|
---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20207E8011999-05-19019 May 1999 Non-proprietary Rev 2 to HI-981933, Design & Licensing Rept DBNPS Unit 1 Cask Pit Rack Installation Project ML20205K5781998-12-31031 December 1998 Waterhammer Phenomena in Containment Air Cooler Swss ML20217P8041998-04-0707 April 1998 11RFO OTSG ECT Insp Scope ML20196B8771996-12-16016 December 1996 First Amended & Restated Master Decommissioning Trust Agreement Dtd as of 961231 Between Toledo Edison Co & Mellon Bank ML20196B8951996-12-16016 December 1996 First Amended & Restated Master Decommissioning Trust Agreement Dtd as of 961216 Between Cleveland Electric Illuminating Co & Mellon Bank ML20134D7821996-05-0808 May 1996 Rev 1 to Instrument Drift Data Analysis Methodology & Assumptions ML20091S4311995-08-31031 August 1995 USI A-46 Seismic Evaluation Rept. W/61 Oversize Drawings ML20138J1411994-02-28028 February 1994 Rev 0 to IPEEE,A-46 & Design In-Structure Response Spectra for Selected Bldgs at Dbnps ML20067D3311993-08-31031 August 1993 Technical Evaluation Rept,Evaluation of B&Wog Pressurizer Surge Line Thermal Stratification Program to Address NRC Bulletin 88-11 ML20091P5721991-10-31031 October 1991 Reactor Containment Bldg Integrated Leak Rate Test Including,Type A,B & C Periodic Test Results ML20070Q1911991-03-25025 March 1991 NRC Form 474 Simulation Facility Certification ML20058L1891990-08-0101 August 1990 Dcrdr Human Engineering Discrepancy Repts 1988 Summary Addendum 1,Vol 1 ML20006E3671990-01-11011 January 1990 Toledo Edison Co Mark-BZ Fuel Assembly Seismic & LOCA Analysis. ML20094J0841989-12-0808 December 1989 Investigation of Acoustic Leak Monitoring for NRC Region Iii. Info Partially Deleted ML19324C1761989-10-30030 October 1989 Hpi/Makeup Nozzle Weld Overlay Repair Contingency Plan. ML19327B0161989-10-11011 October 1989 Cycle 7 LOCA Limits. ML20245K6751989-08-0202 August 1989 Rev 2 to Review 18 Month PM Items for Diesel Generator & Evaluate Extension to 30 Months ML20151Z1941988-08-11011 August 1988 Rept on Reactor Vessel Continuous Vent Line Performance, ML20234F2501988-01-0606 January 1988 Rev 3 to App R Compliance Assessmemt Rept ML20147C0851987-12-0101 December 1987 Fifth Refueling Outage Executive Summary. Related Documents Encl ML20237J9781987-08-24024 August 1987 Performance Indicators for Davis-Besse Nuclear Power Station,Salp 6,Weekly Rept 3 for Period Ending 870824 ML20214J1891987-05-0505 May 1987 Rev 2 to App R Compliance Assessment Rept ML20206J5001987-03-31031 March 1987 Dcrdr Special Study Plans for Davis-Besse ML20212G7461987-01-0707 January 1987 Rept of Emergency Evacuation Review Team on Emergency Response Plans for Perry & Davis-Besse Nuclear Power Plants ML20214E0761986-11-17017 November 1986 Auxiliary Feedwater Calculation Summary ML20211E0651986-09-26026 September 1986 Transient Assessment Program Rept,Davis-Besse Unit 1 Reactor Trip on High Flux,840302 ML20214T7501986-09-11011 September 1986 DB Small-Break LOCA Analysis Assumptions Evaluation ML20154Q6531986-02-28028 February 1986 Westinghouse Owners Group Position on Davis-Besse Event ML20141E6691985-11-30030 November 1985 B&W Owners Group Action Plan for Review of 850609 Davis-Besse Transient ML20138H4891985-11-25025 November 1985 Rev 17 to Seismic Category I Piping Sys Support & Hanger Discrepancies ML20136H0951985-11-15015 November 1985 Revised Davis-Besse Reactor Protection Sys Single Failure Analysis ML20137H3971985-11-12012 November 1985 Rev 16 to Seismic Category I Piping Sys Support & Hanger Discrepancies Summary Rept ML20137S9031985-10-29029 October 1985 Toledo Edison Davis-Besse Nuclear Power Station Unit 1 Seismic Category I Piping Sys Support & Hanger Discrepancies,Summary Rept ML20209H5861985-10-28028 October 1985 Rev 3 to Course of Action ML20137S8241985-10-22022 October 1985 Rev 14 to Seismic Category I Piping Sys & Hanger Discrepancies,Summary Rept ML20209H6481985-10-15015 October 1985 Rev 3 to Auxiliary Feedwater Pump Turbine Overspeed Trip Throttle Valve Problem ML20138J4811985-10-15015 October 1985 Seismic Category I Piping Sys Support & Hanger Discrepancies ML20133M9911985-10-0808 October 1985 Rev 12 to Seismic Category I Piping Sys Support & Hanger Discrepancies,Summary Rept ML20133K9881985-10-0404 October 1985 Independent Mgt Assessment of Toledo Edison Davis-Besse QA Program ML20138A9411985-09-24024 September 1985 Rev 10 to Safety-Related Piping Sys Support & Hanger Discrepancies, Summary Rept ML20132E4471985-09-17017 September 1985 Rev 9 to Safety-Related Piping Sys Support & Hanger Discrepancies, Summary Rept ML20137C3021985-09-0909 September 1985 Toledo Edison