IR 05000339/1978020
| ML19294A354 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/28/1978 |
| From: | Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19294A351 | List: |
| References | |
| 50-339-78-20, NUDOCS 7810120092 | |
| Download: ML19294A354 (5) | |
Text
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Report No.:
50-339/78-20 Docket No.:
50-339 License No.-
CPPR-78 Category: A3 Licensee:
Virginia Electric and Power Company P. O. Box 26666 Richmond, Virginia 23261 Facility Name:
North Anna Power Station, Unit 2 Inspection at: Louisa County, Virginia Inspection conducted:
July 18-20, 1978 Inspector:
C.
McFarland Reviewed by:
T 7[
A. R. IIerdt, Chief Date Projects Section Reactor Construction and Engineering Support Branch Insoection Su arv Insnection on Julv 18-20, 1978 (Recort No. 50-339/78-20)
Areas Inspected:
Routine, unannounced inspection of licensee actions on previous inspection findings, 10 CFR 50.55(e) ite=s and IE Bulletins.
This inspection involved 22 inspector-hours on site by one NRC inspector.
Results:
No ite=s of noncompliance or deviations were disclosed.
78191M 99 L
.
RII Rpt. No. 50-339/78-20 I-1 DETAILS I Prepared by:
-
U D'M C. R.'McFarland, Principal Inspector Date Projects Section Reactor Construction and Engineering Support Branch Dates of Inspec 'on:
July 18-20, 1978 Reviewed by:
4/ /
I A. R. Herdt, Chief Date Projects Section Reactor Construction and Engineering Support Branch 1.
Persons Contacted a.
Virginia Electric and Power Compt.ny (VEPCO)
E. R. Bane, Supervisor, Construction Quality Assurance (QA)
- P. A. Slater, Resident QA Engineer
- M. A. Harrison, QA Engineer
,
J. E. Wroniewicz, QA Engineer S. V. Lowry, Senior Resident Engineer b.
Contractor Organization Stone and Webster Engineering Corporation (S&W)
- R. L. Spence, Assistant Superintendent, Field Quality Control (FQC)
C. S. Majumdar, Senior Engineer, Electrical, FQC G. A. Carter, Senior Inspector, Electrical, FQC
- Denotes persons attending exit interview.
2.
Licensee Action on Previous Inspection Findings a.
(Open) Item of Noncompliance 339/78-10-02; Inadequate Document Storage The licensee's corrective action program has been stated in the VEPCO letter to Region II dated May 12, 1978.
The licensee has scheduled completion of the work by August 15, 1978.
The inspector discussed the subject with the staff, observed the work completed to date, reviewed VEPC0 documentation of an inspec-tion of the records vaults on July 17, 1978, and reviewed docu-mentation of the S&W work related to the corrective action program.
Tr.e S&W urk encompasses changes to procedures and documentation as well as physical changes to the vaults and the equipment in the vault.
RII Rpt. No. 50-339/78-20 I-2 b.
(Closed) Item of Noncompliance 339/78-11-01; Failure to Assure Conformance of Purchased Material to Procurement Documents The licensee's corrective action program has been stated in the VEPC0 letter to Region II dated June 14, 1978.
S&W has replaced the plates which did not have full penetration welds and inspected the work in progress and after completion of the work.
The inspector reviewed the Nonconformity and Disposition Report -
Quality Control (N&D) No. 3116 and the associated documentation for the weld repair, the preheat and heat treat, the NDE inspec-tions, the QC report that the work required was completed, and the S&W documentation of the review made to verify that there were no other supports of this design that did not meet the drawing requirements.
The inspector observed the work in progress during a previous inspection.
c.
(Closed) Unresolved Item 339/77-35-06; Steam Mounted Limit Switches The inspector reviewed the VEPC0 final 10 CFR 50.55(e) report dated November 4,1977, serial number 495, a supplementary letter to Region II dated May 3,1978, serial number 243, the VEPC0 letter to Nuclear Reactor Regulation (NRR) dated May 9, 1978, serial number 259 and the VEPCO letter to Region II dated March 27, 1978, serial number 115A (related to IEB 78-04, same subject).
The above documentation informs the NRC that Westinghouse has informed VEPC0 that certain stem mounted limit switches (SMLS) associated with certain containment isolation and ECCS alignment valves should be designated as safety-related and be seismic and environmentally qualified.
