ML20009C987
| ML20009C987 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 07/10/1981 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | OMAHA PUBLIC POWER DISTRICT |
| Shared Package | |
| ML20009C984 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM NUDOCS 8107220295 | |
| Download: ML20009C987 (10) | |
Text
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
)
In the Matter of
)
Docket No. 50-285
)
l OMAHA PUBLIC POWER DISTRICT
)
)
-(Fort Calhoun Station,
)
Unit No.1)
)
I ORDER CONFIRMING LICENSEE COMMITMENTS ON POST-TMI RELATED ISSUES l
I.
Omaha Public Power District (the licensee) is the holder of Facility Operating License No. OPR-40, which authorizes the operation of the Fort Calhoun Station Unit No.1 (the facility) at steafv-state power levels not in excess of 1500 megawatts thermal. The facility consists of a pressurized water reactor (PWR) located at the licensee's site in Washington Ceunty, Nebraska.
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 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 l
- m. -
7590-01 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 -
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timplementation 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 implementation
'and; specific information to be submitted by the if censee, scheduled to be completed on or before June 30,1981 -(see the Attachment to this Order).
NUREG-073~ vas transmitted to each licensee and applicant by an NRC letter f
from my office dated October 31, 1980, which is hereby incorporated by
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.. reference. In' that letter, :it was' indicated that although -the NRC cstaff expected each requirement to be implemented in accorda.'ce with the
- schedule set:forth in NUREG-0737, the staff would consider licensee requests l-for relief from staff proposed requirements and their associated implementa-l.
tion dates.-
l III.
The ~11censee's submittals dated December 12, 1980, as supplemented by letters l
dated'Oecember 31, 1980, and January 6 and 26, and February 27, 1981, and
' the references stated therein, which are incorporated herein by reference, L
'connitted to complete each' of the actions specified in the Attachment. The Llicensee's submittals included a modified schedule for submittal of certain l
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 scnedule for submittal of infermation 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 103,1611,1610, and 182 of the Atomic Energy Act of 1954, as amanded, and the Commission's regulaticas 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 appropriate to the licensee's facility) as early as practicable but no later than 30 days after the effective date of the ORDER.
7590-01 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.3. 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 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 desig ating the time and place of any such hearing.
If a hearing is held concerning this Order, the issue to be considered at t'he 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 unce-clearance number 3150-0065 which expires June 30, 1983. Comments on bur en 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 i
r 5
1 (
I Ctor Division of Licensing Office of Nuclear Reactor Regulation
- Dated at Bethesda, Maryland this 10th day of July' 1981
Attachment:
NUREG-0737 Requirements t.
I I
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ATTACHMENT NUREG 0737 REQUIREMENTS'
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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 : individual s (or equivalent), trained to licensee's program.
(b) Submit description of 1/1/81-
. current traiaing program 5
and demonstrate compliance
/
with 10-30-79 letter.
(c) Submit description of long 1/1/81 term training program.
!4 1.A.C.1 Reactor. Opera tor
'ALL Submit description of and imple-8/1/80
. Qualification ment Upgraded 1 raining 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 feedbeck of operating experience
-(no documentation subrittal 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 submittal is required).
s
4.
Impl/ Doc
- Item Title App 14cability Specific Requirement
-Sabm Due Dates II'. B. 2
-Shielding ~
ALL-
- (a) Have a <ailable design 1/1/81 detait for vital area modif.ations.
(b) Subnit technical 1/1/81 deviations to staff positions.
JII.B.3
. Post-Accident ALL Submit description 1/1/81 Sampling of deviations from staff positions.
II.B.4 Training to ALL (a) Have available for 1/1/81
'ititigate Core ~
review a training Damage; program for mitigating core damage (no documen-tation submittal required) 7 (b) Implement training 4/1/81 program (no documentation submittal required).
.II'D.1
- Performance
. ALL (a)Submittestprogram 7/1/80 (PWRs)-
eTesting of
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(both BWR/PWR's).
10/1/80 (BWRs)
- RV/SRV's (b) Subnit qualification program for PUR's block L
valve.
1/1/81 (PWRs)
'II.E.1.2l
- Aux Feed.
PWRs (a) Submit final design and I/1/81
^
-Initiation:
documentation on safety and Flow grade flow indication.
i (b) Subnit final design and 1/1/81 documentation on safety grade flow initiation.
II.E.4.2
. Containment ALL
',a) Submit documentation 1/1/81 LIsolation justifying minimum contain-ment pressure setpoint for isolation of non-essential penetrations.
(b) Submit statement that 1/1/81 purge valves not meeting CSB 6-4 (or interim post-tion)are seale,d and verifi-cation is performed every 31 days.
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3-Irhpl/ Doc Item-Title Applicability Specific Pequirement sam Due Dates
- II.F.1.
Post-Accident ALL.
a.
For noble' gas monitor 1/1/81 Monitoring and Iodine / particulate e
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.Fi2 Inst. for Inadequate
.ALL Submit a report detailing the 1/1/81
- Core Cooling planned instrumentation systes 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 Feedwa ter.-
IllK.3.2 PORV/SV Failures PWR Submit report on SB LOCA 1/1/S1 and probability of failure of PORV/SV/RV.
l II.K.3.3 SRV/3V Failures ALL Submit report (historical 1/1/81
.& Challenges and annually thereafter) of SRV/SV failures and l
challenges.
r.
II.K.3.7-PORV Opening B&W Submit report
~II.K.3.9 PID Controller Selected W Modify the Proportional 12/1/80 Modification plants Integral Derivative Controller (as recommended by 'f). Advise NRC when modification is completed.
Submit confirmation 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 implementatfort.
r.
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Impl/ Doc Item' Titl e '
Applicability Specific Recuirement Subm Dans II.K.3.13 Separation of
.BWRs w/HPCI/RCIC Submit results of 1/1/B1 HPCI/RCIC evalcation and pronosed 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 l
outages and propose changes to reduce outages.
II.V. 3.18
_ ADS Logic BWR Submit report of feasibility 4/1 /81 Modifications of ADS system logic chaages to i
climinate need for manual actuation.
II. K.'3. 21 CSS /CPCI Restart BWR Submit report of evaluation, 1/1 /81 proposed modifications and cnalysis t( satisfy staff positions.
II.K.3.22 RCIC Suction SWF w/RCIC Implement procedures and '
1/1 /81 document verification of this change.
L II.K.3.27 Common Reference BWR Implement change and submit 1/1 / 81 for H O Level Instruments documentation of changes.
2 7,I.K.3.2g Isolatien BWR w/ICs Submit evaluation of I.C.
4 /1 / 81 Condensor performance.
l Performance II.K.3.30 SB LOCA Methods ALL Submit outline of program 11/15/80 for model.
II.K.3.44 Fuel Failure BWR Submit evaluation to verify 1/1/81 no fuel failure.
II.K.3.45 Manual Depressur-BWR Submit evaluation on other 1/1/51 ization than ADS method for depressurization.
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.'Impl/ Doc i ter.
Ti,tle Applicability Specific Requirement 5,ub,,m Due Da tes III.D.3.3 Improved Inplant ALL Have available means to 1/1/81 Iodine Monitoring accurately measure airborne radioiadine inplant during an accident.
III.O.3.4 Control Room Habitability ALL a.
Submit control room 1/1/81 habitability evaluation in fonnation.
b.
Subnit modifications 1/1/81 necessary to assure CR habitability with a schedule for completion.
.