IR 05000338/1978039
| ML19269B932 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/01/1978 |
| From: | Herdt A, Mcfarland C, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19269B931 | List: |
| References | |
| 50-338-78-39, 50-339-78-33, 50-405-78-09, 50-405-78-9, NUDOCS 7901190043 | |
| Download: ML19269B932 (10) | |
Text
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- RicO UNITED sT ATEs
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(o, NUCLEAR REGULATORY COMMISSION
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f,g REGION ll
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y, 101 M ARIETT A sTRE ET, N.W.
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ATLANTA GEORGIA 30303 o
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Report Nos..
50-338/78-39, 50-339/78-33, 50-404/78-9 and 50-405/78-9 Docket Nos.
50-338, 50-339, 50-404 and 50-405 License Nos.-
NPF-4, CPPR-78, CPPR-114 and CPPR-115 Categories:
C, A3, A2 and A2
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Licensee:
Virginia Electric and Power Company Post Office Box 26666 Richmond, Virginia 23261 Facility Name:
North Anna Power Station, Units 1, 2, 3 and 4 Inspection at: Louisa County, Virginia Richmond, Virginia (November 16-17, 1978)
Inspection conducted:
November 13-17, 1978 Inspectors:
C. R. McFarland E. J. Vallish L. P. Modenos J.
- Wilcox, Jr.
Reviewed by:
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A. R. Herdt, Chief Date Projects Section Reactor Construction and Engineering Support Branch Inspection Summary Inspection on November 13-17, 1978 (Report Nos. 50-338/78-39, 50-339/78-33, 50-404/78-9 and 50-405/78-9)
Areas Inspected:
Routine, unannounced inspection of licensee action on pre-vious inspection findings, 10 CFR 50.55(e) and Fart 21 items, IE Bulletins for Units 2, 3 and 4.
Licensee Event Reports for Unit 1, LER-78-006/0lT and LER-78-007/0lT-0, piping penetration and pipe surf ace elimination of Unit 2.
Reactor vessel, steam generator and pressurizer storage for Units 3 and 4.
This inspection involved 104 inspector-hours on-site by four h7C inspectors.
Results: No item of noncompliance nor deviation was disclosed.
79011900 6
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RII Rpt. JJos. 50-338/78-39, 50-339/78-33, 50-404/18-9 and 50-405/78-9 I-l
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/M DETAILS I Prepared
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R.McFa rland / PTincipal Inspector D'a t(
Proj ects Section Reactor Construction and Engineering Su ort Branch
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v J. D.%'ileox, Jrf,/Re'adtor Inspector D te
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Projects Section Reactor Construction and Engineering Support Branch Dates of Inspect'on N vemoer 13-17, 1978
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Reviewed by:
A. R. Herdt, Chief Date Proj ects Section Reactor Construction and Engineering Support Branch 1.
Persons Contacted Virginia Electric and Power Company (VEPCO)
a.
- J. L. Perkins, Director, Quality Assurance (QA)
E. R. Bane, Supervisor, Construction QA P. A. Slater, Resident QA Engineer M. A. Harrison, QA Engineer J. E. Wroniewicz, QA Engineer P. G. Perry, Senior Resident Engineer G. A. Helm, Supervisor, Engineering QA F. M. Alligood, Jr., Director, Nuclear Project Engineer E. G. Lifrage, Project Engineer D. P. Batalo, Associate Engineer S. G. Eccles, Associate Engineer
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RII Rpt. Nos. 50-338/78-39, 50-339/78-33, 50-404/78-9 and 50-4.05/78-9 I-2 b.
Contractor Organization-Stone and Webster Engineering Corporation (S&W)
A. A. Dasenbrock, Resident Engineer C. D. Lundin, Superintendent, Field Quality Control (FQC)
R. L. Spence, Assistant Superintendent, FQC A. J. Mills, QC Engineer W. Scott, QC Engineer
c.
Fischbach and Moore, Inc.
V. R. Dowdy, Electrician G. D. Jones, Electrician
- Denotes those attending the Exit Interview.
2.
Licensee Action on Pre'.ious Inspection Findings No previous inspection findings were examined.
3.
Unresolved Items There were no new unresolved items identified during this inspection.
4.
