ML19327A650

Discusses Activities for Wk of 890627-0703.On 890622, Transient Occurred at Seabrook Due to Steam Dump Valve Failure.Manual Scram Initiated

ML19327A650
Person / Time
Site:	Seabrook
Issue date:	06/27/1989
From:	Hodges M Office of Nuclear Reactor Regulation
To:	Thadani A Office of Nuclear Reactor Regulation
Shared Package
ML19327A649	List: ML19327A648 ML19327A650 ML19327B267 ML19327B268
References
FOIA-89-209, FOIA-89-309 NUDOCS 8908100098
Download: ML19327A650 (44)

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NEMORANDUM FOR:

Ashok C. Thadani, Assistant Director I

L for Systems Division of Engineering & Systems Technology l

t FRON:

M. W. Hodges, Chief Reactor Systems Branch Division of Engineering & Systems Technology

SUBJECT:

ACT!YITIES FOR THE WEEK OF 6/27/89 - 7/3/89 A.

potential EDO Items /SRXB Highlights i

i At the Seabrook Station on June 22. 1989 While operators were attempting to establish natural circulation, a transient occurred due to a steam dump failing open. A manual scram was initiated.

Reactor power was about 3% at the time.

An Ali is being dispatched and will include L. Lois as a participant.

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New Hampshfre MEMORANDUM SSPf 890965 i

i BASIS FOR THE MINIMUM PRESSURIZER LEVEL TRIP CRITERIA FOR THE NATURAL

$vbject CIRCULATION TEST 1-87-22 From R. A. Owinn Dole June 29, 1989 To P. V. Curney Reference Westinghouse Precautions, f

Limitations, and Setpoints t

(PLS)

The following is a response to the question regarding why the Natural circulation Test, 1-ST-22, required a manual trip at a pressurizer level below 171.

The manual reactor trip requirement on pressuriser level of 172 is baced upon the ability to operate plant in a condition where reactor coolan?

1 system pressure is capable of being maintained, and without violating plant

,L technical specifications (3.4.9.2 item c).

At a pressurizer level of 17! and decreasing, the reactor coolant system flow to the chemical volume control system is isolated and the preseurizer heater groups are automatically deenergized. This is a normal syatem r

control function as defined in the above Reference. Once reactet coulant system letdown flow is isolated and pressurizer heaters are der 'iz 3 the ability to use auxiliary spray to reduce pressurizer is great):. rdnimited since the charging flow to the reactor coolant system to no longer neated though the regenerative heat exchanger. Without this charging flow preheating via the regenerative heat exchanger the differential temperature between the pressurizer spray nozzle and the fluid can be exceeded if i

auxiliary spray flow is used. Without the use of auxiliary spray and backup i

heaters pressurizer pressure.is not controllable and further test performance cannot be expected to continue. Since it is not the intent to perform startup tests that'would violate technical specifications or plant i

design parameters the manual trip criteria of 172 pressurizer as vell as the other trip criteria were established to be utilized as anticipatory reactor I

, trip requirements to stop the test should specified plant. conditions be l

exceeded.

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W R. A. Owinn l

ccs D. E. Hoody l'

J. M. Grillo G. J. Kline G. A. Kann L. V. Rau W. J. Temple 1

New Hampshire Yonlee Division of Public Service Company of New Hompshire rI ))

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P.O. Box 300

• Seobrook, NH 03874

• Telephone (603) 474 9521

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C O N D.E N S E R STEAM DUMP VALYE E V A L U A.T I O N I

M Prepared by)tf Bibber, Systf!n Engineer

$//o/M Date t

ChOm R M "C_ et 11c2th ce/sc/e9 C. P. McCafferty, I&C System Eng1nter Date P

k Reviewed by b&1 [d d /30/89

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ade, Lead 80P Engineer Date k\\t b /3) /b A. Kodal, Sys ;em E'ngineer Date

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.r CONDENSER SYEAM DUMP VALVE EVALUTA!0N l

CONTENTS 1.0

SUMMARY

2.0 RECOMMENDATIONS

3.0 DESCRIPTION

OF VALVE AND ACTUATOR I

4.0 MS-Y3011 : WHY IT MALFUNCTIONED I

t 5.0 BALANCE OF CONDENSER STEAM DUMP VALVES i

l 6.0

'A' TRAIN

'B' TRAIN AND OUAL TRAIN LOGIC CHECKS 7.0 ATTACHMENTS A) SYSTEM SUPPORT CHRONOLOGICAL LOG B) PHOTOGRAPHS C) SYSTEM SUPPORT MEMO SS 49036, Secondary Plant Valves with A and B Train Logic b

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SUMMARY

The twelve condenser steam dump valves are pilot operated, air to open, Copes Vulcan Valves.

