IR 05000483/1980013

Forwards IE Insp Rept 50-483/80-13 on 800506-09.No Noncompliance Noted

ML19320B762
Person / Time
Site:	Callaway
Issue date:	06/04/1980
From:	Fiorelli G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Bryan J UNION ELECTRIC CO.
Shared Package
ML19320B763	List: IR 05000483/1980013
References
NUDOCS 8007150017
Download: ML19320B762 (2)

Text

{{#Wiki_filter:<.pg , TIC s . k UNITED STATES !"' N, NUCLEAR REGULATORY COMMISSION $ nE REGION lli , \\ "==</br>IE Inspection Report No. 50-483/80-13</br></br>REGION III==</br>Report No. 50-483/80-13 Docket No. 50-483 License No. CPPR-139 Licensee: Union Electric Company P.O. Box 149 St. Louis, MO 63166 Facility Name:</br>Callaway, Unit 1 Inspection At: Callaway Site, Callaway County, MO & Corporate Offices, St. Louis, M0 Inspection Cond ted: May 6-9, 1980 b</br>.-t'e6</br>.</br>Inspectors:</br>H. M. Wescott g _ J - /A</br>[.2 [8</br>*</br>r</br>.</br>g sal</br>'</br>'</br>T. E. Vande -</br>-)-M l't</br>&</br>. Hug l -)-TO</br>.</br>'2 Ob</br>/? proved By:</br>R.</br></br>no, Chief</br>_</br>Projects Section 1 Inspection Summary Inspection on May 6-9, 1980 (Report No. 50-483/80-07)</br>Areas Inspected: Routine, unannounced inspection: Follow-up of previously identified items; followup of 10 CFR 50.55(e) reports; followup of IE Bulletins and Circulars; procedures and work on seal welds for control rod drive mechanisms; quality records for anchor bolts for lateral supports on Class I components. The inspection involved a total of 102 inspector-hours by four NRC inspectors.</br></br>Results: Of the five (5) areas inspected, no items of noncompliance were identified.</br></br>O23</br>"</br>8007150</br>{</br>r</br></br>.</br>I i</br>*</br>DETAILS Persons Contacted Union Electric Company (UEC)</br>W. S. Babnar, Nuclear Engineer</br>**R.'W. Dettenmeier, Nuclear Engineer</br>*M. I. Doyne, General Superintendent Construction</br>*S. M. Hogan, QA Assistant Engineer</br>*J. V. Laux, QA Assistant Engineer</br>**A. C. Passwater, Nuclear Engineer Supervisor</br>*R. L. Powers, Site QA Superintendent</br>**D. E. Shafer, Nuclear Engineer</br>*W. H. Stahl, QA Engineer</br>**W. S. Strothman, QA Supervisor</br>*R. Veatch, Assistant Engineer Daniels International Corporation</br>*J. R. Cook, QC Manager</br>*J. A. Holland, Principal QA Manager</br>*W. L. Sykora, Assistant Project Manager C. Tye, Lead Civil Engineer R. Wilson, Area Superintendent Westinghouse S. Martinez, Site Manager Bechtel C. Plows, Liaison Engineer Hartford Steam Boiler Insurance Company</br>*H.</br></br>Potter, Authorized Nuclear Inspector</br>** Denotes those attending the exit meeting on [[Exit meeting date" contains a listed "[" character as part of the property label and has therefore been classified as invalid. in UEC's general offices, St. Louis, MO

• Denotes those attending the exit meeting on May 9, 1980 at the Callaway site.

'I.

Licensee Action on Previously Identified Items (0 pen) Unresolved Item (483/78-07-04): The inspector reviewed NCR 2-3293-C-A dated June 29, 1978 and letter QM-249, UTD QA-417, dated

-2- .

. . .

April 18, 1980. This letter established that further response is required from Daniel International regarding NCR's 2-2833-C-A, 2-3006-C-A, and 2-3292-C-A.

This item remains open pending f.ne licensee's acceptance of the response.