Independent Inspection The inspectors toured Unit 1, 2,
3 and 4 facilities, observed work inside the containment vessel and in the auxiliary building of Unit 2, talked to various craf t personnel, and discussed the schedule for work to be pe r f o rmed in Units 2, 3 and 4 with the VEPC0 Senior Resident Engineer.
At this time, no actual work is being performed on Units 3 and 4.
No items of noncompliance or deviations were identified.
5.
Licensee Identified Ite.s VEPC0 has reported a number of items to Region 11 as reportable items in compliance with 10 CFR 50.55(e) and/or 10 CFR 21, and the inspector reviewed the items noted below and the supporting documentation, and discussed the items with responsible staf f during the inspectio.
RII Rpt. Nos. 50-338/78-39, 50-339/78-33, 50-404/78-9 and 50-405/78-9 l-3
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a.
(Open) Item 339/78-33-01, CDR-Nonconservation in the Axial Power Distr 2bution Monitoring System (APDMS)
The inspector has reviewed the VEPC0 interim 10 CFR 50.55(e) reports dated October 11 and November 3, 1978, serial numbers 575 and 575A, respectively.
The interim reports documents that Unit 2, Axial Power Distribution Monitoring System (APDMS) provided by Westing-house, has an error in the LOCA peaking factbr shape limits. VEPCO and Westinghouse are currently working together to develop a mutual permanent solution to this problem.
b.
(0 pen) Item 339/78-33-02, CDR Bolts for High Density Fuel Rack Barriers The inspector has reviewed the VEPC0 initial Part 21 report dated October 18, 1978, serial number 591. The interim report documents that the bolts used to attach mechanical guard barriers to the sides of the high density spent fired rocks have no documented evidence of a nechanical properties test after the heat treatment of these bolts. The 64 bolts have been returned to SMATCO to be tested from sample or to replace the bolts.
c.
(Open) Item 404-405/78-09-01, CDC-Recirculation Spray
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(RS) Fump Flow Limitation The inspector has reviewed the VEPCO interim 10 CFR 50.55(e) report dated October 12, 1978, serial number 570.
The interim reports documents that the present recirculation spray system does not provide the design flow for the low pressiire core injection mode of operation.
S&W and Babcock and Wilcox Company (B&W) are currently stedying the low pressure core injection requirements and the recirculation spray / core injection system cepabilities.
d.
(Open) Item 339/77-35-05, Recirculating Spray Pump Motors-Low Meggaring The inspector reviewed Nonconformity and Disposition Reports (NEDI 2(71 and 6005 that document the repair work on the electrical pigtails for the motors for the subject pumps, 2RSPIA and 2RSPIB.
The pigtails have been reinsulated and the wate r tests were passed.
This item remains open pending the final meggaring after the final termination of the motor leads as required by E&DCR 1336.
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RII Rpt. Nos. 50-338/78-39, 50-339/78-33, 50-404/78-9 and 50-405/78-9 I-4 e.
(Closed) Item 339/77-36-02, Pressurizer Nozzle Specifications on Quality Release Form The inspector reviewed documentation that amended the quality release fo rm QR25072 for the subject nozzle on pressurizer VGB-RCPCPRI to document the repair weld, the hydrostatic pressure test of the pressurizer and nozzle on September 21, 1978, and the certification of hydrostatic test of the repaired vessel by the ASHI authorized nuclear inspector, dated September 22, 1978.
f.
(Open) Item 339/78-24-05, Embedment Plates for Upper Steam Generator Support Snubbers The inspector reviewed the VEPC0 final 10 CFR 50.55(e) report to Region II dated September 28, 1978, serial number 543, related documentation by S&W and B&W, and VEPCO documentation of meetings and other communications related to the subject. This item remains open pending an NRC evaluation of the deficiency and the licensee's evaluation of the deficiency.
g.
(Closed) Item 404/405/78-01-04, Overstressed Reactor Internals The inspector reviewed the VEPC0 final 10 CFR 50.55(e) report to Region II dated August 14, 1978, serial number 620B, and related documentation by B&W and VEPCO. The B&W documentation confirms the in f o rma tion in the VEPC0 final report, and the interim report to Region II dated.lanuary 26, 1978, serial number 620A.
h.