(See Photograph No. 1.)

l Il d The cool down bank consists of three valves, MS-V3011. V3015 and V3019.

j At the beginning of preparation for the natural circulation test, MS-V3011 I

was known-to be non-operational, because WR87 WOO 5592 was still open for

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stroke test at NOP/NOT.

MS-V3015 was known to be non-operational, because it was isolated, due to air leaks.2 I

However, MS-V3011 was used, and_it failed to operate correctly. The I.

reason MS-V3011 failed to cperate correctly was due to mechanica,1 binding within the val e bg (See Photographs No. 2, 3, 4 and 5.)

MS-V3015, although it was isolated due to air leakage, also had mechanical i

binding and could not be stroked.

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The reason for the mechanical binding in Valves MS-V3011 and MS-Y3015 is I

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.I that the valve actuators were misaligned with the valve stems.

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, _-V3019: This valve, at the present time, can be stroked with minimum I

binding, but as it is used, the binding can be expected to increase until

.g it is solld.

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L-7 Therefore, two of the three. valves in the cooldown bank are non-fl operational, due to binding, and the third valve has the initial signs of LJ binding.

The remaining valves have been evaluated. All the actuators have to be p

disconnected from the valves and checked for alignment, and the valves s

have to be checked for binding.

(See Section 5.0.)

The 'A' train, 'B' train and dual train logic checks show that the. valves

'g will perform their design functions, once the valve and actuator problems t

have been rei,olved.

(See Section 6.0.)

N Maintenance work on these valves consists of an I&C RTS to check the l

calibration and positioner every two years. We feel that the maintenance on these velves is adequate, and although not specifically instructed on the RTS, the I&C technicians do, in fact, check the valve positioner, linkage and look at the packing, etc. as ' skills of the worker', and, there-fore, no changes in maintenance practices are required. However, as this j

is a two year RTS, it must be perfonned when due and not delayed.

g As stated earlier, the condenser steam dump valves are pilot operated

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valves.

This is not the first pilot operated valve which has experienced stroke problems. We, therefore, feel that other secondary valves should be observed. System Support memo SS49036, dated June 27, 1989 (Attachment C),

outlines this work. The valves listed are not necessarily Copes Vulcan valves, but valves that have 'A' train, 'B' train and dual train operation; the major secondary plant valves.

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Throughout this evaluation, which was started on Thursday, June 22nd at 7

I 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />, to Friday, June 30th 1989, various steam dump valves have been stroked. _.,It has become apparent _t. hat.t.he. mpre you stroke the valves with

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.the actuator misalignment, the worse the valve movement becomes (i.e.,

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binding of the valves gets worse with stroking the valve).

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.g RECOMMENDAT10NS 1.

All twelve condenser steam dump valve actuators should be removed and checked for smooth operation. Replace all actuators which cannot be

'l made to stroke correctly.

g 2.

Disassemble all twelve valves and check for signs of binding.

Particular attention must be paid to plug rings, and valve stem inter-l' ference within the packing gland follower.

g 3.

On reassembly, perform static stroking of the valve to ensure correct operation.

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Before entering Mode 2, all valves should be dynamically stroked at l'

NOP/NOT several times and the results evaluated.

Incorporateadesignmodificationtoensureapositivelockingarrange-f g'

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ment for the pnsitioner feedback linkage, thereby having positive l

-l locking.

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Complete and evaluate results of System Support Memo SS 49036; other secondary plant valves to be evaluated.

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g DESCRIPTION OF VALVE AND ACTUATOR j

The steam dump system is comprised of twelve power operated steam dump valves which are arranged in four operating banks with three valves per bank. The system is capable of passing foYty percent of the full steam

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load into the condensers. The steam dumps are six inch, air actuated plug valves that fail closed on loss of air or electrical signal.

Each steam dump valve's normal full-open flow is 510,000 lbs/hr at a steam header pressure of 1,100 psia.

The valve assembly consists of the valve body with its internals, a reverse-acting diaphragm operator, a direct acting positioner and a hand wheel operator.

The valve's main body houses the tandem plug arrangement (Figure 1),

the balancing chamber and the valve seat. The valve bonnet is bolted to the valve body to provide a pressure boundary. The upper frame is mounted to the valve bonnet and has a valve position indicator mounted on it.

