ML20032A346

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QA Program Insp Rept 99900528/81-01 on 810708-09. Noncompliance Noted:Project Instructions Did Not Reflect Latest Operability Stress Limits or Provide Guidance on Use of Blume Curves for IE Bulletin 79-14 Activities
ML20032A346
Person / Time
Issue date: 10/07/1981
From: Brickley R, Hale C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20032A341 List:
References
REF-QA-99900528 IEB-79-14, NUDOCS 8110290439
Download: ML20032A346 (11)


Text

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CRGANIZATION: EDS NUCLEAR, INCORPORATED SAN FRANCISCO, CALIFORNIA REPORT NO.: 99900528/81-01 INSPECTION DATE(S):

7/8-9/81 INSPECTION ON-SITE HOURS: 32 CORRESPONDENCE ADDRESS: EDS Nuclear, Incorporated ATTN: Mr. L. W. Cooley Vice President 220 Montgomery Street San Francisco, CA 94104 ORGANIZATION CONTACT:

Mr. B. F. Phipps, QA Manager TELEPHONE:

(415) 544-8050 PRINCIPAL PRODUCT:

Engineering Consultant Ser< ices NUCLEAR INDUSTRY ACTIVITY: EDS Nuclear Inc., has 55 contracts involving approximately 49 domestic reactor units for consulting services such as engineering analysis, equipment qualification, licensing assistance, pipe support design, pipe whip analysis and protection design, piping analysis, seismic analysis, and safety analysis.

ASSIGNED INS!MCTOR: T.M M

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R. H. Brickley,yactor Systems Section (RSS)

Date OTHER INSPECTOR (S):

I. T. Yin, RIII; D. H. Danielson, RIII (Observer); J. R. Fair, HQS

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APPROVED BY:

s C. G a9e, Chief, RSS Date INSPECTION BASES AND SCOPE:

A.

BASES:

10 CFR Part 21. and 10 CFR Part 50, Appendix B.

B.

SCOPE:

Analytical errors made by EDS concerning steei containment penetration assemblies for Sequoyah and Watts Bar,10 CFR Part 21 report of piping analysis errors for Sequoyah, IE Bulletin 79-14 activities, and status of previous inspection findings.

DEy;ED ORICHAL Certified By l W LN - -

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8110290439 811014 PDR GA999 EECEDS 99900528 PDR

ORGANIZATION: EDS NUCLEAR, INCORPORATED SAN FRANCISCO, CALIFORNIA REPORT NO.:

99900528/81-01 INSPECTION RESULTS:

PAGE 2 of 3 A.

VIOLATIONS:

None B.

NONCONFORMANCES:

Contrary to Criterion V of 10 CFR Part SC<, Appendix B, Project Instructions contained conflicting design acceptance criteria, did not reflect the latest NRC accepted operability stress limits, and did not provide guidance on use of the Blume Curves.

Further, the operability criteria for the evaluation of hangers was not apparent.

C.

UNRESOLVED ITEMS:

None D.

STATUS OF PREVIOUS INSPECTION FINDINGS:

1.

(Closed) Follow-up Iten (80-01):

The examination of calculation package No. Q1-HPCI-01 revealed that the formal system operability evaluation did not appear to be adequately documented.

The subject of operability evaluations including calculation No. Q1-HPCI-01 was reviewed.

The piping stress analysis shows that the system is within the operability stress limit for the SSE.

2.

(Closed) Follow-up Item (80-01):

The examination of calculation package No. 02-LPCI-03C revealed that the present method of using the center of gravity of the pipe system to select the horizontal static coefficient used in the calculation appears questionable.

It was stated by the licensee that the center of gravity method was the original method used by Sargent & Lundy.

This item 12, therefore, not considered to be within the scope of IEB 79-14.

3.

(Closed) Follow-up Item (80-01):

It appears that stress intensification factors had not been considered in those system evaluations based on Blume Curve design.

EDS Nuclear had assumad that these factors had been considered in these curves. The actual tases of the curves were not available for examination.

The licensee has committed to use only the rigid span criteria of the Blume Curve, therefore, this item is closed.

4.

(Closed) Follow-up Item (80-01):

In reviewing the requirements for using the Blume Curves it appeared that on piping above elevation 579 feet restraint loads will be multiplied by a factor of three to account for amplification.

Based on the commitment to use rigid span criteria (D.3. above) RIII will resolve this matter with the licensee.

  • ORGANIZATION: EDS NUCLEAR, INCORPORATED SAN FRANCISCO, CALIFORNIA REPORT NO.: 99900528/81-01 INSPECTION RESULTS:

PAGE 3 of 3 E.

OTHER FINDINGS OR COMMENTS 1.

Analytical Error Concerning Steel Containment Penetration Forces - This item was reported to RII per 10 CFR Part 50.55(e) by TVA concerning the omission of axial forces on piping penetrating containment during pipe stress analysis of Sequoyah 1 and 2 and Watts Bar 1 and 2.

From the records examined at EDS Nuclear (EDS) it was determined that this analysis was not included in their scope of work for these plants.

This item had been brought to TVA's attention by EDS as a result of EDS's in-vestigation of this problem on an analysis performed by them for Duke's McGuire 1 and 2.

EDS had recommended that TVA investigate to see if this omission had occurred on analyses performed by other organizations for TVA.

With respect to the omission on the McGuire 1 and 2 analysis, the Safety Review Committee concluded that:

(1) it had occurred ocly on McGuire 1 and 2, and (2) that analysis of these forces was not included in their scope of work and they were not directed to include them.

2.

Piping Analysis Error - This item, reported to RII per 10 CFR Part 50.55(e) by TVA, concerned the omission of an installed lateral support from the thermal load case analysis performed by EDS on Sequoyah 2.

From the records examined at EDS it was revealed that the mathematical model that was used was revised on June 17, 1977, as a resu't of the relocation of valves TVA-51 and FCV-1-182.

The corresponding support summaries were updated with respect to loads, however, the displacewats were not updated as they should have been, and thus the lateral supNrt was not deleted from the design.

The support summaries were processed in accordance with procedures that were in existence at the tims of these activities. Subsequent to this, EDS developed and issued Technical Procedure 2.1.12 (Piping Analysis Checking Procedure) which imposes detailed specific items to check on the analysis and all associated documents that should prevent recurrence of these type errors.

3.

IE Bulletin 79 Fourteen technical Project Instructions related to IEB 79-14 activities were examined.

It was concluded that the instructions contained conflicting requirements and therefore not in conformance with NRC requirements (see B. above).

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