IR 05000483/1999004

Refers to GL 96-05 Issued by NRC on 960918,UE Responses & 970313 & NRC Insp Rept 50-483/99-04,dtd 990427. Forwards Request for Addl Info Re GL 96-05 Program at Callaway Plant,Unit 1

ML20212H837
Person / Time
Site:	Callaway
Issue date:	06/18/1999
From:	Mel Gray NRC (Affiliation Not Assigned)
To:	Randolph G UNION ELECTRIC CO.
References
50-483-99-04, 50-483-99-4, GL-96-05, GL-96-5, TAC-M97027, NUDOCS 9906280176
Download: ML20212H837 (4)

Text

yxI

'~

.

Mr. Grrry L. Rrndolph June 18, 1999'

>'

Vice President End Chief Nuclerr Officer

'

, Union Electric Ccmprny

'

Post Office Box 620 Fulton, MO ' 65251'

.

SUBJECT: - REQUEST FOR ADDITIONAL INFORMATION - GENERIC LETTER 96-05,

!- " PERIODIC VERIFICATION OF DESIGN-BASIS CAPABILITY OF SAFETY-RELATED MOTOR-OPERATED VALVES," CALLAWAY PLANT, UNIT 1 (TAC NO. M97027) .

Dear Mr. Randolph:

. .

i On September 18,1996, the NRC issued Generic Letter (GL) 96-05, " Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves," to request that nuclear power plant licensees establish a program, or ensure the effectiveness of a current program, to ,

'

verify on a periodic basis that safety-related motor-operated valves continue to be capable of performing their safety functions within the curre; t licensing basis of the facility.

. By letters da'ed t November 6,1996, and March 13,1997, Union Electric Company (UE)

provided to the NRC. staff responses to GL 96-05. On March 29 through April 2,1999, the NRC staff conducted an inspection of the GL 96-05 program at Callaway Plant, Unit 1. The staff documented the results of that inspection in NRC Inspection Report (IR) 50-483/99-04, dated

April'27,1999.

Based on a review of UE's submittals and the results documented in IR 50-433/99-04, enclosed

!s a request for additional information. The staff has determined that this additional information is required to complete our review. This information request was discussed with UE staff members on June 15,1999. A 30-day response time from the date UE receives this letter was agreed upon.

If you have any questions, please contact me at (301) 415-3021.

Sincerely, S. Dembek /s/ for

, Mel Gray, Project Manager, Section 2 9906280176 990618 Project Directorate IV & Decommissioning DR MM0 Division of Licensing Project Management p

Office of Neclear Reactor Regulation Docket No.-50-483 Enclosure: Request for AdditionalInformation ccw/ encl: See next page IRC FR.F CBHS COM /

DISTRIBUTION Docket File SRichards-- TScarbrough r

- \,g\

PUBLIC - OGC- DGraves, RGN-IV PDIV-2 Reading '

ACRS SBlack DTerso To secome a copy or sus cocumern, mecate y m me cox OFFICE - PDIV-2/PM C PDIV-2/LA . C PDIV-2/SC NAME MGray:[ EPI)kOf SDembek DATE 6 //f '/99 G2 I '. 9 /99 [o //b99 -

DOCUMENT NAME: G:\PDIV-2\Callaway\RAl97027.WPD c7 r o rjg OFFICIAL RECORD COPY e >

'

,

,

.

• Af?

1. '

p UNITED STATES

! g

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. - *1

,

% June 18,1999 Mr. Garry L Randolph Vice President and Chief Nuclear Officer Union Electric Company Post Office Box 620 i Fulton, MO 65251 SUBJECT: REQUEST FOR ADDITIONAL INFORMATION - GENERIC LETTER 96-05, .

" PERIODIC VERIFICATION OF DESIGN-BASIS CAPABILITY OF SAFETY- I'

RELATED MOTOR-OPERATED VALVES," CALLAWAY PLANT, UNIT 1 '

(TAC NO. M97027)

Dear Mr. Randolph:

On September 18,1996, the NRC issued Generic Letter (GL) 96-05, " Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves," to request that nuclear power olant licensees establish a program, or ensure the effectiveness of a current program, to verify .,n a periodic basis that safety-related motor-operated valves continue to be capable of performing their safety functions within the current licensing basis of the facility.

