IR 05000237/1985019

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Insp Repts 50-237/85-19,50-249/85-16,50-254/85-14 & 50-265/85-16 on 850513-17.No Violation or Deviation Noted. Major Areas Inspected:Followup on Licensee Actions on Previous Insp Findings & IE Bulletins
ML17195A862
Person / Time
Site: Dresden, Quad Cities, 05000000
Issue date: 06/17/1985
From: Danielson D, Yin I
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML17195A861 List:
References
50-237-85-19, 50-249-85-16, 50-254-85-14, 50-265-85-16, IEB-79-07, IEB-79-14, IEB-79-7, NUDOCS 8507090028
Download: ML17195A862 (20)
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Text

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Reports N U.S. NUCLEAR REGULATORY COMMISSION

REGION III

50-237/85019(DRS); 50-249/85016(DRS);

50-254/85014(DRS); 50-265/85016(DRS)

Docket No ; 50-249; 50-254; 50-265 Licenses No. DPR-19; DPR-25; DPR-29; DPR-30 Licensee:

Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name:

Dresden Station, Units 2 and 3 Quad-Cities Station, Units 1 and 2 Inspection At:

Impell Corporation, Bannockburn, IL (Impell)

NRC-Region III, Glen Ellyn, IL (RIII)

Inspection Conducted:

May 13-17, 1985 at Impell June 4, 1985 at Region III

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Approved By:

D. H. Danielson, Chief Materials and Processes Section Inspection Summary Date Ins ection on Ma 13-17, and June 4, 1985 Re orts No. 50-237/85019(DRS 50-249/85016 DRS ; 50-254 8501 DRS ; 50-265 85016 DRS Areas Inspected:

Special announced inspection to followup on licensee actions on previous inspection findings, IE Bulletins and a RIII Confirmatory Action Letter. The inspection involved 40 inspector-hours at the AE's office and at Region III by one NRC inspecto Results:

No violations or deviations were identifie ~

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DETAILS Persons Contacted Commonwealth Edison Company (CECo)

+D. Scott, Plant Manager, Dresden Station

  • S. Javidan, Engineer, Station Nuclear Engineering Department J. Achterberg, Technical Staff Supervisor, Dresden Station Impell Corporation (Impell)
  • W. Tschudi, Division Manager K. C. Wanapius, Section Manager
  • W. J. Wagoner, Senior Engineer
  • O. W. Zuriga, Supervisor Engineer P. Staller, Supervisor Engineer
  • Denotes those attending the management exit meting on May 17, 198 +Denotes those participating in the management exit interview telephone conference on June 4, 198.

Licensee Action on Previous Identified Items (Closed) Open Item (237/83-23-01; 249/83-20-01; 254/83-22-01; 265/83-21-01):

Impell evaluation of !EB 79-14 "No Action Supports" was reviewed by the inspector. See Paragraph 4 for detail.

Licensee Action on IE Bulletins (Closed) IE Bulletin No. 79-07 (237/79-07-BB; 249/79-07-BB; 254/79-07-BB; 265/79-07-BB):

IE Bulletin No. 79-07, "Seismic Stress Analysis of

. Safety-Related Piping, 11 dated April 14, 1~79. The bulletin requested the licensees to verify that appropriate load combination methods had been utilized in the piping stress analysis computer program The inspector reviewed the CECo letter to Region III, "Response to IE Bulletin No. 79-07, 11 dated October 12, 1979, including the attachment to the letter, entitled "Description of Computer Programs as the Verification Procedure Used by URS/John A. Blume and Associates, Engineer for the Seismic Analysis of General Electric Company Supplied Piping.

Based on the NRC staff review of the above documents and Region III followup on the piping analysis performed by the A-E based on the IE Bulletin No. 79-14 requirements, the NRC inspector concluded that CECo had taken adequate measures to resolve this matte.

