ML19345F254
| ML19345F254 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 02/04/1981 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | John Miller Office of Nuclear Reactor Regulation |
| References | |
| P-81042, NUDOCS 8102170037 | |
| Download: ML19345F254 (3) | |
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,s Fort St. Vrain Unit No. 1 P-81042 Mr. Jim Miller Special Projects U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Docket No. 50-267 J
SUBJECT:
Fort St. Vrain Unit No. 1 Scheduled Refueling
Dear Mr. Miller:
As we indicated to you during the onsite meeting on January 26, 1981, and during the ACRS subcommittee meeting on January 27, 1981, it is our intent to shut down Fort Saint Vrain in early April for refueling. We also indicated that the refueling schedule of early April was dependent on our ability to consume the Cycle II fuel (200 EFPD), and was limited somewhat by the Technical Specification surveillance test intervals.
We are continuously evaluating plant operation for consumption of Cycle II, and it appears that with the many uncertainties of operating above - 70*;
power, the uncertainties of the power levels we will actually achieve after the release to test above 70P. power as well as plant operations prior to the release above 70*J power, we may not be in a position to refuel in early April, and may have to extend the schedule refueling start date in order to realize a maximum benefit from Cycle II operation.
Recognizing that we could be in a position to refuel as early as April 3, 1981, we are attemtping to define the late start date for refueling, which must necessarily be dictated by the Technical Specification test interval.
On this basis we have determined that the surveillance tests on the following page require plant shutdown conditions to perform the tests.
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Next Sched***
Dates Test For Completion Date For Surveillance Test Descriotion Peformed Per rech Specs Completion
- 1. SR5.3.4 SA/
Safe Shutdown 9-26-80 5-26-81 8-28-81 5.3.3 c-A Cooling Valve 3-4-80 Test 9-19-79 (Semi-Annual)
- 2. SRS.6.lb-SA Loss of Outside 9-27-80 5-27-81 8-28-81 Electric Power 3-21-80
& Turbine Trip 9-5-79 a
(Semi-Annual)
- 3. SR5.6.2c-A Station Battery 2-20-80*
5-21-81 2-20-82 Check (Annual) 5-17-79
- 4. SR5.4.1.1.10CR Circulator Inlet 2-15-80*
5-15-81 2-15-82 Temp. Scram 7-18-79 Calibr. (Annual)
- 5. SR5.4.1.3.1dR Circulator Speed 2-25-80*
5-25-81 2-25-82 Steam Water 3-31-79 Calibration Tests were performed earlier than required as a part of the circulator change out activities in Jan/Feb 1980.
i This date assumes the fully extended test interval permitted by Technical Specifications (i.e., normal test interval 125%).
Although the dates for the Technical Specification test interval will be extended to the limit permitted by Technical-j Specifications, the next scheduled test would continue to be based on a frequency dictated by the normal scheduled date (i.e.,
6 months or 12 months after the normal-scheduled date rather than 6 months or 12 months after the extended date).
Test Items 1 and 2 above must be done on a semi-annual basis, but the window in which these tests can be done is given by the Technical Specification and no sooner than every four (4) months and no later than every eight (8) months. Based on the fact that these tests were last completed on September 26 and September 27, 1980, and taking the full eight (8) month' interval allowed by the Technical Specification the latest -due date to complete these tests or have the reactor below 2% power is May 26 and May 27, 1981, respectively.
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For test Items 3, 4 and 5, these tests were completed during the circulator outage in January and February,1980 (specifically on February 20, February 15, and February 25, 1980, respectively).
Taking credit for the 125's allowed by Technical Specifications for completion of these surveillance tests and applying this to an annual test frequency the latest due dates to complete these tests or have the reactor below 2?; powar are May 21, May 15, and May 25, 1980, respectively.
4 In accordance with our interpretation of the Technical Specifications we feel that we could operate the reactor in compliance with Technical Specifications over the extended period allowed by the Technical Specifications provided that the reactor is below 2". power on or before May 15, 1981 (the most restrictive date listed).
On this basis, we would propose that the date for starting refueling be established as any time period between April 3, and May 15, 1981, with the provision that the reactor be below 2?e power on or before May 15, 1981, and that the five surveillance tests be satisfactorily completed prior to i
returning the reactor to a power level above 2?;. The additional provision that exists is that the future scheduling of these tests be based on the normal schedule interval established prior to extending the test period as indicated in the preceding tabulation.
We believe that operation of the plant as outlined above is within the confines of the Technical Specification to the health and safety of the public.
We would appreciate your review of this position and if you are in disagreement or have any comments please let us know as soon as possible.
If you are in general agreement please let us know at your earliest convenience so that we may consider this letter as our official notification that the scheduled refueling start date for Cycle III is-an I
early date of April 3, 1981, and a late date of May 15, 1981.
Very truly your:,
W Don W. Wa & m
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rembourg f
Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station DWW/dkm
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