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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20024G4911972-04-25025 April 1972 Ro:On 720328,improper Fuctioning of RHR Svc Water Regulating Valve Control Occurred.On 720403,malfunction of Containment Isolation Valve Discovered.On 720403,HPCI Steamline High Area Temp Switch 1972-04-25
[Table view] Category:LER)
MONTHYEARML20024G4911972-04-25025 April 1972 Ro:On 720328,improper Fuctioning of RHR Svc Water Regulating Valve Control Occurred.On 720403,malfunction of Containment Isolation Valve Discovered.On 720403,HPCI Steamline High Area Temp Switch 1972-04-25
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D1261999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Monticello Nuclear Generating Plant.With ML20216E7031999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Monticello Nuclear Generating Plant.With ML20210Q0521999-08-0404 August 1999 Safety Evaluation Approving Relief Request 10 to License DPR-22 Per 10CFR50.55a(g)(6)(i).Inservice Exam for Relief Request 10,Parts A,B,C,D & E Impractical & Reasonable Assurance of Structural Integrity Provided ML20210Q6611999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Monticello Nuclear Generating Plant.With ML20209F7901999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Monticello Nuclear Generating Plant.With ML20195H0351999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Monticello Nuclear Generatintg Plant.With ML20206N1721999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Monticello Nuclear Generating Plant.With ML20205N0861999-04-12012 April 1999 Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20205P5701999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Monticello Nuclear Generating Plant.With ML20204H4951999-03-18018 March 1999 SER Concluding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Monticello.Therefore Staff Concludes Licensee Adequately Addressed Action Required in GL 96-05 ML20205G7391999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Monticello Nuclear Generating Plant.With ML20202F7901999-01-25025 January 1999 1999 Four Year Simulator Certification Rept for MNGP Simulation Facility ML20199E4871999-01-0606 January 1999 SER Accepting Licensee 951116,960214 & 0524 Responses to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode ML20199F6211998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Mngp.With ML20205H0561998-12-31031 December 1998 Northern States Power Co 1998 Annual Rept. with ML20198P0691998-12-28028 December 1998 Safety Evaluation Concluding That NSP Proposed Alternative to Paragraph III-3411 of App III to 1986 Edition of Section XI of ASME Code Provides Acceptable Level of Quality & Safety.Alternative Authorized ML20198D0751998-12-10010 December 1998 Safety Evaluation Supporting NSP Proposed Change to EOPs to Use 2/3 Core Height as Potential Entry Condition Into Containment Flooding ML20198B2531998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Monticello Nuclear Generating Plant.With ML20195E3691998-11-12012 November 1998 Safety Evaluation Concluding That Licensee USI A-46 Implementation Has Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20195D2381998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Monticello Nuclear Generating Plant.With ML20198J4451998-10-22022 October 1998 Rev 2 to SIR-97-003, Review of Test Results of Two Surveillance Capsules & Recommendations for Matls Properties & Pressure-Temp Curves to Be Used for Monticello Rpv ML20154L3471998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Monticello Nuclear Generating Plant.With ML20153F0511998-09-21021 September 1998 Rev 2 to MNGP Colr,Cycle 19 ML20153E9361998-09-0808 September 1998 Rev 1 to MNGP Colr,Cycle 19 ML20153B0861998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Monticello Nuclear Generating Plant.With ML20237B8461998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Monticello Nuclear Generating Plant ML20236W5041998-07-21021 July 1998 ISI Exam Summary Rept - Refueling Outage 19 ML20236R1941998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Monticello Nuclear Generating Plant ML20249A5861998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Monticello Nuclear Generating Plant ML20247K3971998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Monticello Nuclear Generating Plant ML20217D8731998-04-13013 April 1998 Rev 0 to MNGP Colr,Cycle 19 ML20217F6431998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Monticello Nuclear Generating Plant ML20216D1041998-03-0505 March 1998 Rev 21 to Operational QA Plan ML20216H6481998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Monticello Nuclear Generating Plant ML20203G1431998-02-10010 February 1998 Rev 2 to Inservice Insp Exam Plan,Third Interval,920601- 020531 ML20203B2821998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Monticello Nuclear Generating Station ML20202F9161998-01-29029 January 1998 Special Rept:On 980128,two of Three Fire Protection Pumps Were Removed from Svc as Result of Sys Configuration Necessary to Support Planned Maintenance.Fire Pumps Were Returned to Svc on 980128 ML20216D2071997-12-31031 December 1997 1997 Annual Rept for Northern States Power Co ML20197J8131997-12-31031 December 1997 Revised Evacuation Time Estimates for Plume Exposure Pathway Emergency Planning Zone at Monticello Nuclear Power Plant. W/One Oversize Drawing ML20198P2201997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Monticello Nuclear Generating Plant ML20203J7131997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Monticello Nuclear Generating Plant ML20199G7051997-11-19019 November 1997 Safety Evaluation Authorizing Relief Request 8 of Third 10 Yr Inservice Insp Interval ML20199H8181997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Monticello Nuclear Generating Plant ML20217K2081997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Monticello Nuclear Generating Plant ML20216H7771997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Monticello Nuclear Generating Plant ML20217K2741997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Monticello Nuclear Generating Plant ML20196H1081997-07-0808 July 1997 Rev 20 to Operational QA Plan ML20141B9271997-06-30030 June 1997 LOCA Containment Analyses for Use in Evaluation of NPSH for RHR & Core Spray Pumps ML20149E2921997-06-30030 June 1997 Monthly Operating Rept for June 1997 for MNGP ML20148S6341997-06-23023 June 1997 NPSH - Rept of Sulzer Bingham Pump 1999-09-30
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'. . Reguistory File Cy, NORTHERN STATES POWER COMPANY ,
Minneapolis, Minneso T*}h l t /
November 24, 1971 O h tent owc
~ CD g~ i Dr. Peter A. Morris g NOV 201971 > = ,, g l
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- RtsuutoRy e M Division of Reactor Licensing QQEg k { 1 _U United States Atomic Energy Corrnission .
