ML20009E269
| ML20009E269 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/10/1981 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | ALABAMA POWER CO. |
| Shared Package | |
| ML20009E270 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM NUDOCS 8107270361 | |
| Download: ML20009E269 (10) | |
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
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In the Matter of
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Docket No. 50-348
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ALABAMA POWER COMPANY
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(Joseph M. Farley Nuclear Plant,
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Unit No.1)
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ORDER FOR CONFIRMI,G LICENSEE COMMITMENTS ON POST-TMI R. LATED ISSUES I.
Alabama Power Company (the licensee) is the holder of Facility Gperating License No. NPF-2, which authorizes the operation of the Farley Nuclear Plant, Unit No.1 (the facility) at steady-state power levels not in excess of 2652 megawatts thermal. The facility consists of a pressurized water reactor (PWR) located at the licensee's site near the City of Dothan, Alabama.
II.
Following 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 reouirements 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 st:bstantial additional protection for the operation of nuclear facilities based on the 8107270361 810710 PDR ADOCK 05000348 P
.. 7590-01 experience from the accident at TMI-2 and the official studies and investi-gations of the accident. The staff's proposed requiremants and schedule for implementation are set forth in NUREG-0737, " Clarification of TMI Action Plan Requirements." Among these requiraments 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 conpleted on *r 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 NkC staff expected each requirement to be implemented in arcardance 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 January 14, February 5, Fet:ruary 9, February 13, February 23, and February 23, 1981, and the references stated therein, which are incorporated hereih by reference, committed to complete each of the actions specified in the Attachment. The licensee's submittals inclyded a modified schedule for submittal of certain information. The staff has reviewed the licensee's submittals and determined that the licensee's modified schedule is acceptable based on the following:
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. 7590-01 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
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plant modifications. Therefore, plant safety is not affected by this modification in schedule for the submittal of information.
I have determined that these connitments 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 Farts 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 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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' 7590-01 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 manr.er in which the interest is affacted by this Or der. A REQUEST FOR HEARING SHALL NOT STAY THE IMMEDIATE EFFECTIVENESS OF THI5 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 Urder 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 th'.4 Order, the lic2nsee should comply with the conditions set forth in Section IV of this Order.
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.o 5-7590-01 This request for information was approved by OMB under clearance number 3150-0065 which expires June 30, 1983. Coments 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.
FOR THE NUCLEAR REGULATORY COMMISSION is
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Darrell (I. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland this 10thday of July, 1981
Attachment:
NUREG-0737 Requirements i
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ATTACHMENT NUREG C737 REQUIREMENTS Impl/ Doc Item Title Applicability Specific Requirement Subm Due Ottes 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 procram and demonstrate compliance with 10-30-79 letter.
(c) Submit description of long 1/1/81 term training program, I.A.C.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.,
4 (b) Submit reanalysis of 1/1/81 transients and ac:idents for emergency procedures, OR propose schedule and justify delays.
I.C.5 Feedback of ALL Implement proceduras for 1/1/81 Operating Experience feedback of operating experience 4
(no documentation submittal is required).
1.C.6 Correct Performance ALL Implement procedures to verify
'/1/81
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or Operating Activities correct performance of cperating.
activities (no documentation submittal is required).
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Impl/ Doc Item Title App!4cability Specific Requirement Subm Due Dates 4??.B.2 Shielding ALL-(a) Have availc'ie design 1/1/81 a
tetails for vitri area modificattans.
(b)' Submit technical 1/1/81 deviations to staff positions.
II.B.3 Post-Accident ALL Submit description 1/1/81 Sampling of deviations from staff positions.
87.B.4 Training to ALL (a) Have available for 1/1/81 fif tigate Core review a training Damage proo am for mitigating
- e. ore da nage (no documen-tation submittal required)
(b) Implement training 4/1/81 program (no documentation submittal required).
1 II.D.I Performance ALL (a) Suomit test program 7/1/80 (PWRs)
Testing of (both SWR /PWR's).
10/1/80 (BWRs) l RV/SRV's (b) Submit qualification program for PWR's' blect valve.
1/1/81 (PWRs)
I I. E~.1. 2 Aux F9ed PWRs (a) Submit final design and I/1/81 Initiation documentation on safety ar t Flow grade flow indication.
(b) Subm;. final design and 1/1/81 documentation on safety grade flow initiation.
fl.E.4.2 Containment -
ALL (a) Submit documentation 1/1/81 Isolation justifying minimum contain-ment pressure setpoint for c
isolation of non-essential penetrations.
i (b) Submit statement tnat 1/1/81 purge valves not.neeting CSB 6-4 (or interim posi-tion} are seale.d and verifi-cation is perfonned every 31 days.
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Impl/ Doc Item _
Title Applicability Specific Requirement Subm Due Dates II.F.1 Post-Accident ALL a.
For noble (;as monitor 1/1/81 Monitoring and Iodine / particulate scoling and analysis submit description and justification for deviations from staff requirements, b.
Have available the jfjjgj final design lufor-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 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.
- 12. 0 3.2 P0HV/SV Failur's PWR Submit report on SB LOCA 1/1/S1 and probability of failure of PORV/SV/RV.
If.K.3.3 SRV/SV Failures ALL Submit report (historical 1/1/ 81
& Challenges and annually thereafttr) of SRV/SV frilures and challenges.
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II.K.3,7 PORV Opering B&W Submit report *on the 1/1/81 Probability probability of a PORV opening during an over pressurizatio, transient.
l fl.K.3.9 PID Controller St:lected W-Modify the Proportional 12/1/80 l
Modification plants Integral Derivative Controller l
(as recommended by 'f). Advise NRC when modificatien is completed.
II.K.3.12 Anticipatory Trip W
Submit confirmation of 1/1/81 l
on Turbine Trip Anticipatory Trip.
If not currently implemented, sut:mit modification design and schedule for implementation.
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9 Impl/ Doc Item Title Aoplicability Specific Recuirement Subm Dans I t. K. 3.13 Seoaration of BWRs w/HPCI/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.3.17 ECCS System Outages ALL Submit report on ECCS 1/1 / 81
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outages and propose changes to reduce outages.
II.K.3.iB 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 E'iR 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 document verification of this change.
II.K.3.27 Common Reference BWR Implement change and submit 1/1 / 81 for H O Level Instruments documentation of changes.
2 II.K.3.29 Isolation BWR w/ICs Submit evaluation of I.C.
4 /1 / 81 Condensor performance.
performance II.K.3.30 SS LOCA Methods ALL Submit outline of program 11/1S/80 for nodel.
II.K.3.44 Fuel Failure BWR Submit evaluation to verify 1/1/8.1 l
no fuel failure.
II.K.3.45 Manual Depressur-BWR Submit evaluation on other 1/1 / 81 l
ization than ADS method for l
depressurization.
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Impl/ Doc f2em Title Applicability Specific Requirement Su,bm Due Dates 118.D.3.3 Improved Inplant ALL Have available means t0 1/1/81 Iodine Monitoring
. accurattly measure airborne radiofodino inplant during i
an accident.
!?f.D.3.4 Control Room Habitability ALL a.
Submit control room 1/1/81 habitability evaluation information.
b.
Subnit modifications 1/1/81
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necessary to assure CR habitability with a schedule for completion.
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