-(Closed) Open Item (483/78-08-03) - DIC Procedures No. WP-303, Revi-sion 0 and WP-305, Revision 1 utilizes attachment exhibits which were not completed to identify specific acceptance criteria for specific equipment and components. The RIII inspector reviewed the following DIC procedures: Work Procedure No. QP-303, Revision 3, dated April 7, 1980; Work Procedure No. WP-30,5, Revision 3, dated February 22, 1980; Quality Control Procedure No. QCP-303, Revision 2, dated April 9, 1980; Quality Control Procedure No. QCP-305, Revision 3, dated January 15, 1980. Specific acceptance criteria for the aforementioned procedures in the form of exhibits were found to be satisfactory.

(Closed) Noncompliance (483/79-03-02) - Electrical Department Manager (DIC) had not prepared or presented courses of instruction in ac-cordanc with Section 4 of Daniel International Construction (DIC) Procedure APXIII-07. The RIII inspector reviewed training records of DIC's electrical engineering department to determine if they had started their training program. Training classes were first con- , ducted on May 18, 1979 and successive months following. All training has been documented.

(Closed) Open Item (483/79-03-03) - Storage and eating of food in equipment areas as defined in DIC Procedure AP-V-10.

Housekeeping throughout the powerblock has been upgraded from Zone 5.

DIC is monitoring areas to maintain housekeeping at an acceptable level.

(Closed) Deviation (483/79-04-01) - Penetrameter used in radio-graphing the containment liner was 60% thicker than required by ASME Code Section III, Appendix X.

The inspector reviewed the enclosure to letter VLSE 7299, dated June 13, 1979 which stated that Bechtel specifications and CB&I procedures are in compliance with the intent of Regulatory Guide 1.19 and with Bechtels intention of clarifying the position of Regulatory Guide 1.19 in SNUPPS, PSAR, Section 3.12.

A response will be made in the FSAR to clearly indicate that the exception applies only to those items which are specified to be within the jurisdictional bounds of the ASME Code, Section III, namely welds at penetrations, air locks, and access openings. Union Electric Company's letter to RIII, ULNRC-320, dated June 27, 1979 appear adequate. This item is considered closed.

(Closed) Unresolved Item (483/79-14-01) - No QC signoff on percent bearing under reactor pressure vessel nozzles. A W 1etter WSM261 verifies that a W representative inspected the area in addition to the field 1 engineer. This item is closed.

-3- _ _ ,

.

(Closed) (10 CFR 50.55(e) report dated November 8, 1977) - Dravo provided three pipe spools with incorrect flange material (304 SS rather than the required 316 SE). Dravo also reported this item under 10 CFR Part 21.

The three pipe spools have been repaired and accepted by the licensee. The letter from Dravo to NRC RIII dated November 10, 1977 advises of corrective action to prevent future occurrences. This item is considered closed.

(Withdrawn) (10 CFR 50.55(e) Report dated October 26, 1977) - Dravo supplied the licensee with scledule 40 pipe rather than the required schedule 140 for the RHR system. The licensee withdrew this report based on, 1) the pipe initially provided could not have been properly fit-up, therefore, could not be installed, 2) two check valves are located upstream of the pipe spool, 3) there are two other flow paths through the CVCS charging pumps. Dravo has submitted a 10 CFR Part 21 report to NRC RIII describing corrective action to prevent future occurrences. This item is considered closed.

2.

Licensee Action on the I&E Bulletins and Circulars A. Bulletins 77-03 Lack of Testing of Safeguards Actuation Reset Circuitry The licensee, in a letter to the Region III office of Inspection and Enforcement, dated November 4, 1977, committed to providing testing of all reset circuitry by inclusion of the testing required in the system technical manual. This is considered to be an adequate re-sponse. The testing provisions will be reviewed as part of the technical manual review conducted by NRC Operations Inspectors.

78-12 A and B, Atypical Weld Material of Reactor Pressure Vessel The inspector reviewed correspondence to the NRC which included submittal of a combustion engineering generic report submitted on June 8, 1979 (Letter LD-79-036) to IE Headquarters for review with Revisions 1 and 2 submitted on January 15, 1980.

It was noted that, in addition, a commitment was made in the June 1979 letter for West-inghouse to develop surveillance weldment data which will be docu-mented following completion of the pre-irridation testing program.

This bulletin remains open for further review at a later date.

78-14, Deterioration of Buna-N Component in ASCO Solenoids This bulletin applies to BWR's with operating licenses. However, ASCO solenoids are being reviewed under Bulletin 79-01.

