ML20009F086
| ML20009F086 | |
| 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 | |
| ML20009F088 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM NUDOCS 8107290103 | |
| Download: ML20009F086 (10) | |
Text
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Ul!ITED ST/.!!'
HUCLEAR REGt!
In the flatter c6 ARKANSAS POWER A!!D LIGHT COMPAt1Y
( Arkansas Nuclear One, Unit No.1)
ORDER C0t!FIRMDb $ i POST-Pil 1
Arkansas Power and Light Company ( th Operating Liccase No. DPR-51, whic' Nuclear One, Unit No.1 (the facil excess of 2568 megawatts thermal.
water reactor (NR) located at the Following the a:cident at Three s' 1979, the Nuclear Regulatory Con.
proposed requirenents to be
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under construction. These and Design, and Emergency P 1
additional nrotection for ti e'
8107290103 810710 PDR ADOCK 05000313 P
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i 7590-01
- l experience-from the accident at TMI-2 and the official studies and investi-gations of the accident.
The staff's proposed requirements and schedule for implementetion are set forth in NUREG-0737, " Clarification of TMI Action Plan Requirements." Among these requirements are a rumber of itena, con-sisting of hardware modifications, administrative procedure implementation i
and specific information to be submitted by the licensee, scheduled to be completed on or before June 30,1981 (see the Attachment to this O der).
NUREG-0737 was transmitted to each licensee and applicant by an NRC letter f rom 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 schedale set forth in NUREG-0737, the staff would consider licensee requests for relief from staff proposed requirements and their associated implementa-
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tion dates.
Ill.
The licensee's submittals dated December 19 and 31,1980, J anuary 19,1981 and February 5 and 27,1981, which are incorporated herein by reference, j
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 sub-mittals and determined that the licensee's nodified schedule is acceptable based on the foilowing:
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, 7590-01 The licensee'c schedule for submittal of informati~on 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 fl0 REG-0737. Therefore, this deferral of the licensee submittal will not alter the implementation of plant modifications. Therefore, plant safety is not
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affected by this modification in schedule for the l
submittal of information.
I have determined that these commitments are requirad in the interest of public health and safety, and therefore, should be confirmed by ORDER.
c IV.
Accordingly, pursuant to Sections 103, 1611, 1610. and 182 of the Atomic 4
Energy Act of 1954, as amended, and the Commission's regulations in 10 CFR Parts 2 and 50, IT IS HEREBY ORDERED EFFECTIVE IMMEDI ATELY THAT the licensee shall cocply with the following conditions:
J The licensee shall satisfy the specific requirements described in the Attachment to this Order (as appropriate to the licensee's f acility) as early as practicable but no.later than 30 days af ter the effective date of the ORDER.
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. 7590-01 V.
s 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 Comission, Washington, D.C.
'0555. A copy shall also be se.nt to the 1
Executive Legal Director at the same address.
If a hearing is requested 3
by a person other than the licensee, that persen 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 af. acted 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 Comission 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 e-mly 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 Managerent and Budget, Reports Management, Room 3208, New Executive Office Building. Washington, D. C.
This Order is effective upon issuance.
OR THE NUCLEAR REGULATORY COM.'ilSSION b.
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Da rel'1 G. Elsheh ut, D[irector Division of Licensing Office of Ni clear Reactor Regulation Dated at Bethesda, Maryland this 10 day of July 1981 Attcchment:
NUREG-0737 Requiremen;-
.s-ATTACHMENT.
l NUREG 0737 REQUIREMENTS l.
Impl/ Doc
.{ ~ Item Title Applicability ~
Specific Requirement Subm Due Dates
. I. A.1.1 STA ALL (a) Provide STA coverage by.
1/1/81 degreed individuals i
(or equivalent), trained to licensee's program.
(b) Submit description of 1/1/81 current training proliance ram and demonstrate comp with 10-30-79 letter.
l (c) Submit description of long 1/1/81 term train'ing program.
1 i-I. A..'.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-
[/1/81 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.
