ML17179B070

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Discusses Schedule for Licensee Response to GL 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance
ML17179B070
Person / Time
Site: Dresden, Byron, Braidwood, Quad Cities, Zion, LaSalle  Constellation icon.png
Issue date: 09/09/1993
From: Dyer J
Office of Nuclear Reactor Regulation
To: Delgeorge L
COMMONWEALTH EDISON CO.
References
GL-89-10, IEB-85-003, IEB-85-3, NUDOCS 9309160020
Download: ML17179B070 (5)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Docket Nos. STN 50-454, STN 50-455 STN 50-456, STN 50-457 50-237, 50-249, 50-373 50-374, 50-254, 50-265 50-295, and 50-304 Mr. L. 0. DelGeorge Vice President of Nuclear Operations Commonwealth Edison Company Executive Towers West Ill, Suite 500 1400 opµs Place Down~rs Grove, Illinois 60515

Dear Mr. DelGeorge:

September 9, 1993

SUBJECT:

SCHEDULE FOR COMMONWEALTH EDISON RESPONSE TO GENERIC LETTER 89-10, "SAFETY-RELATED MOTOR-OPERATED VALVE TESTING AND SURVEILLANCE" On ~une 28, 1989, the NRC issued Generic Letter (GL) 89-10, "Safety-Related Motor-Operated Valve Testing and Surveillance," requesting that licensees establish a program to verify the design-basis capability of safety-related motor-operated valves (MOVs) and certain other MOVs in safety-related systems in nuclear power plants.

In GL 89-10, th~ NRC requested that licensees complete the verification of the design-basis capability of MOVs within the scope of the generic letter by June 28, 1994, or the third refueling outage after December. 28, 1989 (whichevei was later}.

On September 28, 1990, following discussions with the NRC staff, Commonwealth Edison Company (CECo) submitted its plan for responding to GL 89-10.

In that submittal, it was stated that the corporate MOV program developed in response to NRC Bulletin 85-03 would be expanded to address the recommended actions of GL 89-10.

At that time, CECo had determined a total of 1540 MOVs at its 12 nuclear units to be within the scope of GL 89-10 and of these, 1090 had been categorized as Priority 1 MOVs (those that were required to (a) ensure adequate core cooling, ensure reactor shutdown, or minimize consequences of a high energy line break, or (b) mitigate accidents described in the Final*

Safety Analysis Report or other events covered in the Emergency Operating Procedures).

The remaining MOVs in the program were categorized.as Priority 2. Other actions CECo committed to were:

1) to statically test all MOVs in safety-related systems using diagnostic equipment; 2) to test these MOVs under full differential pressure using diagnostics where practicable;
3) to assign the highest priority to the most critical valves for design-basis review and for scheduling of testing; and 4) to utilize analytical correlations between static test data and industry full dynamic test data to verify correct MOV torque switch settings (correlations between different CECo stations, or between other utilities* and te-st facilities would be included).

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Mr. L. 0. DelGeorge September 9, 1993 In the September 1990 submittal, CECo stated that its implementation of the program would reflect its corporate objective of focusing limited discretionary resources such that improvement in plant safety and reliability was maximized.

Consequently, CECo's schedule for its HOV program extended significantly beyond the reconunended schedule in GL 89-10. Specifically, CECo stated that design-basis reviews, static and practicable dynamic testing for Priority 1 MOVs would be completed by the end of the third refueling outage per unit beginning with the Spring 1991 outages and that activities for Priority 2 MOVs would be completed by the end of the fifth refueling outage per unit beginning with 1991 outages.

For MOVs that could not be in situ tested, analytical correlations between static and dynamic test data would be completed within the respective schedule for their assigned priority.

CECo has contended that its longer schedule should result in' only a marginal reduction in the net benefit resulting from the generic letter action items.

In the NRC staff's reply (dated January 23, 1991} to your response to GL 89-10, the staff accepted the schedule for your response to GL 89-10, but requested that you make every effort to complete the first stage of the two-stage approach (that is, setting MOVs using the best available information}

for all GL 89-10 MOVs within the schedule recommended in the generic letter.

Since then, the nuclear industry has identified significantly more problems with the performance of MOVs thari the staff believed to exist when GL 89-10 was issued.