(Closed) Item 404/405/78-01-06, Reactor Coolant Decay Heat Nozzle Amplified Response Spectra Calculations The inspector reviewed the VFPC0 final 10 CFR 50.55(e) report to Region II dated September 8, 1978, serial number 492, related documentation by S&W, B&W and VEPC0 and documentation of meetings and their communicatio s related to the subject. The resolution for the final design as presented in the final report to Region 11 has the concurrence of B&W and S&W.
i.
(Closed Item 338/78-01-06, Auxiliary Steam Generator Feed Pump Control Circuit ry, Unit 2 The inspectors reviewed the VEPC0 final report dated November 29, 1977, serial number 545; the S&W surveillance inspection job order
- 12050 of October 5,1978, VEPC0 Checklist for circuits / equipment I.E. #2.6.4.1 of September 21, 1978, and E&DCR P-2073 of August 5, 1978, relates to changing the safety injection time delay and of
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RII Rpt. Nos. 50-338/78-39, 50-339/78-33, 50-404/78-9 and 50-405/78-9 I-5 the Auxiliary Feed Pump to establish the correct flow.
The inspectors visually checked various items of the respective timer devices in cabinets 2EDCB28A and 2EDCB28B for correct settings as performed in the above E&DCR.
j.
(Closed) Item 339/78-24-03, Color Coded Cable Separation in Control Boards
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The inspectors reviewed the VEPCO final report dated September 5, 1978, serial number 486, the S&W N&D Reports QA #3329, and #3333 and #3336, the appropriate S&W QC Inspection Reports, summaries of the training program and the surveillance of the applicable wiring to the Main Control Board. The above N&D's relate to correct ing the redundancy separation violations encountered on the main control boards.
The inspectors visually checked varicas items on the redundancy separation of Main Control Boards, Panels 2El-CB-01, 2EI-CB-02, 2EI-CB-03 and 2El-CB-04, as noted in the above N&D's as typical of the work performed.
6.
Cutting of Installed Rebar The inspector reviewed the VEPC0 letter to Region II dated October 16, 1978, serial number 323C, which submits supplementary information relative to the evaluation of potential damage to embedded reinforcing steel during the installation of drilled-in anchors in the reactor containment.
The inf ormation is similar to that submitted in the VEPC0 letter to Region II dated December 29, 1976, serial number 323, and other documen-tation previously reviewed as reported in Region II reports 50-338/77-7 and 50-339/77-5.
No items of noncompliance nor deviations were identified.
7.
Exit Interview The inspector met with the licensee representative (denoted in paragraph 1) and reviewed the scope and findings of the inspection. There were no unanswered questions or dissenting comment RII Rpt. Nos. 50-338/78-39, II-1 50-339/78-33,50-404/78-9 and 50-405/78-9 Iz !i bif DETAILS II Prepared by:
e
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E. J. Vallish,1ech4nical Engineer Date Engineering Support Section No. 1 Reactor Construction and Engineering Su port Bra ch
_ k r tw%
frlr l7 V L."Modenos, Mechanical Engineer Date Engineering Support Section No. 1 Reactor Construction and Engineering Support Branch Dates of Inspection:
Fovember 14-17, 1978 Reviewed by.
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Bate l 't 7's J'. C. 3ryan~t, Chief
's Engineering Support Section No. 1 Reactor Construction and Engineering Support Branch 1.
Persons Contacted Virginia Electric and Power Company (VEPCO)
a.
- E. R. Bane, QA Construction Supervisor M. A. Harrison, QC Engineer J. E. Wroniewicz, QC Eng,ineer b.
Contractor Organizations Stone and Webster Company (S&W)
P. R. Bone, Head of Boston Field Engineering Office E. W. Spurrell, QC Engineer 2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (339/78-33-01)Tailure to Check for Fluorides After Cleaning External Fipe Surface. This item was previously reported and closed for Unit I as (338/77-44UI).
The item also applied to Unit 2 but was not addressed to include Unit 2.
The NRC has no further questions concerning this matter for Unit 2 and the item is close,
RII Rpt. Nos. 50-338/78-39, II-2 50-339/78-33, 50-404/78-9 and 50-405/78-9
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3.
Unresolved Items No unresolved items were identified during this inspection.
4.
Independent Inspection Ef fort-Units 2, 3 and 4 This inspection effort included the progress of installation of the Unit 2 steam generator's upper lateral support hydraulic snubbers, the reactor in-core neutron instrumentation system and the safety related pipe dynamic restraint systems. The Units 3 and 4 reactor and auxiliary buildings were inspected.
