ML20002C150

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Forwards IE Info Notice 80-40, Excessive Nitrogen Supply Pressure Actuates Safety-Relief Valve Operation to Cause Reactor Depressurization. No Written Response Required
ML20002C150
Person / Time
Site: Callaway  Ameren icon.png
Issue date: 11/07/1980
From: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Bryan J
UNION ELECTRIC CO.
References
NUDOCS 8101090421
Download: ML20002C150 (2)


Text

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UNITED STATES

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GLEN ELLYN.1LUNol5 6o137 November 7, 1980 Those on Attached Address Listing:

This IE Information Notice No. 80-40 is provided as an early notification of a possibly significant matter.

It is expected that ret tients will review the information for possible applicability to their facilities.

No specific action or response is requested at this time.

If further NRC evaluations so indicate, an IE Circular or Bulletin will be issued to recommend or request specific licensee actions.

If you have questions regarding this matter, please contact this office.

Sincerely, LQ.

James G. Keppler v Director

Enclosure:

IE Information Notice No. 80-40 cc w/ enc 1:

l Mr. D. W. Kane, l

Sargent & Lundy Mr. Gary N. Wright, Chief 1

Division of Nuclear Safety l

Reproduction Unit NRC 20b l

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RIII'o CORPORATE ADDRESSES FOR OPERATING LICENSEES AND CONSTRUCTION PERMIT HOLDERS (BWR's and PWR's)

Docket No. 50-346 Toledo Edison Company ATTN: Mr. Richard P. Crouse

's Vice President Nuclear c

Edison Plaza r-300 Madison Avenue f2

'f Toledo, OH 43652 3

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Mr. T. Murray, Station

-i I:T!

Superintendent I4

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'i3 Central Files G

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J Director, NRR/DPM Director, NRR/ DOR AEOD Resident Inspector, RIII PDR Local PDR NSIC TIC Harold W. Kohn, Power Siting Commission Helen W. Evans, State of Ohio Docket No. 50-483 Docket No. 50-486 Union Electric Company ATTN:

Mr. John K. Bryan Vice President - Nuclear P. O. Box 149 St. Lecis, MO 63166 cc w/ encl:

Mr. W. H. Weber, Manager, clear Construction ral Files trector, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Region I & IV Ms. K. Drey Mr. Ronald Fluegge, Utility Division, Missouri Public Service Commission

RlI2's CORPORATE ADDRESSES FOR OPERATING LICENSEES AND CONSTRUCTIOB PERMIT HOLDERS (BWR's and PWR's)

Docket No. 50-266 Docket No. 50-301 Wisconsin Electric Power Company ATTN: Mr. Sol Burstein Executive Vice President Power Plants 231 West Michigan Milwaukee, WI 53201 cc w/cael:

Mr. G. A. Reed, Plant Local PDR Manager NSIC Central Files TIC Director, NRR/DPM Sandra A. Bast, Lakeshore Director, NRR/ DOR Citizens for Safe Energy Timothy Colburn, ORB /NLR Mr. John J. Duffy, Chief AEOD Boiler Inspector Resident Inspector, RIII Mr. Peter Anderson, Wisconsin's PDR Environmental Decade Docket No. 50-305 Wisconsin Public Service Corporation ATTN:

Mr. E. R. Mathews Vice President Power Supply and Engineering P. O. Box 1200 Green Bay, WI 54305 cc w/ enc 1:

D. C. Hintz, Plant AEOD Superintendent Resident Inspector, RIII Mr. W. Sayles, Chief PDR Engineer Local PDR Central Files NSIC Director, NRR/DPM TIC Director, NRR/ DOR Mr. John J. Duffy, Chief Boiler Inspector

RIII'S CORPORATE ADDRESSES FOR OPERATING LICENSEES AND CONSTRUCTION PERMIT HOLDERS (BWR's and PWR's)

Docket No. 50-315 Docket No. 50-316 American Electric Power Service Corporation Indiana and Michigan Power Company ATTN:

Mr. John E. Dolan Vice Chairman Engineering and Construction 2 Broadway New York, NY 10004 cc w/ encl:

