ML17053B293
| ML17053B293 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/13/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Rhode G NIAGARA MOHAWK POWER CORP. |
| References | |
| NUDOCS 7912280212 | |
| Download: ML17053B293 (6) | |
Text
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Docket No. 50-410 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA19406 DE.c 13
>979 Niagara Mohawk. Power Corporation ATTN:
Mr. G.
K.
Rhode Vi'ce President System Project Management 300 Erie Boulevard, West
- Syracuse, New York 13202 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 questions regarding this matter, please contact this office.
Sincerely, Boyce H. Grier Director
Enclosures:
l.
IE Information Notice No. 79-31 2.
List of Recently Issued IE Information Notices CONTACT:
L.
E. Tripp (215-337-5282) cc w/encls:
Eugene B. Thomas, Jr.,
Esquire
ENCLOSURE,1 SSINS:
6870 Accession No.:
7910250507 UNITED STATES NUCLEAR REGULATORY COMMISSION
'FFICE.OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Information Notice No. 79-31 Date:
December 13, 1979 Page l.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 8 Webster (S8W), the Architect Engineer for the Virginia Electric 8
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 8 Constructors (UE8C).
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.
The NRC is currently pursuing this issue in detail with S8W and UE8C to deter-mine the extent of the problem and the generic implications for other facilities.
ENCLOSURE 2 IE Information Notice No. 79-31 Date:
December 13, 1979 Page 1 of 1 RECENTLY ISSUED IE INFORMATION NOTICES Information Notice No. 79-22 79-23 79-24 Subject qualification of Control Systems Emergency Diesel Generator Lube Oil Coolers Overpressurization of Con-tainment of a PWR Plant After a Main Steam Line Break Date Issued 9/14/79
'/26/79 10/1/79 Issued to All Power Reactor Faci-lities with an OL or CP All Power Reactor Faci-lities with an OL or CP All Power Reactor Faci-lities with an OL or CP 79-25 79-26 Reactor Trips at Turkey Point Unit 3 and 4 Breach of Containment Integrity 10/1/79 All Power Reactor Faci-lities with an OL or CP ll/5/79 All Power Reactor Facil-ities with an OL or CP 79-12A Attempted Damage to New Fuel Assemblies 11/9/79 All Fuel Facilities, Research Reactors and Power Reactors with an OL'r CP 79-27 Steam Generator Tube Ruptures at Two PWR Facilities ll/16/79 All Power Reactor Faci-lities with an OL or CP 79-28 Overloading of Structural ll/16/79 All Power Reactor Faci-Elements Due to Pipe Support lities with an OL or CP Loads 79-29 79-30 Loss of Nonsafety Rel'ated ll/19/79 Reactor Coolant System In-strumentation During Operation Reporting of Defects and 12/6/79 Noncompliances, 10 CFR Part 21 All Power Reactor Faci-lities with an OL or CP All Power Reactor Faci-lities with an OL or CP
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