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Discusses Atmospheric Dump Valve Failures at Plant.Cause Still Under Investigation.Related Documentation Encl
	ML20127G512
Person / Time
Site:	Palo Verde
Issue date:	03/15/1989
From:	Marlone Davis; Office of Nuclear Reactor Regulation
To:	Miraglia F, Murley T, Sniezek J; NRC
Shared Package
ML20127G485	List: ML20127G480; ML20127G512; ML20127J296; ML20127J361; ML20127J386; ML20127J403; ML20127J416;
References
	FOIA-92-87 NUDOCS 9301210293
	Download: ML20127G512 (171)
	v • d • e

{{#Wiki_filter:_ .S .a /gb3 8tfGg 'o,j UNITED STATES 1 = p NUCLEAR REGULATORY COMMISSION. ,t WASHINGTON, D. C. 20555 k*...* March 15, 1989 Docket.No.- 50-528, 50-529 and 50-530 -MEMORANDUM FOR: T. Murley* B. Grimes P. McKee J. Sniezek* F. Congel A. Thadani-F. Miraglia, ADT* J. Roe C. McCracken S. Varga, ADP* C. Grimes J. Larkins D. Crutchfield,- ADSP* B. Boger W. Lanning G. Lainas E. Adensam T. Martin, EDO G. Holahan M. Virgilio Operations Ctr.** C. Rcesi L. Rubenstein F..Gillespie L. Shao B. D. Liaw W. Bateman L. Miller, RV** THRU: George W. Knighton,' Director f og, Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects FROM: Michael J. Davis, Project Manager Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects-

SUBJECT:

ATMOSPHERIC DUMP VALVE FAILURES-AT PALO VERDE (PALO VERDE UNITS 1, 2, AND 3) The atmospheric dump valves (ADV's) did not operate remotely during the Unit 3 load rejection event of. March 3, 1989. The cause is still under investigation. Unit 1, which is currently in Node 3, following a-' reactor trip on March 5,-1989, attempted to exercise ADV 184 on SG #1'last night __to prove operability. The test was-conducted using the nitrogen accumulator with the-normal instrument air supply isolated and vented. The licensee ~was unsuccessful in; opening ADV-184 with-incremental demand signals up to 50% on the handwheel controller.. Additional testing / troubleshooting is' planned for this evening. _ As-a result the licensee is commencing a rampdown of Palo Verde Unit 2 to ' Mode 3 to test ADV's. Resident inspectors and Region V personnel are_providing 24 hour coverage onsite. Wh M. Michael J. Da is, Project Manager i Project Directorate V. Division of Reactor Projects - III, IV, Y'and Special Projects cc: PD's 1 n \\ (bh - 9301210293 920828 k PDR-FOIA \\

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t CONTROLLED DOCUMENT 0< 3.0 controls, Instrumentation, and Alarms Objectives Describe, controls, instrumentation, and alarms used ( _' for Hain Steam System operation: i 1. List, from memory, alarm and trip setpoints 2. List system parameters that initiato automatic controls 3. Describe operation of the main steam isolation valves. The most important

controls, instrumentation, and altras associated with the Hain Steam System are located in the control room.

Instrumentation enables the control room operator to monitor system parameters. Controls and instrumentation available in the control room are shown in Figure PGS-1A-10. 3.1 Controls 3.1.1 Atmospheric Dump Valves Two, two-position (OPEN PERMISSIVE /CLOSE) control switches and one Foxboro control. station are provided in the control room for each atmospheric dump valve. The OPEN PERMISSIVE /CLOSE control switches each control one solenoid valve in the positioning air supply line (see Figure PGS-1A-5). When placed in the OPEN PERMISSIVE position, the associated solenoids are de-energized, isolating the vent port. When placed in the are energized, venting CLOSE position the associated solenoids the downstream positioning air supply line. Spring force then closes the atmospheric dump valve. The Foxboro control station (see Figure PGS-1A-11) allows the operator to control dump valve position. It provides an electrical control signal to the I/P converter which then applies a control air signal to the dump valve (Bailey) pneumatic positioner. The control station can be operated either in a manual or automatic mode. When the controller is in the automatic mode the green AUTO light: is illuminated, and l when in the manual mode the red MANUAL light is illuminated. PGS-1A-21 ~

CONTROLLED DOCUMENT J, valve opens. The associated accumulator is lined up to quickly close the HSIV. (It is not known when this feature should be used (later)). The two-position (SLOW OPEN/ SLOW CLOSE) switch is normally in a neutral position. When momentarily placed in the SLOW OPEN j position, the actuating system is lined up to open the HSIV using only discharge flow from the oil pump (i.e., the accumulator remains isolated) and the HSIV slowly moves in the open direction. When momentarily placed in the SLOW CLOSE position, the actuating system is lined up to close the HSIV using discharge flow from the oil pump, and the HSIV slowly moves in the close direction. . Valve motion in either direction is stopped through limit switch action when the valve reaches its full-opan/ closed positions. The ~ switch spring returns to a neutral position. The two-position (EX/ACC CH) switch is normally in a neutral position. When momentarily placed in the EX (exercise) C position, the actuating system is lined up to slowly close the HSIV using only discharge flow from the oil pump. When the ReIV reaches the 95% closed position, a limit switch causes the lineup to change and slowly open the valve to its fully open position. This is done periodically to ensure the HSIVs are operable. When momentarily placed in the ACC CH position, the actuator system is lined up to discharge the associated accumulator's contents to the hydraulic reservoir without causing MSIV movement. When momentarily dupressed, the FAST CLOSE pushbutton lines up the associated actuating system to quickly close the HSIV using the accumulator. Upon receipt of a MSIS, the HSIVs are all quickly closed by their associated accumulators. The actuating system line up following a MSIS is identical to the FAST CLOSE lineup _. Following a MSIS, the HSIVs can be overridden open by the ' control room operator. The SLOW CLOSE/ SLOW OPEN switch must ~ PGS-1A-23 4 w e---.

first bo coved to tho SLOV CLOSE 'and than to the SLOV OPEN [ position. When placed in the SLOV CLOSE position, c ' white override light will be illutninated. When placed in the SLOW OPEN position, the valve clowly opens as previously described. A logic diagram for these controls is shown in Figure PGS-1A-12. Red and green valve position indicating lights are provided for each HSIV. The red light is illuminated when the valve is fully open. The green light is illuminated when the valve, is fully closed, and both lights are illuminated when the valve is at an intermediate position. Blue lights are also provided to indicate when the valves,are in either the EX or ACC CH mode. 3.1.3 MSIV Bypass Valves

Two, two-position (OPEN/CLOSE) control switches are provided for each air-operated bypass valve.

Each switch controls one solenoid-operated three-way valve in the air supply line. Both solenoids must be closed (energized) to open the bypasa valve, and only one need be open (de-energized) to close the bypass valve. When momentarily placed in the OPEN position, the associated solenoid valve is aligned to supply air to the ( bypass valve actuator (if a MSIS is not present). When momentarily placed in the CLOSE

position, the associated __

solenoid valve is al,igned to vent the bypass valve's actuator to atmosphere and isolate the air supply. The switch spring returns to a neutral position. On receipt of a MSIS, the solenoids are automatically de-energized causing the bypass valves to close. Following automatic

closure, the control room operator can reopen the valves by momentarily moving their control switches to the CLOSE position and then to OPEN.

White override lights are illuminated when the switches are mov'ed to

CLOSE, indicating the valves can be overridden.

The solenoid valves are provided with red and green indicating lights in addition to" the white OVERRIDE light. The red lights ,5 PGS-1A-24 r

CONTROL. ED DOCUME MT are illuminated when t in va.vas ero anurg:.zod and thE grocn lights are illuminated when the valves are de-energized. i h 3.1.4 Main Steam Line Drain Valves Two, two-position (OPEN/CLOSE) control switches are provided in the control room for the steam line drain valves. The upstream to.in line valves (UV-31, -32, -33, and -34) are controlled by switch, and the downstream drain line valves (UV-35,, -36, -37, and -38) are controlled by the other switch. When momentarily placed in' the OPEN position, the valves' motor operators are energized, moving them in the open direction. j When momentarily placed in the CLOSE position, the motor operators are energized, moving them in the close direction. The control switches sp, ring return to a neutral position. The drain line valves all open upon receipt of a turbine trip signal. 1 Red and green lights are provided for valve position indication in the control room and at the associated MCCs. The red light is illuminated if the associated valves are fully open, and the k green light is illuminated if the valves are fully closed. Both lights are illuminated if the valves. are at an intermediate position. 3.1.5 Steam Trap Isolation Valve Control Means to isolate steaa traps (SGN-H01 through -H04, -H23. -H25) upstream of the HSIV's is om vided by two-position (OPEN/CLOSE) spring return control wit t, (

located in the control room.

When modentarily placed u the OPEN position, the valves' solenoid is energized, opening the valves. When momentarily placed in the CLOSE position, the valves' solenoid is de-energized, closing the valves. The control switches spring return to a neutral position. When in the neutral position, the valve automatically closes upon receipt of an HSIS condition. Following automatic closing, the control room operator can open the valve by moving the control switch to CLOSE and then to OPEN. When moved to PGS-1A-25

4 0 PEN, a white OVERRIDE light illuminatos indiccting ths valvo ( can be overridden. ( In addition to the white OVERRIDE light, red and green position [ indicating lights are provided for each steam trap isolation valve or set of isolation valves. The red light is illuminated when the valve is fully open; the green light is illuminated when the valve is fully closed. Both lights are illuminated when the valve is at an intermediate position. 3.1.6 Auxiliary Feedpump (Train A) Steam Supply Valven. A two-position (OPEN/CLOSE) control switch is provided for each valve (UV-134, ~138) in the control room and remotu shutdown panel. When the switch for valve UV-134 (supply from No. 1 steam generator) is momentarily placed in the OPEN position, the valves's motor operator is energized, moving it in the open direction. When the switch is momentarily placed in the CLOSE position, the valve will close tinless an AFAS-1 is present. The switch spring returns to a neutral position. When in the neutral position, the valve automatically opens upon ' receipt of ( ( an AFAS-1. Following automatic

opening, the control room operavr can close the valve by moving the control switch to OF% %i then to CLOSE.

When moved' to OPEN a white OVERRIDE lighe uiuminates indicating the valve can be overridden. When the switch for valve UV-138 (supply from No. 2 oteam generator) is momentarily placed in the OPEN position, the valvt's motor operator fa energized, moving it in - the OPEN direction unless an AFAS-1 is present. When the switch is momentarily placed in the CLOSE position, the valve closes unless an AFAS-2 is present. The switch spring returns to a neutral position. When in the neutral position, the valve automatically opens upon receipt of an AFAS-2.

the valve automatically closes if an AFAS-1 is received after the AFAS-2 to provent both steam generators from supplying steam simultaneously.

Following automatic opening, the control' room operator can close the valve by moving the control switch to PGS-1A-26 ~

_ ~., -+ 1, [ [' 6.4.3 Shutdown Cooling (Residual Heat Removal) System The design of the shutdown cooling system is within the CESSAR scope, and the staff's evaluation of this system is found in Section 5.4.3 of the CESSAR SER. A number of interface criteria are established in the CESSAR document, for elements of the shutdown cooling system which are within the BOP scope. The applicant has satisfactorily demonstrated compliance with these interface criteria in Section 5.4.7.2 of the PVNGS FSAR. In the CESSAR SER, the staff indicated a number of areas where additional information or action would be required of all applicants referencing the CESSAR document. This material, as it relates to the PVNGS application, is presented below. The staff's evaluation of CESSAR requires that each applicant referencing that document must demonstrate that the SDCS is housed in a structure which is designed to withstand tornadoes, floods and seismic phenomena in accordance with GDC 2. In Section 5.4.7.2 af the FSAR, the applicant has demonstrated that all components of the SDCS are located in Seismic Category I structures in accordance with RG 1.29 and 1.48. The protection of these structures against natural phenomena such as flood, tornado or high winds is demonstrated in Section 3.3 and 3.4 of the PVNGS FSAR. The acceptability of these sections is dircussed in Section 3 of this report. Applicants for multiple unit sites are required to demonstrate that there are no shared systems between the units, in conformance with GDC 5. The shutdown cooling systems of PVNGS 1-3 contain no shared components and, therefore, are in compliance with GDC 5. The applicant must demonstrate the adequacy of power supplies to the shutdown cooling system suction isolation valves. The applicant has demonstrated that the four suction isolation valves and two low pressure barrier valves are powered in such a way that a fault in one power supply or valve will neither line up the RCS to either of the two SDCS trains inadvertently nor prevent the initiation of shutdown cooling with at least one train. This is accomplished-through the use of four independent power trains; the two diesel trains, plus two independent safety grade battery sources. This meets staff requirements as specified in the CESSAR SER. The steam generator atmospheric relief valves are supplied as part of the balance of plant. These valves are air operated and normally are actuated by the plant's instrument air system, which is non-seismic. The staff' requested the applicant to demonstrate that these valves, which are needed for shutdown, -would be available following an SSE, The applicant complied with this request by showing that PVNGS 1-3 provides,-as a backup to the instrument air systes, safety grade nitrogen accumulators to operate the steam generator atmospheric dump valves. These accumulators, one per SG, provide a nitrogen supply for_3 - C , 8 hours of operation of the valves.these accumulators, the staff will requir In order to demonstrate the adequacy of [ff'acooldownwiththeinstrumentairsystemisolatedfromthesevalves.The applicant must commit to these tests prior to fuel loading. Additioncily, when the C-E Owners Group effort on providing guidelines for natural circulation 4 f l Palo Verde SER 5-13 I ~ ~ " ' "

A. ~h -Q C Accoidown without voiding are completed, the-staff will require the applicant to reevaluate the acceptability of the siili@~of the"61,trogen accuniators. ]/2.) lThe applicant has committed to this.. a In the staff evaluation of the shutdown cooling system for CESSAR, the staff identified a deficiency in the makeup and boration portion of the system. The design did not enable the plant operators to shutdown from the control room, if offsite power is unavailable. For this postulated loss of offsite power, a minimum of two manual valves must be operated in the auxiliary building to i provide an open gravity feedline from the RW to the charging pumps suction. d This is not in accordance with BTP RSB 5-1. As discussed in the CESSAR SER, / C-E made a commitment to provide a method for re.notely operating from the C control room those valves needed for shutdown. $The staff will confirm that (//l PVNGS 1-3 implements this design change. ~ The CESSAR SER reports that each applicant must provide individual control room low flow alarms for each LPI pump, which provide assurance that problems with pump suction or discharge paths will be identified, and corrective action taken prior to pump damage. In response to a staff request, the applicant stated that low flow alarms (audible and visual) are provided in the control room. This meets staff requirements, pending confirmation that these alarms j , are powered from emergency power sources. The applicant was asked to provide information related to pipe breaks or leaks in high-or moderate-energy lines outside containment associated with the SDCS system when the plant is in shutdown cooling mode. The applicant reported that the maximum credible leak (in accordance with BTP MEB 3-1) is a 2.375 in.2 crack in the shutdown cooling heat exchanger discharge line. This provides a maximum discharge rate of 990 gpm. The applicant demonstrated that sump alarms are provided to promptly identify the faulted train and allow for its isolation. The applicant has demonstrated that'30 minutes is available to isolate the leak, before flooding of essential equipment needed for shutdown is predicted to occur. With respect to maintaining core cooling, assuming no operator action for 30 minutes even at this maximum discharge rate, there would be no adverse effect on core cooling as the redundant train can provide full heat removal capability. In addition, sufficient RCS inventory will exist, as the water level will be above the midpoint of the RCS hot leg. This meets the staff requirements specified in the CESSAR SER. The staff review of the PVNGS 1-3 application indicates that the applicant has satisfactorily met the CESSAR interface requirements and has provided the additional information specified in the staff's CESSAR SER, with the exceptions noted above. With the successful resolution of these issues, which are sum-marized below, the staff finds the PVNGS 1-3 shutdown cooling system to be acceptable, as it meets Commission regulations as described in the CESSAR SER. The resolution of the following issues will be discussed in a supplement to _ this SER: '" ~ 1. The applicant must commit to a test during the startup test program, which includes a cooldown with the instrument air system isolated from the steam 6 generator atmospheric relief valves. This test is to verify that the safety grade nitrogen accumulators hold sufficent vo M e to bring the plant from Palo Verde SER 5-14

