IR 05000382/1981010
| ML20004B109 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/12/1981 |
| From: | Crossman W, Stewart R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20004B104 | List: |
| References | |
| 50-382-81-10, NUDOCS 8105270249 | |
| Download: ML20004B109 (10) | |
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U. S. NUCLEAR REGULATORY COMMISSION O
OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report:
50-382/81-10 Docket:
50-382 Category A2 Licensee:
Louisi.ana Power and Light Company 142 Delaronde Street New Orleans, Louisiana 70174 Facility Name: Waterford Steam Electric Station, Unit 3 Inspection at:
Waterford Site, Taft, Louisiana Inspection Conducted:
Apr'
7-16, 1 1
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s Inspector:
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R. C. Stewart, Reactor Inspector, P'roject Section 3 Date Reactor Projects Branch wm -
57/2 ef!
Approved:
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W.' A Crossman, Chief, Project Section 3
' Date Reactor Projects Branch Inspection Summary:
Inspection on Aoril 7-16, 1981 (Recort No. 50-382/81-10)
Areas Inspected:
Routine, unannounced inspection of construction activities and observation of work activities related to the setting in place of Reactor Coolant Pump (RCP) internals; safety-related pipe supports and restraints; and the review of QA/QC records related to the fabrication of Class 3 components for the Emergency Feedwater and Component Cooling Water systems.
The inspection involved 49 inspector hours by one NRC inspector.
Results:
No violations or deviations were identified.
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OETAILS 1.
Persons Contacted Principal Licensee Employees s
T. Gerrets, QA Manager
- L. Bass, Site QA Engineer
- B. Toups, QA Engineering Technician
- G. Pittman, OA Engineer
- J. Woods, QC C9gineer
- R. Bennett, QA Engineer
- B. Brown, QA Engineer Other Personnnel R. Milhiser, Site Manager, Ebasco R. Hartnett, QA Site Supervisor, Ebasco
- L. Stinson, Manager, 5f te Quality Program, Ebasco L. Richardson, QA Supervisor, Tompkins-Beckwith (T-B)
The NRC inspector also interviewed other licensee and contractor personnel including members of the Engineering and QA/QC staffs.
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- Denotes those attending the exit interview.
2.
Site Tour i
The NRC inspector walked through varicus construction and storage areas to observe construction activities in progress and to inspect the general state of cleanliness and adherence to housekeeping requirements.
The tour included the Reactor Building, Reactor Auxiliary Building and the Fuel Handling Building.
No violations or deviations were identified.
3.
Installation Reactor Coolant Pumo (RCP) Internals Positioning of the 1B RCP impeller assembly on the 18 Pump volute was
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completed by t;.e subcontractor. This was the first of the four RCP internals to be installed.
The NRC inspector observed the final lowering and final positioning of the assembly.
The work activities were being accomplished in accordance with the NISCO Process Control Traveler No. 804,
" installation of driver mount and rotating element subassembly" and at the dir $ction of the Combustion Engineering site representative.
Final bolt torquing and installation of the drive motor is to be done at a later date.
No violations or deviations were identified.
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4.
Safety-Related Pipe Supoorts and Restraints a.
Review Of Work Procedures The NRC inspector conducted a review of the T-B Procedurcs relative to the installation of safety-related pipe support and restraints
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and in conjunctica with the ASME,Section III, Subsection NF (Summer 1976 Addenda).
The principle T-B procedures reviewed were:
I TBP-24, " Hanger and Support Installation Procedures," Revision H, dated July 24, 1980.
TBP-44, " Installation and Inspaction of Pipe Rupture and/or Whip Restrair.ts and Seismic I Structural Steel," Revision C, dated May 12, 1980.
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TBP-25, " Inspection of High Strength Bolts and Calibration of Inspection hand Torque Wrench," Revision B, dated November 11, 1980.
No violations or deviations were identified.
b.
QC Records Review In conjunction with the above procedures review, the NRC inspector
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made a random selection of completed pipe hanger and support in..lla-tions to verify installation inspections were conducted and docu-mented in accordanca with procedure TBP-24, " Hanger and Support Installation Procedures."
The NRC inspector selected from the "Comnleted Traveler Log," The following installed hanger and/or supports for the documentation Review:
System CS-ISO-14, Hangers CSRR-333, 336, 338, 339 and 418; System SI-ISO-6, Hangers SIA-1E5, SIRR-167, and SIHR-181.
For each of the hanger and/or support assemblies, the NRC inspector reviewed the following QA/QC inspection documents:
Form GP-723-12, Revision 2, " Surveillance Report."
Form GP-723-91, " Weld Control Record."
Form GP-723-38, Revision 1, " Field Inspection Checklist."
Form GP-723-25, " Field Sketch" Form 8009, " Weld Filler Material Issue."
No violations or deviations were idertified.
