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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising SRs 4.8.2.3.2.d,4.8.2.3.2.e, 4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,Modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134D7621997-01-30030 January 1997 Proposed Tech Specs Revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm 1999-09-07
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm ML20107C3021995-10-16016 October 1995 Rev 8 to Odcm ML20199L1821995-09-0909 September 1995 Rev 3 to DB-OP-00000, Conduct of Operations ML20082V4071995-02-0303 February 1995 Offsite Dose Calculation Manual Rev 7 ML20072S8611994-06-22022 June 1994 Rev 6 to Davis-Besse Offsite Dose Calculation Manual ML20056F3071993-08-0808 August 1993 Rev 3 to Emergency Plan Off Normal (Epon) Occurrence Procedure HS-EP-02820, Earthquake. W/Rev 23 to Epon Occurrence Procedures Manual Table of Contents ML20072S8401992-12-18018 December 1992 Rev 5 to Davis-Besse Process Control Program ML20072S8501992-12-18018 December 1992 Rev 5.2 to Davis-Besse Offsite Dose Calculation Manual, Reflecting Rev 5,Change 2 to ODCM ML20101R1721992-06-11011 June 1992 Rev 1 to Vol I of Inservice Insp Plan,Second 10-Yr Nuclear Interval Pump & Valve Inservice Testing Program ML20114C6321992-05-19019 May 1992 Change 1 to Rev 5 to ODCM ML20114C6301992-03-0606 March 1992 Rev 5 to ODCM ML20217C3661991-07-0808 July 1991 Rev 3 to Administrative Procedure NG-IS-00002, General Nuclear Security Requirements. Pages 7,9,10 & 15 Only ML20084U5911991-02-22022 February 1991 Rev 4 to ODCM ML20217C3481990-12-18018 December 1990 Rev 1 to Security Dept Procedure IS-DP-04007, Performance Test for Alco-Sensor ML20059D4181990-08-28028 August 1990 Second 10-Yr Interval Pump & Valve Inservice Testing Program ML20217C3001990-08-23023 August 1990 Rev 5 to Security Dept Procedure IS-AC-00011, Protected & Vital Area Badge Issuance & Control ML20217C3571990-08-0909 August 1990 Rev 3 to Security Implementing Procedure IS-AC-00516, Unescorted Access Requirements ML20217C3071990-07-27027 July 1990 Rev 2 to Security Dept Procedure IS-AC-00015, Fingerprint Processing & Controls ML20217C3201990-06-27027 June 1990 Rev 1 to Security Dept Procedure IS-AC-00018, Drug & Alcohol Testing Process ML20217C3811990-06-22022 June 1990 Rev 4 to Nuclear Group Procedure NG-IS-00004, Fitness for Duty Program ML20217C4001990-04-0202 April 1990 Corporate Ref Manual - Nuclear NU-102, Fitness for Duty ML20217C3401990-01-12012 January 1990 Rev 1 to Security Dept Procedure IS-DP-00101, Bac Simulation ML20217C3281989-11-0909 November 1989 Rev 1 to Security Dept Procedure IS-DP-00100, Bac Exams ML20217C3141989-10-25025 October 1989 Rev 2 to Security Dept Procedure IS-AC-00017, Denied Access List Control ML20217C3941989-08-0101 August 1989 Corporate Ref Manual - Human Resource HR-604, Drug & Alcohol Policy ML20244A8421989-05-31031 May 1989 Pressurizer Surge Line Thermal Stratification Phase I Program ML20213A0311987-03-31031 March 1987 Rev 2 to Vol IV of Procedure Writers Manual:Operation Procedures Guidelines ML20213A0361987-03-31031 March 1987 Rev 1 to Davis Besse Emergency Procedure Verification & Validation Program ML20212D1621987-01-27027 January 1987 Rev 1 to Maint Procedure MP 1411.06, Preventive Maint for Type Smb & Smc Valve Operators ML20198D2551986-12-27027 December 1986 Rev 2 to Maint Procedure MP 1411.04, Maint & Repair of Limitorque Valve Operators Type SMB-000 & SMB-00. Temporary Mod Request T-9969,indicating Rewiring of Fcr 85-302 MU-11 to Torque Out in Open Direction,Encl