ML20236E386
| ML20236E386 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain |
| Issue date: | 04/07/1989 |
| From: | Warenbourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| P-89097, TAC-69264, NUDOCS 8904140364 | |
| Download: ML20236E386 (40) | |
Text
{{#Wiki_filter:_ _ _ - _ _ _ _ _ f ',.y s, h Public Service ~ ~ nh 2420 W. 26th Avenue,. Suite 1000, Denver, Colorado 80211 p i 1 April 7, 1989 Fort St. Vrain Unit No. 1 P-89097 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk hE-[."'"" l Washington, D.C. 20555 !h l3
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Docket No. 50-267 y=y' ! E".-1"'
SUBJECT:
REQUEST FOR ADDITIONAL i E=,".'"' INFORMATION - SLRDIS AND !!Ed. 2 LER 87-020 FrE92~ t--
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REFERENCE:
- 1) PSC Letter, Warembourg s
to Document Control pq/b Desk, Dated November C,.., (,C) 22, 1988 (P-88414)
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- 2) NRC Letter, Heitner to Williams, Dated September 20, 1988 (G-88398)
- 3) NRC Letter, Heitner to Williams, Dated January 12, 1989 (G-89013)
Gentlemen: Public Service Company of Colorado (PSC) submitted in Reference 1 the results of a Failure Modes and Effects Analysis (FMEA) performed on the interactions of the Plant Protective System (PPS), the Steam Line Rupture Detection / Isolation System (SLRDIS) and the normal plant control system to address NRC con erns documented in Reference 2. The NRC staff submitted, in Reference 3, an initial Safety Evaluation in response to PSC's submitted FMEA. The initial Safety Evaluation concluded that the NRC's concerns previously identified were still i considered open and therefore additional infonnation was being requested. 7 701/40 %
P-89097-Page 2 April 7, 1989 . Telephone conferences were held on' January 30, 1989 and February 15, 1989 with Mr. Ken Heitner of the NRC staff and PSC personnel to -further ' discuss the open concerns and the request for additional information. In the latter conference call, Mr. Ken Heitner requested that PSC submit additional drawings for the specific valves .(variable valves) identified in the. initial Safety Evaluation and confirmation of the ' valves' failure mode-for a common mode failure such as loss of control power. PSC hereby submits in Attachment I the requested drawings and confirmation of the loss of electrical control power. failure mode for'- the specified valves. .In addition, PSC provides the NRC requested confirmation of the closure of the reheater inlet attemperator line block and flow. control valves as a result of a SLRDIS actuation. Should you have any questions on this matter, please contact Mr. M. H. Holmes at (303) 480-6960. Very truly yours, /0 TY ' WWW D. W. Warembourg, Managet Nuclear Engineering Division DWW/JCS:tmk Attachment cc: Regional Administrator, Region IV Attn: Mr. T. F. Westerman, Chief Projects Section B Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain 1
Attachment I to P-89097 Page 1 L Recuest ' for Additional Information - SLRDIS Interactions and failure Moces and Effects Analysis. NRC Request 1: Section 2.5 of the initial Safety Evaluation (See Reference 3 in the Cover Letter) documented the following NRC request for confirmation: The staff notes that System Description-93-2, entitled "Overall Plant Control and Plant Protective System" states that on the trip of both circulators in a loop results in closure of the reheater inlet attemporator line block and flow control valves. It is the staff's understanding that the attemporator inlet lines are small, and therefore the closure of these valves by SLRDIS is not required to mitigate the effects of a line break. However, the staff would appreciate a confirmation of the role of these valves in the operation of the SLRDIS system. PSC Response: Reheater attemperator bicek valves HV-22133 and HV-22134 and reheater inlet attemperator line controi vaives FV-22119 and FV-22120 are valves associated with the circul6 tor trip function of the Plant .) Protective System. The circulator trip logic provides a close signal to the loop associated valves upon the trip of both circulators in the loop. SLRDIS, as discussed in FSAR sections 7.1.2.6 and 7.3.10 l and in LC0 4.4.1 of the Technical Specifications, is a circulator trip parameter. An actuation of SLRDIS results in tripping both circulators in each loop. The resultant closure of the above valves would be accomplished via the existing PPS circuitry upon SLRDIS actuation. The closure of these valves are normal PPS functions and their closure is not required for isolation of any postulated HELB scenario. _m_m.___.____ _________-._.-_-____m_______