,j f L il power generation. The steam produced in the two steam generators is routed by four main steam lines up to the common header at the high pressure turbine. a Each main steam line contains one main steam isolation valve (MSIV). The ~ portions of the main steam lines from the steam generators through the con-tainment, and up to and including the main steam isolation valves and including the main steam safety valves and atmospheric dump valves, are located in the flood and tornado protected main steam support structure (refer to Sections 3.4.1 and 3.5.2 of this SER) and are Quality Group B and seismic Category I, thereby satisfying the requirements of GDC 2, " Design Bases for Protection Against Natural Phenomena," and the guidelines of RG 1.26, " Quality Group Classifications and Standards for Water, Steam, and Radioactive Waste-Containing Components for Nuclear Power Plants," and RG 1.29, " Seismic Design Classification." The main steam isolation valves are designed to close in a maximum of five seconds upon receipt of a main steam isolation signal (MSIS). The valves are designed to stop steam flow from either direction. Failure of one main steam isolation valve to close coincident with a steam line break will not result in the uncontrolled blowdown of more than one steam generator. In the event of a steam line break upstream of a main steam isolation valve and a failure of a main steam isolation valve to close on the unaffected steam generator, blowdown of the unaffected steam generator through the break is prevented by the closure of the HSIVs for the affected steam generator. Blowdown through the turbine and condenser is prevented by closure of the nonseismic Category I turbine stop valves and turbine bypass valves, which is considered by the staff to be an acceptable backup for this accident. Safety valves and atmospheric dump valves are provided for each steam generator immediately outside the containment structure upstream of the main steam isolation valves. The atmospheric dump valves (two per steam generator) are air-operated and fail in the closed position on loss of air supply. Backup-seismic Category I nitrogen accumulators are provided for these valves in order to maintain their operability from the control room. The backup nitrogen supply is sized to maintain the valves operable for 8 hours. The atmospheric dump valves are also equipped with handwheels for local manual ope'rution.,. Thus, the requirements of GDC 34, " Residual Heat Removal," are satisfied, provided that the confirmatory issue identified in Section 5.4.3 of this SER is acceptably resolved. The equipment required to function in order to assura main steam isolation is protected against the effects of high-energy pipe breaks (refer to Section 3.6.1 of this SER). This equipment is located in a tornado missile protected structure (the main steam support structure) and is located such that it is not affected by internally generated missiles (refer to Section 3.5.1.1 of this SER). Thus, the requirements of GDC 4 " Environmental and Missile Design Bases," and the guidelines of RG 1.117, " Tornado Design Classification," and BTP ASB 3-1, " Protection Against Postulated Piping Failures in Fluid Systems Outside Containment," are satisfied. Environmental qualification of this equipment is' discussed in Section 3.11 of this SER. Based on the above, the staff concludes that the main steam supply system from the steam generators through the main steam isolation valves meets the require-ments of GDC 2 and GDC 4 with respect to protection against natural phenomena, missiles, and environmental effects, meets the requirements of GDC 34 with respect to residual heat removal capability and the single failure criterion, Palo Verde SER 10-4

Y f&% /t71 3/Mht A n'> h% N$ t. g SEQUENCEOFEVEQS TIME EVENT: Initially at 98% power. No activities In progress. 01:02:18 Single phase to ground fault at Devers Valley Switchyard 525 KV breakers 922 and 712 trip open. T +5 Palo Verde 525 KV Devers transmission line feeder breakers 992 and Cycles 995 trip open. T +16.5 Palo Verde Unit 3 main generator 525 KV output breakers open due to Cycles a sub-synchronous oscillation relay (SS0) trip signal. This trip signal was not expected. 01:02:18 Turbine control for Unit 3 main generator shif ts to Power / Load Unbalance mode which begins closing turbine control and intercept valves to maintain generator output frequency near synchronous with the grid. Generator is supplying Unit 3 in-house loads only. 01:02:19 Large load rejection causing rapid decrease in main steam flow generates Steam Bypass Control System (SBCS) quick open demand signal to all eight SBCS valves. A Reactor Power Cutback (RPC) signal is generated by SBCS (by design causing partial control rod insertion), Due to SBCS time delay relay failure, 4 out of 8 SBCS valves cycle between 10% to 100% open ten times over the next 90 seconds. Other 4 valves cycle between 80% to 100% open at the same frequency. During the next 90 seconds Reactor Power experiences 3% oscillations centered around values ranging from 56% to 60% in response to SBCS valve oscillations, and steam generator (SG) pressures decrease due to excessive steam demand. 01:03:48 Reactor Trip and Main Steam Isolation Signal (MSIS) due to Low No. 2 (SG) TDAS pressure of 920 psia (Trip setpoint is 919 psia for both Reactor Trip and MSIS). No.1 SG minimum pressure reached was 928 psia. No. 2 SG minimum pressure reached was 916 psia. Turbine trip occurs due to Reactor Trip. Unit 3 Main Generator continues to supply non-class in-house loads (13.8 KV busses NAN-501 and NAN-502) as turbine coasts down (per design). No reverse power trip occurs since the generator previously separated from offsite power. 01:03:58 SIAS and CIAS occur due to low RCS pressure of approximately 1860 psia (trip setpoint is 1837 psia for both SIAS and CIAS). (This strips emergency lighting in ADV rooms) Lowest observable RCS pressure = 1860 psia lowest observable T hot = 558 degree F Lowest observable T cold = 545 degree F Lowest observable pressurizer level = 13% Lowest observable saturation margin = 28 degree F [

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h

~ { Within a few seconds following SIAS/CIAS initiation, RCS pressure and temperatures, pressurizer level, and saturation margin begin increasing in response to the termination-of steam flow following MSIS. Minimal high pressure safety injection. flow occurred (HPS1 pump shutoff head = 1850 psia), a 01:04:09 RCS Low Flow reactor trip signals occur _from the Plant Protection i System, due to Reactor Coolant Pump coast down due to NAN-501 and t NAN-S02 decrease in voltage and frequency as generator coasts down. Note however, reactor previously tripped on low steam generator pressure. From this time on, busses NAN-S01 and NAN-S02 have insufficient voltage and frequency to meet synchronization requirements for fast transfer to offsite power. This has occurred as the generator has continued to coast down. Also note that the fast transfer circuit has not yet been called upon to actuate since conditions for a generator trip have not yet occurred as per design. 01:05 Control Room operators noted the ADV's were apparently not responding to Control room demand signals. These valves have no automatic control. All ADV's were given their permissive signals and a 15-20% open demand signal, and were not seen to move by Control room indications (either by controller analog position or position indication lights). Also, one ADV (184) control room controller analog position indication was stuck at approximately 50% open and was a recognized and tagged deficiency. Control room operators trip two out of four RCP's (RCP's 18 and 28) due to SIAS in accordance with emergency procedures. 01:05:59 Genertor trip 01:06:01 Loss of the 13.8 KV non-Class in-house power resulted in de-energiring the following loads, among others: - RCP's - Nuclear Cooling Water Pumps - Circulating Water Pumps - Normal Lighting (including ADV room) - All Control Radiation Monitor System (RMS) Displays (Control Room and-RP area). - Containment temperature, humidity and radwaste sump level indication in the Control Room. - Instrument Air Compressors (This initiates rapid reduction in air pressure to 60 psi in two minutes impacting-ADVs.) 01:07:45 Instrument Air Low Pressure Alarm (Setpoint 95 psig)c 01:08:42 Nitrogen backup to instrument air system isolation valve open (Setpoint 85 psig on instrument air). 01:10 MSSV 579 lifts at approximately 1210 psia (Setpoint is 1250 psia) 01:20 Steam Driven AFW pump (AFA-P01) started to assist with steam generator heat removal.

t' h 01:26 Control Room operators directed the actions of an Auxiliary Operator 1 (AO) at the Remote Shutdown Panel (RSP) to attempt control of ADV's from that location, it should be noted here that Auxiliary Operators are not trained to operate the RSP; this activity is the-responsibilit,v of licensed operators. Following Control Room direction, the A0 correctly transferred ADV 178 to manual at the RSP and inserted a 30% open demand signal. The demand signal was applied for "a few minutes" before it was removed. The other 3 ADV's were transferred to manual local control, then all ADV's were transferred b6ck to Control Room control. Only ADV 178 was given a demand signal from the RSP. A second attempt to operate ADV's from the Control Room was also unsuccessful. 01:30 The first two A0's enter the North room in the Main Steam Support Structure (MSSS) containing ADV's 184 and 178 for SG No.1. Although.they experienced difficulty due to; 1) No apparent lighting _ of any kind, including emergency lighting, 2) No labeling on valves needing to be repositioned. (Operators had to hand trace instrument air lines to locate equalizing and isolation valves), End-3) Periodic lifting of Main Steam Safety Valve (MSSV) 579, they were able to line up manual control for ADV 178 according to posted instructions and manually open to approximately 7% upon Control Room direction. 01:35 The third A0 enters the MSSS and, seeing that SG No. 1 North room was manned, proceeded to SG No. 2 South room where ADV's 179 and 185 are located. This room was not lighted either. The A0 chose ADV-185 to operate since Control Room operators had specified only that one ADV per SG be placed in manual local, but had not specified which one. He completed the manual lineup procedure, by Flashlight, and started to open the valve when he realized the hand wheel was slipping on the actuator shaft. The ADV 185 hand wheel, when engaged in manual operation must be turned clockwise to open the valve. The ADV 185 hand wheel disengaged (free-wheeled) from the actuator shaft with the valve approximately 3% open and the valve would not open further. 01:35 A fourth A0 heard on the radio that one of the ADV hand wheels was free-wheeling and started toward the MSSS with a box of tools. At about this time MSSV 579 on SG No.1 lifted, creating considerable noise making radio communications difficult, in the area of the ADV's. The third A0 decided to re-direct his efforts and gain manual control of ADV 179. He advised the Control room of this l intent and proceeded to align ADV 179 for manual operation. He had just completed placing ADV 179 in manual when the fourth A0 arrived l with the tools. The third A0 paused while the fourth A0 attempted to restore ADV 185 hana wheel engagement and further open the valve. l During this time MSSV 579 lifted again and the third A0 re-dilected i-attention back to ADV 179 which was ready for manual operation. It should also be noted that following the lifting of MSSV 579 there was steam in the room containing the ADV's, contributing to the confusion. ADV 179 hand-wheel open and close directions are opposite those of ADV 185 due to valve / hand-wheel orientation. The 7 fourth A0 attempted to open ADV 179 by turning the hand-wheel in the same direction, clockwise, used to open ADV 185. Failing to move the I

g.

d. '. -

1.l ~ _ valve by' hand, and. believing the urgency of the situation required-- o it,'the fourth A0 placed a 24" pipe wrench on the!ADV 179 hand-wheel-and at the direction of the third A0 rotated the hand-wheel +- approximately one full rotation in -the closed direction before the valve actuator broke, rendering ADV 179 inoperable. t 01:38 MSSV 579 on No.1 SG lifts (2nd time). 01:39 Operators declared an Unusual Event (NUE) baseci on the' loss of 13.8 KV power to the NAN-501 and NAN-502 busses concurrent with SIAS on-low RCS pressure. 01:48 MSSV579 lifts (3rdtime). 01:53 MSSV 579 lif ts (4th time). 01:57 MSSV 579 lifts (5th time). 02:07-MSSV 579 lifts (6th time). Operators unsuccessfully attempted to.open #1 steam generator MSIV bypass valve from the control room apparently due to the high differential pressure across the valve with the downstream piping de-pressurized. This was done to enable the use of the SBCS to bleed steam. 02:18 MSSV 579 lifts (7th time). 02:22 Operators successfully opened #1 steam generator MSIV bypass valve manually at the valve. It should be noted here that operators did not follow procedures in the Main Steam System Operating procedure' for opening SG-V169. It was either during this manual jacking open-process, or during the subsequent closure on the next shift that. SG-V169_was damaged. 02:30-Operators opened #2-steam generator MSIV bypass valve from the control room.~ Operators then began controlling steam generator. heat removal from two SBCS valves which dump to the atmosphere.- (Main-condenser vacuum was lost due to loss of Circulating Water Pumps powered from S01 and S02). 02:32 Bus 501 was reenergized from off-site source. 02:38 MSIS was reset. 02:39 -Operators secured use of ADVs for steam generator heat removal.- 02:41 SIAS-and CIAS were reset. 02:43 Buss S02 was reenergized from its off-site source. 3 02:52 The Unusual Event was-terminated, j 03:15' NRC resident arrived in the Control Room. 04:49 RCP 1A was restarted. 1 04:55. RCP 2A was restarted.

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's si II:22 CJ:!!'i '.;::f;::37,5 ~ l in ij 5 y,. q-t U. f 4 w Control Components Inc. AnIMIvehecompany 17 March 1989 U.S. NUCLEAR REGULATORY COMMISSION Washington D.C. 20555 Attention: Mr. W yno Lanning From: Mr. Curtis Sterud Prin. Engineer, CCI

Subject:

Locations Where Valves By Control Components of The " Pressurized Seat" Design, Similar To The APG Valves S/N 21408-1, Arc Installed In The Same Service I.E. Modulating Atmosphoric Durp Valve Upstream Of The MSIV. Safety Related. Plug Size Is 10" CCI valves as identified above are in the following locations: Operating Utility Station CCT S/N Act. Plue Sito LP&L Waterford 17285 Pneumatic 10" FLP&L St. Lucie 25589-1 Limitorque 8" Duke Power Catawba 18789-3 Pnoumatic 8" So Cal Edison San Onofre 18447-1 & 2 Pncumatic 8" Georgia Powcr Vogle 23469-1 Elec/ Hydraulic 8" 23468-1 HL&P South Texas 35199-1 Elec/ Hydraulic B" WFPSS Not In Servico Pneumatic 8" Sin

ely b, A2 v

Curtis Sterud P:!ncipal Engineer, CCI cc: H. Miller

Attachment:

Section Drawing OF APS ADV Valvo 21408-1 22591 Avenca E r:presa C Aaacho Saeta Marga ita. Caifom.a 92688 eiephcre (714) B58-1877 C FAX. (714) 8531878 C Teiex 685500

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SUMMARY

EVENT AND CAUSAL FACTORS CHART l.l.R. 2-3-89-001 + a sso y SBCS FAST BUS ADVS FAILED ADvs LOCAL j j OPERATION TRANSFER DD TOOFERATE OPERATION j. ERRATIC POTOCCLR REAUTELY OtFFUCLAT I 1r 1r y v i RG LOAD REACTOR LOSS CF DECRADED HEAT NON-CLASS TRIP /ESFAS HON-CLASS REJECT HEAT REMOVAL SY m. POWER 010 2 d 9 ACTUATION POWER REMOVAL SBCS RESTORED 0103:48 010s:01 CAPACITY 0230 0243 Jk 1r usSS LIGHTNG 4 SEAS NADEOUATE ANOMADES NSTRUMENT AIR SYSTEM 4 OEGR/OED RCS LEAKAGE O NCREASED INDICATES DETAILED EVENTS AND EFTitENTM CAUSAL CHART FCR' THAT TOPIC (ATTACHED) CALCULATION i i :l h.. L u v' i h v r e t y

. -pasy SSO RELAY EVENTS AND CAUSAL FACTORS CHART 1.1. R.. 2-3-89-001 4 SSORELAY OPERATED t I e V AT PVNGS, UNIT 3 DEVERS LINE DEVERS GENERATOR BREAKERS C PHASE BREAKERS LARGE LOAD FAULT PL 992 & PL 985 & REJECT ~ PL'995 PL 988 -OPEN OPEN 4 PRE _VINARY

STEAM BYPASS CONTROL ERRATIC OPERATION EVENTS AND CAUSAL FACTORS CHART 1.1. R. 2-3-89-001 I PREVQJSLY A O PERM NO M TASK NOREFAIRS i IDENTIFIED H-> TIMER CARD FOR TIMER 711 7188 INRIATED FAILURE CARD v i.ARGE LOAD SBCS VALVES A OR AR SBCS. I 001 00 SECONDARY l TRIP /MSIS VALVES REJECT Z C PRESSURE C ON LOW S/G Z CLOSE ON 0102:19 E 0102:30 A .O. ROM 0103:48 0103:51 1REJ/fNARY

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e FAST BUS TRANSFER EVENTS AND CAUSAL FACTORS CHART l.l.R.

