IR 05000395/1979011
| ML19259C452 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/23/1979 |
| From: | Bryant J, Swan W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19259C449 | List: |
| References | |
| 50-395-79-11, NUDOCS 7906220081 | |
| Download: ML19259C452 (6) | |
Text
.
.
.
UNITED STATES (g>R RIG Og NUCLEAR REGULATORY COMMISSION
,o,,
R EGION 11 o
O
/ :. $
101 M ARIETTA STREET, N.W.
s..v['/
,gg ATLANTA, GEORGI A 303o3
o,
...
t Report No.
50-395/79-11 Licensee: South Carolina Electric and Gas Company P. O. Box 764 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 Jenkinsville, South Carolina Inspector:
-)/ 8,
~ yL 4 - 2 3 - 7f W. B. Swan Date Signed
' M'J, fm M
/fL3 ff Approved by:
J
. BFyant ction Chief, RCES Branch Date Signed SUMMARY Inspection on April 3-6, 1979 Areas Inspected This routine, unannounced inspection involved 27 inspector-hours onsite in the areas of prestressing tendons, electrical penetrations through containment wall, and emergency diesel generators.
Results Of the areas inspected, no apparent items of noncompliance or deviations were identified.
2281 249
</
/
,
Ih
!
7906220 of /
f
.,
.
.
.
DETAILS
'
1.
Persons Contacted Licensee Employees
- R. J. Bouknight, Surveillance Specialist L. C. New, Surveillance Specialist A. S. Bashore, Assistant Site Manager Ms. M. Glenn, QC Supervisor M. B. Jones, Manager of Construction
- J. M. Woods, QC Manager
- D. R. Moore, Director of QA Audits and Surveillance Systems Other Organizations J. Brown, INRYC0
- C. W. Novak, Viscosity Oil Company
- R. W. Williams, Daniel Construction Company
- W. L. West, Daniel Construction Company
- C. C. Wagoner, Daniel Construction Company
- Attended Principal Exit Interview
- Attended Second Exit Interview 2.
Exit Interview The inspection scope and findings were summarized on April 5 and April 6, 1979, with those persons indicated in Paragraph I above. The second interview concerned tendon rust.
It was necessary due to the late arrival of a Viscosity Oil Company representative. Findings are discussed in Paragraph 5.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
2281 250
-
.
s-2-5.
Independent Inspection Effort
'
The inspector examined the f ollowing:
,
a.
Installation of emergency diesel generators and support facilities.
b.
Overall construction status.
No items of noncompliance or deviations were identified.
6.
Containmer.t (Prestressing) Observation of Work and Work Activities The acceptance criteria in FSAR Section 3 for the containment prestressing system were incorporated in GAI, Inc.
Specification SP-207-4461-00,
" Fabrication and Installation of Reactor Building Post Tensioning System".
Implementation of quality control is provided by the INRYC0 manual approved by the licensee.
FSAR Section 3.8.1.6.3.3 required that stressing of the vertical tendons in the reactor building would be done using six sets of stressing equipment placed symmetrically around the structure.
One set had been taken out of service due to calibration problems with INRYC0 stressing jack #6 (9366).
After consultations between the licensee, GAI, INRYC0 and NRR an ECN was issued and a revision to the FSAR was submitted to provide for acceptable symmetrical stressing using three sets of stressing equipment utilizing any three of the five acceptably calibrated jacks. A revision to SP-207, Section 301.11.4 was initiated.
Recalculations of the actual stresses imposed on tendons stressed prior to March 31, 1979, based on jack calibration data, showed that nine tendons were stressed to greater than the specified initial stress of 80%
of ultimate and five tendons were stressed to greater than the specified lock off stress of 70% of ultimate. An NCR was issued requiring evaluation by GAI of the impact of the over stressing on tendon integrity. The measured elongations for all tendons were within the specified range for each tendon.
Previously identified inspector Followup Item 395/79-06-01 concerning calibration of hydraulic ram #6 (Serial 9366) will be kept open pending clearance of the NCR and evaluations of data supporting resumption of use of this jack.
'
The inspector observed stressing and associated QC activities for tendons V-21, V-59, V-97 and Ve25, V-63, and V-101 (sets of three).
2281 251
,
.
.
.
-3-During the earlier stressing of vertical tendons, a SCE&G inspector observed evidence of rust on tendon wires extending down from the anchor head as much as eight inches. Evidently when tendons were removed from the shipping tubs, installed in the sheaths and the lower end button headed, some wires which extended through and above the upper, factory installed, anchor head were pulled down into the head and protective grease was scraped off. During the months in which the tendons hung in the sealed sheaths temperature cycling at the top of the sheaths condensed water onto the tendon wires below the anchor head and exposed surfaces were corroded.
Investigation of accesible wires found no pitting as deep as the rejection limit of 1/64". A representative of the Viscosity Oil Company (VOC),
supplier of the protective grease which will be used to pack the tendon sheaths, arrived at the site on April 6.