Co Davis-Besse Nuclear Power Station Course of Action Rept ML20137M5431985-09-0909 September 1985 Vols 1 & 2 of Davis-Besse Course of Action ML20135D7421985-09-0303 September 1985 Rev 7 to Safety-Related Piping Sys Support & Hanger Discrepancies, Summary Rept ML20133K9941985-08-30030 August 1985 Rept of Assessment of Actions at Davis-Besse Resulting from 850609 Loss of Feedwater Event ML20134Q0161985-08-27027 August 1985 Rev 6 to Safety-Related Piping Sys Support & Hanger Discrepancies, Summary Rept ML20137U3061985-08-16016 August 1985 Rev 5 to Safety-Related Piping Sys Support & Hanger Discrepancies, Summary Rept ML20134B8371985-08-0909 August 1985 Rev 4 to Safety-Related Piping Sys Support & Hangar Discrepancies, Summary Rept ML20133M3261985-07-26026 July 1985 Rev 3 to Safety-Related Piping Sys Support & Hanger Discrepancies,Summary Rept ML20126L9021985-07-0505 July 1985 Rev 1 to Action Plans 5,6 & 7, Steam & Feedwater Rupture Control Sys Trip/Msiv Closure 1999-05-19
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML20217D5441999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Davis-Besse Nuclear Power Station.With ML20211R0811999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20211B0271999-08-13013 August 1999 SER Accepting Second 10-year Interval Inservice Insp Requests for Relief RR-A16,RR-A17 & RR-B9 for Plant, Unit 1 ML20210Q8541999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20209E6231999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20195K2871999-06-16016 June 1999 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20195F4871999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20207E8011999-05-19019 May 1999 Non-proprietary Rev 2 to HI-981933, Design & Licensing Rept DBNPS Unit 1 Cask Pit Rack Installation Project ML20207F4351999-05-0404 May 1999 Rev 1 to DBNPS Emergency Preparedness Evaluated Exercise Manual 990504 ML20206M6341999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Davis-Besse Nuclear Station,Unit 1.With ML20205M2931999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Davis-Besse Nuclear Power Station.With ML20207J1461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20199H5931999-01-20020 January 1999 Safety Evaluation Accepting Thermo-Lag Re Ampacity Derating Issues for Plant ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20199E2501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl ML20205K5781998-12-31031 December 1998 Waterhammer Phenomena in Containment Air Cooler Swss ML20197J3441998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20195D0001998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20155B6781998-10-28028 October 1998 Safety Evaluation Accepting Proposed Reduction in Commitment Changes in QA Program Matl Receipt Insp Process ML20154H5801998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20151W1611998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Dbnps.With ML20237E3171998-08-21021 August 1998 ISI Summary Rept of Eleventh Refueling Outage Activities for Davis-Besse Nuclear Power Station ML20237B1681998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236U5011998-07-23023 July 1998 Special Rept:On 980624,Unit 1 Site Damaged by Tornado & High Winds.Alert Declared by DBNPS Staff,Dbnps Emergency Response Facilities Activiated & Special Insp Team Deployed to Site by Nrc,As Result of Event ML20236R1441998-07-15015 July 1998 SER Related to Quality Assurance Program Description Changes for Davis-Besse Nuclear Power Station,Unit 1 ML20236N7451998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236K3981998-06-30030 June 1998 SER Accepting in Part & Denying in Part Relief Requests from Some of ASME Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Davis-Besse Nuclear Power Station,Unit 1 ML20236K5131998-06-29029 June 1998 Safety Evaluation Accepting Proposed Alternate Emergency Operations Facility Location for Davis-Besse Nuclear Power Station,Unit 1 ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A4121998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20196B5221998-05-23023 May 1998 10CFR50.59 Summary Rept of Facility Changes,Tests & Experiments Dbnps,Unit 1 for 960602-980523 ML20236E7581998-05-19019 May 1998 Rev 0 to Davis-Besse Unit 1 Cycle 12 Colr ML20236N7501998-04-30030 April 1998 Rev 2 to Monthly Operating Rept for Apr 1998 for Davis-Besse Nuclear Power Station,Unit ML20247F6721998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Davis-Bess Nuclear Power Station,Unit 1 ML20249A4141998-04-30030 April 1998 Revised Monthly Operating Rept for Apr 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20217P8041998-04-0707 April 1998 11RFO OTSG