This bulle-tin is considered closed.

79-01 A and B, Environmental Qualification of Class IE Equipment-4-

. -_ ._ .. _ . .

b The inspector reviewed Letter SNP-301, S.O. SNP-220, dated November 15, 1979, referencing BLWE-1111 dated November 8, 1979.

ASCO air pilot solenoids have limited environment qualifications.

These valves are qualified for their intended service based on short term functions. ASCO solenoids identified in Bulletin 79-01A are not used.

79-17, Pipe Cracks in Stagnant Borated Water Systems in PWR Plants The inspector reviewed Letter BLSE-7744, dated October 3, 1979, stating that borated water systems are to be solution annealed ati control of weld heat input. The inspector reviewed randomly selected certifications which stated tLat material had been solution annealed.

79-21, Temperature Effects on Level Measurements This Bulletin is currently being reviewed by the licensee.

This Bulletin remains open.

79-24, Frozen Lines This bulletin was sent to the licensee for information only. The licensee requested a review by the Architect Engineer (Bechtel) which was completed on December 4, 1979 and responded to by Bechtel letter BLSE 7834 dated December 4, 1979. This item has been satisfactorily resolved.

79-26, Boron Loss From BWR Control Blades This bulletin was sent to the licensee for information only. However, no action was ti.an, since it was felt not to be applicable to Callaway.

The inspector had no further questions ragarding this item.

B.

Circulars The following IE Circulars are not applicable to the Callaway facility: IEC 77-09, 77-12, 78-11, 78-17, 79-07, 79-18, 79-22, and 79-24.

Action relative to these circulars is considered closed.

IE Circular No. 79-17 Contact problem in SB-13 switches on General Electric Company metalclad , i circuit breakers.

The RIII inspector reviewed Nonconformance Report (NCR) 2SN0822E dated July 17, 1979 identifying all defective SB-12 switches throughout the plant.

" Hold" tags have been placed on equipment and components also.

The licensee has reported a 50.55(e) on this matter to the Region.

Therefore, this circular is considered closed.

-5-

, . - IE Circular 79-25 and 79-25A Shock arrestor strut assembly interference.

The RIII inspector reviewed the licensee's report from the vendor that indicated that no affected hangers have been shipped to the Callaway plaat. This circular is considered closed IE Circular Fo. 80-01 Service advice for GE induction disc relays.

The RIII inspector reviewed deficiency report 2SD-1311-E, dated March 18, 1980, identifying all safety-related relays in the plant.

The licensee has reported a 50.55(e) on these relays to the Region office. This circular is considered closed.

~ -6- , - . - -

.,, - - - -1-,a aa, - - N+N+ eg$'M) ' %4 +

, .eEEv <e 1,em TEST TARGET (MT-3) ! , I l.0 iffm an EE E I.I [* EE i .8 . 1.25 1.4 1.6

6" > l l MICROCOPY RESOLUTION TEST CHART h ////A . 4% +f//h

• h!k 'N kY 3,pp/

4)p,9,,4 -- . -- -..- . _ ..._.-_

A -- ~ -C

• r-a8-A

-- -- a - J k h ?*

" /# . ___ TEST TARGET (MT-3) '

I'O "Heau Ei tu 6s t em ! 1.1 [88 EM l 11. 8 ,, 1.25 f.4 1.6 _ l < 6~ = MICROCOPY RESOLUTION TEST CHART f $ $ ' 6 L _ %s s ; 0 / g 4: , . '+* 'ww%g+~w%.. -m.,,.,-

-- --W= _

O . '

Section I Prepared by: C. M. Erb Reviewed by: D. H. Danielson, Chief Engineering Support Section 1 Functional or Program Areas Inspected 1.

Seals Weld CRDM's to Reactor Vessel Head Quality records for the Control Rod Drive Mechanisms were examined.

The certificate of design from W and the N-2 form indicate these mechansims are Section III, Class 1 items meeting the requirements of ASME Section III 1974 edition witn 1974 addenda.

The welds were smooth with excellent contour, were tacked manually, and made with automatic Astro Arc equipment to Procedures NM-8-8-B-1-W and N-8-8-B-2, Revision 1.

