ML19262B540
| ML19262B540 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/13/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Dunn C DUQUESNE LIGHT CO. |
| References | |
| NUDOCS 7912280194 | |
| Download: ML19262B540 (1) | |
Text
(
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) c ( (,g NUCLEAR REGULATORY COMMISSION 7,h)V REGION I
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Docket No. 50-334 DEC 131979 Duquesne Light Company ATTN:
Mr. C. N. Dunn Vice President Operations Division 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Gentlemen:
This Information Notice is provided as an early notification of a possibly significant matter.
It is expected that recipients will review the infor-mation for possible applicability to their facilities.
No specific action or response is requested at this time.
If further NRC evaluations so indicate, an IE Circular or Bulletin will be issued to recommend or request specific licensee actions.
If you have questic s regarding this matter, please contact this office.
Sincerely, l
Y V.
n c.
Boyce H. Grier
" Director
Enclosures:
1.
IE Information Notice No. 79-31 2.
List of Recently Issued IE Information Notices CONTACT:
L. E. Tripp (215-337-5282) cc w/encls:
F. Bissert, Technical Assistant Nuclear R. Washabaugh, QA Manager J. Werling, Station Superintendent G. Moore, General Superintendent, Power Stations Department J. J. Carey, Nuclear Technical Assistant R. Martin, Nuclear Engineer 1649 027 A
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ENCLOSURE 1 SSINS: 6870 Accession No.:
UNITED STATES 7910250507 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Information Notice No. 79-31 Date:
December 13, 1979 Page 1 of 1 USE OF INCORRECT AMPLIFIED RESPONSE SPECTRA (ARS)
Description of Circumstances:
Recently, the NRC was informed that, during a review of valve weights in conjunction with the as-built review for IE Bulletin 79-14 at North Anna Unit 1, it was discovered that incorrect amplified response spectra (ARS) had been used as input to the analyses of some piping on both units 1 and 2.
The reanalyses are being performed by Stone & Webster (S&W), the Architect Engineer for the Virginia Electric & Power Company's facilities.
Similarly, Public Service Company of New Hampshire informed the NRC that the wrong ARS were used for the design of some containment supports at their Seabrook units.
The Architect Engineer for these plants is United Engineers & Constructors (UE&C).
The NRC is currently pursuing this issue in detail with S&W and UE&C to deter-mine the extent of the problem and the generic implications for other facilities.
This Information Notice is provided as an early notification of a possible significant matter.
It is expected that recipients will review the informa-tion for possible applicability to their facilities.
Specific action has been requested by IE Bulletin 79-14.
This bulletin requires that input to seismic analyses of piping, which includes the use of the correct ARS, be verified against the as-built condition of the plant.
No specific actions are requested in response to this Information Notice.
If NRC evaluations so indicate, further licensee actions may be requested or required.
If you have any ques-tions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
No written response to this IE Information Notice is required.
1649 028 o
ENCLOSURE 2 IE Information Notice No. 79-31 Date:
December 13, 1979 Page 1 of 1 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued to Notice No.
Issued 79-22 Qualification of Control 9/14/79 All Power Reactor Faci-Systems lities with an OL or CP 79-23 Emergency Diesel Generator 9/26/79 All Power Reactor Faci-Lube Oil Coolers lities with an OL or CP 79-24 Overpressurization of Con-10/1/79 11 Power Reactor Faci-tainment of a PWR Pla:.t lities with an OL or CP After a Main Steam Line Break 79-25 Reactor Trips at Turkey 10/1/79 All Power Reactor Faci-Point Unit 3 and 4 lities with an OL or CP 79-26 Breach of Containment 11/5/79 All Power Reactor Facil-Integrity ities with an OL or CP 79-12A Attempted Damage to New 11/9/79 All Fuel Facilities, Fuel Assemblies Research Reactors and Power Reactors with an OL or CP 79-27 Steam Generator Tube 11/16/79 All Power Reactor Faci-Ruptures at Two PW' lities with an OL or CP Facilities 79-28 Overloading of Structural 11/16/79 All Power Reactor Faci-Elements Due to Pipe Support lities with an OL or CP Loads 79-29 Loss ci Nonsafety Related 11/19/79 All Power Reactor Faci-Reactor Coolant System In-lities with an OL or CP strumentation During Operation 79-30 Reporting of Defects and 12/6/79 All Power Reactor Faci-Noncompliances, 10 CFR lities with an OL Part 21 or CP 1649 029