Mr. D. V. Shaller, Plant Manager j

Central Files Director, NRR/DPM Director, NRR/ DOR AEOD Resident Inspector, RIII PDR Local PDR NSIC TIC Ronald Callen, Michigan Public Service Corporation 1

4 t

RIIH's CORPORATE ADDRESSES FOR OPERATING LICENSEES AND CONSTRUCTION PERMIT HOLDERS (BWR's and PWR's)

Docket Nos. 50-10, 50-237, 50-249; 50-254, 50-265; 50-295, 50-304; 50-373, 50-374; 50-454, 50-455; 50-456 and 50-457 Commonwealth Edison Company ATTN:

Mr. Cordell Reed, Vice President Post Office Box.767 Chicago, IL 60690 cc r/ enc 1:

Mr. J. S. Able, Director Mr. Gunner Sorensen, Site of Nuclear Licensing Project Superintendent Mr. D. J. Scott, Station Mr. R. Cosaro, Project Superintendent Superintendent Mr. N. Kalivianakis, Mr. J. F. Gudac, Station Station Superintendent Superintendent Mr. K. Graesser, Station Central Files Superintendent Director, NRR/DPM Mr. L. J. Burke, Site Director, NRR/ DOR Construction Superintendent AE0D Mr. T. E. Quaka, Quality Resident Inspectors, RIII Assurance Supervisor PDR Mr. R. H. Holyoak, Station Local PDR Superintendent NSIC Mr. B. B. Stephenson, TIC Project Manager Mr. Dean Hansell, Office of Mr. V. I. Schlosser, Assistant Attorney General Project Manager Myron M. Cherry, Chicago Mr. R. E. Querio, Station Superintendent Docket No. 50-358 Cincinnati Gas and Electric 3

Company ATTN:

Mr. Earl A. Borgmann Senior Vice President Engineering Services and Electric Production 139 East 4th Street Cincinnati, OH 45201 cc w/ encl:

Mr. J. R. Schott, Plant Local PDF Superintendent NSIC Central Files TIC Director, NRR/DPM Harold W. Kohn, Power Director, NRR/ DOR Siting Commission AEOD Citizens Against a Radioactive i

Resident Inspector, RIII Environment PDR Helen W. Evans, State of Ohio l

1

RIII's CORPORATE ADDRESSES FOR OPERATING LICENSEES AND CONSTRUCTION PERMIT HOLDERS (BWR's cnd PWR's)

Docket No. 50-440 Docket No. 50-441 The Cleveland Electric Illuminating Company ATTN: Mr. Dalwyn R. Davidson Vice President - Engineering P. O. Box 5000.

Cleveland, OH 44101 cc w/ enc 1:

Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Harold W. Kohn, Power Siting Commission Mr. Daniel D. Wilt, Attorney Helen Evans, State of Ohio Docket No. 50-155 Docket No. 50-255 Consumers Power Company ATTN:

Mr. R. B. DeWitt Vice President Nuclear Operations 212 West Michigan Avenue Jackson, MI 49201 cc w/ enc 1:

Mr. D. P. Hoffman, Nuclear Resident Inspectors, RIII Licensing Administrator PDR Mr. C. J. Hartman, Local PDR Plant Superintendent NSIC Mr. R. W. Montross, Manager TIC Central Files Ronald Callen, Michigan Director, NRR/DPM Public Service Commission Director, NRR/ DOR Myron M. Cherry, Chicago AEOD

RIII'o C0kPORATE ADDRESSES FOR OPERATING LICENSE 1 LMD CONSTRt'CT10?4 PERMIT HOLDERS (BWR's and PWR's)

Docket No. 50-329 Docket No. 50-330 Consumers Power Company ATTN:

Mr. James W. Cook Vice President Midland Project 1945 West Parnall Road Jackson, MI 49201 cc w/ encl:

Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Ronald Callen, Michigan Public Service Commission Myron M. Cherry, Chicago Docket No. 50-409 Dairyland Power Cooperative ATTN:

Mr. F. W. Linder General Manager 2615 East Avenue - South La Crosse, WI 54601 cc w/ encl:

Mr. R. E. Shimshak, Plant Superintendent Central Files Director, NRR/DPM Director, NRR/ DOR AEOD Resident Inspector, RIII PDR Local PDR NSIC TIC Mr. John Duffy, Chief Boiler Inspector