By letters dated November 6,1996, and March 13,1997, Union Electric Company (UE)

provided to the NRC staff responses to GL 96-05. On March 29 through April 2,1999, the NRC staff conducted an inspection of the GL 96-05 program at Callaway Plant, Unit 1. The staff documented the results of that inspection in NRC Inspection Report (IR) 50-483/99-04, dated April 27,1999.

.

Based on a review of UE's submittals and the results documented in IR 50-483/99-04, enclosed

'

is a request for additionalinformation. The staff has determined that this additional information is required to complete our review. This information request was discussed with UE staff members on June 15,1999. A 30-day response time from the date UE receives this letter was agreed upon.

If you have any questions, please contact me at (301) 415-3021.

Sincerely, Mel ray, Project Manag , bion 2 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-483 Enclosure: Request for AdditionalInformation cc w/enct See next page

E.

l

\

Callaway Plant, Unit 1

.

cc:

Professional Nuclear Mr. Otto L. Maynard Consulting, Inc. President and Chief Executive Officer 19041 Raines Drive

,

Wolf Creek Nuclear Operating Corporation l Derwood, Maryland 20855 Post Office Box 411 Burlington, Kansas 66839 John O'Neill, Esq. - !

Shaw, Pittman, Potts & Trowbridgg Mr. Dan 1. Bolef, President 2300 N. Street, N.W. Kay Drey, Representative Washington, D.C. 20037 Board of Directors Coalition for the Environment Mr. H. D. Bono 6267 Delmar Boulevard Supervising Engineer University City, Missouri 63130 Quality Assurance Regulatory Support i Union Electric Company Mr. Lee Fritz Post Office Box 620 Presiding Commissioner Fulton, Missouri 65251 Callaway County Court House '

10 East Fifth Street

.U.S. Nuclear Regulatory Commission Fulton, Missouri 65151 Resident inspector Office 8201 NRC Road Mr. Alan C. Passwater, Manager Steedman, Missouri 65077-1302 Licensing and Fuels l Union Electric Company Mr. J. V. Laux, Manager Post Office Box 66149 Quality Assurance St. Louis, Missouri 63166-6149 Union Electric Company Post Office Box 620

'

Fulton, Missouri 65251 Manager- Electric Department Missouri Public Service Commission 301 W. High Post Office Box 360 Jefferson City, Missouri 65102 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower & Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 -

Mr. Ronald A. Kucera, Deputy Director Department of Natural Resources P.O. Box 176 '

Jefferson City, Missourl 65102 r

e~~4 .#-- . ,.. ++ - ,, .

,

.

.

i REQUEST FOR ADDITIONAL INFORMATION REGARDING RESPONSE TO GENERIC LETTER 96-05

" PERIODIC VERIFICATION OF DESIGN-BASIS CAPABILITY OF SAFETY-RELATED MOTOR-OPERATED VALVES" CALLAWAY PLANT. UNIT 1 DOCKET NO. 50-483 In NRC Inspection Report (IR) 50-483/99-04, the NRC staff was unable to determine, based on a sample review, that the licensee's motor-operated valve (MOV) setup methodology, with the licensee's assumed 25% margin, would be sufficient to bound potential age and service-related degradation over the operating life for MOVs in the program established at Callaway Plant, Unit 1 in response to Generic Letter (GL) 96-05, " Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves."

Similar to the information provided to the NRC inspectors during IR 99-04 for the sample review, the staff requests that Union Electric Company (UE) provide the data necessary for the NRC staff to calculate, for each GL 96-05 MOV at Callaway Plant, Unit 1, the " required valve factor" and "available valve factor that would be applied in the MOV standard industry sizing equation to yield the thrust requirements and capabilities equivalent to the licensee's methodology. Information for the " required valve factor" calculation includes, for example, valve size, type, manufacturer, and mean seat diameter; design-basis differential pressure and system pressure; measured or assumed packing load; pullout thrust and torque; measured or calculated design-basis thrust and torque requirements; and diagnostic error. Information for the "available valve factor" calculation includes, for example, stem diameter, pitch, lead, and friction coefficient; closing thrust and torque at control switch trip (torque or limit control);

diagnostic error; rate-of-loading assumptions; motor rated starting torque; application factor; actuator pullout efficiency; overall actuator ratio; design-basis minimum motor voltage; rated motor voltage; attemating or direct current specification; and ambient temperature degradation factor. Some of the above information might not be applicable to certain MOVs because of valve type, setup, or other considerations.

.

ENCLOSURE

. . - _ - . - - . . - -