ML20030A811
| ML20030A811 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 07/10/1981 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | VERMONT YANKEE NUCLEAR POWER CORP. |
| Shared Package | |
| ML20030A812 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM NUDOCS 8107290061 | |
| Download: ML20030A811 (10) | |
Text
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3g0 "01 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
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Docket No. 50-271
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VERMONT YANKEE NUCLEAR POWER
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CORPORATION
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(Vermont Yankee Nuclear Power Plant) )
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ORDER CONFIRMING LICENSEE COMMITMENTS ON POST-TMI RELATED ISSUES The Vermont Yankee Nuclear Power Corporation (the licensee) is the holder of Facility Operating License No. DPR-28, which authorizes the operation of the Vermont Yankee Nuclear Power Plant (the facility) at steady-state reactor power levels not in excess of 1593 megawatts thermal. The facility is a boiling water reactor located at the licensee's site in Windham County, Ve rmont.
II.
Folicwing the accident at Three Mile Island Unit No. 2 (TMI-2) on March 28, 1979, the Nuclear Regulatory Commission (NRC) staff developed a number of proposed requirenents to be implemented on operating reactors and on plants
~ under constructicn. These requirements include Operational Safety, Siting and Design, and Energency Preparedness and are intended to provide substantial additional protection for the operation of nuclear facilities 4
6107290061 810710 DR ADOCK 050002fg
, 7590-01 based on experience from the accident at TMI-2 and the official studies and investigations of the accident. The staff's proposed requirements and schedule for implementation are set forth in NUREG-0737, " Clarification of TMI Action Plan Requirements." Among tnese requirements are a number 'of items, con-sisting of' hardware modifications, administrative procedure implementation and specific information to be submitted by the licensee, scheduled to be completed on or before June 30,1981 (see the Attachment to this Order).
NUREG-0737 was transmitted to each licensee and applicant by an NRC letter from my office dated October 31, 1980, which is hereby incorporated by reference.
In that letter, it was indicated that although the NRC staff expected each requiremant to be implemented in accordance with the schedule set forth in NUREG-0737, the staff would consider licensee requests for relief from staff proposed requirements and their associated implementa-tion dates.
III.
The licensee's submittals dated December 15 and 30,1980, January 13, March 10 and 31, April 3 and 17,1981 and the references stated therein, which are in-corporated herein by reference, committed to complete each of the actions specified in the Attachment. The licensee's submittals included a modified schedule for submittal of certain information. The staff has reviewed the licensee's submittal and determined that the licensee's modified schedule i s acceptable based on the following:
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Tre licensee's schedule for submittal of information in scme instances does not meet the staff's specified submittal dates. Most of the information requested by the staff describes how the licensee is meeting the-guidance of'NUREG-0737. Therefore, this deferral of the licensee submittal will not alter the implementation of plant modifications. Therefore, plant safety is_ not affected by this modification in schedule for the submittal of. information.
I have determined that these ccmmitments are required in the interest of public health and safety, and therefore, should be confirmed by ORDER.
IV.
Accordingly, pursuant to Sections 103,1611,1610, and 182 of the Atomic Energy Act of 1954, as amended, and the Commission's regulations in 10 CFR Parts 2 and 50, IT IS HERI.SY ORDERED EFFECTIVE IMMEDIATELY THAT i
the licensee shall comply with -the following conditions:
The licensee shall satisfy the specific requirements described in the Attachment to this Order (as appropriate to the i
licensee's facility) as early as practicable but no later I
than 30 days after the effective date of the ORDER.
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. 7590-01 i
V.
Any person who has an interest affected by this Order may regrest a hearing w' thin 20 days of the date of publication of this Order in the Federal Register. Any request for a hearing shall be addressed to the
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Director, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555. A copy shall also be sent to the Executive Legal Director at the same address.