No Action Supports (NAS) Review of Procedures The inspector reviewed the following NAS and related IEB 79-14 work and specifications and had no adverse comment '*

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Impe 11 Procedure, 11 Bl ume Criteria Support Documentation Project Plan, 11 Revision 2, dated August 198 Impell/S&L Interface Control Instructions for the Blume Criteria Support Documentation Project, 11 Revision B, dated September 7, 198 S&L Letter to EDS Nuclear, Inc. (now Impell), "As-Built Pipe Analysis Interface IE Bulletin 79-14, 11 dated May 9, 198 Impell Specification 0591-102-02, "Installation of Pipe Supports for the Blume Criteria Support Documentation,"

Revision 3, dated June 14, 198 Inipell Support Design Section procedure No. 003, "Use of the Field Change Request, 11 Revision 0, dated September 15, *198 Impell Specification 0590-003-21, "Installation of Pipe Supports for the IEB 79-14 Effort for Dresden Station,

Revision 9, dated January 12, 198 EDS Nuclear,. Inc. PI-18, "Use of Field Change Request,

Revision 3, dated August 24, 198 Bechtel Power Corporation, Ann Arbor, Michigan procedures,

"Procedure for Verifying Conformance of Seismic Analysis Configuration to Actual Configuration of Safety-Related Piping Systems In Response To IE Bulletin 79-14, 11 Revision 4, dated March 4, 198 Morrison Construction Company procedure QSPC-16B, 11 Installation*

and Modification of Component Supports and Restraints (for Quad-Cities),

11 Revision 0, dated December 198 Wfl 1 i am A. Pope Company procedure QAP-2, 11Tra ve 1 er Package Preparation and Control, 11 Revision 5, dated November 19, 198 IEB 79-14 NAS Evaluation By Impell The inspector reviewed the following Impell p1p1ng system stress analyses and suspension design calculations:

D2-DGSW-02B(c), "Diesel Generator Service Water, 11 Revision 3, dated November 1, 198 D2-LPCI-02B(c), "Low Pressure Coolant Injection Piping,

Revision 1, dated April 5, 198 D3-CRDS-03B(c), "Control Rod Drive System, Line 3-0308-4,

Revision 2, dated November 13, 198 *

Ql-RBCW-02B, 11Reactor Building Cooling Water, 11 Revision 1, dated December 23, 198 Ql-STGA-03C, 11Standby Gas Treating Lines, 11 Revision 4, dated February 28, 198 Q2-HPCI-04B(c),

11Reactor Building - Torus and HPCI Pump 2-2340-4 Piping Between Nutech Anchor and 2-2304-14 Pipelines,

Revision 2, dated September 22, 198 Areas reviewed included:

(1) line analysis decoupling, (2) valve model basis, (3) stress intensification factor calculation, (4) restraint auxiliary steel calculation, (5) response spectra selection, (6) line configuration, (7) anchor load interface, and (8) modelling of non-safety-related piping connecting to the NAS pipin No violations or deviations were identified as a result of this revie.

Followup on RIII Confirmatory Action Letter (CAL) dated July 4, 1982 Based on the previous RIII inspections conducted at Impell, the licensee's office, and at Region III, the subject CAL items were previously considered close Item 4 of the CAL, states that 11Complete all other required safety-related piping and piping suspension system modifications to the FSAR conditions on or before December 31, 198 For Dresden 2 and Quad-Cities 1 and 2 the latest estimated completion date is June 1, 198 For Dresden 3,.the work should be completed during the extended plant outage (recirculation loop piping replacement) starting September 198 Region III considers the revised completion schedule acceptabl.

QC Inspection for Modified and Added Piping Supports A failure of the licensee to conduct a complete QC inspection for the modified and added piping supports that were installed as a result of IEB 79-14 evaluations and the Mark I program was identified during a recent inspectio (Inspection Report No. 50-237/84-27; 50-249/85-13.)

As a result CECo requested that Impell perform inspections on 20 safety-related supports installed on Dresden Unit 2 *

in addition to the 66 supports already inspected by Sargent and Lundy Engineers (S&L).

