ML20155K139

Final Rept MSIV 3-Way Dual Solenoid Valve Failures

ML20155K139
Person / Time
Site:	Perry, 05000000
Issue date:	12/30/1987
From:	CLEVELAND ELECTRIC ILLUMINATING CO.
To:
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ML20155K026	List: IA-88-165, Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl ML20155K021 ML20155K074 ML20155K102 ML20155K120 ML20155K139 ML20155K174 ML20155K200
References
FOIA-88-165 NUDOCS 8806210121
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Text

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I FINAL REPORT  :

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3-VAY DUAL SOLENOID VALVE FAILIRES i,

4 December 30, 1987 1 .

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TABLE OF CONTENTS

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Section P_a age

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1. Executive Summary 2 Introduction

2. 5 A. Brief Description of Applicable Systems 5 B. Purpose and Scope of the Recovery Effort 7 C. Brief Description of Report Contents 7

3. October 29 and November 3 Event Description 8  ;

A. Chronology of Events 8 B. Troubleshooting Activities 9 C. Data Analysis and Root Cause Determination 11 D. Corrective Actions 12 E. Safety Evaluation / Significance 20 F. Conclusion 24

4. November 29 Event Description 26 A. Chronology of Events 26 B. Troubleshooting Activities 27 C. Data Analysis and Root Cause Determination 31 D. Corrective Actions 34 E. Safety Evaluation / Significance 35 F. Conclusion 36

5. Overall Conclusion 37

6. Diagram 1 3-Vay Dual Solenoid Diagram 2 Energized & Deenergized Solenoid Valve Diagram 3 Physical Arrangement of MSIV Lines Appendix At Photos of Affected Solenoid Components Appendix B: Analysis Plan for EPDM Solenoid Components Appendix C: Foreign Material From Solenoid Plunger Area Microscopic Evaluations: Ricera, Inc.

Appendix D Summary of Instrument Air Testing Appendix E: Baseline Temperatures l l

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Enclosure  !

PY-CEI/0IE-0297 L j 1

Executive Summary 1

l This report summarizes the findings and conclusions.resulting from investigations following Main Steam Isolation Valve (HSIV) failures on i October 29, November 3 and November 29, 1987.

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Initial Event '

l On October 29, 1987 the Perry Nuclear Power Plant was completing the final stages of the Startup Test Program. One of these tests involved fast closing a Hain Steam Isolation Valve (MSIV). Durir.g this test, the valve (lB21-F022D) failed to stroke closed within the required time. All other MSIVs (7) were cycled in order to verify adequate stroke times.

Two of the other HSIVs failed to satisfy the required stroke time  ;

(IB21-F028D, 1B21-F0288).

The three valves that initially failed vere stroked satisfactorily upon subsequent demand. The problem was attributed to a one time deposit of debris in the respective solenoids which was exhausted as shown by the subsequent successful strokes. The debris was believed to have caused a delay in the solenoid responses. Based upon a satisfactory stroke, the valves vere considered Operable and startup testing resumed. Plant management decided to perform the HSIV stroke tests again prior to the last startup test, the full MSIV isolation scram. This approach was discussed with NRC Region III.

On November 3, in preparation for the final startup test, additional stroke timing tests of HSIVs were performed. During the first stroke attempt, two of the same HSIVs (IB21-F022D, 1B21-F028D) that previously stroked slowly, again failed to close within the required time. The valves vere subst.quently recycled satisfactorily within minutes of their tirst tests. However, because the valves again failed to meet the required closure time on the first att empt, the basis for an isolated failure was no longer considered valid. NRC Region III was informed of the problem. The decision was made to shutdo.m the plant and troubleshoot the problem. l 2

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s Enclosure PY-CEI/0IE-0297 L On November 4, an NRC Augmented Inspection Team (AIT) arrived on site. A.

7 troubleshooting plan was established and implemented. The air actuators of the three valves which had exhibited slow closing times vere disassembled and the inspection results documented. The conclusion drawn is that the dual solenoids exhibited sluggish action after operating in localized high temperature conditions. It is believed that steam leaks caused an elevated temperature environment in the vicinity of the solenoids. The elevated temperatures degraded the Ethylene Propylene Diene Monomer (EPDM) material causing the solenoid to stick or to be sluggish. Corrective actions included replacing or rebuilding all 8 MSIV dual solenoids and implementing additional testing. Repair work and necessary retests were completed satisfactorily and plant startup.

conducted on November 13.-

Second Event On November 29, the plant was conducting periodic stroke tests of the MSIV in accordance with commitments originating from the previous event.

The tests were performed by fully closing each MSIV individually utilizing the test solenoid, followed by placing the control svitch'to the "close" position. Performance of this test verifies proper operation of the MSIV dual solenoid, since the MSIV vill only remain closed if the dual solenoid de-energizes and properly repositions.

During this test, the 1B21-F022B valve failed to remain closed af ter two separate attempts using the sequence described above. In accordance with commitments documented in our letter, PY-CEI/0IE-0289 L dated November 13, 1987, the plant was shutdovn and notifications made.to the NRC Operations Center and Senior Resident Inspector. The remaining seven MSIVs satisfactorily passed the test requirements. -

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Enclosure PY-CEI/01E-0297 L

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On November 29 and 30, an NRC Augmented I,nspection T,e_am (AIT) arrived onsite. A troubleshooting plan was established and implemented. The plan included various MSIV solenoid valve disassemblies, visual inspection of valve parts, chemical analysis of as found materials, Instrument Air System analysis and microscopic examinations. The root cause analysis conclusion is that a sliver of foreign material, discovered in the IB21-F0228 solenoid valve body, caused mechanical binding of the valve.

This binding caused the solenoid to remain in the normally energized position, after it was verified that the solenoid was deenergized, which then prevented air bleed off from the MSIV actuator and valve (MSIV) closure. The foreign material was Ethylene Propylene Diene Monomer (EPDM) which was demonstrated to have come loose during previous valve rebuild activity. Corrective actions included complete replacement of all MSIV solenoid valves with new valves. Replacement work and necessary retests vare completed satisfactorily and plant startup performed on December 9.

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'PY-CEI/0IE-0297 L Introduction

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A. Brief Description of Applicable Systems Perry Nuclear Power Plant is a boiling water reactor supplied by the General Electric Company and designated BVR/6 with a Mark III

. containment. The main steam system consists of four main steam lines (A, B, C, and D) each consisting of a flow restrictor and two ,

redundant Main Steam Isolation Valves (MSIVs) (see Diagram 3). The combination of two MSIVs in each steam line provides a highly reliable means of isolating the reactor vessel to-minimize the loss of reactor coolant inventory and to limit the release of radioactive materials. The inboard valves are labeled IB21-F022A-D and the outboard valves IB21-F028A-D. The upper end of each valve's stem is attached to an actuator with a combination air cylinder / dashpot.

The cylinder provides the motive force to open and close the valve, while the dashpot controls the speed of valve operation. The hydraulic dashpot consists of an oil filled cylinder, hydraulic piston, two external speed control valves ard piping. The valve actuator also contains helical springs vnich provide valve closing force.

The MSIVs are opened by air pressure supplied by the Instrutent Air System. Air pressure is directed to the bottom of the air cylinder in the opening operation by the positioning of various control valves. To close an MSIV, air pressure is applied to the top of the air cylinder piston while air is bled off the bottom of the piston.

The solenoid valve which directs air pressure to and from the HSIV actuator during fast closure is an ASCO 3-vay dual solenoid (Model NP8323A20E; see Diagrams 1 and 2). Vhen deenergized, the core assembly and seat of solenoid A are held against the inlet port orifice by the core spring. The core asserily also forces the dise holder subassembly dovr, compressing the disc holder spring of solenoid B and unseating the disc from the exhaust port orifice.

This allows air to pass from the cylinder through the exhaust port orifice to the atmosphere. Vhen energized, the solenoid A core assembly is lifted from its seat on the inlet port orifice.

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I Enclosure l PY-CEI/01E-0297 L I

This allows the solenoid "B" disc spring to lift the disc-holder l

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subassembly and seat against the exhaust port orifice. Air then passes through the inlet port orifige and pressurizes the process cylinder. When solenoid B is energized, the core is forced upwards, pushing the stem against the bottom of the disc-holder subassembly.

I The disc-holder subassembly forces the solenoid A core assembly to its energized position, unseating the core assembly from the process pilot orifice and seating the disc-holder subassembly against the exhaust pilot orifice.

In the event of a failure of the air supply, the helical closing springs along with an air accumulator provide sufficient forces to close the valve. In addition, steam flov through the valve assists in valve closure. The closing speed can be adjusted over a required range of 3 to 5 seconds which is fast enough to provide sufficient protection in the event of a main steam line rupture, but slov enough to prevent imposing an excessive pressure transient on the reactor vessel.

f The Instrument Air System provides clean, dry, oil free air for '

control purposes throughout the plant. The system meets the guidelines of ANSI Standard MC-ll-1 (ISA-S7.3) with the exception (as documented in FSAR Section 9.3.1.2) that the maximum allovoble particle size for air to safety related equipment is 40 microns.

The normal supply of air pressure to the instrument air system is from one of four air compressors (2 service and 2 instrument air i compressors). The instrument air (from any of the sources) passes through an after cooler, a receiver tank, a pre-filter, an air  ;

dryer, an after-filter and a piping network prior to distribution to various plant components. The instrument air system has no safety-related function. Depressurization of this system vill not compromise any safety-related systems or component and vill not  !

prevent safe reactor shutdown.

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1 Enclosure PY-CEI/0IE-0297 L B. Purpose and Scope of the Recovery Effort i

The purpose of the follovup effort was to (1) conduct a timely, thorough and systematic investigation of the events surrounding the MSIV failures; (2) collect, analyze and document the factual information and evidence sufficient to determine the probable root and contributing causes to the failures: and (3) review the actions taken at the time of the events and assess their compliance with applicable requirements.

The scope of this effort included conditions preceding the events (e.g. maintenance histories, past surveillance tests), event chronology, system, response, human factors considerations, equipment performance, possible precursors to the events, previous industry experiences, the shifts response to the events, the safety significance (including radiological considerations), and whether proper regulatory guidelines and/or requirements were followed.

C. Brief Description of Report's Contents A summary is provided for each of the two events, October 29-November 3 and November 29, documenting the significant evidence, analyses and conclusions identified from the initial MSIV failures through the final determination and restart action items. Briefly, the following is included:

o A chronology of events o An assessment of the actions taken o Equipment performances / failures o Relationship to previou; similar events o An assessment of the safety significance o Corrective actions o Plans for restart 7

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October 29 and November 3 Event Description

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p Erclosure P)-CEI/0IE-0297 L October 29 and November 3 Event Description t.

A. Chronology of Events On October 29, at 1837 Startup Test Instruction (STI)-B21-025A, "MSIV Functional Test" was being performed on 1821-F022D, inboard MSIV. Ti.e D Main Steam Lire (MSL) inboard MSIV closed in 22.14 seconds, in excess of the required closure time of Technical Specifications 3.4.7 and 3.6.4.. At 2103 and 2106 the D inboard MSIV was satisfactorily cycled twice with closure times of 3.24 and ^

l 2.94 seconds. All other MSIVs were then cycled to verify closure time. The B and D outboard MSIVs closed in 11.9 and 77 seconds respectively, and each was recycled with satisfactory results. The cause of the slow closures was thought to be a one time deposit of debris in the respective solenoid valves causing a delay in their response. Once the valves were cycled and the stroke times passed, the debris was assumed to be exhausted. Since initial conditions causing MSIV slow closure could not be repeated, all MSIVs were

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declared Operable and plant startup testing continued.

On November 3 at 1150, MSIV stroke timing commenced in preparation for performing a full MSIV closure scram as part of the startup test program. At 1157 the D inboard MSIV closed in 18 seconds but recycled satisfactorily at 1159. At 1208 the D outboard MSIV failed to close. A second attempt was satisfactory at 1213 vith a closure time of 3.4 seconds. Based on repeat failures a plant shutdown was commenced at 1330. The Reactor Recirculation (RRC) Pumps vere shifted to slov speed at if30, resulting in a reactor pover decrease from 32 percent to 23 percent of rated. Vith reactor power below the Lov Power Set Point (LPSP)(26 percent), the Rod Pattern Controller (RPC) generated control rod insett and withdraval blocks.

Preparations were made and the reactor was manually scrammed by placing the Mode Svitch in "Shutdown" at 1819.

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Enclosure PY-CEI/01E-0297 L 4

On November 4, the Nuclear Regulatory Commission (NRC) issued a k '

Confirmatory Action Letter (CAL) det, ailing various actions to take in preparation for an NRC Augmented Inspection Team (AIT). The team arrived onsite November 4. i B. Troubleshooting Activities Prior to performing any work in the field, a troubleshooting plan was writtcn. Based on the symptoms shown on October 29 and November 3, it was felt that the component with the highest probability of causing the slow closures was the ASCO model number NP-8323A20E dual solenoid found on each MSIV air actuator. The troubleshooting plan was set up to determine what the root cause was and whether any secondary problems had an impact.

On November 5 "As Found" conditions vere documented wherein a more j detalJed troubleshooting plan was developed to establish the root cause of the MSIV failures and corrective actions necessary to

• • restore the valves to operable condition. The revised plan was agreed to by the NRC AIT. On November 5 through November 8 various troubleshooting activities were carried out. t o

(1) Tests conducted on the IB21-F022D, F028D and F028B solenoids '

included the following: '

a. Solenoid voltages and solenoid air exhaust port samples vere taken as the valves vere cycled and all results vere sa t is f ac tory. Next, the field viring and air lines were disconnected from the air actuator or air pack. All connect'ons and pipe openings were inspected. The air '

pack vas then removed from the valve actuator and taken to the'I&C hotshop for disassembly. The IB21-F022D single (slow close) solenoid was inspected and no problems were found. Any discrepancy no matter hov small was documented for further evaluation. Whenever possible, pictures were taken of what was found. I l

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l Enclosure PT-CEI/0IE-0297 L Results:

a. All dual solenoids disassembled had impact marks on the

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star shaped disk subassemb'ly and a deep depression (dimple) on the disc holder seal (EPDM), with the solenoids of the B21-F028D valve indicating the most degradation (see Appendix A).

b. Many of the EPDM Body Assembly 0-Rings were hard, flattened, and adhering to metal valve body surfaces.

c. In the 1B21-F028D valve rust was found inside the solenoid

, housing cover and the B solenoid coil was badly corroded.

(This was incorrectly identified as IB21-F022D in our letter PY-CEI/0IE-0288 L dated November 13, 1987).

1 (2) In addition to the component disassembly, other analyses vere performed to determine what contribution, if any, instrument

, air quality may have had in the failure of the MSIV valves.

Instrument air dev point temperature was measured in the supply to both the inboard and outboard MSIV's. Air supply particle size distribution was measured. Various unknown substances observed in or collected from internal component surfaces vere analyzed using infrared spectroscopy to determine the origin of the material. Crab samples of the air supply were analyzed by gas chromatography for hydrocarbon content, and quantification of organic contaminants, if present in significant quantities.

Results:

The measured dev point temperatures were vell below the maximum

-40*F allovable. Initially a particle countet was used to measure air particle size distribution. Due to a recent change in vendor calibration standards, the maximum range of 10 i

P Enclosure PY-CEI/01E-0297 L

( quantification was greater than 15 microns. Testing did indicate a small number of particles in..tbe greater than 15 micron range. In an effort to quantify those particles, an alternate sampling method using filter paper was attempted.

Samples were taken and particle sizes measured using a microscope. This did indicate a few particles it the greater than 40 micron range, but this sampling method is susceptible to contamination from the sampling environment which may have been the reason for the greater than 40 micron particles measured. Analyses of the substances collected during disassembly identified the presence of thread sealant ar.d silicone lubricant, both of which are normally used during assembly of solenoid valves and air lines. Air supply grab samples revealed no detectable condensable hydrocarbons greater than 0.1 PPM.

Based on the information and analysis conducted it appears that

( the EPDM material used in various parts of the solenoid vas interfering with solenoid valve movement. Thus, the decision -

vas made to remove the dual solenoids on all 8 MSIVs, and replace / refurbish as necessary.

C. Root Cause of Failures The cause of the MSIV delayed closures has been isolated to a failure of the ASCO dual solenoid valves. This failure is attributed to EPDM elastomer degradation due to elevated temperatures in the vicinity of the air packs resulting from steam 1 leaks. This condition c:.used the disc holder assembly to  ;

intermittently vedge in place and the solenoid valve to stick in the normally energized position. The observed hardened dimples on the j disc holder assembly and core assembly hardened elastomer seals is consistent with high temperature coiditions. Other evidence of l localized steam effects include degradation of the solenoid valve g

0-rings and observed rust / moisture contamination of the 1B21-F028D l solenoid. l l

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9 Enclosure PY-CEI/0IE-0297 L Localized high temperature conditions existed during the plant cycle due to steam leakage as evidenced by elevated area temperature indications. Steam leakage is known to have occurred in MSIV 1B21-F022B packing and the MSIV leakage control system isolation valves. This leakage was in the direct vicinity of those MSIV's

, which exhibited slow closure. Steam is suspected.of leaking in the direct location of the subject MSIV air packs based upon the degradation of the EPDM.

D. Corrective Actions

• As a result of the findings and conclusions identified subsequent to the October 29 and November 3 avents, the following evaluations and corrective actions have been or vill be completed:

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(1) For the dual (fast closure) solenoids, the total IB21-F0280 air pack, including a new solenoid unit, has been replaced and a new dual solenoid was installed on the 1B21-F022D valve.

Additionally, the 1B21-F022A dual solenoid valve was replaced due to a frayed vire at the termination. No other dual solenoids shoved significant degradation or required replacement. All of the remaining MSIV dual solenoids vere rebuilt.

(2) The single (slov elosure) test solenoid was replaced on the  ;

IB21-F028D valve since the whole air pack vas replaced.

Additionall,y, the 1B21-F028B singic solenoid valve was replaced due to a frayed vire at the ter=ination. Based on the inspection results above, no other replacements were necessary.

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PY-CEI/0IE-0297 L  !

I (3) An evaluation has been performed of other ASCO solenoid valves k

required for Class lE harsh environment applications in the plant, including those which miy have beeEsubject to the steam leak environment which affected the HSIV solenoids. The reviev identified two normally deenergized solenoids which vere l subject to the same conditions as the HSIV solenoids. Since the solenoids are normally deenergized no further action was considered necessary because in this state, the suspected  !

failure modes vere not expected to occur.

The two solenoids vere 1821-F0451 (solenoid for valve 1B21-F0069) and lH14-F0063A (solenoid for valve lH14-F0060A).

A vork history review of all other applications has shown no solenoid failures, indicating the ASCO solenoid degradation anpears to be limited to the HSIV solenoid valves. Further reviews are described in Item 11 below.

The 1H14-F0060A valve is a normally closed valve and has no s..

safety function to mitigate an accident. It is associated vith a dryvell purge system damper that is closed during normal operation vil,h a water seal in place for shielding purposes.

This valve was satisfactorily cycled during the recent shutdown. The 1B21-F0069 valve is a one inch "before" seat drain valve that is closed at greater than 50% main steam flov (at which time the solenoid is deenergized). The valve was i

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subsequently cycled on November 7, 1987 with no deficiencies identified. In addition, this valve was satisfactorily cycled again during the November 13 plant startup.

(4) An evaluation has been performed of other equipment in the vicinity of the 1B21-F022D, 1B21-F028D, and 1B21-F028B valycs, to assess any impact that the steam leaks may have had on these components. This evaluation revealed that there vere six valve operators in the steam tunnel and two in the dryvell that vere in close proximity to the known steam leaks. These actuators were inspected and no steam / heat degradation was observed.

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Enclosure PY-CEI/01E-0297 L Viring, terminal blocks, torque switches, limit switches, splices, gaskets, and limit svitch gear box lubricants were inspected by a team that included EQ' personnel. There vas no evidence of a thermal degradation from a steam environment that would affect valve operability. It should be noted that the Limitorque actuators do not contain EPDM material. In addition, a further review for qualified life adjustment has been completed (described in Item (11) below). There is no concern of Limitorque motor operators qualified life in the dryvell or steam tunnel areas.

(5) Following the November 13 startup, temperatures in the vicinity of the MSIVs were initially monitored using permanently installed plant instrumentation. Monitoring was later accomplished using additional temporary instrumentation. The historical readings of the existing permanent steam tunnel and dryvell temperature elements in the vicinity of the MSIVs vere reviewed, and a baseline was determined for each element.

m Until the temporary temperature monitoring baseline values vere determined, the existing permanent temperature elements vere used. It was determined that a 10% rise above these baseline values may be indicative of a localized steam leak and vould require investigation. This value was conservatively selected since it is approximately one half of the temperature rise expected for the Technical Specification trip value for leak detection. It was sufficiently conservative for the interim period until the MSIV area and surface temporary temperature element readings were fully baselined. This temperature rise vould have indicated the steam leaks which impacted the inboard MSIV (24 degrees F differential temperature). A lover threshold temperature rise could have resulted in unnecessary ac< ions or reduction in power operation due to minor temperature fluctuations.

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Enclosure PY-CEI/0IE-0297 L ,

A procedure vas established specifying necessary actions to be k taken upon exceeding the interim temperature values. The interim temperature thresholds ' vere establfshed and based on area temperature plus a 10% rise or a selected 225 degrees P for the temporary temperature elements in the area surrounding ,

the HSIVs in the steam tunnel and dryvell. The NRC Senior Resident Inspector vill be notified if any of the following corrective actions are to be taken o Reduce power, as necessary, to perform a visual inspection -

to determine the equipment affected.

o Immediately repair the leakage or shield the adjacent Class 1E components to limit the impact until a repair is possible.

o Note components being affected and assess the thermal impact (EO). Evaluate and determine the necessary time

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-- frame for taking additional action, such as increasing surveillance frequency or changing replacement interval.

o At least 1 temporary temperature element in the area of each MSIV vill be maintained in service in Operating i Conditions 1, 2 and 3. If all temporary temperature elements fail fcr a specific HSIV, the adjacent temperature elements vill be utilized in an interim period not to exceed 7 days. In the interim a correlation vill be established between the adjacent temperature elements and the specific HSIV vithout individual monitoring.