1.C.5 Feedback of ALL Implement procedures for
'1/1/81 Operating Experience feedback of operating experience (no documentation submittal is j
required).
I.C.6 Correct performance ALL Implement procedures to verify 1/1/81 or Operating Activities correct performance of operating activities (no documentation submittal is required).
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2-Impl/ Doc Item Title Aop'4cabil ity Specific Requirement Subm Due Dates 11.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.
11.8.3 Fost-Accident ALL Submit description 1/1/81 Saroling of deviations from staff positions.
?!.B.4 Training to ALL (a) Have available for 1/1/81 flitirate Core review a training 4
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 (BWRs)
RV/SRV's (b) Submit qualification program for PWR's block valve.
1/1/81 (PWRs)
- 11. 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 statement that 1/1/81 purge valves not meeting, CSB 6 t.
(or interim posi-tion)are seale.d and verifi-cation is perfonned every 31 days.
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Impl/ Doc e
Item' Title Applicability Specific Requirement Subm Due Dates XI 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-requi remen ts'.
l b.
Have available the 1/1/81
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final design infor-mation for noble gas'.
monitor and iodine /
particulate sampling and analysis.
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II.F.2 Inst. for Inadequate ALL Submit a report detailing the 1/1/81 Core Cooling planned instrumentation systen for monitoring inadequate core cooling.
I I. K. 2.10 Antic. Trip on B&W Submit final design for 1/1/81.
LOFW and TT anticipatory trio as 4
1 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/S1 and probability of failure of PORV/SV/RV.
II.K.3.3 SRV/SY Failures ALL Submit report (historical 1/1/ 81 1
& Challenges and annually thereafter) of SRV/SV failures and challenges.
1 II.K.3.7 PORV Opening B&W Submit report'on the
.1/1/81 1
Probability probability of a PORV i
opening during an over-pressurization transient.
Modify the Proportional 12/1/80 II.K.3.9 PID Controller Selected W Modification plants Integral Derivative Controller (as recommended by W). Advise NRC when modification is completed.
t II.K.3.12 Anticipatory Trip W
Submit confirmation of 1/1/81 on Turbine Trip Anticipatory Trip.
If not currently implemented, submit modification design and schedule for implementation.
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Impl/ Doc Ittm Title Applicability Specific Reouirement Sub: Dans I I. K. 3.13 Separation of BWRs w/RDCI/RCIC Submit results of 1 /1 /81 HPCI/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. 2.17 ECCS System Outages ALL Submit report on ECCS 1 /1 /51 outages and propose changes to reduce outages.
II. K. 3.15 ADS Logic BRR Submit report of feasibility 4/1/S1 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 proposed modifications and analysis t6 satisfy staff positions.
II.K.3.22 RCIC Suction BWR w/RCIC Implement procedures and 1/1/S1 document verification of this change.
II.K.3.27 Cc= mon Reference BWR Implement change and submit 1/1/51 for H O Level Instruments docurantation of changes.
2 II.K.3.25 Isolation BWR w/ICs submit evaluation of I.C.
4/1 / 81 Condensor performance.
Perfo rma nce II.f. 3.30 SS LOCA Methods ALL Submit outline of procram 11/15/80 for redel.
II.K.3.a4 Fuel Failure BWR Submit evaluation to verify 1/1/81 no fuel failure.
II.K.3.a5 Manual Depressur-BWR Submit evaluatien on other 1/1 / 51 i:ation than ADS method for depressurization.
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4 Impl/ Doc Ite~
Title Applicability Specific Requirement S_u_b_m Due Da tes III.D.3.3 Improved Inplant ALL Have available means to 1/1 /81 lodine Monitorir.g accurately measure airborne radioiodine inplant during an accident.
III.D.3.4 Control Room Habitability ALL a.
Submit control room 1/1/81 habitability evaluation in fonnation,
b.
Suomit modifications 1/1/81 iecessary to assure CR
.iabitability with a schedule fo. completion.
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