IR 05000395/1978022

IE Inspec Rept 50-395/78-22 on 781003-05 During Which No Items of Noncompliance Were Noted.Major Areas Inspected Incl:Progress of Installation of Safety Related Mechanical Components in Svc Water Intake Structure

ML20150D065
Person / Time
Site:	Summer
Issue date:	11/25/1978
From:	Bryant J, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20150D043	List: IR 05000395/1978022 ML20150D040 ML20150D049
References
50-395-78-22, NUDOCS 7812040175
Download: ML20150D065 (4)

Text

. . . . _

.

nungoe,in, n NUCLEAR REGULATORY COMMISSION j

-

Oe[s,smaa, ,. c o

g

REcioNii

+ 3 r 101 M ARIETT A sTRE ET. *

o ".I- [ ATLANTA. GEORGI A 30303

,;..... ,

Report No.: 50-395/78-22 Docket No.: 50-395

,

' License No.: CPPR-94 Category: A3 Licensee: South Carolina Electric and Gas Company P. O. Box 764 Columbia, South Carolina 29202 facility Name: V. C. Summer Nuclear Station, Unit 1 Inspection at: Fairfield County, South Carolina

Inspection conducted: October 3-5, 1978 Inspector: E. J. Vallish Reviewed by: , tg _

~

l 2h4 Dat'e J. C. Bryant, Ehief Q Engineering Support Section No. 1 Reactor Construction and Engineering Support Branch Inspection Summary

'

Inspection on October 3-5, 1978 (Report No. 30-395/78-22)

Areas Inspected: Progress of installation of safety-related mechanical components in the service water intake structure, reactor building, and auxiliary building; reactor vessel installation quality records; reactor vessel internals werk; safety-related structures work and quality records; and corrective action on noncompliance (78-12-03), Failure to Protect Pipe Ends Nozzles (paragraph 2). The inspection involved 16 inspector-hours on site by one h7C inspecto Results: No items of noncompliance or deviations were identifie (75~ i

$

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

..

.

i

.

RII. Report No.: 50-395/78-22 -2-

DETAILS I Prepared by:

E. J. Tallish, Mechanical Engineer Date Engineering Support Section No. 1 Reactor Construction and Engineering Support Branch Dates of Inspection: October 3-5, 1978 r~

Reviewed by:

J. C. Bryant,\ Chief ,.. d hhsJ ~ % # lo!?s'7f

' Date Engineering Support Section No. 1 Reactor Construction and Engineering Support Branch Persons Contacted South Carolina Electric and Gas Company (SCE&G)

• D. A. Nauman, Quality Assurance Manager

• H. I. Donnelly, Site QA Coordinator J. E. Bocock, QA Mechanical Supervisor Daniel Construction Company (DCC)

• L. West, Project Quality Assurance Manager J. Frick, Mechanical QC Supervisor J. Neff, Hanger Engineer

• Indicates attendance at exit intervie . Licensee Action on Previous Inspection Findings (Closed) Noncompliance (395/78-12-03); Failure to Protect Pipe Ends Nozzles The licensee % letter of corrective action dated August 18, 1978, was reviewed prior to this inspection. The licensee's corrective action to avoid further noncompliance in this area was inspected during this inspection and all observed openings that required covers were found

,

to be covered.

'

This item is close O

.__ _ __ ____ ___________________

_

. .

%

? RII. Report No.: 50-395/78-22 -3- Unresolved Items No unresolved items were identified during this inspectio . Independent Inspection Effort This effort included inspection of the progress of installation of the steam generator's hydraulic snubbers, mechanical snubbers, the service water intake structure, safety injection / charging pumps and the reactor containment building tendon No items of noncompliance were identifie . Reactor Vessel Installation - Quality Records Review FQCP 3.5.0, titled " Housekeeping Inspection", was reviewed to determine licensee commitments to maintain cleanliness in and around the reactor pressure vessel. Documentation reviewed indicated the reactor vessel was designated as a Zone IV cleanliness area on September 13, 1978. Eight of the most recent QC records of reactor vessel inspections, indicating that the required cleanliness was maintained, were reviewe No items of noncompliance were identifie . Reactor Vessel Internals - Work Observation The reactor vessel internals were observed in storage in the refueling pool and on the operating floor level. All items were adequately covered, protected and supporte No items of noncompliance were indicate . Safety-Related Structures (Structural Steel and Supports II) -

Work Observation The structural steel supports on the horizontal heat exchangers for the spent fuel cooling system were selected as representative safety-related steel supports for major equipment outside the containmen The supports on these heat exchangers, serial numbers 2278A and 2278B, i

were inspected for use of specified materials, proper installation and anchoring, adequate NDE inspection using QC personnel, recordkeeping and testing. Josepb Oat Corporation drawing number 5706, R7, was reviewed and used to verify orientation, installation requirements and material requirement No items of noncompliance were observe l

.

. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _

(

.. .

..

RII. Report No.: 50-395/78-22 -4- Safety-Related Structures (Structural Steel and Supports II) -

Quality Records Review The quality records pertaining to the structural steel supports of the horizontal heat exchangers for the spent fuel pool cooling system were reviewed. Record package files 307 SF XHE 0007A and 0007B were observed to contain material certifications, vendor inspection reports, receiving inspection reports and test results on the structural steel and welding materials. QC Form No. 6.2.2-1, " Inspection of Installation of Equipment",

was reviewed which verified that the erection specifications were adhered to and that the installation and testing requirements were met. Records were complete, legib.le and readily retrievabl Mechanical QC inspection personnel are qualified in accordance with the requirements of DCC procedure AP-VI-01, " Selection, Training and Certification of Mechanical Quality Control Personnel." Interviews with mechanical QC inspectors indicated they were adequately trained and knowledgeable in their fiel No items of noncompliance were identifie . Exit Interview At the end of this inspection a meeting was held with the licensee's representatives and others denoted in paragraph 1 to discuss the inspection finding Items discussed included mechanical equipment installation in the service water intake structure, progress of installation of the safety injection / charging pumps, containment building tendons and dynamic snubbers. Reactor vessel installation quality records pertaining to housekeeping, storage of the reactor vessel internals, installation and records concerning the structural steel supports for the fuel pool cooling system heat exchangers were also discussed. The inspector stated that noncompliance number 78-12-03 was observed to be adequately resolved and is close The licensee was notified that no noncompliances or new unresolved items were identifie The licensee acknowledged these finding .