After 7 days, reactor power vill be reduced in order to repair / replace the failed element within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the plant vill be placed in Hot Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Cold Shutdovn within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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Enclosure PY-CEI/0IE-0297 L g' o If the local temperature monitoring in the area of an MSIV exceeds 284 degrees F, the affected MSIV vill be declared inoperable in accordance With Techni' cal Specification

-3.6.4.a or cycled daily consistent with the EQ test parameters. This remains in effect until the additional-environmental testing is complete'd (see Appendix B).

The temporary steam tunnel and dryvell temperature monitoring equipment was installed at preselected locations in the MSIV area. In the steam tunnel, this included pl'acement on the dual and the single solenoid bodies, and in the vicinity of the MSIVs to monitor ambient air temperatures. The dryvell temperature elements were located on the dual solenoid bodies, along with ambient air monitoring.

(6) The temporary temperature elements installed in the dryvell and steam tunnel vere monitored during full power operation until baseline temperatures were established (see Appendix E). The procedure outlined in Item (5) vas then revised to monitor the temporary temparature elements in lieu of the permanent elements. A temperature rise of 10% above the baseline was determined and included in the procedure. The actions to be t; ken upon exceeding this temperature limit vere the same as outlined in Item (5).

The temporary temperature monitoring program vill continue until the final analysis results of the environmental testing (see Appendix B) are fully evaluated. At this time, possible design improvements vill be evaluated and a determination vill be made un future actions, including replacement frequencies or correlation to permanent area temperature elements. The NRC l vill be notified prior to removal of the temporary temperature elements.

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6 Enclosure PY-CEI/0IE-0297 L (7) A test has been performed which shows that air does not flov

( between the instrument air compressor reduction gear vents and the air compressor intake. Consequently, it was determined that there was no need for any equipment modification.

(8) To further substantiate the high temperature root cause, laboratory analyses vill be performed to confirm the failure mechanism of the EPDM degradation. A review of industry experiences and discussions with various industry sources vill continue to be conducted in order to input l'nto our analysis plan. The preliminary analysis plan, which included these industry contacts, is completed, with a summary provided in Appendix B.

Ve have completed an initial evaluation of industry experience.

The initial industry review did not change our preliminary conclusion that the root cause of the problem was primarily localized elevated temperatures near the ASCO solenoid valves.

t The visual inspection of the EPDM did not exhibit the normal ,

signs of hydrocarbon degradation (stickiness, sponginess, or svelling), however, ve have not eliminated the potential of hydrocarbons having a deleterious effect. Ve plan to use data obtained from other plant experiences as described in IEN 86-57, along with our own analysis, to confirm the root cause.

Our preliminary schedule is to have initial infrared analysis for hydrocarbon degradation by the end of January 1988 with the remaining results and analyses by end of the first quarter 1988. Any further analyses required vill be determined I at that time. Ve plan to use a local research laboratory, as our primary analyses contractor. Results vill be provided to the NRC. Vith respect to environmental testing, a test plan has been provided to the NRC (CEI/0IE-0292 L dated November 23, 1987). Interim test results vill be provided to the NRC as they become available during the 92 day test duration.

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s Enclosure PY-CEI/0IE-0297 L Following completion of the analysis program, possible design improvements vill be evaluated and a determination vill be made i

on future actions, including replacement 'ffequencies.

(9) Presently, in order to minimize the vo tential for introducing hydrocarbons to the air system, a preventive maintenance requirement has been established for periodic replacement of the instrument air system prefilters. The maintenance frequency is consistent with replacement of the instrument air system after filters. Additionally, a generic precaution vill be added to all work orders requiring piping / tubing systems to be opened regarding the use of thread sealants and lubricants.

If the outcome of the chemical analyses indicates the presence of hydrocarbons, ve vill immediately implement an appropriate hydrocarbon sample and analysis program for the instrument air system. This vill include weekly sampling of the supply lines to the HSIV's at the containment penetration connection as well

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as other main J-headers throughout the air supply system. The Senior NRC Resident Inspector vill be notified upon implementation of this action.

Dev point and particulate sampling of the instrument air system vill continue in accordance with the existing plant administrative procedure. Any unacceptable results vill be evaluated and system blovdowns vill be conducted until satisfactory results are obtained.

(10) Until the first refueling outage, the fast closure dual.

solenoids vill be checked for proper operation during the monthly slow closure check. The existing monthly surveillance instructions were revised to reflect the following test procedure. The test vill be performed by fully closing each MSIV individually utilizing the test solenoid, followed by placing the control switch to the "close" position.

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Enclosure PY-CEI/0IE-0297 L Performance of this test vill verify the proper operation of the dual soleroid, since the HSIV vill remain closed only if the dual solenoid deenergizes and properly Tepositions. If any MSIV should reopen during the test, indicating failure of a dual solenoid, the associated MSIV will be declared inoperable and the plant vill be placed in Hot Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The NRC vill be notified upon discovery cf such a failure.

Also during this time frame (until the first refueling outage) the HSIVs vill be cycled individually on a quarterly basis regardless of plant operating conditions, and the fast closure time verified. If a failure is detected during this quarterly test due to a temperature related problem with a dual solenoid, or associated air pack components, the plant vill be shutdown and the NRC vill be notified as described above. The monthly slow closure test described above vill not be performed during those months when the quarterly fast closure test is performed.

(

Prior to exceeding a six month period an inspection vill be performed during an outage of opportunity, on the dual solenoid experiencing the highest temperature profile. This inspection vill visually verify no degradation of the solenoid valve internals. If acceletated heat degradation is observed, a  ;

complete investigation vill be~ initiated and the NRC notified. l (11) A review has been completed of all known steam leaks in the plant which could have affected Class 1E equipment. For all of the potentially affected equipment identified, there is no configuration where elastomer compression set or degradation could result in the equipment not being able to perform its intended function. These components vere also evaluated to determine if there has been any affect on their long term qualified life based on the environment under which they were j t subjected. The results of this evaluation are documented in l

19 I l

1 Enclosure PY-CEI/0IE-0297 L  ;

I our letter PY-CEI/0IE-0294 L dated November 30, 1987. An

(

additional reviev vill be conducted for potentially high temperature area environments for all Class 1E solenoids and related equipment with EPDM subcomponents where elastomer compression set or degradation could result in equipment not being able to perform its intended function. This reviev vill be completed by the end of the first quarter 1988.

E. Safety Evaluation / Significance The safety significance of the event has been divided into two parts; the immediate safety significance of having one or more HSIVs with isolation times outside their Technical Specification Limit, and the effect on accident analysis of having one Main Steam Line isolate at a time greater than five and one-half seconds.

(1) Immediate Safety Significance On October 29, 1987 Main Steam Isolation Valve (MSIV)

IB21-F022D exceeded it's allowable stroke time during performance of a startup test and was declared inoperable at 1900. Technical Specification 3.6.4 Action (a) then became applicable. This required the plant to make the valve operable vithin four (4) hours or isolate the penetration. At 2103 and 2106, 1B21-F022D vas cycled and stroked closed within the 5 second isolation time required by Technical Specification 3.6.4. The D Hain Steam line vas isolated at approximately 2240 as required by the Technical Specification.

Subsequent to the 1B21-F022D valve testing, all MSIVs were cycled in order to verify adequate stroke times. At 2144, the 1B21-FON8D failed it's stroke time test and was considered inoperable. At this point, Technical Specifications required the plant to be shutdovn within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. (One other HSIV, 1B21-F028B, also failed it's first stroke time test at 2216).

20 .

. _, , - .~

0 Enclosure PY-CEI/01E-0297 L By 2310, all MSIVs that failed their initial stroke times had 7

successfully completed subsequent tests and the results evaluated. The valves were considered Operable. The bases for this decision was that the cause of the slow closures was attributed to be a one time deposit of debris in the respective solenoids causing a delay in their response. Once the valves were cycled and the stroke times passed, the debris was assumed to have been exhausted. This conclusion was believed to be c:nsistent with known industry problems regarding air systems and MSIV solenoid valves. In addition, a full MSIV closure test was to be performed in less than one week. These factors were considered heavily in the final decision. No further actions per Technical Specifications were required. None of the Technical Specification Limiting Conditions for Operation (LCO) were violated.

On November 3, 1987 another series of stroke timing tests were

(,

' performed on the HSIVs. At 1157, the 1B21-F022D failed it's stroke time and was declared inoperable. At 1208 the 1821-F028D failed to close. Both valves were subsequently recycled satisfactorily within minutes of their first tests.

However, because the valves again failed to properly actuate on the first attempt, the bases for an isolated failure was no longer considered valid. The plant commenced a shutdoca at 1330 and the D and B lines were isolated by 1354. The plant was shutdown within the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> required by Technical i Specification 3.6.4 Action (a).

Since no LC0 was violated during either event, the plant remained within the constraints of the analytical bases contained in the operating license. Consequently, the incidents resulted in no immediate safety significance.

21

Enclosure PY-CEI/0IE-0297 L (2) Effects on Accident Analysis It was determined that two accident scenatibs and three transients described in the FSAR took credit for closure of the HSIVs. The events were as follows:

a. Steamline break outside containment

b. Inside containment breaks which reach RPV Level I

c. Pressure regulator failure transient

d. Loss of condenser vacuum transient

e. Loss of AC power transient If Regulatory Guide 1.3 assumptions vere used a delay or failure to isolate one steamline substantially effects the radiological evaluation of the DBA recirculation line break inside containment since it requires the assumption that 100%

of all activity in the core is released. This activity would then be available for transport outside the containment until all steamlines are isolated. However, the Perry FSAR Chapter 15 analysis concluded that for the original accident scenarios (a and b), no fuel failure vould occur. Using this premise, FSAR Table 15.6-17 values were used for isotopic content of the reactor coolant when performing the evaluations.

The bounding event of those described above was determined to be the steamline break outside co.;tainment since this event vould permit the largest amount of activity to reach the site boundary. An analysis was performed to determine what the mass flov vould be for a main steam line break outside containment given the as found conditions that existed on November 3, 1987 (i.e. three main steam lines isolate with proper times, and the remaining main steam line isolates in 18 seconds). The analysis was done using the GE's SAFE 06 Code, a NRC approved code which has been previously used by Perry in the ECCS 22

1 o . 1

,1 Enclosure PY-CEI/0IE-0297 L performance analyses (FSAR Chapter 6). The mass release

( determined by this code was much less than the mass release '

discussed in FSAR 15.6.4.4 for -the main steam line break outside containment. This was due to the conservative assumptions used in the FSAR analysis, such as assuming that i level rise time is 1.0 seconds, that mixture quality is a l constant 7.0%, and that the system pressure remains constant at  ;

1060 psig throughout MSIV closure. I l

However, it was decided that two calculations vould be done.

The first vould use the mass release given in the FSAR (FSAR page 15.6-10) for the first 5.5 seconds and then use the GE I l

supplied flov data after 5.5 seconds when only one main l steamline is open. The second calculation used the GE supplied data throughout the event. For each calculation two results were determined. First the postulated amount of radiation which would be released in the 18 seconds it took for the D

(

line to isolate on November 3, and secondly the total time it vould take with one main steam line unisolated before 10CFR Part 100 limits were exceeded. For these calculations it was conservatively assumed that there vould be no plateout or hold up time for the release.

For the calculation using the FSAR mass release the following i conclusions vere dravn:

Exclusive Boundary Area Iodine dose with 18 second single MSIV closure - 192 Ret l

Exclusive Boundary Area Iodine dose with 79 second single MSIV closure - 300 Rem 23

Enclosure PY-CEI/0IE-0297 L

(

For the calculation using the GE data the following conclusions were dravn: - -

Exclusive Boundary Area Iodine dose with 18 second single MSIV closure - 82 Rem Exclusive Boundary Area Iodine dose with 120 second single MSIV closure - 300 Rem As shovn above for either calculation the slow closure l (18 second) of the D HSIV line on November 3 vould not have resulted in a, release exceeding 10CFR100 guidelines. Also,  ;

depending on which calculation was used, it was determined that l the plant would have had between 79 and 120 seconds to isolate that line under accident conditions prior to exceeding 10CFR100 i guidelines. Therefore, the 18 second slow closure of the D main steam line penetration has been shown to be within the  !

bounds of accident guidelines. In conclusion, the Technical  !

Specifications vere followed negating any immediate safety l

significance, and analyses using appropriate assumptions shoved  !

that had an accident occurred on November 3, 1987, the plant vould have responded in a manner which would have met NRC guidelines.

I F. Conclusion i

In summary, the HSIV slow closure problem vas thoroughly evaluated I and diagnosed. The actions taken by the operations staff during the '

initiating events vere evaluated as proper and in accordance with plant procedures and regulatory requirements. The root cause was determined to be a failure of the respective MSIV 3-vay dual solenoid valves. This failure resulted from a hardening and dimpling of the EPDM rubber disc seat material and other EPDM seals, c' c the dise holder assembly to vedge in place when the solenoid

..tergized.

24

s Enclosure PY-CEI/0IE-0297 L

(

Following troubleshooting, extensive short and long term evaluations and corrective actions were initiated. These included solenoid valve replacement, work history reviews, environmental evaluations, installation of additional temperature monitoring, instrument air laboratory analysis, and a follovup laboratory analysis of the solenoid valves to confirm the failure mechanism.

An evaluation of this event vas-performed and concluded that since the plant remained within the constraints of the analytical bases contained in the operating license the incidents resulted in no immediate safety significance. In addition, the effects on the design bases accident analysis vere reviewed and also determined to not be significant. The repairs to the MSIV solenoids have been completed and the plant successfully restarted.

L 2r

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November 29 Event Description ~

w 8

1 l

Enclosure l PY-CEI/0IE-0297 L n

November 29 Event Description

~

A. Chronology of Events On November 29, 1987 u 2240, modified Surveillance Inst action, j SVI-C71-T0039 "Hain Steam Line Isolation Valve (MSIV) Closure Channel Functional" vas being performed on 1B21-F022B, Main Steam Line (MSL) B inboard MSIV. The test is performed by fully closing each MSIV individually, utilizing the test solenoid, followed by taking the control switch to close. Performance of the test in this .

manner verifies proper operation of the HSIV dual solenoid, since ,

the HSIV vill remain closed only if the dual solenoid de-energizes and properly repositions (see Diagrams 1 and 2). When the 1B21-F022B control switch was taken to the closed position (following slow closure), the valve stroked open, indicating a failure of the dual solenoid. Approximately three minutes later, the test was repeated with the same result. Two more attempts vere made utilizing only the control svitch. The valve failed to close

• during both attem,nts and was subsequently declared inoperable.

At 0410, a reactor shutdown was commenced in accordance with commitments documented in our letter PY-CEI/0IE-0289 L dated November 13, 1987. In addition, at 0509, MSL B vas isolated in accordance with Technical Specification Action requirement 3.6.4.a.

After reducing reactor power, a manual scram was initiated at 1114. l Operators commenced a plant cooldown in preparation for entering Operational Condition 4, Cold shutdown.

During the plant cooldovn, personnel entered the Dryvell to visually inspect the 1B21-F022B valve while operators again attempted to stroke the valve using the control svitch. At 1303, with assistance from dryvell personnel (providing a slight tap on the solenoid body), the valve was successfully stroked closed. The valve was then reopened and at 1306, again stroked satisfactorily from the control svitch. By 1720, the plant was in cold shutdovn.

26

Enclosure PY-CEI/01E-0297 L On November 30, the Nuclear Regulatory Commission (NRC) issued a Confirmatory Action Letter (CAL) detailing various actions to take in preparation for an NRC Augmented nspection' Team (AIT). The team arrived on site November 29 and 30.

B. Troubleshooting Activities On November 30, the 1B21-F022B dual solenoid valve (ASCO Hodel Number NP-8323A20E) was removed from the field, disassembled and visually inspected. Vhile the visual inspections were underway, a troubleshooting plan was developed. The plan's purpose was to conduct a thorough, timely and systematic investigation of the circumstances surrounding the HSIV failure. The plan was comprised of three major segments; (1) collection and documentation of pertinent information (2) analysis of that data for root cause determination and (3) implementation of corrective action necessary to prevent recurrence. The troubleshooting plan and associated work orders vere presented to and approved by the NRC AIT. The details

~-

of the plan are discussed below.

The information collection and documentation of results included visual and microscopic examinations of various valve parts and foreign materials. In addition, chemical analysis was performed on these samples which included destructive and consumptive tests.

Specifically:

(1) Tests conducted on the IB21-F0228 solenoid included the following:

a. Tne solenoid was disassembled and visual inspections performed. The visual inspections vere intended to identify surface defects, impurities or the presence of foreign material.

27

Enclosure PY-CEI/0IE-0297 L

( Results:

~

A sliver and two other small segments of foreign material vere discovered in the B solenoid valve body area (see Diagram 1 and Appendix A). The seating surface was also inspected and no evidence found of hardening of the discs or 0-rings. The discs and 0-rings remained flexible and non-rigid. There was only slight dimpling of the exhaust port disc and a minor depression on the inlet port disc.

There was no resemblance to the extruded hardened dimples observed on the seats identified during the November 3, 1987 event.

b. Chemical analysis was performed of the foreign material identified above (see Appendix C). The chemical analysis included infrared analysis to determine material composition, and microscopy, intended to enhance the ability to conduct visual inspections.

~~

Results:

(1) The infrared analysis indicated the presence of EPDH and small amounts of silicone on the sliver and on the only other particle found capable of analysis. Both materials are part of the solenoid valve assembly. This analysis also concluded that there was no evidence of oxidation. Oxidation if present, vould be indicative of the presence of hydrocarbons.

(ii) The microscopy indicated that the material vas black in color, spongy in construction and exhibited a compression set'similar to EPDM material. This supports the conclusion that the material was EPDH.

28

• l l

• 1 Fnclosure PY-CEI/0IE-0297 L (iii) Hieroscopy Dimensional Analysis of the foreign

( material and that of the pre-rebuild 0-ring from the 1B21-F022B solenoid valve were compared.

The results indicated that the foreign material was similar to a gouge identified in one of the pre-rebuild 0-rings in it's shape and overall dimension (0.8 mm X 4.2 mm X 0.3 mm). l (iv) An infrared analysis was performed on the pre-rebuild 0-ring and confirmed that the foreign material organic chemical composition matched that of the 0-ring (EPDH).

(v) Further chemical composition analysis for metallies was performed by Scanning Electron (

Hicrograph (SEM) on all particles (e.g. foreign material) and the pre-rebuild 0-ring. This l

(

analysis provided further confirmation of material source by comparing trace metal catalysts and cross linking agents present in the samples. The results of this analysis document that the microstructure of the 0-ring and sliver are the same.

(vi) Microscopy evaluation of both the pre-rebuild and existing 0-rings was performed and verified no other potential sources of the foreign material.

(2) The 1B21-F022C and F022D /.SCO solenoid valves vere disassembled and visual inspections performed. (The F022C solenoid valve 1

vas previously rebuilt while the F022D solenoid valve was l renlaced with a new valve as a result of the November 3, 1987 event).

Results:

No foreign materials vere identified. Only minor seat impressions vere visible on the disk (similar to 1B21-F022B disk).

29

Enclosure 1 PY-CEI/0IE-0297.L (3) Evaluations conducted on the pre-replacement 1B21-F022A k solenoid valve included seat leakage tests followed by disassembly and visual inspecti~on.

Results:

No seat leakage vas observed. No significant foreign materials (other than small particulate) or other discrepancies were identified.

(4) Air blows were performed on the Instrument Air System followed by dev point and particle count analysis.

Results:

a. The air blov was conducted using a pillovcase as the filter medium. Although slight discoloration was noted, no visible particulate was identified. Additional particulate count analysis demonstrated that Instrument I.

Air quality was within design requirements. The largest particle measured was in the less than 20 micron range.

b. A dev point check vas performed at the air supply line to the F022B solenoid. The results (-42 degrees F) were satisfactory,

c. Samples were collected and results concluded that no hydrocarbons were present within the Instrument Air System.

(5) A reviev vas performed on solenoid valve construction, allovable tolerances and dimensional analysis for thermal affects which may have contributed to the solenoid valve failure. The solenoid valve spring constants including any resulting heat effects on these values vere also evaluated to determine if they had contributed to the solenoid valve failure.

]

j 30

)

-o .

D Enclosure PY-CEI/0IE-0297 L Results:

\

The vendor has provided vritten certification documenting that spring characteristics and valve dimensions-are within design tolerances and are bounded by the results of the Environmental Qualification Tests. In addition, it was determined that the particles found vere of sufficient size to become lodged between sliding surfaces around the solenoid core thus inhibiting movement and causing the valve to malfunction.

(6) A review of the Air Quality Standard for the~ Instrument Air System was performed. Included in this reviev was a justification of previous data collected on Novemb9r 7, 1987 l which documents greater than 40 micron size particles.

Results:

Because of the probability of some contamination occurring due to the large amount of exposed sample handling involved with the filter paper collection method, it is not easily

(

sseertained what percentage of these results vere due to contamination. It is suspected that the majority of fibers found are dust particles from room air. As a more accurate l method, the particle counter instrument was recalibrated to detect and quantify particles in the 40-50 micron and

>50 micron range and vas used to test the validity of the filter paper collection results. The results of this analysis l concluded that Instrument Air quality was within design requirements for particulate (see Appendix D).

C. Data Analysis and Root Cause Determination (1) Summary A detailed root cause analysis was performed with a draft report provided to the NRC AIT. It concluded that the root cause of the HSIV failure was binding of the "B" solenoid (refer to Diagram 1) due to the presence of foreign material.

31

+- - ---- , , . -

b Enclosure PY-CEI/0IE-0297 L During visual examination, a sliver of foreign material (EPDH) was discovered in the IB21-F022B solenoid valve body core cavity. The material was demonstrated to have originated from rebuild activities conducted during the previous MSIV outage (early November 1987). This sliver was inadvertently dropped into the core area of the "B" scienoid and since that portion of the solenoid was not disassembled, it was not detected until the current investigation. Inspection of the "B" solenoid core area required removing the "B" coil. However, the leads for the "B" coil vould have required cutting to remove the coil. .

By the time this solenoid valve was being rebuilt, the root cause had already been determined to be heating of EPDM material. Consequently it was decided that the "B" solenoid core area vould not require inspection.

l The sliver of foreign material caused mechanical binding of the solenoid valve. This binding caused the solenoid to remain in The normally energized position which prevented the air bleed off from the HSIV actuator and thus valve (HSIV) closure.

l i

(2) Supporting Analysis Microscopic and infrared analysis performed on this foreign material and on the pre-rebuild 0-ring from the ID21-F022B valve support this root cause determination. A summary of other analysis demonstrates no other reasonable cause or contributing factor. Specifically;

a. Visual inspections of other solenoid valves and associated parts revealed no other discrepancies which could have j contributed to the valve failure. l

b. Instrument air samples and analysis identified no problems which could have contributed to the solenoid failure.

