IR 05000346/1977017
| ML19326A456 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/06/1977 |
| From: | Hayes D, Naidu K, Williams C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19326A452 | List: |
| References | |
| 50-346-77-17, NUDOCS 8002040618 | |
| Download: ML19326A456 (16) | |
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UNITED STATES NITCLEAR REGUT.ATORY C0ff;tISSION OFFICE OF INSPECTION AND ENFORCEMENT
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REGION III
Report of Construction Inspection IE Inspection Report No. 50-346/77-17 Licensee: Toledo Edison Company
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Edison Plaza 300 Madison Avenue Toledo, OH 43652
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,i Davis-Bess'e Nuclear Power Station, Unit 1 License No. CPPR-80 Oak Harbor, OR Category:
B Type of Licensee:
PWR (B&W) 926 MWe Type of Inspection:
Routine, Announced
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Dates of Inspection:
April 5-8, 1977 8t 4 C
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Principal Inspector:
C. C. Willians.
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(Date)
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Accompanying Inspectors:
K. R. Naidu g
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F.
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u. 3. ney 7/s ~/?' 7 (Date)~
Other Accompanying Po,rsonnel:
None
'7/[!7'7 Reviewed By :
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Projects Section
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SU!! MARY OF FINDTNCS
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Inspection on April 5-8, 1977, (Unit 1, 77-17): Review of resolution of previously identified unresolved matters, construction deficiencies reported pursuant to LO CFR 50.55(e) and action eclative to IE nulletins and Circulars.
' observations and examination in various areas of thReview of stat items, e as-built plant.
Enforcement Action None identified.
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Licensee $ction on Previousiv Identified Enforcement Items Not applicable.
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t Licensee Action'on Previous!v Identified Deviations
_ Electrical Fire Barriers (IE Inspection Reports No.
No. 50-346/76-18. No. 50-346/76-25, No. 50-346/77-08 and No.
50-346/76-02, 50-346/77-15)
As documented in IE Inspection Report No. 50-346/77-15 to vertical panels, central panels, cable tray and wircu
, matters relative Report Supplement No. 3, dated April 8. 1977, is Nuc ays are closed.
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valuation i
Regulation's (NRR) approval of the design for redundant Clas frs actor (
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installed in metallic conduit.
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s lE cables V
taken by Toledo Edison Company (TECo), this matterBased upon NRR's approv
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i NRR's October i.e., item 15 of 6-8, 1976 visit, is c1csed.
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Other Significant Items A.
Systems and Components 1.
10 CFR 50.55(e) Reports (Review of Corrective Actions)
Diesel Generator Sequencer - Anti Pump a.
This matter was resolved in accordance with TECo's letter to RIII dated January 21, 1977.
(Closed)
b.
Diesel Generator Sequencer - SFAS This matter was resolved in accordance with TECo's letter to RIII dated March 23, 1977.
(Closed)
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Westinghouse Motor Control Centers - 400 Amp Stabu (
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Thic matter was resolved in accordance with Tr.co's letter to RIII dated April 4,.1977.
(Closed)
d.
Component Cooling Surge Tank Instrumentation This matter was originally reported to HIII in accordance with the requirements of 10 CFR 50.55(e).
Evaluation was made by TECo on March 2, 1977 trat the matter was not considered to be reportablu. The RIII inspector concu'rred with the evaluation as documented.,This matter is closed.
e.
Veland Valves Licensee is currently reviewing the documentation on the
yoke material and replacement stems used on seven Velan
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supplied valves and operators. This item continues to remain open.
f.
High Pressure Injection Pumps The licensee is currently reviewing the documentation on components for the High Pressure Injection Pump bearing forced lube oil system. This item continues to remain open.
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Final System Ralkdown x_ /
Observations were made of Class lE instrumentation identifi-cation, conduit color coding, and separation-protection of instruments and sensing lines. All of the above items were determined to meet NRC requirements and licensee commitments.
