ML20009C965
| ML20009C965 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/10/1981 |
| From: | Purple R Office of Nuclear Reactor Regulation |
| To: | WISCONSIN ELECTRIC POWER CO. |
| Shared Package | |
| ML20009C962 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM NUDOCS 8107220249 | |
| Download: ML20009C965 (10) | |
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UNITED STATES OF AMERICA 7590-61 l
NUCLEAR REGULATORY COMMISSION j
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In the Matter of
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Docket Nos. 50-266
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and 50-301 WISCONSIN ELECTRIC POWER COMPANY
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_ (Point Beach Nuclear Plant-
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Units 1 and 2).
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ORDER CONFIRMING LICENSEE COMMITMENTS ON POST-TMI RELATED ISSUES I.
Wisconsin Electric Power Company (the licensee) is the holder of Facility Operating License Nos. DPR-24 and DPR-27 which authorize the operation of the Point Beach Nuclear Plants Units 1 and 2-(the facilities) at steady-state power levels not in excess of 1518 megawatts thermal. The facilities are pressurized water reactors (PERs) located at the licensee's site in Manitowoc County, Wisconsin.
II.
Following the accident at Three Mile Island Unit No. '. (TMI-2) on March 28, 1979, the Nuclear Regulatory Commission (NRC) staff developed a number of proposed requirements to be implemented on operating reactors and on plants under construction. These requirements include Operational Safety, Siting and Design, and Emergency Preparedness and are intended to provide substantial additional protection in the operation of nuclear facilities based on the k[$$$bo P
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experience from -the accident at TMI-2 and the official studies and investigations of the acci<!;nt. T'ie staff's proposed requirements and schedule for implenentation are set forth in NUREG-0737, " Clarification of TM: Action. Plan Requirements." Among these requirements are a
- number of items, consisting 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 licenses' and applicant by-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 requirement to be implemented in accordance with the schedule set forth in NUREG-0737, the* staff would cor. sider licensee requests for relief from staff proposed requirements and their associated implementation dates.
III.
The licensee's submittals dated December 23, 1980, January 19, 1981, March 4, 1981, March 31, and July 6,1981, 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 I
i licensee's 'submittals and determined that the licensee's modified schedule is acceptable based on the following:
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. The licensee'.s schedule for submittal of information in some 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 commitments are required in the interest of public health and safety, and therefore, should be confirmed by ORDER.
IV.
Accordingly, pursuant to Sections 103,1611,161o, 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.HEREBY ORDERED EFFECTIVE IMMEDIATELY THAT the licensee shall comply with the following conditions:
The licensee shall satisfy the specific requirements described in the Attachment to this Order (as apprcpriate to the Itcensee's facility) as early as practicable but no later than 60 days after the effective date of the ORDER.
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-I 7590-01 4-Y.
~ Any person who has an interest affected by this Order may request a
-hearing within 20 days of the date of publication of this Order in the Federal Register. Any request for a hearing shall be addressed to the Director, Office of Nuclear Reactor Regulatiot., 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 cf the person's interest
- and the manner in which the interest is affected by this Order. A REQUEST
- 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 l
forth in Sections II and III of this Order, the licensee should comply l
with the condition.e set forth in Section IV of this Order.
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7590-01 5-h I
l 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 issuar.ce.
FOR THE NUCLEAR REGULATORY COMMISSION A
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Robert A. Purple, Deputy Director Division of Licensing Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland this 10thday of-July
- 1981
Attachment:
NUREG-0737 Requirements l
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ATTACHh NT NUREG 0737 REQUIREMENTS Impl/ Doc Item
-Title Applicability Specific Requirement Subm Due Dates
- I. A.l.1 STA' ALL (a) Provide STA coverage by 1/1/81 degreed individuals (or. equivalent), trained to licensee's program.
-(b) Submit description of 1/1/81 current training orogram and demonstrata compliance with 10-30-79 letter.
(c) Submit description of-long 1/1/81 term training program.
f.A.:.1
- Reactor Operator ALL Submit description of and imple-8/1/r,C l
-Qualification ment Upgraded Training Program.
- I.C.1 Accident Procedures
.ALL (a) Submit reanalyses of inade-1/1/81 quate core cooling and propose guidelines for
. emergency procedures. OR propose schedule and justify oelays.
(b) Submit reanalysis of 1/1/81 transients and' accidents for emergency procedures, OR propose schedule and justify delays.
I.C.5 Feedback of ALL Implement procedures for 1/1/81 Operating Experience feedback of operating experience (no documentation subrittal is required).
I.C.6 Correct Performance.
ALL Implemant procedures to verify 1/1/81 or' Operating Activities correct performance of operating activities (no documentation submittal is required).
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Impl/Occ Item Title _,
Aopl4cability Specific Requirement Sabm Due Dates II.B.2 Shielding ALL' (a) Have available design 1/1/81 details for vital area modifications.