Although earlier filter collection samples identified some amount of particles in excess of the 40 micron limit, 32

Enclosure PY-CEI/0IE-0297 L subsequent samples using a particulate counter found the

(, air quality within design requirements. Consequently, particulate in the Instrument Air System are not believed to be a contributing factor to the solenoid valve failure.

. The system is designed to meet the guidelines of ANSI Standard MC-ll-1 (ISA-S7.3) with the exception that the maximum allovable particulate size for air to safety related equipment is 40 microns. Recent instrument air analysis has confirmed the dev point, hydrocarbon levels and particulate to be within required limits.

c. A variety of destructive and chemical tests were performed on many pre-rebuild and new solenoid valve parts. The results of these tests identified no discrepancies which could have contributed to the solenoid valve failure.

(3) Relationship of November 29, 1987 Event to Previous Events As discussed in Section 3 of this report, HSIV solenoid valves experienced failures to shift in the past (also refer to our letter PY-CEI/0IE-0288 L dated November 9, 1987 and 0289 L dated November 13, 1987). During the October 29 and November 3 events, the root cause was determined to be failure of the solenoid valves due to EPDM elastomer degradation of the seating surface. This degradation was caused by elevated temperatures resulting from steam leaks in the vicinity of the  !

HSIV air packs.

The root cause of these previous events is unchanged by any of the post November 29 event investigations completed to date.

This conclusion is based on the following:

33

Enclosure PY-CEI/0IE-0297 L I

a. Temporary instrumentation mounted on the ASCO valve and contact readings taken during the November 29 dryvell entry indicated temperatures below the maximum allovable values documented in the existing Environmental Qualification Report.

b. Subsequent disassembly (post November 29 event) of the 1B21-F022B ASCO solenoid valve and examination of elastomers indicted no evidence of hardening of the discs or 0-rings. The discs and 0-rings remained flexible and non-rigid. There ves only slight dimpling of the exhaust '

port disc and v. minor de;rtssion on inlet port disc.

These indication.t are ecpected due to the operational design of the so]snoid valve. In addition, 0-rings installed during the rebuild vere removed freely. -

D. Corrective Actions To prevent recurrence, all MSIV dual solenoid valves have been replaced with new valves and vere cycled 10 times as part of the retest activity prior to the December 9 reactor startup. In addition, administrative controls vill be instituted on future Class 1E ASCO solenoid valve work to require the use of new valves or complete disassembly and cleanout to ensure no particles are introduced during the rebuild process.

Previous corrective actions discussed in Section 3.D of this report and documented in our earlier letter, PY-CEI/0IE-0289 L dated November 13, 1987, vill be completed as planned with the following clarifications:

34

i Enclosure PY-CEI/0IE-0297 L

( (1) The dual solenoid valve inspection discussed in Section 3.D.

(10) and on page 5 of the enclosure to our -previous let ter vill be performed during an outage of opportunity prior to the end of October 1988. This is based on the complete replacement of all MSIV solenoid valves discussed above.

(2) The modified monthly slow closure surveillance test discussed in Section 3.D. (10) and on page 5 of the ,sure to our previous letter vill be performed on a staggered basis as follows:

a. Until the January 4, 1988 outage, the test vill be performed veekly, staggered between the inboard and outboard MSIV's.

b. For a one month period following the January outage this test vill be performed once every two weeks, again staggered between the inboard and outboard MSIV's, i

c. A revision to the baseline temperatures for a fev selected points vas necessary following removal and reattachment of the cmporary temperature monitoring elements required for the solenoid replacement discussed above.

E. Safety Evaluation / Significance Throughout the November 29 event, the outboard B MSL isolation valve remained operable ari capable of performing its intended saf'ety function. There was no loss of safety system function.

In addition, operator actions vere in accordance with Technical Specification requirements and previous commitments. Vithin three hours following the discovery of the failure, the affected Hain Steam Line was isolated and a reactor shutdown commenced.

Consequently, the event was not safety significant.

35 I

l

Enclosure l PY-CEI/0IE-0297 L I F. Conclusior.s J This section describes the event < :pnology, troubleshooting efforts and evaluations performed to determine the cause of events on November 29, 1987 when one Perry Unit 'l Main Steam Isolation Valve  !

(MSIV), 1B21-F022B, failed to remain closed during performance of a l

modified surveillance test to verify the MSIVs vould fast close on j command. The cause was attributed to the failure of an Automatic i Switch Company (ASCO) Model NP8323A20E 3-vay dual solenoid valve. l The root cause was binding of the "B" solenoid due to the presence  !

of foreign material in the solenoid core area. The source of l foreign material has been identified by visual examination and j laboratory testing as a sliver of EPDM material which separated from l 1

an 0-ring. This occurred during the solenoid rebuild process l

conducted subsequent to the events of November 3, 1987. This sliver was inadvertently dropped into the core area of the "B" solenoid and, since that portion of the solenoid was not disassembled, it was I

not detected until the current investigation. l l

l l

36

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i Overall Conclusion f

b i

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1 1

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Enclosure PY-CEI/0IE-0297 L Overall Conclusion

(

This report summarizes the findings,and conclusions reached during investigations following the MSIV solenoid valve failures of October 29, November 3 and November 29. The first event (October 13 and November 3) identified the cause of failure to be EPDM elastomer degradation due to elevated temperatures in the vicinity of the air packs resulting from steam leaks. The second event (November 29) was discovered during special testing initiated as a result of the first event. The cause of this event was determined to be binding of the MSIV ASCO solenoid valve due to the presence of foreign material. The material was demonstrated to have originated from rebuild activities which occurred following the November 3 event.

No evidence was discovered during the latest investigation which changed the root cause determination of the previous event.

Evaluations for safety significance vere performed during the inves,tigation of both events. In neither case vere there any significant safety hazards identified nor any risk to the health and safety of the public.

Corrective actions vere initiated following both events. As a result of the corrective actions generated from the November 29 event, it was appropriate to modify several of those actions initiated following the October 29/ November 3 event.

In summary, each MSIV solenoid problem was thoroughly evaluated and diagnosed. A reviev of operator decision making during each event identified no actions which were contrary to existing commitments or requirements. The final corrective actions initiated vill ensure that (1) the probability of recurrence of either failure type is minimal (2) thst detection of any such problem vill be rapid and (3) upon detection of such a problem, administrative controls vill ensure that the plant is placed in a safe condition.

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PY-CEI/01E-0297 L l t

ANALYSIS FLAN FOR EPDM S012N01D COMPONENTS

(

1. INTRODUCTIO,N, - -

To determine the cause for f ailure of solenoid pilot valves which resulted in the slow closing of MSIV'S, two approaches will be taken. Both l approaches involve analyses of the EPDM elastomer gasket material. The  ;

physical properties of the elastomeric material which was in service will l be compared to new material to observe degradation, loss of material, deformation, anomalies in surf ace characteristics, and reduced performance. In addition, the gasket material will be subjected to ,

chemical analyses to discover changes f rom original material at the molecular level. Data obtained from the analysis regimen along with data f rom a similar f ailure experienced at Brunswick in 1985 will be used to determine cause.

II. PERSONNEL C0fffACTED l l

Interviews with the Harris Research Personnel and NRR provided information l regarding analyses performed and resulting postulations. PNPP analyses will include methods to confirm or deny these postulated failures. The l full Brunswick Failure Analysis Report has been sent and wal be used as l guidance. A meeting with Ricerca, Inc. personnel regarding this f ailure analysis program resulted in the following proposed course of testing.

(

III. ANALYSIS PROGRAM A. Samples  !

1. Unused Elastomer Gasket material. '

l

2. Used Elastomer f rom pilot solenoids which did not f ail.

3. Used, degraded Elastomer Material f rom f ailed pilot solenoids.

4. Pilot Solenoid valve bodies with elastomer residue.

B. Physical Testing

1. Profilimetric analysis to compare indentations in EPDM discs (sample nos. 3, and 2) j

2. Optical Microscopy to determine the presence of foreign j material, or loss of material from surf aces. '

3. Hardness testing to compare with original specifications.

4. Compression set to compare with unused material and note performance degradation.

C. Chemical Testing

1. Inf rared survey to determine carbonile content. This will provide information about mode of attack (organic acids f rom

, the presence of hydrocarbons) and extent of oxidation.

2. Scanning Electron Microscopy /X-Ray dispersion Spectrometry to confirm or negate copper-catalyzed accelerated oxidation.

(Which was a postulated Failure Mode at Brunswick)

(

Appsndix B PY-CEI/01E-0297 L D. Environmental Testing

( '

Six new dual coil solenoids will be sent to e laboratory for additional environmental testing. The solenoids will be placed in three separate environmental chambers (two pec. chamber) at various elevated temperatures in an energized condition. ne solenoids will remain energized to demonstrate that they will perform their safety f unction at a variety of elevated temperatures for a specific length of time.

IV.

SUMMARY

he above analyses and their results will provide evidence of f ailure mode and will describe any further confirming analyses which may be needed. In addition, recommendations will be made in order to preclude recurrence.

I s

Appendix C

'PY-CEI/OTE-0297 L Ricerca,inc.

7528 Awourn Roaa PO Boa 1000 Pacesvdte Oruo J4077 216 357 3300 TO: J. J. Grimm - CEI FROM: K. A. Krutyholowa DATE: Dececber 3, 1987

SUBJECT:

FOREIGN MATERIAL FROM SOLENOID PLUNGER AREA MICROSCOPIC EVALUATIONS SAMPLE ggg Three particles identified as MSIV 32.and o-ring MSIV 23 were to be compared.

METHODS i The particles and o-ring were examined under a Zeiss Universal stereo widefield optical microscope (SV-8) equipped with indirect reflected light. All particle size measurements were taken from the optical micrographs. ,

Scanning electron micrographs were taken on the JEOL 35 SEM, equipped with Tracor Northern Energy Dispersive X-ray Spectroscopy (EDS) detector. Before examination, the o-ring and particles were mounted on carbon stubs and carbon coated.

Elements from Na (Z=ll) thru U (Z=92) can be detected by EDS.

Backscatter electron imaging (BEI) was used on both the l o-ring and particles. In this technique, the contrast is dependent upon the average atomic number. The brighter areas reflect the presence of relatively heavier elements. )

For example, Pb will have a brighter image than Cu and Zn which will have a brighter image than Si.

RESULTS OPTICAL MICROSCOPY (OH)

Particles MSIV 32 The particles are black and spongy in appearance. A few fibers are attached to the particles (Figures 1, 2 & 3).

The approximate particle dimensions are listed in Table I.

l

Page 2 J.J. Grimm December 3, 1987

[-

i 4

f TABLE I

~

Length Width Depth Particle 1 4.2 mm 0.8 mm 0.3 mm Particle 2 0.6 mm 0.4 mm 0.1 mm Particle 3 0.9 mm 0.3 mm 0.3 mm 0-ring MSIV 23 The brittle side of o-ring MSIV 23 has a piece missing whose length would be 4.2 mm. The indentation or gap is narrower ,

at the edges and bent in the middle (Figure 4). The size and shape of this gap is similar to the largest particle  ;

(Particle 1). i SEM/EDS OF O-RING MSIV 23 (FIGURES 5 & 6)

The edge of the o-ring has numerous areas where pieces of material are missing. Examination of the o-ring by back-scatter electron imaging (BEI) reveals numerous brighter areas indicating the presence of heavier elements (Figure 5d).

The bright areas contain primarily Cu, Zn & Si. Spot mode analysis of areas A, B, C &  ;

EDX spectra attachad. D in Figure 5d have corresponding' ,

SEM/EDS OF PARTICLES MSIV 32 (FIGURES 7-10)

The particles contain many of the same elements present

• in the o-ring. Copper, Zn and Si are present in both the o-ring and particles. Iron is present in both the o-ring and the particles but the Fe counts are significantly higher in the particles. Cr is present only in the particles and not in the o-ring.

Note the morphology at higher magnification of the particles (Figures 10a, 8c & d, 7c) and compare this to the higher magnification micrographs of the gap in the o-ring (Figure 6a). The microstructures of the two materials are very similar.

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x e W , 4 Appendix D PY-CEI/01E-npo7 ( l [

SUMMARY

OF AIR QUALITY TESTING Introduction Work order 87-9983 was generated to perform dewpoint temperature measurements and air particle size distribution for the Instrument Air (IA) supply to, the "B" inboard MSIV (1B21F022B). The WO was initiated to help in determining if air. quality could have contributed to the failure of the ASCO dual solenoid valve that occurred 11/29/87.

, Method Testing was performed at the 3/8" air supply to the ASCO dual solenoid valve and at the 1 5/8" air supply from the MSIV  !

accumulator to the air pack. Prior to performing the dew point '

temperature check, an air blow of approximately 8 minutes through a i pillow case was performed. The pillow case was affixed so that the air was blown through an area equal in size to the end of the connection. Dewpoint temperatures were determined using a dewpoint -

hygrometer sensor (MPL L70N502B). Air particle size distribution was determined using a HIAC/ROYC0 particle counter (MPL L70YO91A) .

t Results Dewpoint temperature measurement satisfied the acceptant:( criter,ia of -40 degrees F. The measured dewpoint temperature of G.4 3/8"'

air supply to the ASCO dual solenoid was -49 degrees F, and to the 1 5/8" supply from the accumulator was -42 degrees F. This is approximately 165 degrees F below the-normal ambient area temperature during operations.

Air particle size distribution measurements satisfied the acceptance criteria of zero particles in the greater than 40 micron range at both of the sample points. The largest particle measured was in the less than 20 micron range. Attachment 1 presents the measured particle distributions. A uniform light grey stain was observed on the pillowcase. This is similar to what was previously observed when air blows were performed on 11/06/87 following the original ASCO solenoid failures.

• Conclusion The instrument air supply to the "B" inboard MSIV was tested to determine if dewpoint temperature and air particle distribution met acceptance criteria of -40 degrees F and zero particles greater' than 40 microns. This acceptance criteria was satisfied. Based on

__ _ _ _ _ ___ -._.___,_,- _. _ , . . . ~ . . . , _ . _ . _ ~ . _ _ _ _ , .

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these acceptable results, it does not appear that the failure of

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PARTICIE SIZE DIFIRIH7FICN i

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Sample 1 : Instzunent Air supply fran MSIV accumulator to air pack for 1821F022B performed 12/04/87 at 0452. -

- Sample 2 : Instrunent Air supply to ASCO dual solenoid for IB21F022; perfonned 12/04/87 at 0505.

t O mNNNEL SIZE SAMPLE 1 SAMPLE 2 1 > 3uM 37 9 2 >10uM 1 0 3 >20uM 0 0 r 4 >3 cum 0 0 5 >40uM 0 0 6 >S0uM 0 0 i

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a P . Appondix E PY-CEI/0IE-0297 L MSIV SOLEN 0ID AND AREA TEMPERATURES Outboard Temporary Monitoring Point Baseline ( F) Action Level ( F)

, 1B21-F028B At solenoid 2 coil 193 212 At solenoid 2/3 body 186 205 At solenoid 3 coil 185 204 Behind actuator 133 146 At solenoid 1 body 133 146 At top of actuator 132 145 Between air pack and actuator 133 146 Bottom of actuator 134 147 At air pack 136 150 1B21-F028D At solenoid 2/3 body 189 208 At solenoid 1 body 131 144 1B21-F028A i At solenoid 2/3 body 194 214 At solenoid 1 body 129 142 .

1B21-F028C At solenoid 2 coil 168 185 At solenoid 2/3 body 168 185 At solenoid 3 coil 165 182 Top of actuator 122 134 Bottom of actuator 104 114 At solenoid 1 body 117 129 At air pack 107 118 Between air pack and actuator 112 123 Behind ac'.uator 113 124 1E12-F00BC Point 33 117 129 e

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e Appindix E PY-CEI/0IE-0297 L

(

MSIV SOLENOID AND AREA TEMPERATURES,,

Inboard 1B21-F022A Six inches from airpack solenoid 130 143 Mounted to airpack solenoid 165 182 Between F022A and F022D 127 140 IB21-F022B Six inches from airpack solenoid 132 146 Mounted to airpack solenoid 167 184 1B21-F022C _

Six inches from airpack solenoid 132 145 Mounted to airpack solenoid 167 184 1B21-F022D Six inches from airpack solenoid 130 143 -

Moun+:d to airpack solenoid

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63 SAMPLE DATE/ TIME DESCRIPTION ANALYSIS MSIV-1 11/6/87:1115 B21-F028B Deposits from 1 5/8" air hose. IR MSIV-2 11/6/87:1545 B21-F028B exhaust port (unknown fluid) IR HSIV-3 11/6/87:1115 Fitting from B21-F028B v/ foreign mat'l IR inside (black solids and oily fluid)

MSIV-4 11/6/87:2101 B21-F022D: = 0.1 ft.3 solenoid supply PSC collected on 0.45p filter paper.

MSIV-5 11/6/87:2108 B21-F0220: = 0.1 ft. solenoid supply PSC collected on 0.459 filter paper.

MSIV-6 11/6/87:2125 B21-F022D = 0.1 ft.3 actuator supply PSC collected on 0.459 filter paper.

MSIV-7 11/6/87:2135 B21-F0220: = 0.1 ft.3 actuator supply PSC collected on 0.459 filter paper.

MSIV-8 11,*7/87:0800 Rectorseal ta Thread sealant sample. IR ta MSIV-9 11/7/87:0800 Neverseeze Thread lubricant sample IR Da Aegel MS 11/7/87:0730 P52-F556: Instr. air at Containment GC

( e cr W l'd"]I-1Qf) penetration (outside). 10 min. blow-down, 5 min. purge of sampler.

es MSIV-11 P52-F556: -Instr. air at Containment GC oNb'*f1/7/87:0745 penetration (outside). 10 min. blov-down, 15 min. purge of sampler.

MSIV-12 11/7/87:1151 B21-F028B: Solenoid supply, =0.lft.3 PSC on 0.459 particulate filter.

MSIV-13 11/7/87:1202 B21-F028B: Solenoid supply, =0.1ft.3 PSC on 0.459 particulate filter.

MSIV-14 11/7/87:1214 B21-F028P: Actuator supply, a0.lf t.3 PSC on 0.45p particulate filter.

HSIV-15 11/7/87:1220 B21-F028B: Actuator supply, =0.lft.3 PSC on 0.45p particulate filter.

MSIV-16 11/7/87:1503 B21-F028B: Solenoid supply, =0.lft.3 PSC on 0.45p particulate filter.

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SAMPLE ,y(E/ TIME DESCRIPTION ANALYSIS MSIV-17 11/7/87:1521 B21-F028B: Solenoid supply, =0.5ft. PSC on 0.45a particulate filter.

MSIV-18 11/7/87:1537 B21-F028B: Actuator supply, a0.lft. PSC on 0.45p particulate filter.

MSIV-19 11/7/87:1553 b21-F028B: Actuator supply, aO.5ft.3 PSC on 0.45p particulate filter.

MSIV-20 11/16/67:1600 B21-F028D: Solenoid valve body.

MSIV-21 11/16/87:1600 Solenoid Rebuild Kits (3 kits v/ elastomer parts)

MSIV-22 11/16/87:1600 B21-F028A: Gaskets, disc, core assembly.

MSIV-23 11/16/87:1600 B21-F022B: Gaskets, disc, core assembly. '

MSIV-24 11/16/87:1600 B21-F028B: Gaskets, disc, core assembly.

MSIV-25 11/16/87:1600 B21-F022C: Gaskets, disc, core asambly._

MSIV-26 11/16/87:1600 B21-F028C: Gaskets, disc, core asset >ly.

MSIV-27 11/16/87:1600 B21-F022D: Gaskets, disc, core assembly.

MSIV-28 11/16/87:1600 B21-F028D: Gaskets, disc, core assembly.

MSIV-29 11/30/87:1230 B21-F022B: Plungers, solenoid "B" MSIV-30 11/30/87:1230 B21-F022B Core Assembly, seats & gaskets.

MSIV-31 11/30/37:1230 B21-F022B: Valve body.

MSIV-32 11/30/87:1230 B21-F022B Foreign Material from Plunger area "B" solenoid (3 particles total)

MSIV-33 11/30/87:2200 B21-F022B Instrument Air grab sample from 2" supply.

MSIV-34 11/30/87:2215 B21-F022B: Instrument Air grab sample from Solenoid supply line.

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CLASS 1E SOLENOID VALVES (ASCO NP SERIES)

EXCLUDING THE MSIV APPLICATIONS, PNPP EMPLOYS A TOTAL OF 55 0F THE SUBJECT VALVES.

OF THIS 55, 37 ARE EITHER LOCATED IN MILD ENVIRONMENTS OR HAVE NO DESIGN BASIS EVENT SAFETY FUNCTION AND ARE VERIFIED NOT TO FAIL IN A MANNER DETRIMENTAL TO OTHER SAFETY SYSTEMS, ie, ARE CLASSIFIED AS "A3" (NUREG 0588 APPENDIX E, PARA.2.C.)

EXCLUDING THESE 37 LEAVES A TOTAL OF 18 VITH DESIGN BASIS EVENT SAFETY FUNCTIONS FOR VHICH THEY ARE CURRENTLY QUALIFIED. OF THIS 18 IHERE ARE A TOTAL OF 5 VHICH ARE OF NORMALLY-ENERGIZED CONFIGURATION.

TECH. SPEC REQUIREME! TIS REQUIRE THAT THESE 5 BE CYCLED PER THE APPLICABLE SVI'S AT FREQUENCIES OF 92 DAYS (0UARTERLY) OR LESS.

BASED ON MAINTENANCE HISTORIES REVIEV, THE SVI'S HAVE BEEll PERFORMED PROPERLY, AS SCHEDULED. NONE OF THE VORK HISTORIES SHOV ANY PROBLEMS VITH THE OPERABILITY OF THESE SOLEN 0ID VALVES VITH RESPECT TO SEAT / DISC "STICKING".