Also observed were cable tray thermal blankets (Kawool) and cable spreading room penetration seal installations.
Kawool was approximately 98% completed; the ' cable spreading room seals were virtually completed. Areas other than the spread-ing room, which require sealing, were approximately 60% completed
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B.
Facility Items (Plans and Procedures)
None.
C.
Managerial Items The licensee reported that as of April 1, 1977 approximately 881 construction personnel were employed at the site.
Further, system turnover from Bechtel to TEco was progressing as expected and the projected " milestones" to be accomplished prior to plant were being reasonably maintained on schedule.
start up
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Deviations None idenLified.
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Status of Previously Reported Unresolved Items 1.
Reactor Protection and Safe!mard System Cabinetn (TF. Inspection Reports No. 50-346/73-23, Mo. 50-346/75-24, No. 50-346/76-02, No. 50-346/ 76-13, No. 50-346/76-18, No. 50-346/ 76-25. No.
50-346/77-08, and No. 50-346/77-15)
As documented in IE Raport No. 50-346/77-15 and the Davis-Besse Unit 1 Safety Evaluation Report Supplement No. 3, dated
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April 8, 1977, item 7.2, the matter of cabinets and reactor coolant flow transmitter sensing lines will be resolved between TECo and NRR and as such will no longer be reported by RIII. NOTE: This matter is also identified as item No. 5
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in the report of URR's October 6-8, 1976 visit.
2.
Fire Barrier Tests (IE Inspection Reoort No. 50-346/77-15)
On April 6,1977 a meeting was held with NRR and members of IE's staff relative to fire barrier testing. As a result of the meeting, it is RIII's understanding that a condition of TEco's operating license will include requirements for retest-ing, further documentation < f tests aircady performed, or some f-s other method of removing e doubt concerning the identified
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discrepancies.
Relative to RIII reporting requirements, this matter is resolved.
3.
Valve seismic oualifications (IE Inspection Report No.
50-346/77-15)
As previously reported, examination of seismic documentation for the decay heat system valves Hv DH 11 and Hv DH 12 were found to be inadequate in that the math model for the system failed to consider that these valves were installed at 46 from the vertical. During the inspection the licensee produced
- interim calculations which indicated that this discrepancy was an acceptable deviation. A conforming math model and comprehensive seismic analysis is now available at the sitt, and is acceptable. This matter is resolved.
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LIE Inspection Report No. 50-346/77-15)
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Documents to certify that
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operated dampers in the !!catinn Ventilating and Air Cthe m
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System arc scismien11y qualified, are being compil d
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onditioning considered incomplete.
e and are This item remains open.
Mannnement Interview
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A.
The following persons attended the Management
clusion of the inspection:
Interview at the con-Toledo Edison (TECo)
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L. E. Rowe, TECo Vice President J. D. Lenardson, QA Manager
C. R. Comeck, Nuclear Engineer
G. W. Eichenauer, QA Engineer
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E. C. Novak, General Superintendent Power i
D. A. Poage, QA EngineerR. E. Blanchong, Engineering and Con
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, Construction Manager i
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E. M. Wilcox, QA Supervisor C. T. Daf t, QC Supervisor J. C. Buck, QA Engineer
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Bechtel Company (Bechtel)
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p R. RosenthalC. L. Houston, Field Construction Manager
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I Project Manager P. P. Anus, Project Engineer H. F. McCluskey, Project Operations W. C. Lowery, Quality Assurance Engineer R. W. Jackson, Mechanical EngineeringJ. D. Heaton,
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l C. - D. Miller, Project Engineer
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B.
Matters discussed during the interview were as foll ows:
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1.
of large piping hangers and anchors within the s examiaation spray and containment spray systems.
t urizer these remarks and' stated that a very significa tThe licensee acknowled progress to fully complete this work.
effort was in n
Report Details)
(Paragraph 1,Section I,
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2.
