ML19209C577: Difference between revisions

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{{#Wiki_filter:F-,..Jersey Central Power & Light Company
{{#Wiki_filter:F
, Madison Avenue at Punch Bow! Road
-                                                                                           .
.Morristown, New Jersey 07960
  ,
-^(201)455-8200 August 31, 1979 Mr. Boyce H. Grier, Director Office of Inspection and Enforcement Region I U. S. Nuclear Regulatory Commission 631 Park Avenr-King of Prussia, Pennsylvania 19406  
.
      ,
Jersey Central Power & Light Company
          .                                                              Madison Avenue at Punch Bow! Road
    -^
Morristown, New Jersey 07960 (201)455-8200 August 31, 1979 Mr. Boyce H. Grier, Director Office of Inspection and Enforcement Region I U. S. Nuclear Regulatory Commission 631 Park Avenr-King of Prussia, Pennsylvania 19406


==Dear Mr. Grier:==
==Dear Mr. Grier:==
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==Subject:==
==Subject:==
Oyster Creek Nuclear Generating Station Docket No. 50-219 IE Bulletin 79-14 and 70-14, Rev. 1 By letter dated August 1, 1979, we responded to IE Bulletin 79-14, Rev. 1 entitled " Seismic Analysis for As-Built Safety Related Piping." In this response we indicated that an inspection in accordance with the IE Bulletin had been initiated and a report of the results of this inspection would be submitted by September 1, 1979.
Oyster Creek Nuclear Generating Station Docket No. 50-219 IE Bulletin 79-14 and 70-14, Rev. 1 By letter dated August 1, 1979, we responded to IE Bulletin 79-14, Rev. 1 entitled " Seismic Analysis for As-Built Safety Related Piping." In this response we indicated that an inspection in accordance with the IE Bulletin had been initiated and a report of the results of this inspection would be submitted by September 1, 1979.
Attached is a report of the inspectien conducted at the Oyster Creek Nuclear Generating Station. Of the 295 items inspected, thirty-four nonconformances were identified. Each *onconformance was evaluated to determine the effect on design require..n.ts'.
Attached is a report of the inspectien conducted at the Oyster Creek Nuclear Generating Station. Of the 295 items inspected, thirty-four nonconformances were identified. Each *onconformance was evaluated to determine the effect on design require..n.ts'. In rost cases the non-conformances did not affect the system design requirements; however, nonconformances w2re identified affecting the operability of core spray system II. Consequently, Reportable Occurrence Report No. 50-219/79-27-IT was submitted to the Office of Inspection and Enforcement pursuant to our Technical Specifications. This situation has since been corrected and core spray system II is now in conformance with the system design requirements.
In rost cases the non-conformances did not affect the system design requirements; however, nonconformances w2re identified affecting the operability of core spray system II.
Consequently, Reportable Occurrence Report No. 50-219/79-27-IT was submitted to the Office of Inspection and Enforcement pursuant to our Technical Specifications. This situation has since been corrected and core spray system II is now in conformance with the system design requirements.
Of the total number of inspection items, only 34 nonconformances were identified, and of these, only 6 were found to affect system operability.
Of the total number of inspection items, only 34 nonconformances were identified, and of these, only 6 were found to affect system operability.
Since, with very few exceptions, all nonconformances have been corrected and/or found not to affect system design requirements and since the number of nonconformances were a small percer tige of the total number of inspection items, it is felt that those systems which are inaccessable will likewise prove to be installed in accordance with design documents.
Since, with very few exceptions, all nonconformances have been corrected and/or found not to affect system design requirements and since the number of nonconformances were a small percer tige of the total number of inspection items, it is felt that those systems which are inaccessable will likewise prove to be installed in accordance with design documents. Even though core spray system II was found to be inoperable (considering seismic loads) . this situation occurred in a test line as a result of local phenomenon and it is not expected that this situation exists in the inaccessable portions of this or any other system.
Even though core spray system II was found to be inoperable (considering seismic loads) . this situation occurred in a test line as a result of local phenomenon and it is not expected that this situation exists in the inaccessable portions of this or any other system.
The next scheduled shutdown of the Oyster Creek plant will occur January 5, 1980; therefore based on the above discussion we request 1147 037 7D10160 Il g' :
The next scheduled shutdown of the Oyster Creek plant will occur January 5, 1980; therefore based on the above discussion we request 1147 037 Il 7D10160 g' :...,M__--,,.~e.. m -, _ __..n s _ , , .  
_    --,,.~e     .. m -       , _ _        _..n s _ , , .
>...-2-that <:! ittal c' ths report required by item 3 of IE Bulletin 79-14, Rev. i ha delayed until February 22, 1980.
                                                                            ...,M
We feel that this delay will not acle- ,1y affect the health and safety of the public based on the resu1*.e this inspec*,io s and the relatively short duration of operation allowea by the delay.
 
