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{{#Wiki_filter:UNITED STATES 0 NUCLEAR REGULATORY COMMISSION REGION IV 612 EAST LAMAR BLVO, SUITE 400 ARLINGTON, TEXAS 76011-4125 September 5, 2008 Mr. Ross T. Ridenoure Senior Vice President and Chief Nuclear Officer Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128 | {{#Wiki_filter:UNITED STATES 0 NUCLEAR REGULATORY COMMISSION REGION IV 612 EAST LAMAR BLVO, SUITE 400 ARLINGTON, TEXAS 76011-4125 September 5, 2008 Mr. Ross T. Ridenoure Senior Vice President and Chief Nuclear Officer Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128 | ||
==SUBJECT:== | ==SUBJECT:== | ||
ALLEGATION NO. RIV-2008-A-01 17 | ALLEGATION NO. RIV-2008-A-01 17 | ||
==Dear Mr. Ridenoure:== | ==Dear Mr. Ridenoure:== | ||
IwvU o | IwvU U o I LJUU I'U, I | ||
Your response to this request should not be docketed, and the distribution of your response should be limited.Should you have any further questions concerning our requests, our role in this matter, or require additional time to accomplish this request, please contact Mr. Freeman at 817-860-8245.Sincerely, Dwight D. Chamberlain, Director Division of Reactor Projects | ,r VIPIV l lLy-i ;cli*J i y QUi VIIIOI 1,'-. IVIIUQQlI advised that Southern California Edison Company was investigating discrepancies identiri between the times recorded on the surveillance data sheets and the actual key card data. | ||
We request that you provide the results of your investigation within 30 days of the date of this letter to NRC, Region IV, ATTN: Harry Freeman, Senior Allegation Coordinator, and make records of the investigation available for NRC inspection. Your response to this request should not be docketed, and the distribution of your response should be limited. | |||
Should you have any further questions concerning our requests, our role in this matter, or require additional time to accomplish this request, please contact Mr. Freeman at 817-860-8245. | |||
Sincerely, Dwight D. Chamberlain, Director Division of Reactor Projects | |||
==Enclosure:== | ==Enclosure:== | ||
As Stated Dockets: 50-361; 50-362 Licenses: NPF-10; NPF-15 Informaton in accordanceinwith thisthe record was deleted m | |||
-CERTIFIED MAL' | |||
.. TU. ,RECEI-PT REQUESTED e | |||
7:.. | |||
" ....... 2008 0117; Received By: .Receipt Date: 08/26/2008. | |||
Michael Hay O Receipt Method: Pho0ne C-all Other Method | |||
Michael Hay O Receipt Method: Pho0ne C-all Other Method&Faclt Name: San OnI | & | ||
However, key card checks were performed indicating that lime spent in the battery areas by the electricians wouldn't be adequate to perform the surveillance. | Faclt Name: San OnI LoainSa Clementelh CA. . . . | ||
2ttgin concern specifics. | Electrical technicians failed to perform Tech Spec SR3.8.4.1, 'Verily battery terminal voltage is greater than or equal to 129 V on float charge.' Specifically, during a licensee investigation it was identified that performance of the surveillance was documented as being completed satisfactory. However, key card checks were performed indicating that lime spent in the battery areas by the electricians wouldn't be adequate to perform the surveillance. | ||
Mat is the cqpcein, hndjdjloccu,, | 2ttgin concern specifics. Mat is the cqpcein, -M- hndjdjloccu,, whowasinvo)ved.etc. [-Ihg c*ncem Involve$ discrimination ýIlinthgI@Ak seglion Qf the torm. | ||
[-Ihg c*ncem Involve$ discrimination | What is the potential safety impact? Is this an-ongping.concem? | ||
ýIlinthgI@Ak seglion Qf the torm.What is the potential safety impact? Is this an-ongping.concem? | Failure to perlorm surveillance impacts ability to assess functionality of the electrical bus. This surveillance has a frequency for being performed every 7 days. | ||
Failure to perlorm surveillance impacts ability to assess functionality of the electrical bus. This surveillance has a frequency for being performed every 7 days.Nhat re-quirement/reaulation ooverns this con ern?Tech Spec SR 3.8.4.1 What records should ling NRQ review?Completed Tech Spec surveillance procedure records for SR 3.B.4.1, key card entry reports for the control building 50 toot level (location of all batteries) | Nhat re-quirement/reaulation ooverns this con ern? | ||