RIII's CORPORATE ADDRESSES FOR OPERATING LICENSEES AND CONSTRUCTION PERMIT HOLDERS (BWR's and PWR's)

Docket No. 50-341 The Detroit Edison Company ATTN:

Mr. Edward Hines, Assistant Vice President and Manager Quality Assurance 2000 Second Avenue Detroit, MI 4&226 cc w/ enc 1:

Central Files Director, NRR/DPM Director, NRR/ DOR AEOD Resident Inspector, RIII PDR Local PDR NSIC TIC Ronald Callen, Michigan Public Service Commission Eugene B. Thomas, Jr.,

Attorney Docket No. 50-461 Docket No. 50-462 Illinois Power Company ATTN:

Mr. W. C. Gerstner Executive Vice President 500 South 27th Street Decatur, IL 62525 cc w/ encl:

Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Mr. Dean Hansell, Office of Assistant Attorney General Mr. Gary N. Wright, Chief Division of Nuclear Safety w

RIII's CORPORATE ADDRESSES FOR OPERATING LICENSEES AND CONSTRUCTION PERMIT HOLDERS (BWR's and PWR's)

Docket No. 50-331 Iowa Electric Light and Power Company AT7N: Mr. Duane Arnold President IE Towers P. O. Box 351 Cedar Rapids, IA 52406 cc w/ encl:

D. Mineck, Chief Engineer Central Files Director, NRR/DPM Director, NRR/ DOR AEOD Resident Inspector, RIII PDR Local PDR NSIC TIC Docket No. 50-367 Northern Indiana Public Service Company ATTN:

Mr. Eugene M. Shorb Senior Vice President 5265 Hohman Avenue Hammond, IN 46325 cc w/enel:

Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Mr. Dean Hansell, Office of Assistant Attorney General

XIII'c CORPORATE ADDRESSES TOR OPERATING LICENSEES AND CONSTRUCTION PERMIT HOLDERS (BWR's and PWR's)

Docket No. 50-263 Docket No. 50-282 Docket No. 50-306 Northern States Power Company ATTN:

Mr. Dennis E. Gilberts Vice President Power Production and System Operation 414 Nicollet Mall Minneapolis, MN 55401 cc w/ encl:

Mr. W. A. Shamla, Resident Inspectors, RIII Plant Manager PDR Mr. F. P. Tierney, Jr.,

Local PDR Plant Manager NSIC Central Files TIC Director, NRR/DPM John W. Ferman, Ph.D.,

Director, NRR/ DOR Nuclear Engineer, MPCA AEOD Docket No. 50-546 Docket No. 50-547 Public Service of Indiana ATTN:

Mr. S. W. Shields Senior Vice President Nuclear Division Post Office Box 190 New Washington, IN 47162 cc w/ encl:

Mr. Steve J. Brewer, Nuclear TIC Safety and Licensing Supervisor LeBoeuf, Lamb, Leiby & MacRae Central Files Mr. Dave Martin, Office of the Director, NRR/DPM Attorney General l

Directar, NRR/ DOR Mr. John R. Galloway, Staff PDR Director, Environment, Energy Local PDR and Natural Resources Subcommittee NSIC l

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i i UNITED STATE ui 008220269 NUCLEAR REGULATORY COMMISSION IN 80 OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 November 7, 1980 IE Information Notice No.: 80-40:

EXCESSIVE NIROGEN SUPPLY PRESSURE ACTUATES SAFETY-RELIEF VALVE OPERATION TO CAUSE REACTOR DEPRESSURIZATION Description of Circumstances:

On October 7 and 31, 1980, the reactor coolant system was spuriously depres-surized at Boston Edison Company's Pilgrim Nuclear Power Station Unit No.1.

The Pilgrim Station Unit 1 uses a GE BWR. The depressurizations resulted when excessive. pressure in the nitrogen supply system caused the "A" Target Rock (TR) safety relief valve to open and remain open until the excessive supply pressure could be isolated, pneumatic operator pressure vented and the main steam system depressurized sufficiently to allow the main disk to reseat.