ML20212B5721986-12-15015 December 1986 Rev 0 to Security Training & Qualification Plan, Superseding Rev 24 to App B of ISP AD1808.00.W/o Revised Pages ML20212C9481986-11-21021 November 1986 Rev 8 to Maint Procedure Mpo 1410.32, Testing of Motor- Operated Valves Using Movats ML20212D3131986-10-28028 October 1986 Change 3 to Temporary Mods T10161 & T10144 to Rev 0 to Maint Procedure MP 1411.07, Maint & Repair of Limitorque Valve Opr Smc 04, Incorporating Fcr 86-0092,Rev a Re Removal & Installation of Limiter Plate ML20212D1091986-10-21021 October 1986 Change 1 to Rev 2 to Maint Procedure MP 1411.04, Maint & Repair of Limitorque Valve Operators Type SMB-000 & Smb 00, Addressing Need for Procedure to Address Replacement of Defectrive Parts ML20212D1471986-10-0303 October 1986 Rev 1 to Maint Procedure MP 1411.05, Maint & Repair of Limitorque Valve Operators Types SMB-0 Through SMB-4 ML20212C9181986-09-22022 September 1986 Rev 1 to Procedure NEP-092, Establishing D/P Limits & Tests for Q Motor Operated Valves ML20203M0201986-08-21021 August 1986 Specs for Mist Continuous - Venting Tests ML20210V1131986-08-20020 August 1986 Rev 0 to Emergency Plan Implementing Procedure EP-2320, Emergency Technical Assessment ML20206P6511986-06-30030 June 1986 GE Owners Group Action Plan as Result of Davis-Besse Event, June 1986 ML20198D2361986-05-0202 May 1986 Rev 5 to Maint Procedure MP 1410.32, Testing of Motor- Operated Valves Using Movats ML20141J5231986-04-18018 April 1986 Human Engineering Discrepancy Review & Closeout Process for Davis-Besse Dcrdr Program ML20205M6981986-04-0707 April 1986 Rev 0 to Nuclear Engineering Procedure NEP-092, Establish Differential Pressure Limits & Tests for Motor-Operated Valves ML20205M7031986-03-25025 March 1986 Rev 0 to Nuclear Engineering Procedure NEP-091, Motor- Operated Valve (MOV) Data Evaluation ML20141N1501986-02-26026 February 1986 Procedure Fcr 85-227, Main Feedwater Block Valve Interlock ML20141N1561986-02-26026 February 1986 Procedure Fcr 85-200, Main Feedwater Pumps Rapid Feedwater Reduction Speed Setpoint ML20141N1531986-02-26026 February 1986 Procedure Fcr 85-201, Steam Generator Level Setpoint 1998-08-28
[Table view] |
Text
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ACTION PLAN i 10 TITLE: REVIEW OF THE OPERATION OF THE PORV
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l CHAIRMAN REV DATE REASON FOR REVISION BY TASK FORCE O 6/22/85 Initial Issue T. Isley
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r508050130 850627 PDR ADOCK 05000346 PM g P
c TITLE: REVIEW OF THE OPERATION OF THE PORV REPORT BY: Tom Isley PLAN NO: 10 DATE PREPARED: 6/22/85 PAGE 1 of 4 This report has been prepared in accordance with the " Guidelines to Follow When Troubleshooting or Performing Investigative Actions into the Root Causes Surrounding the June 9, 1985 Reactor Trip", Rev. 4.
I. INTRODUCTORY STATEMENT:
This report describes the way the PORV responded during the transient on 6/9/85 and identifies analysis and actions needed to identify root cause(s).
II.
SUMMARY
OF DATA:
During the transient on 6/9/85, the PORV cycled three (3) times. The first time the PORV opened for 3 seconds and then closed at the proper setpoint. The second time the PORV opened at the proper setpoint for 3 seconds and then closed approximately 25 psi below the required setpoint. The third time the valve opened at the proper setpoint but did not reseat at the proper pressure. The operator manually closed the PORV block valve. RCS pressure stopped decreas-ing at approximately 2075 PSIG. The block valve was reopened 2 min.