Vr truly yours, h-.D. A. Ross Manager-Nuclear Generating Stations la cc: Director Office of Inspection and Enforcement Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Wcshington, D. C.
.
20555 Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C.
  >
20555 1147 038}}
  .
.
that <:! ittal c' ths report required by item 3 of IE Bulletin 79-14, Rev. i ha delayed until February 22, 1980. We feel that this delay will not acle- ,1y affect the health and safety of the public based on the resu1* .e this inspec*,io s and the relatively short duration of operation allowea by the delay.
Vr truly yours, h                 .
                                                                                -
D. A. Ross Manager-Nuclear Generating Stations la cc: Director Office of Inspection and Enforcement Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Wcshington, D. C. 20555 Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555 1147 038}}

Revision as of 13:32, 19 October 2019

Forwards Insp Rept in Accordance W/Ie Bulletin 79-14 & 79-14,Revision 1.Of 295 Items inspected,34 Noncomformances Were Identified.All Noncomformances Have Been Corrected &/Or Found Not to Effect Sys Design Requirements
ML19209C577
Person / Time
Site: Oyster Creek
Issue date: 08/31/1979
From: Ross D
JERSEY CENTRAL POWER & LIGHT CO.
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19209C579 List:
References
NUDOCS 7910160170
Download: ML19209C577 (2)


Text

F

- .

,

.

,

Jersey Central Power & Light Company

. Madison Avenue at Punch Bow! Road

-^

Morristown, New Jersey 07960 (201)455-8200 August 31, 1979 Mr. Boyce H. Grier, Director Office of Inspection and Enforcement Region I U. S. Nuclear Regulatory Commission 631 Park Avenr-King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 IE Bulletin 79-14 and 70-14, Rev. 1 By letter dated August 1, 1979, we responded to IE Bulletin 79-14, Rev. 1 entitled " Seismic Analysis for As-Built Safety Related Piping." In this response we indicated that an inspection in accordance with the IE Bulletin had been initiated and a report of the results of this inspection would be submitted by September 1, 1979.

Attached is a report of the inspectien conducted at the Oyster Creek Nuclear Generating Station. Of the 295 items inspected, thirty-four nonconformances were identified. Each *onconformance was evaluated to determine the effect on design require..n.ts'. In rost cases the non-conformances did not affect the system design requirements; however, nonconformances w2re identified affecting the operability of core spray system II. Consequently, Reportable Occurrence Report No. 50-219/79-27-IT was submitted to the Office of Inspection and Enforcement pursuant to our Technical Specifications. This situation has since been corrected and core spray system II is now in conformance with the system design requirements.

Of the total number of inspection items, only 34 nonconformances were identified, and of these, only 6 were found to affect system operability.

Since, with very few exceptions, all nonconformances have been corrected and/or found not to affect system design requirements and since the number of nonconformances were a small percer tige of the total number of inspection items, it is felt that those systems which are inaccessable will likewise prove to be installed in accordance with design documents. Even though core spray system II was found to be inoperable (considering seismic loads) . this situation occurred in a test line as a result of local phenomenon and it is not expected that this situation exists in the inaccessable portions of this or any other system.

The next scheduled shutdown of the Oyster Creek plant will occur January 5, 1980; therefore based on the above discussion we request 1147 037 7D10160 Il g' :

_ --,,.~e .. m - , _ _ _..n s _ , , .

...,M

.

>

.

.

that <:! ittal c' ths report required by item 3 of IE Bulletin 79-14, Rev. i ha delayed until February 22, 1980. We feel that this delay will not acle- ,1y affect the health and safety of the public based on the resu1* .e this inspec*,io s and the relatively short duration of operation allowea by the delay.

Vr truly yours, h .

-

D. A. Ross Manager-Nuclear Generating Stations la cc: Director Office of Inspection and Enforcement Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Wcshington, D. C. 20555 Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555 1147 038