ML19323D970
| ML19323D970 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/26/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19323D757 | List: |
| References | |
| NUDOCS 8005220603 | |
| Download: ML19323D970 (7) | |
Text
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101 MARIETTA ST., N.W., sutTE 3100 e'4 ATLANTA, GEORGI A 30303 MAR 2 61980 0
MEMORANDUi FOR:
Norman C. Moseley, Director, Division of Reactor Operations Inspection, Office of Inspection and Enforcement, EQ FROM:
James P. O'Reilly, Director, Office of Inspection and Enforcement Region II t
SUBJECT:
VIRGINIA ELECTRIC AND POWER COMPANY, NORTH ANNA 2 DOCKET NO. 50-339 - STATUS OF FACILITY COMPLETION i
Based on the results of our inspection efforts, we have determined that Construc-tion and Preoperational Testing of the subject facility have been completed in substantial agreement with docketed commitments and regulatory requirements, with the exception of items indicated in the enclosures. With the exception of noted items, we have completed our inspections in accordance with the requirements contained in MC 2500. Additionally, pre-fuel load activities prescribed in the October 29, 1976 memorandum from B. H. Grier to N. C. Moseley concerning Phase 4 of the North Anna Investigation have been completed.
Remaining construction, testing, and inspection items identified in the enclosures have been categorized by our recc,mmended mandatory completion milestones.
Licensee personnel estimate that the unit will be ready for fuel loading by April 1, 1980. Region II believes this date is achievable.
As part of our inspection efforts, we have reviewed the licensee's preparations for implementation of the Quality Assurance Program for Operations, and have found that they meet the requirements of 10 CFR 50, Appendix B, as specified in the licensee's Quality Assurance Program Topical Report (which was reviewed by the Office of Nuclear Reactor Regulation).
b-James P. O'Reilly Director
Enclosures:
1.
Items To Be Completed Before Fuel Loading 2.
Items To Be Completed Before Two Unit Operation 3.
Items To Be Completed Before Initial Criticality 4.
Items To Be Completed Prior To Exceeding 25 Percent Power Level 5.
Status of Inspections Required By MC 2511. MC 2513, MC 2593, and MC 2514 cc:
H. D. Thornburg, RCI/IE J. H. Sniezek, FFMSI/IE F. M. Howard, SI/IE CONTACT:
R. C. Lewis 242-5535 80 05220
aA ENCLOSURE 1 OUTSTANDING ITEMS TO BE RESOLVED PRIOR TO FUEL LOADING 1.
Copplete preoperational testing and satisfactory resolution of significant test and construction deficiencies. As of March 26, 1980, test procedures 2-PO-30.4A, 2-PO-69A, 2-PU-698, and 2-PO-70D had not been completed.
2.
Complete development and cpproval of 'perational procedures required by Technical Specifications and by R. G.
33.
As of March 24, 1980, eight (8) surveillance test procedures needed for early operating stages had not been approved.
o
.,g ENCLOSURE 2 OUTSTANDING ITEMS TO BE RESOINED PRIOR TO FILLING AND VENTING THE REACTOR COOLANT SYSTEM AFTER FUEL LO.GING Cokpletion 1.
of calibration and checkout of the overpressure protection sy= tem, including the high pressure nitrogen system for the power operated relief valves.
2.
Replacement of the control rod guide tube support pins.
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,y ENCLOSURE 3 ITEMS TO BE h_ SOLVED PRIOR TO INITIAL CRITICALITY 1.
Verify that no mechanical interferences exist between incore guide tubes or
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modified insulation supports and the reactor vessel lower head insulation due to thermal growth during precritical testing (78-24-02).
2.
Visual verification of hydraulic snubber operability at operating temperature (79-78-02).
3.
Verify adequate seismic stress analysis of safety related piping per IE Bulletin 79-07 (79-28-07).
4.
Verify adequacy of service water and component cooling water pipe supports to resist thermal loadings over service water temperature range (78-36-01).
5.
Determine if atypical weld material was used in the reactor vessel seam welds (IE Bulletin 78-12A).
6.