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REPORT ON PARTICLES-INSTRUMENT AIR AT MSIV'S t_#- m _zQ[1/T7 Prepare By Date IEIEQRUCTION h Samples were collected on instrument air supply lines on November 7, 1987 to visually inspect and measure particles collected on 0.45 micron, gridded filter paper. The samples were then logged and sent to Ricerca Inc. for visual inspection and sising.

i METHOD The samples were collected by installing a filter paper holder assembly in series with a rotameter to determine flow rate. The filter paper holder assembly with rotameter was then connected to the MSIV instrument air supply l

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line with tygon tubing. Air was then admitted to the filter paper until a total of 0.1 cubic feet was collected (0.5 cubic feet for samples MSIV-17 &

MSIV-19 ). This total volume was selected as this is the standard volume drawn f or sample collection 'by the laboratory particle counter. Results i obtained could then be more closely correlated to past data collected by use of the particle counter.

The samples were then transported to Ricerca Inc. for inspection and measurement. The particles were inspected and measured by Ricerca laboratory  !

personnel using a Zeiss Universal optical microscope at a magnification power of 125x for particles < 40 microns and at 161x for particles > 40 microns.

The calibrated eyepiece used to measure the particles was calibrated against a stage micrometer. Any fibers found were classified as fibers (instead of particles) if their length to width ratio was greater than 10:1.

Each filter had an effective filtering area of 980 square millimeters. For each sample, this entire area was evaluated.

RESULTS

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Table 1 lists the samples by number, total number of particles >20 microns and the actual particle sise.

The particle characteristics could be described as follows:

1. Clear, crystalline-like particles *

2. White, cloudy particles *

3. Dark particles * ,

4. Metallic-like particles

5. Fibers

• indicates the type of particles making up the majerity of the particles 740 microns. Non-asterisi:ed particles and fibers were relatively few ir.

number by comparison, but aeveral were greater than.40 micron in siso.

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pCCUCLUSIRD Because of the probability of some contamination occuring due to the large l amount of exposed sample handling involved with the filter paper collection method, it is not easily ascertained what percentage of these results may be due to contamination. It is suspected that the majority of fibers found are dust particles from room air. The particle counter instrument is currently being recalibrated to detect and quantify particles in the 40-50 micron and >50 micron range and will be used to test the validity of the filter parer collection results.

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, + l Page 3 Table 1 t MSIV-4 (ath) t MSIV-5(tt6 Particle il 43 pm 2 43 Particle i1 56 um  !

3 2 130 56 3 167 4 62 5 68 4 186 Fiber il >500 6 68 No fibers found  :

MSIV-6(zt@ MSIV-7(210) . i Particle il Particle il 38 um '

37 um 2 40 2 56 3 50 i 3 68 4 '

4 68 62 5 81 1 5 68 6 6 87 93  !

7 93 7 93 1 B 124 No fibers found I 9 155 10 260 Fiber il 143 MSIV-13 (2e Gh l 2 >l60 Particle il 43 pm 3 >600 2 4 NM 50 l 3 68 '

5 NM NM=not measured 4 87 5 174  !

6 174 '

x Fiber MSIV-12 (J.e (5 )

il 217 2 279 )

Particle il 3 400 38 um 4 3000 2 50 3 62 4 74 5 >186 MSIV-15(2eB) 6 280 Particle il No fibers found 2 43 um 50 3 136 Fiber il >700 MSIV-_14[284\ 2 >6000 Particle il 40 pm 2 43

, 3 50 4 50 5 62 6 62 7 81 8 87 9 105 10 130 No fibers found

t Page 4 Table 1 Cont'd MSIV-16(it3)

Particle il 56 um 2 56 3 87

, No fibers found ,

MSIV-18[f.BB)

Particle il 38 um 2 62 3 68 4 74 5 124 No fibers found MSIV-17(268) ,

Particle il 43 km 2 62 3 62 4 43 5 68 6 68 No fibers found MSIV-19hs8)

Particle il 74 um 2 143 3 217 4 NM Fiber il NM NM=not measured N - _ _ _ - - - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ -- ____

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ISEG Review of R61 & C91 for MSIV Failure The Independent Safety Engineering Group vas asked to review the Sequence of Events Recorder and Process Computer Sequence of Events Log over the time period that the Main Steam Isolation Valves (MSIVs) were being tested. The October 29 and November 3, 1987 printouts were reviewed for any alarms associated with the MSIVs. There vere no alarms associated with the MSIVs on the Sequence of Events Recorder. The Process Computer Sequence of Events Log appropriately listed those times when the MSIVs moved past the ninety percent open position.

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1 INTENT pe wa 'c. jn l E'di" INSTRUCTION TEMPORARY CHANGE eu.em., aj"- /U  !

MV 1418411> II M (

llouttac.OMIA:

SVI-C71-T0039 I MAIN STEAM LINE I SO1 AT10N VA1.V" Pl oWRF CHANNT1 TUNETinN A1 l

( wms iWsp NONE ___

on,:uty Datt L!st ta:a attaxo Pet: 2,3,4.5,6,7,8,9,10,i1,14,15,16,

!, IA[ M l oitt /p 3

17.IA 10.20 gas >; a>1= vst xv Half Scraes and associated annunciators will not occur as l I

discribed by this instruction. Deleted those steps that were not in accordance with the system logic.

INF0fif/ild10h l

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Is there a Change to the pisa.t es cescribec in the r$AR? OE REA$oN: MO [ fA AME *TD PL 43? iS f W CLtl E'b .

Is there a Change to a procedurelinstruction es oescribed in the FSAR?

Agaso,,; Tlh5 1 +,11.7 2 O( 'p i r,3 iS L3 nT 'D F TA I LE D 1M 'T?E FSAR Is there a test or experiment not describec in the F$AR? g RE ASch: NO 3 $7 M E v f 460 R s H C~.L37 iS l OY3Ld6 D -

Is there a change to technical 50ecifications? O9 '

!s there an effect on the enviroment or change to the Environments 1 Protection Plan?

RE M : k& F F ~r- e"r Od 'TH F T: /&/ P h & & F CR t C.11 A M G E Th 'Tb F 1:9P I5 iOW LVC-D I l

'60'. 680 potential for en threviewed l h Answers to all Westler.s are Safety or Environmental Osestion exists. Peo further review rowired. l Answers to one or acre Questions is 'YES'. Further review recNited.

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tc cetential for en Unteviewec h Answers to all Questions are C' Sa:ety cr Envirerrental Ovestion exist. No further review reostre:.

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OM7At SVI-C71-T0039 Page: i Rev.: 1 THi' CLEVELAND ELECTRIC ILLUMINATING COMPANY PERRY NUCLEAR POWER PLANT OPERATIONS TNUAL Surveillance Instruction TITLE: MAIN STEAM LINE ISOLATION VALVE CLOSURE CHANNEL FUNCTIONAL REVISION: 1 EFFECTIVE DATE: /o[/>/h ; '

(

DATE

+ ____ .._________...______..____________.....__________ .....+

l PREPARER: l T.B. SHAFFER/ R.C. MILLER l i________________l__________________.......______i.4F4fdf._! l l REVIEWER: l l l

. _______________l_ _ _ ___

........____l__ ..l l PORC MEETING NO:l g l l

[ ____.______ ..._______....

._..___...l.___ ..___l

• l APPROVED: la l _ _.._ _ _ _ _ r qm I

___.______.__ __ J.__ll l ,

l_________________ .________.. __________________ .. __________;

1 1 l l

_______.. l l

+....______.._________....____________________________ ..____.+

. - . - . . - . . . - - - . , . . _ . _ . . . _ _ _ . _ , . , . . . _ _ . . . _ . . . , . ~ . . . . . . . . . _ . . , _ . - _ . _ _ . _ . _ ~ . . , . _ . ~ . . _

l l

OM7A: SVI-C71-T0039 l Paget 11 Rev 1 .

i r

10CFR50.59 Applicability Check -

+____ ______________. ______.___.._________.__._-.__.__________+

l Yes No

~~ l l Is there a change to the plant as described in l  :

l the FSAP.? l ,

I I .

l Is there a change to a procedure / instruction ,/ l  :

l as described in the FSAR? V l  !

I I l Is there a test or experiment not described in ,/ l ,

l the FSAR? ,

V l  :

l Is there a charge to the Technical Specification? P!l I I

l (If yes, perfo.in a 10CFR50.59 Safety Evaluation j  ;

I per PAP-0305). l ,

l......__________.__________________________. ______________l ,

- 1 l .

( l l Applicability Check I l I

l Performed by ,

Date Idd/4df4, '

+ ......___________;____________________________________s______. ,

?

SCOPE OF REVISION: 1. Instruction revised to incorporate format l changes of TAP-0503. ,

2. Numerous corrections were made throughout i the instruction.

I s

, - .,,m-, w,

i g l S fC ANGL OM7A 5 -C71-T0039

, Page: 1 I Rev.I 1 PAGE Of M Main Steam Line iso;ation valve closure Channel Functional

1.0 DESCRIPTION

1.1 Scope

The Main Steam Line Isolation Valve Closure instrumentation channels are functionally tested by stroking the MSIV's and monitoring'each trip relay and their common annunciator.

,This instruction fully satisfies the fun:tional surveillance requirements of Technical Specification 4 3 1 1 T*bl* 4 3 1 1-1 It** 5-Tc B This instruction fully settsfies the functional surveillence requirements of Technical Specifiestion 4 3.1.1 Toble 4.3.1.1- 1 liem 6, and the fail sefe function and pertiel exercise testing of velves 1821-F022A,1821-F022B,1821-F022C,1821-F022D, 1821-F026A,1821-F028E,1821-F0280 and 1821-F02BD per Technicel Specification 4.0.5.

This instruction will verify the operability of the following:

1. 1C71-N700A 9. 1C71-N702A

2. IC71'-N7 00B 10. 1C71-N702B

3. 1C71-N700C 11. 1C71-N702C

4. 1C71-N700D 12. 1C71-N702D

5. 1C71-N701A 13. 1C71-N703A

6. 1C71-N701B 14. 1C71-N703B

7. 1C71-N701C 15. 1C71-N703C

8. 1C71-N701D 16. 1C71-N703D

1.2 Frequency

At least once per 31 days TC 1.3 Technical Specification Applicable operational Conditions:

8 Ct3 This function shall be automatically bypassed when tl.a REACTOR MODE SWITCH is not in the RUN position.

1.4 Cross-Reference N/A 2.0 PRICAUTIONS AND LIMITATIONS

1. Step numbers marked with a dollar sign ($)ifications.immediately to the left are required by Technical spec Such items, if found to exceed their Allowable value may be NRC reportable and shall be brought to the attention of the Unit Supervisor.

2. Those steps of this instruction designated by an "at" sign (t) are to be initialed or signed on the g appropriate data sheet or Data Package Cover Sheet as data is entered or an each step is completed.

8

Aggg ~ og7A:

TEUP A} IGE }Lgy gyg.C71-T0039

1. # Paget 2 i'

PAGE ./_ 0F 6_ PAQg org Rev.: 1

3. All steps are to be performed in sequence and the instruction carried through to completion, unless otherwise indicated.

4. The Unit Supervisor or designated alternate must be -

notified immediately whenever an instructional step cannot be completed as stated, or if problems develop during the performance of this instruction.

5. This instruction should be read in its entirety before proceeding with the performance of the instructional steps.

Tc g 6. During the performance of this SYl the INBD and OTBD MSlY's vill be stroked, in modes 1, 2 or 3 e steam sink may be required.

9 '

• 10 DEkTEb TC

{ 8

**"'N""'""""""""'**'"*"'"'

9. To avoid unecessery velve vetr, full stroking of MSlY's must be kept to e minimum.

3.0 MANPOWER AND EQUIPMENT 3.1 Manpever/cormunications TC g 1. Two IEC technicians are required to perform this instruction.

a. Two technicians in Control Room to monitor the I trip relays at the following panels (

1. .DIV 1 RPS INSTRUMENTATION & AUXILIARY RELAY l PANEL (1H13-P691)

2. DIV 2 RPS INSTRUNINTATION & AUXILIARY RIIAY '

PANIL (1H13-P692)

3. DIV 3 RPS INSTRUMIN1ATION & AUXILIARY REIAY PANEL (1H13-P693)

4. DIV 4 RPS INSTRUMENTATION & AUXILIARY REIAY TC PANIL (1H13-P694) 8 .

2. Establish communications between the technicians and the supervising operator.

TC. .

8

I C N5f.-- TEMPC ANGI OM7At SVI-C71-T0039

, PAGE .2_0F d pAgg grM' ,

3.2 Required Measuring and Test Equipment (M&TE)

1. 2 Digital Multimeters (DMM-1 & DMM-2), T1 uke 77.

3.3 Additional Tools and Equipment

1. Keys needed for P691, P692, P693 and P694.

Tc 8 .

4.0 PRIREQUISITIS 9 1. Obtain the Unit Supervisor's "Authorization to Start Prerequisites" signature on the Data Package Cover sheet.

Y f 2. This instruction may be performed in Operational 8 Condition 1,a.3.9 or s. Attachment 1.

t 3. ~

Verify that no testing or maintenance is being

( performed which would initiate t. half scram RPS signal. Attachment 1.

4. Verify the following annunciators are reset:

Attach =ent 1.

6 a. 1/2 SCRAM A/C (P680-5A-A9)

G b. 1/2 SCRAM B/D (P680-5A-39)  ;

N $'

pq bObTLD

6. If Unit is in N0DE 2,4, or 5, verify the following:

Attachaent 2.

6 a. C95 computer point RPS CHANNEL IS01ATION A STATUS, 321EC013 indicates NORM.

O b. C95 computer point RPS CHANNEL IS0IATION B STATUS, 321EC014 indicates NORM. -

O c. C95 computer point RPS CHANNEL IS01ATION C STATUS, 321EC015 indicates NORM.

O d. C95 computer point RPS CHANNEL IS01ATION D STATUS, 321EC016 indicates NORM. .

'Tr. performance of this 3 07. A RWP mcq bt, f@rt.A ##

instruction. Aftachment 1.

TEMPC IGE

(- .

PAGE A or d _

TE iPC ANGE JgW gxAgq[ CN7At SVI,C71,Tgo2, PAGE f 0F .sI_ fAGE OF M s 1 0 8. Verify the Calibration Due Date is current on all test equipment. Attachment 1.

9 9. Record all test instruments, MPL, Cal Date, and Cal Due Data. Attachasnt 2.

10. Vertfy the folloving: Attachmentf.#.L.

8 9 e. Svit:h IC71 A $6A MAIN $ TEAM LINE ISOLYALVE TEST (P691)isin the WRM parition.

+ b. Svitch IC71 A-565 mlN $ TEAM LINE ISOL YALYE TEST (P692)is in the ERM posttien.

e c. Svitch IC71 A 36C MAIN STIAM LINIISOL YALVE TEST (P695)is in the ERM position.

9 d. $dt:h IC71/ $60 $lN STIAM LINE ISOL YALYE TEST (P694) 13 in the L' ICRM positic3.

5.0 SU*AVT!LIANCT TN!p0CTION 5.1 Su weillance Tert 4 1. Obtain the Supervising Operator's Authorization to Start Test' signature on the Data Package Cover Sheet. .

2. -Ir.f;n Ou;;; ti;ir.; ^;;r;t;r O.;t the fellwir.g

.=y,igt0g yill .ter? ^- iM reett d".-in; '":

'F- a. Eis Ee:ri s . a (;;;;4A-A;; G-LI 1.Q)

T c T c.

I' D E,ltTE p .

9 8

1 g gggg ggg OM7A: SYl-C71-T0039 O , Page . Ha I

Or M '

PAGE t

(PAGE lhTENTIONALLY LEFT BLANK) l l

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l

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( '

3 MPCA NGE CM7As SVI-C71-T0039

1. l TEMPChAN7 q PS9*t S

, PACED. Of d PACEf_.0Fb'.

8

5. Connect Digital Multineter (DMM-1) to terminals 6 and C of relay 1C71A-K3A (P691) (set to oms) .

6. Cent.ect Digital Multir.eter (DMM-2) to terminals 6 and C. of relay 1C71A-K38 (P692) (set to avo) .

47. Inform Una %pervwor that the MSIV's, vill be stroked. Record time and date. CWh u.% Sph-4.

AWAAtke 3..

4 8. Request Supervising Operator to place MSL A INBD MSIV 1521-T022A switch (P601-18C) to TEST. Attachment 2.

9 9. Request Supervising operator to place MSL A OTBD MSIV

( 1321-T028A switch (P601 19C) to TEST. Attachment 2.

w -

/0

10. Request Supervising operator to depress and hold MSL A INBD MSIV TEST switch 1821R-83A (P601-18C) until the following occurs, den release switch:

Attachment 2. .

9 a. MSL A INBD MSIV 1521-F022A green indicating light )

(P601-18C) is on. J "TC $$ b. DMM-1 indicates relay 1C71A-K3A con %A menem g 8 $4 c. DMM-2 indicates relay 1C71A-K3B csa w k ch ed.

d. bi,[s.vt.o ,

After MSL A INBD MSIV 1521-F022A green indicating j 11.

light (P601-18C) is off, verify the following:

Attachment 2.

O

a. MSL A INBD MSIV lb21-F022A green indiccting light .

(P601-18C) is off. '

7C- 9 b. DMM-1 indicates relay 1C71A-K3A c66MW open.

c. DMM-2 indicates relay 1C71A-K3B cankd op.

Q t I

9 I

~

I TEUP CHA5GE '

,g TLVF ANGE OM7At SVI-C71-T0039

, PAG E .5_ OF ./.1 # Page: 6 PAGE OFM / Rev.2 1 p

l0 ,

12. Request Supervising operator to depress and hold MSL A OTBD MSIV TEST switch 1821H-S4A (P601-19C) until the following occurs, then release switcht  :

l Attach =ent 2.

I 4 a. MSL A OTBD MSIV 1321-F028A green indicating light j l

g (P601-19C) is on. '

v $$ b. DMM-1 indicates relay 1C71A-K3A c4Me.d ,doud.

Tl8 $$ c. DW.-2 indicates relay 1C71A-K3B ceMcrA cAos@

l0 0 P Lis.rA D

13. After MSL A OTBD MSIV 1B21-F028A green indicating light (P601-19 C) is off, verify the fcllowing:

. Attachment 2.

O a. MSL A OTBD MSIV 1821-7028A green indicating light (P601-19C) is off.

O b. DMM-1 indicates relay 1C71A-K3A (c.r#4r te t.n .

p8 0 c. DW.-2 indicates relay 1C71A-K3B C4W.* cpm.

10 d . D r.t e n .p 4 14. If in Mode is.4 request Supervising operator to place MSL A INBD MSIV 1B21-F022A switch (P601-18C) to AUTO.

Attachment 2'.

0 15. If in Mode 16.-Arequest Supervising operator to place g

7Cl* MSL A OTBD MSIV 1521-7028A switch (P601-19C) to AUTO.

Attachment 2.

0 16. If in Mode 3,4, or 5, request Supervising operator to place MSL A INBD MSIV 1521-F022A switch (P601-18C) to CIASE. Attachment 2.

0 17. If in Mode 3,4, or 5, request Supervising Operator to place MSL A OTBD MSIV 1821-F028A switch (P601-19C) to CIASE. Attachment 2. ,

18. Connect Digital Multimeter (DMM-1) to terminals 6 and 8 C of relay 1C71A-K2C (P693) (set too u ).

19. Connect Digital Multimeter (DMM-2) to terminals B and C of relay 1C71A-K3M (P694) (set tok ) .

0 20. Request Supervising Operator to place MSL C INBD MSIV 1821-F022C switch (P601-18C) to TEST. Attachment 2.

1 1

I TD.IPChCE g, / TEMPC ANGE OM7At SVI-C71 T0039 P # Page: 7 L AGE 42. OF /.].PAGE OF k Rev.: 1 0 21. Request Supervising operator to place MSL C OTBD MSIV 1321-T024C switch (P601-19C) to TEST. Attachment 2.

22. Request Supervising Operator to depress and hold MSL C INBD MSIV TEST switch 1821H-53C (P601-18C) until the following occurs, then release switch:

Attachment 3.

O a. MSL C INBD MSIV 1321-F022C green. indicating light TC $9 (P601-18C) is on.

b. DW.-1 indicates relay 1C71A-K3C Cate.ct C.bhed.

K6 50 c. DW.-2 indicates relay IC71A-X3H cWe.d C.\ow.1.

jg d. D LlLTED

23. After MSL C INED MSIV 1321-T022C green indicating light (P601-18C) is off, verify the following:

Attach =ent 2.

O a. MSL C INBD MSIV 1321-T022C green indicating light E (P601-18C) is off.

f b. DMM-1 indicates relay 1C71A-K3C comt.ct cst %

8

( e c. DW.-2 indicates relay 1C71A-K3M c.6,at.a open.

d.Dt.len.)

10

24. Request Supenising Operator to depress and hold MSL C OTBD MSIV TIST switch 1521H-54C (P601-19C) until the following occurs, then release s,vitch:

Attachment 2.

O a. MSL C CTBD MSIV 1B21-F028C green indicating light T (P601-19C) is on.

$8 b. DMM-1 indicates relay 1C71A-K3C ccmc.t& clow:A.

p 8 $4 c. DMM-2 indicates relay 1C71A-K3H caMach chac1.

y A. DLILTC)

25. After MSL C OTBD MSIV 1821-F028C green indicating ligh*. (P601-19C) is off, verify the following:

Attachment 2.

4 a. MSL C CTBD MSIV 1521-F028C ' green indicating light (P601-19C) is off.  ;

I $ b. DMM-1 indicates relay 1C71A-K3C CafA d opm. '

.$ 0 c. DMM-2 indicates relay 1C71A-K3M CArbet opth. l

'y k D LinTEk .

t .

8 ' 28- 2 ' 1" " d ' ' *

• i" * ' t '"P '"i'i"' P*** ** Pl***

MSL C INBD MSIV 1821-F022C switch (P601-18C) to AUTO.

Attachment 2.

l l

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.- , -,3. -.y-,, ,-, , -%..

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(

l TEMP 2HAIJGE CM7A: SVI-C71-T0039 TiMP HAhGg 6 /d #*I"I 8 8

PACE 4 0F/7 -- PAGE .L 0F A/._, Rev. 1 g8 l 9 27. If in Mode k 1 request Supervising Operator to place MSL C CTBC MSIV 1321-7028C svitch (P601-19C) to AUTO.