Inserts used were ER308-L. An information only Penetrant Test is made, since the final PT must be made after the hydro test. Hydro test will be performed at a pressure of 3,125 psi for ten minutes. Welding of the CRDM's had stopped, pending the hydro test since accessibility to center units for repair would be very difficult if surrounding units were in place.

2.

Anchor Bolts for Class 1 Equipment Certified quality records for various sizes of bolts and nuts used in supports for steam generators and reactor coolant pumps were examined to determine if mechanical requirements hu been met.

These bolts and studs were procured from Southern Bolt to Bechtel Specification 10466-C-134-A (1-5).

The Bechtel specification referenced ASTM A540-70 with two different classes as shown below: ' Item Bolts Size Material

• Hardness BHN Deformation Mils Class Pump Anchor.3"x4'1" AISI 4340-H 321-341 40, 39, 40 B23, C14 L. Generator Support 3\\"x5'10" AISI 4340-H 321-341 60, 64, 60 B23, C14 U. Generator Support 3"x5'3" AISI 4340-H 311-341 45, 42, 42 B23, C14 Generator Tie Down 3\\"x5'11" AISI 4340 341-463 26, 30, 28 B23, C14 l

! i i l-7-

e

• The hardness readings taken on the surface are in the proper range for the specification and the yield and tensiles are also acceptable.

Magnetic testing was performed on all the above orders.

The problems with the nuts is a dimensional one, because the threading tool was not centered in the hole properly. The studs, mostly 3 " diameter, are out of tolerance on pitch diameter.

Bechtel is running stripping experiments at Lehigh University to as-certain if out of tolerance conditions in the threads will develop the required strength. Where assembly of a stud and nut is difficult, a hardened ' e 3A fit, will be used to chase the threads.

This item is open and will be checked upon in later inspections.

Unresolved Items Several studs and bolts were seen to be without covering of any kind out in the plant. Since an eight thread bolt or stud is so dependent on cleanliness cf the thread, these threads should be covered and protected from dirt and contamination. This item is unresolved pending action by the licensee (50-483/80-13-01) Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompli-ance, or deviations. One unresolved item disclosed during this inspection is discussed in Section I.

Exit Interview The inspectors met with the licensee representatives (denoted under Per-sons Contacted) at the conclusion of the inspection. The inspector sum-marized the purpose and findings of the inspection.

The licensee acknow-ledged the findings reported herein.

. -8- ... .. -

_ . .. List of Attendecs and Agenda for , - . June 12 Meet.ing - with the NUCLEAlt 10'GULATORY CON 4.1 ssloNens ATTENDEES Mr. Floyd Lewis, Chairman and Presiden t, Middle South Utilities c Chairman, Three Mile Island Ad floc Nuclear Overniuht.. Committee

. . . Mr. Byron' Lee, Execut ve Vi eri President Conuncnwea 3 tb Edi-Gon Co.

Chairman vif NSAC C ormn i i t oe of PDHT Research Advisorv Crnomi t.t.c o Cha.irman, is t P Po]iey Comfnjttce on Fu.1 low-up to the TMI Accident Dr. Edwin Zebroski, Director, 14 SAC Mr. Robert Breen, Deputy Director, NSAC Mr. William Layman, Director, Engineering Dej)artmon t., ASAC . -.. -. . .. - - - -. _. . _ _ _, _, ._.g_ AGENDA . 10 minutes Introduction, I oc lu st.ry Po.' icy on NDhc - Floyd 1,ewi n - - - 10 ruinutes - NSAC Scope and Uti1it y I n t.c rart i on n - Byron Lee . 10 minutes - NSAC P. roar,im and Organi.ation - Ed Zelo or'hi . 10 minuten - Op< rat.irry J:xi'eri e'n'. e Ana)ynin - DiiI Layman I.r:R ' ri, C ry s t. a.1 Hivir An a l y r. i n . 10 minuten P roluibi l i ni. i e Ana l yn i r; and n.i s h A n n e n r.me n t Itob Dreen - - Emr:rgency Deci vi on Procenn 30 minut en - Degraded Co r r-St ud i er- - 1:d 7.< I r t in h i . Saiety Pnrarnet ert: me Sa t < t y Gr $a J f: D .q .. q . . ,WW-d a a

10 mi n u t er. - Question 1 An t wr o

'I' i me - Al) 8007150 og }}