ML19269C872

Responds to NRC 790115 & 0122 Ltrs Requesting Info on Inservice Insp & Tech Spec Surveillance Planned for Upcoming Refueling Outage.Forwards List of Surveillances Planned. Confirms Three Surveillance Which Will Not Be Performed

ML19269C872
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/07/1979
From:	Justin Fuller PUBLIC SERVICE CO. OF COLORADO
To:	Speis T Office of Nuclear Reactor Regulation
References
P-79040, NUDOCS 7902200009
Download: ML19269C872 (5)

Text

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February 7, 1979 Fort St. Vrain Unit No. 1 P-79040 Mr. Themis P. Speis, Chief Advanced Reactors Branch Division of Project Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket #50-267

Subject:

Surveillance Activities First Refueling Gentlemen:

In your letter of January 15 and January 22, 1979, you requested infor-mation as to what in-service inspections and Technical Specification sur-veillances are being planned for the upcoming refueling outage. At the present time, our in-service inspection program is presentl:- defined by the Technical Specifications. In this respect, we have attached a listing of all Technical Specification surveillance activities which are presently planned for the refueling outage.

In addition to those surveillances listed, we had originally planned to perform those surveillance activities associated with the following:

1. SR 5.2.13 PCRV Concrete Permeability

2. SR 5.2.14 PCRV Liner Corrosion

3. SR 5.2.6 Plateout Probe Surveillance We have, however, requested relief from performing Items 1 and 2 above in our letter of January 26, 1979, (P-79028). We also discussed with you on February 5, 1979, the fact that we could not perform Item 3 because of the unexpected forced outage of unit on February 1, 1979, and our inability to remove the plateout probe in a time frame that would permit meaningful analyses. We received your verbal approval in our February 5 discussion to perform the plateout probe removal at a later date.

Other than the surveillance activities listed in the attachment and the inspection plan for Region 35 (See P-79026), we are not planning for any other special inspection activities, N

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Mr. Themis P. Speis February 7, 1979 Other inquiries contained in your letters of January 15 and January 22, 1979, have been or will be addressed in separate correspondence.

Very truly yours, dziE/d/,  ::

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J. K. Fuller, Vice President Engineering and Planning JKF/DDW:sc

Fort St. Vrain Unit No. 1 P-79040 SURVEILLANCES TO BE DONE DURING REFUELING OUTAGE SR Number Description 5.1.la-A Control Rod Scram Test 5.1. 2c-X Reserve Shutdown Assembly Functional Test 5.1. 2e-X Reserve Shutdown Hopper Pressure Switch Calibration 5.1.3-R Temperature Coefficient of Reactivity 5.1.5-R Control Rod Reactivity Worth 5.2.la-A PCRV Rupture Disc and Safety Valve Test

5. 2. lb-X Steam Cenerator and Circulator Penetration Safety Valve Test

5. 2. lC2- A PCRV Relief Valve Indicators Calibration and Functional Test 5.2.7a-A Circulator Operability Test on Water Turbine Drive 5.2.7b-A Water Turbine Safety Valves 5.2.9-A Helium Circulator Bearing Water Accumulator Calibra-tion 5.2.16b-A PCRV Closure Leakage Ir atrumentation Calibration

5. 2.17-X/ 5 . 2.18-X Helium Circulator Pelton Wheels / Helium Circulator 5.2.21a-SA IACM Pneumatically and Electrically Operated Valves Functional Test

5. 3.1-R Steam Water Dump Tank Level Indicators Calibration 5.3.2-A > Sin and Hot Reheat Steam Stop Check Valves Full Stroke Test 5.3.3-A Bypass and Safety Valves Test 5.3.4-SA Safe Shutdown Cooling Valves Tes t 5.3.5-A Hydraulic Power System Calibration 5.3.6-A Instrument Air System Calibration 5.3.8d-R Hydraulic Snubber Functional Test

Fort St. Vrain Unit No. 1 P-79040 SURVEILLANCES TO BE DONE DURING REFUELING OUTAGE (continued)

