ML20009C944
| ML20009C944 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/10/1981 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | ARKANSAS POWER & LIGHT CO. |
| Shared Package | |
| ML20009C945 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM NUDOCS 8107220206 | |
| Download: ML20009C944 (10) | |
Text
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o 7590-01 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
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In the Matter of
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Docket No. 50-368
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ARKANSAS POWER & LIGHT COMPANY
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(Arkansas Nuclear One, Unit No. 2)
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ORDER CONFIRMING LICENSEE COMMITMENTS Oh POST-TMI RELATED ISSUES I.
Arkansas Power & Light Company (the licensee) is the holder of Facility Operating License No. NPF-6, which authorizes the operation of Arkansas Nuclear One,' Unit No. 2 plant, (the facility) at steady-state power levels not in excess'of 2815 megawatts thermal. The facility consists of_ a pressurized water reactor (PWR) located at the licensee's site in Pope County, Arkansas.
II.
Followirg the accident at Three Mile Island Unit No. 2 (TMI-2) on March 28, 1979, the Nuclea. Regulatory Commission (NRC) staff developed a number of procosed 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 for the operation of nuclear facilities based on the 1
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7590-01
. experience from the accident at TMI-2 and the official studies and investi-
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gations 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 these requirements are a number of items, con-sisting of hardware modifications, administrative procedure imple. intati,on 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 requirement to be implemented in accordance with the schedule set forth in NUREG-0737, the staff would.onssder licensee requests for relief from staff proposed requirements and their associated implementa-tion dates.
l III.
The licensee's submittals dated December 19 and 31,1980, January 19, February 27. (two letters), March 11,13, and 31, and April 30,1981 and the references stated thereira, wnich are incorporated herein by reference, l
The comitted to complete each of the actions specified in the Attachment.
licensee's submittals included a modified schedule for submittal of certain The staff has reviewed the licensee's submittals and determined I
i nformation.
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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 sub:nittal dates. Most of the information requested by the staff describes how t1e 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 103,1611,1610, 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 HEREBY ORDERED EFFECTIVE IMMEDIATEl.Y THAT 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 licensee's facility) as early as practicable but no later than 30 days after the effective date of the ORDER.
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4 V.
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 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 interest and the manner in which the interest is affected by this Order. A REQUEST FOR HEARING'SHALL NOT STAY 1HE 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.
l If a hearing is held concerning this Order, the issue to be considered i
l at the hearing shall be whether, on the basis of the infonnation 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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. This request'for information was approved by OMB under clearance number 3150-0065 which expires June 30, 1953. Comments on burden and duplication may be directed to the Office of Management and Badget, Reports Management, Room 3208, New Executive.0ffice Building, Washington, D. C.
This Order is effective upon issuance.
OR THE NUCLEAR REGULATORY COMMISSION Darrell (!.' Ei entut, r ctor s
Division of Licensing Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland this 10th day of July 1981
Attachment:
NUREG-0737 Requirements
ATTAC!! MENT NUREG 0737 REQUIREMENTS Impl/ Doc Item Title Appl icabil i ty 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 program and demonstrate compliance with 10-30-79 letter.
(c) Submit description of long 1/1/81 term training program.
I.A.2.1 Reactor Operator ALL Submit description of and imple-8/1/80 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 delays.
(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 submittal is required).
I.C.6 Correct Performance ALL Implement procedures to verify 1/1/81 or Operating Activities correct performance of operating activities (no documentation submit;al is required).
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Impl/ Doc Item Title _,
Aopl4cability Specific Req.iirement Subm 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.
II.B.3 Post Accident ALL Submit description 1/1/81 Samoling of deviations from staff positions.
II.B.4 Training to ALL (a) Have available for 1/1/81 fiitigate 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.1 Performance ALL (a) Submit test program 7/1/80 (PWRs)
Testing of (both BWR/PWR's).
10/1/80 (SWRs)
RV/SRV's (b) Submit qualification program for PWR's block valve.
1/1/81 (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 docueentation 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 statement that 1/1/81 purge valves not meeting CSS 6-4 (or interim post-tion)are seale.d and verifi-cation is performed every 31 days.
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. Impl/ Doc Item Ti,tl e Applicability Specific Requirement
. Subm Due Dates
- II.F.1 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 1/1/81 final design infor, mation for noble gas monitor and iodine /
particulate sampling and analysis.
' II.F.2 Inst. for Inadequate ALL Submit a report detailing the 1/1/81 Core Cooling planned instrumentation system for n;onitoring inadequate core cooling.
II.K.2.10 Antic; Trip on B&W Subnit 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 PORV/SV Failures PWR Submit report on SB LOCA 1/1/81 and probability of failure of PORV/SV/RV.
II.K.3.3
.RV/S'] Failures ALL Submit report (historical 1/1/81
& Challenges
~ and annually thereaftar) of SRV/SV failures anc challenges.
II.K.3.7 PORV Opening B&W Submit report'on the 1/1/81 Probability probability of a PORY cpening during an over-pressurization transient.
II.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.
II. K.3.12 Anticipatory Trip d
Submit confirmation of 1/1/81 or. Turbine Trip Antici atory Trip.
If not currently implemented, submit modification design and schedule for implementation.
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Impl/ Doc Item Title Aeolicability Specific Requirement Sub= Dans II. K.3.13 Separation of BWRs w/HPCI/RCIC Submit results of 1 /1 /81 HFCI/RCIC evaluation and proposed Initiation Levels; modification as appropriate.
Auto Restart of RCIC II.K.3.16 Reduce Challenges BWR Submit 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 EWR Submit report of evaluation, 1 /1 /81 proposed modifications and analysis t6 satisfy staff positions.
II.K.3.22 RCIC Suction BWR w/RCIC Icplement procedures and 1/1 / 81
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document verification of this change.
II.K.3.27 Co==en Reference BWR Icplement change and submit 1/1/81 for H O Level Instruments documentation of changes, 2
II.K 3.2g Isolation SWR w/ICs Submit evaluation of I.C.
4/1 / 81 t
l Condensor performance.
Performance
'II.K.3.30 55 LOC'kMethods ALL Sutcit outline of program 11/15/80 for model.
r II.K.3.44 Fuel Failure BWR Subtit evaluation to verify 1/1/81 l
no fuel failure.
II.K.3.45 Manual Depressur-BWR Submit evaluation on other 1/1 / 81 ization than ADS method'for depressurization.
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Impl/ Doc Item Title Applicability Specific Requirement S bm Due Dates l
III.D.3.3 Improved Inplant ALL Hcve available means to 1/1/81 Iodine. Monitoring ac urately measure airborne rad oiodine ir. plant during i
an afcident.
III.D.3.4 Control Room Habitability ALL a.
Submit control room 1/1/31
' habitability evaluation in formation.
b.
Submit modifications Ul/81 necessary to assure CR habitability with a schedule for completion.
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