Attachnent 2. ,

9 28. If in Mode 3,4, or 5, request Supervising operator to place MSL C INBD MSIV 1321-T022C switch (P601-18C) to CLOSE. Attachment 2.

If in Mode 3,4, or 5, request Supervising Operator to 0 29.

place MSL C CTBD MSIV 1821-7028C switch (P601-19C) to CLCSE. Attachment 2. .

'** DEIcTO p

/0 .31 D s.(dch.

32. Connect Digital Multimeter (DMM-1) to ter=.inals 6 and 8 - C of relay 1C71A-K3G (?693) (set tonbo) .

k

23. Connect Digital Multimeter (DMM-2) to ter=inals 6 and C of relay 1C71A-K37 (P692) (set toe w ).

9 34. Request Supervising Operator to p* ace MSL B INBD MSIV 1321-70223 switch (P601-18C) to TEST. Attachment 2.

9 35. Request Supervising operator to place MSL B OTBD MSIV 1B21-70283 switch (P601-19C) to TEST. Attachment 2.

TC<

/0

36. Request Supervising operator to depress and hold MSL 3 INBD MSIV TEST switch 15215-333 (P601-18C) until the following occurs, then release switch:

Attachment 2.

4 a. MSL B INBD MSIV 1B21-70225 green indicating light (P601-18C) is on. .

7C. gg b. DMM-1 indicates relay 1C71A-K3G coch.a ciow.1.

e 6 30 c. DMM-2 indicates relay 1C71A-K3T caWe eM.

ek. M 2. fic,TT.D

1 .

i f TCbPCHANGE g /g 1&MP ANGE OM7As SVI-C71-T0039  !

f Page 9 l LPAC

~E.d OF JJ

- - PAGE OF Rev.I 1

37. After MSL B INBD MSIV 1321-F0225 green indicating light (P601-18C) is off, verify the followings Attachment 2.

i 9 a. MSL B INBD MSIV 152'l-F0225 green indicating light  !

E (P601-18C) is off.

9 b. DMM-1 indicates relay 1C71A'-K3G Co%s.d o p .

O 9 c. DMM-2 indicates relay 1C71A-K3F cah% d ope.%

1C' d. pnIMs.b

/0

38. Request Supervising operator to depress and hold MSL l B OTBD MSIV TIST switch 1821H-54B (P601-19C) until j the following occurs, then release switch: L Attach =ent 2.

9 a. MSL B OTBD MSIV 1321-F028B green indicating light ,

(P601-19C) is on.

$ b. DMM-1 indicates relay 1C71A-K3G abwe.d c.icMd.

8 s$ e c. Dw.-2 indicates relay 1C71A-x3r comer.cters:e, gc. f. Pituo

/0 39. After MSL B CTBD MSIV 1321-F028B green ind! cats .g i light (P601 *.9C) is off, verify the follow! -

Attach =ent 2.  !

$ a. MSL B OTF" MSIV 1B21-F0283 green indicating light (P 601-19 ; '; is off.

A 9 b. DMM-1 ineicates relay 1C71A-K3G 00 NTcer o;R.,%

t 8 e c. DMM-2 ine: cates relay 1C71A-K3r come opas, ,

d DEILT4, 9 40. If in Modeleta request Supervising Operator to place 8 MSL B INBD MSIV 1821-F0223 switch (P601-18C) to AUTO.

Attachment 2.

9 41. If in Modeloc1 request Supervising operator to place MSL B OTBD MSIV 1B21-F0285 switch (P601-19C) to AUTC.

Attachment 2.

9 42. If in Mode 3,4, or 5, request Supervising Operator to place MSL B INBD MSIV 1B21-F0223 switch (P601-18C) to CIASE. Attachment 2. ,

9 43. If in Mode 3,4, or 5, request Supervising Operator to place MSL B OTBD MSIV 1B21-F0288 switch (P601-19C) to ,

CICSE. Attachment 2.

- a I

TEMP CHdilGE p /0 _ILW C ANGE OM7A: SVI-C71-T0039

1. Page 10 PAGE 4 0F./.7_ i 1

I Rev.:

m PAC ( l.l 0F_ k

44. Connect Digital Multimeter (DMM-1) to terminals 6 and 8 .C of relay 1C71A-K3E (P691) (set to che) .

45. Connect Digital Multimeter (DMM-2) to terminals 6 and C of relay 1C71A-K3D (P694) (set tooN 6).

0 46. Request Supervising Operator to place MSL D INBD MSIV 1B21-T022D switch (P601-18C) to TEST. Attachment 2.

9 47. Request Supervising operator to place MSL D OTBD MSIV 1B21-T028D switch (P601-19C) to TEST. Attachment 2.

48. Request Supervising Operator to depress and hold MSL D INBD MSIV TEST switch 1B218-S3D (P601-18C) until the following occurs, then release switch:

At*;achment 2.

O a. MSL D INBD MSIV 1B21-T022D green' indicating light g (P601-18C) is on.

$$ b. DMM-1 indicates relay 1C71A-K3E cashr.A c.\cMdi

• O Si c. DMM-2 indicates relay 1C71A-K3D Ct,rkad c\crAd.

( -

• a.>uno

/0 49. Af ter MSL D INBD MSIV 1321-T022D green indicating .

light (P601-18C) is off, verify the following:

Attachment 2.

9 a. MSL D INBD MSIV 1B21-7022D green indicating light E' (P6.)1-18 C) is off.

0 b. DMM-1 indicates relay 1C71A-K3Z enheY spts 6 c. DMM-2 indicates relay 1C71A-K3D h etopt%

Yb d. b Mr u.p g

50. Request Supervising operator to depress and hold MSL D OTBD MSIV TEST switch 1B21H-54D (P601-19C) until the following occurs, then release switch:

Attachment 2.

9 a. MSL D OTBD MSIV 1821-F028D green indicating' light 1 (P601-19C) is on.

$8 b. DMM-1 indicates relay 1C71A-K3E OceAc4 e.%r.tli 6 $$ c. DMM-2 indicates relay 1C71A-K3D on%ft eiew1.

O. bMBGP

$ 51. After MSL D OTBD MSIV 1B21-r028D green indicating ,

light (P601-19C) is off, verify the following:

Attachment 2.

-. . _ , - . - . - , , - , - - _ - - . ..,,,-.,_r-.,w-...w..~...----.,,--__..._.__..,---.-....._,w.~.,--e--,

I TE5PCHANGE p fD TEMF ANGE og7A: syg.C71-T0039

, OF M e P AG F ._ _ _OF

_ 1./.

6 a. MSL D OTBD MSIV 1321-T028D green indicating light (P601-19C) is off.

9 b. DMM-1 indicates relay 1C71A K3E cardach apaA. -

.p B e c. DMM-2 indicates relay 1C71A-x3D e_est.cv .pss y A. DK lCTE) 0 52. If in Modelar1 request Supervising operator to place O MSL D INBD MSIV 1821-T022D switch (P601-18C) to AUTC.

Attachment 2. .

t 53. If in Modelera raquest Supervising operator to place MSL D OTBD MSIV 1821-F028D switch (P601-19C) to AUIO.

Attach =ent 2.

0 54. If in Mo'de 3,4, or 5, request Supervising operator to place MSL D INBD MSIV 1B21-F022D switch (P601-18C) to CLOSE. Attachment 2.

4 55. If in Mode 3,4, or 5, request Supervising Operator to place MSL D 0".BD MSIV 1521-T028D switch (P601-19C) to CIhSI. Attachment 2.

N

~

jo b e tcce)

.57 G8. DISCONNICT DMM-1 and DMM-2.

1 0 Co. Inform (Aww $@a.Nw- that the stroking of the.

8 MSIV's is completed. Record time and date. Otu h I LAs% Syatw1L. 5%s AmaM L 5.2 Plant / System Restoration 0 1. Complete the Systen Restoration Checklist )

(Attachment 3) using the methods of Independent l Verification. Upon completion, infors Supe?.'ising operator of systen restoration and return the keys for P691, 7692, P693 and 7494.

f

- - - -----,-,.,-,..-.,,.,,,.,,.,.,__,__,.,n.,,,.,__.,, _, , _ _ , ,

l l

.' l l

l OM7A: SVI-C71-T0039 I Page: 12 Rev.: 1 5.3 Acceptance criteria

1. If any Technical Specification required items as i indicated by dollar signs ($) on the Data Sheet have not been performed satisfactorily, notify the Unit Supervisor. l

2. If any other items checked in this surveillance did not perform satisfactorily, notify the I&C l Supervisor. '

3. Satisfactory completion of the surveillance will be based on Technical Specification items (marked with a dollar sign) only. l l

9 4. Check the appropriate block on the Data Package Cover  !

Sheet as to whether the test results were acceptable or unacceptable and obtain Unit Supervisor's signature. i 5.4 Records 1

The follovir.7 documents are generated by this l instruction:

(

1. Quality Assurance Records: '

l Data Package Cover Sheet I l

Prerequisites Sign-off Sheet Data Sheets System Restoration Checklist

2. Non Quality Records:

None Record; identification and disposition are accomplished in accordance with Records Retention / Disposition Schedule (RR/DS) and handled in aucordance with PAP-1701, Plant Records Management.

6.0 REFERENCES

6.1 CEI Perry Technical Specifications 6.2 CEI Prints B-208-013 B-108-040 I B-208-222 l

1

1 I

t OM7A: SVI-C71-T0039  !

Page: 13 Rev.s 1 7.0 ATTACRMENTS 7.1 Attachment 1-Prerequisites Sign-off Sheet I

7.2 Attachment 2-Data Sheets 7.3 Attachment 3-System Restoration Checklist 7.4 Attachment 4-Relay Base Diagram l k

l l

\1 . . _ - - . - . . - - . . - - . . . . .-

TEMP CHMiGE F 10. .,

PACE //_, Or /1 i

Attachment 1 TLMPC ANGC OM7At SVI-C71-T0039 Sheet 1 of 1 iP > Paget 14 PAGE]3. OF.2./ ,Rev. I 1

Main Steam Line Isolation valve Closure Channel Functional ,,

Prerequisite Sign-off Sheet Initials 4.0.2. This instruction any be performed in operational b Condition 1,LL M or 5.

4.0.3. No testing or maintenance is being performed which would initiate a half scran RPS signal.

4.0.4. The following annunciators are resets

a. 1/2 SCRAM A/C (P680-5A-A9)

b. 1/2 SCRAM 3/D (P680-5A-B9)

TC- 4.0.5. DE LETf D

/0 4.0.6. If unit is in MODE 3, 4, or 51 k a. C95 co=putor point, RPS CHANNEL ISOLATION A STATUS, B21EC013 indicates NORM.

b. C95 computer point, RPS CHANNEL ISOLATION B STATUS, B21EC014 indicates NORM.

c. C95 computer point, RPS CHANNEL ISOLATION C STATUS, B21EC015 indicates NORM.

d. C95 computer point, RPS CHANNEL ISOLATION D STATUS, B21EC016 indicates NORM. l 4.0.7 h W M eMe . CNLS C3MD 4.0.8. Calibration Due Date is current on all test equipment.

TL - BY_E. f%%CMB 19GTr_, %

g Performed bys_ / /

/ /

Signature Initials Date 1

. - _ , , _ _ - _ _ _ _ _ _ _ , - . _ , . _ _ _ . , _ , _ ,,....._,,__.___--,_,,....,,,.,,_,.m____~_._,. -

m,_,, , , , , , _ , , - , , , . . _ _ - ,

Tc l

,. 8 TEke enAnot OM7^ : SY'-C7'-70 39

, p Pepe : 14o.  ;

R'Y' I PAGE18 OF M ' l Attechment 1 (Cont.)  :

Sheet la of 1 inittels  !

4.0.10.a. Svitch IC71 A-S6A MAIN STEAM LINE ISOL YALYE TEST is in the NORM

- position. -

4.0.10.b. Svitch IC71 A-56B MAIN STEAM LINE ISOL YALYE TEST is in the NORM $

position. ,

4.0.10.c. Svitch IC71 A-56C MAIN STEAM LINE ISOL YALYE TEST is in the NORM position.

j 4.0.10.d. Svitch IC71 A-56D MAIN STEAM LINE ISOL YALYE TEST is in the NORM position.

l I

f I

l t

s '

TEhiP CHMiGE PAGE d =

I i TEMPC ANGE ,

PAGE 10F 2.,_

Attach =ent 2 ggp igggg OM7As SVI-C71-T0039 Sheet 1 of 4 , Page 15 R"v'I 1 PACE OF k Main Steam Line Isolation valve closure channel Functional Data Sheet SECTION 5.1 Initials 7C TC.-

8 9 k

" ~

7. una ' a:c/-

i informed that the MSIV's vill b @e stroked. /

Time Date

. U . *J i *b '.W% ri.

8. . MSL A IN3D MSIV *321-7022A switch (P601-18C) placed to TEST.

9. MSL A OT3D MSIV 1321-F028A switch (P601-19C) placed to TEST.

10.a. MSL A INED MSIV 1321-7022A green indicating light (7601-18C) is on.

$ 10.b. E00(-1 indicates relay IC71A-DA curaut chad.

8 10.c. E20(-2 indicates relay 1C71A-D3 came cicmA 1

l Y

g to.4 ' DERTO 11.a. MSL A IKBD MSIV 1321=F022A grata indicating light (7601-18C) is off.

~FC g 11.b. 320(-1 indicatas relay T C71A-DA (JW.ct opan. ,

11.c. DMM-2 indicates relay 1C71A-D 3 em A e4 ep.s.

8 Denotes Technical specification requireaant.

. - _ _ . - _ _m__ _ .- . , _ _ _ - ._. . , _ . . _ . , , , , -,. .,~... _-._ -- ., . - -.-. - ,_m

. -....- - _ - _s --______ - - -

l TEMPCHANGE 4 l.O I

dQ OF ,/,7 +

Attachr.ent 2 (Cont.) f pg. g [ OM7A Page SVI-C71-T0039 16 Sheet 2 of 6 ,

1. • • • ' 1 PACT . Of A.),,_

_ ~

SECTION 3.1 Initials i .

ja H.A b r fa m .

12.a. MSL A CTBD MSIV 1321-7028A green indicating light (P601-19C) is on.

IC- $ 12.b. DMM-1 indicates relay 1C71A-K3A ce%:,c4 c.lusa B 12 4 c. DMM-2 indicates relay 1C71A-K3B conga c,ww, W II D D L{r, N b

, jp 13.a. MSL A OTBD MSIV 1B21-T028A green indicating light (P601-19C) is off.

13.b. DMM-1 indicates relay 1C71A-K3A cofWc d opLn.

13.c. PMM-2 indicates relay 1C71A-K3B CCAht opta.

N jf 13 b h L IbTO

14. MSL A INBD MSIV 1521-T022A switch (P601-18C) 8 placed to AUTC. (Mode 1 or a )  ;

15. MSL A OTBD MSIV 1321-7028A switch placed (P601-19C) to AUTO. (Mode lera, )

16. MSL A INBD MSIV 1521-T022A switch (P601-18C) placed to CLOSE. (Mode 3,4, or 5)

17. MSL A OTBD MSIV 1821-F028A switch placed (P601-19C) to CIASE. (Mode 3,4, or 5)

20. MSL C INBD MSIV 1921-7022C switch (P601-18C) placed to TEST.

21. MSL C CTBD MSIV 1821-F028C switch (P601-19C) placed to TEST.

22.a. MSL C INBD MSIV 1821-F022C green indicating light (P601-18C) is on.

$ 22.b. DMM-1 indicates relay 1C71A-R3C Caet.d c.had, -

i l

B '

i $ 22.c. DMM-2 indicates relay 1C71A-K3R caA6 thW.

S Denotes Technical specification requirement. l

, - - . _ _ _ . , , _ _ . . - . , , . _ _ . _ _ _ . , , ,__,,,,.._,.,y_...,,_,,,,,,_...,,,,_,,_...,_--,_.m., ,,.,,,,..,_,.,_,_,__,,-y__.--.,,,,,._,ri

.' i 1

TEMPCH NGE o

( dGE OF d  ;

Attachment 2 (Cont.) 7(gpg gggg OM7A: SVI-C71-70039  ;

Sheet 3 of 6 , Page: 17  ;

PAGE OFM l SECTION 5 1 Initials i Y ZZ.d D CJLTE b

/0 23.e. MSL C INBD HSIV 1521-7022'c green indicating '

light (P601-18C) is off.

l Tc g 23.b. DMM-1 indicates relay 1C71A-K3C esNToct optA.

l 23.c. DMM-2 indicates relay 1C71A-K3M h % th opth.

N bdctsp

,g z.3.R 24.a. MSL C CTBD MSIV 1321-F028C green indicating l light (P601-19C) is on.

l TC 24.b. DMM-1 indicates relay 1C71A-K3C Cekd clW4L. I 8

$ 24.c. DMM-2 indicates relay 1C71A-K3M cors%d c.ksti.  ;

• .,,24.4 hL{CfEp

( /d 25.a. MSL C OTBD MSIV 1B21-T028C green indicating light (P601-19C) is off. j K i g 25.b. DMM-1 indicates relay 1C71A-K3C ce % c4 apt.n.

25.c. DMM-2 indicates relay 1C71A-K3H cahu op. <

"f C jg M.d DC (L'TQ

% 26. MSL C INBD MSIV 1B21-F022C switch (P601-18C) '

8 Placed to AUTC. '(Mode larl) l

27. MSL C OTBD MSIV 1821-F020C switch l placed (P601-19C) to AUTC. (Mode larl )

28. MSL C INBD MSIV 1521-7022C switch (P601-18C) placed to CIASE. (Mode 3,4, or 5)

29. MSL C CTBD MSIV 1521-F028C switch gc, placed (P601-19C) to CICSE. (Mode 3,4, or 5) lb '

p ilLTE,k s<.

$ Denotes Technical' specification requirement.

I

?

TD.iP CH UGE A i PAGE OF M Attache,ent 2 (Cont.) TLMPC ANGE OM7At SVI-C71-T0039  ;

Sheet 4 of 6 # Paget 18 i Rev.I 1 {

PAGE Or M_

SECTION 5.1 Initials. l

)

34. MSL B INBD MSIV 1521-F022B switch (P601-18C)  !

placed to TEST. ,

l

35. MSL B OTBD MSIV 1821-FC285 switch (P601-19C) placed to TEST. l 36.a. MSL B INBD MSIV 1B21-F0225 green indicating I light (P601-18C) is on. ,

S 36.b. DMM-1 indicates relay 1C71A-K3G CzA4c.c4 do%1.

8 36.c. DMM-2 indicates relay 1C71A-DF OfAthth c1Mi "fC jp JG S D ClzTip 37.a. MSL B INBD MSIV 1521-F0225 green indicating light (P601-18C) is off.

Y 37.b. DMM-1 indicates relay 1C71A-K3G corWe.ch opta.

L 8 37.c. DMM-2 indicates relay 1C71A-K3F CvAktf opt.A.

N p e ittu jo n.J ,

38.a. MSL B CTBD MSIV 1321-F028B green indicating light (P601-19C) is on.

$ 38.b. DMM-1 indicates relay 1C71A-D G coh%c4 cica ed. a B 38.c. DMM-2 indicates relay IC71A-DF co M A t4 C M ed.

N 10 0 NElitL}

~

jp 39.a. MSL B CTBD MSIV 1821-F0288 green indicating light (P601-1pC) is off.

"TC 39.b. DMM-1 indicates relay 1c71A-UG coh%d spem 8 39.c. DMM-2 indicates relay 1c71A-DF ashhd opeA _  ;

I "IC

/0 J'I A D McTtp l 1 40. MSL B INBD MSIV 1521*F022B switch (7601-18C) 8 placed to AUTO. (Mode 1.c a >

$ Denotes Technical' specification requirement.

.,y

,y. - , . - _ - - - - - - - - _ , . - - - - - ,, , . . , _ ,- , , , , , , , _ . , . . ,w-.,----..-..~,,,,.rr-,._-e. ..mw.-,wI

TEMP AhGE R.-lSe OF }_]_

Attachment 2 (Cont.) TEMPC ANGE CM7A: SVI-C71-T0039 Sheet 5 of 6 y Page 19 PAGE _ 0Fg Rev. 1 SECTION 5.1 Initials l

41. MSL B OTBD MSIV 3B21-T0285 switch I O placed (P601-19C) .to AUTO. (Mode 1 or'1 )

42. MSL B INBD MSIV 1321-T022B switch (P601-18C) placed to CLosE. (Mode 3,4, or 5) .

43. MSL B OTBD MSIV 1821-T0288 switch placed (P601-19C) to CI4SE. (Mode 3,.4, or 5) _

46. MSL D INBD M1 '*21-T022D switch (P601-18C) placed to TEC

47. MSL D OTBD MSI\ '21-T028D swi.tch (P601-19C) placed to TEST.

48.a. MSL D INBD MSIV 1821-T022D green indicating i light (P601-18C) is on.

7C $ 4 8.b DMM-1 indicates relay 1C71A-K3E cath tA t.kMd.

(

g 48.c. DMM-2 indicates relay 1C71A-r3D C.oN*tc.d cicAtII.

Y 64 g f L (C-TLD 49.a. MSL D INBr MIIV 1321-T022D green indicating light (P601-18C) is off.

49.b. DMM-1 indicates relay 1C71A-K3E cv.Act o;mn.

8 49.c. DMM-2 indica.es relay 1C71A-X3D hb d opqA.

Y jf $W O E (LTi.)

50.a. MSL D OTBD MSIV 1821-T028D green indicating light (P601-19C) is on.

Tf- $ 50.b. DMM-1 indicates relay 1C71A-K3E cuerati ciud41, 8

$ 50.c. DMM-2 indicates relay 1C71A-K3D CLAWi C3&W.li N SO A b 5-IK'tLD jg .

51.a. MSL D OTBD MSIV 1B21-F028D green indicating light (P601-19C) is off.

5 Denotes Technical Specification requiremant.

i

~

TCMf COANGI PACE R Attach:tont 2 (Cont.) '

IEMPC ANGE CM7A: SVI-C71-T0039 Sheet 6 of 6 Page: 20 lPAGE . Ord SECTION 5.1 Initials 51.b. Oh 1 indicates relay 1C71A-X32 Ot.ft%6 0Fi 51.c. DMM-2 incicates relay 1C7'1A-K3D C h Yc.tX n P4A l0 , St. A h E(4 YLp TC 52.

