IR 05000313/1973011
| ML19317H065 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/31/1973 |
| From: | Brownlee V, Crossman W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19317H054 | List: |
| References | |
| 50-313-73-11, NUDOCS 8004110693 | |
| Download: ML19317H065 (10) | |
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RO Inspection Report No. 50-313/73-11 Licensee: Arkansas Power and Light Company Sixth and Pine Streets Pine Bluff, Arkansas 71601 Facility Name: Arkansas Nuclear One, Unit 1 Docket No.:
50-313 License No.:
CPPR-57 Category:
A3/B1 Location: Russellville, Arkansas Type of Licensee:
B&W, PWR-2568 Mwt, 880 Mwe Type of Inspection: Special, Announced, Construction
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Dates of Inspection: July 18-20, 1973 x
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Dates of Previous Inspection: July 17-20, 1973 Principal Inspector:
V. L. Brownlee, Reactor Inspector Facilities Section, Facilities Construction Branch Accompanying Inspectors:
W. D. Kelley, Reactor Inspector
Engineering Section, Facilities Construction Branch Other Accompanying Personnel: None Principal Inspector: I!L IhtL LL
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7 N!7.2 V. L. Brownlee, Reactor Inspector, Facilities Date Section, Facilities Construction Branch Reviewed by:
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7/8//IU em W. A. Crossman, Senior Inspector, Facilities Section Date Facilities Construction Branch s
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Rd Rpt. No., 50-313/73-11-2-
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SUMMARY OF FINDINGS I
I.
Enforcement Action
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A.
Violations Certain items appear to be in violation of 10 CFR 50, Appendix B,
" Quality Assurance Criteria for Nuclear Power Plants," as indicated below. These apparent violations are considered to be of Category II severity.
73/11-Al Control of Special Processes Contrary to Criterion IX, the inspection revealed that the procedures for verifying valve wall thick-ness did not require measurements of the valves '
nozzles or weldend preparations.
(Details II, para-graph 2)
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B.
Safety Items None II.
Licensee Acticn on Previously Identified Enforcement Matters A.
Violations 73-6-Al Lack of Documentation and Effecting Followup of
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Corrective Action Regarding Possible Nonconforming
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Materials, Parts or Components i
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AP&L's letter of response, July 6,1973, is considered
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adequate. Discussion with site personnel and record raview confirms follow-up. This item is closed.
(Details I, paragraph 2)
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73-6-A2 Documentation of Nonconforming Materials, Parts or Components AP&L's letter of response, July 6,1973, is considered adequate. Discussicn with site personnel and record review confirms followup. This item is closed.' (Details I, paragraph 3)
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Safety Items
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RO Rpt. No. 50-313/73-11-3-IIl. New Unresolved Items i
73-11/1 Malfunction of Containment Purge Supply Valve Switch
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ROB No. 73-2
AP&L is being responsive.
(Details I, paragraph 4)
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IV.
Status of Previously Reported Unresolved Items 72-4/2 Cable Routing (Region II Letter, July 27, 1972, Item 2)
The routing of cables under the control roep removable floor may not meet safeguards and reactor protection systems separations and loading criteria.
It is our understanding that the licensee will evaluate this item and corrective measures will be initiated as may become necessary. This item remains open.
72-4/3 Cable Routing (Region II Letter, July 27, 1972, Item 2)
The separation of safety channel wiring inside the B&W f "'sl supplied panels may not meet the requirements of the safeguards and reactor protection systems separations and loading requirements.
It is our understanding that the licensee will evaluate this item and corrective i
measures will be initiated as may become necessary.
This item remains open.
72-7/1 Pressurizer Safety and Relief Valve Mounting and Connecting Piping (Region II Letter, August-21, 1972, Item 1)
t It is our understanding that the licensee will evaluate the pressurizer safety and relief valve mountings and connecting pi 'ng to assure that these have been analyzed for dynamic teaction forces during blowdown. This item remains open.
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72-11/3 Cable Installation in Control Room and Computer Room False Floor and Floor of Main Control Panels (Region II Letter, December 19, 1972, Item 3)
(See Item 72-4/2)
It is our understanding that the licensee will require.
Bechtel to evaluate cable insta11ationunder the control room and computer room false floor regarding separations, loading and quality workmanship criteria.
This item remains
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open.
N 72-12/2 Valve Wall Thickness Verification (Region II Letters, June 30, 1972, and February 16, 1973)
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The valve thickness verification program is in progress (
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RO Rpt. No. 50-313/73-11-4-
but has not been completed. The ultrasonic test procedure was found to be inadequate.
(Details II, paragraph 3).
This item remains open.
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Design Changes None
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VI.
Unusual Occurrences None VII. Other Significant Findings A.
Proj ect Status None B.
Personnel or Organizational Changes O
None C.
Inquiry Reports
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Nee VIII. Management Interview The inspectors met with Moore, Bland, Bean, Quattlebaum and l
Humphrey of AP&L and Beckham, Sly, Katanics, Leonard and l
Patel of Bechtel.
The attendees were apprised of the scope and findings of the inspection. No major areas of concern were discussed.
AP&L confirmed that the valve wall thickness verification
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program would be documented in a letter to RO:II defining
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scope, valves selected for measurement and engineering justifi-
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cation for those valves not to be measured.
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R0 Rpt. No. 50-313/73-11 I-1 l
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t O Cl 7 /!N DETAILS I Prepared By:
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V. L. Brownlee Date
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Reactor Inspecte
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Facilities Sec*
Facilities Co.
- cion Branch Dates of Inspection: July 18-20, 1973
Reviewed By:
w W. A. Crossman Date Senior Inspector Facilities Section Facilities Construction Branch 1.
Individuals Contacted a.