The most widespread problem involves the design weakness resulting from the underprediction of the thrust required to operate gate valves during the sizing and setting of their motor operators. Therefore, the staff has been conducting inspections at nuclear power plants to ensure that licensees are making progress toward resolving the MOV issue in a timely manner.

The staff has conducted inspections to review the programs being developed at each CECo nuclear power station. Recently, the staff initiated inspections of the implementation of those programs.

During these inspections, the staff raised concerns regarding the safety focus of the programs, the management control over the programs, and several important technical issues related to ensuring the design-basis capability of your safety-related MOVs.

The staff hai met several times with CECo to discuss the staff concerns and your plans to improve the GL 89-10 programs at CECo facilities.

As discussed during a meeting in the NRC Region III office on August 26, 1993, the staff believes that CECo has not satisfied the commitments made in its September 1990 response to GL 89-10 or the assumptions m~de by the staff in accepting CECo's extended schedule for responding to GL 89-10.

In particular, the staff found that CECo:

l} has not implemented its programs such that Priority 1 MOVs are tested in advance of lower priority MOVs; 2} has not attempted to complete the first stage of the two-stage approach within the GL 89-10 recommended schedule; 3} has not incorporated either the findings of significant MOV problems or the test data identified at CECo and other nuclear plants into the methodology for ensuring the adequate sizing and setting of MOVs; and 4} continues to use an outdated valve factor of 0.3 in its methodology for sizing and setting many gate valves despite CECo and industry

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-. Mr.

L~ 0. Del George

  • september* 9.,> 1993.~

testing_ that revealS this valv'e factor to b.e inaq~qiJate.for general use.

(During th.e Augusf'-26, 1993 meeting, CECo sta.ted that.it recently began

  • ass,umi ng a*.0. 55 valve factor for *west i nghouse gate. valves.)

During the.

inspections, t~e staff found.CECo-to be -reduci,_ng the number of MOVs to be*..

,dynamica-lly te~ted from*the large number Charac;terized.by CECo in*meetings** *

  • with the staff when if accepted the* CECo schedule..

Further; CE Co ha,s not

~tested **any MOVs. under dynamic.conditions at th~ Dresden station in response to**

GL 89-°IO,,.. Based* 011 these* fi hdi rigs,* it appears that the CE Co.schedule will result* iri a mu¢h la~ger.reduction in safety benefit than CECo.asserted.when

  • the staff accepted the extended CECo schedule for.responding to GL 89-10 in*

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.. *Based On the *above -concern~, the.. s.taff requests th.at CECo resubmit.

. :justification.for the scheduTe*~for its. response.to GL. 89.,.10 within 45 days of

-.rece1pt of:thi_s:letter.

As" part of that*submittal,"th~ staff requests CECo to-.

provide.a statu.s o_f its:static_t,esting of.the MOVs.withiri its GL 89.-10 program

  • to set the MOVs using the best avai.lable information-.such that CECo can affirm their des.ign-basis ;capability __ J As previously. discussed, th~ staff. does not.*

'. ::c'onsid'er 'a.0.. 3 ~al~e factor :.to.*represent. "the best. av.a-ilable infcirmatiotf.for

.v~fifying thE?.. d~sig*n~basis cap.ability.of gate.valves.

The staff::Will evaluate**

... the _feq1.:1.ested Jrifopitat ion' to. det~_rmi r:ie whether CECo' s extended ;tSC~~dul e: for.

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r.esponding-to**GL":.8~~-10 continues to be acceptable..

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  • .\\ES/NO YES/NO YES/NO

Mr. L. 0. DelGeorge cc:

Mr. William P. Poirier Westinghouse Electric Corporation Energy Systems Business Unit Post Office Box 355, Bay 236 West

  • Pittsburgh, Pennsylvania 15230 Joseph Gallo, Esquire Hopkins and Sutter 888 16th Street, N.W., Suite 700 Washington, D.C. _20006 Regional Administrator U. S. NRC, Region III 799 Roosevelt Road, Bldg. #4 Gle~ Ellyn, Illinois 60137 Ms. Bridget Little Rorem Appleseed Coordinator 117 North Linden Street Essex, Illinois 60935 Mr. Edward R. Crass Nuclear Safeguards and Licensing Division Sargent & Lundy Engineers 55 East Monroe Street Chicago; _Illinois 60603

. U.

