant parameter indications in evaluating olant con-ditions. Amend your response to clarify this point.
3.
Provide a schedule for any actions on item 5 that have not yet been completed.
[}()()
Ob
VERMONT YANKEE Item No. 6 1.
It is not clear from your response that safety-related valve positioning requirements were reviewed to ensure proper operation of engineered safety features. Please supplement your response to provice a commitment to conduct 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 indicated that refinements to valve line-up procedures are being made and a procedure prescribing instrumentation rack valve line-ups is being developed. Please provide a schedule for the completion of these activities.
4.
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.
Item No. 7 1.
Verify that the systers listed in part b of your response include all those systems designed to transfer potentially radioactive gases and liquids out of containment.
2.
Item No. 7 of IES 79-08 requires assurance that inadvertent transfer of radioactive gases and liquias be prevented on resetting engineered safety features instrumentation.
In your response you stated that apprcpriate procedural precautions are used.
Discuss these precautions further and indicate how they are used to prevent inadvertent transfer on reset.
If sucn precautions are not yet available, provide the schedule for their completion.
Item No. S 1.
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.
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.
Item No. 9 1.
Provide the date on which you completed the actions required by item 9 of IE3 79-OS.
n0"
, (10 0 0
i ) i