2-3-89-001 e l AND GRO OUT \\ GDERATOR COASTS SOCS (DWJ l ERRATIO. OPERATO4 p P T GDJERATOR i SEPERATED. l SWJCHCHECM T l FFOJGRO j VOLTSHERTZ HI wonxS AS i l MJED V V V REACTOR FAST BUS LARGE LOAD TRtPt CENERATOR TRANSFER I' ' REJECT 1 TURBlNE - 1 TRIP 1 DO NOT 1 j 0102:19 TRIP O106 0103:48 OCCUR DE ENERGtZE 0to6 05:01 l gFASTBUS T TM Q =w TRANSFER a L PRK MIL ARY l

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ADV OPERATION FROM THE CONTROL ROOM AND REMOTE SHUTDOWN PANEL EVENT AND CAUSAL FACTORS CHART l.l.R. 2-3-89-001 SIMULATOR POTENTIAL 0 DESGN ACT ADVs-DEFE DJOES O mg MAIN STEAM ggg 84 REMOTE l 150LATIOr4 SH M tiPANEL SGNAL V V OPERATORS V ADV STEAMING UNABLE TO COMROL OF OPEN ALL. ADVs CONTROL DtFFICULTY PATH TO CONDENSER 1 ADvs FROM L VEmFIED TO SHfFTED TO IN REMOTE ISOLATED ^ 1 REMOTE C SHUTDOWN CONTROL BE IN THE ROOM COMR% SHUTDOWN PANEL 0103:48 0106:30 ROOM PANEL OPERATION 0111 OPERATOR N?ERTS 15 20% DEMAND SGNAL 1 I ADVs UNABLE ADV ADV 173 ADV TO BE CONTROL UNABLE TO CONTROL TO OPERATED SHIFTED BE OPENED MANUAL C FROM C BACK TO C FROM LOCAL CONTROL -CONTROL DEMOTE O13T ROOM ROOM PANEL PANEL 0126 0126 0120 Jk A O. INSERTS 30% 3 hm l L. R Y t >NAL DEMANDSG I A

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.MSSS BUILD!NG LIGHTING EVENT AND CAUSAL FACTORS CHART 2-3-89-001 AS BULT i SHEDS POWER M19/20 j l 1 P.C.R CANCHLED NON CLASS ONLY 1 LAMP I PCW4n l 28 EACH 147 l V V V V EMERGENCY ESSENTIAL LIGHTS LOSS OF UC NO ESS. LIGHTS ENERCtZE NORMAL DE ENERGtZEI HTS m DE-ENERGIZED ESSEWAL 140" SOUTH BUT LIGHTING 0103:54 DECRADED 0106:01 UCHTS "III 0103:54 ENERCIZE BURDWO 0230 0230 JL (D { l PMs l O ( WAlVED. h, 9OQ Cy w. ON SAME PM TASK PRFI IVINi ARV

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.~ c OFF-SITE DOSE CALCULATION ERRORS EVENT AND CAUSAL FACTORS CHART l.l.R. 2-3-89-001' ACTUAL LOSS OF RELEASE NON-CLASS CALCULATED POWER BELOW TECH 0105:41 SPEC LIMITS d b r 1 P NOTIFICATION RMSMESOREM REVIEW OF i OF UNUSUAL /RU-141 EPIP-14 EVENT SAMPLE CART OtSCOVERS DECLARED NOTAVAILADLE MATH ERROR $ 0139 g g k 7 '" 8 oFFSnE oOSE MANUAL CALCULATIOt; RECO ENDS A AION CALC PER - 1 7 COM M ED NO PROTENE g. E PIP-14 ' $^N C TERMINATED 0139 0139-0150 ECESSARY 0252 0150 h 00GE RATE FCR MATH CONSERVATIVE ALLRELEASE ERRORSirNECT ' OEFAULTVALUES i POriTS NOT 'I CtrNERSO4 USED N ESFAS NON-CLASS CALCULATED FACTORS CALCtA.ATION ACTUATIONS FOWER ( RESET m.uw l { RU-139 AND t { RU-140 READNGS l 1, L'}u,o RY OsrAt <T_x _c

~ INSTRUMENT AIR EVENTS AND CAUSAL FACTORS CHART l.i.R. 2-3-89-001 RX TRIP TUR8!NETRTP.I LOS3OF MANY PLANT LAPRESS NON CLASS ,f VALVES ( 00SERVEDAT i FOVER OPERATrG. 64 PSIG 4 INSTRUMENT AR ^ m F BACK-UP 1r POWER COMPRESSORS m s i VALVE OPENS RESTORED RE-ENERCtZED OR AL DEE RG12ED 02 O N01 0166:01 INSTRtMENil AIR LOW - -. NR PRESS DECREASES ALARM ? M,. ARY

'I.. RCS LEAKAGE FROM RCP 1B EVENTS AND CAUSAL FACTORS CHART

1. l. R.

2-3-89-001 l RX TRIP OPERATORS SI ASfC1 AS - 7 LETDOWN l

. CYCLECHARGNG l

0103:48 ISCX.ATED PUMPS I f 1r ' LOSS OF CH UV-507 j LEAKS BYOR ACPSEAL NAN S01 AND 6 M R I HAN S02 FAILS TO REMAIN i FUECTON l UMVRRE 0106:41 N STOFf1ED l 1 E 1P 1P 1P l RCP SEALS ^ ^" ALL 4 RCPs RCP SEAL EXPOSED TO ' S OSm B N OU ROW DE-ENERGl2ED C ' COOLING LOST C 7 C ELEVATED 0106:01 0106:41 TEMPERATURES 0 0135 j 1 E RCP 18 SEAL INSPECTION 3 PRES $URES A PPROX. 1.25 N CPM LEAK FROM RMAL RCP 18 SEAL 1900 ) a. 1

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.-.,n,. ..c I RCS LEAK AGE FROM CHV 435 ~ EVENTS AND CAUSAL FACTORS CHART

l. i. R.

2-3-89-001 l f l M84 JN g gg E)OWEER r LOCAL CHARGrG MEASUREMENT RX1Cwen . TEMPERATURE l TRNM EDUCED j V V CH V435 CHV 435 FURMANETED TO EXPERIENCES FURMANtTE A*E REDUCE THERMAL MATERIAL ggy g ^- LEAKAGE PRIOR TRANSIENT SHRINKS 0" TO EVENT 0103:54 900 CHV435 i I LEAKAGE.5 GPM 3P1E VI ARV

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! I D i r,. Astatw An em.b ly (See rigure JJ l Z 7 44 3 g natically operated and connected to the a. The actuator assembly is pneu.,* E M.y'., o4__ body assembly by a yoke. The actuator A~ shaft is joined to the plug stem. The actuator assembly extends or retracts O 'l tha plug assembly within the body assembly ON by pressure applied to either side of the pisten. U.'l? 1-Coi3ROL ELEPZNT b. Air to position the actuator shaft within the cylinder is received 4 QAsse bly (See Figure 2) at an air port, forcing the actuator shaft to esve in the preper direction. The body assembly is an offaat globe. This transfers mechanical force through cor/iguration uish, the shaft to repos# tion the plus within 3 i.=

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\\ =~ 4 a.- m Misk'stsek permits than . ec.u.'" ; _ p i in Cow rate while limiting flaw vel.ge: weity through the control'e3enent. The 'j; l disk stack censists of a nu=ber of diskt 10 l into _which tabyrinth flow passages have a, 4i M been etched.te allow a fixed i=pedance. ,Ij

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Impedance in the-passages -is ~ developed. Ih l by a series of right-angle turns. with

I a specific nu=ber of turns in sach k

l[ l passage-to. limit the velocity to an? - 4 gg, I acceptable level.-'Since-each disk has~t: .knoyn flow capacity, flow thragh the - d: I I(--. cont:31-element can be-securately-M' 7 '" % *,* censured and controlled. The position' of the plug within the disk stack' bort 1 i detades now by ex 1,. N! fewer disk passages. posing more or {. b. h'ith the valve in the closed Fi;

3 - Actuator Asse:bly position, upstream pressure-fills:the-

_{. cha-ber above the plug by way of:a con. trolled leak acressLths Pist:n ring. ehe body asse=bly. In the eva-. of power failure, springs, when..;; plied, This provides a seating load equal to the ] inlet pressure ti=es_the_ full area of will force the piston to' cove the plug the plug. {5ee Figure 4). i into the 'specified failure position. @pg*,a Os'*:~.**"' Oye D C.mu=:. } i p[,s 3 i a ~ ^ -, s-Wx pt: s ht p*:N! 2 -- - ) u s hs! /'s M b.d *A =h h h 1 / / .N 5 2y.g*' e.w -4 j/N = ,.o I j' T,R?.$N;'S' . p. ' ~ MbY g lh // Y~iy' %.I' // [ /~h ( 6 <y g-p Figure 4 Figure As Figure 4b:

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W 15/1989 15:27 t.s E Pr4_O WRDE W M D..,,,No . When a signal to open _the valve is e so. When the plug is in the modulating : de, received, the actuator iifts the Sten, biasing force provided by pressurs ac: tin y[ cpening the pilot seat which alb ws the ber above the plug to beco:e balanced on the differential area overcomes fluctuating pressures from the fluid the downstream pressure. Upstreaa-jets exiting the disk stack, p.sure acts-upon the differential plug area (see Figure da), and provides an When a signal to close the valve is axial biasing force which causes the plug received, the ' actuator saves the ste: in to re:ain on the e. sin seat, the closing direction. The biasi.ng forti-As the stem continues to cove in the. on the plug causes it to folicw the sters-opening direction, the pilot valve, until the main seat is contacted. ne shoulder engages the plug to lift it off operator then seats the pilot section. The controlled leak. then fills the chs. be the r.ain seat. The ax.ist biasing force above the plug seating force. providing additional, causes these opposing faces to re: min in contact under all operating conditions. (See Figure 4b). -7. Nuclear Qualification This valve has been environmentally and seismically qualified conditions of the equipment to meet the location (as defined in the customer specificatio: The valve assembly requires periodic maintenance in order to naintain the qua. Afted status of tno valve. Maintaining the qualified status of the valve is r the responsibility of Control Components Inc. Detailed maintenance of the valve assembly is identified under Section vi, Naintenance. Qualification. s G 4 ese, 4

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, e i L. e 4 SECTION V A ACWATOR AssunLY k1. Disasse:bly (See Figure 10) If a unusi override asser.bly is installed on the upper cap of the actuster asserbly ! *I8I S refer to unual override unual for mQ re: oval instrettions, M f b S rp t wa p en WARNit[G THE ACWATOR ASSDOLY IS O l i' SPRING LOADED. USE CARE

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70 FOLLOW NOR'ut SAFE'IY FROCEDURES AND Td! FOL-6 ', ;j ); LCWING INSTRU:TICNS h"rEN r Locawa: Men i RDOVING THE END CAPS. N INJURY TO PER30WEL OR DAVGI TO THE ASSDIBLY COULD RESULT 77.0M Dl-PROPER D15A5112tBLY. Figure 9 - Installing Ex.ension studs a. Re:cve two ( ctly c;;o. Re ove springs (7) (FAIL CLOSE s. site studs (4) fr:c the sctuator type actusters only.) b as s e r.bly. f. Tilt cylinder (3) at the top b. Repisce the two recoved studs to break sealing tension at the lower cap. Recove the cylinder. with two all-thread stud of a length at letst 50% longer than the length of cylin-g. Slide actuator shaft (5), uith der (3). Allow the excess length of the studs to extend above the upper cap. pisten (9) attached, from lower iap (2), Install lockv. hers under the stud.s nuts ~h. Remove springs (7). (FAIL OPEN cn the lower cap end of the studs and fist vahsets under the upper cap ends a.s shown type actusters only.) b Figure 9. Re:ove remining four studs NOTE c. (4). See Figure 10 If a eianual override asse".bly ^ is installed on the upper capg CAUTION nut (10) is deleted and an ex. tension shaft retains the Nuts on the extension studs pisten to the actuator shaft. cust be renoved evenly by increments to prev ing the upper cap.ent cant-1 Secure the actuator shaft in a vise equipped with soft brass jaws. Recove nut (10), or the extension shaft. d. Alternately back-off the nuts on and piston (9). Os eatension studs until all spring ten-sion is re11'eved. Recove upper cap (1). "dh.. 1 p .__--_______________________-.-_-_____-_____a

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~. ,, _ _.. - - - oysvae 15'30 LG % [ U. [, h t.1 s itJ M C M l. 7 cc2 3cs 7738 P.03 .;,..., '.7 ^ ' NOTE Secure pisten (9) to tr.. /* s. Secure the shaft by the r.illed actuator shaft. Dats. If the shaft does not ( have nats install the stem clamp onto the shstt and clamp NOTE the stem cla=p in the vise. If a r.snual overr_ide asser.bly is installed on the upper cap, 2. Assemblv (See Figure 10) nut (10) is deleted and the piston is secured to the actuster a. Apply tubricant, as specified by shaft by an extensio'n shaft. the top assembly drawing, to all o rangs and Apply Lectite 242 to the actuttor install as shom in figure 10. shaft threads before instal?i.ng the extension shaft. NOTE If a manual overtido assembly is installed on the upper cap refer to f. Insert the actustor shaft the nsnust override manual for install-< e.sse:bly into the lower esp. 4 tion instructions. Lubricant to be at s ing.pecified by the top assembly draw-NOTE b. Apply a light cost of lubricant. S:ep h is syptic:ble for FAIL as specified by the top assembly drawing, CLCSE type attuators caly, to the anterror surface of the cylinder (3).' Install the cylinder onto the loher cap (2). g.,, 33 3,pgn;g (7) g,g g3, cy1! dar. h. Install two all-thread, studs of a length at least 50% longer than the A.llow the excess 1cngth of the st NOTE Stcp a fa cyptic:ble for extend from the upper cap and.- Install TAIL OFtt/ type c::u.: tor lockwa.shers under the nuts on the low esp end of the studs and Gat wa assemblies only, under the nuts on the upper cap.shers (See Figure 9). end. Install springs (7) into the c. cylinder. i Align the air p lover cap a.nd upper cap (orts in the 1). Slide the d. Secure actuator shaft 8 vise equipped with soft brass jaw (s) in a upper cap onto the extension studs. i. CAUTION NOTE TICHTTN THE hVTS EVENLY ON THE Secure the acutator shaft by EXTENSION STUDS BY INCREMEh75 the milled flats. If the TO PREVENT CANTING THE UPPER shaft does not have M ats ("f install the stem clamp on the TO O RINGS 1.HILE INSTALLING THI CAP. USE CARE TO PREt"EhT D M GE shaft and clamp the staa UPPER CAP. clamp in the vise. '"h e- ,r-r3-

s -- " ~~ eyis,tte9 15833 LG !FC C.02 30G ;msa P.09 ,y.g3 g y,ei e,i,* { t,, 7 ,,/*' NOTE Continue to tighten the extensi n. ( 5teps j through a are applicable stud nuts until the end caps are seated \\('. if the actuator shaft does not against the cylinder. extend through the lower cap when the upper cap is installed on the Install four studs (d. Figure it o. and tighten the nuts. extension studs. Step n through p are applicsble for all other acutator asser.blies, p. Re=ove the two extensten studs and replace with the rer.sining stads (4). 3. Test Asse: bled Actuator Asserbiv

j. Raise the cylinder fr:: the lower cap to allow sight of the actuater

~~ shaft. Connect an air line to the lower a. esp air port and slowly apply 80 psi air k, Place wood blocks between the pressure. Check for leakage at the bottoa lower cap and the cylinder to support the Check for air flow at the upper ca seal. cylt.. der in the raised p:sition. air port, indicsting pisten seal teskage,p Vent the air pressure. 1. Using an appropriate length of b. Recove the air !!ne fess the wooden dowel, guide the actuater shaft into the lower cap while alternately lower cap sir port and connect to the tightening the nuts un t.he extension vpper cap air port. Repest step a above stuts. to test for upper esp Icakage. Remove the blocks as soon as m. the shaft is through the lower esp _s a 7, m.... '..,,.',,. . " ' " ~ ~ ' m., w ' ....' '..t i -l' :.,p~ ~..e l '...i'. ~* . t. *. ~ - ,.i l. . w g 9 54