' MSL D INBD MSIV IB21-F022D switch (P601-18C) g placed to AUTO. (Mode larh )

.g 53. MSL 1 CTBD MSIV 1B21-TC28D switch placed (P601-19C) te AUTC. (Mode lar ."lL )

54. MSL .*> INBD MSIV 1321 FC22D switch (P601 18C) placed to c'oSE. (Mods 3,4, or 5)

55. MSL D OTBD MSIV 132'l-T028D switch pla ad (P601-itC) ts CicSE. (Mode 3,4, or 5)

L0 bLfcti)

J7

(

503 P.N,6 5 irformed that stroking #

8 e.eus#N.w ec=r.ct.c. /

Time Date LL.3 7 !qu4 L' L SECTION 4.0 TIST INSTRUMINTS:

MPL NUMBER CAL. DATE CAL DUE DATE INI DIJITAL MULTIMETER -

DIGITAL MULTIMITER .

COMMENTS:

Performed bys,_ _ ,_ / /

.. .. ... / /

Independant Verifies " / / -

~ ~ ;, J s . . - Ziiiiials Date

$ Denotes Technical c, .; -. e guirement.

t

.e-i l

i 1

I .. 1 Attachment 3 idOPC ANGL OM7At SVI.C71-T0039  :

Sheet 1 of 1 # Pege: 21  !

IPAGE Rev. : 1 i or- .a.l.b. i SYSTEM RISTORATION CHICKLIST  ;

l

Title:

Main steam Line Isolation Valve closure l Channel Functional  !

verified By:  ;

l Signature /Initinis Date  !

+ ....__..___..............__.........- __.....___......___....+ INITIALS l

l l COMPONINT lRIQUIRID l l l l l LOCATION l MPL OR NAMI POSITICN FIRST SECONDI RIMARKS l {

l l VERIF VIRIF l l .

.g. i.__.....__ ____............+ ... ___.+..... +......+_. ______l l lContro. Ral MSL A INBD MSIV l l l l 6 l P601-18C l1B21-F022A switchl

_____..+..__....__....__.+..__.....+ __. _+_.....+__..__

l l

..I l

l_. l

• l l Control Rml MSL B INAD MSIV l l l l l P601 .....+... l1321.F0225 switchl l l l g.____-18C ____________.+......____+....._+ .....+.___...._; j IControl Raj MSL C INBD MSIV l

• l l l l

( l P601-18C l1321-F022C switchl l..........+.__..__.....____.+.........+______+..____

l l l l

• l l Control Rml MSL D INBD MSIV l l -

l l l i

l P601-18C l1521-F022D switchl l l l l l

j_... _____+ .....___.... ...+.__ .....+__..._+....__+........_l Control Ral MSL A OTBD MSIV l l l  !

l P601-19C l1321-F028A switchl l l l l______ ...+..__.. ___ ..____+.....____+_.....+......+___......;

• l l Control Ral MSL 3 OTBD MSIV l l l l l l l P601 19C l1321-F028B switchl l l l l );

___.......+.__.....____.....+_........+ ...__+__....+..___....l Control Rml MSL C OTBD MSIV l l l l l P601 19C l1321 7028C switchl l l l l

..___.....+____..........___+.__......+ .... +.__.. +....... _l I j. Control Ra MSL B OTBD MSIV

• l l l P501-19C 1321-F0295 switch ] l l

....__....+_................+_........+._____+ __. .+..______ y l Control Ral DMM l removed l l l l P691 l l l l l 1

.__..... ____+.....__..+.___..+......,___.___..

l......__..+...

l Cont o2. Ral EL. l removed l

• l l l P692 l 1 l l l l....... ___+..___ ..... _____+ ________+ .....+.___..+ ._____..

l Control Ral DMM l removed l l l l 7693 l l l l

_+. _..._..l l

l..........+___..............+_....__..+......+....

l Control Raj DMM l removed l l l l l l l,____.............__..........__.-_-____......

P694 l l l l

__.....___ .__...+

yn h bD N el "*

-- - - -.--- -.-._n. ,,,,e . . , , - - - . , , , , ,,.,-_-.n.,..v.,,,,m__e ,wn,...m_m-m,m--.,_,-,

Attachment 4 OM7A: SVI-C71-T0039 I Sheet 1 of 1 Page 22-Last Rev.: 1 RELAY DRAWING l POTTER & BRUMFIELD f MDR RELAY j i

i

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DATA PACKAGE COVER SHEET "5*'72* *-

c w m. uss erv 1eru re.neut, SV[-Cy/-1*0039 .

TEST PERF'ORMANCE -

AUTHGt!ZAT :N 70 sTM7 PRDtW13ITts: ww #'l y J fpyj g' ' st= *2r a rt A m 11,<

AUTHCFI:Af!:N 70 sTMT T137: O 11 Mb SPDMsDC (FDATGt CAtt #c TDC INsiMil:N CDeLITICN ruu. O raarm.- s i t.c., t. .rt tim it:H. sPC. AC !*fANCI CFt:TDIA AC t?tA=I O taac: rrear = ZOs %'%f,t';',%';- ,

- C M CATA CRITD IA AO:I?fA8LI LNAC:!PTAOLI = then both As Lart and As fas4 sta are tsee.

ac sstarse vill be cases an As Lef t cata tr.!y.

TA.4 C"'e.!*:0N CRC:7" * " *

• 2 " * * " 2' "

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TEST RESULTS REVIEW '

CD*4.<ts I

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sysit.w t : :wtmistsP ss:tLI st:::cs mes:re

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TEhfP CHA.%GE fL i _ PACE,f) ork Attachment 1 TLMPC ANGE QM7A: SVI-C71-T0039 Sheat 1 of 1 # Page 14 FACE OF~eM Rev.* 1 Main Steam Line Isolation Valve Clowure Channel Functional ,,,

Prerequisite Sign-off Sheet Initials "IT.

4.0.2. This instruction may be partnrzad in operational 8 Condition 1,L L M or S.

4.0.3. No testing or maintenance is being performed which would initiate a half scram RPS, signal.

4.0.4. The following annunciators are reset:

a.1/2 SCRAM A/C (P680-5A-A9) <

i b.1/2 SCRAM B/D (P680-5A-39) g) ,,

TC. 4.0.5. DurTf D *

/0 ,

4.0.6. If unit is in MODE 3, 4, or 5:

( a. C95 co=puter point RPS CHANNIL ISCLATION A STAWS, 321EC013 indicates NORM. V

,p

'/

b. C95 cc:puter point, R.PS CHANNEL ISCI.ATION B STAWS, 321EC014 indicates NCE.

I-

c. C95 cc:puter point, RPS CHANNIL IS0IATION C STAWS, 321EC015 indicates NORM. I

d. C95 corputer point, RPS CHANNEL ISCLATION D f l STAWS, 321EC016 indicates NOM. "

l 4.0.7 R6 M9 h MAA*

• C%S $

4.0.8. Calibration Due Data is current on all / ._V U U

test equipment.

i

..,3 C/

"iC.

g - DYE. N C.BE.B M V N-Performed by: c... / /-

- </

W i _- A ;-

' 'J e Signature Initials Date t

-,-v~ .- r,- --e. ,e,, - , - - - - ,e, - , - . , ,- --, ~ , - , - - , _ , , , , , ,

TC 1 I OH74; gy,,g,I y *"

t 8 II5PCyAngg F

notsaz; !% l P 1

2?, ,7lll(cono initfg3 4.0.104. Svitch IC71 A-36A MAIN STEAM LINE ISOL YALYE TEST is in the NORM position.

4.0.103. Svitch IC71 A-36B MAIN STEAM LINE ISOL YALYE TEST is in the ERM /

sk position. .

4.0.10.c. Svitch IC71 A-36C MAIN STIAM LINE ISOL YALVE TEST is in the NORM i

position. -

4.0.10.d. Svit:h 1C71 A-S60 MAIN STEAM LINE ISOL YALYE TEST is in the NORM '

position.

v .

l 1

L f

t t - '- t ' -- - - - - --e- -----

+---v' -- Pw* - - - - P -- *- --* -- w--- v + - - - - - - -

t--

l TEMV CnMict t ,

PAGE E I

TEMP ~iRGL .

t- \

0 noe or E_.

l Attac.bant 2 9ghp gg CM7As SVI-C71-T0038 i

, Sheet 1 of 6 , Paget 13 i PACE Of j

~ '

- Main steen Line foolation  ;

Valve Clesure Channel Functiema_1 '

Data Sheet i.ICTION 5.1 ID.itials <

it .

Tc- l 8 9  ;

(

i l

[

I i

7. hc- infor=ed that the MSIV's )

l Unh @treket..

vil es Jero / a > -3? * ~ 1 6

/- "A Tlas case I . f d . % *b'. W w e4. / f

8. . MSL A IX3D MSW 1121-7022A switch (7601-18c) l b placed to TIS *

/ i

9. MSL A CT3D MSW 1321-F028A svit:h (7601-15c) ,

plaeed to TIS':. .

s l 10.a. MSL A ZX3D fts31321-F022A green indicating light (7601-1sc) is on. u 0  :

• ic 10.b. DNM-1 indicates relay 1C73-mA sedut ek:ns1. ww ,

N  ;

8 10.c. DMM-2 indicates relay ac7n-23 cau car.ui.h -

i jf 10. 5 ' b E \ LTL.b 11.a. MSL A INBD MSIV 1321-F0221 green indicating light (7601-18C) is off. OT ,,

7 M l g 11.b. EDet-1 indicates relay ac71A-mA t.a*.et op q . -

li.e. DMM-2 indicates relay 1C71A-23 anAd ep.s. t 8 Denotes Technical specification requirement.  :

4 I

TEMP CH ANGE

(

tP L AGE

-- d Attach::ent 2 (Cont.) ,

CM7At svI-C71-T0039 Sheet 2 of 4 ygygg[gggg

, Page 16 "Y 1 PAGE M. Of M SECTICN 5.1 Initials jp IIA bl.in m . _

12.a. MSL A CTBD MSIV 1321-T028A green indicating ,

light (P601-19C) is on. G ~

7C- $ 12.b. DMM-1 indicates relay 1C71A-DA cae.c4 c.1chuA n

e$ 12.c. DMM-2 indicates relay 1C71A-U3 Cs4.M c.bg.l.

, jf it D D i.[A.Tt' D 13.a. MSL A CT33 MSIV 1521-7028A green indicating light (P601-19C) is off. _ /

0 13.b. D!O'.-1 indicates relay 1C71A-DA coh8es tA opc.%. N 13.c. DMM-2 indicates relay 1C71A-D3 ccedc.tt optNQj

-fc

( jf 13 A DE-la LD 7c 14. MSL A IN3D MSIV 1321-TC22A switch (P601-18C) '

h placed to AUTC. (Mode 1 or 2 ) t ,

15. MSL A CTBD MSIV 1321-7028A svitch ,

placed (P601-19C) to AUTC. (Mode 1er".1. ) %_o w/

16. MSL A IN3D MS*v 1321-T022A svitch (P601-18C) J.

placed to CLcsE. (Mode 3,4, or 5) F /N

17. MSL A CT3D MSIV 1321-T028A switch  !.

placed (P601-19C) to CICSE. (Mode 3,4, or 5) /'/ 9

20. MSL C IN3D MSIV 1321-7022C svitch (P601-18C) placed to TIST.

1 Ng ).&

21. MSL C CTED MSIV 1321-T028C switch (7801-19c) /-

11 aced to TIST. , i) 22.a. MSL C INED MSIV 1321-7022C green indicating C light (P401-18C) is on. tN' 5 22.b. DMM-1 indicates relay 1C71A-K3C Cahd c.k+.ad.

' $ 22.c. D.d-2 indicates relay 1C71A-DE ca e.6 C h uJ.

c___ . ~

$ Denotes Technical specification require.ent.

.- _ _ _ _ _ __ _ _ _ _ - . - _ _ _ . . ~ . _ . _ _ _ . _ _ _ . _ . . _ . _ __ __ _ _ _ _ _ _ _

TE!.iP CH tlGE l OF d

(

Attach =ent 2 (Cont.) IEMPC WE CM7A: SVI-C71-70039 Sheet 3 of 6 , Pages 17

• • Y 1 PACC_ 0FM.

SECTICN 5.1 Initials Y 22.A .D C Ir.7E b 23.a. MSL C IN3D MSIV 1321-7022'c green indicating ,

light (P601-18C) is off. .

Tc '

g 23.b. DM-1 indicates relay IC71A-DC esNTscr efRA. y  !

2J.c. DE-2 indicates relay 1C71A-UR Ca8%L4 6pt.N.

n .R. b cic. tsp

,g ,

l ,

24.a. MSL C CTBD MSIV 1321-T028C green indicating ' l light (P601-19C) is on. b I~ ~ I TC $ 24.b. DE-1 indicates relay IC71A-DC Ca8%d cicM.t.L. x x

6

-W' s 24.c. re-2 indicates relay IC71A-Ma emme ch'er.l.

~l M.4 DL.(r4L.)

{ /d 25.a. MSL C CTED MSIV 1321-7028C green indicating a

')

light (P601-19C) is off. __ A .

V. ,

25.h. CW-1 indicates relay 1C71A-DC ccmt.et op. -

b "

l 6

25.c. C5-2 indicates relay 1C71A-K3H c.aA%C4 op. Qs jf Md DClLT Q ,

TC. 26. MSL C IN30 MSIV 1321-F022C switch (7601-18C) placed to AUTC. (Mode lar'A )

C')

g

27. MSL C CT3D MSIV 1321-F028C switch ,

l Placed (P601-19C) to AUTC. (Mode Isr2. ) ,

l

28. MSL C IN3D MSIV 1321-7022C switch (P601-18C)

/-)-[i placed to CI4SI. (Mode 3,4, or 5)

29. MSL C CTED MSIV 1321-F028C switch placed (P601-19C) to CICFI. (Mode 3,4, or 5) f-I',r ff fc l0 '*- p u t. n ? ,

$t.

5 Denotes Technical' specification requirement.

9 TEMP CH "JGE 9

PAGE OF./.2

( SVI-C71-T003P Attach =ent 2 (Cont.) TLMPC NGE CM7A Sheet 4 of 6 p Page: 18 fAGE Cr$j Rev.: 1 SECTION 5.1 Initials i '

34. MSL 3 INBD MSIV 1321-T0223 switch (P601-18C) f placed to TIST. ,

b,

35. MSL 3 CTED MSIV 1321-70283 switch (P601-19C) placred to TIST.

36.a. MSL 3 INED MSIV 1321-T0223 green indicating , ,

light (P601-18C) is on. ,

$ 3 6.b. DMM-1 indicates relay 1C71A-DG Ca h c\ d o4 d .

$ 36.c. DW.-2 indicates relay 1C71A-K3T 04Nrad clu%scJ. G '

sc jo JG A 9CicTtp

37. a . MS L 3 INED MSIV 1321-70223 green indicating light (P601-18C) is off. .

4' Y 37.b. DMM-1 indicates relay IC73k-K3G corftad opt.N. Dx 8

( 37.c. CMM-2 indicates relay IC71A-DT C.n W tf CptA. '

-fG jf J7.d p L it.YG ,

38.a. MSL 3 C73D MS!V 1321.T0283 green ir.dicating light (P601-19C) is on. ..

$ 38.h. DMM-1 indicates relay 1C71A-K3G cch* lea ciched'.7%

$ 38.c. DW.-2 indicates relay 1C21A-DT con %e4 cmed. l jy A0 NE ldQ 1

39.a. MSL 3 CT3D MSIV 1321-70283 green indicating light (P601-19C) is off. C~ -

l "TC 39.b.13MM-1 ind!, cates relay 1C71A-K3G CJ.h%d spw . q= .

7 8 39.c. DMM-2 indicates relay 1C71A-K3T c.shhct apan.

TC-l0 .

39 0 W'N 1 40. MSL 3 IN3D MSIV 1321*T0223 switch (7601-18C) /

6 placee to Acto. (Mod. 1.r a )  %

$ Denotes Technical' specification requirement.

. . i

~

TE cg

( $ 8c 0F /_7, Attach =ent 2 (Cent.) TEMP C ANGg CM7A SVI-C71-T0039 j Sheet 5 of 6 , Page: 19'  ;

PAGE OFg Rev.: 1 SECTION 5.1 nitiais l TC '

41. MSL 3 CTED MSIV 1321-F0283 svitch ,

O placed (P601-19C).to AUTC. (Mode 1 or'1 )

42. MSL 3 IN3D MSIV 1321-70223 switch (7601-18C) \ j placed to CMSE. (Mode 3,4, or 5) .h j

43. MSL 3 OT3D MS V 1321-70283 switch / \ i placed (P601-19C) to CIASI. (Mede 3,,4, or 5) <N l n l

i

46. MSL D IN3D MSIV 1321-T022D switch (P601-18C) I placed to TIST. ~ )  !

47. MSL D CTED MS:V 1321-7028D svitch (P601-19C) ,

placed to TIST. Lv v 48.a. MSL D TN3D MS:V 1321-T022D green indicating / )

light (P601-18C) is on. -

l 1 $ 48.b. DMM-1 indicates relay 1C7M-K3I ca&d c.htd _ e_

$ 4 8.c. DMM-2 indicates relay 1C7u-K3D caer.d cW.tziu

+

Jg 94 A L. (LTE.D ,

49.a. MSL D INED M5:V 1321-TC22D green indicating ) )

light (P601-18C) is off. __M -

% 49.b. DMM-1 indicates relay 1C73-K3E cv.atic.ct eMA. \[I 49.c. DMM-2 indicates relay 1C7M-K3D Ccht apt.i._ j

+ $.0 jQ 0&ICTL) 50.a. MSL D OT3D MSIV 1321-7028D green indicating j light (P601-19C) is on. u . 3 Tf- ; 50.b. DMM-1 indicaten relay 1C7D.*K3r cuers.ti c.Wdel. ,. ,

8 30.c. DKM-2 indicates relay 1C7u-K3D Crataxt Cknecti -

~

4 l

4C. '

50 0

\

y b i lK'TL.>

51.a. MSL D DTED MSIV 1321-7028D green indicating / ,

light (P601-19C) is off. .

5 Denotes Technical specification requirement.

1

_ - _ . , , _ , , , _ . . . _ _ _ _ _ - . . _ _ . _ , , - . , , - , , _ _ - _ . . . .-_m ~_-,,,.._.._--,w_,-_- ,, ..__.--

e s .

l TEMP CHANGC

. PACE .]_].

Attachment 2 (Cont.) CM7A: m - M -T0039 l Jheat 6 of 6 -

gggphgggg

,_ Page: 20 l

~

n:t.20er2L SECTICN 5.1

• Initl*18 51.b. DMM-1 indicates relay 1C71A-K3E CattM AP ,

51.c. DMM-2 indicates relay acilA-K3D cmc.CY *Pt^

e JO St.d O El4 'ftp 9 TC 52. MSL D IN3D MSIV 1321-7022D svitch (P.601-18C. / .

placed to AUTO. (Mode 14r1 )

. g

53. MSL D CT3D MS!v 1321-7028D svitch '/ l Placed (P601-19C) to AUTO. (Mode lara. ) -

54. MSL D INED MSIV 1321-T022D switch (P601-18C) placed to CLCSE. (Mode 3,4, or 5) F Af

55. ESL D CTED MSIV 132'l-7028D switch placed (P601-19C) to CLCSI. (Mede 3,4, or 5) g, L l0 bzkte 17 1 I

• TL

60. unu $@'.ht.r infor=ed that streking _

t. plated. J J /w- 3' i

.J. 7 qN ed u a TIST INSTRL* MIN S:

MPL NUM3ER CAL. DATI CAL DUI DATE

. nzaIm McLTIxim wo-!Jos2F ivM :E , a mIoIm xetTIx m l 7e P MA , -/h . ,-!M .N l

) v -

ccMMINTS:fNJ Performed by w

,'u-

< // N Ub u ( ~ i_ l

^

Independant verifies 4/OWI - i / - ' - - - - -

' signature Initials Date

$ Danctas Technical Specification requirezant.

---w- - -- <~ _ + , , - - , - - - - - - , - - , - --,,v,-w ,,,-- --w,e-rus- --,-,,-+-,,----*---,----,-e r--e- = w , -w ee e

r O

(.

Attachment 3 f tMP C ANGr. oM7A: sVI.C71_T0039 Sheet 1 of 1 # Paga: 21 PA0! 1

=.M.Rev.I 0F SYSTIM RISTORATION CNICXI.IST

Title:

Main Steam Line Isolation valve~~ closure B annel tunctional Verified By: * <

- 1/'74"I

%rM a Signature / Initials

'/ t 9 - s-n Date

+ ....... __.......___..____.....__....._____"... _______....

- I ecxPcNINT LRIQUIRED l INITIAI.S l l LCCATICN l MPL CR NA.E PCSITICN l TIRSTlSICCNDl RIMARKS l l l VIRITIVIRIT l l g ....._____.....____.........+_.____...+ .... .....%.........l '#

l Centrol Psl MSL A IN3D MS*V l

• l l N l b P601-18C l1321-T022A switchl l

....c - __ + g...__l p l

.__.._...____...........__+_____..%

l Control P l MSL 3 INED MSIV l

• l l l l P601-18C l1321-70223 switch] l ' 1, l l...______...........______+_......._e.._

l l Control Rsl MSL C IN3D MSIV l *

{ l l P601

t. l... __-18C

_.. ,_________ l1321-7022C

...... switchl .. ___...+____. a ,__.. ..__...._l l

lC ntrcl Psl MSL D IN3D MSIV l

• 1 P601-18C l1321-7022D switchl l

l f

Ml . . - .... l l

l l

.__.....__+.______.......__.+-__.....%. ....

.__..l

Centrol P=l MSL A CTBD ESIV l P601-19C l1321-7028A svitchl l

l 31---g l

l l

l ,

......___........___.......+......_+.....::pw. _ w _........l )

Centrol R=l MSL 3 CT3D ES!V l

• 1 l

......_...+......_........__+.__......+.h___.+,

P601-19C l1321-70283 svitchl . . . . . ......

l Centrol R=l MSL C CISD MSIV l

• l l P601-19C l1321-7028C. switch l l l l.......... ..... ____......_ . ..__ +. h.. . _~.____..  !

Control Rml MSL B CTSD MSIV l

• l l 3 P601-19C l1321-T0283 switch

..........+....... ........ l........__+.. h... l g, ...