Washington, D. C. 20545 HOV29197W -
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Dear Dr. Morris:
gy nem (f.9 f f.ONTICELLO NUCLEAR GENERATito PLANT Docket No. 50-263 License No. DPR-22 Report on Off-Gas Sysim Explosion A condition has occurred recently at the Monticello Nuclear Generating Plant which we interpret to be reportable in accordance with section 6.6.B of the Technical Specifications. The Region ill Compliance office has been notified of this event.
On Novanber 14, 1971, an explosion occurred in the plant off-gas system.
At the time of the occurrence, the plant had been shutdown for about 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, and the condenser equalized to the atmosphere for 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />. The off-gas system had been isolated from the condenser at the air ejectors and the off-gas line loop seal was being cut with an acetylene torch to install a liquid level switch on the loop seal.
No personnel injuries resulted from this occurrence. Following the event, the stack gas monitor indicated an activity release rate of less than the normal operating activity release rate. (The stack gas monitor showed an increase in the activity release of from ~2500 uci/see to 10 The mechanical vacuum pump was started t thisa,000 uci/sec time to purgeat thethe time of separators, moisture the event) and the change is due to mechanical vacuum pump flog Airborne activity _fn the air ejector room increased slightly (from 8.8 x 10~ uci/cc to 1.7 x 10 uci/cc),
and ihe reactor buiIding venti 1ation radiation monitors did not show any change in ventilation air activity.
The rupture diaphragms on ihe sicam jet air ejector discharge ruptured io relieve the internal pressure created by the explosion and protected the air ejectors from any overpressure damage. The relative location of the air ejectors, rupture diaphragms, and the off-gas pipe protected the air ejectors from the j shock wage. The shock wave would have to follow a 180 bend in the pipe (a tee, '
and a 90 elbow) to enter the air ejector after condenser, but would only have to follow a straight pipe to impact on the rupture diaphragm.
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One pressure switch (PS-1921) used to cause isolation of the off-gas suction valves on high pressure was damaged by the explosion. The remaining iristrumentation connected to the off-gas systm has been tested and found to be in good working order.
, inspection and testing performed on the off-gas system has detected no damage.
l The air ejector condensers have been hydrostatically tested, the off-gas piping l from the air ejectors to the inlet of the stack off gas filters has been pressur-l ized with air and the leakage rate measured, the stack HEPA filters have been tested with DOP, and ultrasonic testing has been performed on welds at pipe t elbows. The piping system has been visually inspected for signs of pipe movement and none can be found.
L General Electric Company and Bechtel Corporation have been involved in the review of the occur rence. Representatives of these two companies support our conclusion that the piping systen has not been damaged.
Two changes will be made as a result of this occurrence. It was found that the off-gas system suction valves ( A01083A & B,1084A & B) isolation logic does not
" seal in" on trip action. The logic circuit will be changed to " seal in" and requirc operator action to reset an isolation. (Note that the isolation of these valves {
was meaningless with respect to this occurrence, since the explosion occurred on the discharge side of the air ejectors, and the manual valves at the air ejectors were closed. The off gas system suction valves are located between the air ejectors and the condenser, or on the suction side of the air ejectors.)
l A procedure will be prepared to purge the off gas line prior to maintenance on the system. This procedure will become a part of the Operations Manual.
Based on all findings, the off-gas system damage was limited to the rupture j diaphragms, and the one pressure switch. These components will be replaced '
before the plant is returned to service. This information has been made available to the Compliance inspector. An Event report has been written and will be reviewed by the Safety Audit Committee. l Yours very truly, h.h L. O. Mayer Director of Nucle.ar Support Services LOM/GHJhrrn
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