ML19260B585
| ML19260B585 | |
| Person / Time | |
|---|---|
| Issue date: | 09/26/1979 |
| From: | Brickley R, Hale C, Modenos L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19260B580 | List: |
| References | |
| REF-QA-99900522 NUDOCS 7912100409 | |
| Download: ML19260B585 (10) | |
Text
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i U. S. NUCIEAR REGULATORY CO? MISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION IV Report No.
99900522/79-04 Program No. 51200 Company:
Bechtel Power Corporation San Francisco Power Division 425 Market Street San Francisco, California 94119 Inspection Conducted: September 10-11, 1979 f
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Date Projects Evaluation Section Vendor Inspection Branch N.
k{_fL I24\\ O rW T-2 C-79 L.Modenos,Rsactorl Ins'pector Date Region II P.J.Morrill,lteactog In5pector
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C. J. Hale, Chief'
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Program Evaluation Section Vendor Inspection Branch Summary Inspection on September 10-11, 1979 (99900522/79-04) 1519 342 79121004-O]
2 Areas Inspected:
Implementation of 10 CFR 50, Appendix E, in the area of IE Bulletin 79-14.
The inspection involved forty-eight. (48) inspector-hours on-site by four (4) NRC inspectors.
Results:
In the one area inspected there were no deviations or unresolved items identified.
8
3 DETAILS SECTION I (Prepared by R. H. Brickley and L. Modenos)
A.
Persons Contacted B. B. Belin, Stress Group Leader
- G. Borsteins, Assistant Project Engineer W. J. Castagnaro, Supervisor Designer
- J. L. Carton, Project Manager
- M. Clary, Mechanical Engineer, Arkansas Power & Light Company (APSL)
- M. Z. Khlafallah, Plant Design Staff
- M. O. White, Licensing Engineer
- Denotes those present at the exit interview.
B.
Seismic Analysis for As-Built Safety-Related Piping Systems 1.
Objecitves This was a special inspection of the Bechtel Power Corporation /
San Francisco Power Division (BPC/SFPD) activities with respect to IE Bulletin 79-14. The inspection consisted of two (2) phases.
a.
Phase 1 The objectives of this phase of the inspection were to determine the followir.g:
(1) The licensees that are inspecting systems to the latest drawings and comparing the results with the seismic analysis input used.
(2) The number of people that will be comparing the marked-up drawings with the seismic analysis input, a general descrip-tion of their qualifications, and the schedule for these activities.
(3) The guidelines that will be used to identify the noncon-formances of the marked-up drawings to the siesmic analysis input used.
(4) The identification of units where eccentric masses have been modeled.
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4 b.
Phase II The objectives of this phase of the inspection were to select a plant (ANO-1) and determine that:
(1) The IE Bulietin 79-14 activities are being conducted in a documented, planned and systematic manner.
(2) The inputs to-the seismic analysis for this system can be readily identified.
(3) Identified nonconformances are analyzed and the results properly documented.
(4) Personnel conducting the e activities have received indoc-trination and training.
2.
Metbod of Accomplishment a.
Phase I The preceding Phase. objectives were accomplished by discussions between the inspection team and BPC/SFPD representatives, and examination of the following:
(1) BPC/SFPD tentative schedule for completing the~79-14 activities.
(2) BPC/SFPD field procedure for "As Built" verification for NRC Bulletin 79-14.
(3) BPC/SFPD document, " Comprehensive Implementation for Operating Plants," and its updates Nos. 1, 2, and 3.
(4) BPC/SFPD document, " Guideline.for the Verification of the Seismic Analysis for the Safety Related Piping Systems for Arkansas Nuclear One - Unit 1."
(5) BPC/SFPD document, " Eccentric Mass Modeling."
b.
Phase II The preceding objectives were accomplished for ANO-1 by an examination of:
(1) AP&L letter dated August 31, 1979, to the Director, Region IV, in response to IE Bulletin 79-14 for Arkansas Nuclear One-Unit 1 (ANO-1).
