IR 05000281/1979014
| ML19263E764 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/29/1979 |
| From: | Herdt A, Wilcox T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18114A722 | List: |
| References | |
| 50-281-79-14, NUDOCS 7906250146 | |
| Download: ML19263E764 (4) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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Report No. 50-281/79-14 Licensee Virginia Elect ric and Power Company P
O. liox 26666 Richmond, Virgini. 23261 Facility Name Surry Power Stat ion, Uni t 2 Docket No. 50-281 License No. DPR-37 Inspection at Surry Site near Williamsburg, Virginia L La l e
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lospector-J. D. Wi) ( ox, J p r.
Da e Signed 3[ Signed Approved by:
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nu-Date A. R. lierdt, Sect i n Chief, RC&fS liranch SUMMARY Inspec tion on March 6-9, 1979 Areas inspeited This routine, unannounced inspection involved 28 inspector-hours onsite in the areas of const ruction status pertaining to the steam generator repl.n ement (SGRP) for Surry Power Station storage of new steam generator lower units, follow-up on previous identified unresolved item, QA Audit Review, and observation of saf ety-related work activities.
Results Of the f ive areas inspected, no apparent items of noncompliance or deviat ions were identified in four areas.
One apparent item of noncompliance was found in one area (def iciency - Inadequate rec ords - Nit rogen Purge S. G.
Lower Assembly pa ragraph 6).
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DETAILS
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Persons Contacted Licensee Employees A. L. Parrish, Ill, Project Manager SGRP i
l kJ. W. Patrick, VEPCO kJ. L. Wilson, Station Operations Superintendent 2T. A. Peebles, Technical Services Superintendent AR. M. Smith, H. P Supervisor i< R. L Baldwin, VEPCO, Supervisor, Admini st rat ive Services SE, P DeWandel, Administrative Assist. int kF L Rentz, Resident QC Engineer
- P P Not tingham,11. P. Coordinator, SGRP 2C. W. Rhodes, Resident Engineer Construction SGRP SY P Mangum, Jr., Resident Engineer Project Control SGRP SR. E.
Titone, Engineering Technician
&M. D. Tower, VEPCO (Corporate QA)
SS. Sarver, VEPCO (Corporate llP)
Other licensee employees cc.aacted during this inspection include! 4 technicians, I security f orce member, arni 3 construction craftsmen,
office personnel.
NRC Resident Inspector CD. J. Burke i'At teinled ex i t i rit e rv i ew.
2.
Exit interview The inspectton scope and findings were s t.mma r i z e d o n March 9, 1979 with those persons indicated in Paragraph I above lhe inspector summari7ed the scope of the inspectton as follows:
Const ruc t ion status, QA Audit Review, Review of Previous identified l'nresolved I t e:
and observation of safety-related work activit ies.
3.
Licensee Action on Previous Inspyct ion l'pulings (Closed) Unresolved item (280-281/79-04-01) "ASMF. Code Requirement:
Per concurring telcon conversation i rom D. Neighbors (NRR) t o J. D. Wi i. ox,
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(IE:Hil), the intent of Pa rag raph.'.1 of the Saf ety Evaluat ion Report (SER) under "ASME Code and Regulatory Guide implementation ~ i:
the following: All piping weld end preps, welding, and nondestrut t ive examinat ion will be in accordant e with the 19 7.'. Edi t ion o f t he ASMF 2218
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i-2-Code, including addenda through Winter 1976.
Therefore, the S.E.R.
agrees with VEPCO's submittal (Steam Generator Pr oject, jSurry Power l
Station Units Nos. I and 2, Revision 9) to NRR dated Auyast 1977 for the Surry Steam Generator Replacement (SGRP) pertaining to the AS?!F.
Code Requirements. This item is closed.
4.
Unresolved Items Unresolved items were not identified during this inspection.
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Independent Inspection Effort a.
Construction Status The biological shield walls are being removed from around the steam generators of the Unit 2 Reactor Building.
Installation of Crane Wall jib cranes and monorail transport system are being accomplisbed. Containment floor and crane wall modifications are also in progress.
The new steam generator lower assemblies are being stored near the unloading dock on the James River in VEPCO's construction security area.
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Quality Assurance Audit The inspector examined the following QA audit conducted by the site VEPCO's QA unit for completeness, de f ic iencies f cund, c orrec-tive action taken, timeliness and implementat ion taken.
Audit Number Subj ec t SGRP 78-1 Test and !!easuring Equipment The audit reviewed was found to be conducted and documented in a thorough, timely and objective manner.
No items of noncompliance or deviations were identifted in the above area inspected.
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Observation of Safetv-Related Work Activitses The following safety-related work was obsened by the inspecter during the course of the inspection:
(1) Preparation f or installation of Crane Wall jib crancs (2)
Preparat son f or modi f icat ion of Crane Val 1 2218
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-3-(3) Preparation for removal of instrumentation, feedwater and mainsteam piping f rom Steam Generators "A", "B",, and "C" f
(4) Preparation for cutting reactor coolant pipuin for Steam Generator "C" No items of noncompliance or deviations were identified in the above areas inspected.
Storage of Steam Generator Lower Assemblies The inspector observed the storage of four (4) steam generator lower assemblies. The lower assemblics are located near a unloading dock on the James River in \\T.PCO ' s construction security area.
The lower assemblics were checked to ensure proper nitrogen purges were being maintained as required by West inghouse Process Specification NPT 91,
" Protective measures for long term storage of steam generator lower assemblies" and NPT 94, " Protective measures for short term storage of steam generator lower assemblies" Paragraph 4.0 of these process specifications contain the following requirements:
The following monitoring schedules for nitrogen pressure gage readings of primary and secondary sides of the steam generator lower assemblies shall be documented. The monitoring of the site storage will be to take pressure gage readings daily for the first three days at the piant site Also take readings daily for the first three days after any handling of the generator at the plant site Thereafter, take pressure gage readings every two weeks until the nitrogen charge is intentionally released for installation into the nuclear steam supply system.
On March 8, 1979, the inspector observed that inadequate records were being main-tained for monitoring pressure gage reading of primary and secondary sides of three (3) lower assemblies (identified as "2972, "2973, and
- 2981).
It should be noted that the primary side of lower assembly ident if ied as d2971 is present ly having nonles re endprepped; theref ore, a purge is not being maintained on the primary side of this generator assembly.
This is in nonc omp l i ance with 10 CFR 50, Appendix B, Cri-terion XVII as implemented by the VEPCO's licensing submittal (Steam Generator Project, Surry Power Station Unitt Nos 1 and 2 - Revision 9)
to the Steam Generator Project.
This is identified as deticiency 281/ 79-14-01 " Inadequate Records - Nit rogen Purge S. G. lower Assembly'
No other items of noncompliance or deviat ions were identified.
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