ML20098G797
| ML20098G797 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/18/1984 |
| From: | Van Brunt E, Van Bruntt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Bishop T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| REF-PT21-84-471-000 ANPP-30549-TDS, DER-84-30, PT21-84-471, PT21-84-471-000, NUDOCS 8410050530 | |
| Download: ML20098G797 (5) | |
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liECEIVED
!!nc Arizona Public Service Company
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!M SEP 21 pg g g September 18, 1984 gggg ANPP-30549-TDS /TRB U. S. Nuclear Regulatory Commission.
Region V Creekside Oaks Office Park 2 1450 Maria Lane - Suite 210 Walnut ' Creek, California 94596-5368 Attention: Mr. T. W. Bishop, Director
, Division of Resident.-
Reactor Projects and Engineering Programs
. Subject : - Final Report - DER 84-30 A 50.55(e) Reportable Condition Relating to Iraproper Documentation Of Diesel Generator Components.
-File: 84-019-026; D.4.33.2
Reference:
A) Telephone Conversation between P. Narbut and T. Bradish on May 11, 1984 B) ANPP-29669, dated June 5,1984 (Interim Report)
C) ANPP-30306,' dated August 23,1984 (Time Extension)
Dear Sir:
Attached is our final written report of the deficiency referenced above,
-which has been determined to be Not Reportable under the requirements of 10CFR50.55( e).
Very truly fours, E. E. Van B runt, Jr.
APS Vice President Nuclear Production ANPP Project Director EEVE/TRB/nj fAttachment
= ce:- See Page Two-8410050530 040918 PDR ADOCK 0500052G S
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Mr. T. W. '. Bishop DER 84-30
-Pag 3 Two cc:'
Richard DeYoung,-Director-Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. -20555 T. G. Woods, Jr.
.D. B. Karner-W.-.El Ide
-D. B.-Fasnacht-A. C. Rogers L. A. Souza D. E.. Fowler T. D. Shriver-C. N. Russo
!J; Vorees J. R. Bynum
. J. M. - Allen J. A. Brand --
D. N. Stover
'A.'C. Gehr
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W.' J.-Stubblefield W. G. Bingham;
-R. L. Patterson R. W. Welcher-
-H. D. Foster D. R.- Hawkinson -
L. E. Vorderbrueggen s
R. P. Zinumerman S. R. Frost L. Clyde
-M. Woods T. J. Bloom
-Records Center
- Institute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500-Atlanta, CA' 30339-Mi i
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- ,7 FINAL REPORT - DER 84-30 n
" DEFICIENCY EVALUATION 50.55(e)
ARIZONA PUBLIC SERVICE COMPANY (APS)
PVNGS UNITS 1, 2, 3 I.-
Description 'of Deficiency Corrective Action Report (CAR) C83-186N reported that certain parts -of the Diesel Generator package do not have ASME Section III documentation at the jobsite. The parts in question are within the ASME Code boundaries established by P&ID 13-M-DGP-001, Rev.12, and the vendor (Cooper Energy
-Services). They.are located'on the Train A and B lube oil and Jacket water heat exchanger subsystems. ' The parts that lack
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the code required documentation for each heat exchanger, as shown in the CAR, are listed below:
'1. Four 1" dia, half couplings. (these are for three
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thermowells and an isolation valve).
2; One' reducing bushing.
- 3. One isolation valve. ' (PSPA V341,-FSPA V342, PSPB V441, PSPB 442):
- 4. Two 3/4" dia. - half couplings for vent..and drain lines.
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. 5. ~ Six attactment welds for items 1 and 4 (half couplings).
2.
The CAR was generated based on an ASME code documentation review of the Unit 2 diesel generators. The N-1 Manufacturer's Code Data Reports -( American Standard Heat
- Transfer Division) for each of the items do not list these parts, nor is there any supporting documentation, i.e.,
material certifications, weld documentation, etc., available
'in the files.
In addition to the four isolation valves listed above, further b
investigation has found 26 other root valves not "N" stamped.