If a hearing is requested by a person other than-the licensee, that person shall describe, in accordance with 10 CFR 2.714(a)(2), the nature of the person's ir.terest and the manner in which the interest is affected by this Order. A REQ' JEST FOR HEARING SHALL NOT STAY THE IMMEDIATE EFFECTIVENESS OF THIS ORDER.
If a hearing is requested-by the licensee or other persons who have an interest affected by this Order, the Commission will issue an Order
. designating the time and place of any such hearing.
If a hearing is held concerning this Order, the issue to be considered at the hearing shall be whether, on the basis of the information set forth in Sections II and III of this Order, the licensee should comply with the conditions set forth in Section IV of this Order.
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, 7590-01 This request for information was approved by OMB under clearance number 3150-0065 which expires June 30, 1983. Comments on burden and duplication may. be directed to the Office of Management and Budget, Reports Management, Room 3208, New Executive Office Building, Washington, D. C.
.This Order is effective upon issuance.
TOR THE NUCLEAR REGULATORY COMMISSION i
I 4 g pG. Eisenhut,t ecc Carre 1 rector Division of Licensing Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland this 10 day of July 1981
Attachment:
'NUREG-0737 Requirements Lh
([:
ATTACHMENT NUREG 0737 REQUIREMENTS Imol/Occ Item Title Acolicability Soecific'Recuirement Subr Due Dates I. A. l.1
.STA
'ALL (a) Provide STA coverage by 1/1/S1 degreed.
individual s
-(or equivalent), trained to licensee's program.
-(b) Submit' description of 1/1/31 current training procram -
anc demons trate compliance.
with'10-30-79 letter.
(c) Submit description of long
_1/1/81 term training program.
I.'.~.1 Reactor 0:erator ALL Submit descriotion of and imple-sel >3c-
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Qualification ment Upgraded Training Program.
I.C.1
. Accident Procedures ALL (a) Submit reanalyses of inade'-
1/1/81 cuate core cooling and propose guidelines for emergency procedures, OR procose schedule and justify delays.
(b) Submit reanalysis of 1/1/31-transients and accidents for emergency procedures, OR propose-schedule and ' justify delays.
I.C.5-Feedback of ALL-Implement rocedures for 1/1/81 Operating Experience feedback of_ operating experience (no documentation subrittal is required).
1.C.6 Correct Performance ALL Implement crocedures to verify 1/1/81
-or Operating Activities correct performance of coerating activities-(nc dccumentation submittal is required).
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Impl/Occ Item T1:1e Ao pl 4c a bil_i_ty, S_pecific Recairement Subm Due Dates II.B.2 Snielding ALL
'(a) Have available design 1/1/81 details for vital area modifications.
(b) Submit technical 1/1/81 deviations to staff positions.
II.B.3 Post-Accident ALL Submit description 1/1/81 Samoling of deviations from staff positions.
II.S.
Training to ALL (a) Have available for 1/1/81 Mitigate Core review a training
. Damage program for mitigating.
core damage (no documen-tation submittal required)
(b) Implement training 4/1/81 program (no documenta:fon submittal required).
II.D.1 Fer'ormance ALL (a) Submi: test program 7/1/80 (PWRs Testing of (both BWR/FWR's).
10/1/80 (BWRs)
RV/SRV's (b) Submit qualification program for PWR's block valve.
1/1/31 (PWRs)
II.E.1.2 Aux Feed PWRs (a) Submit final design and I/1/81 Initiation documentation on safety-and Flow grade flow indication.
(b) Submit final design and 1/1/81 documentation on safety grade flow initiation.
II.E.4.2 Containment ALL (a) Submit documentation 1/1/81 Isolation justifying minimum contain -
ment pressure setpoint for isolation of non-essential penetrations.
(b) Submit statemen: that 1/1/81 purge valves not meetine CSS 6 c. (or interim pos'i-tion)are sealed and verifi-cation is perfomed every 31 days.
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Item Titl_e Apolicability Soecific Recuirement Summ Due Dates II.F.1 Dost *ccident -
ALL a.