What other indMduats could the NRC contap.1 for ini r__tj ?Ucensee is p6rforming an investigation of the issue. Contacts ar I I)Yas ft 2Qncem brought to manaaemerý'j gtgti9p? | Tech Spec SR 3.8.4.1 What records should ling NRQ review? | ||
Potential willfut aspects Inf -....F1,1171-}} | Completed Tech Spec surveillance procedure records for SR 3.B.4.1, key card entry reports for the control building 50 toot level (location of all batteries) | ||
What other indMduats could the NRC contap.1 for ini r__tj ? | |||
Ucensee is p6rforming an investigation of the issue. Contacts ar I not? | |||
I)Yas ft 2Qncem brought to manaaemerý'j gtgti9p? ion? 11sg wbal actions have been taken if not. why ' ' | |||
Yes brouaht to !he NRC',* ptle.n | |||
:W.*hwas the COncern ) | |||
IPotential Why was the aspects concern willful brought to the NRC's a~ltention? | |||
Potential willfut aspects Inf - .... | |||
F1,1171-}} |
Revision as of 05:24, 12 November 2019
ML12118A142 | |
Person / Time | |
---|---|
Site: | San Onofre ![]() |
Issue date: | 09/05/2008 |
From: | Chamberlain D NRC/RGN-IV/DRP |
To: | Ridenoure R Southern California Edison Co |
References | |
FOIA/PA-2011-0157, RIV-2008-A-0117 | |
Download: ML12118A142 (2) | |
Text
UNITED STATES 0 NUCLEAR REGULATORY COMMISSION REGION IV 612 EAST LAMAR BLVO, SUITE 400 ARLINGTON, TEXAS 76011-4125 September 5, 2008 Mr. Ross T. Ridenoure Senior Vice President and Chief Nuclear Officer Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128
SUBJECT:
ALLEGATION NO. RIV-2008-A-01 17
Dear Mr. Ridenoure:
IwvU U o I LJUU I'U, I
,r VIPIV l lLy-i ;cli*J i y QUi VIIIOI 1,'-. IVIIUQQlI advised that Southern California Edison Company was investigating discrepancies identiri between the times recorded on the surveillance data sheets and the actual key card data.
We request that you provide the results of your investigation within 30 days of the date of this letter to NRC, Region IV, ATTN: Harry Freeman, Senior Allegation Coordinator, and make records of the investigation available for NRC inspection. Your response to this request should not be docketed, and the distribution of your response should be limited.
Should you have any further questions concerning our requests, our role in this matter, or require additional time to accomplish this request, please contact Mr. Freeman at 817-860-8245.
Sincerely, Dwight D. Chamberlain, Director Division of Reactor Projects
Enclosure:
As Stated Dockets: 50-361; 50-362 Licenses: NPF-10; NPF-15 Informaton in accordanceinwith thisthe record was deleted m
-CERTIFIED MAL'
.. TU. ,RECEI-PT REQUESTED e
7:..
" ....... 2008 0117; Received By: .Receipt Date: 08/26/2008.
Michael Hay O Receipt Method: Pho0ne C-all Other Method
&
Faclt Name: San OnI LoainSa Clementelh CA. . . .
Electrical technicians failed to perform Tech Spec SR3.8.4.1, 'Verily battery terminal voltage is greater than or equal to 129 V on float charge.' Specifically, during a licensee investigation it was identified that performance of the surveillance was documented as being completed satisfactory. However, key card checks were performed indicating that lime spent in the battery areas by the electricians wouldn't be adequate to perform the surveillance.
2ttgin concern specifics. Mat is the cqpcein, -M- hndjdjloccu,, whowasinvo)ved.etc. [-Ihg c*ncem Involve$ discrimination ýIlinthgI@Ak seglion Qf the torm.
What is the potential safety impact? Is this an-ongping.concem?
Failure to perlorm surveillance impacts ability to assess functionality of the electrical bus. This surveillance has a frequency for being performed every 7 days.
Nhat re-quirement/reaulation ooverns this con ern?
Tech Spec SR 3.8.4.1 What records should ling NRQ review?
Completed Tech Spec surveillance procedure records for SR 3.B.4.1, key card entry reports for the control building 50 toot level (location of all batteries)
What other indMduats could the NRC contap.1 for ini r__tj ?
Ucensee is p6rforming an investigation of the issue. Contacts ar I not?
I)Yas ft 2Qncem brought to manaaemerý'j gtgti9p? ion? 11sg wbal actions have been taken if not. why ' '
Yes brouaht to !he NRC',* ptle.n
- W.*hwas the COncern )
IPotential Why was the aspects concern willful brought to the NRC's a~ltention?
Potential willfut aspects Inf - ....
F1,1171-