ML20009C957
| ML20009C957 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 07/10/1981 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | FLORIDA POWER & LIGHT CO. |
| Shared Package | |
| ML20009C958 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM NUDOCS 8107220235 | |
| Download: ML20009C957 (10) | |
Text
c UNITED STATES OF AMERICA 7590-01
- NUCLEAR REGULATORY COMMISSION
)
In 'the Matter.of
)
Docket No. 50-335
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FLORIDA POWER & LIGHT COMPANY
)
)
(St. Lucie Plant, Unit No.1)
)
)
ORDER CONFIRMING LICENSEE COMMITMENTS ON POST-TMI RELATED ISSUES 1
I.
Florida Power & Light Company (the licensee) is the tolder of Facility
- Operating License No. DPR-67 which authorizes the operation of the St.
Lucie Plant, Unit No.'l (the facility) at steady-state power levels not in excess of 2560 megawatts thermal. The facility is a pressurized
_ water reactor (PWR) located at the licensee's site in St. Lucie County, Florida.
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 in the operation of nuclear facilities based on the i
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o 7590-01 2-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
' implementation are set forth in NUREG-0737, "Clarificatio., of TMI Action Plan Requirenents." Among these requirements 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 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 consider licensee requests for-relief from staff proposed requirements and their associated implementa-tion dates.
III.
1
-The licensee's submittals dated December 23, 1980, May 28, 1981, and June 19, 1981, and the references stated therein, which are incorporated herein by l
. reference, committed to complete each of the actions specified in the l
Attachment. The licensee's submittals included a modified schedule for l.
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 specific 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 imple.1entation of plant modifications. -
Therefore, plant safety is not affected by this modification 4
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 IMMEDIATELY THAT the licensee shall comply with the following conditions:
.~
. 7590-01
~The-licsnsee shall satisfy the specific requirements described 4
in the Attachment to this Order (as appropriate to the licensee's' facility) as early as practicable but no later
. than 30' days af ter the effective date of the ORDER.
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 Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555. A copy of the request should 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 EFFECT.VENESS OF THIS ORDER.
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. 7590-01
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.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 forth in Sections II and III of this Order, the licensee should comply with 'the conditions set forth in Section IV of this Order.
This request-*or information was approved by OMB under clearance number 3150-0065 which expires June 30, 1983. Comments on burden and duplication ay be directed to the Office of Management and Budget, Reports Management, m
Room 3208, New Executive Office Building, Washington, D.C.
This. Order is effective upon issuance.
FOR THE NUCLEAR' REGULATORY COMMISSION I
h Darrell G.'
- isenhut, frector Division of Licensing Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland, this 10th-day of July 198'.
Attachment:
-NUREG-0737 Requirements
ATTACHMENT NUREG 0737 REQt)!REMENTS Impl/Coc
" Item Title Applicability Specif.: Recuirement Subm Due Dates
'I.A.l.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 training procram and demonstrate compliance with 10-30-79 letter.
(c) Submit description of lona 1/1/81 term training program.
I.A.C.l!
Reactor Operator-ALL Submit description of and imple-S/1/80
~
Qualification.
ment Upgraded Training Program.
4 I.C.1 Acci xe- 'es 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 erperience (no documentation subrittal is required).
-fl. C. 6.
Correct Performance.
ALL Implement procedures to verify 1/1/81 i '
or Operating Activities correct performance of operating activities (no documentation submittal is required).
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.o 2-Impl/ Doc Item Title -
rr?dcability Specific Recuirement Subm Due Dates i
II.B.2
'5hielding ALL (a) Have available design 1/1/81 details for vital area modifications.
(b) Submit technical 1/1/81
' deviations to staff positions.
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II.S.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 Mitigate 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 (BWRs)
RY/SRY's (b) Submit qualification program for PWR's block valve.
.l/81 (PWRs)
II.E.1.2 Aux Feed PWRs (a) Submit final design and I/1/81 Init16; ton documentation on safety
' and Flow grade ficw indication.
(b) Submit final design and 1/1/81
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documentation on safety
[
grade flow initiation.
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II.E.4.2 Containment ALL (a) Submit documentation 1/1/81 l
Isolation justifying minimum contain-ment pressure setpoint for e
isolation of. non-essential penetrations.
l-(b) Submit statement that 1/1/81 purge valves not meeting CSB 6-4 (or interim posi-tion)are seale.d and verifi-cation is performed every 31 days.
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-Item Ti tl e_
Applicability Specific Pequirement
' SA n Oue Dates II.F.1 Post-Accident ALL
.a.
For noble gas monitor 1/1/31
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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 systes 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 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/S1 and probability of failure of PORV/SV/RV.
II.K.3.3 SRV/SV Failures ALL Submit report (historical 1/1/81
& Challenges and annually thereafter) of SRV/SV failures and challenges.
II.K.3.7 PORY Opening B&W Submit report'on the 1/i/81 Probability probability of a PORV opening during an over-pressurization transient.
II.K.3.9 PID Controller Selected W Modify the Proportional 12/1/80 Modification plants Integral Derivative Control 7 er (as ecommended by WJ. 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 implementation.
4-Impl/ Doc
. Item Title Acolicability Specific Reoutrement
_Subm Dans II.K. 3.13 Separation 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. R'/ ' -
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 feasib'lity 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 proposed modifications and analysis t6 satisfy staff positions.
II.K.3.22 RCIC Suction-SWR w/RCIC Implement procedures and 1/1 /81 document verification of this change.
II.K.3.27 C:= mon 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 l
II.K.3.30 SS LOCA Methods ALL Submit outline of program 11/15/80 I
or model.
LII.K.3.a4 Fuel Failure BWR Submit evaluation to verify 1/1/81 no fuel failure.
II.K.3.a5 Manual Depressur-BWR Submit evaluation on other
'1/1 / 51 ization than ADS method for depressurization.
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Title Applicability Specific Requirement Subm Due Dates 7.N.D.3.3 I:np-eved Inplant ALL-Have available means' to 1/1/81 Iodine Monitoring accurately measure airborne radiofodine inplant during an accident.
-111.'0.3.4 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 completion.
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