ML18139C062: Difference between revisions
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{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND~ VIRGINIA 23261 R.H. LEASBURG VxoE PRESIDENT | {{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND~ VIRGINIA 23261 R.H. LEASBURG VxoE PRESIDENT NUCLEAR 0PERATXONS September 21, 1982 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn: | ||
SURRY POWER STATION INSERVICE INSPECTION PROGRAM Pursuant to 10 CFR 50.55a (g), the Virginia Electric and Power Company hereby submits its program for inservice inspection and testing ASME Code Systems during the second ten year interval for Surry Power Station Unit 1. | Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen: | ||
Per 10 CFR 50.55a (g) (4), the ASME Code and addenda "in effect" for this period has been determined to be the 1980 Edition of Section XI with Addenda thru the Winter of 1980. Surry Power Station was not, however, designed to meet the detailed inservice inspection and testing requirements of the ASME Code, Section XI. Therefore, pursuant to 10 CFR 50.55a (g) 6 (i), we request specific relief from ASME Code requirements pertaining to inservice inspection and testing as outlined on the enclosed attachments. | Serial No. 546 | ||
Attachments | _NO/WDC: acm Docket No. 50-280 License No. DPR-32 SURRY POWER STATION INSERVICE INSPECTION PROGRAM Pursuant to 10 CFR 50.55a (g), the Virginia Electric and Power Company hereby submits its program for inservice inspection and testing ASME Code Systems during the second ten year interval for Surry Power Station Unit 1. | ||
Per 10 CFR 50.55a (g) (4), the ASME Code and addenda "in effect" for this period has been determined to be the 1980 Edition of Section XI with Addenda thru the Winter of 1980. | |||
Surry Power Station was not, however, designed to meet the detailed inservice inspection and testing requirements of the ASME Code, Section XI. | |||
* G | Therefore, pursuant to 10 CFR 50.55a (g) 6 (i), we request specific relief from ASME Code requirements pertaining to inservice inspection and testing as outlined on the enclosed attachments. | ||
Attachments | |||
.-* 82io-130421 020921 | |||
; PDR ADOCK 05000280 | |||
* G PDR}} | |||
Latest revision as of 21:02, 5 January 2025
| ML18139C062 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/21/1982 |
| From: | Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18130A377 | List: |
| References | |
| 546, NUDOCS 8210130427 | |
| Download: ML18139C062 (1) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND~ VIRGINIA 23261 R.H. LEASBURG VxoE PRESIDENT NUCLEAR 0PERATXONS September 21, 1982 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
Serial No. 546
_NO/WDC: acm Docket No. 50-280 License No. DPR-32 SURRY POWER STATION INSERVICE INSPECTION PROGRAM Pursuant to 10 CFR 50.55a (g), the Virginia Electric and Power Company hereby submits its program for inservice inspection and testing ASME Code Systems during the second ten year interval for Surry Power Station Unit 1.
Per 10 CFR 50.55a (g) (4), the ASME Code and addenda "in effect" for this period has been determined to be the 1980 Edition of Section XI with Addenda thru the Winter of 1980.
Surry Power Station was not, however, designed to meet the detailed inservice inspection and testing requirements of the ASME Code,Section XI.
Therefore, pursuant to 10 CFR 50.55a (g) 6 (i), we request specific relief from ASME Code requirements pertaining to inservice inspection and testing as outlined on the enclosed attachments.
Attachments
.-* 82io-130421 020921
- PDR ADOCK 05000280
- G PDR