IR 05000395/1979020
| ML19249A556 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/10/1979 |
| From: | Bryant J, Burdette T, Mcfarland C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19249A554 | List: |
| References | |
| 50-395-79-20, NUDOCS 7908230599 | |
| Download: ML19249A556 (5) | |
Text
.
[ga ancoq'o UNB1ED STATES E ",,, cf[,.,
NUCLEAR REGULATORY COMMISSION REGIO J ll
- -' / ~
101 MARIETT A si, N.W., sulTE 3100
,
%<
g'
ATL ANT A,.sEoRGI A 30303
.....
Report No. 50-395/79-20 Licensee: South Carolina Electric and Gas Company Columbia, South Carolina 29218
~
Facility Name:
V. C. Summer Nuclear Station Unit 1 Docket No. 50-395 License No. CPPR-94 Inspection at Summer Site near Columbia, South Carolina c'/7 '/
Inspectors:
ecumentation during inprocess work.
The licensee has revised FQCP 6.2.3 to clarify inspection requirements on hold points, inspection points, and changes to procedure data.
Daniel Procedure WP-VI-04 is being revised to include instruc-tions for making and documenting corrections and changes to produce data.
Assembly / disassembly guides have been reviewed in order to identify and correct similar problems.
Documenta-tion discrepancies and corrective action for other assembly /
disassembly guides were documented in Deficiency Notice No.
2537M.
This item will remain open pending issuance of the Daniel procedure revision and review by Region II.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Inspector Follow-Up Items (Closed) Inspector Follow-Up Item (395/79-05-03):
Craft training on reporting quality concerns.
Beginning in June 1979, new employees NRC of quality concerns. received specific information in indoctrination training on Efforts have been made to document the time andThis has box meetings.
place that individuals received training on reporting quality concerns.
This item is closed.
6.
Independent Inspection Effort The inspectors conducted a walk-through inspection of the a.
observed construction activitiesreactor, auxiliary, intermediate, and fuel han construction progress, and work practices in these areas; an,d talked to various craft personnel and discussed with licensee personnel the schedule of work in the reactor building.
b.
The inspectors reviewed recent changes in the South Carolina Electric and Gas (SCE&G) and Daniel Construction Company (DCC)
organizations.
In the SCE&G organization, D. A. Nauman's title has been changed to Group Manager for Quality Assurance and Security.
In the DCC organization, W. L. West has been named Project Quality Manager; K. E. Heaton has been named i
774040
.
-3-
-
Assistant QC Manager; and J. Fletcher has been named Assistant QA Manager.
K.W. Nettles (SCE&G) has been named Electrical Manager replacing the Daniel Electrical Manager.
In addition, the responsibility for procedures and response coordination has been moved under the Proj._ct Quality Manager.
No items of noncompliance,ar deviations were identified.
7.
Reactor Vessel Internals Review of Procedures, Observation of Work, and Review of Records The inspector reviewed the Westinghouse (W), DCC and SCE&G procedures relative to the storage and installation of the reactor vessel (RV)
internals. The (W) Nuclear Energy Systems (NES), Pensacola, Florida,
" Reactor Internals Assecbly Specification", " Number 2463A54G01 defines the procedures, w)rk, and records required and provides for QA/QC services.
The on-site (W) Nuclear Service Division (NSD)
staff assists the r i staff in the implementation of the specifica-tion requirements.
the HTS QA work is conducted per the requirements of the HTS QA Program Manual as an extension of the Pensacola shop, hence it includes the related QC and quality engineering work. DCC performs mi11 wright work and welding, and SCE&G performs QA surveil-lance and QC surveillance of the housekeeping and storage activities.
Section 3.2.3 of the PSAR and section 4.2.2 of the FSAR relate to the RV internals. The inspector reviewed the DCC work procedure for rigging, WP-V1-01, Revision 6, and the related SCE&G QC procedures, FQCP3.2 0 and MS-5.
The inspector reviewed the (W) records of the first fitup of the RV internals to the reactor pressure vessel that was made on October 15, 1978 when customizing dimensions were established; the second fitup made June 20-22, 1979 to determine the as built dimensions; and a fitup of the upper internals to the lower internals made in December, 1977. The insp?ctor reviewed the NES checklist of opera-tions required by the specifications for the work through June 22, 1979, including the liftirg and placement work and the current work on the installation of thermocotples. Forty-one of the seventy applicable items on the checklist have been completed.
The RV internals are now stored in the refueling pool and will be fitted into the RV a few weeks before the cold hydro test which is currently scheduled for September or October, 1979. The inspector reviewed SCE&G QA audit and surveillance records of work typical of the storage, handling and installation work to date. The RV inter-nals have been protected satisfactorily to date; access to the internals has been administratively controlled.
Cleanliness of the internals has been maintained per the requirements of NES specifica-tion PS292722-1.
A clean zone has not been defined to date; it will be established prior to the cold hydrotest.
774041
.
-4-
.
No items of noncompliance or deviations were identified in this area of inspect ion.
8.
Licensee Identified Items (50.55(e))
(0 pen) Item 395/79-20-01:
Pipe support loading with Velan valves.
On June 7, 1979, the licensee informed Region II that pipe supports associated with three Velan valves will have to be redesigned due to incorrect valve weights used in the piping analysis. On June 18, 1979, the licensee reported that the status of the redesign actions and issuance of engineering changes to resolve the problem will be provided in future reports.
This item will remain open pending issuance af the licensee's final report, completion of corrective actions, and review by Region II.
9.
10 CfR Part 21 Reports (0 pen) Item 395/79-20-02:
Namco limit switches.
On June 14, 1979, the licensee informed Region II that proper QA controls had not been provided for the manufacture of Namco limit switches. Namco Controls has issued a 10 CFR Part 21 report to NRC on the switches.
The report, dated June 14, 1979, indicates that the limit switches will be returned and replaced when the required quality control
,
requirements can be met.
10.
Status of Inspection and Enforcement Bulletins (IEB's)
a.
(Closed) 79-BU-03:
Longitudinal weld defects in ASME SA-312 type 304 stainless steel pipe spools manufactured by Youngstown Welding and Engineering Co.
The licensee has issued a letter in response to IEB79-03. This letter, dated May 11, 1979, reported that pipe manufactured by Youngstown Welding and Engineering Company is not in use or planned for use in safety-related systems.
This item is closed.
b.
(Closed) 79-BU-09: Failures of GE type AR-2 circuit breaker in safety-related systems. The licensee has issued a letter in response to IEB 79-07. This letter dated June 4, 1979, reported that no G. E. type AR-2 circuit breakers are used in safety-related systems. This item is closed.
774042