The results of inspection including engineering evaluation are discussed in:

Impe 11 1 etter to CECo, No. 0590-096-038, "Summary of the Engineering Impact of Pipe Support As-Built Deviations at Dresden Unit 2, 11 dated April 16, 198 Impell letter to CECo, No. 0590-096-039, 11Summary of Pipe Support As-Built Deviations at Dresden Unit 2, 11 dated May 13, 198 Of the 20 supports inspected, 3 were IEB 79-14 supports using Impell installation tolerance criteria. The other 17 were Mark I program supports using Nutech installation tolerance criteria. The inspection results identified the following deficiencies:

For IEB 79-14 supports, 3 out -0f 3 contained deviations exceeding installation tolerance For Mark I program supports, 12 out of 17 contained deviations exceeding the allowable tolerance There was a total of 29 deviations identified in the 15 nonconforming supports. These deviations consisted of both small and large deviations in a random manne Impell compared the deviations they identified with the tolerance acceptance criteria established by S&L for the 66 supports that were inspected by S&L on the main steam syste Of the 20 Impell inspected supports, 13 contained deviations that exceeded the S&L inspection tolerance On June 7, 1985, the above inspection findings were discussed with CECo personnel during a telephone conversatio CECo stated they would review the matter 'further and would inform Region III on June 24, 1985, of any proposed additional actions concerning these deviations. This is considered an open item (237/85019-01; 249/85016-01; 254/85014-01; 265/85016-01). Exit Interview Exit Interviews with licensee representatives were conducted on May 17 and June 4, 1985 to discuss the finding The inspector discussed the likely informational content of the inspection report with regard to documents reviewed by the inspector during the inspection. The licensee did not identify any such documents as proprietar,~,Rc,;~ORM 766

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Docket No. 50-237 Docket No. 50-249 Docket No. 50-254 Docket No. 50-265 Commonwealth Edison Company ATTN:

Mr. Cordell Reed Vice President Post Office Box 767 Chicago, IL 60690 Gentlemen:

JUN 181985 This refers to the special safety inspection conducted by Mr. I. T. Yin of this office on May 13-17, 1985, at Impell Corporation, Bannockburn, Illinois, and on June 4, 1985, at the Region Ill office, of activities at Dresden Station, Units 2 and 3, authorized by NRC Operating Licenses No. DPR-19 and No. DPR-25, and of activities at the Quad-Cities Station, Units 1 and 2, authorized by NRC Operating Licenses No. DPR-29 and No. DPR-30 and to the discussion of our findings with Messrs. D. Scott and S. Javidan of your staf The enclosed copy of our inspection report identifies areas examined during the inspection. Within these areas, the inspection consisted of a selective examination of procedures and representative records, observations, and interviews with personne No violations with NRC requirements were identified during the course of this inspectio In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter and the enclosures will be placed in the NRC Public Document Roo. Commonwealth Edison Company

JUN 18 1985 We will gladly discuss any questions you have concerning this inspectio

Enclosure:

Inspection Reports No. 50-237/85019(DRS);

.

No. 50-249/85016(DRS);

No. 50-254/85014(DRS);

No. 50-265/85016(DRS)

REGION I II Reports N /85019(DRS); 50-249/85016(DRS);

50-254/85014(DRS); 50-265/85016(DRS)

Docket No ; 50-249; 50-254; 50-265 Licenses No. DPR-19; DPR-25; DPR-29; DPR-30 Licensee:

Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name:

Inspection At:

Dresden Station, Units 2 and 3 Quad-Cities Station, Units 1 and 2 Impell Corporation, Bannockburn, IL (lmpell)

NRC-Region Ill, Glen Ellyn, IL (RIII)

Inspection Conducted:

May 13-17, 1985 at Impell June 4, 1985 at Region III

/tfA-lnspector:

I. T. Yin

/-

~~~

Approved By:

D. H. Danielson, Chief Materials and Processes Section Inspection Summary Date Ins ection on Ma 13-17, and June 4, 1985 Re arts No. 50-237/85019(DRS ;

50-2 9/85016 DRS ; 50-254/8501 DRS ; 50-265 85016 DRS reas Inspected:

Specia announced inspection to followup on licensee actions on previous inspection findings, IE Bulletins and a Riii Confirmatory Action Lette The inspection involved 40 inspector-hours at the AE's office and at Region III by one NRC inspecto Results:

No violations or deviations were identifie,,*

DETAILS Persons Contacted Commonwealth Edison Company (CECo)

+D. Scott, Plant Manager, Dresden Station

  • S. Javidan, Engineer, Station Nuclear Engineering'Department J. Achterberg, Technical Staff Supervisor, Dresden Station Impell Corporation (Impell)
  • W. Tschudi, Division Manager K. C. Wanapius, Sectio~ Manager
  • W. J. Wagoner, Senior Engineer
  • O. W. Zuriga, Supervisor Engineer P. Staller, Supervisor Engineer
  • Denotes those attending the management exit meting on May 17, 198 +Denotes those participating in the management exit interview telephone conference on June 4, 198.

Licensee Action on Previous Identified Items (Closed) Open. Item (237/83-23-01; 249/83-20-01; 254/83-22-01; 265/83-21-01):

lmpell evaluation of IEB 79-14 11 No Action Supports" was reviewed by the inspecto See Paragraph 4 for detail.

Licensee Action on IE Bulletins (Closed) IE Bulletin No. 79-07 (237/79-07-BB; 249/79-07-BB; 254/79-07-BB; 265/79-07-BB):

IE Bulletin No. 79-07, "Seismic Stress Analysis of Safety-Related Piping, 11 dated April 14, 197 The bulletin requested the licensees to verify that appropriate load combination methods had been utilized in the piping stress analysis computer program The inspector reviewed the CECo letter to Region III, "Response to IE Bulletin No. 79-07, 11 dated October 12, 1979, including the attachment to the letter, entitled "Description of Computer Programs as the Verification Procedure Used by URS/John A. Blume and Associates, Engineer for the Seismic Analysis of General Electric Company Supplied Piping.

Based on the NRC staff review of the above documents and Region JII followup on the piping analysis performed by the A-E based on the IE Bulletin No. 79-14 requirements, the NRC inspector concluded that CECo had taken adequate measures to resolve this matte.

No Action Supports (NAS) Review of Procedures The inspector reviewed the following NAS and related IEB 79-14 work and specifications and had no adverse comment..

Impell Procedure, "Blume Criteria Support Documentation Project Plan," Revision 2, dated August 198 "Impell/S&L Interface Control Instructions for the Blume Criteria Support Documentation Project," Revision B, dated September 7, 198 S&L Letter to EDS Nuclear, Inc. (now Impel l), "As-Built Pipe Analysis Interface IE Bulletin 79-14," dated May 9, 198 Impell Specification 0591-102-02, "Installation of Pipe Supports for the Blume Criteria Support Documentation,"

Revision 3, dated June 14, 198 Impell Support Design Section procedure No. 003, "Use of the Field Change Request," Revision 0, dated September 15, 198 Impell Specification 0590-003-21, "Installation of Pipe Supports for the IEB 79-14 Effort for Dresden Station,

Revision 9, dated January 12, 198 EDS Nuclear, Inc. PI-18, "Use.of Field Change Request,"

Revision 3, dated August 24, 198 Bechtel Power Corporation, Ann Arbor, Michigan procedures,

"Procedure for Verifying Conformance of Seismic Analysis Configuration to Actual Configuration of Safety-Related Piping Systems In Response To IE Bulletin 79-14," Revision 4, dated March 4, 198 Morrison Construction Company procedure QSPC-16B, "Installation and Modification of Component Supports and Restraints (for Quad-Cities)," Revision 0, dated December 198 Willi am A. Pope Company procedure QAP-2, "Trave 1 er Package Preparation and Control," Revision 5, dated November 19, 198 IEB 79-14 NAS Evaluation By Impell The inspector reviewed the following Impell *piping system stress analyses and suspension design calculations:

D2-DGSW-02B(c), "Diesel Generator Service Water," Revision 3, dated November 1, 198 D2-LPCI-02B(c), "Low Pressure Coolant Injection Piping,