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These valves 'are also located ' on the. jacket water and lube oil subsystems as well as one valve per train on the intercooler water outlet.. The Unit 2 valves which do not conform to ASME Section III requirements, and have no traceability, are listed below by tag number:
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e i Mr. T.)W; ; Bishop P
cDER 84-30 Page Two 2
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' Train A Train B 2PSPAV340' 2PSPBV440 2PSPAV341 2PSPBV441 2PSPAV342 2PSPBV442 ~
2PDGAV503 -
2PDGBV603 2PDGAV504 2PDGBV604 2PDGAV506 2PDGBV606 2PDGA1507-2PDGBV607 2PDGAV508 2PDGBV608 2PDGAV509 2PDGBV609
- 2PDGAV511.
2PDGBV611 2PDGAV512 2PDGBV612 2PDGAV513 2PDGBV613 2PDGAV514 2PDGBV614 2PDGAV515 2PDGBV615 2PDGAV516
-2PDGBV616 p.,
Evaluation >
With' respect to-the reducing bushing, in volume one of the' '
vendor instruction manual, drawing KSV-58-7 parts list, item number 148 shows 15-1" x 1/2" bushir.gs manuf actured 'to ASME-Section III requirements.- Furthermore, the bushing, the four
- 1" and two 3/4" half couplings were examined at the supplier's
. facility by an authorized inspe'etor. Quality Surveillance j.
' Reports (QSR) 123,.125,126,- 127; 157,1 and 164 f ound the code documentation-to be satisfactory.
QSR-121 and 124' stated-that t
documentation for some half couplings was missing from the file. The missing-documentation was later. f ound, as recorded by QSR 215. -Therefore, call required documentation for the bushing and,the half couplings are satisfactory -~and on file at -
the supplier's facility.
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Weld ' documentation for' atta-hing the six half couplings is maintained ~at the supplier /sub-supplier's f acility. ASME Code,Section III, Subsection ND, Paregraph ND-4322.1 allows maintenance of weld records b" the manufacturer or installer or identification of welds by stamping. Theref ore, the
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welding 11s in conf ormance 'with code.
- It is
- the. opinion.of Cooper Energy Services (CES), the supplier of the' root valves, that the valves listed above do
.not.have to be ASME Section III,' Class 3.: Consequently, the
. root valves supplied for all 3 units-were not N-stamped.
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~ The' root cause of: this discrepancy is a difference in code interpretation which will ultimately be resolved by the
'ASME Conaittee.-
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' Mr. T.cW2 - Bishop.
4 1 DER 84-30 "
- Page Three '-
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- II. :
,- Analysis of Safety Implications n-L Each' valve -has been stamped with a serial number by the vendor pm that is -traceable back to a 500 psi pressure test performed on i.
- each valve. Additionally, the vendor inspected the valves-
'under their Quality Control Inspection Plan QC/IP-01V g (Rev. 2,: sheets 1 and 2.
Attached to.the plan is a valve 2-rdrawing which notes that;the maximum valve test pressure is
?10;000 nt;i-(the valves are installed in a 100 psi. system).
-M l Based on:the"above, this condition is evaluated as not.
reportable under the requirements of _10CFR50.55(e) and.
Part 21; since, if lef t uncorrected, it. would - not represent a-
- significant saf ety hazard.
.Since the evaluation conducted byLBechtel Engineering -
concluded that-the ins::rument root valves are included under code jurisdiction, CES -has been asked via Bechtel letter
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B/CES-E-48254, deted May. 24, 1984 to provide.a f ormal, written justification:f rom ASME that permits. the use of' these non-ASME j
stamped root valves on the diesel generator systems.
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III;'
Corrective Action:
L As-a result of the review of 'all code-related documentation
is concluded thattall-ASME III, Class 3 documentation and
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= certifications ard correct 'and on file at', the supplier's
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facility. - Theref ore, the 1" and 3/4" half couplings, the -
reducing bushings, Land the attachment welds are dispositioned
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"use-as-is."
- With resp'ect to the-root valves, NCR SM-4593 was written to
-tocument the nonconf ormance. f 'An interim disposition has been l given to the NCR to replace the 30 Unit 1 ASME III ~ stamped '
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isolation valves with 3/8" stamped valves. This valve
' replacement: will be completed prior to Unit 1 fuel load.
u.
Concurrently, the vendor has ' written to the ASME Committee f or
- a-code clarification. '.Upon receipt of the clarificaton, Units
_1, :2, 'and 3 will be modified as required by.the ASME Committee, 7
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Since the discrepancy involves code interpretation, not valve
- integrity, no procedural ~ changes _or detailed investigations u,
are required.
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