.The inspector reported that he reviewed the conforming seis satisfactory. reports for decay. heat valves Hv DII 11 and 12 and f This previously identified unresolved matter i ound them resolved.
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3.
The inspector reported that it is his understandinn that the (,~)
Reactor Vessel Calibration Source Shroud Tubes (two) are to be
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replaced because of damage incurred through handling. The licensee acknowledged and confirmed this remark.
4.
The inspector reported that he reviewed the re-work of approxi-mately 70 small (2 - 31/2 inch) valves including associated hydrostatic test requirements. The effort although incomplete meets the pertinent requirements. The licensce acknowledged this remark.
5.
The inspector. reported that he reviewed the previously identified Electrical Fire Barrier issues which are avaiting NRR action.
The licensee acknowledged this remark.
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The inspector noted that he reviewed open 10 CFR 50.55(e) items and the following issues were ecsolved:
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(a) Diesel generator sequencer anti-pump (b)
Diesel generator sequencer SFAS (c) Westinghouse motor control centers 400 amp stabs (d)
Component cooling surge tank
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Further, the inspector stated that he performed a walk-down inspec-
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tion of the Class lE instrumentation system and components.
The licensee acknowledged these remarks.
7.
The inspector reported that he examined the status of the reso-lution of reactor protection and safeguard system cabinet. This matter is to be resolved by NRR.
The licensee acknowledged this rcmark.
8.
The inspector stated that the questions relative to the adequacy of existent testing and certifications relative to representative fire testing of penetration sealant and fire barrier materials is to be resolved by URR.
9.
The inspector stated that the documentation on Velan valves, High Pressure Injection pump lube oil system modification and ilVAC damper motor operators remained incomplete.
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10.
The inspector stated that work on s
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series remain to be accomplished everal EIRs 5000 and 8000 they proposed to complete the wo k bThe licensee statdd that s
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(Paragraphs 1 and 2,Section II y the end of April 1977.
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, Report Details)
11.
The inspector stated that during ha he identified several instances ot dinger installation verificati licensec stated that mensional errors.
(Paragraph 3.c, Section IIthis matter will be reviewed fu
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The
, Report Details)
rther.
12.
The inspector stated that erated by Grinnell and determined they whe reviewed the closu
manner.
(Paragraph 4 Section II, Report Dere closed in an acceptable
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13.
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etails)
i The inspector stated that he had sel ing syste
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hangers; ms for inspection of installed seismic restraints these being:
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(a)
Spent fuel pool cooling system
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(b)
Main feedwater system t
(c)
Main steam lines No deficiencies were noted in the the steam lines where the install dfeedwater sy
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screpancy items were noted in
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ance with the Bechtel drawing. FCN's had been generated foritem e
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these changes, but had not as y t b
'd revisions.
(Section III, Report Details)een incorporated in drawing e
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Section I-g rOu ' TO '.. b.
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Prepared by C. C. IJ1111ams Reviewed by D. W. Ilaycc
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Persons Contacted The following persons.in addition to those listed in the n,nagement Interview section of this report were contacted during this inspection.
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Toledo Edison (TECo)
J. Tapley, H.P. Foreman
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D. Rhodes, QC Engineer
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Bechtel Company.
L. Savastio, QC Engineer
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T. Horst, QC Engineer Inspection Results
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1.
Pipe Hangers and Anchors
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The inspector performed a detailed examination of the Pressurizer Spray surge line and Containment Spray piping systems.
Every attri-
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bute and/or design detail documented on the drawings and instruction for the selected hangers and anchors was compared to the as-built condition observed in the plant. Measurements were made where appropriate. Documentation and production control measures were also examined in detail. This inspection task was accomplished on a total of 10 hangers and/or anchors within the pressurizer spray and contain-ment spray systems which were at various stages of completion. The
remaining hangers were observed.
Shock suppressor attributes were included in this examination.
a.