13 sec. later and the PORV appeared to hold RC pressure. When the PORV failed to close, the operator noticed that the close light was lit indicating the control circuit worked properly, deenergizing the PORV solenoid.
It should be noted the PORV block valve stoke time is approximately nine seconds. The accoustical monitor indicated that flow stopped in approximately seven seconds af ter the block valve started to move to the c. lose position. The exact time at which flow stopped is uncer-tain because the accoustical monitors are not designed to indicate accurately at low flow rates. Therefore, it cannot be positively identified if the PORV reset (at approximately 300 psi below the required setpoint) or the block valve closed which stopped the flow through the PORV.
Reviewing the previous operations of the PORV shows a total of 91 hot
' cycles and 17 cold prior to 6/9/85. Adding the 3 hot cycles gives a
. total of .94 hot and 17 cold, as compared to an allowable number of 440 hot and 25 cold cycles. It has also been determined that the temperature of the loop seal was 469'F which is greater than the required 400*F (minimum), therefore, no piping analysis is needed.
s k
Pagn 2 of 4 III. MAINTENANCE AND SURVEILLANCE / TEST HISTORY:
12-14-76 The PORV was disassembled, inspected, and the seating surfaced lapped (MWO 2161). The valve had lifted 8 times since it was installed.
08-01-77 The PORV failed to open. Replaced power fuses (MWO 77-1592).
09-06-77 The PORV was disassembled, inspected, and seating surfaces lapped (MWO 77-1903). The valve had lifted 14 times since last maintenance.
09-24-77 The PORV failed open during a loss of feedwater accident.
The valve was disassembled and the pilot valve was found stuck open. The pilot valve stem was replaced and the nozzle guide was cleaned. When the valve was reassembled and tested, the valve again failed open on the sixth cycle.
The valve was again disassembled and inspected. The pilot valve stem was machined to correct the pilot stem-nozzle guide clearance, and the stroke of the pilot valve was adjusted. The valve was cycled 12 times at reduced pres- ,
sure and once at 2200 psig with no problems. (Reportable Occurrence NP-32-77-16, MWO 77-2120 and MWO 77-2256.)
01-18-79 Because the PORV was leaking, it was disassembled'and inspected. The disc, seat, and pilot valve were found to have minor cutting. They were lapped and the valve was reassembled (MWO 79-1307). The valve had lifted 67 times since last maintenance.
04-19-79 The PORV actuating linkage was checked for proper operation and proper supply voltage to the solenoid coil was veri-fied. No problems found (MWO 79-1978).
05-17-79 The setpoints for the PORV were changed to open at 240,0 psig and close at 2350 psig (FCR 79-169).
10-29-79 Because the PORV was leaking, it was disassembled and inspected. The valve disc and pilot dise were lapped and the valve was reassembled (MWO 79-3433). The valve had lifted 2 times since last maintenance.
03-24-82 Because the PORV was leaking, the valve was disassembled and repaired (MWO 81-3662). No lifts since last maintenance.
09-01-82 The PORV was stroked per FT 5164.02. No problems found.
09-06-83 The setpoints for the PORV were changed to open at 2425 psig and close at 2375 psig (FCR 79-348).
__. . _ _ 09-14-83 The bistable setpoints were checked by ST 5040.02 and found to be acceptable.
O Pa.gs 3 of 4 12-28-84 The bistable setpoints were checked by ST 5040.02 and found to be acceptable.
Maintenance and Test Summary The majority of the maintenance was to correct for minor leakage.
The valve failed open one time, was repaired, and had operated properly prior to June 9, 1985. The routine testing has not found any problems with the PORV.
Change Analysis Since the PORV was last operated on September 1, 1982, the only
^
change was to the bistable setpoints. Since the bistable functioned properly and the setpoints have been verified twice since they were changed, this did not have any effect on the operation of the PORV.
