IR 05000454/1983019
| ML20024A336 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 05/16/1983 |
| From: | Ang W, Jape F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20024A334 | List: |
| References | |
| 50-454-83-19, NUDOCS 8306170023 | |
| Download: ML20024A336 (5) | |
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paato UNITED STATES g
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NUCLEAR REGULATORY COMMISSION
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a 101 MARIETTA ST., N.W, SUITE 3100
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ATLANTA, GEORGIA 30303
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r Report No.: 50-454/83-19 Licensee: Coninonwealth Edison P. O. Box 767 Chicago, Illinois 60690 Docket No.:
50-454 License No.:
CPR-130 Facility Name: Byron Station Unit 1 Inspection at Byron Station site near Byron, Illinois Inspector: b
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Date Signed F A-6'3 W. P. Ang Approved by:
4 o#t, 5!/6/cf3 F. Jape, Section Chief
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Date Signed Engineering Programs Brandff Division of Engineering and Operational Programs SUMMARY Inspection on April 27 - 29, 1983 Areas Inspected This routine, unannounced inspection involved 17 inspector-hours on site in the areas of testing of pipe support and restraint systems.
Results Of the area inspected, no violations or deviations were found.
8306170023 830527 ~
PDR ADOCK 05000454 Q
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- R. E. Querio, Station Superintendent
- V. Schlosser, Project Manager
- R. C. Ward, Assistant Superintendent, Administrative and Support Services
- P. Donavin, Project Engineer
- A. L. Javorik, Engineer, Technical Staff
- B. Koehler, System Test Engineer, Technical Staff Westinghouse (W)
D. Fraser, Byron Structural Services Manager
- M. Pitlyuk, Mechanical Engineering Manager
- J. Koziol, Structural Engineering Manager B. Manz, Piping Design and Analysis Manager NRC Region III Inspector
- 1. Ring
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on April 29, 1983, with those persons indicated in paragraph 1 above. The licensee was informed of the inspection finding listed below. The licensee acknowledged the inspection finding with no dissenting comments.
Unresolved Item 454/83-19-01, Pipe Supports Sysems Thermal Expansion Testing Question, paragraph 5.d.
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Licensee Action on Previous Enforcement Matters Not inspected.
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Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or devia-tions. New unresolved items identified during this inspection are discussed in paragraph 5.d.
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5.
Testing of Pipe Support and Restraint Systems (70370B) - Unit 1 (a) FSAR
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The licensee's FSAR requirements and commitments regarding system design criteria and examination and testing of safety-related pipe support and restraint systems during hot functional testing were reviewed. The piping system design criteria was outlined in FSAR Section 3.7.3.
The licensee's program for examination and testing of safety-related supports was outlined in FSAR Section 3.9.2, Tables 14.2-27, 54, 58, 59, 60, and responses to NRC Questions 110.37 and 110.63.
FSAR Section 3.7.3.3.2 Amendment 33 states that "All seismic Category 1 piping except for the reactor coolant loops is designed by Sargent and Lundy, including the location of supports and restraints". During the inspection and during discussions with the licensee, it was noted that W, not Sargent and Lundy, was providing for the design and analysis of aT1 safety-related seismically analyzed piping inside the containment. The licensee was requested to further determine the accuracy of the FSAR statement.
(b) Procedure The licensee's Test Procedure (TP) 2.028.10 Revision 2, Tnermal Expansion Primary Side (EM), up to and including Test Change Request (TCR) Number 27 was reviewed for compliance with FSAR requirements and commitments. The procedure provided for examination of applicable piping support systems to detect interference and displacement due to thermal expansion and to determine the setting of snubbers and spring type pipe supports. The examinations were required by the procedure to be performed at ambient conditions, 250 F, 350 F, 450 F and at the maximum no-load temperature.
In addition, an examination was also required to be performed upon cooldown to ambient conditions to correlate with baseline data. The following items were noted during the review of the test procedure:
(1) TP 2.028.10 Revision 2 had been reviewed and approved by Project Engineering. However, 27 TCR's had been issued to the procedure.-
Many of the TCR's had not been reviewed by Project Engineering for accuracy of the pipe support listing and its corresponding thermal movements.