The valve actuator is mounted partially to the frame and partially to the valve yoke.

l The valve operator (Figure 2) uses a diaphragm plate, yoke, cover and spring to position the steam dump valve. The diaphragm plate is connected by long cap screws and spacers to the frame, which is fixed to the bonnet, and is, thus, stationary. The operator base and cover are assembled to the yoke, which, in turn, is assembled to the valve stem and plug. The upper seating surface of the compression spring is fixed against the diaphragm 3.1 I

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plate and the lower seating surface of the spring rests on the adjusting screw and nut. Thus the spring, through the adjusting screw and nut, is g_

supported at the lower seat by the yoke, so that the compressed force of l

the spring is placed against the diaphragm plate (which is stationary) and against the yoke, stem and plug assembly to force the plug toward the

.g closed position.

The valve assemblics are also provided with direct acting positioners. The direct acting positioner is a two-stage amplification, ' push-pull' action, force-balance tvpe control instrument located in the control loop between the controller and the valve actuator. A change in the pneumatic controller signal results in an output pressure change from the positioner. This l

change is directed to the diaphragm chamber of the valve actuator causing the valve to be repositioned. As the valve is repositioned, a linkage attached from the valve yoke to the positioner causes a feedback force to g

be exerted on the positioner bellows resulting in a counterbalance of the pneumatic controller signal. The circuit is designed to result in a con-l tinued loading change on the valve's diaphragm by the positioner until the valve has actually repositioned itself and has rebalanced the initial pneumatic signal change.

This arrangement provides fast, accurate, posi-tive positioning of the valve.

The tandem plug design allows for a positive force to ensure tight seating

'I when the valve is closed. The tandem plug is located inside the balancing g.

chamber, which also guides the valve plug throughout its complete stroke.

The inner plug is an integral part of the valve stem.

Steam header pressure l'

is equalized across the balancing chamber via the leakage past the plug 3.2 1

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E rings. This pressurizes the area above the plug ensuring a positive seating force on top of the valve's main plug.

4 During operation, the valve stem moves upward, unseating the inner plug and opening a bleed port between the valve's outlet chamber and the pressurized g

area above the plug. That bleed port is larger than the leakage area around the plug rings. Because of the small area of the inner plug that is exposed to steam' header pressure, the inner plug is easily opened. With the larger port open to the valve's outlet, the upper chamber pressure bleeds to the outlet port through holes drilled in the: plug bushing. That g

equalizes the pressure across the main plug, removing the positive seating pressure.

Further movement of the valve stem causes the stem shoulder to stroke the main plug and unseat it from its seating surface.

An inherent design feature holds the main plug rigid against the valve stem shoulder. The area above the main plug in the balancing chamber is slightly smaller than the seat bore area created when the valve is opened. That creates a difference in pressure that maintains the main plug and inner I

plug in their proper positions during operation.

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When the valve is closing, the main plug is seated first.

Further stem movement lowers the inner plug to its seat on the main plug. When the inner plug is in that position, inlet pressure builds up again on top of l

the tandem plug to ensure tight seating.

g The steam dump valves are also provided with manual operators. The hand l

wheel attached to the top of the actuator is used to position the steam l l dump valves when air or electrical power is not available.

The valve hand 3.3 o

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wheel is attached to the valve cover, and its stem contacts the steam dump valve actuating mechanism. Operating the hand wheel forces the manual actuator stem to act on the valve diaphragm plate. This creates a counter-force on the valve cover which is transmitted to the valve stem.

That force overcomes spring tension and opens the steam dump valve.

LJ The steam dump valves and their controls are designed to meet three i

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requirements.

• The valve shall go from full closed to full open within three seconds from l

5 receipt of trip open signal (including response of solenoid valves).

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• The valve shall go from full open to full closed within five seconds af ter deenergization of solenoid valve.

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• The valve shall be capable of being modulated with a maximum full stroke time of ten seconds or less to open and twelve seconds or less to close.

Steam Dump Valve Data:

Manufacturer Copes Vulcan h

Model 0100 Quantity 12 E

Size 6"

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Capacity 510,000 lb/hr Actuator 160 Material ASTM A216, Gr. WCB Body Positioner Bailey AP2 Positioner

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4.0 j

MS-V3011 : WHY IT MALFUNCTIONED g

On Thursday, 22 June 1989, at approximately 1313 hours0.0152 days <br />0.365 hours <br />0.00217 weeks <br />4.995965e-4 months <br />, a Priority One work l

request was issued from the control room. The work request number was g

89 WOO 3110, and it instructed I&C to troubleshoot Condenser Steam Dump Valve MS-V-3011.

Working with the control room, the valve was stroked with an !&C technician f

at the valve. The valve failed to move, and it was noticed that the booster relay,1-MS-PY3011-1,-was

• bleeding air at-a- hghyste. The booster relay I

was changed out, but this did not so,1ve,the, prob,13. The valve posit g was tnen checked for proper calibration, and it was found that the valve j

positioner feedback linkage was disconnected.