(b) Submit technical 1/1/81 deviations to staff positions.
LII.S.3
' Post-Accident ALL-Submit description 1/1/81
. Samol ing of deviations from staff positions.
II.B.4' Training to ALL (a) Have available for 1/1/81 flitigate Core review a training Damage program for mitigating core damage (no documen-tation submittal required)
(b) Implement training 4/1/81 program (no documentation submittal required).
II.D.I.
Performance ALL (a) Submit test program 7/1/80 (PWRs)
. Testing of (both BWR/PWR's).
10/1/80 (BWRs)
RV/SRV's (b) Submit qualification program for PWR's block valve.
1/1/S1 (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) Subnit final design and 1/1/81 documentation on safety grade flow initiation.
58.E.4.2 Containment ALL (a) Submit documentation 1 /1 / 31 Isolation J.dtifying minimum contain-ns.nt pressure setpoint for isolation of non-essential penetrations.
(b) Submit statement that 1/1/81 purge valves not meetinq CSB 6-4 (or interim post-tion)are seale.d and verifi-cation is performed every 31 days.
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Impl/Occ Item Title _
Applicaoility Specific Requirement Sgm Due Dates
.II.F.I
. Post-Accident
.ALL a.
For noble gas monitor 1/1/81 Monitoring and Iodine / particulate sampling and analysis.
submit description and justification for deviations from staff requirements.
b.
Have available the 1/U81 final design infor-mation for noble gas monitor and iodine /
particulate sampling and analysis.
II.F.2.
Inst, for Inadequate ALL-Submit a report detailing the 1/1/81 Core Cooling planned instrumentation systeri for monitoring inadequate core cooling.
-II.K.2.10 Antic. Trip on B&W Submit final design for 1/1/81 LOFW and TT-anticipatory trip as described in NUREG 0737.
. II; K. 2.13 Thermal Mechanical B&W Submit report on effects 1/1/81 Report of Hi Pressure Injection on vessel integrity for SB LOCA with no Aux Feedwater.
II.K.3.2 P0HV/SV Failures PWR Submit report on i LOCA 1/1/S1 anc; probability of failure of PORV/SV/RV.
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'II.K.313 SRV/SV Failures ALL Submit report (historical 1/1/81
'& Challenges and annually thereafter) of SRV/SV failures and challenges.
II.K.3.7 PORV Opening B&W Submit report on the 1/1/81 Probability probability of a PORV opening during an over-pressurization transient.
?I.K.3.9 PID Controller Selected W Modify the Proportional 12/1/80 Modification' plants Integral Derivative Controller (as recommended by W).
Advise NRC when modification is completed.
Submit c:nfirmation of 1/1/81 II. K. 3.12 Anticipatory Trip W-Anticipatory Trip.
If not on Turbine Trip currently implemented, submit modification design and schedule for implementation.
Impl/ Doc Item-Title Aeolicability Specific-Reouirement Subm Dans II.K.3.13 Separation of BWRs w/HPCI/RCIL Submit results of 1/1/B1 HPCI/RCIC evaluation and proposed
. Initiation Levels; nodification as appropriate.
Auto Restart of RCIC II. K. 3.16 _
Reduce Challenges BWR Sub it report on actions 4/1 /81
'to RV's planned to reduce RV challenges.
II.K.3.17 ECCS System Outages.
ALL Submit report on ECCS 1/1 /81 outages and propose changes to reduce outages.
II.K.3.18 ADS Logic BWR Submit report of feasibility 4/1 /81 Modifications of ADS system logic changes to eliminate need for manual actuation.
- II. K. 3. 21 -
CSS /CPCI Restart BWR Submit report of evaluation, 1/1 /81 propo".d modifications and anal is t6 satisfy staff positions.
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If.K.3.22 RCIC Suction BWR w/RCIC-Icplement procedures and 1/1 /81 document verification of this change.
- II.K.3.27 C
- m=on Reference BWR Implement change and submit 1/1/81 for H O Level Instruments documentation of changes.
2 II.K.3.29
' Isolation SWR w/ICs Submit evaluation of I.C.
4/1 / 81 Condensor performance.
' Performance II.K.3.30 55 LOCA Methods ALL Submit outline of program 11/15/80 for model.
II.K.3.a4 Fuel Failure BWR Submit evaluation to verify 1/1/81 no fuel failure.
'II.K.3.45 Manual Depressur-BWR Submit evaluation on other
- 1/1/81 ization than ADS method. for depressuri:ation.
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Title Applicability Specific Requirement So,bm Due Dates III.O.3.3 Impreved Inplant ALL-Have available means to 1/1/81 Iodine Monitoring.
accurately measure airborne radiofodine inplant during 4
an accident.
-1I I ~. D. 3.4 Control Room Habitability ALL '
a.
Submit control room 1/1/81 habitability evaluation in formation.
b.
Submit modifications 1/1/81 necessary to assure CR habitability with a schedule for ampletion.
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