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to P-89097 Page 2 NRC Request 2: As discussed in the February 15, 1989 telephone conference, Mr. Ken Heitner of the NRC, requested that PSC submit the valve control schematics for the valves specified in Section 2.1 of the-initial Safety Evaluation (See Reference 3 in the Cover Letter) and provide confirmation of the valves'. failure mode for a common mode failure such as a loss of electrical control power. The valves specified in Section 2.1 are the: o circulator speed controls o feedwater flow controls o reheat steam bypass pressure ratio control PSC Response'2: A discussion o f. each of the above specified valves, in additiori to the Superheater Steam Bypass valves (PV-2243 and PV-2244), is provided in the following pages. Each discussion identifies the applicable reference drawings and includes a brief discussion of the PPS/SLRDIS/ Plant Control System operation. An evaluation discussion is also provided for a loss of control power scenario. A summary table is also provided for all of the SLRDIS valves. Included'in this table are the valve failure modes for loss of hydraulic power and loss of instrument air, as applicable. The Hydraulic System is included in the FSV Environmental Qualification Program. The system utilizes separate hydraulic power units for Loop 1 and Loop 2. Two of the three hydraulic pumps in each hydraulic power unit normally operates (one pump in standby) to supply valve actuators and to maintain the accumulators charged. The accumulators are sized to meet the maximum simultaneous valve actuator demand. The Instrument Air System is also included in the FSV Environmental Qualification Program. The system utilizes three air compressors (one associated with each loop and a standby compressor that can be aligned to either loop) redundant air receivers, and two headers to operate valves which are equipped with dual solenoids, each powered from a different instrument bus. Both the Hydraulic and Instrument Air Systems are designed to be single active failure proof. contains the requested schematic drawings for the specified valves for one loop. Also included for your information are the applicable loop shutdown and circulator trip drawings of the Plant Protective System. e
Attachment I to P-89097 Page 3 Valve No. FV-2205 (FV-2206) Loop 1 (Loop 2) Feedwater Flow Control [alves Schematic Diagram: FV-2205; E-1203 pg 454, pg 1620, pg 1621, { pg 1864, pg 1868 l FV-2206; E-1203 pg 455, pg 1620, pg 1621, pg 1864, pg 1869 P&I Diagram FV-2205; PI-22-1, PI-91-1, PI-91-4 FV-2206; PI-22-6, PI-91-2, PI-91-4 IB Diagram: FV-2205, FV-2206; 15-93-7 sht lof3 & sht Sof3 Control System Operation o Normal Plant Operation (Loop 1, Loop 2 similar) (E-1203 pg 1620, pg 1621, pg 1864, pg 1868) The feedwater flow control valve FV-2205 is hydraulically operated and controls the flow of feedwater to the main section of the Loop 1 Steam Generators. The control signal to FV-2205 is generated by Flow Controller FC-2205. The Flow Controller receives process input from the High Selector, FM-2205-2, which selects and transmits the higher of two redundant differential pressure inputs from Flow Transmitters FT-2205 and FT-2207. Feedwater flow is then controlled automatically via FC-2205 by comparing this process signal to the remote generated programmed setpoint which is developed utilizing throttle pressure and 1st stage pressure inputs. Following a Reactor or Turbine trip, the Feedwater Program remote setpoint is disconnected and feedwater flow is automatically ramped to 25% at a rate of one-half percent per second. In the case where Loop 2 is out of service (Loop Trouble Trip) the lower limit on Feedwater Flow is increased from 25% to 50%. o Plant Protective System (PPS) Input to Feedwater Control (E-1203 pg, 454, pg 455) The PPS will automatically close the FV-2205 valve via the Loop Trouble Trip Logic utilizing the electrically actuated hydraulic solenoids mounted on the valve body via contact input from XCR 93161-1A which operates CR161-1A. The Loop Trouble Trip Logic is developed with 1st in with lockout which precludes the isolation of feedwater on Loop 2. Loop 2 Feedwater Flow low limit is automatically ramped from 26% to 50%. 1
to P-89097 Page 4 o Steam Line Rupture Detection Isolation System (SLRDIS) Input to Feedwater Control (E-1203 pg 454, pg 455) The SLRDIS will automatically close the FV-2205 and FV-2206 valves simultaneously upon a SLRDIS actuation via additional redundant control relay contacts added to the-Steam / Water Dump and PPS Control Logic. These new SLRDIS contacts are wired in the valve control circuit so as to bypass the loop dependent Steam / Water Dump and Loop Trouble Trip Logic by providing power to the solenoids mounted on the valve. Evaluation of Loss of Power o Blown-Fuse (F5) pg 454 If ESSB1 power was lost to the FV-2205 PPS/SLRDIS control circuit due to Fuse F5 opening and SLRDIS actuated, the following would occur: A. If the SLRDIS input to the Circulator Trip Logic locked in a Loop 2 Trouble Trip, the FV-2205 would position, via servo input from the normal control circuit, to 25% open. B. If the SLRDIS input to the Circulator Trip Logic locked in a Loop 2 Trouble Trip, the FV-2205 would position, via servo input from the normal control circuit, to 50% open. For either case A or B above, the overall SLRDIS objective is achieved since the Feedwater Isolation Valve HV-2201, powered from ESSB2, would close and the Emergency Feedwater Isolation Valve HV-2203, powered separately from ESSB1, would also close. j o Loss of Essential Instrument Bus No. 1 If the entire ESSB1 power was lost due to any reason, and SLRDIS actuated, the following would occur: A. FV-2205 would fail as-is with the potential to drift either to the open or closed position. B. HV-2201 would be actuated full closed since it's powered from ESSP2. C. HV-2203 would fail closed since the solenoids on this valve require power to open valve HV-2203 (ETO) and the circuit is supplied power from ESSB1. As indicated above, the overall SLRDIS objective is achieved. /