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j DISTRIBUT10th i ~1p i AUGHENTED INSPECTION TEAN PLAN PAL 0 YERDE UNIT 3 t TEAM HEMBERSHIP D. F. Xtrsch, Chief, Reactor Safety Branch - Team Leader ' J. Burdoin, Reactor Inspector W. Ang, Reactor Inspector W. TenBrook, Radiation speel611st 4. Davis, Project Managar, NRR John Knor., Power Systems Engineer NRR l
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Q A., mal"i comm e-M r/ % i 5 M, 41 $LUf kl,J n' o puiI H<phiirht t PALO RDE 3 2//g ATHOSPHERIC DUMP VALVE FAILURES o' On March 3, 1989, at 1:05 a.m Palo Verde Unit 3 experienced a 100 percent load rejection and subsequent reactor power runback from 100 percent to 45 percent The turbine bypass valves opened but the bypass valve controller power. malfunctioned causing excessive steam relief and overcooling of the reactor rred from low pressure in the No. 2 Main steam lineggiogpgy8n low pressurizer pressure. system. enerator and the.r n..... p;41 Following steam steam ine isolation the atmospheric dump valves (ADV's) remained clo:ed after operators attempted to open them from the control room. The valves do not receive an automatic open signal. When the dump valves f ailed to open remotely,M Attempts to open We e-=re a T w o h valves were opened locally using handwheels. 4 eve 4 ADV were not pedormed correctly and the valve housing was broken. TheADV'satPaloVerdeweremanufacturedbyControlComponentsInc.(CCl). (ADV's of a similar design to those a alo Verde are manufactured by CCI are installed at Vogtle, South Texas WH arris, Waterford, St. Lucie, and p CCI reports that in previous testing of ADVs at Palo Verde and other Catawba. facilit.Qsinstancesofvalvestickingandcontroldifficultieshaveoccurred. CCI has propend-modification to the valve design that increases the pilot flow g p A m in the main valve pistons. Yalves with larger pilot areas have been installed at Vogtle, South Texas, WNP, and Harris. CCI reports no failures of ADV's similar to those at Palo Verde 3 have occurred at these plants. CCI has proposed ADY modifications increasing the pilot area at Waterford, St. Lucie, Catawba, and Palo Verde. CCI do not propose rodification to the San Onofre 2 and 3 ADV's due to design differences. F.h wbyu4 b.N The ADV's at aio Verde Units 1, 2, and 3 are pneumatically operated with air or nitrogen. Following failure of the ADV's to open remotely at Unit 3.-the licensee attempted to stroke the Unit I and Unit 2 ADV's. One ADV had a maladjusted valve postioner and did not open fully. One valve oscillated but stroked open. Two ADV's had malfunctioning nitrogen pressure regulators. These were subsequently opened with air pressure. Four ADV's were opened with nitrogen. The licensee reported that about twice as much force was required to open the Unit 1 ADV as those on Unit 2. The licensee for Palo Verde is continuing to investigate the cause of valve failure but has not yet identified a root cause. t I 1
I... 7i* UNITED STATES Q, NUCLEAR REGULATORY C06ftl5510N OFFICE OF NUCLEAR REACTOR REGULATION f WASHINGTON D. C. 20555 j i April 1989 INFORMATION NOTICE NO. 89-ATHOSPHERIC DUMP VALVE FAILURES AT pALO VERDE Addressees: All holders of operating licenses or construction permits for nuclear power
~~reactors, purpose:~~
$d A ggp+.,Aou.;cf 8 L, This information is being provided to sleet addressets to p;t;r.thi feibis of 5% stee % =+=>a=Paric hep velves. It is expected that recipients will review the information for applicability to their facilities and consider actions, as appropriate, to avoid similar-problems. However, suggestions contained in this information' notice do not constitute NRC requirements; therefore, no specific action or written response is required. ~ Description of Circumstances: On March 3, 1989, Palo Verde Unit 3 experienced a 100. percent load tejection and subsequent reactor power runback from 100 percent-to 45 ' percent power. 1 The turbine bypass valves opened but the bypass valve controller malfunctionati causing excessive steam relief and overcooling of the reactor system. Main steam line isolation occurred from low pressure in the No. 2 steam generator - and the-reactor tripped on low pressurizer-. pressure. Following steam line-isolation 1heatmosphericdumpvalves:(ADV)remainedclosedafteroperators attempted to open them from the control room. The valves do not receive an automatic open rignal. When the dump valves failed to open remotely, threeMo valves were opentd locally using handwheels. AttemptstoopendT57tF.} A Pu
8 {' 1H 89-April 1989 [, Page 2 of ADY were not perforred correctly and the valve housing was broken. The ADV's at Palo Verde Units 1, 2, and 3 are pneumatically operated. The pneumatic operators on the valves are actuated using plant instrurent air or a stored pressurized nitrogen supply. The valves were manufactured by ControlComponentsInc.(CC1). CCI reports that in previous testing of j ADVs at Palo Verde and other facilities instances of va M niG ii M g g} 9 sw4 eel-d+H4ttAt4es have occurred. Cxcessive bonnet pressure caused by hgttoes 1ug piston ring is suspected abnonnally high leakage past the main valve)f8Metting into the M e the u se. Foreign particles in the 94 d .( clearance areas and under the piston ring sealing surfaces may produce the high piston ring leakage. CCI has pmposed-design modifications to address this problem. dueJqd a hN N Following failure of the ADV's to open,r potely at Unit 3, the licensee OnevalveosciliatedbutS{trokedopen. One AgV gadg g a uy ed attempted to stroke the Unit 1 and Un ( 2 ADV's. valve positioner and did not open 11y. s Two ADV's had r.alfunctioning ni rogen pressure regulators. These were subsequently opened with air ressure. Four ADV's were opened with nitrogen. Thelicenseereportedtha)abouttwiceasmuchforcewasrequiredtoopentheJ Unit 1 ADV'd as thue-w Unit 2 f The licensee for Palo Verde is b.Kd t, continuing to investigate the cause of valve failureSbut has not yet identsf ghs TVAT a root cause. Contributing to the simultaneous ADV failure at Palo Verde is the lack of inservice testing under hot steam conditions. The valves are routinely tested with the steam lines cold and depressurized. For testing,the pneumatic actuators are energized using plant air rather than with the pressurized nitrogen supply.yfressure regulator problems would not be discovered. fkLo uR W 6 0 i
y f.... f. -IN 09-I!' April ,1989 Page 3 of ~ f f Licensees inay wish to evaluate their ADV surveillance test procedures and ~ consider performing the tests under conditions which better simulate inservice conditions. No specific action or written response is required by this information notice. If you have any questions about this matter, please contact one of the technical contacts listed below or the Regional Administrator of the appropriate regional office. Charles E. Rossi Director Division of Operational Events Assessment . Office of Nuclear Reactor Regulation Technical Contacts: Horace Shaw, NRR (301)492-0906 i Walton Jensen, NRR (301)492-1190
~~Attachment:~~
List of Recently Issued NRC Infomation Notices g .,[,_.,.
^ -(- 69-12 b f PALO VERDE _ UNIT 3 PLANTS WITH CCI ADVs_SJMILAR TO PALO VERDE'S Ell.3I /CTUATOR PLUG SIZE HARRIS ELECTR0 HYDRAULIC 8" WATERFORD 3 PNEUMATIC ' 10" ST. LUCIE 1/2 LIMITOROUE 8" CATAWBA 1/2 PNEUMATIC 8" SAN ON0FRE 2/3 8" V0GTLE 1/2 ELECTR0 HYDRAULIC 8" SOUTH TEXAS 1/2 ELECTR0 HYDRAULIC 8"
7-; l ARIZONA NUCLEAR POWER PROJECT 1 M. SURVEILLANCE TEST PAtlaGE E g i l r WORK ORDER ( Q st Wo# 00332774 ST Procedure 73ST-3ZZ10 Work Center OENG j Task # 054801 Scheduled Completion Date 01/13/89 System ZZ 8 Mode 1234 Tech Spec Maximum Ext Date Reason for 7 Test: Scheduled Y Conditional Retest Other Explain Authorized by SANDY HENRY Plan Rgrd Perform Group (s) Man Hrs Est/Act Matls Rgrd N Lead Support Support ~' Est/M.t Est/Act Est/Act Clear Rgrd N REP Rqrd N Discp OPS ( Confnd Space N Permit Rgrd Crew Sz 1/ / / Safety Anal Rgrd Man Hrs 1/ / / M&TE Rqrd Y Est Dur Hrs 1 Actual Dur Hrs Extra data sheets rqrd N (#of sheets /page#) / / '/ ,4 1 ? WORK ORDER DESCRIPTION: PERFORM SURVEILIANCE TEST PROCEDURE 73ST-3ZZ10 ON APPENDICES A-G g ASME SECTION XI VALVE TEST o { i
a _...___ h SURVEILLANCE TEST PACKAGE REVIEW SHEET ,uee x _SE R._ _e.., D.,.. (' user cur,.nt current y D.t.:,0f A/ y VERIFICATION: Rev No D PCN No IO S6gn.turt e e.,,,,.., s e n.iu,. inw.i. E ov.. No. Dei.. 90vt G2:4t a s/u in .gh&Y h &SRW
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x w ~ ACCEPTANCE REVIEW:(Applios only to Tech. Spec. systems: components, etc.) MO MODE Performed in: Plant Unit No. ST Proedr. No. 7 WERE ALL TECH. SPEC. COMPONENTS AND/OR TRAINS ADDRESSED IN THE ST PROCEDURE TESTED? YES .$ NO (11fJO, identify the train or component (s) tes tedin this performance.) /?pp c sq S - u y-GB, i%i4-Aff Q $ C A - U V-l6%, %A-v/- I(Y{ tyl LT. 7 drup(scu " n tso-) N u n re q (sc.u,nat u d S ( WERE ALL APPLICABLE TECH. SPEC. SURVEILLANCE REOUIREMENTS SATISFIED? YES O NO (If NO. refer to 73AC 9ZZO4.) ) g < <dh SHOULD THE SPCO USE THIS PACKAGE TO RESET THE SCHEDULE FOR THl3 ST? YES $NO (Check NO, for shittly, daily and intervat S T's.) - Date:I~S-Time:b@ ACCEPTANCE REVIEWER: e /\\ / ) TEST STATUS REVIEW: V e SIMS STATUS ENTERED BY: A STWO No.: SN b (Not applicable to shiftly, daily or kh ur normat nterval 2) ASSTJSHIFT SUPERVISOR: M Date: I, ~ TEST RESULTS REVIEW: PE RF. GROUP IM MED. SUPV.! 2fW - Date: I /, / Time: O TECHNICAL REVIEW: Date: / /
~~h" SPCG USE:~~
Received by: SIMS Closing Data Entered: pmuno m., m 73ACSZZ04 - ..w s.. ..n p
1 SURVEILLANCE TEST PACKAGE REVIEW SHEET ANPP P4 D NAM USE: ReviS60n checked by. Date' h USER Current ] Current 7 bgf.g/ VERIFICATION: Rev. No PCN No Signature > /v"_ M Date 1 + Performer Signature S __ _.m initiets Employee No Date 0 $$ hL,,,, Al 7211'? / ~ 19 -d'f/ k ti,$ kshlO 'L/ NYN b H 1 -M v' c () ACCEPTANCE REVIEW:(Applies only to Tech. Spec. systems: components, etc.) Ptant Unit No. ST Proedr. No. / MODE Performed in: WERE ALL TECH. SPEC, COMPONENTS AND/OR TRAINS ADDRESSED IN THE ST PROCEDURE TESTED? O vES E No (If NO, identity the train or component (sj testedin this perf ormance.) /g rF t ", s sG il36 A 4 5 6 B t!3 5 3 u w e h-WERE ALL APPLICABLE TECH. SPEC. SURVEILLANCE REQUIREMENTS SATISFIED? h YES O No (lI NO. refer to 73AC 9ZZO4.) SHOULD THE SPCG USE THIS PACKAGE TO RESET THE SCHEDULE FOR THIS ST? hYES O No (Check NO. for shiftly, daily and 72 hout interval S T's,) ACCEPTANCE REVIEW Date: D Time; 14 / TEST STATUS REVIEW: SIMS STATUS ENTERED B * - ( [O D MA b{ ~ STWO No.: I (Not applicable to shiftly, dat or 72-hour normalinterval S T's) y ASSTJSHIFT SUPERVISOR:y # y O % cL Date: i, i TEST RESULTS REVIEW: O f ERF. GROUP iM M ED, SUPV - Date: s ECHNICAL REVIEW: Date: Time: ~~ 'I [' SPCG USE: Received by: SIMS Closing Data Entered: l em+mo n +.e nAcoz204 l < n. N.'"iL.. .n. I L
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~~~;; / Y CI 32735 r. ,, ( 3 Hr, v. G. 1inghact M 13 'J !s:htel PMr C:rporation !!OO tast tegorial Highway h'o rval k, C A 50550~~
~~Subject:~~
Aritena Nuclear Pevar Project Bac',te) 00b 10407 Ehhan:enent of $tsen 3ypast Yelves Bacht:1 File MM.00) Referen:e: (A) Eccht:1 letter 5/CE.I.51MS, Mc 1937CE, Wa',ed My 25,1H5, W. S. Ein;ht a to C. Fe ;vson Enclosuress (1) CCI 1stist dated July as,1925 (2) CCI letter ditsd June 4, lu3 to " i,)r.;htm; 1his letter is in trply to Esitrants ( A), T.,tf eren:t (A) re:uested C-! to tDa the lead responsibility to prcvidt re r erettier.s for a icng term solutten tc the physical and'c;crttienti prchhits which have heen fcond with the steam bypass vaivas, Enclesure (l') details CCI recomandations f;r enhancit.; valves to ia. crease reliablitty in an encitan syste:,, Yalses as currantly sr:dified will cperate in a clean system enviter.Mnt. The fellowing is C E's recemst,tetier.s f or n.aintaining the stesa by;ess velves et the 7410 Y rce plants, Vt have includid it=tdlate rec.wantations as well as 1:ng term re:cmend6ti:na ter your considerttion, Ire.:dt a_te r e:nr4 neat _ lens A) Take all necessary.;rt::vdens to $ntain a ekte systm Valve rtM151M*.y is MTuuy pr:::rd:G to t*.e cittmrtu of the syste. B) Do'not.%diff worMog vthus that have ban succenniully tested. c) One, valves are inst:11ed in syste.?, cycle <sch vaive at least cact/sonth-with valve isciated (t.o A P across pic;) to assure 0;4rability. This viH help to e41ntain a clean viive. Fest-history indicates thzt tha siste a R 3 valV8 is e78FCi3k0 Ih8 ffCrt ICI!IDII it D M 0043* h D) When flushing the syntam in Palo Verde 93 cherve the irstalletten instr.;;tions e s netts by Fe;e 2.1, Paragraph 3. Vrdar " Flushing'. i l r. [ a s,: ' n. co'a a t ces sie sa roaa i u sses accesa etita sesusano w
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g. f A. Ciciqint the fyttsm? cf Trash :nd teatahine$es $tt Item "A' under "imediate Rec:crandctionst 5, Adding A Vave $srin; tieder the Hston 'Alnq Fest experience with thess vehts indicets thet extsphe pitte?.rits lt6 it has b4en the pririary probie. The tiittien cf vava springs ts - dirtetly related to thls prebis. Pisten rir.g cocking due to trash- ~ contamination vald be haid to a r.inirerwhh this ennsnce::er:t. vt recem end that wave springs !:e added to any Yohes ther are currently-disassembled or re:iuire dtsessertir due to c$en-roblean, This nedttf estic, has teen installed en vehe tag n' T510,% Psio Verte #2. Currently Faio Ytrde hes f our (4) additional wete se., -evailabic for installathn at the site, C. fa:retslM the $ Uet Aret This a:dification b untrsted and is currentirbeing nenutacured by CCI fer trsteiluten to.one vahc et 3MB3 A ints cost;n will si) W the pMet ditchers.e arcs to r.er.riy c:vble and wm enhance vehe re11ablitty tccordlo;)y, ya recmsnd, beauver, tht.t this cones;T. to testte et SONGS rrior to use at Fein Verde. In:locsta (2) further expicins this design co.ne;t. ch nebe i3e S W N sten ;tng pesjen To Reduce terreft e D. i this chen;e would invohe cocting the cutsWe barrtd of the plus dth ste111tc, This shcuid net bc necessary for ncrmal operation.cf the phnt, n<tver, during the construtMon stage, ve,he interneis shouW not be installed until after the systen has t.een pre;:erV flushed and the systet is rescied f er testing and inspectich. St Mita vim, hewtyer, increase the lif e of tha phic and should lucrease rellebtitty of the pisten. ring ) s e e), Based on this C-I su; test,s ut.t exis' dug: pluss termed f rsn Palo verde #2 valves T5-1003 and 13-R07 be returned to Ct! and rewor' sed trtMi:it'.c stcMita f acing. These plugs thould be t:sintained as spares end used in c:njuncticn with the exhting wave springs shouh) it becme rg:essary to dis ($:eele a vahe cuo to cperatinmG pecbhms. g, tr.eresstnc The Actuat_er she C-5 f:es nct rec: mend increasing the cetutter tire at this tim,, Wa believe the soJrce of the prchie.-: to bv excesths, ;,isten. rina iceuge and s therefore recot;nered niodifyin9 the vthe inttrnals to 31hivitic this ccnditten, p, Inceersire ihe Se-:W preuvre io ibe Actuator C-! does net recreand ir.creasir; air vi:pp'.y prtssure et this ttne bee Perursph 1 atcyt). For inf ernatien, the,utn:m thebit-eie s@y pretsure to the f.cteter is U.3 pity, &4 a e to'd sset tr6 sty sa road 2 A13 des 801003a 61:40 sesteso re' _r
