ML19347A848: Difference between revisions

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{{#Wiki_filter:"Im Es:: I     ,
{{#Wiki_filter:"Im Es:: I L. :-
L. :-   1 -    - - - -
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                                      ,..  .
400 Chestnut Street Tower II September 25, 1980 Mr. James P. O'Re y, Director Office of Insp lon and Enforcement U.S. Nuclear egulatory Commission Region II Suite 3100 101 Mar *,,ta Strect Atlant, Georgia 30303
                                                      .-- -
400 Chestnut Street Tower II September 25, 1980 l
Mr. James P. O'Re       y, Director l
Office of Insp     lon and Enforcement                                       '
U.S. Nuclear egulatory Commission l
Region II     Suite 3100                                                       !
101 Mar * ,,ta Strect Atlant , Georgia 30303


==Dear Mr. O'Reilly:==
==Dear Mr. O'Reilly:==
SECUOYAH !!UCLEAR PLANT UNIT 2 - UHI HYERAULIC ISOLATI0t! VALVE ACCUMULATOR WEIGhI:.G SYSTEM - NCR SQN NEB 8007 - FOURTH I!CERIM REPORT The cub, ject deficiency was initially reported to NRC.-0IE Inspector M. J. Gougo en March 25, 1980, in cccordance uith 10 CFR 50.55(e).
SECUOYAH !!UCLEAR PLANT UNIT 2 - UHI HYERAULIC ISOLATI0t! VALVE ACCUMULATOR WEIGhI:.G SYSTEM - NCR SQN NEB 8007 - FOURTH I!CERIM REPORT The cub, ject deficiency was initially reported to NRC.-0IE Inspector M. J. Gougo en March 25, 1980, in cccordance uith 10 CFR 50.55(e).
Interim reports wrc submitted on April 24, June 18, and July 23, 1980.
Interim reports wrc submitted on April 24, June 18, and July 23, 1980.
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TVA has decided to delay the design changes proposed by Westinghouse until fbrther toating is completed. These design changes will use direct pressure indicatiens to verify propor necumulator charge. The addi-ticnal testing will be conducted to verify that this change is sufficient to correct this problem.
TVA has decided to delay the design changes proposed by Westinghouse until fbrther toating is completed. These design changes will use direct pressure indicatiens to verify propor necumulator charge. The addi-ticnal testing will be conducted to verify that this change is sufficient to correct this problem.
If you l' ave cny qucations, please got in touch with D. L. Lambert at FTS 8S7-2581.
If you l' ave cny qucations, please got in touch with D. L. Lambert at FTS 8S7-2581.
Very truly yours, T3NNESSEE VALLEY AUTHOL:TY l
Very truly yours, T3NNESSEE VALLEY AUTHOL:TY L. M. Mills, Manager i
L. M. Mills, Manager               i Nuclear Regulation and Safety cc:   Mr. Victor Stel2o, Director l
Nuclear Regulation and Safety cc:
Office of Inspecticn and Enforcement U.S. Nuclear Regulatory Concission Washington, DC 20555 30/7 S
Mr. Victor Stel2o, Director Office of Inspecticn and Enforcement U.S. Nuclear Regulatory Concission Washington, DC 20555 30/7 S
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Latest revision as of 06:42, 24 December 2024

Fourth Interim Deficiency Rept Re Upper Head Injection Hydraulic Isolation Valve Accumulator Weighing Sys.Util Will Delay Design Changes Proposed by Westinghouse Until Further Testing Completed
ML19347A848
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 09/25/1980
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
10CFR-050.55E, 10CFR-50.55E, NCR-SQNNEEB8007, NUDOCS 8009300395
Download: ML19347A848 (1)


Text

"Im Es:: I L. :-

1 -

400 Chestnut Street Tower II September 25, 1980 Mr. James P. O'Re y, Director Office of Insp lon and Enforcement U.S. Nuclear egulatory Commission Region II Suite 3100 101 Mar *,,ta Strect Atlant, Georgia 30303

Dear Mr. O'Reilly:

SECUOYAH !!UCLEAR PLANT UNIT 2 - UHI HYERAULIC ISOLATI0t! VALVE ACCUMULATOR WEIGhI:.G SYSTEM - NCR SQN NEB 8007 - FOURTH I!CERIM REPORT The cub, ject deficiency was initially reported to NRC.-0IE Inspector M. J. Gougo en March 25, 1980, in cccordance uith 10 CFR 50.55(e).

Interim reports wrc submitted on April 24, June 18, and July 23, 1980.

We expect to submit cur next report by January 9,1981.

TVA has decided to delay the design changes proposed by Westinghouse until fbrther toating is completed. These design changes will use direct pressure indicatiens to verify propor necumulator charge. The addi-ticnal testing will be conducted to verify that this change is sufficient to correct this problem.

If you l' ave cny qucations, please got in touch with D. L. Lambert at FTS 8S7-2581.

Very truly yours, T3NNESSEE VALLEY AUTHOL:TY L. M. Mills, Manager i

Nuclear Regulation and Safety cc:

Mr. Victor Stel2o, Director Office of Inspecticn and Enforcement U.S. Nuclear Regulatory Concission Washington, DC 20555 30/7 S

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