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4 5.
ASME Code Class 3 Components - Documentation Review LP&L applied for a Construction Permit for the Waterford Unit 3 facility in December 1970. Major components for the Nuclear Steam Supply System were ordered consistent with the application date and anticipated licensing and construction schedule for the Waterford Unit 3 Protect.
LP&L received a Construction Permit for the Waterford Unit 3 Project in November 1974.
As described in the Waterford PSAR, Waterford components were ordered to be designed and fabricated in accordance with ASME Code Requirements in effect on the date of the applicable purchase orders.
In addition, the Waterford 3 FSAR, Sections 1.8.126 and 3.22 states in part that the Waterford 3 Project meets the intent of Regulatory Guide 1.26 (June 1975)
and that, although the N-Symbol is not required, Quality Group C (ASME Safety Class 3) components have been purchased only from suppliers wha possess the proper ASME Certificates of Authorization and that the licensee's Quality Assuranco Program ensures that an inspection equiva-lent to that performed in canjunction with an N-Stamp is imposed on Safety C14ss 3 components.
In a meeting during the week of September 29, 1980, between the NRC Mechanical Engineering Branch Representatives and LP&L/EBASCO Representa-tives, held in the Ebasco New York Offices, the cognizant NRC Representa-tives expressed a concern regarding the adequacy of the licensee's QA Program inspection requirements being equivalent to that obtained by an l
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otherwise ASME,Section III, authorized inspection agency.
In order that the licensee demonstrate the QA Program inspection require-ments were equivalent to the ASME,Section III, Class 3 r: airements for component fabrication, the NRC representatives requested the licensee provide QA/QC inspection records for the emergency feedwater and component cooling water system components for an NRC review.
During this inspection the NRC inspector conducted a detailed review of documentation relative to the licenseg's Quality Standards applied to i
the fabrication of Quality Group C (A5ME Code Class 3) components for the Emergency Feedwater and Component Cooling Water systems.
i The following tabulation summarizes the pertinent fabrication documentation i
records retained by the licensee that reflect equivalent ASME require-
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ments:
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trlLKlatitL I t LLLJWil8L K SI S 4LPs
CONTACT N0.
VENDOR H. CERT.NO.
EXP.DATE MANUF.DATE CMTR'S CODE DATA REPORTS IN PROCESS INSP.
D0C.REV.
PIPING hY 401433 Dravo N1320 3/1/82 1975-1980 Yes
- No Yes Yes
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(3/1/79)
VALVES NY 403461 Anchor N-1742/NPT 4/25/83 8/77 / 5/78 Yes
- No Yes Yes Darling 743 5/20/80 N1712 4/15/80 NY 403488 Pactfic N1202/NPT 8/4/81 1977 Yes
- No Yes Yes
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j 1203 NY 403S01 Velan N649 6/19/76 1975 Yes
- Some Yes Yes N1738 5/3/83 NY 403505 TRW Mission N1137 6/16/78 1976 Yes
- No Yes Yes
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i FEEDWATER PUMPS NY403431 8in9 ham-N1654 2/28/80 5/77 Yes
- No Yes Yes Willamette TURBINE DRIVE HEAT EXCHANGER NY403431 Bingham-842 8/6/77 10/2/75 Yes Yes Yes Willamette Turbine (for above)
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INSTRUMENTS
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NY403502 Rosemount None NA 1979 No/C of C
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Yes Yes
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Reg'd NY403565 Vickery Sinmis None NA 6/19/78 Yes
- Mo Yes Yes NY403470 BIF N2038 3/17/81 Material Not Received NY403485 ITT Barton N1957 12/9/80 Material Not Received 10/1/83
- Equivalent Code Data Reports Provided by Ebasco.
" Quality Compliance Report" and
" Release for Shipment," Form #1305.
(1 of 5)
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COMPONENT COOLING WATER SYSTEM
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VENDOR N. CERT.NO.
EXP.DATE MANUF.DATE CMTR'S CODE DATA REPORTS IN PROCESS INSP.
D0C.REV.
PIPING l
SPOOLS Dravo NY-403433 N-1320 3-01-82 1975-1980 Yes
- No Yes Yes (3-01-89)
ACCESSORIES Pathway Bellows H-106 5-05-74 6-1977 Yes
- No Yes Yes NY-403452 N-1834 2-19-77 H-1835 5-19-80 Vickery Simms None N/A 1978 Yes
- No Yes Yes NY-403565 MATERIAL
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McJunkin N-1029/
3-03-81 4/78 Date Yes
- No Yes WP3-3887 N-1029-1 Field Purchases WP3-2558 Bou9ht to Class 2 WP3-2018 ASME, Winter 1977 WP3-2134 and Suanner 1978 WP3-1235 Guyon WP3-2095 N-934-2 1- 06-81 1979 Yes
- No Yes Gulfalloy WP3-1234 N-1241 10-27-78 1978-1979 Yes
- No Yes 10-27-81 (2 of 5)
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COMPONENT COOLING WATER SYSTEM
VENDOR N. CERT.NO.