(2) Pipe support ISI24008S was listed on inspection data sheet 11.9 of TP 2.028.10 as a rigid type support. Appendix D of TP 2.028.10, the support drawing and the Project Engineering listing of supports required the support to be a snubber type support. Subsequent NRC inspection of the support verified it to be a snubber type support.
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(3) Pipe Support 1SI24001V, a spring type support, was required by pipe support isometric drawing number M-2539C Rev. D sheet 7 and the Project Engineering pipe support listing. TP 2.028.10 does not list pipe support 1SI24001V.
Subsequent NRC inspection noted that the support was not installed.
(4) Pipe Support 1SIO6038S, a snubber type support, was required by the Project Engineering listing but was not listed in TP 2.028.10.
(5) Typographical errors in TCR's for TP 2.028.10 regarding pipe supports IFW16013V and ICV 8070X were noted by the inspector and corrected by issuan.ce of a TCR by the licensee during the inspection.
(c) Observation of Pipe Supports at Ambient Conditions Safety Injection subsystem ISI24 and Chemical Volume and Control subsystem ICV 11 were randomly selected and their pipe supports were sampled and visually inspected. The pipe supports listed below and
'their corresponding support structure were visually inspected at ambient condition for conformance with pipe support drawing requirements, deterioration, corrosion, deformation and initial settings.
In addition, Steam Generator "C" hydraulic snubbers were inspected for hydraulic fluid level and leaks.
Dynamic Pipe Supports 1SI24008S ISI24012S 1CV11010S 1CV11011S 1CV11009S 1RC01BC-A Hydraulic snubber IRC01BC-B Hydraulic snubber Fixed Pipe Supports ISI24011X 1SI24015X 1CV11012V 1CV11014V 1CV11018V Based on the inspectors visual examination of the supports listed above and the subsequent inspection of applicable licensee ambient condition pipe support examination records, the following items were noted:
-(1) Pipe support ISI2400BS was observed to be a snubber type support. The licensce's ambient condition examination records verified it to be a rigid type pipe suppor n
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(2) The cold load setting for spring type support ICV 11012V was observed to be at approximately 335 pounds. Engineering Change Notice (ECN) 47609 requires it to be set at 435 pounds. The W Structural Engineering Manager stated that issued ECN 567 further changed this to a cold load setting to be 456 pounds. The licensee's ambient condition examination did not identify the noted discrepancy.
(3) The cold setting for snubber type support ICV 11010S was observed to be at approximately 1 inch. The pipe support drawing requires a cold setting of 1 3/16 inch.
(4) Snubber type support ICV 11019S had a cold load setting of approximately 17/8 inch. The pipe support drawing required a cold load setting of 1 1/8 inch.
Drawing noted pipe movements indicated a potential for this snubber reaching its full range of travel. The licensee had noted this condition but had not written a deficiency nor obtained an engineering evaluation regarding the noted condition.
In addition, the weld location between structural member piece 4 and the supporting W4X13 member did not appear to be in accordance with the pipe support drawing.
(5) Steam Generator "C" hydraulic snubbers 1RC01BC-A and B had signs of hydraulic fluid leakage. The hydraulic fluid reservoirs were empty. The licensee had identified this condition for all eight hydraulic snubbers on the four steam generators on deficiency number 4348 issued 4-14-83.
However, the licensee was unable to determine if a 10 CFR 50.55(e) or 10 CFR 21 reportable condition had been identified.
In addition, an engineering evaluation for the acceptability of performing hot functional testing with the above noted condition had not yet been performed.
(6) Construction protective covers for snubbers had been removed for testing and subsequent plant operation. During the inspection it was noted that water was leaking on mechanical snubbers of support ICV 11010S and 1CV11011S. The acceptability of the noted condition had not been evaluated.
(d) Based on the findings noted in paragraph 5(a), (b) and (c) above, it
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was concluded that further determination by the licensee of the applicability of the noted items was required. The licensee had agreed to research engineering documents, ECN's, drawing changes, construction documentation, etc., to determine if the noted conditions had already been identified, evaluted or resolved prior to the inspection.
Pending further licensee determination of existing documentation, the items noted in paragraphs 5(a), (b) and (c) were identified as Unresolved Item 50-454/83-19-01, " Pipe Support System Thermal Expansion Testing Questions".
No violations or deviations were identified.