ML20154E318
| ML20154E318 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 05/06/1988 |
| From: | Chan T Office of Nuclear Reactor Regulation |
| To: | Cockfield D PORTLAND GENERAL ELECTRIC CO. |
| References | |
| IEB-88-002, IEB-88-2, TAC-67328, NUDOCS 8805200170 | |
| Download: ML20154E318 (4) | |
Text
.
!!ay 6, 1988 i
l i
Docket No.:
50-344
,DISTRIBUTLON.
ipoetet J1 c-Mr. David W. Cockfield NRC'& LPDRs Vice President, Nuclear DCrutchfield Portland General Electric Company TChan 121 S.W. Salmon Street 0GC I
Portland, Oregon 97204 EJordan JNeighbors f
JPartlow KWichman
Dear Mr. Cockfield:
ACRS(10)
EMurphy
SUBJECT:
NRC BULLETIN 88-02; RAPIDLY PROPAGATING FATIGUE CRACKS l
IN STEAM GENERATOR TUBES (TAC NO. 67328)
On February 5, 1988, NRC Bulletin 88 02 requested that holders of operating l
licenses or construction permits for Westinghouse designed nuclear power reactors with steam generators having carbon steel support plates implement l
certain specified actions to minimize the potential for a steam generator tube rupture event caused by a rapidly propagating fatigue crack such as that which occurred at North Anna Unit 1 on_ July 15, 1987. The bulletin also specified a schedule for the submittal of the requested information, and included t
l provisions by which schedular variances would be considered.
l By letter dated March 11, 1988, Portland General Electric Company (PGE) responded to the Bulletin and requested a schedular extension for the submission of the results of the steam generator tube analyses and proposed corrected actions, to July 31, 1988. The March 11, 1988 response was i
supplemented by PGE letter dated April 1, 1988.
l t
1 The staff has reviewed your responses and concludes that the requested j
schedular extension is warranted, and is therefore acceptable.
i Sincerely, original signed by Terence Chan Terence L. Chan, Project Manager Froject nirectorate Y Division of Reactor Projects - Ill, IV, V and Special Projects Office of Nuclear Reactor Regulation 1
i cc: See next page
' 0FC :DRSP/PDV
- DRSP/D:PDV NAME :TChan:cw
- G ighton 3
4DATE :05/ /88
- 05/6 /88 i
0FFICIAL RECORD COPY s
4 8805200170 080506 PDR ADOCK 05000344 G
PDR 1
-. _ ~ - -
.o
!!ay 6,1908 9
\\
Docket No.:
50 344 DISTRIBUTION Docket File Mr. David W. Cockfield NRC & LPDRs Yice President, Nuclear DCrutchfield Portland General Electric Company.
TChan 121 S.W. Salmon Street OGC Portland, Oregon 97204 EJordan JNeighbors JPartlow KWichman
Dear Hr. Cockfield:
ACRS (10)
EMurphy
SUBJECT:
NRC BULLETIN 88-02; RAPIDLY PROPAGATING FATIGUE CRACKS IN STEAM GENERATOR TUBES (TAC NO. 67328)
On February 5,1988, NRC Bulletin 88-02 requested that holders of operating licenses or construction permits for Westinghouse designed nuclear power i
reactors with steam generators having carbon steel support plates implement certain specified actions to minimize the potential for a steam generator tube rupture event caused by a rapidly propagating fatigue crack such as that which j
occurred at North Anna Unit 1 on July 15, 1987.
The bulletin also specified a j
schedule for the submittal of the requested information, and included provisions by which schedular variances would be considered.
i By letter dated March 11, 1988 Portland General Electric Company (PGE) responded to the Bulletin and requested a schedular extension for the submission of the results of the steam generator tube analyses and proposed corrected actions, to July 31, 1988. The March 11, 1988 response wa; 4
supplemented by PGE letter dated April 1, 1988.
The staff has reviewed your responses and concludes that the requested schedular extension is warranted, and is therefore acceptable.
Sincerely, original signed by Terence Chan Terence L. Chan, Project Manager i
Project Directorate Y Division of Reactor Projects. III, IV, Y and Special Projects Office of Nuclear Reactor Regulation cc: See next page UFC
- DRSP/PDV
- DRSP/D:PDV NAME :TChan:cw
- Gl~'ghton :
DATE :05/ /88
- 05/ 6 /88 l
0FFICIAL RECORD COPY l
- 'pusam o
UNITED STATES
- g
' I" w NUCLEAR REGULATORY COMMISSION g
W ASHINGTON, D. C, 20655
%...../
"ay 6, 1938 Docket No.:
50-344 for. David W. Cockfield Vice President, Nuclear Portland General Electric Company 121 S.V. Salmon Street Portland, Oregon 97204
Dear Mr. Cockfield:
SUBJECT:
NPC BULLETIN 88-02; RAPIDLY PROPAGATING FATIGUE CRACKS IN STEAM GENERATOR TljBES (TAC NO. 67328)
On February 5,1988, NRC Bulletin 88-02 requested that holders of operating licenses or construction permits for Westinghouse designed nuclear power reactors with steam generators having carbon steel support plates implement certain specified acticns to minimize the potential for a steam generator tube rupture event caused by a rapidly propagating fatigue crack such as that which occurred at North Anna Unit 1 on July 15, 1987.
The bulletin also specified a schedule for the submittal of the requested information, and included provisions by which schedular variances would be considered.
By letter dated March 11, 1988, Portland General Electric Company (PGE) responded to the Bulletin and requested a schedular extension for the submission of the results of the steam generator tube analyses and proposed corrected actions, to July 31, 1988. The March 11, 1988 response was supplemented by PGE letter dated April 1,1968.
The staff has reviewed your responses and concludes that the requested schedular extension is warranted, and is therefore acceptable.
Sin
'ely,
/
Terence L. Chan, Project Manager Project Directorate V Division of Reactor Projects - 111, IV, V and Special Projects Office of Nuclear Reactor Regulation ec:
See next page
2 Mr. David W. Cockfield Portland General Electric Company Trojan Nuclear Plant cc:
Senior Resident Inspector I
U.S. Nuclear Regulatory Commission Trojen Nuclear Plant Post Office Box 0 Rainier, Oregon 97048 Mr. Michael J. Sykes, Chairman Board of County Commissioners Columbia County St. Helens, Oregon 97501 Mr. William T. Dixon Oregon Department of Energy Salem, Oregon 97310 Regional Aoministrator, Region V U.S. Nuclear Regulatory Commission i
1450 Maria Lane, Suite 210 Walnut Creek, California 94596 1
J l