For noble gas monitor 1/1/81 Monitoring and. Iodine /carticulate sampling and analysis submit description and justification for deviations from staff requirements.
b.
Have available the 1/1/81 final design infor-mation for noble gas monitor and iodine /
particulate sampling and analysis.
II.F.2 Inst. for Inadequate ALL Submit a report oe: ailing the 1/1/81 Core Cooling planned instrumentation systen for monitoring inadequate core cooling.
II. K. 2.10 Antic. Trip on B&W Submit final design for 1/1/81 LCFW and TT anticipatory trio as described in N'JPSG 0737.
II.K.2.l?
Tner al Mechanical B&W Submit recort on effects 1/1/81 Repor:
' of Hi Pressure Injection on vessel integrity for SB LOCA with no Aux Feedwater.
II.K.3.2 PORV/SV.r 4ures PWR Submit report on 55 LOCA-1/1/S1 e
and probability of failure of PORV/SV/RV.
II.K.3.3 SRV/SV Failures ALL Submi: report (historical 1/1/S1
& Challenges and annually thereafter) of SRV/SV failures and challenges.
II.K.3.7 PORV Opening B&W Submit recor:~ on :ne 1/1/81 Probabil ity probability of a :0RV opening during an over-pressurization transient.
II.K.3.9 PID Controller Selected W-Modify the Proportional 12/1/80 Modi fica tion plants Integral Derivative Centro 11er (as recoc. ended by ' ). Advise f
NRC wnen modification is completed.
i I!.K.3.12 Anticipatory Trip W
Submit confirmation of 1/1/Si on Turbine Trip Anticipatory Trip.
If not currently imolemented, submit modification design and senedule for implementatiort.
4 Impl/Dec Item.
Titie Acolicability Specific Recuirerent Sub Dans II.K.3.13 Separation of BWF.s w/H?CI/RCIC Submit results of 1/1 /81 HFCI/RCIC evalcation and proposed Initiation Levels; modification as appropriate.
Auto Restart of RCIC II.K.3.16 Reduce Challenges BWR Submit report en actions 4/1/S1 to RV's planned to redu:e RV challenges.
II.K.3.17 ECCS System Outages ALL Submit report on ECCS 1/1 /51 outages and prop se changes to redu:e outages.
II.K.3.15 ACS Logie BWR Submit report of feasibility 4/1 /51 Modifications of ADS system logic changes to eliminate need for manual actuation.
C I. K. 3. 21 C55/CPCI Restart EWR Submit report of evaluatien, 1 /1 /51 proposed modift:ations and analysis :( satisfy staff positions.
I~.K.3.22 RCIC Su: tion SWR w/RCIC I=plement proce:ures and 1/1 /51 document verifi:ation cf this change.
II.K.3.27 C:==:n Reference SWR Implement change and su.ti:
1/1 / 51 fer M 0 Level Instruments docunentation cf changes.
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.II.K.3.29 Is:1ation SWR w/ICs Sub-J: evaluation cf I.C.
4/1/51 Conder.sor perfo rmanc e.
Perfo rma nce II f.3.30 55 LCCA Methods ALL Submit outline Of progra 11/15/30 for model.
!!.K.3.44 Fuel Failure BWR Submit evaluatten to verify
'. /1/ 51 no fuel failure.
II.K.3.45 Manual Depressur-BWR Submit evaluati n on other 1/1 / 51 i:ation than ACS method for depressuri:stien.
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. D,:3 Applicability.
5:ecific Requirement Suy,m Oue Dates II:.D.3.3-Impresed Inplant-ALL Have available means to 1/1/31 Iodine Monitoring accurately measure airborne--
radioiodine inplant during; an. accident. -
'II.D.3.4 Control Room Habitability ALL a.
Submit control room 1/1/81 habitability evaluation in fonna tion.
b.
Submit modifications 1/1/81~
necessary to assure CR habi tabili ty.with a schedule for completion.
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