No construction activities were observed in these buildings.
Cleanup of construction debris and erosion sediments was in progress and blasting activities for the foundation of the service building was observed.
No items of noncompliance were identified.
5.
Reactor Vessel Installation - Work Observation - Units 3 and 4 The reactor pressure vessels were inspected in their storage areas as a follow-on of RII Report No. 50-404/78-6 and 50-405/78-6. The vessels were identified as 3RC-REV1 and 4RC-REV1.
Adequate supporting and protective structures were observed to be in place and their seals, protective coating, and dessicants which 3re to preserve internal environmental conditions were observed. The two closure heads are maintained in sealed tanks purged with dry nitrogen gas.
No items of noncompliance were identified.
6.
Reactor Vessel Installation - Quality Records Review - Units 3 and 4 Records of QC in-storage inspections f rom June 1978 to November 14, 1978, for the two reactor pressure vessels, were reviewed.
These inspections of the stored vessels were made oc an adequate frequency and indicated that protection requirements were maintained. Acceptarce criteria is in accordance with QC Procedure Nc. 17.2 and Procedure NAS-3101.
No items of noncompliance were identified.
7.
Safety Related Components I - Work Obse vation - Units 3 and 4 The four steam generators and two pressurizers were inspected as a follow-on of RII Report No. 50-404/78-06 and 50-405/78-06.
These steam generators were identified as 3RC-SGIA and IB and 4RC-SGIA and IB.
The pressurizers were identified as 3RC-PREl and 4RC-PREl.
These safety
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RII Rpt. Nos. 50-338/78-39, II-3 50-339/70-33, 50-404/78-9 and 50-405/78-9'
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related components were inspected in the lay-down storage area for storage environment, protection, results of handling, identification, cleanliness preservation and surveillance during storage.
No items of noncompliance were identified.
8.
Safety Related Components I - Quality Record Review - Units 3 and 4 This is a follow-on of the inspection reported in RII Report No.
50-404/78-6 and 50-405/78-6. Records of QC in-storage inspections from June 1978 to November 14, 1978, for the four steam generators and two pressurizers were reviewed. These inspections of the stored components were made on an adequate frequency and indicated that storage requi:e-ments were maintained.
Acceptance criteria is in accordance with QC Procedure QC-17.2.
No items of noncompliance were identified.
9.
Licensee Event Reports Licensee Event Report LEF '9-007/0IT-0, Heat Tracing Controller Cabinets Units 1 and 2,was reviewed by the inspector. Corrective action was verified on IE Report No. 50-338/78-08. Interviews with licensee representatives indicated adequate action was taken to prevent recurrence of this event.
There are no further questions on this item.
Licensee Event Report LER-78-006/0IT-0, Omission of Certain Pipe Hangers - Unit 1,was reviewed by the inspector.
Corrective action was verified on IE Report 50-338/78-12.
Review of the new system imple-mented for the approval of hanger location drawings provides for an adequate method to prevent recurrence.
There are no further questions on this item.
10.
Discrepancies in Piping Penetrations From That Considered in the Original Piping Stress Analysis - Units I and 2 The inspector discusseo the subject with the responsible S&W Stress Engineer and reviewed their M3K drawings.
The Stress Engineer, daring the final " stress walk down" of a piping sys".em, checks for discrepancies of the design.
For each penetration a check is made for clearance This verifies if penetration is anchored against the stress movements.
or not.
This method would eliminate the potential of discrepancy as detected at another nuclear power plant where pipe was solidly grouted
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RII Rpt. Nos. 50-338/78-39, II-4 50-339/78-33, 50-404/78-9 and 50-405/78-9'
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through the wall penetration. The MSK's are the isometrics of each pipe system that indicate the location of hangers, restraints and anchors.
There are no further questions on this item.
11.
Exit Interview A meeting was held with the licensee's representatives identified in paragraph 1, to discuss the results of this inspection.
Items discussed included the unresolved item 339/78-33U1; the licensee event reports LER-78-006/0IT-0 and 007/0IT-0, piping penetrations, progress of con-struction in Units 2, 3, and 4, and the Units 3 and 4 reactor vessel, pressurizer and steam generator storage and QC storage inspection records.
The licensee was informed that no new uaresolved items or noncompliances were identified.
The licensee ecknowledged these findings.