IR 05000338/1980023
| ML19320C386 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/04/1980 |
| From: | Compton R, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19320C381 | List: |
| References | |
| 50-338-80-23, 50-339-80-23, IEB-79-14, NUDOCS 8007160742 | |
| Download: ML19320C386 (5) | |
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UNITED STATES
NUCLEAR REGULATORY COMMISSION o
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.r REGION 11
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o 101 MARIETTA ST., N.W SulTE 310o o
ATLANTA, GEORGIA 30303 v
JUN - 51E Report Nos. 50-338/80-23 and 50-339/80-23 Licensee: Virginia Electric & Power Company Richmond, VA 23261 Facility Name: North Anna Docket Nos. 50-338 and 50-339 License Nos. NPF-4 and NPF-7 Inspection at North Anna site near Mineral, Virginia
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Inspector k.
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Date Si ned Approved by:
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[o A. R. Herdt, Section Chief, RCES Branch D'a te' Signed SUMMARY Inspection on May 12-15, 1980 Areas Inspected This routine, announced inspection involved 29 inspector-hours on site in the areas of IE Bulletin 79-14, " Seismic Analysis for As-Built Safety-Related Piping Systems" and licensee actions on licensee identified items.
Results Of the two areas inspected, no items of noncompliance or deviations were identified.
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DETAILS
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1.
Persons Contacted Licensee Employees
- W. R. Cartwright, Station Manager
- P. A. Slater, Resident QC Engineer, Construction
- R. T. Johnson, QC Engineer, Construction Other Organizations
- E. Spurrell, Head, Site Engineering, Stone & Webster (S&W)
S. K. Patel, Supervisor, Engineering Mechanics (S&W)
NRC Resident Inspector
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M. S. Kidd
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on May 15, 1980 with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
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5.
Licensee Identified Items Vepco has reported the following items to Region II as reportable items in
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compliance with 10 CFR 50.36 (Licensee Event Reports-LER's) for Unit I and
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10 CFR 50.55(e) (Construction Deficiency Reports-CDR's) for Unit 2.
These
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items are also identified in the Unit 2 Technical Specification (TS) as j
items to be resolved prior to initial criticality.
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(0 pen) Item 338/79-15-02 and 339/78-36-01:
Stress Analysis of Service Water and Component Cooling Water Systems Piping and Piping Supports. This
j; item is also identified as Unit 1 LER 78-124 and Unit 2 TS Item 7.3(4).
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Prior inspection of this item was detailed in NRC inspection Report 50-338/
79-5; 50-339/79-7.
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The inspector reviewed numerous Engineering and Design Coordination Reports (E&DCR's) concerning piping and support modifications resulting from the
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reanlaysis. Modified piping to charging pump 2-CH-P-1B; lines 2"-WS-947, 953, 962, 963 and 977; was examined in the field for conformance to dravings WS-2946A, Revision 13; WS-2952A, Revision 6; and WS-2953A Revision 11.
Modifications, additions and/or deletions of the following pipe supports were also verified by field inspection:
a.
Modified support FPH-CC-599-1 on line 3" CC-599-151-Q3, Isometric CC-208A, E&DCR P-2387B-2.
b.
Removed spring hangers H196 on line 4" WS-56-151-Q3 and H199 on line 4" WS-57-151-Q3, E&DCR OSD-10018-1 c.
Additional anchors FPH-CC-554-8 on line 2 1/2" CC-554-151-Q3 and FPH-CC-601-10 on line 3" CC-601-151-Q3, E&DCR P-2537G-2.
d.
Modified restraint shown on ZFSK-CC-550-5-9 on line 21/2" CC-550-151-Q3, E&DCR P2386B-2 S&W site engineering reported that small bore piping (6 inch diameter and smaller) and related supports, which was originally analyzed by chart methods, had been checked to verify that the original analysis was conserva-tive and that the supports could accommodate the increased movements of the large bore piping. This review effort will be examined during a future inspection at S&W Boston office. Pending examination of this information
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this ites remains open. However, this inspector considers that the require-i ments 'of Unit 2 Technical Specification item 7.3(4) have been met by the licensee.
(Open) Item 338/80-16-01 and 339/80-17-10: LHSI Discharge Lines Not Analyzed for Temperatures Below 70 Degrees Fahrenheit. This item is also identified as Unit 1 LER 80-34 and Unit 2 TS item 7.3(23). On March 10, 1980, Vepco reported to the NRC that several lines in the low and high head safety injection (SI) syste for both Units 1 and 2 had not been stress analyzed for fluid temperature '.elow 70 F. However, the SI supply water from the Refueling Water Storage Tank could be as cold as 40 degrees F.
The inspector reviewed Vepco correspondence with the NRC dated March 12 and 14 and April 8, 1980.
Reanalysis of the affected piping and supports f
resulted in modifications to six Unit I supports and three Unit 2 supports.
The Unit 1 Design Change Package with the safety evaluation and applicable
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E&DCRs OSD-0068-1 and OSD-0068B-1 was examined. The modification to Unit 2 support 2RH-R-20 in line 6" RH-427-153A-Q3 was exaniined in the field by
.this in.tpector and found in conformance with the new support detail sketch ZFSK-726B. Unit 2 E&DCR's PS-5321-2, PS-5321A-2 and PS-5321B-2 were also i
reviewed.