1 The reason for the linkage being disconnected is that the screw holding the linkage to the positioner feedback arm was not long enough, and the nut,

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which was only engaged by approximately two threads, had fallen off.

j (See Photograph 6).

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After the positioner feedback linkage was connected, calibration of the positioner was performed. On the first attempt, the valve would not open l

more than 50% of stroke; air was slow 1',

oled off the actuator, and the valve moved to 20% open in an erratic manner. When all the air was bled I1 off the actuator, the valve slamned closed by the spring force, breakin'g l

lg the hand wheel.

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'5 It is concluded that the effect of the positicner linkage being discon-nected is secondary, and the primary reason the valve did not operate i

correctly was due to mechanical binding within the valve.

5 Further evaluation has shown that the valve actuator is tilting at the top g

and bottom of its stroke. This tilting motion will not allow the valve stem to move up and down smoothly.

The valve stem and plug have some very

[9ht tolerances.,,and this misaligryment caused galling be. tween the valve E

stem and the guide bushing, which, with successive stroking of the valve, worsened and ultimately lead to total stezure between the stem and the.-

g guide bushing.

(See Photographs 2 through 5.)

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' g BALANCE OF CONDENSER STEAM DUMP VALVES On June 26, 1989, a work request, 89 WOO 3173, was initiated to examine the g

Unit.1 steam dump valve. The scopa of the work was as follows; the valves

'g were to be stroked; run out of stem; positioner linkage and smoothness of operation was to be checked on each valve.

Results of the work request are as follows.

l 1-MS-PV-3009 no problems found; s

1-MS-PV-3010 no problems found; 1-MS-PV-3011 this valve was not stroked, due to damage already found; 4----

1-MS-PV-3012 the stem was lightly scored; positioner linkage is tight t--

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and the valve operates smoothly; g

1-MS-PV-3013 no problems found; 1-MS-PV-3014 the positioner ann and linkage was found to be loose; w h

stem lightly dragged on the gland follower; t valve stroked smoothly; E

1-MS-PV-3015 the positioner link:ge was found to be loose; the valve *-- -

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1-MS-PV-3016 the stem was lightly scored; the valve strokes smoothly e=-

j and the linkage is tight; l

1-MS-PV-3017 no problems found; l

1-MS-PV-3018 no problems found; g

the positioner linkage was found to be loose; the stem <

1-MS-PV-3019 was found to be slightly scored; the valve stroked, but l

a slight in cation of binding was noted; L

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1 1-MS-PV-3020 the valve linkage was found_ to be_tigh1 but the valve,_--

g was hunting at 3 psig and would not close until the signal was <2 psig.

All valves were checked with a straight edge for stem run out and no g

visable run out was seen.

This initial examination will be followed by a more detailed follow-up exa-mination conducted by the system engineer and a representative of Copes l

Vulcan, the valve manufacturer.

g In an effort to establish the operating history of the Copes Vulcan, Model 0-100-160, valves, a search has been made of the Nuclear Operations and l

Maintenance Information Service (NOMIS). The data base indicates several plants have had both good and poor results, and that several plants have I

made modifications to ensure proper valve response. A new query has been g

made of NOMIS, and the plants that respond with positive feeaback will be contacted. This experience will be factored into our evaluation. The l

expected completion date is 07/21/89.

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'A' TRAIN. 'B' TRAIN AND DUAL TRAIN LOGIC CHECKS Steam Dump Valves 1-MS-PV-3009 through 1-MS-PV-3020 Control Logic Verification Review A review of the main steam dump control logic verification testing was per-formed. Two procedures, 1-PT(I)-40.7, Condenser Steam Dump System Preopera-tional Test Procedure, and 1-ST-55. Steam Dump System Test, were reviewed.

1-PT(!)-40.7 was started on 11/19/85 and completred on 11/20/85. This test procedure thoroughly tested and verified, at normal operating pressure and temperature, the steam dump control logic including all steam dump valves modulation and bank sequencing in response to 0-100% steam dump demand in load rejection control and plant trip control, as well as steam pressure in manual and auto control. This procedure also verified the steam dump blocking and inter Mck functions involving Train A and Train B input

'ps signals.

Finally, the procedure stroked each valve individually; measuring the modulating open and close times, as well as the trip open and close times. A breakdown of the procedure sections is as follows.

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i, Section 6.1 This section verified all the steam dump valve's modulation from ful n

to full closed, and back to full open, with the mode selector switch, M]

CS-3056, in the ' STEAM PRESSURE' position and the M/A controller, PK-507, in ' AUTO', while varying the steam pressure (PT0507) test signal. This also verified that each bank of three valves modulated open and closed in the proper sequence.

