ML20009C971
| ML20009C971 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/10/1981 |
| From: | Purple R Office of Nuclear Reactor Regulation |
| To: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| Shared Package | |
| ML20009C969 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM NUDOCS 8107220262 | |
| Download: ML20009C971 (10) | |
Text
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UNITED STATES OF AMERICA 7590-0,1
- NUCLEAR REGULATORY COMMISSION
)
In the Matter of
)
Docket Nos. 50-338
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and 50-339 VIRGINIA ELECTRIC AND POWER COMPANY
)
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(North Anna Power Station,
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Units No. I and 2)
)
)
ORDER CONFIRMING LICENSEE COMMITMENTS ON POST-TMI RELATED ISSUES 1.
The Virginia Electric and Power Company (the licensee) is the holder of Facility Operating License Nos. NPF-4 and NPF-7 which authorize the operation of the North Anna Power Station, Units No. I and No. 2 (the facilities) at steady-state
-power -. levels not in excess of.2775 megawatts thermal. The facilities are pressurized water reactors (PWRs) located at the licensee's site in Louisa County, Virginia.
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 0107220262 810710"
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. 7590-01 experience from the accident at TMI-2 and the official studies and investigations of. the accident. The staff's proposed requirements and scheduleLfor implementation are set forth'in'NUREG-0737, " Clarification
'of TMI Action Plan Requirements." Among these req # ements are a numb'6r of items,' consisting of hardware modifications, administrative procedure implementation and specific. information to 'oe submittsd by the,,
licensee, scheduled to be completed on or before June 30, 1981 (see the A'ttachment to this Order). NUREG-0737 was transmitted to each licensee
' and applicant-by 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 i
requests for relief fran. staff proposed requireronts and their associated implementation dates,
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t I-III.
- The licensee's submittals deced December 15, 1980, December 31, 1980, and l
February _27, May 29 and July 6,1981, committed to complete each of the actions specified in the Attachment. The licensee's submittal included a modified schedule for submittal of certain information.- The staff has reviewed the licensee's submittals and determined that the licensee's modified schedule i
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 me(i 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 103,1611,161o, and 182 of the Atomic Energy Act of 1954, as amended, and the Commission's regulations in i
10 CFR Parts 2 and 50, IT IS HERE8Y ORDERED EFFECTIVE IMMEDIATELY THAT the licensee shall comply with the following conditions:
The ifcensee shall satisfy the specific requirements described in the Attachment to this Order (as appropriate to the ifcensee's facility) as early as practicable but no later than 60 days after the effective date of the ORDER.
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d 7590-01
, V.
Any person who has an interest affected by this Order may request a hearing within 20 days of the date s f publication of this Order in the o
- 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 acccrdance 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 pe. sons 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.
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7590-01 5-This~ request for information was approved by OMB under clearance numbar 3150-0065 which expires June 30, 1983. Comments on burden and duplication may be directed to the.0ffice of Management and Budget, Reports Mat gement, Room 3208, New Executive Office Building, Washington, D. C.
This Order is effective upon issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Robert A. Purple, Depu Ofrector Division of Licensing Office of Nuclear Reactor Regulation Dated at Bethesda Maryland this 10tn day of duly 1981 Attrement:
NUREG-0737 Requirements' l
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ATTACHMENT NUREG 0737 REQUIREMENTS Impl/ Doc Item Title Applicability Specific Requirement Subm Due Dates I.4.1.1 STA ALL (a) Provide STA coverage by
.i/81 degreed individual s (or equivalent), trained -
to licensee's program.
(b) Submit description of 1/1/81 current training program 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 reanalyse; 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 eccidents 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 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 i
activities (no documentation submittal is required).
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2-Iapl/ Ooc Item Title Aop14cability Specific Requirement Subm Due Dates II.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.
II.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 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 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 r
isolation of.non-essential penetrations.
(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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Impl/ Doc Item Title Applicability Specific Requirement Sg m Due Cates II.F.I Post-Accident ALL a.
For. noble gas monitor 1/1/81
.*ioni toring and Iodine / particulate sampling and analysis submit description and justification for deviations from staff requirements.
b.
Have available the final design infor-1/1/81 mation for noble gas monitor and fodine/
particulate sampling and analysis.
II.F.2 Inst. for Inadequate ALL Submit a report detailing the 1/1/81 Core Cooling planned instrumentat' n system for monitoring inad:
te 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.'ieunar.ical 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
- POMV/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.
.If K.3.7
- PORV Opening B&W Submit repert'on the 1/1/81 Probability probabili.y of a PORV opening during a.
- over-pressuritation transient.
II.K.3.9 PID~ Controller Selected W_
%dify the Proportional 12/1/80 MJdification plants Integral Derivative Controller (as recommended by W).
Advise NRC when modificaticn is completed.
I.K.3.12 Anticipatory Trip
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Submit confirmation of 1/1/81 I
on Turbine Trip Anticipatory Trip.
If not currently implemented, submit l-modification design and schedule for implementatiors.
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e Impl/Dac Item Title Aoplicability Specific Requirement Sube Dans 11.K. 3.13 Separation of BWRs w/HPCI/RCIC Submit results of 1/1 /81 HPC1/RCIC evalcation and proposed Initiation Levels; modification as appropriate.
Auto Restart of RCIC II. K. 3.16 Reduce Challenges BWR Submit report on actions 4/1/a1 to RY's planned to reduce RV challenges.
II.X.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.
!!.X.3.22 RCIC Suction BWR w/RCIC Implement procedures and 1/1 /81 document verification of l
this change.
l II.K.3.27 C mon Reference BWR Icplement change and submit 1/1/S1 for H O Level Instruments documentation of changes.
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II.K.3.29 Isolation BWR w/ICs Submit evaluation of I.C.
4/1 / 81 l-Condensor perfo rmance.
l performance II.X.3.30 55 LOCA Methods ALL Submit cutline of program 11/15/80 for nodel.
-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 l
depressurizatio'n.
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. - Impi/Occ Item Tith
' Applicability Specific Requirement Subm Due Dates
'!II.O.3.3 Improved Inplant ALL Have available means to 1/1/81 Iodine Monitoring accurately measure airborne radioiodine inplant during an accident.
111.0.3.4 Control Room-Habitability Alt, a.
Submit control room 1/1/81 habitability evaluation in fonnation.
b.
Submit modificatior.s 1/1/81 necessary to assure CR habitability with a-schedule for completion.
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