Inspection Results l
A number of minor dimensional deviations were noted during these examinations. One significant deviation from the current as-built drawings was identified, however, review of the con-tractor documentation showed that this matter had been previously identified and the proposed corrective action was controlled.
An area of inadequately consolidated concretc was identified concurrently by the licensce's representative and the NRC
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This matter van documented on 11cchtel rion (
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corrective action procedures.""""'""""*"'"""""'""'""""norn-A significant portion of the large and small remains to be accomplished.
piping hanger work
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ing subsequent inspections.
This matter will be revieded dur-b.
Examples of Items Reviewed
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(1) Ha'nger No. PS-H2O (2) Hanger No. PS-H21 (3)
Hanger No. 34-GCB-5-H9 (FI/2)
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(4)
Hanger No. 34-GCB-H7 (F2/3)
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(5)
Hanger No. 34-CCB-H5 (F2/3)
(6)
Hanger No. 34-GCB-H25 (F3/2)
(7)
Hanger No. 34-CCB-5-H6 (FI/3)
2.
Reworked Sen11 Valves 1. 2 and 3
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As previously reported, a number of small
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installed and accepted have subsequently been reasons.
(Damaged b valves which ucre previously work is in progress.y debris during flushing op'erat reworked for various the licensee and Hartford Steam Boiler I This pany dated >! arch en 24, 1977 hydrostatic testing of the subject small valwhich confirmed th quirements for ves.
The following listing identifies example the associated documentation and work s of these valves for which inspector:
observations were made by the a.
Valve No. RC 30 b.
Valve No. RC 36 c.
Valve No. MS 756 d.
. Valve No FRI 404 e.
. Valve No. MU 459 f.
Valve No. CF 102
Valve No. MS 485 h.
Valve No. FW 62 1.
Valve No. FW 145
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The progress of this effort will be monitor d d inspections.
e uring subscquent O
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,y p REPORT DETAILS
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Section II Prepared by: [ "'E /'
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K. R. Naidu (Date)
Reviewed by:
R. F. !!eishman (Date)
Persons Contacted
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The following persons in addition to those list d i Interview section of this report were contacted d
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e n the Management Bechtel Corporation (Bechtel) '
uring this inspection.
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D. C. Raylon, QC Mechanical Lumm Irsay (LI)
'T. E. O'Connell, Project Manager Toledo Edison company (TECo)
A. M. Casalena, QC Inspector i
1.
Review of Status of EIR Items (5000 Series)
The inspector was informed that be accomplished by the. electrical and mechanica tively.
emain to are scheduled for completion by. the end of AprilThe contractor respec-nspections i
, 1977.
2.
Review of EIR Items (8000 Series)
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The inspector was informed that the installati
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The licensee stated that the installation and isupports
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scheduled for completion by the end of Aprilnspections are 1977.
3.
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_Large and Small Pipe 11 angers (Verification of Installation)
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~ Inspection Objectives
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To ascertain whether large and small pipe hang safety related systems are in accordance with the l t ers installed In s
a est revision t
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of the respective drawings and whether innpection findings
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. d identified by the Rill inspector during the current
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innpection were previously reported during the contractor's QC hanger inspections.
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b.
Inspection Objectives Accomp1fshed by:
(1)
Selectively identifying hangers in !!akeup and Purifi-cation System !!ath Model Drawing, (Probicm 69A) -
L2310.
(1)
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Selectively identifying hangers in High Pressure Injec-tion System - Auxiliary Building (Math Problem #33(01)
j Drawing H-233D, Revision 1.
(3)
Selectively identifying hangers in !!1gh Pressure
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Injection System Containment Building (Math Problems T-003-2b, T-004-2b, T-004-lb, T-003-lb) Drawing H-233E.
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(4)
Low Pressure Injection System Auxiliary Building (Math Problem A-66) Drawing H-233F.
(5)
Discussions with lic.sce and contractor personnel.
Inr.uection Findings c.