6.1 15

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Next, a Train ' A' Lo-Lo Tavg signal was simulated by jumpering $5PS Slave

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Relay K638A normally open Contacts 1 and 2, and verified that all steam dump valves were blocked. The interlock selector switch, CS-3057A, was then placed in the ' BYPASS INTERLOCK' position, and it was verified that the Bank 1 cool down valves (PV-3011 PV-3015 and PV-3019) only, could be modulated.

Next, a Train 'B' Lo-Lo Tavg signal was simulated by jumpering SSPS Slave Relay K6388 normally open Contacts 1 and 2, and the same sequence as above was verified, using CS-30578.

Section 6.2 This section verified load rejection control _ Tavg and Tret signals were l g simulated, and with the mode selector switch in the 'Tavg' position, each signal was varied to simulate a 50% load reduction.

It was verified that-all steam dump valves modulated from full closed to full open, and back to l'

full closed, in the proper bank sequence. The Tref signal was then varied kg to actuate Hil Tavg - Tref AT bistablo TB-5008, and it was verified that the first half of the steam dump valves tripped open (PV-3010, PV-3011, PV-3014. PV-3015, PV-3018 and PV-3019). The Tref signal was then varied to actuate H12 Tavg - Tref AT bistable TB-500C, and it was verified that the second half of the steam dump valves tripped open (PV-3009 PV-3012, PV-3013, PV-3016, PV-3017 and PV-3020). The mode selector switch, CS-3056, was then placed to the ' RESET' position, which blocks all steam dumps to the condensers, and it was verified that all steam dump valves closed.

Es Section 6.3 This section verified plant trip control. Trains' 'A' and 'B' reactor trip 6.2 ts

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ATTACl94ENT A

!g CHRONOLOGICAL SEQUENCE OF EVENTS RELATED TO FAILURE OF MS-PV-3011 TIME:

1236 DATE: 06/22/89 g

06/22/89

> - l APPROX-TIME EVENT CONTACT

n

~I 1313 WR89 WOO 3110 - investigate why MS-PV-3011 failed to Operations operate.

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1345 The system engineer in the field was to visually check R. Bibber

'the valve; felt solenoids for temperature. Performed visual inspection for obvious discrepancies.

g 1515 McCafferty and Guthrie, with I&C. went to the control R. Guthrie room to check sequence of events with the Operations Department prior to working.

-g 1530 -

WR in the field with I&C - valve stroked - technician N. McCafferty r

2000 noted no change in valve position - noted booster relay l~'t bleeding air - booster relay replaced. Further strokes done locally with !&C technician - (MS-PV-3015 and MS-PV-3019 appeared to stroke properly)s(by ligh P '--

.l dndiutii'nTThis did not correct the problem.

The positioner was then checked for proper calibration l'

and valve operation. F.Qund feedback linkage was dis I

connected from the posit.ioner. ~

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l The valve was restroked; however, the valve would not A.. Smith /

i stroke more than approximately 50% open. When the air J. Ardus I

was removed, the valve stuck open approximately 20%.

l When the air was fully bled off, the valve stamed shut -

l breaking the hand wheel.

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l 2000 Shift engineers stroked the valve locally, loosened the i

2200 packing - the valve never stroked satisfactorily. However, it was noted that when the valve was stroked, an alignment

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problem appeared between the valve and.the operator, causing !j binding.

2200 Tagging order placed.

Mechanical 2300 Tagging order expanded.

Operations 5

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e Page 2 of 8 06/23/89 APPROX TIME EVENT CONTACT g

i 0700 Tagging order hung - Maintenance to verify.

Maintenance 0800 Priority turned around to make MSIV operational -

M. Kenney

-l-isolate MS-PV-3011; clear tags so MSIV could be strokeT WrTr5'ubitshooting, and we would continue the test without MS-PV-3011.

1200 System engineer initiated RTS on MS-PV-3015 and N. McCafferty MS-PV-3019 (to check calibration of the positioner re 15 and the position of the valve).

l 1600 Updated event evaluation team.

M. Kenney

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'1630-

!&C performed RTS - found loose feedback linkage I,f N. McCafferty lubed linkage and performed check -

.on.MS-PV-3019; Eed smoothly; MS-PV-3015 failed RTS.

2200 MS-PV-30197tr6 The valve would not stroke properly - hunted and II would not modulate. WR written (WR89 WOO 3159).

WR later voided and replaced by 89 WOO 3211, initiated on 06/27/89 at 1830).

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Page 3 of 8 i

06/24/89 g

APPR0X-g TIME-EVENT CONTACT t

0700 Group pursued tortionai test - no steam dump. work.'

N. Kenney.

I t-1000 Briefed R. Cliche, Engineering R. Guthrie l

g,rgg,terminete untii soeee, due to mene,eme,t 9

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Page 4 of 06/25/89 APPROX'

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EVENT CONTACT I

NO STEAM DUMP WORK i

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APPROX.

