ML20009C978
| ML20009C978 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/10/1981 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | NORTHEAST NUCLEAR ENERGY CO. |
| Shared Package | |
| ML20009C979 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM NUDOCS 8107220275 | |
| Download: ML20009C978 (10) | |
Text
.
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
)
In the Mattor of
)
Docket No. 50-336
)
THE CONNECTICUT LIGHT & POWER COMPANY
)
THE HARTFORD ELECTRIC LIGHT COMPANY
)
WESTERN MASSACHUSETTS ELECTRIC COMPANY
)
NORTH ~ASf NUCLEAR ENERGY COMPANY
)
)
(Millstone Nuclear Power Station.
)
Unit No. 2)
)
ORDER CONFIRMING LICENSEE COMMITMENTS ON POST-TMI RELATED ISSUES The Northesast Nuclear Energy Comnany, et al. (the licensee) is the holder of Facility Operating License No. DPR-65, which authorizes the operation of the Millstone Nuclear Powar Station, Unit No. 2, (the facility) at steady-state power levels not in excess of 2700 megawatts thermal. The facility consists of a pressurized water reactor (PWR) located at the licensee's site in Waterford, Connecticut.
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
' 8107220275 8107107 DR ADOCK 05000336 PDR
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 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 app 1tcant 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 l
staff expected each requirement to be implemented in accordance with the schedule set forth in NUREG-0737, the staff would consider licensee requests for reli.ef from staff proposed requirements and their associated implementa-l
-tion' dates.
III.
L The licensee's submittals dated December 15 and 31,1980, February 13,19, and 27, and March 4 and 18, 1981, and the references stated therein, which are incorporated herein by reference, committed to complete each of the actions specified-in the Attachment. The licensee's submittals included a modified l
schedule for sulmittal of certain information. The staff has reviewed the licensee's submittals and determined that the IIcensee's modified schedule
. is acceptable based on the following:
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- 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 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.
H.
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 ifcensee 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 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.S. Nuclear Regulatory Commission, Washington, D.C.
20555. A copy shall also be sr.nt 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(al(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 i
interest affected by this Order, the Commission will issue an Order i
designating the time and place of any such hearing.
l 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 l
with the conditions set forth in Section IV of this Order.
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4 7590-01
~ 5-This request for information was approved by OMB under clearance number 3150-0065 which expires June 30, 1983. Comments on burden and duplica M.
- may be directed to the Office of Management and Budget, Reports Mana,.4nent, Room 3208, New Executive Office Building, Washington, D. C.
T.his Order is effective upon issuance.
OR THE NUCLEAR REGULATORY COMMISSION Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland this10th day of July 1981
Attachment:
NUREG-0737 Requirements
e.
ATTACHMENT
-NUREG 0737 REQUIREMENTS Impl/ Doc Item Title Applicability Specific Requirement Subm Cue Dates
'I. A.l.1 S fA
~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 demonstra te compliance with 10-30-79 letter.
(c) Submit description of long 1/1/81 term training program.
..l.A.I.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 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 experience (no documentation submittal is required).
.I.C. 6.
' Co rrect.Perfo rmance ALL Implement procedures to verify 1/1/81
.orf 0perating Activities correct performance of operating activities (no documentation submittal is required).
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i, 2-t Impl/0cc Item Title _
Appl 4cabil ity Specific Requirement Subm Due Dates II.B.2 Shielding.
ALL~
(a) Have available design 1/1/81 details for vital area c--
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).
Performance ALL
'(a) Submit test program 7/1/80 (PWRs)
II.D.1_
' 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)
LII.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 docurrentation 1/1/81 t
Isolation justifying minimum contain-ment pressure setpoint for isolation of non-essential penetrations.
f (b) Submit statement that 1/1/81 purge valves not meeting
=
l' CSB 6-4 (or interim posi-tion)are seale.d and verifi-cation is perfonned every 31 days.
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. Item
' Title Applicability Specific Pequirement
-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.
.'I I. F. 2 Inst. for Inadequate ALL 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.
. 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 Subnit report *on the 1/1/81 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 Controller (as recommended by W). Advise NRC when modification is completed.
II.K.3.12 Anticipatory Trip
'd Submit confirmation of 1/1/81 on Turbine Trip Anticipatory Trip.
If not currently implemented, submit modification design and schedule for implementatiort.
l Impl/Dac
~ Item Titl e Aoplicability 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; 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 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 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
-Ccmmon Reference BWR Implement change and submit 1/1/51 for~H O Level Instruments documentation of changes.
2
~ 11.K.3.29 Isolation BWR w/ICs Submit evaluation of I.C.
4/1 / 81 Condensor performance.
Performance II.K.3.30 53 LOCA Methods ALL Submit outline of program 11/15/8D for nodel.
II.K.3.44.
Fuel Failure BWR Submit evaluation to verify 1/1/31 no fuel failure.
II.K.3.45 Manual Depressur-BWR Submit evaluation on other 1/1/51 ization than ADS method for depressurization.
.9
S-Impl/ Doc
-l}?.em Title Applicability Specific Requirement Subm Due Dates II I'. D. 3. 3
- Improved ~Inplant' ALL
- Have.available means to 1/1/81 Iodine,t nitoring.
accurately measure airborne radioiodine inplant during an accident.
111.0.3.4 Contrdi Room Habitability ALL
. a.
Submit control room 1/1/81 habitability evaluation in formation.
b.
Submit' mod i fications
-1/1/81 necessary to assure CR habitab'lity with a schedu',e for completion.
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