1519 34a
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5 (2) Nine (9) ANO-1 inspection results and evaluation packages consisting of the marked-up as-built isometrics, marked-up stress isomatrics (seismic analysis input), and the en-gineering evaluations (judgements)_ for the Service Water Return & Emergency Cooling Water Discharge System; Reactor Building Spray System; T1, E24A&B Sample System; Hake-Up Pump System; Decay Heat Pumps to B.W.S.T.; Main Steam to Emergency F.W. Pump Turbine Driver; and Main F.W. to Steam Generator E24A.
3.
Findings There were no deviations or unresolved items identified in this a.
area of the inspection.
b.
All BPC/SFPD projects used the latest drawings for the walkdown and will compare the results with the revision of the drawing used as seismic analysis input.
There will be approximately sixty (60) stress engineers comparing c.
inspection results with the seismic analysis inputs and evaluating the nonconformances. These people have an engineering degree and experience in stress analysis, d.
The following is the tentative schedule for completing the 79-14 activities, final scheduling responsibility lies with each client.
This presents BPC/STPD's best estimate at this time on the antici-pated completion date.
It should be noted that completion of this schedule is conditioned by the receipt of field walkdown data at the anticipated dates and the anticipated shutdown date. Other bas M for this schedule is as follows:
1.
60-day report: based on BPC/SFPD's knowledge of work currently in progress.
2.
120-day report (or report for unaccessible areas):
- 30 days to complete the field walkdown after shutdown
- 2 weeks to receive last walkdown data from field and to prepare office packages
- 2 days for engineering judgement
- 30 days for reanalysis of 120-day report review 7
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6 60-Day Ancicipated 120-Day Last Day for Plant Report Shutdown Report 79-14 to Client Date to Client Reanalysis
- Date Date Peach Bottom 2 10-15-79 10-31-79 12-16-79 01-16-80 Peach Bottom 3 10-15-19 09-15-79 11-01-79 12-01-79 Pilgrim 1 09-04-79 01-15-79 03-04-80 04-04-80 ANO-1 09-04-79 11-04-79 12-04-79 Trojan 09-21-79 (Client wrote NRC to waive this part of the Program)
Point Beach 1 10-12-79 10-05-79 11-25-79 12-26-79 Point Beach 2 10-12-79 05-30-80 07-20-80 08-20-80
- Extent of the scope and availability of manpover may dicatate resched-uling of this date.
e.
The document identified in B.2.a. (4) above provides the toler-ances that the stress engineer is to use in his evaluation of seismic input rarameter nonconforma-ices that are identified.
In addition to these parameters, other aspects such as seismic s*ress, system frequencies, mode shapes, etc. from the stress catenlations are also utilized in arriving at an engineering judgement, f.
The following determination was obtained regarding eccentric masses:
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8 S. I. Heisler, Manager,' Division QA W. T. Kellerman, QA Supervisor, Programs H. B. Norris, QA Supervisor, Projects J. F. O' Leary, Project Manager F. Pluchah, QA Supervisor, Projects R. S. Powell, Chief Plant Design Engineer L. E. Shipley, Engineering Supervisor D. Vanderpol, QC Supervisor E. Y. Wong, QA Engineer The inspector summarized the scope and findings of the inspection. Manage-ment comments were generally for clarification only, or acknowledgment of the statements by the inspector.
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7 Project Eccentric Masses Modeled Yes No Arkansas Unit 1 X
Peach Bottom Units 2 & 3 X
Pilgrim Unit 1 X
Trojan X
Point Beach X*
Duane Arnold X
X*
Palisaides X
X*
- When piping system reanalysis is required by other items discussed in the bulletin, the reanalysis effort will consider mass eccen-trr
'y when judged critical. Reanalysis schedule and consequences may be reported outside of I.E.Bulletin 79-14 time frames.
g.
The document identified in B.2.b.(1) above is not the 60-day report as required by IE Bulletin 79-14. The 60-day report will be sub-mitted by AP&L approximately 10-days after receipt of the Bechtel report (See paragraph B.3.d).
h.
Ninety-six (96) nonconformances have been identified on the accessible piping on ANO-1.
Fifty-three (53) have been judged acceptable and the remaining forty-three (43) were judged to be acceptable-calculation required. Acceptable refers to opera-bility of the system during a Safe Shutdown Earthquake.
i.