A team composed of the VOC representative, INRYC0 inspector, GAI resident engineer, SCE&G QA sur-veillance inspector and QA Coordinator and the NRC inspector inspected
'
the tendon wires below the anchor plate on tendons V-25, V-63 and V-101 as they were exposed during stressing.
Color photos of undisturbed rusting were taken by the GAI resident engineer. The exposed wires were regreased.
At the second exit interview those who had participated in the observances discussed the findings, the probable causes, and safety implications.
The participants concluded that integrity of the wires observed had not been seriously impaired and that packing grease would prevent further corrosion. The findings are to be formalized in writing.
No noncompliances or deviations were identified.
7.
Containment (Prestressing) - Review of Quality Records The control documents listed in paragraph 6 require the keeping of quality records. These are detailed in the INRYC0 Manual. The data are signed off by the INRYC0 inspector and a SCE&G inspector.
Prior to this inspection, 51 of the vertical tendons had been stressed.
The inspector reviewed the stressing records for tendons V-18, -20, -56,
-58, -94, and -96.
The measured elongations each fell within the specified range.
Rust spots on some of the wires were noted on the stressing records for V-18, V-20, and V-96.
(See discussion in paragraph 6 above).
Tendon pulling (insertion into sheath) cards were reviewed as detailed below.
All vertical tendons were installed.
Two horizontal tendons remain to be pulled in because blockage of two sheaths (30AC and 22BC)
has not been cleared.
Three other horizontal tendons remain to be installed.
2281 252
.
.
,
.
.
.
i-4-Seven dome tendons were found to be too short. Replacements have held up installation. Errors in field measurements and/or engineering toler-ances resulted in inability to install individual tendqns in their designated sheaths. INRYC0 shifted tendons to compensate for the length discrepancies.
For example V-31 tendon was shifted to V-51 sheath and V-51 tendon to sheath V-31.
The records show the actual location for each tendon.
Pulling records were reviewed for the following tendons:
V-1, -21, -39 D-104, -107, -110, -115, -133, -209, -303 and -332 AC13, BA2, BA6, BA32, BA41, CB11, CB19 and CB28 Button Heading Records were reviewed for tendons:
V-1, -11, -34, -50, -68, -88 and -107 D-38, -112, -125, -205, -221, -232, -327 and -333 Notations of 100% inspection of button heads were found on the cards for V-68 and D-232.
In the records review, no noncompliances or deviations were identified.
8.
Containment (Penetrations) - Observation of Work and Work Activities Acceptance criteria cited in PSAR Section 3 for electrical penetrations were carried ever in Gilbert Associates, Inc. Specification SP-559-044461-00, Rev. 3, February 24, 1978, " Electrical Penetrations". Assemblies are to meet ASME Code, including inspection (except no "N" Stamp) for safety Class 2 structure, Class IE electri al system.
Implementation of design and quality requirements is through Daniel Construction Company (DCC) construction procedure WP-X-02, Rev.
1, February 22, 1979, "Installationof Electrical Penetrations"; individual DCC work packages for each penetration; the D. G. O'Brien Co. manual covering each type of electrical penetration assembly, installation and testing; and through SCE&G Field QC Procedure 7.1.8, " Installation of Electrical Penetrations" with its Appendix A, " Volumetric Leak Rate".
The cylindrical steel penetrations, through which the electrical pene-trations assemblies will be installed, were positioned and installed during erection of the steel containment shell.
No D. G. O'Brien electrical penetration assembly had been installed in its steel sleeve at this inspection.
2281 253
.
.
.
.
.
.
-5-Installation of the flanges onto which the penetrations will be mounted and the inserted cable support was nearing completion.
Pipe caps had been welded on each end of the sleeve for spare (future) penetrations.
The inspector examined the completed installations in the r,eactor building and a sample of the DCC work packages involved.
Twenty-four large diameter electrical penetrations and two small assemblies supplied by the D. G. O'Brien Company were examined. All were in the shipping containers and all were under inert gas pressure. One of the major assemblies was in the " hold" area awaiting documentation. Storage conditions were adequate.
The licensee has agreed to notify the NRC project inspector when the O'Brien assemblies are to be taken to the reactor building so that NRC can observe installation and testing activities.
In the activities observed, no noncompliances or deviations were identified.
9.
Containment (Penetrations) - Review of Quality Records For Electrical Penetrations Two DCC work packets for work in progress for installing flanges and cable supports were reviewed and packet DE-712-EP and Packet DE-725-EP for work on penetration sleeves 712 and 725. DCC drawings, weld procedure designation, NDT requirements and records forms were included.
The records for the following four completed DCC work packets were reviewed:
Elect Penetration Packet DE-504-EP for installation of an 18" S.S. weld neck flange Elect Penetration Packet DE-505-EP, Rev. 3 for installing two caps on an 18" spare sleeve Elect Penetration Packet DE-807-EP-1 for installing two caps on a 12" spare sleeve Elect Penetration Packet DE-812-EP, Rev. 3 for installing a 12" S.S.
weld neck flange The specified inspection and NDT records were found in these packets.
No noncompliances or deviations were identified.
.
2281 254
..
4