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During the inspection, the dimensions indicated on the hanger
sketches were verified:
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i Several instances of dimensional errors were identified.Since no tolerance was specified in the hanger sketch, dimensional
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errors 1/8" and less are identified as minor dimension errors.
The hangers inspected and the respective findings are listed l
below.
inspected by the contractor are denoted by asterisks.Those Makeup and Purification System Hanger No.
Findinns
- 31 IICC-36-H2 3 minor dimensional errors.
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- 31 HCC-5-H3 1 minor dimensional error.
- 31 CCB-13-H25 No error.
High Pressure Injection System
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- 33C-CCB-2-H40
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9 dimensional errors (only l
some of the errors were identi-
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- 3 3C-CCB-19-ill 2 1 dimensional error.
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- 3 3C-CCD-19-l!! 3 1 dimensional error.
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Tile licensee stated that the A/E mechanical enginecen would evaluate the findin;;s indleated above. This matter will be reviewed during a subsequent inspection.
4.
Observation of Protection to Installed Equipment During the inspection, the RIII inspector identified tube ends of flow transmitter FT-MU-31 being left open without protectivo end caps and change in hanger location for the lube oil line relative to High Pressure Injection pump forced bearing lube oil system.
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TECo QC inspector documented these findings on surveillance reports i
'300.75-52 and 56 dated April 7, 1977.
Prior to the conclusion of the inspection it was reported that instrumectation tubing was
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disconnected at the Dragon Valve, flushed with demineralized water,
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reconnected and then recapped. A NCR was generated to correct the h' anger deficiency.
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5.
Review of Crinnell NCRs i
The inspector selectively reviewed NCRs (Deviation Reports) gen-
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erated by the ITT Grinnell the mechanical contractor and determined that they were resolved in an acceptable manner.
Excerpts.of the
NCR review.are as follows:
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a.
Deviation Report F-885
q Report F-685 dated March 21, 1977, identified that QA docu-i
ments on welds in the seismic 1 area of the print PM207B were
not available since at the time the welds were completed 3
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years ago, they were not considered safety related.
Correc-tive action recommended was to waive documentation requirements.
The NCR had not yet been closed.
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Deviation Reports F-871 & F872 i
The above reports dated Februnry 25, and March 2, 1977,
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respectively identified that weld data documentation for several field welds were missing and recommended to accept
" weld: data record" since (1) all weldors who per' formed the welds were qualified to welding procedures utilized,
(2) all weld rod purchased. met nuclear class requirements,
and (3) all welds successfully passed hydrotest. The
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recommended disposition was accepted as evidenced by the
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necessary signoffs.
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- 33C-CCB-2-Il38 Incorrect wcld symbol used.
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- 33C-CCB-2-II-37 Neither staking of the threads
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on the sprinn hanger nor weld-ing as specificd in the astuilt drawing had been accomptished.
A Corrective Action Field Inspection Report was written prior to the conclusion of the inspection.
- 33C-CCB-2-II39 1 apparent pipe shift, 1 minor dimensional error.
~*33C-CCB-2-H47 l' major, 1 minor dimensional deviation.
Contractor QC Inspection identified the errors but were not picked up
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in asbuilt drawings.
33C-CCB-2-H50 No error.
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33C-CCB-2-H51 No error.
33C-CCB-2-H51 No error.
33C-CCB-2-H36 No error.
33C-CCB-2-H28 No error.
Errors due to pipes shif t.
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- 33C-CCB-2-H26D
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3 minor dimensional errors.
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33C-CCB-2-H42 No error.
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33C-CCB-2-H45 No error.
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- 33C-CCB-2-H46 1 minor dimensional error.
- 33C-CCB-2-H44 2 minor dimensional errors.
Low Pressure Inicction System (Auxiliary Building)
- 33B-CCB-2-H6 2 minor dimensional crrors.
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1 dimensional arror
A corrective Field Inspection Report was written on April 7, 1977, prior to the conclusion of the inspection.
