ML20030A801
| ML20030A801 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/10/1981 |
| From: | Purple R Office of Nuclear Reactor Regulation |
| To: | TENNESSEE VALLEY AUTHORITY |
| Shared Package | |
| ML20030A792 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM NUDOCS 8107290049 | |
| Download: ML20030A801 (10) | |
Text
7590 4 1 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
)
In the Matter of
)
Docket Nos. 50-259
)
260 TENNESSEE VALLEY AUTHORITY
)
296
)
(Browns Ferry Nuclear Plant,
)
Unit Nos. 1, 2 and 3)
)
ORDER CONFIRMING LICENSEE COMMITMENTS ON POST-TMI RELATED ISSUES I.
The Tennessee Valley Authority (the licensee) is the holder of Facility Operating License Nos. DPR-33, DPR'-52 and DPR-68 which authorize the operation of the Browns Ferry Nuclear Plant, Unit Nos.1, 2, and 3 (the facilities) at steady-state power levels not in excess of 3253 megawatts thermal for each unit. The facilities consist of boiling water reactors (BWRs) located at the licensee's site in Limestone County, 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 requirements to be implemented on operating reactors and on plants under construction. These requirements include Operational Safety, Siting and Design, and Eoergency Preparedness and are intended to provide substantial-additional protection for the operation of nuclear facilities based on the 8107290049 810710 PDR ADOCK 05000259 P
- 2.-
7590-01 experience from the accident at TMI-2 and the official studies and investi-g d ons 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 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.
The licensee's submittals dated December 23 1980, March 17, April 9 and June 1, and July 2,1981, the references stated therein, which are incor-porated herein by reference, comitted to complete each of the actions specified in the Attachment. The licensee's submittals included a modi.:
fied 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:
9-7590-01 The licensee's schedule for submittal'of information in some instances does not meet the staff's specified submittal dates. Most of the infomation 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 infonnation.
I have determined that these commitments are required in the interest of public health and safety, and therefore, should be confirmed by ORDER.
l IV.
l Accordingly, pursuant to Sections 103,1611,1610, and 182 of the Atomic l
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:
I The licenree shall satisfy the specific requirements described l
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-Q1 v.
\\
Any person who has an interest affected by this Order may request a hearing witain 20 days of the date of publication of thir Order' in the Federal Register. Any request for a hearing shall be addressed to the Director, Office of Nuc1 car 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 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-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.
. 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 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 C
Robert A. Purple, Depi!ty Director 1
Division of Liceneing Office of Nuclsar Reactor Regulation Dated at Bethesda, Maryland this 10 day of July 1981
Attachment:
NUREG-0737 Requirements l
l
o ATTACRMENT
- NUREG 0737 RE1VIREMENTS Impl/ Doc Item Title Applicabil ity' Speci_fic Requirement Subm Due Dates
-(or equivalent), trained to licensee's prograr;.
(b) Submit description of.
-1/1/81 current training proaram and' demonstrate compliance with 10-30-79 letter.
(c) Submit description of long 1/1/81 term trairiing program.
I.A.:.1 Reactor Operator ALL Submit description of and imple-8/1/8C 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 4
propose schedule and justify delays.
(b) Submit reanalysis of 1/1/81 transients and accidents for emergency procedures, 0?
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 sutrittal is required).
. f.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).
~
~.
Impl/ Doc T.i_tl e Appi,icability Specific Requirement Subm Due Dates Item t
11.8.2 Shielding ALL (a) Have available design 1/1/81 details for vital area modifications.
(b) Submit technical 1/1/d1 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 liitigate 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)
RV/SRV's (b) Submit qualification program for PWR's block valve.
1/1/81 (PWRs)
II.E.1.2 Aex 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 pos1-tion)are sealed and verifi-cation is perfomed every 31 days.
3-Impl/ Doc Item Ti tl e_
Applicability Specific Requirement Subn 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.
If.F.2 Inst. for Inadequate LL Submit a report detailing the 1/1/81 Core Cooling planned instrumentation systen 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.
f l. K'. 2.13 Thermal Mechanical B&W Submit report on effects l'/l/81 Report of Hi Pressure Injection on vessel integrity for SB LOCA with no Aux Feedwater.
IX.K.3.2 PORV/SV Failures PWR Subv c report on SB LOCA 1/1/S1 and probability of failure of PORV/SV/RV.
ff.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 PORV Opening B&W Submit report *on the 1/II81 Probability probability of a PORV opening during an over-pressurization transient.
fl.K.3.9 PID Controller Selected W Vc' 'fy the Proportional 12/1/80 Modification plants
. itegral Derivative Controller (as recommended by W).
Advise NRC when modification is completed.
Submit confirmation of 1/1/81 If.K.3.12 Anticipatory Trip W.
Anticipatory Trip.
If not on Turbine Trip currently implemented, submit modification design and schedule for implementation.
l
w 4_
Impl/ Doc Item Title Applicability Specific Requirement 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; madification as appropriate.
Auto Rastart of RCIC II. K. 3.16 Reduce Challenges BWR Submit report on actions 4/1 /81 to RV's planned to reduce RV challenges, i 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 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 /81
(
document verification of this change.
II. K. 3. 27 Co=on Reference BWR Implement change and sub?,it 1/1 / 81 l
for H O Level Instruments documentation of changes.
2 l
! II.K.3.29 Isolation BWR w/ICs Submit evaluation of I.C.
4/1 / 81 l
Condensor-performan:e.
Perfomance
, II.K.3.30 SS LOCA Methods ALL Submit outline of program 11/15/80 l
for model.
II.K.3.a4 Fuel Failure BWR Submit eva)uation to verify 1/1/8.1 l
no fuel failure.
- II.K.3.45 Manual Depressur-BWR Submit evaluation on other 1 /1 / 51 ization than ADS method for depressurization.
l
-q 5-Impl/ Doc
' Item T_i,tl e Applicability Specific Requirement Su,b,m Due Dates III.D.3.3 Improved Inplant ALL Have available means to 1/1/81 Iodine Monitoring accurately measure airborne radioiodine inplant during an accident.
III.D.3.4 Control Room H'abitability ALL a.
Submit control room 1/1/81 habitability evaluation information.
.b.
Submit modifications
-1/1/81 necessary to assure CR habitability with a schedule for completion.
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