Revision 1, dated April 5, 198 D3-CRDS-03B(c), "Control Rod Drive System, Line 3-0308-4,"

Revision 2, dated November 13, 198 *-*

Ql-RBCW-028, "Reactor Building Cooling Water, 11 Revision 1, dated December 23, 198 Ql-STGA-03C, "Standby Gas Treating Lines, 11 Revision 4, dated February 28, 198 Q2-HPCI-04B(c), "Reactor Building - Torus and HPCI Pump 2-2340-4 Piping Between Nutech Anchor and 2-2304-14 Pipelines,"

Revision 2, dated September 22, 198 '

Areas reviewed included:

(1) line analysis decoupling, (2) valve model basis, (3) stress intensification factor calculation, (4) restraint auxiliary steel calculation, (5) response spectra selection, (6) line configuration~ (7) anchor load interface, and (8) modelling of non-safety-related piping connecting to the NAS pipin No violations or deviations were identified as a result of this revie.

Followu on Rill Confirmator Action Letter CAL dated July, 1982 Based on the previous RIII inspections conducted at lmpell, the licensee's office, and at Region III, the subject CAL items were previously considered close Item 4 of the CAL, states that

"Complete all other required safety-related piping and piping suspension system modifications to the FSAR conditions on or before December 31, 198 For Dresden 2 and Quad-Cities 1 and 2 the latest estimated completion date is June 1, 198 For Dresden 3, the work should be completed during the extended plant outage (recirculation loop piping replacement) starting September 198 Region III considers the revised completion schedule acceptabl.

QC Inspection for Modified and Added Piping Supports A failure of the licensee to conduct a complete QC inspection for the modified and added piping supports that were installed as a result of IEB 79-14 evaluations and the Mark I program was identified during a recent inspectio (Inspection Report No. 50-237/84-27; 50-249/85-13.)

As a result CECo requested that Impell perfor~

inspections on 20 safety-related supports installed on Dresden Unit 2 in addition to the 66 supports already inspected by Sargent and Lundy Engineers (S&L).

The results of inspection including engineering evaluation are discussed in:

Impel 1 letter to CECo, No. 0590-096-038, 11Sunmary of the Engineering Impact of Pipe Support As-Built Deviations at Dresden Unit 2, 11 dated April 16, 198 Impell letter to CECo, No. 0590-096-039, "Summary of Pipe Support As-Built Deviations at Dresden Unit 2, 11 dated May 13, 198 *~-....

. -

Of the 20 supports inspected, 3 were IEB 79-14 supports using lmpell installation tolerance criteria. The other 17 were Mark I program supports using Nutech installation tolerance criteria. The inspection results identified the following deficiencies:

For IEB 79-14 supports, 3 out of 3 contained deviations*

exceeding installation tolerance For Mark I program supports, 12 out of 17 contained deviations exceeding the allowable tolerance There was a total of 29 deviations identified in the 15 nonconforming supports. These deviations consisted of both small and large deviations in a random manne Impell compared the deviations they identified with the tolerance acceptance criteria established by S&L for the 66 supports that were inspected by S&L on the main steam sys ter Of the 20 lmpe 11

inspected supports, 13 contained deviations that exceeded the S&L inspection tolerance On June 7, 1985, the above inspection findings were discussed with CECo personnel during a telephone conversatio CECo stated they would review the matter further and would inform Region III on June 24, 1985, of any proposed additional actions concerning these deviations. This is considered an open item (237/85019-01; 249/85016-01; 254/85014-01; 265/85016-01). Exit Interview Exit Interviews with licensee representatives were conducted on May 17 and June 4, 1985 to discuss the finding The inspector discussed the likely informational content of the inspection report with regard to documents reviewed by the inspector during the inspectio The licensee did not identify any such documents as proprietar

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