These two events involved a failure in the pressure regulation of the supply nitrogen and not a failure of the TR safety-relief valve to function as designed.

The safety-relief valves at Pilgrim are designed to be supplied, with other drywell instrumentation, from either the compressed air system or containment atmosphere control system (CACS). The CACS uses nitrogen for containment inerting.

The supply for the safety-relief valves is provided from the CACS through an ambient air vaporizer and then through one of two parallel pressure regulators or a parallel bypass line.

Shortly before the time of each event a new supply of liquid nitrogen had been added to the storage tanks. At the time of the events the two pressure regulators were in service with the bypass closed.

Nitrogen pressure supplying the valves increased to 160 - 165 psi.

This may have been caused by liquid nitrogen reaching the pressure regulators or by a failure in a pressure regulator.

The result was excessive pressure which was sufficient to leak through the solenoid actuator and initiate the pneumatic operator of the safety-relief valve.

The design normal operating pressure of the compressed air or nitrogen systems supplying the safety-relief valves is90-110 psi.

At a pressure of 145 psi the solenoid valve may begin to leak since excessive pressure acts to unseat the disk. The supply pressure must then decrease to 135 psi or less for the solenoid disk to reseat.

In addition, the design of the safety-relief valve is such that as the main steam pressure increases, less instrument pressure is necessary to initiate the pneumatic operator. Approximately 3 to 5 psi at the pneumatic operator is sufficient to initiate the safety-relief valve opening.

Such a pressure begins to build with leakage through the solenoid actuator and was reached in the "A" valve at 160 psi supply pressure.

According to information from GE and TRC, approximately 180 psi pressure is necessary for all of the safety-relief valves to open as result of supply overpressure.

It would appear that under such conditions of overpressure that safety-relief valve openings would be sequential rather than simultaneous.

The particular solenoid actuator valves used with these two-stage safetyrelief valves are manufactured by TRC.

Their design is such that excessive control pressure tends to unseat the solenoid valve disk. The three-stage TR safety-relief valves use either AVC0 (Automatic Valve Company) or ASCO (Automatic Switch Company) solenoid valves according to information from GE.

The AVCo solenoid

o IN 80-40 November 7, 1980 Page 2 of 2 valve has been tested to 300 psi and found not to leak and the ASCo solenoid valve tends to seat with increasing supply pressure. Therefcre, the NRC believes that the tendency for solenoid leakage and hence safety-relief valve opening is conf.ined to the two-stage safety-relief valve installations.

This information is provided as a notification of a possibly significant matter which is still under review by the NRC staff.

It is anticipated that the results of continuing NRC review will culminate in issuance of an IE Bulletin which will recommend or require specific licensee action.

In the interim, we expect that recipients will review the information for possible applicability to their facilities, particularly those with installations of the TR two-stage safety-relief valves.

If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.

9

,, -. ~ -

IN 80-40 November 7, 1980 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No.

Subject Issue Issued to 80-39 Nalfunctions Of Solenoid 10/31/80 All light water reactor Valves Manufactured By facilities holding Valcor Engineering Corporation power reactor OLs or cps 80-38 Cracking In Charging Pump 10/30/80 All PWR facilities Casing Cladding with an OL or CP 80-37 Containment cooler leaks 10/24/80 All nuclear power and reactor cavity facilities holding flooding at Indian Point power reactor OLs Unit 2 or cps 80-36 Failure of Steam 10/10/80 All nuclear power Generator Support Bolting reactor facilities holding power reactor OLs or cps 80-35 Leaking and dislodged 10/10/80 All categories G and Iodine-124 implant seeds G1 medical licensees 80-34 Boron dilution of reactor 9/26/80 All pressurized water coolant during steam reactor facilities generator decontamination holding power reactor OLs 80-33 Determination of teletherapy 9/15/80 All teletherapy timer accuracy (G3) licensees 80-32 Clarification of certain 8/12/80 All NRC and agreement requirements for Exclu-state licensees sive-use shipments of radioactive materials 80-31 Maloperation of Gould-8/27/80 All light water reactor Brown Boveri Type 480 facilities holding OLs volt type K-6005 and or cps K-DON 6005 circuit breakers 1

  • Operating Licenses or Construction Permits 1

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