' f7 TIME EVENT CONTACT i.J 0600 WR89 WOO 3173 written to stroke all steam dumps R. Bibber E

except MS-PV-3011; checking for:

1.

valve / operator run out; 2.

all linkage;

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smoothness of operation; 4.

himejoints.

0745 Meeting with M. Kenney to go over game plan; verified M. Kenney scope of work.

1130

= Briefed: Engineering - J. DeLoach, R. White M. Kenney 1300-I&C performed WR89 WOO 3173; verified additional dis-

!&C 1615 crepancies.

(See WR.)

1400 Called Robert K. Griffith and Associates; was told J. Cade Mr. Griffith was on the road, but Lou Griffith would contact J. Cade.

1500 Received call from Lou Griffith; gave him data, serial J. Cade numbars, etc.

1530 Received call from Lou Griffith; Copes needed PO to J. Cade get tervice representative.

1600 Talked to L. Blanchard, R. Romer for P0; tried to con-J. Cade tact R. Streeter.

1605 Talked to Lou Griffith; gave him MPR #320907; to'J R. Bibber him PO to follow.

1635 Received call from Tom Garmon, Copes-Vulcan Inc.

R. Bibber manager of valve service. He went through valve symptoms; he would get back.

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Pass 6 of 8 06/26/89 continued APPROX CONTACT _

TIME EVENT 1650 Received call from Tom Garmon and Tim Kunkle, design R. Bibber engineer; went through symptoms again; made arrange-ments for vendor to have service rep on site.

1730 Received call from Tom Garmon; 1.eonard Vaz, service R. Bibber engineer would arrive in Boston On 06/27/89, approxi-mately 1200; would come directly to Seabrook Station.

c N

K N

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n 10 10 n.

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Page 7 of 8 06/27/89 APPROX TIME EVENT CONTACT 1515 Leonard Yaz ar ad on site.

R. Bibber 1550-In the field with L. Yaz stroking valve and making R. Bibber i

1730 observations. MS-PV-3011 failed to stroke; MS-PV-3019 stroked; MS-PV-3015 failed to stroke.

Vendor visually checked all steam dumps; wants to see all stroked after we fix 3011, 3015 and 3019.

1830 WR89WO93211 written to support additional trouble-R. Bibber shooting; disassembly of Valves MS-PV-3011, MS-PV-3015 and MS-PV-3019.

RES submitted to Engineering to evaluate locking N. McCafferty device.

RES #89-387 - Priority 2.

I 1, sued e0 from MPR,320907 to cover service ren.

R. Bibber BE pu gs BE 58 38 Bu 9

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Page 8 of 8 i

06/28/89

.i APPROX TIME EVENT CONTACT 0600

!&C to disassemble MS-PV-3011 under vendor rep's R. Bibber direction.

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AnACMENT C W **VM D!SD05.99.99 Now Hampshiro ras' i ' 2 N

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Subiw Secondary Plant Yalves with A and B Train Logic From M. E. Kenney Dok June 27, 1989 7.

D. E. Moody Reference p.s L-J l

Attachment A lists the valves and dampers that have 'A' train

'B' N

train and dual train logic. At a meeting today, it was agreed between LJ Engineering and Tech Support that a review of these components is required. This review will consist of the following.

g L,)

1.

Engineering will perform a design review of component logic.

v 2.

Tech Support will arrange for field verification that field con-l ditions meet current design.

3.

Each component will be checked for 'A' train, 'B' train and dual

[

train logic.

W 4.

All valve positions will be checked for alignment, j

5

,, )

5.

Bench tests will be set up of various solenoid configurations.

6.

QA will be asked to review the Phase I and Phase 2 test data to i

M verify the test program covered 'A' train. 'B' train and dual train actuations.

It is hoped that this work will be complete by July 8, 1989.

f M. E. Kenney System Support Manager HEK:dje cc:

G. S. Thomas 01-40 W. J. Temple 49-CE J. M. Grillo 49-0P R. J. Sherwin 02-29 G. J. Kline 02-08 G.

Tsouderos YAEC Bolton R. E. Cyr 49-55 S. P. Buchwald 02-25 R. M. Cooney 49-S5 J. E. Cade 02-08 J. J. Warnock 02-07 P. E. Falman 02-08 J. M. Yargas 01-62 R. E. Guthrie 02-08 R. E. White 01 62 R. H. Lieder 02'08 J. L. Peterson 49-0P J. O. Ross 08 1

New Hompshire Yonkee Division of Public Service Company of New Hompshire P.O. Box 300

• Seobook, NH 03874

• Telephone (603) 474 9521 I

I(

~

p ATTACHNENT A j

ge 2 M 2 VALVES AND DAMPER $ WITH A AND 8 TRAIN SOLEN 0ID VALVES I

m c

l""[

VALVE / DAMPER [ SERV!CE) 50LEN010 DESIGN BASES j

'f FAH-DP-14 [ Fuel storage building Veret air from the actuator'to keep the exhaustfan(FAH-FN-122) discharge damper closed when in the fuel handling

,j

~

isolation) mode.

l

[~_<

FW-FCV-510, 520, 530 and 540 Vent air from actuator to close valve.

