ML20052A384

Significant Deficiency Rept SD 413-414/82-09 Re Potential Undersizing of Electric Motor Operators for Westinghouse Gate Valves Per IE Bulletin 81-02,Suppl 1,initially Reported 820312.Final Rept Re Corrective Actions Expected by 820617

ML20052A384
Person / Time
Site:	Catawba
Issue date:	04/09/1982
From:	Parker W DUKE POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-SSINS-6820 10CFR-050.55E, 10CFR-50.55E, DEFER-820409, IEB-81-02, IEB-81-2, NUDOCS 8204280285
Download: ML20052A384 (3)

Text

{{#Wiki_filter:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _

          '                                                                                                                                                                I
                                                                                                                                                            ,,g_g o' DUKE' POWER COMPANY Powra Deut.nl 422 Sourn Cnuscu Sraszt, CHAalDTrz. N. C. 28a sa                                                            '

7 c Y WI LLI AM O. PARM ER, JR. Wet PatsiotNT TELEpaowt:Aata704 s'< - PacoucTio~ April 9,1982 273-e a s Mr. James P. O'Reilly, Regional Administrator 9 U. S. Nuclear Regulatory Commission ,

                                                                                                                                                                                                           ' b@,(,   ,

Region II ~ fM 101 Marietta Street, Suite 3100 - ,- .s@g t - 8 'C-Atlanta, Georgia 30303 ij g$ A f A'v 4 . f Q ~ Re: Catawba Nuclear Station TK t8'/ W Units 1 and 2 '/8 J Docket Nos. 50-413 and -414 g s

                                                                                                                                                                                                       /wi \P

Dear Mr. O'Reilly:

Pursuant to 10 CFR 50.55e, please find attached Significant Deficiency Report SD 413-414/82-09. Ver truly yours, I w .' .u. William 0. Parker, J . RWO/php Attachment cc: Director Mr. Robert Guild, Esq. Office of Inspection & Enforcement Attorney-at-Law U. S. Nuclear Regulatory Commission 314 Pall Mall Washington, D. C. 20555 Columbia, South Carolina 29201 Mr. P. K. Van Doorn Palmetto Alliance NRC Resident Inspector 21355 Devine Street Catawba Nuclear Station Columbia, South Carolina 29205 s

                                                                                                                                                                                                                       *ik#, C(j-{n J

d[ 8 2 0 4 2 8 01,g5 ,y _ _-- m

DUKE POWER COMPANY CATAWBA NUCLEAR STATION SIGNIFICANT DEFICIENCY REPORT NUMBER: SD 413-414/82-09 REPORT DATE: April 9, 1982 FACILITY: Catawba Nuclear Station Units 1 and 2 IDENTIFICATION OF DEFICIENCY: NRC IE Bulletin 81-02 supplement 1 provided notification of potential undersizing of electric motor operators (EM0's) for Westinghouse valves. INITIAL REPORT: Initial report was made to Mr. A. Ignatonis, Region II NRC, on 3-12-82 by Messrs. W. O. Henry and John Lanier, Duke Power Company. DECRIPTION OF DEFICIENCY: Westinghouse letter Catawba-2606 and NRC IE Bulletin 81-02 supplement 1 informed Duke Power of a possible closure problem on West-inghouse Electro-Mechanical Division manufactured gate valves. Westinghouse confirmed by phone that the Limitorque and Rotork motor operators on Catawba valves are undersized. These active valves are supplied per Duke Power Design Specification CNS-1205.00-0008 and Mill Power Order A-98524. Attachment 1 is a list of the affected valves by type and current status of Duke evaluation to determine if EM0's provided are capable of meeting functional requirements. ANALYSIS OF SAFETY IMPLICATIONS: Undersizing of the Westinghouse valve electric motor operators can result in failure of these active valves to complete their safety functions. CORRECTIVE ACTION: Design Engineering is evaluating all Westinghouse valve /EM0 applications at Catawba to detennine if the EM0 provided will meet functional requirements. This evaluation is 32% complete with no functional deficiencies identified. Twenty of the 50 valves may require some corrective actions, 18 were found to be acceptable and 18 are still being evaluated. Corrective action for the undersized valve operators will be discussed in a meeting with West-inghouse on April 7,1982. Corrective action is expected to be one, or a com-bination of, the following:

1. Replace EMO with adequately sized operator.

2. Change gear ratio to provide required operating torques.

3. Replace EM0 motor with larger motor to provide required operating torques.

A final report outlining corrective actions to be taken for Westinghouse valves / EM0's will be submitted by June 17, 1982. Duke is reviewing Westinghouse EM0 valve applications on other stations. Any deficiencies will be reported to NRC. l

t.

     -e    ,,
       ?-    .

DUKE POWER COMPANY CATAWBA NUCLEAR STATION

 ,                                     SIGNIFICANT DEFICIENCY l                                            Attachment #1 Duke Westinghouse Model item #         EMO     Quantity    Status 08000GM84FEC510    9D-203         Rotork     16      8 acceptable, 8 under review 18000GM84FEC310    90-204         Rotork        4     under review 120uaGM84FEC400    90-207         Rotork        4     acceptable 08000GM84FEC500    90-211         Rotork        4    corrective action req'd 12000GM84FEC300    9D-213         Rotork        4     under review 08000GM84FEC510    9D-214         Rotork     -2      . acceptable 12000GM84FEC310    9D-215         Rotork        4-   corrective action. reg'd 08000GM86FMC410'   9J-205         Rotork        4     acceptable 10000GM88FME01D    9J-209*        Limitorque 8       corrective action req'd 08000GM88FMC3C0    9J-211         Rotork        4    corrective action req'd 12000GM88FHE00D    9J-213         Limitorque 2        under review l

l~ ( --~__}}