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Deviation Report F-683
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The above report dated March 19, 1976, indicated that during the process of welding a l'4" x 180 x 6" anchor attachment
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plate to spool piece 21-I!CC-36-4 (2 1/2" schedule 10, 0.12 wall) a 3/16" hole developed in the pipe adjacent to the veld.
Recommended corrective action to grind the edges of the cavity perimeter and deposit Elller material was not approved. Grinnell was required to cut the damaged section of the pipe and replace the pipe section.
It was reported that Grinnell generated an internal DR 684 report to perform the repair; Field welds (FW) 53A and 54 were used to replace the damaged section of the pipe as' indicated in planner 5654; the repair was completed on March 29, 1076.
d.
' Deviation Report F864
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s The above report dated February 19, 1977, identified that valve bonnet on item 10, 1" globe valve'D40-27 was damaged during removal for maintenance.
Corrective action to sub-stitute a bonnet from valve D40-38 was not approved. The entire valve was to be replaced.
It was reported that Construction Work Permit No. 83-M-76 dated February 26, 1977, required the entire valve to be replaced.
Rork, including reinspection was documented to be complete on March 27, 1977.
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REPORT DlfrAILS V
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Section-III Prepared by k'Yh[< I
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W. J. Key (Date)
Reviewed by R. F. Heishman (Date)
Persons Contacted,
The following personnel, in addition to those listed in the Management Interview section of this report were contacted during the inspection.
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Toledo Edison Company (TECo)
John Bauchman, Quality Control Engineer Bechtel Power Corporation (Bechtel)
Carl Cote, Field Hanger Engineer
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Results of Inspection
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Seismic Pine Restraints and Hangers v
1.
Spent Fuel Fool Cooling System The inspector selected as-built sketches of sections of the system from drawings, then inspected the installed restraints and hangers
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for conformance with these sketches.
There were no deficiencies noted in the areas inspected in this sys-tem.
The following drawings and sketches of the spent fuel pool cooling system were selected for this inspection.
Drawing Isometric No.
As-built Sketch No.
235A-80B 35-HCC-26-H11
'35A-T-009K 35-IICC-76-il4
35-ilCB-9-il23 35-IICB-10-Il2 235B-T-009R 35-JCB-9-il29
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235B-T-009J 35-licn-24-II9 35-IICB-6-II4 (/
Main Feedwater Svstem The following restraints and hangers were selected from drawing No. C-613, Revision 4, and inspected. There were no deficiencies
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noted in this system.
S.R. No. 24 H-No. 9 S.R. No. 26 H-No. 11 3.
.
The following seismic restraints and hangers of the main steam lines were selected and inspected.
,
Seismic restraint S.R. No. 6 at elevation 629'0" on drawing a.
No. C-609, Revision 7.
The Bechtel drawing disagrees with vendor drawing 7749-CC-123-2, which shows a 2.7" dia. stud.
Bechtel drawing C-609, Revisian 7 shows this stud to be 1 1/4".
Field Change Notico (FCU) No. 5770, dated February 10, 1977, was generated but uas not added to the drawing.
[' 'j}
Action was taken by TECo to incorporate FCN No. 5770 into the drawing.
s,,
Seismic Restraint-Ho. S.R. 8 at eleva' tion 644'3" on Bechtel c.
drawing No. C-611, Revision 12 does not incorporate struc-tural steel changes as shown on FCN No. 3665, dated September 24, 1975 and FCU No. 3840 dated October 29, 1975.
FSK-M-653 revision 1 and FSK-M-654, revision i Bechtel
. generated an NCR to incorporate the changes to show the as-built item on the drawings.
Hangers No. H-9 and H-il were inspected and found to be c.
in accordance with the drawings.
d.
During the inspection it was noted that the snubber on
.
main steam hanger S.R. 7 was leaking. A Corrective Action Field Inspector Report (CAFlR) No. 1061 was generated to correct this condition.
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