__g ___ ..;

l Control Rml DMX l removed l l [ r-l l 7691 l_______..

l l

kl<

__+. . e _,... __ h. 0.__..i l MC l l

l Control Ral DMX l removed l

(

l l l l P692 l l l o l l__........

l Control Raj DMM

___...........__ ........ . _ . w-/ - ;_ , ....l i removed l l i; F693 l l l

..........+.......___...._+..______.....e_' _

..........l control Ral DMM l removed l Q , I I H P694 l l I 3 ._____................__ .____ ..._ ...__..... ___...d...i.____.I 8 *FM &mM N 5+ % 4** ~ l

_ , . _---.-_g - . - . , . _ , ._.7,.,_,,_,,_g . . . . _ _ _ . __~,,._.nm,,_,,_,,,,.y , , _ , , , . , _ . , , , , , - .

/

O W t

i

-. . - . .....-...-.e. -

. ./ - . (N.. - . . . .. -U. ., . .- . . . . . . . _ - - .. .

M 4 . 4= e W Gem W 4 h

, -e e **

_-_L.oD.'

of pnir /w .r fm /o/5 e./r , _

- ._ NY ll 7 -- - . -

1. .d.. uaarw

g. .Oe e S *e scgur.u.s .

k.mr/Hk n 9 _ . - -... .. . .

e .B.* N *M e ga p . m'a g. e NeP ***- *e 3- hm

. me e 9 -e.==. - e. e'.e.& 6 < we p hw - - - m mm ,

ee e@* ee ,ee w- . .-g. -gw g.umm ____ , m ,

• - . + =.e .pe w .. -e = ep- eOg m > . e e ..w. ..e6 .

64 gON.= M-e

__. '1* 6.'M e% W . .N. Mhh

. .He

.we

• • *"" ~ **

_*s . . -~ .,.

.,A i

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^

e', ^*7a . .~ l *=e',I 1

- -  :- ;s --

-. _ l

. . . - I

\

4 s .W'. 1 *

.. ' es.s

. **. So.

6- 4.m. .@,y. e.e.pmy .g -d; n- . J, " 4

-- ,, .+ . , i . <

0

.*M,.e- .x_ -~Kp- . ..

.m = <

_ .....:. . i z : : h..: -

1 f . 4.P.~ . . . . . . . .

3 t '. ~_&. . ,,

% -- s

, . , n:

e . \* g *

.e

• y . -.== 4 *F .y . ,-m j w -

1 4 9 et. l

"=il {, 'j,)

. e.e= w -___

e 1

1 i

o 9

KS:V-Ohreneler_r of Events

l. .

October 29, 198-

'c.

1325 - 5 r:Ked 155: MS:V 1521-T;;22; for S7I-32 -025A Se:tien 5.2, per I?.:S va;ve ci: net :10:e for *E se::n:1. Leve;

• Test Ex:e;::en Aepert written (STA Leg) 1642 - Re-opened 1521-F0022D (Plant Leg) 190: - Ce:;ared 1521-F 022D Inop, elesing time was 22.5 seccids ft:n ST: data (Plant Leg) (LCO written, 87-2031) 2103 - F.e-stroked 1821-T0022D - tire to close 3.2 seconds (Plant Log) 2106 - Stroke: 122*-F 22D agair. - time te close 2.9 se: nds (Plat.: L:g 7

2'- - 5:r: :e: il2'-F 02:: - ti.e :: :~.cse 77 se::r.cz (Flar.t Leg' 2'52 - 22;. stecke: a;; MS:"s (Ur.;: Leg)  ;

222 - : e . ::r. ( h.i.: :een nade ty F. ant Managenent :: ::r:xt a *. '.

MS:V's to ene:k for conn:n mode failure. Found 1521-F002SE ha:

a . ir.itia; s;:. ste:kt t:ne of 11.9 se: nds, se::nd str:ke was

~." s e::r.: !F;att Les; 2:2~ - 1E21-F0022' was re-stroked, valve closed in less than 2 se::nds.

Va;ve vt: ste:xed again ar.: stroke t0:e was less than 3 se::n::

(S! A Let' 1521-F:045; an: FOC2SE also experienced icng clesing

( tines (77 secenes tr.: 12 se: ends). When restroged valves r.a:

ti-t: :f a;; rex. se::ncs es:n. In all cases tne s:;er.::: lign :

en "..-/2-?i22 an 7523 de-energi:e: ( ST A- Log )

' ate: "D" Main !: ear. Line (STA Log.'

2236-2250. - Isolated "" <2L ! Unit Leg)  ;

II-; - !selate: "D" MS'. Il ar.: L:g' 231C - A1; MSIVs were verified to stroke within 3-5 seconds, could n:t bs repeat the initic; conditien causing MSIV to slow close. Strekir.g 4: the MSIV has freed up the Solenoid / Pneumatic valves, which centre; 20 MSIV stroking, of any forsign matter or noisture. In 5 to 7 days ,

~ MS V Isolation S: ram test is scheduled, if this is delayed we'll j fast stroke the MSIV's again to see if event is repeatable. De- '

^

clared 1B21-F00220, F0028D and F0029B operable. (Plant Leg) 2360 - Restored "D" MSL (Plant Log) j October 30, 1997 0010 - Made 4hr. report on slow closing MSIV's (Plant Log) l

• s bx 0300 - Test Exception Report (TER) 451-1 for MSIV closure was approved. '

[7]

All MSIV's restored. (STA Leg)

~ ,

(1) l l

0

f .

Ceteter 30, 1987 IS C3 0 - TEE '51-1 (MS:V Fas: Cicsure) was res: ved and c'cre:. N:.

restr;::icns :: geing ba:x to '.'0-7 (Flar.t Leg)

C355 - Increasirs power (Plant Log)

Nove.ter 2. 1o99 1942 - Commenced SVI C71-T0039, MSL Isol Valve Closure Channel fune:iona; (Uni: Leg) (1C% stroke - partial closure - RPS) 21'2 - Cen;;e:ec S"I C71-70039 - Sat k.r Neve-rea 3. 1 ?'

a 1"i-i - t:resse: ;;wer :: 55 :: ::r:xe MS:'.': ( Flar.: L:2

• 154 1222 - streke: MS:7s (Unit Leg) 1157 - 1321-F0223 t:0k 18 secones to close (Flant Log) .

• • !! - Ur.1: Sutervis:r de:.'.are: F;22: Ine; (Ur.;; Leg:

1159 - 1521-F022D restr:ked in 3.0 se:en:s (Plant Log) 123; - Unit Su;erviser declare: F022D operable (Unit Log)

(

1212 - 122' " 250 cid r.:: c1cse ir. the 2 ninute 49 se::r.:s tr.at tr.e c:r.*r:; switcr. was it. "c;:se". 7::< sw;;:n ta:4 :: "Aute",

tr.er. :: ":1:se", valve ang: ir. 3.4 se::nt: ( F; tt. Leg) 1212 - Ur.it S;;ervis:r ce:;are FC290 In:; (Ur.it Leg' 1230 - Oe:lared MSL "D" Incp based on re;eated failure of 122*-F022:

ar. F;2ED to ste:ge in requirec time. (see 10-29-37 20-24 sr.:ft entry) (Plant Leg) ( ALCO written, 87-2128) e N.

gj 1330 - Informed Syste: Operation Center of intended plant snutdown

• (Unit. Log) 1337 - Coceenced PWR decrease (Unit Log)

Concenced a normal Rx shutdow IPlant Log) 1353 - Clossd 1821-F022D 3.4 secondb (Jnit Log) 1354 - Closed 1821-r028D 3.3 seconds (Unit Log) 1355 - Shut 1821-F022D and r028D, out of T.S. 3.4.7 and 3.6.4 Made 4hr.

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E se.hed.Lled Test () Retest per tra () other

..:.:a c:x:::.cns Test Platen.:: [] W [] E () Inw Pvr [] Mid Pvr E Fl Pvr Test C:rstition: () W () E () 1 () 2 [] 3 () 4 () 5 [] 6 N 7 () 8 C re Pv; 75  % Plant me 885 others

• C re Tlev n i Rx Press 962 9819

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treal 3 : fT Ut. !)h:e;;f=s E N/Al[] Cther () Yes, E13 M;crt r"tted 0:. .e r A .r es:s 15a: ihrer::c .s E N/Af l 5 NO .e I: sed 3- = r'/ ci te st a .: Test Mreau t anc. rert.au ci arf trsat p6 ant, pecc./:. .st.evt , This test closed the f astest MSIV as determined from previous testing .* at approxir.ately 73: peser. The valve, 1821 T022D was slow to start (. closing ( time from solenoid Jeenergitation to valve movement indicated tv l it. i t switch) howeve r closing tirse (time from 9C: te 10: lir.i t switch

    .                    a:t.atice. extrapolated to 100:) was within specification. TER 451-01 wa s ger.e ra t ed t o add r es ? this. This TER was resolved befcre testing war se:.rtd. All otht: analysis was satis f actory.
                                                                                                                                                                                          /

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1 TanaA b PCE Meet. Lag No. s /W//!////////) Jaane '1Tc.s. Manager /Date: l l W  : Plant Ops Manager t/ ate no sreved, i l l l 7 5 N 4,S i l

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As a.s = : : : c::ar.p  ; To t.ar.sfer ter img per Sectims 8.1 and 8.2 frca TC-2 to tt-3. this change crevi:-asiv a: r:ved hv P:r via r:06 203-2-5 and 5.E. 647-280. A :e:.*: steps, sec.t.c=.s. or pa:agragns 2.0, 6.1, 6.1 neta 2, 6.3.1, 6.4.2, 6.5.1, 6.6.3, 6.8.2, 8.1.2.2.a, 8.1.39.4.a.: . 8.: i facter. 8 . 2. 2.1. b . 8 . 2. 2. 2. a . 8 . 2. 3.1. 8. 3. 2.1. e. 8 . 4. 2.1.b . At* w u -t 7 - Nc . 1. a N T' . Fer the abcve stsps chat.ge Test. Condition 2 to Test Coedition 3.

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( 8.3 Full Closure of the rastest MSTV at 70% Power I 8.3.1 Frecautions Applicable to All Sections

1. 3rviewed (5.1) b/ /

Ins t/Date

                                                                                                                                                  ?

8.3.2 Frerequisites ard Initial Corwiition

1. Frerequisites / , ,

f ' Q'::' ~'- -

                                                                                                    >                                             i

a. pl3 sample plan (6.6.1) -u m t/cate

                                                                                                                                              ~

Scra.. and isolatien aarpins // I l

b. ,[J. { I ', ' .'/;'- '

verified. (6.6.2) I:nt/cate i

c. Record (6.6.3):  :

l :5.- .. . i rastest Ms:v roue, t, .:t sec. . AP 10 *'# 90

• 9l M */C'** EYl b n N a ~Z Jr.!y), i

( 2. Initial C::.:iitic:.s Verule.: sy/;a:e i j i I i

a. Test Cerditier. 7, reacter pcwer

                                         >>si n.>.u                           M m .+, . ,c
                                                                              ~ Ira./ tete /:::e , ' I                                            i

b. Facirculatien syste= in Master f.'- . i ,

Ma.-.ut.1 Mode (6.7.2) // /2/h'i /.9 l m t/caten a

c. Evacuate Cent 21 - Ot (6.7.3)  !)mutaceam

                                                                                     /0/b' 43/                              i 8.3.3      Authorization to test

1. Test Conditien 7 and Test Plateau p are approved per f./ *

                                                                                                             /

ST:- p ~704 , nach Pcwer Plateau. /j ' " bd::. h t/cate Serial No. N 5/ _ 1

1 l OfflCIA!.!EST COPf l- o.:. . .

• ot 5: Sr.-521-015A Page: 3C i Pav.: 3 1

(

2. Test incitaie:! in TPCD  ! f I C/ ,-

zwou or Test not in TPCD, approved to test (arri QA notified) f)ll - ff* *$ !Y, Startup Test Program Director Date _ _\ /~T /b Urut Supervisor Date s T.me C: All centrols a.M iruilcaters used in this se ti:t. t.:t Ic: ate:! cn panel 1r.3-P501, ur.less specifir.'

                                ~

otherwise. 8.3.4 Reeerd the fellowing: P680 Alte r-ate 2nstru= eat Paramete: Data Inst./J.itt APF.". Core Powr 77  % i N 1N41-F418 Plant M4e '5-6 Mie [*I J ei: y . ( ICJ4-P409 Reactor Press # e. . psig i 1133-7413 Cere Tlev SE Mit/hr=.C %

                                                                                            *2     inches 1C34-PS:t                         10. Rx tevel                ,

44 (Circle Channel Used) [ b. /*/J %~ Iru tr.4:e NCE : Starting ard stepping of ERIS ard archiving cf D.IS data is at the discretion of the Test Director. 8.3.5 start EKIS recording at least 10 seccmds prior to the MsIV [-[f /5.9. /.'.:

                                                                                                                        -ote SerialNo.A:I                  l        -
                --. ---   n   ,   w  , , - - , - , , . - -
                                                                     --w- ,,--e-      -      -,    , . . - , - .      -y    .----r- , - - - ,                 - ,m -

c. .. : :

0FilCIAL TEST COPY CM !: ST:-a:1-C:!>. 1 ( Page: 31 Rev.: 3 I 8.3.6 Ma.~.s.11y close the fastest MSIV (ree rM in step 8.3.2-ic) by tur.ing its centrol svite.h to the 'C.c.st" positler.. O /0[7. $ ' i h t4mte 8.3.7 Nhen the tr:ctor pressure and power transient has stabilized,  ; step Dl3. Archive the ERIS data and record the informatien necessary fer data retrieval. A" />

• sspe no. HS I T.I / Li 10l3<- l P/T Wt/L4te I

8.3.8 Plant Resteratien l

1. C;e . the tripped MS:V by retuming its cr.tr:1 reitch to l the 'A*.C* position.

o r/~ ~6' , ff'( hy:4u

2. Pla..t c;eratier.s may c=.tinuo as directed by the Ur.it Sepe . .*i se r . j

                                                                                                                     / X' 0 /ek :!<

W:A:4:e 8.3.9 Level 1 A.alysis k 1. Times t' valve s:Te,ne. t g ,isandd S equal the time the MS:V pilot

                                                                                    ..ergi:ed and actuation of the IC) a..d 90' c1: sed limit svitches, respectively.

• Fre: t' t DJS data (IRIS siga.a;s 321r:*0(! thrc'.:gh EllI . .,, re:Ord values for t ,, t90' "~ E 10'

                             ,            St. i                                                                        .

t,= m sec. h0"I' "** ho = i. sec. c + a. r > Mmegatee /, a /,3

2. CaJculate the valve stroke time t,.

Ih0 h0) s" ggp ,, 3, , z 100 I t, = (72 fu see -is es see ) x 100 I ( 't i 4- wT U p us v *1 y t, = L J,1,,,_ sec. Serial No. '/ 5 '

O 'J U , .' O 0FFICIM. TEST COPY cr. 5: 5T:-10-C 29. Page: 32 ( Rev.: 3 NCP:T: Values for AP10 ""d ^#90 are im step 8.3.24. TO r i.' h : ht/te te

3. Verify the MITV stroke time (t ) is greater than or equal to 2.5 seconds and less than of equal to 5.0 seconds:

Acceptance Criteria 3.1.1.

                                                                                                                                                                               $s A     fo/A lr>

h t/Date

4. Calculate closure time t,e3 from the following:

• It90-t10 I (lees - u ;."'

t,,*, = (t,e -t,) . (AFg n - APyg)

                                          =

t,.:** (m. se: nrffsec) +( or (N see 4- 93 L) II Wsec)(100% - 4 !  % ,, E t yg= se:. , h t/te.a ( 5. e.e t:tal effective MsIV closure time equals tgg plus the max 4 - inst..:mentatica delay time (i.e., t + t I* d Calculate the tetal effective cler.tre *dme.g3* T ta! Ef fective C1csure Time = t,,3 + td Teta! Effective closure Time = ci e sec. + Jf__ sec. Total Effective closure Time = Liu,sec. NCTE: 2.e value for t dis from Step 8.3.2-1. To n i- < h ,

                                                                                                                                                                           . wt/ Data

6. Verify the total effective closure time, is not greater than 5.5 seconds. Acceptance criteria 3.1.1.

t,,3 + td is less than or equal to 5.5 sec. f ra 4rt./ 9. /t ,. /2 9 /g., h t/cate nb1N1

                                                                     .                                                 y - rs ,s . . ~ ,, , e serial No.            't! '

h_ U*' CFFiCl.sl.Eycopy] J cr'. 5 : sT:-a!.1-C29. Page: 33 ( kv. : 3 8.3.10 secure free Test

1. A;;reved t% 0l, / hl*de n Teat Daroctor Date

2. Approved / j I hL hl#A unas supervisor

                                                                     / lolv J'/ O 3'1?

oste Time 8.3.11 Level 2 Analysis

1. Verify the reaeter did net scra: er isolate Aring the MS:V closure: A::eptanee criteria 3.2.1.

                        ~

9.Il n / .. h s Inst / tate

2. Scra: Avcidance - Flow Biased Scra= l

a. Deter. .ine the Peak tra..sient value for s! i ntd thermal pcwer (STT). The Peak Trtr.sient STP is the va.lue at peint of closest appecach cf pl5 Beat T1ux channels CSin:19 or 20 to either af DJ3 cha.-r.els

(\ C71A0003 cr C71A0004, respectively.

16. ic 'l Peak Transient $77 =

                                                   ~ ~ ~

f..' (Y# Using: CSin01ME-(Circle) DST 7 = Peak Transient STP - Initial S ? 9a wa dm = _" ' . . f 4 - 7? . 2 %

                                        'i es:2 = M* W I         -
                                        .                                         . h. a r
                                                                          - Ins t/cate

b. Determine Arm Upscale simulated Thermal Power Trip set;cint. The setpoint is the value of ERIs channels C71A0003 or C71A0004 at the point of the Peak TransientSTF.g;,cygc) sespeint - + .5 a  %*'" M *h Inat/Date Serial No. 4 5'

l l 3 CPI 5: ST:-E11-025A L, .. ... .-. , i Page: 34 Rev.: 3

c. Ccep:ta the simulated thermal Power saryin to scram:

Margin to scram = setpcist - Peak Transient 3".7 Margin to scram = 91 929 % - 78. 2c 94 Margin to scrum = /Y 72 % */* M tru t/pau

d. verify the simulated thermal power (5 7) margin t scrar. fer each channel is greater than er epa *. t:

5.04. Acceptance criteria 3.2.2. ,e /.w /t 1 wt/vau

3. Scram Avcidance - React:r Pressure l

a. Calculate the transient reactor pressure sargin t:

scram. Initial Pressure = 9GM CO csig (ER:s C34EA028) Margin to scram = scram setpcint - Peak tra .sient pressut (EA:s signal C34IM;5 ( cr C34EA030 as grepriate) Margin to scram = 1064.7 psig - V8 M h " C9 ag , Margin tc Scran - [C .h' psi *'i //5 $~ 6 t/ tete

t. Verify the reactor pressure margin to scra: is rester thaa. or egal to 10 psi: Ac:eptance Criteria 2 2- y 4,,

   '                                                                                  h t/cate                     ;

4. Scram Avoidance - Neutrco Flux

a. Calculate the transient neutrcm flux margin to scra=: l

1) From the IRIS data, determine the peak transient f neutron fluz. Use highest of Dl3 signals C51EA003 thru C51IA010 and record the channel used.

Using A m .3  : reak riux = 8 9 8 % .

                                                                                      /.:/k/t1 h t/Date                l Serial No. 8/

1 l l l l l

t,.,...

s. . .u

                                                                               .                  c't 5: Sn -a!.1-02EA
                                          ^-
                                                                            .-                    Page: 35 g

Rev.: 3

2) Ccm;nte the margin to Scram as follows:

Margh to scram = setpcht - Peak riux Margin to scram = 118% - 8FCS 4 Margis to Scram = 53 '72 % N/Je h '_ Inst /Date

b. Verify the twutrer: Cux margin to scram is greater than or equa.1 to 7.5% Acceptance criteria 3.2.2.

                                                                                                              ///3:/E 7 Ina t/Date              -

5. F.ala stea: 1.ine Iselatic . Av idance

a. Cale.: late tMe transient irdividual MS:, now margin t.:

isolati=: Margin Iselaticnto , setpektIsolation ,,, hak rn Aatec Individ.:a1 fiew Ms:. F1w x 100%

                                                                                                                                  )

m':I: 'n.e hak Individ.:a1 PA Gev in the abeve l evt.atien is the = staan Scv chse:ved in I

               .                         all unisciate:1 stea= lines. .

k Marg b to , 337g , 3,s.~r ..c lbuhr x 100% l Is:1aden 6 33,g,,, l 3.85 x.10 - > < , 1 Margin t: Isolation = 3' Id4 4 1 k?.ere: Peak transient irdivid.:a1 FE riev'is de e::ined fren D.:5 signals C34r.A014, C34m:* 5, C34r.A016 and C34r.M17. 3.85 x 106 1he is one fourth of rated steam Dev, W 15.4 x 10 6 33,, p W -

                                                                                                           , *s /.,Ll.c '

Inst /Date

b. Verify the margin to isolation to greater than er equal to 10%: Acceptance criteria 3.2.2.

so/>' 87 Inst /Date C 35 ?%E6, ic/se/s 7 Level 2 Analysis veritaec sy/cate serial No. Y'6/

I

g. .. . .....

l 0FF!ClaiTEST COPY. m Si sT:-E21-02 D. ] Page: 35 ) U mav.: 3 . 8.3.12 verify that arnf nts printouts, other ecuputer er recorder i printouts, and any other plant data reqyired is avallatie fer I inclusion in the Test Results Package, M7n ic/30:f2 7 h t4=r e ,j l

                   *************************** De or SECTIm 8. 3 * * * * * * * * * " *" ** * """ " *                        !

I

                                                       <m m m e r nu.w G

5erial No. 4 51

U J , ..'..; a-- -" 1 l 4 e . ;.. .

