ML17054A826
| ML17054A826 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/12/1984 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | NIAGARA MOHAWK POWER CORP. |
| Shared Package | |
| ML17054A827 | List: |
| References | |
| GL-82-33, NUDOCS 8406250263 | |
| Download: ML17054A826 (12) | |
Text
7590-01 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of NIAGARA MOHAWK POWER CORPORATION (Nine Mile Point Nuclear Station,
)
Unit No. 1)
)
Docket No. 50-220 ORDER CONFIRMING LICENSEE COMMITMENTS N
G PN P
LI The Niagara Mohawk Power Corporation (the licensee) is the holder of Facility Operating License No.
DPR-63 which authorizes the operation of the Nine Mile Point Nuclear Station, Unit No.
1 (the facility) at steady-state power levels not in excess of 1850 megawatts thermal.
The facility is a
boiling water reactor (BWR) located at the licensee's site in Oswego
- County, New York.
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 and significant upgradi ng of emergency response capability based on the experience from the accident at TMI-2 and the official studies and i nvestigations of the accident.
The requi rements are set forth in NUREG-0737, "Clarification of TMI Action Plan Requirements,"
and in Supplement 1 to NUREG-0737, "Requirements for Emergency
Response
Capability,"
Among these requi rements 840b2502b3 840b12 PDR ADOCK 05000220 i
I F
7590-01 are a number of items consisting of emergency response facility operability,
, emergency procedure implementation, addition of instrumentation, possible control room design modifications, and specific information to be submitted.
On December 17, 1982, a letter (Generic Letter 82-33) was sent to all licensees of operating reactors, applicants for operating licenses, and holders of construction permits enclosing Supplement 1 to NUREG-0737.
In this letter operating reactor licensees and holders of construction permits were requested to furnish the following information, pursuant to 10 CFR 50.54(f),
no later than April 15, 1983:
(1)
A proposed schedule for completing each of the basic requirements for the items identified in Supplement 1
to NUREG-0737, and (2)
A description of plans for phased implementation and inte-gration of emergency response activities including training.
Niagara Mohawk responded to Generic Letter 82-33 by letter dated April 15, 1983.
By letter dated July 7, 1983, Niagara Mohawk modified a date as a result of negotiations with the NRC staff.
By letter dated September 30,
- 1983, Niagara Mohawk provided a firm completion date for the final summary report and schedule for the detailed control room design review.
In these submittals, Niagara Mohawk made commitments to complete the basic requirements.
By letter dated February I, 1984, Niagara Mohawk provided the following:
firm completion dates for the fully operational Safety Parameter Display System and Emergency Operations Facility; informed the NRC the Operational Support Center is fully functional; and committed to providi ng a firm
7590-01 completion date for the Technical Support Center by Hay I, 1984.
The attached Table summarizing Niagara Mohawk's schedular commitments or status was developed by the NRC staff from the Generic Letter and the information provided by the licensee.
Niagara Mohawk's commitments inc1ude (1) dates for providing required submittals to the NRC, (2) dates for implementing certain requirements, and (3) a schedule for providing implementation dates for other requirements.
These latter implementation dates will be reviewed, negotiated and confirmed by a subsequent order.
1 The NRC staff reviewed Niagara Mohawk's April 15, 1983 letter and entered into negotiations with the licensee regarding schedules for meeting the requi re-ments of Supplement 1 to NUREG-0737.
As a result of these negotiations, the licensee modified certain dates by letters dated July 7 and September 30, 1983 and February 1, 1984.
The NRC staff finds that the modified datesare reasonable, achievable dates for meeting the Commission requirements.
The NRC staff concludes that the schedule proposed by the licensee will provide timely upgrading of the licensee's emergency response capability.
In view of the foregoing, I have determined that the implementation of Niagara Mohawk's commitments are required in the interest of the public health and safety and should, therefore, be confirmed by an immediately effective Order.
IV.
Accordingly, pursuant to Sections 103, 16li, 16lo 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:
7590-01 Implement the specific items described in the Attachment to this ORDER in the manner described in Niagara Mohawk's submittals noted in Section III herein no later than the dates in the Attachment.
Extensions of time for completing these items may be granted by the Director, Division of Licensing, for good cause shown.
V.
The licensee may request a hearing on this Order within 20 days of the date of publication of this Order in the..Federal Register.
Any request for a hearing should be addressed to the Director, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555.
A copy should also be sent to the Executive Legal Director at the same address.
A REQUEST FOR HEARING SHALL NOT STAY THE IMMEDIATE EFFECTIVENESS OF THIS ORDER.
If a hearing is to be held, 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 the licensee should comply with the require-ments set forth in Section IV of this Order.
This Order is effective upon issuance.
OR THE NUCLEA REGULATORY COMMISSION
/
Darrell
. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Dated at Bethesda,
- Maryland, this 12 day of June, 1984.
Attachment:
Licensee's Commitments on Requirements Specified in Supplement 1 to NUREG-0737
Attachment page 1 of 2 C
LICENSEE'S COtdNITl1EHTS OH SUPPLEMENT 1
TO NUREG-0737 TITLE RENDU IREtfENT LICENSEE'S COHPLETIOH SCHEDULE OR STATUS 1.
Safety Parameter Display System (SPDS) la.
Submit a safety analysis and an implementation plan to the HRC.
lb.
SPDS 'fully operational and operators trained.
January 1,
1984 (Submi tted) 1986 Refueling Outage 2.
Detailed Control Room Design Review (DCRDR) 2a.
Submit a program plan. to the HRC.
2b.
Submit a
summary report to the HRC including a proposed schedule for implementation.
October 1, 1983 (submitted)
January 1,
1985 3.
Regulatory Guide 1.97-Application to Emergency
Response
Facilities 3a.
Submit a report to the HRC describing how the requirements of Supplement 1 to NUREG-0737 have been or will be met.
3b.
Implement (installation or upgrade) requirements.
April 1, 1984 (Submitted)
Compl ete
Attachment page 2 of 2 LICEHSEE'S COMMITMENTS OH SUPPLEMENT I TO NUREG-0737 TITLE REQUIREMENT LICENSEE'S COMPLETION SCHEDULE OR STATUS 4.
Upgrade Emergency Operating Procedures (EOPs) 4a.
Submit a Procedures Generation Package.'to the HRC.
4b.
Implement the upgraded EOPs.
March I, 1984 (Submi tted) 1986 Refueling Outage 5.
Emergency
Response
Facilities 5a.
Technical Support Center fully functional.
5b.
Operational Support Center fully functional.
Sc.
Emergency Operations Facility fully functional.
Submit a firm completion date by May 1, 1984-C Complete February 1, 1984 December 31, 1985 0
IIEET V