SR Number Description 5.4.1.1.3.c-R Startup Channel Scram Calibration

5. 4 .1.1. 4. d-R/

5.4.1.4.2.d-R Linear Power Range Channel Calibration 5.4.1.1.5.d-R/

5.4.1.4.3.d-R Wide Range Power Channel Scram Calibration 5.4.1.1.6.c-R Primary Coolant Moisture Scram Calibration 5.4.1.1.8.c-R Reheat Steam Tempera ture Scram Calibration 5.4.1.1.9.c-R Primary Coolant Pressure Scram Calibration 5.4.1.1.10.c-R Circulator Inlet Temperature Scram Calibration 5.4.1.1.ll.b-R Hot Reheat Header Pressure Scram Calibration 5.4.1.1.12.b-R Main Steam Pressure Scram Calibration 5.4.1.1.13.b-R Two Loop Trouble Scram Test 5.4.1.1.15.c-R High Reactor Building Temperature (Pipe Cavity)

Scram Calibration 5.4.1.2.1.h-R S team Pipe Rupture (Pipe Cavity) Calibra tion 5.4.1.2.1.1-R Steam Pipe Rupture (Pipe Cavity) Calibration 5.4.1.2.1.j-R Steam Pipe Rupture (Pipe Cavity) Calibration 5.4.1.2.2.h-R Steam Pipe Rupture (Under PCRV) Calibration 5.4.1.2.2.1-R Steam Pipe Rupture (Under PCRV) Calibration

5. 4.1. 2. 2. j-R Steam Pipe Rupture (Under PCRV) Calibration

5. 4.1. 2. 3.b-R Circulator lA and 1B Tripped Test 5.4.1.2.4.b-R Circulator 1C and ID Tripped Test 5.4.1.2.5.c-R S team Generator Penetration Pressure Calibra cion 5.4.1.2.6.c-R Reheat Header Activity Calibration

5. 4.1. 2. 7. d-R Superheat Header Temperature Calibra tion

Fort St. Vrain Unit No. 1 P-7 904 0

. SURVEILLANCES TO BE DONE DURING REFUELING OUTAGE (continued)

SR Number Description

5. 4.1. 3.1. d-R Circulator Speed (Steam and Water) Calibration 5.4.1.3.2.d-R Feedwater Flow Calibration 5.4.1.3.3.c-R Circulator Bearing Water Pressure Calibration 5.4.1.3.4.c-R Circulator Penetration Pressure Calibration

5. 4.1. 3. 5. c-R Circulator Drain Pressure Calibration 5.4.1.3.6.c-R Circulator Seal Malfunction Calibration 5.4.1.3.7.a-R Circulator Trip (Manual) Test

5. 4.1. 4. 4. b-R Multiple Rod Pair Withdrawal Check 5.4.3-A Core Region Outlet Temperature Instrumentation Calibration 5.4.4-A2 PCRV Cooling Water System Temperature Calibration 5.4.5-A2 PCRV Cooling Water Flow Scan Calibration 5.4.6-R Core Differential Pressure Indicator Calibration

5. 4 . 7- A Control Room Temperature Calibration 5.4.8-R Power to Flow Instrumentation Calibration 5.4.12-R Analytic System Pricary Coolant Moisture Instru-mentation 5.5.1-A Reactor Building Sub-Atmospheric Instrumentation Calibration 5.5.2-Al Reactor Building Pressure Relief Device Calibration 5.5.3a-SA Reacto r Building Exhaus: Filters and Charcaol Filter Samples 5.5.3bc-A Reactor Plant Exhaust Filters Charcoal Filter Halogenated Hydro. Removal and HEPA Leak Test 5.6.lb-SA Loss of Outside Power and Turbine Trip 5.6. led-A Standby Diesel Cencrator Calibration 5.6.2c-A Station and PPS Batteries Check 5.10.4a-A Fire Barrier Penetrations Seals Annual Inspection