                                                                                                                    ,. :*A /j bb                                                                                                                                                 CF. 5: sTI-821-025A Pager 59

( i Bev.: 3 N 2.- Attachment 6 M MIS sanele Plan r

• 4.!

ru tion ID Punction Description scan Interval (ase:) 8 l B21EA001 Rx Wide Range tavel C Rx Wide Range tavel A 8 l B21EA002 Rx Wide Range Level L 8  ; B21EA003 Rx Wide Range Isvel B 8 ( B:1EA004 RPS Isolation status Chamel A 5 B21E0013 l RPS Isolation status Channel B 5 B21E0014 I B:1E :15 PJs Istlatier, status channel C 5 ' PJS Isolatien Status channel D 5 E:1E ::f

                                            *E2;E:011                                              SK/ Initiation Status                                             4
                                            *B 1E0022                                              SK/ Initiation Status                                             4
                                            *E:1E00:3                                              SK/ Initiation Status                                             4
                                            *B21E00*4                                              SK/ Initiatim status                                              4
                                            *E 1E0025                                              SK/ Initiation Status                                             4
              .b                            *B21E00:6
                                            *B21E 0:1 SK! Initiation Status SK/ Initiation Status 4

4

                  /                         *E: E0028                                              SF/ Initiation Status                                             4 ft
                                            *E21E0029                                              SKl Initiation Status                                             4
                                            *E *E0030                                              SK! *nitiation Status                                             4

( *E21E0031

                                            *E 1E 03:

SRI :nitiation status SK! Initiation Status 4 4

                                            *E 1E0033                                              SF/ Ir.itiatien status                                            4           .
                                            *E 1E0034                                              SK/ ::.itiation status                                            4
                ,                           *E21E003!                                               SI' It.itiatien Status                                           4
                '.                          *E '.E:;1i                                              Src *r.itiation Status                                           4
                                            *E 1E 037                                               sr. :r.itiation Status                                           4 ST ;r.itiatien status                                            4
             .,.                            *E21E0032

• ft . *E 1E0039 57/ Ir.ftlation Status 4 l 9 521E 0C SK! P:sitim 10 l Eri Pesiti m 10 4-l- 521E0043 (

j,' . - B21E0044 Sri P:sition 10 321E0045 SRI Position 10

f. 10

         ,E.                                 321E0046                                               SRY Position 4.,                                B21E 047                                               sr/ Pesition                                                   10 321E0048                                               sr/ Position                                                   10 y

3. 521E0049 SK/ Poaititm 10 ,

U B21E0050 sr/ Position 10 i

            *i '                             B21E0051                                               sr/ Position                                                   10                             i 1
          * -l. -                             B21E0052                                              sR/ Position                                                   10 Si                                  321Ec053                                              SRV Positicm                                                    10
         . b',

d

         ..t.

y <

                                                                                                                                                                   ~5!) 45!

l l

                                    . - -..... ....    . 4 ,. ,. -                                                           ,
                                    ., ..s s . . .: : . o .: s s                                                                  ( o u. . . .w.. w tr. 5: ST:-B21-02D.

I Page 60 Bev.t 3 Attachment 6 (cr.t. ) i 1 ERIS Saaple Plan l Tunction ID Punction Description Scan Interval (mse ) B21E 054 Sr/ Position 10

    ,           B21E0055         SRV Position                                                                    ,

10 l 521E0056 SRV Position 10 1 821E0057 Eri Position 10 821E0058 Sr/ Position

• 10 E:' E 055

                   .             Sr.' Pesition                                                                               10 E21E006 0-       SP/ Pesition                                                                                10                           1

• E21E*06 9+ r DE MSN Selenoid Status (22A) 4 i 1

              *E 1E0070+<        DED MSN Position (22A)                                                                        4
              *E 1E :"1-INED MS:'.' Positien (22A)                                                                    4                          I
              *E:1E0072+-        D3D MSIV Solenoid Status (228)                                                                4 I
              *E01E0073+'        D3D MSN Position (223)                                                                        4
              *E 1E 074 '        DGD MSIV Position (223) .                                                                     4                          l
              *E21E0075+'        DC MSIV Solenoid Status (220)                                                                 4                          I
              *E21E0076+-        Dr MSIV Position (22C)                                                                        4                        ,
                                                                                                                                                          )
              *E21E0077+'        Da3 MSIV Positica (220)                                                                       4
              *E21E 076+ '       INED MS:V Solenoid Status (22D)                                                               4 k            '521E0079.         INED MSN Position (22D)                                                                       4
              *E 1E002:- -       DE MS V Positien (223)                                                                        4 i
              *E21E0021 -        CL'"3D MSIV Solenoid Status (28A)                                                             4                          l
              *E 1E0062+-        CLT MS:V Positien (2&A)                                                                       4                          1 I
              *E 1E 053+-        CU 2.0 MS:V Position (2EA)                                                                    4
              *E 1E0024--        CUT MSN Solenoid Status (285)                                                                 4                          i
              *E21E 0!! '        CLT MON Position (28E)                                                                        4                          l
              *E:1E0066 -        CL T MSIV Positien (28B)                                                                      4
              *E 1E00E7+'        O.T MS V Solenoid Status (280)                                                                4
              *E 1E0066+w'       DJIBD MS:V Position (280)                                                                     4
              *E21E089+-         CU:BD MS:V Position (28C)                                                                     4                          l
              *E21EC090+s        CU:BD MSIV Solenoid Status (28D)                                                              4
              *B21E0091+'        CU BD MSIV Position (28D)                                                                     4
              *E21E0092+'        DJ:BD MSIV Position (283)                                                                     4                          I
              *B33EA021+"        Peactor Core Flow                                                                             8                          l
              *B33EA028          Recite Pump Elbow Tap 14A DP                                                                  4
              *B33EA029          Recire Pump Elbow Tap 14C DF                                                                  4
              *B33EA030          Recire Pump Elbow Tap 24A DP                                                                  4
              *B33EA031          Recire Pump Elbow Tap 24C DP                                                                  4 B33EC003          Lm3 Set Gen C3 2A Status                                                                      5 B33EC004          LTNG Set Gen ca 23 status                                                                     5                          I
            . B33E0009          Lm3 Set Gen CB 5A status                                                                      4                          l B33E0010          LmG Set Gen Cs 5a status                                                                      4     ,

• pc+g

                                                                                                                                                    '/

75U 451 1

                                                       .. i ;i .:-."             ; y sqy
                                                                      . .. . . : . , , c , s I ,

U G O .' i G J. ( -- en Si m-a21-025A

                                                                                                    . Page; 61 Rev.: 3

(

                         ;                                                                            Attachment 6 (Cont.)
                         ~
                        .;                                                      IRIS Sa:=le Plan Function ID                     Function Description        Scan 2nterval (asec)
                                     *C34EA013+#        Tetal Reactor steam F1w                                                  8
                                     *C34EA014+-        Steam Line A Flw                                                         8
                                     *C34EA015+<        Stea: Line B F1w                                                         8
                                     *C34EA016v         Steam Line C F1w                                                         8
                                     *C34EA017 /        Stea: Line D F1w                                                         4
                                     *C34EA019          Feedwater Flw A                                                          B
                                     *C34EA0:0          Teedveter Fl w B                                                         8
                                     *C34EA024       'Rx Narrev Range Level A                                                    8
                                     *C34EA;2*-        Rx Narr w Range 14 vel B                                                  8
                                     *C34EA026         Rx Narrew Range Level C                                                   8
                                                     'Narrev unge Rx Dcce Pressure                                               8
                                     *C34EA028+'#

• C3 4 EA: 3 *- Widt unge Rx Decc Pressure 6 C34EA031 Wrbine steam F1w 8 C34EC00: OrF A Trip status 5 C34EC002 O TP B Trip status 5

                                     *C34EC003         FOT7 C Trip status                                                        5
                                     *C51EA003+ /      AFF?. A T1ux                                                              8
                                     *C51EA004+ '      AF??. B T1ux                                                              8
                                     *C51EA00 5- -     AF??. C Flux                                                              8 L                   aC51EA006. /      AFF? D T1ux                                                               8
                                     *C51EA007 '       AFF?. E Tlux                                                              8
                                     *C51EA00' -       AFF? T T1ux                                                               f
                                     *C51EA009+'       AFF?. G Tlux                                                              8
                                     *C51EA010+'       AFFr. H T1ux                                                              8
                                     *C51EA019.-       Heat T1ux A                                                               4
                                     *Ci1EA 20 '       Hea Flux B                                                                4
                               ,     *C71EC001         Channel Scran A Status                                                    2 t :. 7         *C71EC002         Channel Scram B stat..s                                                   2

' - *C71EC003 Channel Scram C Status 2 i~ *C71EC004 Channel Scras D status 2

                     -'s    -

C71EC009 'RFC Logic A status 4 C71EC010 RFC togic 5 Status 4 C85EA011 Main Turbine htal EvP valve Position . 4 0- E22EA001 MPCS F1w ' 8

                     ]                 E22EC001        MPCs Systes Initiation Status                                             5
                          .            E51EA004        RCIC Pump Flw                                                             I E               E51EA014        RCIC Wrbine Speed                                                         8 E51EC001        RCIC systes Initiation status                                            10
                      ;, .             N21EA019        Condenser Pressure A                                                    100
                     .g                N21EA020        Condenser Pressure B                                                    100 e                N21EA021        Condenser Pressure C                                                    100 l i.     "   -

( 3.- (. m

                                                                                                                                 'T'5 9 H5l l

l G u G . , 3 ,~ l

                                     }' .;; ~~    ~ .' :t .~~     ,1 e~a ~r!v           ~;I l i . ;...
    .                                                                                                         Cn si m-a21-c2.9.                         - ?:     #

Page: 62

        -                                                                                                     Rev.               3 Attac.w.t 6 (cont. )

D15 Sancle Plan Function ID Punction Description scan Interval (ase:)

            *N31rA002                       Main Turbine Total CV Position                                                       4
            *N32IA005                       Main Turbine Cont Valve A Position                                                   4
            *N32rA006                       Main Turbine Cent Valve B Position .                                                 4
            *N32rA007                       Main Turbine cent Valve C Position                                                   4
            *N32EA00!                       Main Turbine Cent Valve D Position                                                   4
            *~71A00:3 "                      F1w Bias Sin 11sted Berral Pwer                                                     8 Trip Setpcint A
            *C71A0004+'                     riow Bias simulated Thermal Pwer                                                     8 Trip Setp: int B a

i k l 1 1

• Required point for test. l

            + Printout required in Test Results Package,                                                                                                              j
                    ,                                                                                                                                   r:.
                                                                                                                ,,,-,,,-,-y---             -,-,n,-.- ,, . - , , ,

UdCC13 l l CF.5: ST:-E21-025A

                                                           .                                                                                   Page: 63 g                                                            .                                                                             Rev.: 3 Attachment 7 Pors: STI-B11-021A-6a sheets a-b TC-7 Margin Verification                                                              ;

In'  :

1. From the completed level 2 analysis of sectices 8.2 perfocaed at :a.

TC-f, record the follevugs <p

               .                      a) 1 Fr: : 8.2.11.2a (Simulated Thermal Power) record the largest                                                                       8#

transient change in sindsted thermal power (5:P). dsTP - 65  % b) verify the f=11owing: l

            .                                         10%                 -

dSTP 2 5% lot -

                                                                                                 .T5 % 2 5\

9.45 % 2 54 c) From 8.2.11.3 (Reactor Pressure) record the following:  ;

1. Initial Presrae = 93i psig -

(- 2. Peak Transient Pressure = %b psig 1 E e I..iti d Pressure - Peak Transient Pressure = 9 psig d) Verify the felleving: 55 psig - p 1 10 psig 55 psig - 9 psig 2 10 psig 46 psig 2 10 psig e) From 8.2.11.4 (Neutrert Flux) record the following: den- 2 s l f) verify the following: 1 38% - dAPM 2 7.5% 384 - 2 4 1 7.54

      ,                                                                              ~3 L                     4 1 7.54 serial no. _46/
                     - -w---       ,          - , , , - , , , - , , , - - - - - - - - - , , , - , , , , , , ,                  ,,,- -
                                                                                                                                            -,      ,,n--   --,---,.-.,n.- -

l { i* 1 0 a . <

• 1.")

1 l

                                                    .                                                         CF. 5: C -L 1-C25).

(. - Page: 64 - IMr Dev.: 3 Atta . % : 7

                  -                                                                                           Fom: C -821-C25A-fb
                                                        'IC-7 Margin verification g)   Frrs 8.2.2.1.5 (Ms:, Isolation Avoid =. m) record the follwing:                                                                 I Initial Ms:, f1w                IM

• lo' IkmAir Peak Individual MsL nw - #.at se' 11wttr E T1w = Peak Iailvidual MS:, F1w - Initial MSI. f1w 3.85 x 106 lic,t:

h) Verify the fc11oving: l l 52 L - en rlw 110% 52% - Id P. 1 lot M 4 1 10t i [ [w.td eM~ Ca:plete: rp Dau l M J & ?deh? y nec eyez.a l l e Dremztu4Mk1 serial No. 6-l 1

77 ( Reportability Review Date/ Time Event 10-29-87/2144 Both MSL D Isolation Valves Failed. 10-30-87/0010 4 hour ENS call made to NRC regarding slov HSIVs.

• Call made within the Requirements of 10 CFR 50.72 (b)(2)(iii) - Loss of a safety function.

11-03-87/1212 Both MSL D Isolation Valves Failed. 11-03-87/1337 Commenced Plant Shutdovn. 11-03-67/1255 ENS call rade on Plant shutdern and slov MSIYs.

• Call satisfied 4 hour requirements of 10 CFE 50.72 (6)(2)(111) and I hour requirement of 50 72 (b)(1)(i)A -

Plant shutdovn required by Technical Specificatien. 11-3-87/1819 Plant scrammed to shutdovn. 11-03-87/2130 ENS call made on RPS/EST Actuation.

                   *2130 call was unnecessary since the p1snt scrar vas planned, not unexpected. Never-the-la       call var within 4 hour requirer.ent per 10 CFR 50..' (b)(2)(ii)   -

RPS/EST Actuations.

Conclusion:

   'three calls vere madt. All im ediate N:tificatic:.

Requirements vere satisfied. One call ves cade unnecessarily. A 30 day written report, in accordance with 10 CFR 50.73, was initiated and is forthconing. b P

67 ( l. History On October 29, 1987 at 1900, Main Steam Isolation Valve (MSIV) lE21-T022D i exceeded it's allovable stroke time during perfore.ance of a startup test and ' vas declared inoperable. Technical Specification 3.6.4 Action (a) then becare applicable and the penetration was to be isolated within 4 hours unless the valve could be returned to Operable status. At 2103 and 2106, 1B21-F022D vas cycled and strokcd closed within the 5 second isolation time required by 3.6.4. Subsequent to the IB21-T022D valve testing, all MSIVs vere cycled in order to verify adequate stroke tises. At 2144, the 1B21-F028D failed it's stroke tiec test and was considered inoperable. At this point, Technical Specifications required the plant to be shutdovn in 12 hours. (One other MSIV, 1B21-T02SE, also failed it's first stroke time test at 2216). E:, 2310, all ESIVs that failed the!r initial stroke times had successfully completed subsequent tests and an evaluation of the results vas co plett. The valves were nov considered operable. The bases for this decision was that the cam of th( sler closures was a one tin deposit of detris in the respe:t!": solenoids causing a delay in their response. Once the valves were cycled and the strch tites passed, the debris vas assured to be blevn avay. This conclusion vas consistent vith known industry problems regarding air syster.s and MSIV solenoid valves. These previous experiences vere considered heavily in the final decision. No further actions per Technical Specifications vere. required. None of the Technical Specification Limiting Conditions for ( Opetation (LCO) vere violated. On No'.e-he: 3. loE7 anothei series of stroke timing tests vere perforced on the MSIVs. At 1157, the IB21-T022D failed it's stroke tire and vas declared inc p : alle . At 1208 the IB21-F026D failed to close. Both valves vere subsequently recycled satirfactorily within minutes of their first testt. Hovever, because the valves again failed to properly actuate on the first attempt, th( original hypotheses for the isolated failures vas no longer considered valid. The plant commenced a shutdovn at 1330 and the D and B lines vere isolated by 1354 At 1819, in order to complete the shutdovn thc reactor vas manually scrammed. The plant was shutdown within the 12 hours required by Technical Specification 3.6.4 Action (a). Since no LCO vas violated during either event, the plant remained within the constraints of the analytical bases contained in the operating license. Consequently, the incidents resulted in no immediate safety significance. l l l O .

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V.O. DESCRIPTION 85-12198 Nuclear Boller NSSS - Repair Leaking Instrument Air Fitting. 86-312 Nuclear Boiler NSSS - Determined Sol Leads Form MSIV's. 86-512 Area Rad Monitor - Rework Local Meter. 86-806' Nuclear Boiler NSSS - Revork Sv'agelock Fittings on MSIVs. 86-12963 Nuclea- Boiler NSSS - Sol currently reads "0" Panel 1H13-P622. 86-14977 Nuclear Boiler NSSS - Valve vouldn't slow close per SVI. 87-82 Nuclear Boiler NSSS - MSIV "C" vill not close in Test position. 87-3153 Nuclear Boiler NSSS - Perform Test of Valve as per NR. 87-3156 Nuclear Boiler NSSS - Remove 0-ring and Clean Valve Seats. 87-5841 Nuclear Boiler NSSS - Elect. Support (1B21-F0022C). 87-8290 Nuclear Boiler NSSS - Revork Valve to assure proper operation. l l l 40 0  ; I

                                                                                                                           ~      - , _ _

l i PAGE 1 0F 2 V.O.

SUMMARY

l 85-0572 Checked calibration of 1P52-N0140, Recalibrated. l 85-3756 Machined valve poppet on 1821-F00228. , l 85-4174 Machined valve poppet on 1B21-F00228, 85-4320 Machined valve poppet on 1821-F0022B. 85-4413 Machined Sten Seat per NR P038-6105 for IB21-F0022B. i 85-5198 Machined Valve poppet on 1B21-F0022B. 85-11486 Performed loss of air test per GEN-M-038 on 1B21-F0022B. 85-11512 Performed loss of air test per GEN-M-038 on 1B21-F0022B. ) 85-11839 Performed loss of air test per GEN-M-038 on 1B21-F0028D. 85-11943 Installed flood & moisture seals in cable transits & MSIVs per DCP 85-618. 86-0312 Determined MSIV Solenoid leads to allov disconnection of conduit. 86-0522 Replaced 1B21 Solenoid valves with spares. 86-0806 Reworked Svagelock fittings on MSIVs (1B21-F022 B & D and F028 A, B, C & D). 86-7637 Replaced screws and gasket for 1B21-F0022b. 86-12734 Voided - to close out DAR-269. 86-12963 Troubleshoot Solenoid - replaced rectifier with new diode bridge on 1B21-F0022D (NR MMQS-1382). 86-14977 Troubleshoot - 1B21-F0022D vouldn't slow close per SVI-C71-T038D. Replaced relay 1821-K0077D. l l 87-0729 Revorked 1B21-F0022B due to failed LLRT. 1 87-0735 Contingency V.O. - Not needed. 87-0763 Performed Repetitive Task R85-10868/DCP 87-216. Performed SVI-C71-T0038H, Rebuilt limit switches, & completed SVI-B21-T2001 all for 1B21-F0028D. 87-0769 Performed Repetitive Task R85-10954/DCP 87-216 for 1B21-F0022B. Rebuilt limit switches. Performed SVI-C71-T0038B & SVI-B21-T2001.

PAGE 2 0F 2 h V.O.

SUMMARY

87-5839 Contingency V.O. - Not needed (See V.O. 87-769 for retest). 87-5842 Contingency V.0. - Not needed (See V.O. 87-770 for retest). 87-5846 Contingency V.O. - Not needed (See V.O. 87-763 for retest). 87-8149 1821-F00228 stem threaded out of stem plate. Revorked per NR NEDS-2863. Performed SVI-B21-T2001. 87-8206 1B21-F0022B failed LLRT. Revorked, reasses'uled, and rutest. 87-8236 Adjusted actuator stroke & calibrated limit switches for 1B21-F0022D. 87-8618 1821-F0028D had no close indication due to loose terminal on switch ti.

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TITLE : EOPL/SP 607-000

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REFERENCE DOCUMENTS:.

                                                                                                                                                   ;tgTy;       ,,      pp                             . NOTES:.;
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q REACTOR RECIRCULATIOH SYSTEM ~ # " f

• T .,,3pPiy h'g,

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                                                                                                                                                 .                                    ENCLOSCO IN 30XE!

0 10L R00 DRIVE HIDRAULIC SiSTEN

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                                                                                                                                                 -t TOR Sr$ TEM OUTLINE DRAMINGS                                                                                                         n D                     EU'J I PMENT

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TOR WATER CLEl.NUP SYSTEM

                                                                                                                        # M *.                                  5. LOCATE IN AREA :;ERVED BY ',TANl TOR 100                                                                                                                                                                                                                -

ATION,. VALVE.lNTERFACECONTROLOhlAhG f.OPI:iATION.

                                                                                            '7                                                                        FOR OTHER NDDES.0F;0PERATION, ,

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       'E              dE'RTP,gDCESSlNSTRUMENTE     y                                                                                                                  IN ACCCf,0ANCE WITH SPEC. M,
        ' 'DN99hiN$C                     i               ll l[Ch I ONNsM[ y NEitTARY                                                          i.                    a:

9. PROVISION FOR INSTRUNT. diii

T, MS

                                                    ~-

i (S.IEN sp ; _ ,. ONE ORIFICE SHALL BE INSTALL.E

d. 30tiMDARY (T.CFB). ORIFICE Sils i

               .,  . . .           . ._ J . AW81                            .

4DEECil0NSYSTEN3L.;2t%Yf..ig. j - 3 NAXINUM NDNBER OF ORIFICES PE

        . P00.L' COOLING AND CLE AN-Up~~ ~TSTE,Nj '.;isN.                                                                                                       13. VI.LVE N0 TOR OPERATGRS AND Pil
          ; TOR'RECIRC9tATl0N SYSTEN'                                     Y%                         m...

11. LOCATE TEE AS CLOSE AS POS!!i 1

9 y- .

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        ?uMDANT REACTIVITV COMTR, g .e                                  p TORt JECiljCULAil0N SYSTEN (tg;?lg

, g y t;, i 13. ALL INDMATO'i LANPS LOCATED . I muoAMT REACTWtTY c oWTg 4 , .

14. FOR ;'ONIF.LL RODE. '.ML 0? U I

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l . i -9 61 v' I b~b RT.FERENCE DOI

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l 0-302-M4 0-302-621

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0-332-632

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