S~ Nuclear Regulatory Commission Resident Inspectors Office Rural Route #1, Box 79 Braceville, Illinois 60407 Mr. R*on Stephens, Di rector Illinois Emergency Services and Disaster Agency 110 East Adams Street Springfield, Illinois 62706

  • Robert Neumann Office of Public Counsel State of Illinois Center 100 W. Randolph, Suite 11-300 Chicago, Illinois. 60601 EIS Review Coordinator Environmental Protection Agency Region V 230 S. Dearborn Street Chicago, Illinois 60604 Attorney General 500 South 2nd Street Springfield, Illinois 62701 Conunonwealth Edison Company U. S. Nuclear Regulatory Commission Byron Resident Inspectors Office 4448 North German Church Road Byron, Illinois 61010-9750 Ms. Lorraine Creek Rt. 1, Box 182 Manteno, Illinois 60950 Mrs. Phillip B; Johnson 1907 Stratford Lane Rockford, Illinois 61107 Douglass Cassel, Esquire 17 East Monroe Street, Suite 212
  • .Chicago, Illinoh 60603.

U. S. Nuclear Regulatory Commission Resident Inspe~tors Offi~e 105 Shiloh Blvd.

Zion, Illinois 600Q9 George L. Edgar Newman & Ho ltzi nger, P. C..

. 1615 L Street~ N.W.

Washington, D.C.

20036 Commonwealth Edison Company

'Byron Station Manager 4450 North German Church Road Byron, Illinois 61010 Illinois Dept. of Nucl~ar Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704*

Commonwealth Edison Company Braidwood*Statiori Manager.*

Rt. 1, Box 84.:

Braceville, Illinois 60407 Chairman, Ogle County Board Post Office Box 357

.Oregon, Illinois 61061 Chairman Will County Board of Supervisors Will County Board Courthouse Joliet, Illinois 60434 Mayor of Zion Zion, Illinois 60099

Mr. L. 0. DelGeorge Michael I. Miller, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60690 Mr. G. Spedl Plant Manager Dresden Nuclear Power Station Rural Route #1 Morris, Illinois 60450 U. S. Nuclear Regulatory Commission

.Resident Inspectors Office Dresden Station 6500 North Dresden Road*

Morris, Illinois. 60450-9766 Chairman Board of Supervisors of Grundy County Grundy County Courthouse

  • Morris, Illirtois 60450 Phillip P. Steptoe, Es~uire Sidley and Austin One First National Plaza Chicago, Illinots 60603 Assistant Attorney General 100 West Randolph Street Suite 12 Chicago, Illinois 60601 Resident Inspector/LaSalle, NPS U. S. Nuclear Regulatory Commission Rural Route No. 1 P. 0. Box 224 Marseilles, Illinois 61341
  • Chairman LaSalle County Board of Supervis9rs LaSalle County Courthouse Ottawa, Illinois 61350 Dr. Cecil Lue-Hin~
  • Director of Research and Development Metropolitan Sanitary District of Greater Chicago 100 East Erie Street Chicago, Illinois 60611 Robert Cushing Chief, Public Utilities Division Illinois Attorney General's Office 100 West Randolph Street Chicago, Illinois 60601 Mr. G. Diederich LaSalle Station Manager LaSalle County Station Rural Route 1 P. 0. Box 220 Marseilles, Illinois 61341 Chairman Illinois Commerce. Comrnission Leland Building 527 East Capitol Avenue Springfield, Illinois 62706 Mr. Stephen E. Shelton Vice. President Iowa-11 l fnoi s Gas and Electric Company P. O. Box 4350 Davenport, Iowa 52808 Mr. Richard Bax Station Manager Quad Cities Nuclear Power Station 22710 206th Avenue North Cordova, Illinois 61242 Resident Inspector
  • U~ S. Nuclear Regulatory Commission 22712 206th Avenue North Cordova, Illinois 61242*

Chairman Rock Island County Board of Supervisors 1504 3rd,, Avenue Rock Island County Office Bldg.

Rock Island, Illinois 61201 Mr. D. L. Farrar Manager, Nuclear Regulatory Services Commonwealth Edison Company Executive Towers West Ill, Suite 500 1400 OPUS Place Downers Grove, Illinois 60515

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