To correct the deficiency, the design has been modified to eliminate the SMLS as the " latch in" device. The " latch in" function is provided
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by qualified relays outside contain=ent.
The inspector discussed the subject with "?PC0 and S&W staff, reviewed E&DCR's PS-461 and P-2209 and asr ziated documentation.
The inspector observed completed work in relay cabinets A (AR-LA-2, 2EI-CB-115A) and relay cabinet B (AR-LB-2, 2EI-CB-116A) and the Unit 2 cable tunnel and cable vault areas as representative relays and terminatious for the design modification work required.
The modified circuitry observed was comparable to that required by drawing 12050-FE-18BK-1, Wiring Diagram, Containment Isolation Trip Valve Relay Cabinet-Train A.
The inspection of related work for Unit I was reported in RII report number 50-338/77-5.
.
RII Rpt. No. 50-339/78-20 I-3 d.
(Closed) Unresolved Item 339/78-05-03; Mounting Brackets for Containment Cooling Water (CCW) Isolation Valves, Limit Switches, Unit 2 The inspector reviewed the VEPC0 final 10 CFR 50.55(e)
report dated March 27, 1978, serial number 160, the S&W N&D 2918, Revisions A and B, which report activities related to the installation and inspection of the new stronger support brackets provided by Fisher Controls Company for certain valves identified in the N&D and related QC inspection reports.
The inspector observed the completed work on the following valves as typical of the work performed: TV-CC-200 A, B & C, TV-CC-202 B, C, D & F, TV-CC-203 A & B, TV-CC-204 A, B & C, TV-CC-205 B.
3.
Unresolved Items No unresolved items were identified during this inspection.
4.
Independent Inspection VEPC0 QA Hanual The inspector reviewed QAM No. 5.2, " Control of NRC Correspondence -
Incoming and Outgoing," revision 9 dated June 30, 1978, and discussed the subject with the VEPC0 staff.
The revision provides for changes in the responsibility assignments and other appropriate administrative procedures.
None of the revisions decrease the quality of the program nor conflict with QAM No. 5.13 " Reporting of Items to the NRC as defined by 10 CFR 50.55(e) or 10 CFR Part 23."
No items of noncompliance or deviations were identified.
5.
IE Bulletin (IEB)
a.
(Closed) Item 339/78-BU-01; Flammable Contact-Arm Retainers in GE CR120A Relays, IEB 78-01 The VEPC0 response dated March 21, 1978, has been reviewed.
VEPC0 assisted by the NSS Supplier and the A/E, has determined that none of the subject relays have been used for Unit 2 safety-related equipment or wherein fires have the potential for damaging safety equipment.
RII has no further questions at this tim.
,i
.
RII Rpt, No. 50-339/78-20 I-4 b.
(Open) Item 339/78-02-01; Control of Containment Sump Water pH following a LOCA, IEB 77-04 The VEPCO response dated December 23, 1977, indicates that acceptable pH ranges will be maintained.
This item remains open pending evaluation of the NPSH modifications and the addition of the casing cooling tank as discussed in the VEPC0 letter to RII dated May 16, 1978, serial number 261.
6.
IE Circular IE Circular 78-08; Environmental Qualifications of Safety-Related Electrical Equipment at Nuclear Power Plants VEPC0 has met with S&W to initiate work to assemble tallies of the data available on Units 1 and 2.
An evaluation of the data developed versus the specification requirements will be made.
7.
Licensee Identified Item VEPCO has reported an item to RII as a reportable item in compliance with 10 CFR 50.55(e) and/or 10 CFR 21 and the inspector reviewed the item as noted below, the available supporting documentation and discussed the item with responsible staff during this inspection.
(0 pen) Item 339/78-20-01; Agastat Add On Microswitch Not Seismically Qualified The VEPCO letter to RII dated July 18, 1978, serial number 395, submits a final 10 CFR 50.55(e report relative to the subject as related to Auxiliary Feedwate.
amp ad Component Cooling Water Pump control circuits.
The n -_ss J wiring changes to use spare contacts on existing seismically qualified Emergency Bus Undervoltage Relays have not been made for Unit 2.
8.
Exit Interview The inspector met with the licensec and contractor representatives (denoted in paragraph 1) on July 20, 1978.
The scope of the inspection and the findings were reviewed.
There were no unanswered questions or dissenting comments.