FW-LY-4210, 4220, 4230 and 4240 t

r1

[Feedwatercontrolandbypassvalves) i LJ l

FW-V30, 39, 48 and 57 Pressurization: Connect the pneumatic

[Feedwaterisolationvalves) tank to the actuator to pressurize the actuator.

Hydraulic Oump: Dump hydraulic fluid from the actuator to close the valve.

2 MS Y395 Vent air from actuator to open valve to l

[SteaminlettoturbinedrivenEFW run pump. Opening is delayed af ter the pump (FW-P 37A))

opening of a steam supply valve (MS-V393 or 3g4) for proper starting sequence of the pump. FW-P-378 is redundant.

MS-PV-3009 through 3020 Vent air from actuator to close valve.

[Condensersteamdumpvalves)

MS-Y86, 88, 90 and 92 Hydraulic Dump: Dtanp hydraulic fluid l

[ Main steam isolation MS!Ys) from the actuator to close the valve.

Air Sueoly: Shut off the two air supplies to the hydraulic pump, t

MS-PV-3001, 3002, 3003 and 3004 Nitrogen Supply: Open to pressurize the f

[ Atmospheric steam dump valves actuator from the back-up nitrogen su,91y ASDVs]-

to open the valve.

Vent Isolation: Close off the vent line g

to allow actuator pressurization for t

as opening the valve.

l-Redundant solenoids are provided for l

each ASDV to ensure that ASDVs on two intact SGs are available after a steam generator tube rupture. Closing the g-valve from the control room is not a design basis.

l SB-V9, 10, 11 and 12 Vent air from the actuator to close the

[Steamgeneratorblowdownisolation valve. The solenoids provide redundant valves (outside containment))

signals for closing the valves on a 'T' 3

signal or when FW-P-37A is operating.

l T The 'B' train solenoid also receives signalsforhighenergylinebreak(HELB)

E and FW-P-378 operating.

.T l

l

1 i

1-ST-22 Reva 2 r*

Page 2 of 12

(

)

1.0 OBJECTIVE This test will determine several natural circulation characteristics and 1

will demonstrate the ability to remove heat from the reactor coolant j

system using natural circulation. The characteristics to be determined i

include time necessary to stabilize natural circulations reactor coolant flew distributions depressurization rate following loss of pressurizer heaters: depressurization rate using auxiliary spray; effect of charging 1

flow and steam flow on subcooling margin; subcooling monitor performance.

j

2.0 REFERENCES

CURRENT ~

N0.

TITLE REVISION REVISION j

2.1 1-ST-1. Startup Program Administration 2

oR

-/s#

1 gg/fe?

44e 2.2 Seabrook Station Technical Specifications Amend 1 1

Precautions, Limitations and 5etpoints for 2.3 the Westinghouse NSSS 2

/

5eabrook Station F5AR, RAI Response 2.4 640.51-4t 56 64 2.5 ES-0.2. Natural Circulation Cooldown 6

4 2.8 ASME Steam Tablet 5th Ed.

Sk2 Seabrook Station FSAR, Table 14.2-5, 2.7 Item 22 Amend 61 Amed dl 2.8 Startup Test Program Description 2

of

• • M"4 A IFce INITIALS /DATE

&c 4MaJiq My /k sv Pw mu,y,.,

44/

red @

M 3.0 PREREQUISITES AM f.g,py JW-I4 i

8 88 //-18-87~ 3.1 The test director has reviewed the latest revtsions 'of the i

applicable references to detennine if any system changes that have been made will affect the test performance.

//-/ M f 3.2 Personnst involved with the performance of this procedure 6

have been briefed on the procedure content and informed of Dp#

their respective duties.

,,..j t

I

[ 6-88-@ 3.3 The Temporary Hodifications Log and Danger Tag Log have 7

been reviewed to identify and correct any items which may restrict the performance of the test.

C'

/"22 @ 3.4 Instrument inputs to GETARS is arranged to include those i[, ;

identified by Attachment 9.4, as a minimum, and at a scan

,_ ~

rate of less than or equal to 250 millisecond interval.