l l-l to P-89097 Page 5 Valve No. PV-2229 (PV-2230) Loop 1 (Loop 2) Superheater Steam Bypass Valves Schematic Diagram: PV-2229, PV-2230; E-1203 pg 1915, pg 1915A P&I Diagram: PV-2229, PV-2230; PI-22-2 IB Diagram: PV-2229, PV-2230; IB-93-7 sht lof3 & sht Sof3 Control System Operation o Normal Plant Operation (Loop 1, Loop 2 similar) (E-1203, pg 1915,' pg 1915A) PV-2229 .is utilized' to maintain main steam bypass header pressure. The valve is positioned via a servo valve on the normally closed hydraulic valve, it is operated to open the bypass valve when steam header pressure is above 2550 psig. o Steam Line Rupture Detection Isolation System (SLRDIS) Input to Superheater Steam Bypass (E-1203, pg 1915) PV-2229 will automatically close for a SLRDIS actuation. Redundant Loop A & Loop B SLRDIS relay contacts open the normal input. wiring and provide a zero input to the valve position card and the valve will close. Evaluation of Loss of Power o Loss of Power to Instrument Rack I-35A or Total Loss of Essential Instrument Bus No. 1 PV-2229 would fail as-is with the potential to drift either to the open or closed position. This SLRDIS valve was considered to fail open as the object of a / single active failure in the HELB accident scenario development. i
=- -. 1 to P-89097 Page 6 Valve-No. SV-2105, SV-2111 (SV-2106, SV-2112) Loop 1 (Loop 2) [irculatorSpeedControlValves 1 Schematic Diagram: SV-2105; E-1203 pg 411, pg 1854 { SV-2106; E-1203 pg 412, pg 1855 ) SV-2111; E-1203 pg 413, pg 1854 SV-2112; E-1203 pg 414, pg 1855 P&I Diagram SV-2105, SV-2111; PI-22-3, PI-91-1, PI-91-4 SV-2106, SV-2112; PI-22-8, PI-91-1, PI-91-4 IB Diagram SV-2105,SV-2106,SV-2111,SV-2112, IB-93-8 sht1 i Control System Operation o Normal Plant Operation (Loop 1, Loop 2 similar) (E-1203 pg 1854, pg 1855) The circulator speed valves are used to control steam flow through the circulator turbines when the circulators are being steam driven. The solenoids are de-energized when the circulators are being driven by steam. o Plant Protective System (PPS) Input to Circ Speed Control (E-1203 pg 411, pg 412, pg 413, pg 414) The solenoid valves are energized in pairs for a PPS Circulator Trip via PPS Logic XCRs. Energizing either pair of solenoid valves will close the control valve. o Steam Line Rupture Detection Isolation System (SLRDIS) Input to Circulator Speed Control (E-1203 pg 411, pg (12, pg 413, pg 414) The solenoid valves are energized in pairs for a FLRDIS actuation via existing Loop A and Loop B PPS Circulator Trip Logic XCRs. Energizing either pair of solenoid valves will close the control valve. Evaluation of Loss of Power o Loss of Fuse or Essential Bus The speed valve will still close on loss of either instrument bus / because redundant solenoids are connected to both instrument essential Bus No. I and 2.
to P-89097 Page 7 Valve No. PV-2243 (PV-2244) Loop 1 (Loop 2) Circulator Steam Turbine Pressure Control Valve Schematic Diagram: PV-2243; E-1203 pg 1921 PV-2244; E-1203, pg 1922 P&I Diagram: PV-2243; PI-22-3 PV-2244; PI-22-8 IB Diagram: PV-2243, PV-2244; 18-93-7 sht lof3 & sht 30f3 Control System Operation o Normal Plant Operation (Loop 1, Loop 2 similar) (E-1203, pg 1921, pg 1922) PV-2243 is utilized to maintain a circulator steam turbine upstream to downstream pressure ratio of approximately 1.3 in order to aid circulator speed control. The valve is positioned via a servo valve receiving inputs from a pressure transmitter. o Steam Line Rupture Detection Isolation System (SLRDIS) Input to Circulator Steam Turbine Control (E-1203, pg 1921, pg 1922) PV-2243 valve will automatically close for a SLRDIS actuation. Redundant Loop A and loop B SLRDIS relay contacts open the normal input wiring and provide a zero input to the valve position card and the valve will close. Evaluation of Loss of Power o Loss of Power to Instrument Rack I-35A or Essential Instrument Bus No. 1 If power was lost to Instrument Rack I-35A, for any reason, valve PV-2243 would fail as-is with the potential to drift either to the open or closed position. The overall SLRDIS objective is achieved since the Cold Reheat v Bypass Block Valve, HV-2241 would be actuated full closed by SLRDIS since it receives redundant Essential Bus 1 and 2 power. 4 m_ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _.. _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ - _ _. _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _
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