Verify that piping and support loads are within limits for systems where erroneous Velan check valve weights were used (79-21-03; also see IE Bulictin 79-04).
7.
Resolve error found in DNBR analysis for single drepped control rod event (78-28-01).
8.
Resolution of potential degradation of electrical penetrations due to over-
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current conditions (79-46-01).
9.
Verify adequacy of emergency diesel generator fan cooling systems over all
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ambient temperature ranges (79-44-02).
10.
Replacement of cracked disc for containment isolation valve MOV-2380 (79-54-04).
11.
Upgrade Safeguards building exhaust system to seismic Class I (79-34-06).
i 12.
Verification of adequacy of piping and supports for those systems wherein incorrect seismic response spectrum curves were used in stress analyses (79-56-02).
13.
Modification of circuitry to ensure that engineered safety features equipment do not return to normal operating modes following reset of containment depres-surization actuation (CDA) or safety injection (SI) signals (79-56-04).
14.
Resolution of potential nonconservative feature of Westinghouse large break LOCA-ECCS evaluation model and its impact on peak clad temperatures (79-58-03).
-s
. 15.
Resolution of nonconservatism involving the error analysis of the nuclear instrumentation negative rate trip for dropped control rods (79-58-04).
-16.
Resolution of nonconservatism in the method used to generate power distri-bution and rod worths for dropped rod events (79-58-05).
17.
Completion of the seismic analysis of as-built safety-relating piping syitems (ISB 79-14/80-09-01).
18.
Verification of seismic qualification of control panels for the control room air conditioner chillers (80-05-01).
19.
Rerouting of the steam generator blowdown monitor sensing lines.which were found to be cross-connected (79-54-02).
20.
Completion of k'estinghouse review of low power test procedures (TMI Action Plan requirenent I.C.7(b)).
21.
Development of a training plan for shif t personnel during conduct of low power tests (TMI Action Plan requirement I.G.).
22.
Completion of installation and checkout of relief and safety valve accoustical monitoring instrumentation (STLL Requirement 2.1.3.a).
23.
Completion of installation and checkout of high range radiation monitors (STLL requirement 2.1. 8.b).
24.
Completion of rework and retests of the Safeguards building valve pit sump pumps.
25.
Ccmpletion of retests of volume control tank level control valve (LCV-2115A) following limit switch replacement.
26.
CcT.pletion of reanalysis and corrective actions for stresses in Safety Injection lines for temperatures below 70 F.
27.
Completion of closure of gaps in the containment recirculation sump grating where pipe supports and piping pass through the grati.ng.
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4 ENCLOSURE 4 ITEMS TO BE RESOINED PRIOR TO EXCEEDING 25% POWER LEVEL 1.
Deyelop surveillance program for fiberglass spray pond piping and supports (R.G. 1.72).
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I.
ENCLOSURE 5 STATUS OF INSPECTION REQUIRED BY MS 2512, MC 2513, MC 2593, AND MC 2514 1.
MC 2512 All module inspection requirements of this chapter have been completed 2.
MC 2513 84330B Radioactive Waste Systems Preop Liquid and Solid Waste 90 System 84331B Radioactive Waste Systems Preep Gaseous Waste Systems 90 70320B Evaluation of Test Results 90 70322B Evaluation of Test Results - ESF 60 70324B Evaluation of Test Results - Integrated Hot Functional Testing 90 70325B Evaluation of Test Results - RPS 70 70326B Evaluation of Test Results - Loss of Offsite Power 20 70329B Verification that Tests are Evaluated by Licensee 80 3.
MC 2593 41301C Operating Staff Training 40 601501C Fuel Receipt and Storage (Quarterly) 0 4.
MC 2514 84530B Radioactive Waste Systems - Startup and Power Ascension 0
72576 Power.*acension Phase Procedure Review (Natural Circu-lation of Power Reactivity Coefficient Measurements) 100 72578B Power Ascension Phase Procedure Review (Evaluation of Core Performance) (A&B) 100 72584B Power Ascension Procedure Review (Evaluation of Flux Asymetry or Psuedo Nod Ejection Test) 100 l
.