)

8 M /4 12 8 7 3.5 The reactor coolant system flow measurement test, 1-ST-11.

has been completed and the RCS flow instrumentation has been adjusted as required.

4 P U"t n e.N u~@

M. op+.%4 d pbvg 50 3 W,

• '~ar.oy%,Tb atw.(M 4wuq Qw tt Pf % a, y l..,

nelb Cs 94,m W,4,

/

b b W.%# -N s

l

i 1-$T-22 Rev. 2 Page 3 of 12

[

(

IN!f!ALS/DATE l

3.6 The following systems are available for use f

M //-/E-#

3.6.1 Station Computer.

l M /4-22-87 3.6.2 Service Air.

N//-22ff 3.6.3 Instrument Air.

N //-lJ-f7 3.6.4 Circulating Water System.

N /4-lJ M 3.6.5 Main Condenser.

M /4-12 0 3.6.6 Chemical and Volume Control System (including auxiliary spray).

_M/4-82-87 3.6.7 Steam Dump (including atmospheric relief valves).

M //-2EW 3,7 The station Operations Manager and Training Center Manager i

have been notified of the estimated start of the test, so' i

that as many(Operations personnel as possible may witness the test.

See Reference 2.4.)

[

/4-f8 N 3.8 The Unit Shift Supervisor has been notified that the test l

is about to comence.

4.0 SPECIAL PRECAUTIONS M/4-Jt-P/ 4.1 The requirements of Technical Specifications 3.4.1.1 or 3.10.4 and the associated surveillance requirements must be adhered to throughout the perfonnance of this test.

N //*f24 4.2 Do not exceed 5% thennal power at any time during this test.

I M /4-#M 7' 4.3 ThenormalATandTaNtionconditions.

The wide range hot i

indications will be unreliable during natural circu and cold leg indications should be used to calculate these values.

/N /4-72@ 4.4 Cold leg temperature should be maintained at approximately the initial (pre-RCP trip) temperature.or greater than 550*F unless otherwise directed.

//-EE-f#/ 4.5 All personnel participating in the test should be aware that the moderator temperature coefficient is near zero and may change sign during the test.

This is to reduce reactivity feedback effects related to the moderator tem-perature coefficient.

M ///-El-P7 4.6 Maintain steam generator and feedwater conditions as stable as possible as natural circulation develops.

4

.n--

I 1-5T-22 Rev. 2 Page 4 of 12 l

o i

INITIALS /DATE M/4-Edf7 4.7 Minimize thermal shock on the pressurizer spray nozzle by initiating spray slowly and maintaining a minimum con-tinuous flow once spray is actuated.

M /4-X47 4.8 Do not use auxiliary spray if letdown is isolated.

M /4-//-f7 4.9 If a reactor trip occurs during natural circulation, close the spray valves (RC-PCV-455A and B) and restart Reactor i

Coolant Pump RC-P-1C prior to closing the reactor trip breakers.

M f M f 7 4.10 Refer to the manual trip criteria listed in Attachment 9.3.

Insure that these criteria are available in the s

control room for operator reference.

M[//~22874.11 Maintain C5-Y177 (Loop t, alternate charging path) in the f

' CLOSED' position throughout the test.

N //-7 8 7 4.12 Charging flow should be constant and at as low a flow rate as possible during this test.

i 5.0 INITIAL CON 0!T10N5

~~

/4-2 8 2 5.1 Reactor power is approximately 3% with rod control in

[

' MANUAL".

M /4-//87 5.2 All reactor coolant pumps are operating._

M //-2-ff eam dump is operating in the pressure control mode and maintaining cold leg temperature at approximate 1y 557'F in manual controi. /y/tes/4 &as cfsMy d%y de 4 I

&he 6*ws.4 p tw,eJ/ cz m(ng.p%)*

k 8 //-2247 5.4 fee Stetton compliter 1Hpera.t s

M //-f/47 5.5 Pressurizer pressure control and level control are in e

manual and maintaining pressurizer pressure at approxima-tely 2235 psig and level at 25% (range 25 to 30).

M /4-//-67 5.6 The startup feedwater pump is maintaining steam generator levels at approximately 50% (40-60%) narrow range, through the bypass valves.

M //-EJ 4 7 5.7 RCS boron concentration and control bank rod positions are

'~

configured to establish an approximate 1/ zero moderator temperature coefficient. Control Banks should be arranged so that there is at least 150 pcm of inserted rod worth.

M//-lEff 5.8 The steam generator atmospheric relief valves are avail-

\\

)

able for use as necessary.

8 M /4-2E N 5.9 Secure steam generator blowdown during primary calori-metric test activities.

c.,-

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