p-PO'd T101 3 ), .i i.u m y - l- .Cett 4nd-f tlhtry schtMuz. f tr trycf the abeve vahn tshance svtoltt as u,t:an M:;utst, ments d ii t.e. f f $h:uld yw ban 4*y cuesti qs c:n:tring this above ple#se :entact Ec, ' Ye,y truly y W ts, )m.% ~. j C. Fergusen CF/GBirre Y FCI-85-052 F43 M cc Massrst
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1 a... .re S Control Components Inc. Anocawcompany l January 4, 1989 Mr. Ben Mendoza Arizona Nuclear Power Project Station 4077 P.O. Box 52034 Phoenix, Arizona 85072-2034 subject: Proposal i80750-2 Reference CCI Valve l 5/N 21408-1,4 4 7 ANPP Tag 1, 2 & 3 l JSGA - MV 178, 179, 184 4 185 i
~~Dear Mr. Mendosa:~~
Thank you for this opportunity to be of service to the Arizona Pub-- l lic service company. In conversations with our Sales Representative, Mr. Todd McGregor, l you were interested in possible enhancements and updates to the above valves. Through continued fleid inspections and in service testing, CCI has developed an enhancement package to significantly improva valve re-l liability and extend valve life. This package consists of an in-proved pisten ring design and pilot port configuration.- PISTON RING l Excessive bonnet pressure is a suspected cause of valve sticking l' and control difficulties. This excessive bonnet pressure is caused by higher than designed leakage past the : piston rings. This exces-i sive leakage is caused by foreign partteulates in the pipelines l getting into the clearance areas and under the piston ring sealing surfaces. /) 22591 A4Wa Empsu D Rashe $49:a Ma';rita.C4%mla 82688 \\ Te4p%w. (714) 6561871 D FAX. (714) 8581878 D Ts'ex G65500 j 9 /l *d BIBlBGBtilSIN3NobiO3'10HN00 BC:8 68.03EYW
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~~t-The current piston ring is hydraulically: 1oaded in place and isial-loved 0.003" to 0.005* of vertical movement.~~
This rewired move-ment can allow -foreign particulates to hold the piston ring away from its mating s(trash,, scale,i etc.) h bonnet-urfaces, caus ng hig pressure. The improved piston ring design consists of-a two (3) piece piston-ring and special guide bushing. This design eliminates piston ring .novament, and hydraulically and mechanically - provides. a constant load o the piston ring, keeping it firmly against its sealing sur-faces. Please see the attached sketches. piter pont cowrfaunATYow To further reduce bonnet pres'sure, we have - developed an improved: Pilot port to double pilot port capacity. This increases the area .~ from 2.8 s para inches to 4 9 square inches. This increased area, when used in the - two (2) pier. piston ring, ensures low-operating bonnet pressure. To date eight (8) valves at southern california Edison's, San Onofra Nuclear Osnarating station have been updated with these in-provements. There have been no operational difficulties with the improvements. We recommend the valves at Palo Verda be updated with both the two-(2) piece piston ring and the increased pilot port configuration. The existing plugs can be modified.into the-inproved design.- The re=aining items will be new. cur proposal (40760-2 is as follows: DEECRIPTfoM OTY BELIVERY DRICE 11tMt Update package with 12 la Weeks reworked plug assy. Update package with 4 18-Weeks 4 new plug assy. The first update-package listed includes modifying the plug assen-bly, new piston ring, new guide bushing, the - normal easkets and seals required for reassembly, section XI traveler for the plug re-m work and engineering. Because of the long lead time associated with reworking or manufse-- turing new nuclear clast items,: we propose upgrade packages be pre-positioned at Palo Verde prior-to the next scheduled outage. This can be accomplished by - reworking plug assemblies from the pale. Verde stockroom or manufacturing new plug assemblies. We highly recom: tend one of our Field service Technicians be on alte to provide guidance and assistance with the disassembly and re-assembly of the valve. I have enclosed a copy of our Field service Terza & conditions, form FSTCN-A (1-88), which shall apply. comoscowownsos.
,- ~ 'co, m ami as it to - "J ~ ~ -~~ L This proposal is in offect for sixty (40) days. Shipnant will be F.C.B. - Crange county, California both ways. Freight charges will be prepaid and invoiced. Our payment terms are Nat 30 Days. Again, thank you for'the opportunity to be of s'ervios. Should you have any questions or wish to discuss this proposal, please call at any time or contact our sales Representative, Mr. Todd McGregor with Intermountain Valve, Inc. at (801) 753-2381. Sincerely, CON}R,OL COMPONENTS INC. C4a.LAs,sid Charles A. Hart Field Service Administrator /$t Attachments cc TMcGregor - 2nterzountain Valve Inc. GBergtann - CCI e S e t O 9 /E 'd gig 1958t11 SIN 3N0&i33'1011N00 6E:8 69i03 M .-__________-_--____-________-_-__________-_____-__-___________A
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i i. 9 89-10 N. PALO VERDE UNIT 3 MULTIPLE ECUIPMENT FAILURES FOLLOWING LQAD REJECT 3 MARCH 3, 1989 i PROBLEB UNIT 3 EXPERIENCED A FULL LOAD REJECTION FOLLOWED BY A REACTOR TRIP. SUBSEQUENT MULTIPLE FAILURES INCLUDED: (1) MALFUNCTION OF THE STEAM BYPASS SYSTEM, (2) LOSS OF REACTOR COOLANT PUMPS, (3) FAILURE OF ATMOSPHERIC DUMP VALVES (ADVs) TO ACTUATE FROM THE CONTROL ROOM AND REMOTE S/D PANEL, (4) FAILURE OF SAFETY EQUIPMENT STATUS PANEL TO VERIFY THE FACT THAT SEVERAL DAMPERS AND VALVES HAD REACHED THEIR DESIRED POSITION, AND (5) INDICATIONS OF PRIMARY LEAKAGE (ABOUT 2 GPM). LhDSE THE INITIATING EVENT WAS THE SEPARATION OF PALO VERDE SWITCHYARD FROM A FAULTED 0FFSill LINE AND SUBSECUENT OPENING 0F THE GENERATOR OUTPUT BREAKERS IN THE SWITCHYARD. SAFETY SIGNIFICANCE THE NUMBER OF MALFUNCTIONS THAT AROSE DURING THIS EVENT COMPLICATED RECOVERY AND COULD POTENTIALLY CONFUSE AN OPERATOR AND DELAY EVENT MITIGATION. DISCUSSION o UNIT 3 WAS OPERATING AT 100% POWER. o ALL 3 UNITS WERE ON-LINE WHEN THEY LOST THE DEVERS OFFSITE LINE: HOWEVER, UNIT 3 WAS THE ONLY UNIT AFFECTED. o UNIT 3 525KV GENERATOR OUTPUT BREAKERS OPENED UNEXPECTEDLY - REASONS UNKNOWN. o LOAD REJECT RESULTED IN A POWER CUTBACK AND RESULTED IN A CUICK "0 PEN" SIGNAL TO ALL 8 STEAM BYPASS CONTROL SYSTEM VALVES. STEAM BYPASS CONTRCL SYSTEM MALFUNCTIONED, 4 0F 8 VALVES CYCLED FROM 10% TO 100% 9 TIMES. CONTACT: A. CILEERT SIGEVENT: _YES_
~~REFERENCE:~~
10 CFR 50.72 #s 14912, 14927, 14938 AND PNO-V-89-07A .y
} f. 1 -PALO VERDI UNIT 3 z2 89 1. t; .0 REACTOR TRIPPE0 ON LOW STEAM GENERATOR (SG) PRESSURE, INITIATING A TURBlNE TRIP. 3_ 1 o MAIN STEAM LINE ISOLATION VALVES ISOLATED ON LOW STEAM GENERATOR-i PRESSURE. o ONE MAIN STEAM SAFETY VALVE LIFTED BRIEFLY AT LEAST T31CE. o ADVs DiC NOT ACTUATE FROM THE CONTROL ROOM. UPON LOSS OF-INSTRUMENT AIR, NITROGEN ACCUMULATORS SHOULD PROVIDE REMOTE OPERATION OF ADVs 1 FROM CONTROL ROOM. ADVs WERE LOCALLY OPERATED VIA HANDWHEEL. CAUSE OF PROBLEM NOT YET KNOWN. o SAFETY INJECTION AND CONTAINMENT ISOLATION INITIATED ON AN RCS-PRESSURE OF ABOUT 1837 PSIA. o LOST S01 AND S02 BUSES FOR UNIT AUXILIARY TRANSFORMERS WHICH SUPPLY ~ POWER TO THE RCPs ON TURBINE TRIP, MAIN GENERATOR C0ASTED DOWN-BEFORE FAST-TRANSFER COULD TAKE PLACE. WHEN FAST-TRANSFER WAS ATTEMPTED, THE GENERATOR AND GRID WERE OUT-0F-PHASE AND AT DIFFERENT FREQUENCIES. THEREFORE, THE FAST-TRANSFER, APPROPRIATELY, DID NOT TAKE PLACE. NATURAL CIRCULATION WAS INITIATED WHEN RCPs WERE LOST. PRIMARY HEAT REMOVED VIA 2 NON-CLASS STEAM BYPASS CONTROL VALVES-WHICH VEN1 TO ATMOSPHERE. O DIESEL gel'ERATORS CAME ON WITH SI SIGNAL, BUT DID NOT LOAD SINCE OFFSITE POWER SUPPLY MAINTAINED ESF BUSES. O SEVERAL DAMPER AND DRAIN VALVE PCSITIONS COULD NOT BE VERIFIED BY THE INDICATIONS IN THE CONTROL ROOM. HOWEVER, OPERATORS-FOUND DAMPER AND YALVE POSITIONS TO BE APPROPRIATE'UPON-INSPECTION, EXCEPT FOR THE ONE DAMPER WHOSE POSITION HAS NOT YET BEEN VERIFIED. o PRIMARY LEAKAGE WAS FOUND FROM RCP (IB) SEtl LEAKAGE. OPERATOR THOUGHT THAT SEAL INJECTION AND NUCLEAR COOLANT WATER WERE LOST. SO HE SECURED SEAL LEAK 0FF, WITHOUT ISOLATING THE RELIEF VALVE DISCHARGE TO THE RCDT AS RECulRED BY PROCEDURES. RCP (IB)= SEAL- } WAS DAMAGED, RATE OF SEAL LEAKAGE TO CONTAINMENT SUMP WAS ABOUT 2 GPM. 0 EVENT RECOVERY INCLUDED RE-ENERG121NG BUSES S01 AND'SC2, RESETTING NAIN STEAh ISOLATION, SAFETY INJECTION, AND CONTAINMENT ISOLATION SIGNALS, AND RESTARTING TVO RCPs. c UhlT 3 IS IN COLD SHUTDOWN FOR FURTHER INVESTIGATION. l l
~~,i.~~
PALD VERDI UNIT 3 89-10 1 E01LQWE o AIT IS AT SITE. o PREllMINARY NOTIFICATION HAS BEEN ISSUED. o EAB WILL TAKE APPROPRIATE FOLLOWUP ACTIONS IN ACCORDANCE WITH AIT-FINDINGS. -j ~
i '_ j ENTRANCE HEETING -[ AUGHENTED INSPECTION TEAM ANNEX - EOF CONFERENCE R00H E HARCH 4 _1989 APS Management D. B. Karner - Executive Vice President J. G. Haynes - Vice President Nuclear Production W. C. Marsh - Plant Director J. Bailey - Unit ~3 Assistant Plant Manager R. M. Butler -' standards and Technical Support-_ Director J. E. Kirby_- Nuclear Support Director J. E._ Allen - Engineering and Construction Director J. N. Tench - Site Services Director W. F. Quinn - Nuclear Safety and Licensing Director L. G. Papworth - Quality Assurance Director incident investication Team W. C. Marsh - Investigation Director H. R.- Oren - IIT Leader G. W. Sowers - Engineering -Johnson - Engineering D Gouge'- Operations F. Riedle - Operations D. H. Carnes-- Operations. H. J. Beyer - Work Control J. Reynolds-- Maintenance R. E. Your.ger - Plant Standards C. E. Day - Plant Standards T.-A. Phillips - ISEG D. A. Johnson - Compliance Auamented Inspection Team Compliance Enoineer Ph # Beeper: D. F. Kirsch T. D. Shriver 2521 H. J. Davis R. J. Rouse' 2877 3773 J. L. Knox _ J. J. Napier_.- 3954 2858-T.-E. Collins J. E. Malik 3527 3774 W. Ang K._L. McCandless Clark 3531 2825 J. F. Burdoin S. Karimi 2736 2818-W. K. Tenbrook D. A. Johnson 3703-3775 T. Polich -D. R. Larkin 3512 2709 D. .Coe T. D.' Shriver 2521 8eepers - Dial 7600, following the sound of the tone, dial beeper number, and' following the. tone, leave--a short message. m p.,+
m i 7~. -w n... w,, y:, .p h a. ARIZONA NUCLEAR POWER PROJECT TELECOPY COVER SHEET DATE: 'T h k 'Y DELIVER THE FOLLOWING PAGES TO: s./ TELECOPY # ( ) Nk O ^3'6 6Y NAME:74i Ni b NM DEPARTMEh7: m*,, o EXTENSION: .25 Ps FROM: I NAME: ~/)n 6frA M nluEs DEPARTMENT: / I 'd l-EXTENSION: /Id 9T TOTAL.W.3ER OF PAGES IN THIS MESSAGE IS /b INCLL' DING THIS PAGE. REMARKS / INSTRUCTIONS:' THIS MESSAGE IS EEING SEh7 FROM A RICOH 200 AUTOMATIC MACHINE. IF THERE ARE ANY QUESTIONS PLEASE CALL (602) 371-4202. THE AlfIOMATIC TELECOPIER NP 602) 371-4124 -COMPLETED BY: APRIL BILLj SANDY A\\-
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1 + .a m.o o-"..iMNTROLLED DOCU, MENT,.,. .. :, p y p.y 3.. :.,> u, ~.. -.7 .u..s,., w s T. w-()Mj. S PALO VERDE NUCLEAR GENERATING @*CED" STATION MANUAL. 36sT4SAo4-4 ESTAS TRAIN 1 $UB3R00P REL&Y 62 DAY C0:3 SETDOJH TULTTIONAL TEST 1 Page 44 o.- 8.13 ATA313 Relay R211* ~ t t 10 VIP'fEC ACTUATICN R1 QUIRED At"!T.AL EQUIPMDT PRETEST ACTUATION-j , j- - , ASSOCIATED POSITION /S"'ATUS POSITION /STATU:
~~LOAD 51QUENCIR 3 HDDE O MODE 0~~
~~% D33 H01 STOPPID sTCPygD - ES EXTINGUISHED + II.Lutt1NATE: - 1RDAD$ CPEN c! css QSPDS NOR?tAL ACW ATED 1~~
~~Not testen la this procedura -~~
~~- 8.13.1, Initial Equipment Status Varification...:~~
~~f...s -[ _.u.).2 -~~
~.. ' ~ M' 8.15.1.1' In.the' C'ontrol Roon notify the Operator that the -. 'F - SCP-ESTA5 Diesel ' Gen'erator Start Module and the Sequs will-not assunta upon Arsppias out. Relay E211 sinsa t-J3r.:.-TT. ' input to the 507 I5FAS D311.hodule will halumpered-c- ~ ..la. casa the sequencer $7 ART 3 the, following equipasat - START: ~ ~ 2- -n. p-l M-MAB?20A I AUX 7W PUW RM. -ESS ACU L M-EV3 P01 i E5S C0011NG VATER PW.P l1 M-MA3 205- .ECW PUC RM. ::S$ ACU - ~.~ j_ M SPB-Pol-ESS SPRAY POM ) ?UW 'll. H ECl E01 l-ES$t CIAL CMI;.LIR M MSB J01 i S/P PUM NOUS:
~~30! FAN 1 M-EC3 Pt1 1 ESS CXID VATER C RO. PUMP 8.13.1.2 In the Contrel' Room-request the Operator t'o_varify th-~~
[ Diesal Generator M-D3A-H01 is operable.- i.:-_, 8.13.1.3 -Requant the Operator to verify / position ? control Mode-- select switch J D33 RS 8~ at J.D33*101 in the CT7 post 3.33.1.4 Roguest the Operator to verify / position.handswitchi J-DGB-HS 23 at E-D01-001 la the LOCAL position.'. I ', 3.13.1.5. Request Opprater to verify / position D31reaker I-FE3-t-Disconnect switch CS,-3 en I-P31-5043 :ia the LOCAL position.,i t, va.:. UEV J ~...e... "~~- ~
7-s. %dNTROLLED DOCUMENT u m: ' [.
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~~- ;U ' GAY 'C-PALO VERDE NUCLEAR GENE, RATING gOCEME STATION MANUAL'~~
~~36sT tsA04 I~~
ESTAS TRAIN B SUBOROUP RELAY 62 DAY COLD SlWIDOWN TUNCTIONAL TEST 1 Page 49 of 74 g DO NOT LITT ANY LLADS ON T3-64 VMEN INSTALLING THE JUMPER IN STEP 8.15.1.6. LITTING LEADS WILL START THE DIESEL CENERATOR AND ACTUATE MODE 4A OF T!!E SEQUENCER. s b 8.15.1.6 Plece two parallel jumpers between terminals 9 and 10 on i the terminal board 78 44 in the Train 8 BOP ESTAS Cabinet E J-SAB-C023 Isy 2 (See Step 6.13). Ensure clean and secure contact is mado N 8.1$.1.6.1 !adopendentverificatton,requireAforjumpers,,,,,.,,__ / 8.23.1.7 In the Control Room on the ERTDADS CCD screen, verify ,,H, that the poirit SAYS$D reads: 'C. I. STAWS : OPEN. See - m- ~, section 4.'I3.~ y,' ]
~~Q ','".l.,,,. * ' ',~ '~~
g /,' ' 'e U' 8.15.1.8,,On the Channel B QSPDS page Control / Disp 1sy, dispisy page 103 and verify that'ATAS 1 reeds NORMAL. 8.15.1.9 On the SES$ panel ESB UA-25, verify that the AUX W Sci window SAA is EXIINGUISRED. u '. 8.15.2 Subgroup Relay / Equipment Actuation. I' 8.13.2.1 At the ISTAS TEST MODULE (at J.SAB C01), set the three INDIVIDUAL TEST select switches to r.he following positionsi
2) Switch (S 2) to the position 17 62