EXP.DATE MANUF.DATE CMTR'S CODE DATA REPORTS IN PROCESS INSP.
D0C.REV.
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VALVES Fisher Controls N-1387 5-19-79 1978-19/9 Yes
- No Yes Yes NY-403483 Pacific N-1202 8-04-81 1977 Yes
- No Yes Yes NY-403488 NPT-1203 Velan N-649 5-20-77 1976 Yes
- No Yes Yes NY-403501 N-1738 5-03-80 1977 Yes
- No Yes Yes TRW Mission N-ll37 6-16-78 1976 Yes
- No Yes Yes NY-403505 Lonergan N-1443 8-09-79 1979 Yes Yes Yes Yes NY-403512 Janesbury N-1228 10-27-78 1977 Yes Yes Yes Yes NY-403539 Masonellan N-1836 8-19-80 1980 Yes Yes Yes Yes NY-403606 PUMPS Babcock & Wilcox N-ll52 12-31-78 1976-1977 Yes
- No Yes Yes NY-4u3482 (3 of 5)
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COMPONENT COOLING WATER SYSTEM VENDOR N. CERT.NO.
EXP.DATE MANUF.DATE CMTR'S CODE DATA REPORTS IN PROCESS INSP.
DOC.REV.
,IIEAT EXCHANGERS
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Struthers Wells N-668 1-28-77 1976-1977 Yes Yes Yes Yes Corp. NY-403504
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Combustion N-621 5-03-76 12-10-73 Yes Yes Engineering NY-403402 (9101978)
Required by C. E.
Combustiota N-562 1-09-76 7-30-73 Yes Yes Engineerin9 (Maintained NY-403402 (9102793)
by vendor)
Cooper Bessemer N-1422 6-25-79 1976-1977 Yes Yes Yes Yes Ny-403517 TANKS Buffalo Tank Co.
N-1346 3-01-79 1977 Yes Yes Yes Yes NY-403532
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Zurn Industries N-1555 11-08-79 3-29-78 Yes
- No Yes Yes
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NY-403528 i
(Wet Cooling Towers)
i liudson Products N-1564 11-26-79 1977-1978 Yes Yes Yes Yes l
NY-403479 (Dry Coolia9 Towers)
(4 of 5)
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COMP 0NEhi COOLING WATEJ SYSTEM VENDOR N.CERI.NO.
EXP.DATE. MANUF.DATE CMTR'S CODE DATA REPORTS IN PROCESS INSP.
DOC.REV.
INSTRUMENTS _
Magnetrol N-1605 1-10-80 5-16-77 Yes Yes Yes Yes NY-403489 Pyco (Thermocouples None N/A 1978 Yes
- Ho Yes Yes NY-403899 Rosemount None N/A 1978 Some-C of C
- Ho Yes Yes i(Y-403502 Req'd Mercold None N/A 1979 No-C of C
- No Yes Yes HY-403550 Reg'd Vickery Simms None N/A 9-1977 Yes
- No Yes Yes NY-403565 BIF N-2038 3-17-81 Ma terial NY-403470 not rec'd (5 of 5)
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With reference tc the asterisk noted above, it should be pointed out that although the standard ASME " Code Data Report," which is normally provided by an Authorized Inspection Agency, was r.ot utilized.
The Ebasco " Release for Shipment No. 1305," " Quality Compliance Report," and the " Quality Assur-ance Plan For Vendors," with accompanying attachments, are observed to be equal to the ASME Code Data Reports.
In addition to the above, the NRC inspector made a comparative review of the duties of the Authorized Nuclear Inspector (ANI) (NCA-5200) versus the Ebasco Vendor Inspectors implementation requirements and the qualifications for the ANI (ANSI N626) versus the Ebasco Inspector qualification requirements The NRC inspector observed that the Ebasco Vendor Inspectors' implementation requirements are comparable to those of the ANI and that the Ebasco Vendor Inspectors' qualification requirements are more demanding than the ANI Qualifications (per paragraph 4.0 of N626).
The NRC inspector made a comparative cross check of 18 items regarding ANI duties as defined in the ASME Code versus Ebasco duties and implementa-tion requirements.
The inspection duties and activities of Ebasco were observed to be comparable to that of the ANI.
The NRC inspector observed that the documentary evidence supplied by the licensee demonstrates an inspection program for Quality Group 3 (ASME Class 3) components that is equal to, or, better than ASME Code Requirements
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during the period of fabrication and delivery.
No violations or deviations were identified.
6.
Exit Interview The NRC inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on April 16, 1981.
The NRC inspector
summarized the purpose and the scope of the inspection and the findings.
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