ML20071F588: Difference between revisions

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| number = ML20071F588
| number = ML20071F588
| issue date = 10/13/1978
| issue date = 10/13/1978
| title = Responds to ACRS 780713 Ltr Re Sys Interaction,Regulatory Criteria,Backfitting Instrumentation,Shutdown & Heat Removal & Safety Update
| title = Responds to ACRS Re Sys Interaction,Regulatory Criteria,Backfitting Instrumentation,Shutdown & Heat Removal & Safety Update
| author name = Early P
| author name = Early P
| author affiliation = POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
| author affiliation = POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = IPO-162, NUDOCS 7810230191
| document report number = IPO-162, NUDOCS 7810230191
| title reference date = 07-13-1978
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
| page count = 2
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                                                         /
                                                         /
In response to the ACRS        ,
In response to the ACRS        ,
of Concern expressed in their July 13, 1978 letter to the NRC on the subject facility and as a consequence of the Authority's discussion with your staff on September 15, 1978, the fo. wing is the Authority's intention with respect to the itans.
of Concern expressed in their {{letter dated|date=July 13, 1978|text=July 13, 1978 letter}} to the NRC on the subject facility and as a consequence of the Authority's discussion with your staff on September 15, 1978, the fo. wing is the Authority's intention with respect to the itans.
: 1. Review of the plant for systems interaction that might lead to significant degradation of safety.
: 1. Review of the plant for systems interaction that might lead to significant degradation of safety.
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Latest revision as of 03:30, 31 May 2023

Responds to ACRS Re Sys Interaction,Regulatory Criteria,Backfitting Instrumentation,Shutdown & Heat Removal & Safety Update
ML20071F588
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 10/13/1978
From: Early P
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To: Schwencer A
Office of Nuclear Reactor Regulation
References
IPO-162, NUDOCS 7810230191
Download: ML20071F588 (2)


Text

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POWER AUTHORITY OF THE STATE OF NEW YORK 10 CoLUMaus CIRCLE NEW YORK. N. Y.10019 (212, 397.6200 ,

'* GEORGE T. BERRY gND CM EF NG NEER FREDERICK R. CLARK

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LEWIS R. BENNETT C SE y CE C A a4AN WILBUR L. GRONSERG RICHARD M. FLYNN October 13, 1978 E"E *"E'""U"a no: err t Miu.ONu IPO-162 JOHN W; BC,STON, POWER OPERATIONS WILLIAM F. LUDDY 7"o"^5J;,Qc,", ANN, JR.

Director, Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Ccmnission Washington, D.C. 20555 g Attention: Mr. Albert Schwencer, Chief Operating Reactors ~ Branch No. 1

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Subject:

Indian Pcn[nt 3 Nuclear Power Plant ACRS Concerns Docket No'. 50-286

Dear Sir:

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In response to the ACRS ,

of Concern expressed in their July 13, 1978 letter to the NRC on the subject facility and as a consequence of the Authority's discussion with your staff on September 15, 1978, the fo. wing is the Authority's intention with respect to the itans.

1. Review of the plant for systems interaction that might lead to significant degradation of safety.

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'Ihe Power Authority will attend the ACRS Plant Arrangements Sub-comrnittee treeting on October 25, 1978 at which time the Licensee Event Report review performed by the Ccrmonwealth R3ison Occpany for '

their Zion facility in response to a similar ACRS concern will be discussed. Tne discussions and conclusions reached in that subctmnittee meeting and any subsequent presentation before the ACRS full cermlittee will be reviewed by the Authority before deciding on our approach to address this ACRS tratter.

2. Review of the plant with regard to differences frtrn current regulatory criteria and judgment cancerning possible backfitting requirements.

'Ihe Power Authority will review the report prepared by the Camenwealth Edison Ccupany for their Zion facility in response to a similar ACRS concern. Following review of that documnt by the NRC staff and the ACRS, the Power Authority ,will detennine wtiat level of detail is appropriate in order to ocupare IP3 adequately to current criteria.

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October 13, 1978

3. Review of the instrunentation provided to follow the full range or postulated serious accident.

The Power Authority will survey the capability of the existing IP3 fixed and portable instrumentation to Inonitor the course of accidents that extend beyond conditions asstrned in the design of the plant. This survey will be provided to the NRC by July 9, 1979.

4. Audit of the plant's capability for safe shut-down and residual heat renoval, using only safety grade equipnent.

'Ihe Power Authority will participate in the NRC's Overall Plant Heat Removal Capability Survey to be conducted at the IP3 facility on November 14 15 & 16, 1978.

5. Continuing effort be made to update safety related features to the maximum degree possible.

The Power Authority will provide docunentation of the extent to which the IP3 facility satisfies the ACRS resolved generic items as delineated in their Report No. 6 to the NBC. This information will be provided to the NRC by February 19, 1979.

Very trul urs,

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.) d Paul f. Early Assistant Chi.f Engineer-Projects e

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