ML20039E852
| ML20039E852 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/31/1981 |
| From: | Mayer L NORTHERN STATES POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-2.B.2, TASK-2.B.3, TASK-2.E.1.1, TASK-2.F.1, TASK-2.F.2, TASK-TM NUDOCS 8201110547 | |
| Download: ML20039E852 (4) | |
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Northern States Power Company
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414 Nicollet Matt Minneapohs, Mmnesota 55401 Telephone (612) 330 5500 December 31, 1982
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Director Of.
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' q ",71 i j f PP.AIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 50-306 DPR-60 Delay in Implementation of Post TMI Requirements In our letter dated December 33, 1980Property "Letter" (as page type) with input value "05000000/LER-1982-023-03, /03L-0:on 821121,containment Pressure Sensing Line Found Capped.Caused by Personnel Error.Units Will Be Labeled"December 33, 1980" contains a sequence that could not be interpreted against an available match matrix for date components." contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process. we committed to meet the implementa-tion date of January 1,1982 specified in NUREG-0737 for a number of post TMI requirements. The purpose of
.is letter is to inform the Commission of delays in the implementation of several of these January 1,1982 items and request an extension in the required completion date.
Following is a list of each of the items which will not be completed by January 1, 1982, the reasons for the delay, and a revised completion schedule.
II.B.1 and II.B.2 - Reactor Coolant System Vents and Design Review of Plant Shielding and Environmental Qualification - Unit 2 RCS Vents As noted in our December 30, 1980 letter, our plant shielding study (NUREG-0737, Item II.B.2) did not include the Chemical and Volume Control System. Use of the reactor coolant system vents (NUREG-0737, Item II.B.1) were aseumed for the letdown and degassing functions.
The reactor coolant system vents are now nearly complete in both Prairie Island units. This modification has a required implementation date of July 1,1982.
Control board wiring for Unit 2 vents remains to be completed, however.
A delay in the implementation date for II.B.1 and II.B.2 in the case of the Unit 2 reactor coolant system vents until the next refueling outage of Unit 2 is requested (presently scheduled for August, 1982) since the wiring should be done with the plant in a cold or refueling shutdown condition.
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Director of NRR December 31, 1982 Page II.B.2 and II.B.3 - Plant Shielding and Environmental Qualification and Post Accident Sampling Capability - Loop B Sample Valve Replacement The Unit 1 post accident sampling system is operational with environ-mentally qualified valves. The loop B sample valves for Unit 2, however, must still be replaced with fully qualified valves.
Replacement could not be done during the last Unit 2 refueling outage because of delivery problems. A delay in the implementation date for II.B.2 and II.B.3 in the case of the Unit 2 loop B sample valves until the next refueling outage of Unit 2 is requested. As previously noted, this outage is now scheduled for August, 1982. Valve replacement should be done with the plant in a cold or refueling shutdown condition.
II.E.1.1 - Auxiliary Feedwater System Evaluation As discussed in our letter dated November 24, 1981, NRC Staf review of our auxiliary feedwater system identified two modifications which should be made:
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Separation of cables for Unit 1 and Unit 2 condensate storage tank level indication and administrative controls on cross-tie valves b.
Suction protection for all pumps Recent discussione with members of the NRC Staff have further clarified these requirements and we are now proceeding with this work.
Because of the lead time required to obtain qualified pressure switches for item (b) above, and because this work should be performed with the affected unit in the cold or refueling shutdown condition, a delay in the Unplementation date for II.E.1.1 until the next refueling outage of each unit is requested. The next refueling outage of Unit 1 is now scheduled for November, 1982. As noted above, the next refueling outage of Unit 2 is now scheduled for August, 1982.
II.F.1.1 - Noble Gaa Monitors - Steam Relief Radioactivity Determination In our letter dated December 30, 1980 we committed to install a monitoring system for the steam generator power operated relief and safety valves by Janaary 1, 1982. We will be unable to meet that implementation date for the following reasons:
a.
One circuit board f ailed and is beir.g returned to the manufacturer, b.
Thirty-eight loops of instrumentation must be checked out.
NORTHERN CTRF8L POWER COMPANY, Director of NRR 1
December 31, 1982
.Page At this time it appears another sixty days are needed to complete this project. A delay in the implementation date for II.F.1.1 in the case of this system until March 1,1982 is therefore requested.
II.F.1.3 - Containment High Range Monitor Two monitors are installed in each containment building, however all cabling is not in place. Delivery of environmentally qualified cable has been a problem. Coax cable or'.ginally purchased did not pass qualification tests. Delivery o' qualified cable is expected by the end of the month and we believe installation can be completed within sixty days. A delay in ;he implementation date for II.F.1.3 until March 1,1982 is therefore requested.
II.F.1.4 - Containment Pressure Instrumentation This modification is complete in both units with the exception of some control board wiring and the installation of qualified recorders.
Delivery of the recorders is expected by the end of the year. Wiring can be completed within 30 days of receipt of the recorders. A delay in the implementation date for II.F.1.4 until February 1,1982 is therefore requested.
II.F.2 - Instrumentation for Detection of Inadequate Core Cooling -
Qualified Incore Thermocouples As discussed in our letter dated December 30, 1982 we are installing a qualified core exit thermocouple temperature measurement system in each unit. This system will provide a fully qualified reactor coolant temperature input to the subcooling meters.
Hardware installation in Unit 1 is complete, however all wiring cannot be completed until April, 1982. The Unit 2 system cannot be installed until the Unit 2 refueling outage now scheduled for August, 1982.
Subcoaling meters are now operational with qualified pressure instrument inputs and temperature inputs from the plant computer (an interim measure).
A delay in the implementation date for II.F.2 in the case of the core exit thermocouple system is requested until April 30, 1982 for Unit I and the next refueling outage for Unit 2 (August, 1982).
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. NORTHERN - CTATE'3 POWER COMPANY Director of NRR December 31, 1982 Page Please contact us if you have any questions related to this revised schedule for complying with post TMI NRC requirements.
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L 0 Mayer, PE Manager of Nuclear Support Services e
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Regional Director-III, NRC i
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