2) Switch (S 3) to the position 32 62 L

3) Switch (3-4) to the position &&
8.15.2.1.2 Independent Verification r Euired for the three t ' INDIVIDUAL TEST select switch positions. Y 8.15.2.2 Notify the Control Room Op'erator, then DETRESS and HOLD the INDIVIDUAL TEST (51) pushbutton to activate associated equipment. l 8.13.2.3 In the Control Room on the ERFDADS CCD screen, verify J that the point SDS5D reads: C.I. STATUS: CLOSED. L 8.15.2.4 On the Channel 8 QSPDS page Centrol/ Display, display EB8d 103*.,and: verify that ATAS 1 roads ACTUATED. eme see asv := m a F e ic. :., ;.. J.. i e,.. d , s. . --.t a mmm.*.. 5 .-=-***da* - - - " ~ ^
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~~PALO VERDE NUCLEAR GENERATING~~
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STATION ' MANUAL 36si-ssA04 ESTAS TRA1H 3 SUBGROUP REL&Y 62 DAY COI.D SHU;'D0'.*N TUNCTIONAI. TIST 1 Page 30 of 74 8.13.2.5 On the SES$ panel ISB-UA-23, verify that the AUX }V 3G1 p windw 5AA is ILI.UNINATED. - ~- 8.15.3 Subgroup Relay / Equipment Raset.
8. 13.3.1 AttheESTASTESTMODU:.I,rolsasetheINDIVIDUAk,TT.$T (8-1) pushbutton.

8. 13.3.2 Remove the two parallal jumpers besvatn tersinals 9 and gga 10 on tareinal Board 72-44 in the 30P ESTAS Tra.in B s*
~~Cabinet J SAB-C023 lay 2. M~~
~~8. 13.3.'2.1 Independant v,erification requi. rad.~~
Mb 8.13.3.3 If Section '8.14,1.16, 3.17 or 8.18 g.rt no.t, to be t 'I performed imediately follwing this section, notify the,.. . rr *~ ~ Control Room Oparator that he may place the following three switches to their dasired positicas:_..... '. '.... ..z -.... ..+.;
~~1) J-D;3 RS 8 (on J-DGB 301) ',~~
~~'v>~~
~~1) J-DGB-ES-23 (on I D33 C01) t-~~
.. _ 3 ) es.3. Ten t-Pan sots)1_- -- ~ - - - - .. ~.. - a f......any one of Sections 8.la, A.W8.r/ o...---.r 8.18 itre to.- be' performed imediately following this section, than this step may be N/A" ad. . J...-
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l' 03,y to/o cWY '~ PALO VERDE NUCLEAR GENERATING gesune fgfy pp / 91 Q STATION MANUAL 365T-9sA02 ) //p5 j l E$FAS TRAlH B SUBGROUP RELAY REWS@N MONTHLY FUNCTIONAL TEST 3 Page 25 of 135 I. d N N G2 @ ^ e @ 8.( IS 8 Relay / EOUIPMENT ACTUATION REQUIRED ACTUAL EQUIPMENT PRETEST ACTUATION ASSOCIATED POSITION / STATUS POSITION /$TATUS' J-5GB-UV-219 OPEN CLOSES J-5GB-UV-228 OPEN CLOSES J-5GB-UV-221 OPEN CLOSES J SGB-UV 5000 OPEN CLOSES 8.5.1 Initial Equipment status Verification. 8.5.1.1 The following steps need to be performed if this section.. is not done immediately following section 8~.4 or 8.6,_ otherwise N/A the steps. db. 1)'. 'Nott fy Chemistry that' the following four valves will?'.l'.' be opened and closed ~'
1) Blowdown Sample Cntat valve J-5GB-UV-219 1

2) Blowdown Sample Cntmt valve J-SGS UV 221

3) Blowdown Sample Cntet valve J-SGB-UV-228
~
~~4) Blowdown Cntmt Iso valve J-5GB-UV 5000~~
~~~:f=T* ~2) Notify Operator that to pre. vent possible water hammer \\~~
N'If to 5/G #1 Blowdown isolation valve, J-SGB-UV-5000, blowdown should either be isolated by taking Blowdown Selector switch J-$CN H$-1 to the OFF position or x N blowdown flow should be limited to h0RMAL blowdown N
~~flow by taking Blowdown Rate switch J.SCN-HS-18 to the NORMAL position. i, e..~~
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ih l-l /> l et w# or e: im:.#s u>t' UONTROLLE.D. DOCUMENT P.2 g.g, p, i n., r.....,. QM V PAL.O VERDE NUCLEAR GENERATING QO""" Q' STAT 10N MANUAL, 35$T-95e2 E5FA$ TRAIN 9 $USGROUP RELAY mi ION HONTHLY FUNCTIONAL TE$T 3 Page 25.of 135 8.5 K$l$ B Relay K411 E001ht!NT ACTUATION RE00! RED ACTUAL EQJIPMENT PitETEST ACTUAfica A$$001ATED P051710h/57ATUS PO$ tT10N/5TATUS J $38.UV 219 OPEN CLO$ES J $*.B UV 228 OPEM CLO$!$ J.SGB-UV-221 OPER CLO5ES J.$GB UV-5000 OPEN CLOSES 8.5.1 Initial Equipment $tatus verification. 8.5.1.1 The followine steps need to be performed if this sect.fon s. m is not done Ireediately follcwing section 8.4 cr B.6._ etherwise N/A the steps. ~ d*- - ___.1) Nctify Chemist that'the follo4ng four valves will - ~ ~ -- be cper:ed and c osed: ~ ~
1) 91cwdown $ ample Catet valve J $3B UV 219' 2, -

2) Blowdown $aepts Cntet valve J $33-U M 2:
^
3) 01cwdoKbpli'Cnist yalve}$58-Vv-22L

4) Blowcown Cntet Iso valve J $GS UV-5000

2) Notifv Opera cr that to prevent possible water baseer
~ EM'7 '~i to $IG #1 Blowdown isolation valve, J-$GB L'V 5000. ble-d - sh. le eithe, be is,1.M 93 taking nic=cewn Selector swit:h J.$CN H$ 1 tc the OFF ocsition er bloncewn flow should be limited to NORSL biondean .flo b sking Blowdowe Rate switch J-$Cri.h3-18 to the NO L position. g I - e g 4 g A: %.} I,', ;.,.. e., ~. .., a 0-c. U .p ~ . w .a.. - a m -... *. 2 ea - m v L
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/ iw ce.es ime as ueTdONTROLLED DOCUMENT P3 FOR INFC.PJ:iAT;GN ri *t' i \\/ PALO VERDE NUCLEAR GEN 8 FATING [o*'"' Q STATION MANUAL 3t$1-95A02 "" " 0" CSFA$ TRAIN 8 $USGROUP RELAf MONTHa FUMOTICHAl. TEST 3-Page 26'cf 135 M 8.5.1.2 In the Control Room request the Operator to full CPCli or verify the following four SG.1 Blowdown Semple /Biowdown / Cetet 1so valves are open, by verifying the handswitch litMN.RM) nd linht it ON a9d the creen licht il 0FF.': I[J 1 J.SG8 UV' 219 J 5GB.HS.219)' J-5GB.UV 221 J.$GB.HS-221) 31 J 5GB UV 228 J.5GB-H5-220) 4h J 5GB-DV 5000. (J 5G8 HS.5000) 6.5.2 Sub;rcup Relay /tquipment Actuation. Q 8.5.2.1 At the ESTAS TEST MODULE (et J. stb C01), set the three IMDIV!0 Val it;T select switches to the following - positions : 3 Switch 52 to the position.17 6'2 2 ~ Switch $.3 to the position 32 62 r .* 3 * $ witch $.4 to the position 34 h ' -- ~Ofd 8.5.2.1.1 Independent verificaticn required for the three, l INDIV!CUAL 1[tf select switch politions. B.5.2.2-~~ hetify control rocm operator, then DEFRISS and HOLD the ~~ IMDIVIDUAL TEST ($.1) pushbutton to activate associated equipeent. ~* 4T.5. 8.5.2.3 Jn tM centrol room verify J.$GB-H3-219 red light is 0FF' and the Creen Itgnt in Ott. M T.S. 8.5.2.4 verify J 5G8-H3 228 red light is OFF and the green light is OM. d i.$. 8.5.2.5 verify J-5GB NS.5000 red light is 0FF and the green light is OM. g T.S. 8.5.2.6 r fy J 5GB HS 221 red light is 0FF and the green lignt ,'( I,;U,
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( ^ - - ~ CONTROLLED DUUumen : FOR INEG"NiON ,m u PALO VERDE NUCLEAR GENINATING 7e C' #8 ' h. STATION MANUAL 36ST-95A02 REwsioN ESFAS TRAIN B SUBGROUP RELAY MONTHLY FUNCTIONAL TEST 3 Page 26 of 135 /8 8.5.1.2 In the Control Room request the Operator to fully OPEN or 7 verify the following four SG-1 Blowdown Sample / Blowdown Cntmt Iso valves are open, by ferifying the handswitch (RpN-B07) tpd,,]jaht,js.0N and theigreen_,11,pht i,s_,0FF/g h'
1) J-SGB-UY'-219 J-SGB-HS-219 M ',' W / I d M pt St 5

2) [J SGB-UV-228 J-SGB-UV-221 J-SGB-HS-221
/M.M M 3) J-SGB-HS-228 P MAY / 4) J-SGB-UV-5000.(J-SGB-HS-500Q) eu<L. T M 'W h'/S st A p. B.5.2 Subgroup Reley/ Equipment Actuation. Q 8.5.2.1 At the ESFAS TEST HODULE (at J-SAB-C01), set the three INDIVIOUAL TEST select switches to the following positions
~~1) Switch~~
- ? to the position 17-62 '2)~ Switen -l to the position 32-62 . -..'.-- 3) " Swi tch - J to the position 34 fi 8.5.2.1.1 Independent verification required for the three .].. INDIVIOUAL TEST select switch positions. M. .n. B.5.2.7 Notify control room operator, then DEPRESS and HOLD the . ~. $NDIVlDUAL TEST (S-1) pushbutton to activate associated (equipment. T.S. 8.5.2.3 ~ In the control room verify J-SGB-HSa219 red light is 0FF - and the green light in ON. / d T.S. 8.5.2.4 Verify J-SGB-HS-228 red light is OFF and the green light . is ON. d T.S. 8.5.2.5 verify J-SGB-HS-5000 red light is CFF and the green light is ON. M T.S. 8.5.2.6 Verify J SGB-HS-221 red light is OFF and the green light ' is ON. 't .l
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STATION MANUAL : 3651 95A02 -l ESFAS' TRAIN 6 505 GROUP RELAY HONTHLt. FUNCTIONAL TEST 3 Page 27 of 135 / 8.5.2.7 Request the Operator to OVERRIDE (Jog to CLOSE only) at-the following four handswitches, and verify the white lights are ON: 1 J-$GB HS 219 2 J-SGB-H5-221 3 J-SGB-HS-228 4 J-SGB-H5-5000 8.5.3 Subgroup Relay / Equipment Reset. M 8.5.3.1 At the ESFAS TEST HODULE release the INDIVIDUAL. TEST ' (S-1) pushbutton. 8.5.3.2 Verify the white lights are OFF on the following-four handswitches: 1p J-5GB-HS-219 i-- ...a .c 2p J-5GB-HS-221 ,Q 4h> J 5G8-H5-5000 3 J-5G8 HS 228
~~w 8.5.3.3~~
~~' The' following steps may need to be performed if mot ~ doing section 8.4 or 8.6 imediately following this ~- ~ section, otherwise N/A the steps, b~~
~~1) Notif the Control Room _ Operator that he may place~~
~~^ the following four valves to the desired positions: 1 J 5GB-UV 219-2 J-5GB-UV 221 3 J SGB-UV-228 4 J-SGB-UV-5000-Also, he may place 5/G #1 in its desired blowdown mode. [-8~~
~~2) Notify Chemistry that thel following four 5/G #1~~
~~^ valves will no longer be ou.t of service:~~
~~1) Blowdown 5a.mple Cntet yalv_e'J-5GD UV-219 2)^ Elowdoin Sample Cntmt valvefJtSGB-UV 221~~
~~~ m~~
~~3). Blowdown-Sample Cntmt valve J-5GB UV-228-~~
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~~4) Blowdown Cutmt iso valve J-5GB UV-5000'-~~
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'CUNTROLLED DOCUMhNI ~ . f "" ' '^ 0+LY 4 PALO VERDE NUCLEAR GENERATING [of"*"" O STATION MANUAL 365T gsA02 Mf ISFA5 TRAlH B SUBGROUP RELAT "E V'5'ON MONTHLY FUNCT]hNAL TEsf 3 Page ?8 of 135 8.6 AFAS 19 Relay X402, AFA$ Interposing Relays K628, K728 COUIPMENT AC_TUATION REQUIRED ACTUAL EQUIPMENT PRETEST. ACTUATION A55001ATED POSIT 10N/$7ATUS POSITION /$fATU$. J $GB UV 219 OPEN CLOSES J 5GB UV 228 OPEN CL0f15 J 3GB DV 221 OPEN CLOSES J 5GB-UV 5000 OPEN CLMES "J AFB HV 30 CLOSED OPEN/Ct.0SE$ "J AFB UV-34 CLOSED OPEN/ CLOSES J AFB HV-31 CLOSED CLOSED J AFB UV-35 CLOSED CLO5ED. v " Cycled one at a time ~* "'"~~' a-O NOTE ,,) ... e -- ~-. ~ This Relay is censidered to be HIGH.Rl5Kl refer to step S.I.7. h03 Train 8 Aux F0W REG and !$0 Valves to SG 1 (J-AFB.HV 30 and J. AFB UV-34)( and to 3G 2 (J. AFB-HV 31 and J-AF8 UV-35) will receive a ~ C105E signal upon dropping out relay $402 (maintainedcontacts)only. $G-1 valves J-AFB HV 30 and J-AFB UV 34 will be i individus11y OPENED /CLO$ED by beenergiring/Energ(iringtheassociated interposing relay cycling. contacts) in Section B.6.3. $G-2 valves J. AFB HV-31 and J AFD UV 35,wl11 remain CLOSE0 throughout this section, but the K402 maintained contacts are verified b overriding these valver in Section 8.6.y ..s e.. 4.' 3 w"- l. [ '.. i,,g' .o a.e. m u.. ~
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-. -~ - ovNynggLgguuvuumcN8 i PALO YERDE NUCLEAR GENERATING 2C'*** Q' STATION MANUAL 3657 95A02 J., ESFAS TRAIN 8 SUBGROUP RELAY "'VON MONTHLY FUNCTIONAL TEST 3 page_29 of 135 1 8.6.1 Initial Equipment Status Vertf tcation. [ 8.6.1.1 The following steps need to be performed if this section is not done imediately following section 8.4 or 8.5, 1 otherwise N/A the steps.
1) Notify Chemist that the following four,alves will be opened and c osed:

1) Blowdown Sample Cntet valve J 5GB.UV 219

2) Blowdown Sample Cntmt valve J 5GB UV.221 i

3) Blowdown Sample Cntet valve J.5GB.VY-228

4) Blowdown (:.tmt 1so valve J-5GB-UV-5000

2) Notify Operator that to present possible water
-.- hamer to 5/G #1 Blowdown'iseTatton valve. G J SCB-UV 5000, blowdown should either be isolated by 'V taking 31owdown Selector switch J 5CN.H31 to the ... 0FF positi a or blowdower flow should be limited to NORMAL bicwdown flow by taking Blowdown Rate switch. J 5CN H518. to the NOMA!. position. 8.6.1.2 In the Control Room request the Operator to fully OPEN or vsrify the following four SG 1 Blowdown Sample / Blowdown Catet Iso valves are fully open, by verifying the handswitch (RMN.B07) red lights ce ON and the green lights are OFF 17 J 5GB UV 219 J 5GB H5-219) 2 J 5GB UV.228 J 'GB HS-228 p)J 5GS-UV.221 J.SGB HS-221)) 3 AJ JSGBUV5000(J5GBHS-5000) 8.6.1.3 Requen the Operator to close or verify that the following four SG 1/5G 2 AUX Fdw Re0/lso valves are fully CLO5r.D by verifying the handswitch (MN.006) red lights are DFF and the green lights are ON: 11-J AFB HV-30 J. AFB-HS-30A '2h J3AFO UV 34 J-AFB HS-34A .m 3y J AFB-HV 31 J AFB-HS 31 A 4J J.AfD-UV-35 J. AFB HS-35A ') ,'k. ' N ( i (.,. P.08100 Alv 6N $44 a ^ s t_= .,,,w.;,,.,. d. --u.s-== - e. - - = - - - h=d
7.MTROLLED DOCUMtr.N I "H .-r c :. a: PALO VERDE NUCLEAR GENERATING fo C'0 " .Q STATION MANUAL 3657 95A02 E5FA$ TRAIN 8 5U5 GROUP RELAY RcWSION P.ONTHLY FUNCTIONAL TEST 3 Page 30 of 135 8.6.2 Subgroup Relay / Equipment Actuation'. '~ 8.6.2.1 At the ESFA$ TEST H0DULE (at J.$AB-C01), set the three INDIVIDUAL TE.5T select switches to the following positions: 1 $ witch -)1totheposition1762 2 Switch to the position 32-62 3 Switch J to the position 42 / 8.6.2.1.1 Indrpendent Verification required for the' three INDIVIDUAL TEST select switch positions. 8.6.2.2 Notif the Control Room Operator then DEPP.ESS and HOLD the INDIVIDUAL TEST (5-1) pushbutton to activate 'j n.. associated equipment.... -. c.:.,. -*0 T.S. 6.6.2.3
~~IntheControlReim,'verifyJ.$GBHS219'redlightis hW r : OFF and the green light is ON.~~
M [ 7.'S. 8 6.2.4 ~ Verify J.SGB-HS 228 red light Is 0FT and the green light ~ ..,.,,, i s OL ._ _ _,,7 3'.?'8.6.2.5 - Verify,J, SGB HS 22r red 1igh't' Is OFF and the green light ~ is UN. , s. T. $'. 8.6$256 ~ Verify J-$GB HS light is OH. '. 5000 red light is OFT and the green ] 8.6.2.7 verify J. AFB-HS 30A red light is 0FF and the green light is On. - k ' 8.6.2.8 Verify J. AFB HS-34A red light 0FT and the green light ~ - is ON. ~ d 8.6.2.9 verify J.ArB HS 31A red light is OFT and the green light is ON. B.6.2.10 Verify J.AF8 H$-35A red light is 0FF and the green light is OH. .g 6 e. e
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.Q STATION MANUAL 365T 95A02 ESFAS TRAIN B SW6')UP 4ELAY HONTHLY FUNC 4 lbT 3 Page 31 of 135 .-3,, 8.6.2.11 Request the Operator to OVERR10E (Jog to CLO$t only) at the following four handswitches, and verify the white lights are ONt. 11 J 5GB HS 219
~~2) J SGB H$ 228 3p J-$GB H$ 221 4J J 5GB H5 $000 8.6.3 Interposing (Cycling) Relay /Equiptr.ent Actuation NOTE The ESFA5 Auxiliary,. Relay Cabinet actions / verifications in this Section are~~
~~,. perforted at the Train 8 Cabinet (J-SAB C01.)~ Control Panels. These will be referred to es the ESFAS Control Panel (s).. wm ~~~
~~C.,~~
.$1E ' ~ .w - The INDIV10 VAL TEST pushbutton 51 on the ~_~~~. 8.6.2.2) isMODULE (depressed in step ESFAS TEST n..: e.. v. " ;Z-l 1.. to remain depressed throughout - - - ~ ..~ this Section. a,, 8.6.3.L.. At the ESFA5 Control Panels, verify the following four ~# " ~ ~.' indications: .... ~,... 1)' EFAS 1 ON Indicator 0565 is ON. ..v 2). EFAS 1 OH indicator VS75 is ON. ~ ~- *
~~3) EFAS 2 OH indica or 0566 is ON.~~
4) EFAS 2 ON indicator 0576 is ON. g .'r.. ty. . n. 4.w hY 'l4 3 ..s u. ,.w; aas ,eh. p h l 1 E.. ~... ..... w.m. a e v. 4E [
u.. " Cut 4 TROLLED DOCUMt:N I ' l... i .t PALO VERDE NUCLEAR GENERATING gesms , g STATION MANUAL 3657 95A02 E$FAS TRalN B $UBGROUP RELAY H3NTHLY FUNCTIONAL. TEST 3 Page 32 of 135 b 8.6.3.2 At the PPS Channel B Status Panel, verify that both the EFAS 1 Actuation $ignal indicators 1 3 and 2-4 are ON. NOTE 4 The ETA $.1 on indicator D565 and ACTUATION SIGNAL indicator 13 will go 0FF when Manual Trip pushbutton 5658 is depressed. Alarm window SB7B AFAS 1 B (LEG 13 only) will actuate when the Manual Trip pushbutton $65B is depressed. 8.6.3.3 Notify the Control Room Operator that valve J AFB-HV-30 will be OPENED / CLOSED, then at the ESFAS Control Panel. DEPRESS and HOLO the EFAS-1 MANUAt. TRIP pushbutton 565B to drop out
~~cycling relay,K628 and OPEN J. AFB HV 30. -~~
h.8.6.4 In the Control Room verif and the green light is,0Ff J-AFB-HS 30A red light is ON...--. 8.6.3.5 .At the EhfAS Control Panel, RELEASE the EFAS-1 Hanual .. Trip pushbutton $656 to CLOSE J-AFB.HY-30.- '~ J - m...- .. ' - ~ ~.- . J1 - 8.6.3.6 - In the Control Room, verify J AFB HS-30A red light is ~ ~ OFF and the green light is ON. -~ ~ 8.6.3.7' At the ESFA$ Control Panel, verify the following two.--- --- indicationst 7.~'.'.
~~1) EFAS-1 ON indicator 0565 is ON.~~
~~.~ i...~~
~~2) EEA$-1 ON Indicator D$75 is ON.~~
(( /g B.6.3.8 At the PPS Channel B Status Panel, verify that both the EFAS-1 Actuation Signal indicators 1-3 and 2 4 are ON. U.0l[ ~~ TheEFAS-1Osindicatof0$75and ACTUATION SIGNAL indicatort2 4 will go 0FF when Manual Trip pushbutton 5758 is depressed. Alarm window $878 AFAS-1 0- .3 c.. (tEG2-4only).will'actuatewhenthe' Manual Trip pushbutton $758 is depressed. 8.6.3.9 Notify the Control Room Operator that valve J. AFB UV 34 '~'~~~ ~) will be OPENED / CLOSED. then at the ESFAS Control Panel. .s t DEPRESS and 110t0 the EFA5-1 hanual trip pushbutton 5700 to drop out cycling relay K728 and OPEN J-MD-UV-34. % =e u n u u.. .g h, l <,,
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~~C STATION MANUAL 365T-95A02 aswse E5FAS TRAIN 9 $UBGROUP RELAY HONTHLY FUNCTIONAL TEST 3~~
Page 33 of 135 _,,_,, T. 5. 8.6.3.10 In the Control Room, verify J AFB HS 34A red light is ON and the green light is OFF. 8.6.3.11 At the ESFA$ Control Panel, RELEASE the EFAS 1 Hanual Trip pushbutton $758 to CLOSE J AFB-UV-34 8.6.3.12 in the Control Room, verify J. AFB HS 34A red'11ght is 0FF and the green light is ON. 8.6.3.13 At the E$FAS Control panel, verify the following two indications:
1) EFAS-1 ON indicator 0565 is OH.

2) EFAS 1 ON indicator 0575 is ON.
~~B.6.3.14 At the PPS Channel B $tatus Panel, verify that both the. 4 , EFAS-1 Actuation Signal indicators 1-3 and 2-4 are ON. 8.6.4 AFAS-l'B Relay X402 Haintained Contact verification Q.. .l ..~'.l~$ ~~~
~~u. _~~
~~NOTF . ~ -~~
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. -[ Stept 8.6.4.1 through 6.6.4.4 ' verify that m the AFAS-1 relay X402 maintained contacts operate correctly by providing a CLOSE signal in the associated AFAS-2 valve. ,7.'.- - tircuits(J6 AFB-HV31andJ.AFBUV35). NOTE ~ The INDIVIDUAL TEST pushbutton 5-1 on the E$FAS TEST MODULE (depressed in step 8.6.2.2) is to remain depressed throughout this Section. 8.6.4.1 In the Control Roem, request the Operator to OVERRICE J. AFB-HV 3] by momentarily depressing J-AFB HS-31C' (ATAS O' RIDE), and verify J AFB-HS 31,A (RMN-805) white light is ON. 8.6.4.2 Request the Operator to OVERRIDE J-AFB UV-35 b "* momentarily deppessing J AFB HS 35C (AFAS O'R'Ib!) and .m verify J-AFB-HS-35A (RMN UO6) white light is ON.
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.~...-. GvNTROLLgg DOCUMEN I.. t PALO VERDE NUCLEAR GENERATING QCED" h.. STATION MANUAL 365T 95A02 1 E$FA$ TRAIN B SU8 GROUP RELAY HONTHLY TUNCT10NAL TEST 3 Page 34 of 135 l 8.6.5 $ubgroup Relay / Equipment Reset 8.6.5.1 At the E$FAS TE$T HODULE, release the INDIVIDUAL. TEST ($-1)pushbutton. 8.6.5.2 Verify the white lights are OFF en the following four handswitches ^ ~ 1 J-$GB HS 219 2 J 5GB.HS 228 3 J 5GB HS 221 4 J 5GB HS 500Q Rehuest the Control Room Operator to verify that. the B.6.5.3 following four valves are CLOSED: ....... ~ t.,,\\.
~~$,?_~~
~~.y. 3)p g A 1 .HV-30 e 2 J AFB UV 34 f J. AFB HV 31,,,,, - ~ Ah J. AFB UV-35 ,8.$ $.4, ~ doing section 8.4 or 8.5 incediately follow not-section, otherwise N/A tfie steps. [~~~
~~1) Notify the Control R'com Operator that he may place the following four valve.s to the desired positionst~~
- ~ ' ' ~ Il J 3GB-UV-219 2h J 5GB UV 221. .1 .~ 3g 0-$GB.uy.228 4J J-5GB UV 500Q, Also, he may place $/G #1 in its desired blowdown l mode. 2) Notify Chemist 30nger be out of service:that the follo valves wil.1 no
~~1) Blowdown $ ample Cntmt In14e.J.SGS-UV 219 l~~
~~2[~.BlowdownSampleCntatvalveJ5GBUV221 .m ~ ...,,s. ~ l~~
3) Blowdown $ ample Cntmt valve J-SGB UV 228 i