Arkansas Power and Light Company (AP&L)
N. A. Moore - Chief OA Coordinator A. C. Bland - QC Inspector (Civil)
C. L. Bean - QC Inspector (Mechanical)
E. Quattlebaum - QC Inspector (Electrical)
L. Humphrey - QC Inspector (General)
J. Marlin - Project Management b.
Contractor Organizations
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Bechtel Engineering Corporation (Bechtel)
s W. J. Stubblefield - Project Superintendent C. G. Beckham - Lead QA Engineer P. W. Sly - QC Engineer R. C. McKinnon - Lead Mechanical Engineer
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W. D. Schuster - Senior Field Welding Engineer D. O. Allred - Project QA Engineer (San Francisco)
R. E. Cameron - Project Field Engineer R. G. Paulcheck - QC Engineer G. Katanics - Project Manager B. Leonard - Engineer (Valves)
, E. Patel,- Engineer (Piping)
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R0 Rpt. N. 50-313/73-11 I-2 o
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Babcock and Wilcox Company (B&W)
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j R. M. Moore - Mechanical Engineer (Site)
2.
l Lack of Documentation and Effective Followup of Corrective Action Regarding Possible Nonconforming Materials, Parts, or Couponents
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k AP&L's letter of response dated July 6,1973, is considered adequate,,
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Discussions with Moore and review of letters to Bechtel, B&W, Combustion Engineering, AP&L operations, and the letters of response confirm
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followup by AP&L-and their contractors.
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The present program arrangements and understanding between participants should minimize occurrences of this nature.
3.
Documentation of Nonconforming Materials, Parts, or Components AP&L's Jetter of response dated July 6,1973, is considered adequate.
Discussion with AP&L/Bechtel QA/QC personnel and engineers confirms that followup action was implemented. The site project field engineer held meetings and discussions with the field engineers regarding proper reporting methods.
sessions onsite with all field engineers.The Bechtel, San Francisco, QC sta s~
Both AP&L/Bechtel QA/QC personnel indicate that they have observed an upgrading in the timeliness of reporting, report content and closing of reports.
4.
Malfunction of Containment Purge Supply Valve Switch - R0B 73-2 i
AP&L has been responsive to this area of concern and issued an inquiry I
to Bechtel, San Francisco, referencing Units 1 and 2.
The survey results will be documented by letter to Region II when available.
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R0 Rpt. No. 50-313/73-11 II-1
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DETAILS II (
Prepared By:
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j W. D. Kelley fr Date
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Reactor Inspector l
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Engineering Section i
Facilities Construction Branch Dates of Inspection: July 18-20, 1973
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Reviewed By:
'/8 -/b 7-3/-73 J. C. Bryant Date Senior Inspector Engineering Section Facilities Construction Branch
1.
Individuals Contacted Arkansas Power and Light Company (AP&L)
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j N. A. Moore - Chief, QA Coordinator v
Bechtel Engineering Corporation (Bechtel)
E. Patel - Piping Engineer (San Francisco)
G. Katanics - Project Engineer (San Francisco)
B. Leonard - Mechanical Engineer (San Franciso)
2.
Valve Wall Thickness Verification Program AP&L assigned to Bechtel the responsibility of selecting the valves important to nuclear safety (Ref: RO:II's letter of June 30, 1972)
that require wall thickness verification.
Bechtel stated that 4b valves over one-inch nominal pipe size (nps) require verification.
It is their stated intention to present an engineering evaluation
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or vendor measurement certification for acceptance of the 33 valves 2-1/2-inches and less nps. The 15 valves 3 inches and larger nps have been ultransonicly measured by X-ray' Engineering Company (KEC)
at the site.
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n RO Rp t. No. 50-313/73-11 II-2 All of the 2-1/2-inch and some 2-inch" valves were purchased from
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Velan Engineering Company (Velan). Bechtel has documentation of
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wall thickness measurements on some of these valves and they meet B16.5 requirements. The balance of the 2-inch and smaller valves were purchased from Kerotest Manufacturing Company and their wall thicknesses were measured, documented, and certified correct, prior J
to shipment.
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The wall thickness of the 15 valves 3 inches and larger were not verified in the vendors ' shops. They were measured in the field in accordance with an XEC ultrasonic procedure that had been
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approved by Bechtel. The thickness measurements were made by an
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XEC technician qualified per SNT-TC-1A to Level II for ultrasonics.
The technic'ian was instructed to measure the wa' ' thickness of the
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valve nozzles out from the neck of the valves a distance equal to the specified minimum wall thickness at 00, 900, 1800, and 270.
This resulted in thickness measurement being made on a rib on some m
valves and the technician did not take additional measurements in
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the depression on either side of the ribs.
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Detail drawings of the valves were not available onsite for Bechtel to evaluate and to instruct the XEC technician in the need of i
making additional wall thickness measurements. Measurements were i
not taken along the length of the valve nozzle ends and a visual inspection by the inspector revealed areas on valves that had outside diameters less than the adjoining pipe.
It was also observed that the weld end preparations had been modified by grinding and did not D meet the B16.5 requirement. This condition had not been recorded
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by the XEC technician.
Bechtel concurred that their r ogram for verification of valve
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wall thickness must be revise and they proposed the following
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steps:
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a.
Make contour measurements of valve nozzles b.
Review contour
(1) Design office (stress, code, design conditions)
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.(2) Cons,truction forces (installation, weld)
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RO Rpt. No. 50-313/73-11 II-3
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c.
Specify thickness requirem nts at specified locations -
measure thickness
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Evaluate new measurements e.
Prepare repair procedure if required and have approved
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Proceed with repair where required 3.
Audits An audit had not been performed of the program for verification of valve wall thickness nor the field generated documentation; therefore, the above deficiencies were not found or corrected.
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