ECT Insp Scope ML20216B4041998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20216C5131998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20202D3721998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20199G6321998-01-26026 January 1998 Rev 1 to Davis-Besse Unit 1,Cycle 11,COLR ML20198R4771998-01-13013 January 1998 SER Approving Second 10-year Interval Inservice Inspection Program Plan Requests for Relief for Davis-Besse Nuclear Power Station,Unit 1 ML20198K7931997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Davis-Besse Nuclear Power Station,Unit 1 ML20217K6401997-12-31031 December 1997 1997 Annual Rept First Energy ML20203A3931997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Davis-Besse Nuclear Power Plant,Unit 1 ML20198S5371997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Davis-Besse Nuclear Power Station ML20217H7701997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Davis-Besse Nuclear Power Station,Unit 1 ML20216H3261997-08-31031 August 1997 Monthly Operating Rept for August 1997 for DBNPS ML20217K0241997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Davis Besse Nuclear Power Station,Unit 1 1999-09-30
[Table view] |
Text
.
_e- ,
ACTION PLAN i 10 TITLE: REVIEW OF THE OPERATION OF THE PORV CHAIRMAN REV DATE REASON FOR REVISION BY TASK FORCE O 6/22/85 Initial Issue T. Isley
((
8507300104 050622 PDR ADOCK 05000346 P PDR
\
O
- 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 FORV 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 PSIC. The block valve was reopened 2 min.
13 sec. later and the FORV 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 after the block valve started to move to the close 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 I 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 _gtal was 469'F which is greater than the required 400*F (minimum), therefore, no piping snalysis is needed.
Page 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 (NWO 77-1592).
09-06-77 The PORV was disassembled, inspected, and seating surfaces lapped (NWO_ 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 fcund 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 NWO 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 2400 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 disc 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 PT 5164.02. No problems found.
09-06 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.
Page 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 g[}(
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 Surmary A discussion with B&W about the way the PORV operated, produced several possible causes.
1.- During the first two lif ts 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 I
- . . - . . _ . . - _ . . -. - . .- . . _ - . - - -, . - - ~
I Page 4 of 4 3
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 -
wo:11d provide any information. The testing done by EPRI used a
- similar Crosby valve with a 13/8" 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 i 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 tamediately prior to the first lift of the valve. In the EPRI test the valve closed properly, however, they only did one cycle while we f experienced multiple cycles.
i 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.
1 2. The valve mechanically malfunctioned causing it to not close '
during the transient.
j 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 j stick.
t i
i TRI:lrh Attachment t
I e
y- r- e+ e -
vrw - -- a v e- w,,we--,mw---w=-- e e- <w c-,---,w,r vm-+--+.-s w*~-- < = gw - e a-w e e- rw-yw
C O l. ..
9 ACTION PLAN PL AN NUMHE H PAGE sm" _._ _ ._
Rev. 0 10 1- a'1 '.
TITLE DATE PREPARED PREPARED BY REVIEW OF THE OPERATION OF THE PORV 6/21/85 T. R. Isley_
SPECIFIC OBKCTIVE ,
1 STEP PRIME ASSIGNED START TARGET DATE A
NUMBER RFSPONSIBILITY TO DATE DATE COMPLET ED 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".
1 Perform a visual inspection of the PORV and associated linkage. Isley Check for broken or missing parts, boric acid buildup, or other abnormalities.
- I 2 Under the direction of the Crosby representative, disassemble Isley the PORV. Check the internals for damage, proper clearances, i abnormal wear, or foreign material. Also check the bellows
[ l for proper fit or cracking. / , -
3 Analyze the results of the inspection and data surrounding Isley , [/ j l j, v
the transient to determine if differential expansion caused , f (( o the valve to stick open. This analysis is expected to take / h[ /
several weeks and will require the results of the valve i / n) / A ,A inspection before proceeding.
} j ,
,1 YY f Y