4) _ Blowdown Cntmt 150 valve J SGB UV 5000
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CONTROLLED DOCUMENI r PALO VERDE NUCLEAR GENERATING $0C"U"E l Q-STATION MANUAL 3657-95A02 v i E$FAS TRAIN B $USGROUP RELAf "EY' O N HONTHLY FUNOTIONAL TEST 3 Page 117 of 135 l 8.37 H515 9 Relay K105 EQUIPMENT ACTUATION REQUIRED, ACTUAL EQUIPMENT PRETEST ACTUATION A$5001ATED POSITION /$TATUS POSITION / STATUS i J 5GB-HV 200 OPEN CLO$t$ J.$GB HV 2DI.' OPEN CLOSES ERFDADS ^ OPEN CLOSED 0$PD$ NORMAL ACTUATED SESS EXTINGUISHED ILLUMINATED 8.37.1 Initial Equipment Status Verification. N '. 8.37.1.1 In the Control Room request the Operator to open or . - verify the following two valves are fully OPEN, by .2 .4 verifying the handswitch (RMN.506) red light is ON and O the green light is OFF. ~~ ' ~ ' ' ~ 1)' 3G I Chem Inj !so va1ve J 3GB HV 200- ~" . - - 2) SG 2 Chem Inj 150 valve J SGB.HV 201 8.37.1.2-On he ERFDADS CCD screen, verif thatkhepointSAYS3D _. reads: C.I. STATUS: OPEN See Section 6.3.11. 1 8 37.1.3 On the Channel 8 Q$PDS page Control / Display, display page 103 and verify that HSIS reads NORMAL. k' 8.37.1.4 'On the SESS panel ESB-VA-28, verify that the NAIN.5 TEAM ~ _s )!$0Lwindow2AKisEXTINGU15HED. (. j ~_- 8.37.2.3ubgroep Relay / Equipment Actuation. /i 8.37.2.1 At the ESFA5 TEST MODULE (at J SAB-001), set the three INDIVIDUAL,TEll select switches to the following positions:
~~1) Switch 5-2)totheposition17-62 l~~
. 2) Switch 5 3) to the position 32-62 ..s e- '3) $witoir 5-4).to the position 41 8.37.2.1.,1 Independent Verification required for the three ll:DlV! DUAL TEST select switch positions. / f *. :.. '. ' l - m. .m.: m l .. k:. 2- - & " ~ ~ ' '- E' ^ " " ~ _ s s. .--c ....w. 7,.. - -.. = ,. -,, ~, ., ~
~ ~* ' 'vuNTROLLED Uuvuman i PALO VERDE NUCLEAR GENERATING 7e caouns Q.. STATION MANUAL 36ST 95A02 ESFAS TRAIN B SUBGROUP RELAY "EV38'ON HONTHLY FUNCTIONAL TEST 3 Page 118 of 135 8.37.2.2 Notify the Control Room Operator, then DEFRESS and HOLD the INDIYlDUAL TEST (S 1) pushbutton to activate associated equipment. 2 8 T.S. 8.37.2.3 in the Control Room verify J-$GB HS 200 red light is 0FF and the green light is ON. 8 7.2.4
~~Verify J $GB HS 201 red light is OFF and the green is ON.~~
2.rew+f 8.37.2.5 On the ERFDADS CCD screen, veri'y that the point SAYS3D readst. C.I. STATUS: CLOSED. See Section 6.3.11. 48 8.37.2.6 On-the Channel B QSPDS page Control / Display, display page-103 and verify that MSIS reads ACTUATED. M 8.37.2.7 On the SESS panel 'ESB-UA-28, verify that the MAIN STEAM 1. ISOL window 2AA is ILLUMINATED. - / A - 8.37.2.8 hquest the Operator to 0VERRIDE (Jog to CLOSE only)ite at T the following two handswitches, are verifying the wh C.]~ light is ON. 2)) 1 J SGB-HS-200 ~~ ~~ J-3GB HS 201 8.37.3 Subgroup Relay / Equipment Reset. "b 8.37.~3.1 'At the ESFAS TEST H0DULE release the INDIVIOUAL TEST ~. ($-1) pushbutton. k. 8.37.3.2 Verif / hands (itches:the white lights are OFF on the foTlowing two
1) J-SGB-HS 200

2) J SGB-HS 201 h
~~8.37.3.3 Notify the Control Room Operator that he'may place the following two valves to the desired positions:~~
1) -J SGB HV-200

2) J $GB-HV 201 5A+pys%,t.3.if-C
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t J 4 AGENDA FOR ELECTRICAL MEETING MARCH 16, 1989 I. PVNGS AC ELECTRICAL SYSTEM DESIGN II. PVNGS TRIP EVENTS EVALUATION III. SCHEDULE AND RESULTS OF ELECTRICAL SYSTEMS CONFIGURATION AND RELIABILITY STUDIES i
l'
r i ,p,v lll ') o t/ PVXGS LICENSING ACTIVITIES PSAR SUBMITTAL AND REVIEW IDRs (INDEPENDENT DESIGN REVIEWS) PERFORMED BY PVNGS FOR NRC - PVNGS presented PSAR Positions to NRC Staff ^ Reviewers / Plant Participants / Industry Reps. In Aid of NRC Review. 4 - NRC an Active Participant - AC &DC Power Systems Presented CP AWARDED FSAR SUBMirrAL AND REVIEW ACRS HEARINGS ASLB HEARINGS OL AWARDED 1 Arizona Nuclear Power Project
~.- { AC DISTRIBUTION SYSTEM DESCRIPTION 500 KV Switchyard Start.Up Transformers / Switchgear 13.8 KV Transmission Lines Normal Power System; 13.8 / 4.16 KV,480 V Class IE Power System; 4.16 KV,480 V Emergency Diesel Generators Protective Relaying Same Connnected In StartUp/ Shutdown Configuration b Arizons Nuclear Power Project
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f SPECIAL DESIGN FEATU.RES Fast bus transfer system Reactor Power Cutback System o S S R. Relay System 1 Arinma Nuclear Power Project
. - -- c. *~ ~ ~~~ AUTO FAST (SEQUENTIAL) TRANSFER DESIGN
~~Purpose:~~
o Provide power to Non Class IE Power system (esp. RCP's) for longest tirne possible. Operational Modes: 13.8 KV Bus voltage degraded with offsite power available. o Generator protection relays initiate Auto Fast Transfer (such as Gen. Differential, Gen. Loss of Field. Gen. Negative. Sequence, Unit Aux. Differential) Auto Fast Transfer occurs if 13.8 KV bus and 13.8 KT preferred bus can by synchronized. Otherwise Auto Fast Transfer is designed not to initiate. o Main generator disconnected from grid (main generator breakers open), but energized. SSO Relays, Main Generator Backup Distance Relays, manual operation initiates this condition. Auto Fast Transfer is designed not to initiate. o Generator disconnnected from the grid. preferred bus degraded, reactor and turbine trip Coast down scheme initiated to feed RCP's from generator as long as possible Auto Fast Transfer is designed not to initiate i
,.~, j ) i Reactor Power Cutback System The Reactor: Power Cutback System consists of the Reactor Power Cutback Module and a separate manual input control panel located in the control room. Its purpose, in conjunction with other NSSS control systems, permits the NSSS to remain at power following a : ~
~~1) Large load rejection.~~
~
~~2) Loss of one of two operating Main Feedwater Pumps.~~
0' ArhonaN clearrowerProject
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.l ~ kbkWER v WM = SBCS = MEkvss m,mo, V ifELR > FWCS RE = myew = E M,. mys, RPCS = MI, ARM / DROP v y " ' " ^ " j[(,= RRS > CEDMCS =
~~c "3 REACTOR CONTROL SYSTEM RTMDT I si12D T4T OPTC DT AGR AA4~~
,.,._.o.ur RPCB RESPONSE FEEDWATER TRA.NSIENTS Scenerio: Lose 1 of 2 MFW Pumps. Result: Rx and unit remains on line at 20-60% power - RCP's powere'd from Unit Aux Transformers 1. RPCB reduces Rx power to 40-75% 2. RPCB runs back turbine to 60% and then adjusts to equilibrium 3. RPCB inhibits SBCS quick open if > 60% (to avoid over cooling SG) 4. ~ FWCS, RxReg maintain NSSS/ BOP equilibrium [ CRS Arizona Nuclear Power Project i
T.- 5 a J ELECTRICAL NON-TRIP RELATED ISSUES ADDRESSED AT PVNGS ISSUE Rf. CVE RELAYS IN FAST TRANSFER SCllEME Completed BUCK-BOOST TRANSFORMERS NEEDED ON SOME AC CIRCUTFS Completed AGASTAT RELAYS (General Purpose Types on the DG System) Comp'leted CALVERT BUS PROBLEMS Completed SUPER SYNC 11RONOUS RESONANCE in progress RELAY PROB! SMS (HEA, IIFA, HGA, etc.) In progress BATTERY STRATIFICATION Completed MAIN XFMR CABINET COOLING Completed ISO-PHASE BUS; CRACKED INSULATORS Completed GE ARC CHUTE PROBLEMS Completed NORYL INSULATION (GE) Completed GE FUSE BLOLi'S Completed TERMINAL BLOCKS Completed DIESEL GENERATOR POLE-PIECES Completed GROUND FAULT RELAYS In progress COOLING TOWER SWGR CORROSION Completed SRP SWITCHYARD PROBLEMS Completed SWGR BREAKER CHARGING MOTORS Completed ARD RELAYS Completed WATER INTRUSION IN THE POWER-BLOCK SWITCHGEAR, LOAD CENTERS & MCC's Completed 500 KV ELECTRICAL CONNECTIONS / HARDWARE Completed [ JTB 8/1U89 Arizona Nuclear Power Project
1 '7 ,3 i PROJECT EVALUATION STATUS Descriptions Phase 1 - Evaluation of PVNGS performance on its own i base and against the industry. Phase 2 - Incorporation of the results of the Electrical Reliability Studies. Phase 3 - Incorporation of the results of the EEP IE Systems Reviews t Phase 4 - Incorporation of the results of the EEP non-IE Systems Reviews l Schedules /.) Arizona Nuclear Power Project
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~ ~.l , j-PHASE 2 PHASE 1 FINALIZED a) AC Reliability Study b) SRP Switchyard Study c) Lightning Evaluation d) Station Blackout Study l. e) Relay Setting / Coordination Evaluation i ? Arizona Nedear Power Project
3,. PHASE 3 ~ EEP SYSTEM WORKING GROUP REVIEWS OF IE SYSTEMS The EEP system review working groups for the Q class electrical systems will factor the findings of the Phase 2 report into their evaluation of the design basis and will also factor their evaluation findings back into the report, in order to accomplish the Phase 3 report. The Q class electrical systems are as follows: a) PB - Class 1E 4.16-kV Power System b) PE - Class 1E Standby Generation System c) PG - Class 1E 480-V Power Switchgear System d) PH - Class 1E 480-V Power MCC System l e) PK - Class 1E 125-V DC Power System f) PN - Class 1E Instrument AC Power System b Arizona Nudesr Power Project
~ ~9 PHASE 4 ^ EEP SYSTEM WORKING GROUP REVIEWS OF NON-IE SYSTEMS The EEP system review working groups for the Non-Q electrical systems will factor the findings of the Phase 2 report into their evaluation of the design basis and will also factor their evaluation findings back into the report, in order to accomplish the Phase 3 report. The Non-Q electrical systems are as follows: a) MA-Main Generation System b) MB - Excitation and Voltage Regulation System l 1 c) NA - Non-Class 1E 13.8-kV Power System d) NB - Non-Class IE 4.16-kV Power System e) NG - Non-Class 1E 480-V Power Switchgear f) NG - Non-Class 1E 480-V Power MCC System i g) NK - Non-Class 1E 125-V DC Power System h) NN - Non-Class 1E Instrument AC Power System l i) NQ - Non-Class 1E Uninterruptible AC Power System D L
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1 2 e n 3 E E Ry Sy yd e oy t y E Pa EPt I e r d Pd a ot id hd eon ttau ge s us S S Cu Rtu l S Im SEy t it t P. s A A AS 3S RCE SS LS A IR AES I 11 I H I I I P P P 1
i, PROJECT EVALUATION OLTPETS U Phase 1 - Lessons. Learned j - Preliminary Recommendations ~ for Consideration Phase 2 - Lessons Learned - Recommendations forImplementation j Phase 3 - Refinement of Phase 2 i Phase 4 - Refinement of Phase 3 i l l 1 l. 1 I N -l ~ I 6
s ? -f ~ 89-15 Sj GENERIC 11SJ1E = _CCI ATMOSPHERIC DUMP VALVES (UPDATES) PROBLEM _ AIR OPERATED ATMOSPHERI DUM,P VALVES MANUFACTURED BY CONTROL COMP 0NENTS INC (CCl) N R MAND AT PALO VERDE AND AT OTHER PLANTS. ChDSL CAUSE BEING INVESTIGATED. MAY BE COMBINATION OF DIRTY AIR, VALVE STEM BINDING, UNDERSIZED VALVE PILOT, AND NITROGEN PRESSURE REGULATOR. . SAFETY SIGNIFICANCE ATMOSPHERIC DUMP VALVES (ADVs) ARE REllED UPON FOR EMERGENCY PLANT C00LDOWN INCLUDING STEAM GENERATOR TUBE RUPTURE. DISCUSSIOR o ON MARCH 3,1983, PALO VERDE UNIT 3 EXPERIENCED A LOAD REJECTION TRANSIENT WHICH CHALLENGED THE STEAM LINE ADVs. O ALL FOUR ADVs AT UNITS 1 AND 2 WERE TESTED AND SOME MALFUNCTIONED. o lhFORMATION NOTICE 89-38. o VALVE VENDOR CCI CONTACTED BY NRC STAFF AND REPORTED A PCTENTIAL DESIGN DEFICIENCY. O CCI INFORMED CUSTOMERS OF THE POTENTIAL DEFICIENCY UNDER 10 CFR 21, DATED APRIL 4, 1989, o PLANTS IDENTIFIED FOR CONCERN BY CCI AS HAi!NG ADVs SIMILAR TO THOSE AT PALO VERDE ARE: WATERFORD 3 - TWO VALVES CATAWBA 1 8 2 - FOUR VALVES EACH SAN ONOFRE 2 8 3 - TWO VALVES EACH o NRC STAFF REQUESTED JUSTIFICATION FOR ADV OPERABILITY FROM AFFECTED PLANTS. O ADVs TESTED AT SAN ON0FRE 3. ONE OPENED SLOWLY (1 MIN). CONTACT: W. JENSEN SIGEVENT [
~~REFERENCE:~~
10 CFR 50.72 #s 14932, 14927, 14938, AND MORNING REPORT 7 04/10/89
3. U! =, g..-
~~lI GENERIC ISSUE- -89-15;~~
~~,j-o SAN ONOFRE 2 ADVs TO BE-TESTED LATER THIS WEEK (04/10 - 04/14/89). L o ADVs TESTED AT CATAWBA 12. ONE ADV FAILED TO OPEN. CORRODED j PISTON RING FOUND. He~~
~~o. CCI REQUESTED MEETING WITH NRC STAFF.-~~
o CCI MEETING SCHEDULED FOR 1:30 P.M. APRIL 13, 1989, ROOM OWFN, 2F-17. FOLLOWUP o PLANT-JUSTIFICATION FOR ADV OPERABILITY TO BE REVIEWED BY NRR AND THE-REGIONS. o ROOT CAUSE OF VALVE FAILURE TO BE REVIEWED BY NRR. 9 l ~.m y
~. _ _ _ - _ _ _. -._...-_. _ _ _ ~ _.... _,[* MAR 20'89 8:40:o CONTROLCOMPONENTS7148581878= ' LlIP.'.$/ 6 l 1
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