The indoctrination of personnel involved in the engineering evaluation aspects of IE Bulletin 79-14 took place on August 23, 1979, and was documented in Update #3 to the Comprehensive Imple-mentation for Operating Plants document.
j.
The examination of the documents identified in B.2.b(2) above revealed some documents with inspection resnits that were not very legible.
BPC/SFPD engineers responded that, for those cases, they verify the data via telephone with their field represent-atives prior to their evaluation.
C.
Exit Interview An exit interview was held with management representatives on September 11, 1979.
In addition to those individuals indicated by an asterisk in para-graph A of each Details Section those in attendance were:
R. C. Anderson, Engineering Manager D. L. Damon, Project Engineer C. W. Dick, Manager of Engineer
}h W. D. Greenwell, QA Supervisor D. W. Halligan, Vice President and. Deputy Division Manager
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D. B. Hardie, Supervisor, Quality Engineering
9 DETAILS SECTION II (Prepared by P. J. Morrill)
A.
Persons Contacted Bechtel Personnel
- S. Cozzens, Project Q. E.
- S. Chitais, Asst. Bechtel Stress Group Supervisor
- A. Ayod, Trojan Project Stress Group Leader T. Flickinger, QA Engineer PGE Personnel
- A. Robe, Mechanical Engineer
- Denotes those present at the exit interview.
B.
Seismic Analysis for As-Built Safety-Related Piping Systems 1.
The inspector reviewed the Index of Seismic Class I isometrics to be inspected per IE Bulletin 79-14.
It appeared to adequately identify drawings per PGE response to the bulletins (dated 8/1/79 and 6/31/79) and to furnish a means to track the same.
2.
Nonconformances identified by the licensee letter of 8/31/79 and their resolution / evaluation were examined by a review of the related isometric drawings, evaluation sheets (tabulations of geometry differences), and stress calculations; and discussions with Bechtel and PGE Personnel.
3.
Selected engineering evaluations were also examined and discussed with licensee personnel to verify the criteria utilicad and compliance to QA requirements.
4.
Examined the documents listed below to verify that inputs to seismic analysis can be readily identified and that QA program requirements are satisfied.
a.
Marked up Fabrication Isometric Drawings Approximately 200 drawings sent from the licensee to Bechtel -
all were examined with the e yhasis on the following drawings.
and a follow through to specific seismic analysis on selected deviations.
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10 (1) Isome*.rics CS-15 R-6-1 (Room 167)
DBD-5 2 (Room 90)
CS-151R-6-2 (Area 12)
HBD-50-2 (Room 183)
HCC-48-2 HCC-49-3 (Room 255)
HFD-4-8 (Room 86)
HFD-5-6 (Room 86)
HED-7-3 (Room 157 & 90)
(2) " Tabulation of Geometry Differences RDC79-075" Calculations /re
.ution/ bases - examined the following r
calculations:
10-15 evaluated 8/30/79 (CS-151R-6-1) 2-13 & 2-14 evaluated 8/14/79 (DBD-5-2) 2-12 evaluated 8/28/79 (HBD-50-2) 11-19 evaluated 9/1/79 (HCC-48-2) 13-17 evaluated 8/30/79 (HCC-49-3) 7-18 evaluated 8/31/79 (HFD-4-8) 7-5 evaluated 8/21/79 (HFD-5-6) 7-1 evaluated 8/29/79 (HFD-1-3)
(3) 'The following seismic analyses were examined:
Stress Calulation 10-15/ Problem 35 dated 11/11/78 (CS-151R-6-1) (OK low stress)
Stress Calulation 7-5/ dated 10/10/75 (EED-5-6)
(OK low stress)
Stress Calculation / Operability Study dated 8/14/79 (DBD-5-2) (Upset stress was 900 PSI over code allowable but this appears acceptable in that emergency stress was 3 KSI below code allowable - in any case the missing sutport was reportedly replaced within the Technical Specification time frame)
Stress Calcula. ion 10-26/ Problem 35 dated 7/21/79 (CS-151R-6-2)
(included modeling for lumped mass for valve M08100) (all stresses acceptable) 5.
Findings There were no deviations or unresolved items identified in this area of the inspection.
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