ML20210D199
| ML20210D199 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/04/1987 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 87-005, 87-5, NUDOCS 8702100034 | |
| Download: ML20210D199 (3) | |
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10 CFR 2.201 VINGINIA ELECTRIC AND Pownu ComiwNY Rscuwoxu,Vrwaix A 2 3 2 61 W.L.STMWANT Vsca Pammspawr Noca. man OPERATIONW U. S. Nuclear Regulatory Commission Serial No.87-005 Attn: Document Control Desk N0/WDC/pms/vlh Washington, D. C.
20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 NRC INSPECTION REPORT NOS. 50-280/86-34 AND 50-28V86-34 We have reviewed your letter of January 6, 1987, in reference to the inspection conducted at Surry Power Station on October 20-23 and October 27-31, 1986 and
-reported in Inspection Report Nos. 50-280/86-34 and 50-281/86-34. Our response to the Notice of Violation is addressed in the attachment.
We have no objection to this inspection report being made a matter of public disclosure.
If you have any further questions, please contact us.
Very truly yours.
W. L. Stewart Attachment cc:
U. S. Nuclear Regulatory Commission 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector l
Surry Power Station Mr. Chandu P. Patel NRC Surry Project Manager i
PWR Project Directorate No. 2 l
Division of PWR Licensing-A l
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O RESPONSE TO NOTICE OF VIOLATION ITEM REPORTED DURING NRC INSPECTION CONDUCTED ON OCTOBER 20-23 AND OCTOBER 27-31, 1986 INSPECTION REPORT NOS. 50-280/86-34 AND 50,-281/86-34 NRC COMMENT During the Nuclear Regulatory Commission (NRC) inspection conducted on October 20-23 and October 27-31, 1986, a violation of NRC requirements was identified.
The violation involved failure to provide appropriate inservice inspection drawings for the examination of safety related welds on the pressurizer.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR' Part 2, Appendix C (1986), the violation is listed below:
10 CFR 50 Appendix B Criterion V, as implemented by Virginia Electric and Power Company (VEPCO) Topical Report VEP1-5A, paragraph 17.2.5, requires that activities affecting the quality of structures, systems and j.
components be prescribed by documented instructions, procedures and drawings of a type appropriate to the circumstances. VEPC0 inservice inspection (ISI) Drawing VIR-1-2100, Rev.
1,. dated June 18, 1985, is the drawing provided to locate the welds in the Unit 2 pressurizer. VEPCO ISI Drawing VIR-1-2100, Rev. I depicts the lower head to shell weld'(weld #4) i as being three inches above the support skirt to lower head weld _(weld
- 8).
Contrary to the above, the. original issue of drawing VIR-1-2100 as well.as the fabrication drawing for the pressurizer depict weld #4 as being 27 inches above weld #8. As a result of this drawing error, on October 22, 1986, an ultrasonic inspection was conducted on an area of base material 3 l
inches above weld #8 instead of the segment of weld #4 and'an intersecting i
segment of longitudinal weld #3 located 27 inches above weld #8.
This inspection was conducted despite the fact that _ visual inspection on October 21, 1986, revealed the area 3 inches above weld #8 to be smooth i
with no evidence of a weld and the area 27 inches above weld #8 appeared to be a weld even though_the drawing showed no weld at that location. The J
review of previous drawings which substantiated the visual inspection L
location of the weld #4 was done at the insistence of the NRC inspector who witnessed the activities of October 21 and 22, 1986. A review of drawings used during the June outage of Unit 1 indicates that this drawing control problem also existed during examination of Unit 1.
This is a Severity Level IV violation (Supplement I).
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RESPONSE
1.
ADMISSION OR DENIAL OF THE ALLEGED VIOLATION The violation is correct as stated for Unit 2.
Review of the inspection records has determined that the pressurizer inspections were performed on Unit i using the correct drawing.
2.
REASONS FOR VIOLATION Isometric drawings VIR-2100 and VPA-1-2100 were revised incorrectly depicting the location of pressurizer weld #4.
Subsequent reviews did not detect this error.
3.
CORRECTIVE STEPS WHICH HAVE BEEN TAKEN AND THE RESULTS ACHIEVED Examination of the correct location of weld #4 on the Unit 2 pressurizer was performed satisfactorily prior to startup. New isometric drawings of the pressurizer have been developed.
4.
CORRECTIVE STEPS WHICH WILL BE TAKEN TO AVOID FURTHER VIOLATIONS The outage inspection plan will be reviewed to ensure the correct drawings are used at the. next outage. An ongoing program has been initiated to review and upgrade isometric drawings for use by the Inservice Inspection Program.
5.
THE DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED Full compliance has been achieved.
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