ML18081A800
| ML18081A800 | |
| Person / Time | |
|---|---|
| Site: | Salem |
| Issue date: | 12/13/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Schneider F Public Service Enterprise Group |
| References | |
| NUDOCS 7912280234 | |
| Download: ML18081A800 (3) | |
Text
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UNITEDSTATES NUCLEAR REGULATORY COMMISSIOt\\l REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406 Docket No. 50-272 DEC 13 197~
Public Service Electric and Gas Company ATTN:
Mr. F. W. Schneider Vice President - Production 80 Park Place Newark, New Jersey 07101 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,
~~;r,,__
~
Boyce H. Grier
('.-.-- Di rector
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. P. Librizzi, General Manager - Electric Production E. N. Schwalje, Manager - Quality Assurance R._ L. Mittl, General Manager - Licensing and Environment H. J. Midura, Manager -
Sal~m Generating Station I
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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 conjuncti-0n with the as-built review for IE Bulletin 79-14 at North Anna
- Unit l, it was discovered that incorrect amplified response spectra CARS) 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.
0
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Information Notice No. 79-22 79-23 79-24 79-25 79-26 79-12A 79-27 79-28 79-29 79-30 ENCLOSURE 2 IE Information Notice No. 79-31 Date:
December 13, 1979 Page l of 1 RECENTLY ISSUED IE INFORMATION NOTICES Subject Date Issued to Issued.
Qualification of Control 9/14/79 All Power Reactor Faci-lities with an OL or CP Systems Emergency Diesel Generator
- 9/26/79 Lube Oil Coolers All Power Reactor Faci-lities with an OL or CP Overpressurization of Con-10/1/79 All Power Reactor Faci-lities with an OL or CP tainment of a PWR Plant After a Main Steam Line Break Reactor Trips at Turkey 10/1/79 All Power Reactor Faci-1 ities with an OL or CP Point Unit 3 and 4 Breach of Containment 11/5/79 All Power Reactor Facil-ities with an OL or CP Integrity Attempted Damage to New 11/9/79 All Fuel Facilities, Research Reactors and Power Reactors with an OL or CP Fuel Assemblies Steam Generator Tube Ruptures at Two PWR Facilities Overloading of Structural Elements Due to Pipe Support Loads Loss of Nonsafety Related Reactor Coolant System In-strumentation During Operation Reporting of Defects and Noncompliances, 10 CFR Part 21 11/16/79 A 11 Power Reactor Faci-1 it i es with an OL or CP 11/16/79 All Power Reactor Faci-lities with an OL or CP 11/19/79 All Power Reactor Faci-lities with an OL or CP 12/6/79 All Power Reactor Faci-lities with an OL or CP.