There have been no other changes since the last successful operation.
Failure Hypotheses Summary A discussion with B&W about the way th' ePORV operated, produced several possible causes.
- 1. During the first two lifts of the PORV, the loop seal could have emptied which would have allowed the valve to pass only steam during the third lift. The hot steam could have caused the disc
, to expand more rapidly than the valve body causing the disc to stick. After the valve temperatures had equalized, the disc would free up and then reseat. Subsequent Toledo Edison calcu- -
lations have shown that the loop seal would have been emptied during the first lift of the PORV.
- 2. The linkage for the pilot valve could have broken allowing closed indication but the pilot valve would still be open, keeping the PORV open.
- 3. One of the solenoid coil guides could have broken causing the valve to stay open. This has happened on a similar valve by a different manufacturer.
- 4. Possible corrosion or boric acid buildup on the solenoid coil linkage causing the linkage to stick,
, 5. A-piece of foreign material inside the valve caused the disc or pilot valve to stick open.
- 6. The possibility exists that pressurizer level was high enough to put water through the valve. This has been rejected as a possible cause for the failure because the valves tested by EPRI all worked properly when tested with water.
The Crosby Valve and Gage Co._was contacted and they were unable to provide any additional information about possible failure modes for
W Pagt 4 of 4 the PORV. They reminded us that their valve worked very well in all of the testing done by EPRI.
We have reviewed the EPRI test data to determine if the testing done would provide any information. The testing done by EPRI used a similar Crosby valve with a 1 3/8" bore while ours has a 1 " bore.
They had some problems initially with the pilot valve bellows crack-ing or being improperly machined but the valve functioned properly after those problems were corrected. Previous maintenance has detected no problems with the bellows in the valve at Davis-Besse.
The EPRI test demonstrated that the tested valve closed in 0.1 to 0.2 seconds.
The EPRI test set up did have a loop seal. In one test, the condi-tions were very close to the conditions experienced on June 9, 1985 immediately prior to the first lif t of the valve. In the EPRI test the valve closed properly, however, they only did one cycle while we experienced multiple cycles.
Our review of the NPRDS data since TMI 2 found a PORV failed open at another utility one time. The valve that failed is a different design and that failure is not believed to be related to the failure we experienced.
IV. HYPOTHESES:
- 1. The PORV stuck open due to differential expansion of the disc and body.
- 2. The valve mechanically malfunctioned causing it to not close during the transient.
- 3. The solenoid coil linkage could be broken or have corrosion buildup causing faulty operation.
- 4. A piece of foreign material caused the disc or pilot valve to stick.
4
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Attachment
t
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' ACTION PLAN PLAN NUMHEH PAGE ,
so .4ee Rev. 0 10 l_ 'l DATE PREPARED PREPARED BY f TITLE 6/21/85 REVIEW OF THE OPERATION OF THE PORV T. R. Isley_
SFECIFIC OBJECTIVE ,
i I
STEP ! A I D MART TAMET DATE ACTION STEPS FIFSPONSIBILITY TO DATE DATE COMPLETED NUMBEH ALL STEPS OF THIS PLAN ARE TO BE PERFORMED IN ACCORDANCE WITH THE LATEST REVISION OF " GUIDELINES TO FOLLOW WHEN ,
! TROUBLESHOOTING OR PERFORMING INVESTIGATIVE ACTIONS INTO THE ROOT CAUSES SURROUNDING THE JUNE 9, 1985 REACTOR TRIP".
I 1 Perform a visual inspection of the PORV and associated linkage. Isley Check for broken or missing parts, boric acid buildup, or other abnormalities.
) 2 Under the direction of the Crosby representative, disassemble Isley I
l the PORV. Check the internals for damage, proper clearances.
abnormal wear, or foreign material. Also check the bellows
.I for proper fit or cracking.
l l 3 Analyze the results of the inspection and data surrounding Isley the transient to determine if differential expansion caused l l
the valve to stick open. This analysis is expected to take several weeks and will require the results of the valve inspection before proceeding.
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