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The effects of the thermal load changes on containiment penetrations had
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' been reviewed by S&W. The Unit 1 penetrations were determined to be adequate
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by analysis. Preliminary S&W engineering evaluation of the Unit 2 penetra-
'I tions is that they are adequate also. Formal calculations are scheduled to j
be complete by June 17, If*0.
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Subsequent to this inspection it was determined that the loadings on the Low Head Safety Injection Pump nozzles exceed the design stress' allowables.
A number of supports in each unit will require modification. This change
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l in acceptability was apparently based on the pump suppliers recent reduction l
in allowable nozzle loads. The licensee has been requested to provide more details.
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This item remains open pending completion of the penetration evaluation and modifications to supports.
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(Closed) Item 338/79-15-03 and 339/79-21-03: Incorrect Valve Weights Used in Piping Analysis. This item is also identified as Unit 1 LER's 79-35 and 79-73 and Unit 2 TS item 7.3(6). This item relates to incorrect weights for 3 inch and 6 inch Velan swing check valves (IE Bulletin 79-04) and 12 inch accumulator discharge valves (LER 79-73). Licensee correspondence and actions related to the incorrect valve weights has been previously addressed
in NRC Inspection Reports 338/79-15, 338/79-20, 338/79-28, 339/79-21, 339/79-28, 339/79-35 and 339/79-40. Report 339/79-40 closed this item as it related to 6 inch Velan swing check valves (LER 79-35).
The inspector reviewed Vepco letters to the NRC serial Numbers 221A dated
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May 3, 1979; 221C dated May 23, 1979; and 430 dated May 30, 1979 and S&W letter to VEPCO NAS 11,556, dated May 18, 1979. These letters indicated that re-analysis of Unit 1 piping containing the 3 inch valves showed that pipe and support stresses were acceptable. They also stated that a worst
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case analysis of the Unit 2 three-inch valve weight changes showed accept-
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able pipe and support stresses. The inspector has no further questions on this matter.
LER 79-73 and Vepco lecters to the NRC Serial 409, dated May 24, 1979 and 409A dated June 20, 1979 related to weight changes for Units 1 and 2 twelve-
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inch motor operated valves in the accumulator discharge lines were reviewed.
The inspector examined Unit 2 stress report SSR-2, MSK's 113A-4,113B1-5,
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and 113C-4 and stress anslysis summaries for each MSK. The calculation /
review sheets for hangers adjacent to one of these valves, as shown on MSK
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113A-4, lines 12" SI-467-1502-QI and 12" SI-523-1502-Q3, were reviewed.
These hangers were designated as H11, H12, H13, H2O and H106A. New loads from the reanalysis were compared with the existing calculation loads. All pipe and support stresses were determined to be acceptable and the caly
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j modifications were adjustments to three spring hangers.
This ites is closed for both Units 1 and 2.
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(open) IE Bull. tin 79-14. " Seismic Analysis for As-Built Safety-Related Piping Systems", Units 1 and 2 t
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& previous inspection of this item is detailed in NRC inspection Report
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50-338/80-08; 50-339/80-06. All piping, support and structural reanalysis
i-is reported complete with the exception of RHR pump nozzle loadings which 4..
were to be supplied by Ingersol-Rand to Westinghouse and S&W. Field modifi-1j cations were still in progress at the. end of this inspection.
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Calculations for the following supports were reviewed by this inspector:
Main Steam System Stress Isometric 101K, Supports FPH-SHP-546, 547 and a.
548.
b.
Service Water System Stress Isometric 105A, Supports H13 and H13A.
The following protions of safety-related piping systems were walked down to compare as-built conditions to design drawings.
Supports / restraints listed were inspected for conformance to detail drawings:
Unit I 8" Containment Vacuum system, lines 8" CV-8-151-Q3 and 8" CV-7-151-Q3, a.
supports RH67, R68, SH69, R70, R71, R72, A66, R65, R11 and SH10.
These lines are shown on MSKs 121J1-2 and 121El-3.
b.
8" Safety Injection system, lines 8" SI-40-153-Q2, supports A2, H32, H32A, H33 and H34. This line is shown on MSK-111D1-2.
Unit 2 i
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Safety Injection system, line 12" SI-405-153A-Q3, support H5; line 10" SI-628-153A-Q2, supports R51, RS2, R53 and R54.
b.
8" Quench Spray System, line 8" QS-404-153A-Q3, supports H12 and H17;
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line 8" QS-403-153A-Q3, supports R13 and A16.
6" Residual Heat Removal system, line 6" RH-427-1536 -Q3, sup~por u. H19, c.
R20 and R21. Stress isometrics MSK-104H1-1 and MSK-104J.
During this walkdown it was noted that a baseplate gusset plate on anchor A2 of 8" SI-40-153-Q3 had been notched to clear an adjacent drain valve.
Although this was not shown on the support etail drawing it has subsequently been marked on the as-built and evaluated as acceptable by S&W site engineers.
Also observed was an extensive grindout in the piping basemetal of line 10" SI-425-153A-Q2. The licensee provided the QA records indicating this had been properly identified and accepted based on calculations by S&W engineering.
- No deviations or items of noncompliance were identified.
Although IE Bulletin 79-14 remains open pending completion of all work and inspection of the analytical program at S&W's Boston office this inspector considers that the licensee has met the requirements of Unit 2 Technical Specification item 7.3(16) when all field modifications and related inspec-
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tions have been completed.
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