ML19347F429
| ML19347F429 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/13/1981 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| JPN-81-36, NUDOCS 8105190262 | |
| Download: ML19347F429 (4) | |
Text
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POWER AUTHORITY OF THE STATE OF NEW YORK 10 Cotuusus CIRCLE NEW YORK. N. Y.10019 o E*",G,E,,T 8,8,""Y....c..........
a 212 as7.62oo raustras JOHN W. SOSTO JoMN S.DvsON
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....s Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. Thomas A.
Ippolito, Chief Operating Reactors Branch No. 2 Division of Licensing
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Reactor Protection System Power Supply Upgrade
References:
- 1) Letter, J.P. Bayne (PASNY) to T.A.
Ippolito (NRC) dated January 19, 1981 (JPN-81-8)
- 2) Letter, T.A.
Ippolito to G.T.
Berry dated September 24, 1980
Dear Sir:
Attached is the Reactor Protection System Power Supply con-ceptual design information the Power Authority committed to pro-vide in Reference 1 and initially requested by Reference 2.
These l
modifications will provide redundant class IE protection at the interface of the non-class IE power supplies and Reactor Protection System.
The modifications are based upon General Electric's con-ceptual design and the modifications installed on, Hatch 1 as applicable to the James A. FitzPatrick plant.
The Authority anticipates installing these modifications during the 1981 refueling outage contingent upon timely equipment delivery.
Proposed Technical Specification changes if required, will be in-cluded with our Reload 4 submittal.
Very truly yours,
,AT '.':
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Senior Vice President
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ATTACHMENT JAMES A. FITZPATRICK NUCLEAR POWER PLANT REACTOR PROTECTION SYSTEM PROTECTIVE RELAY UPGRADE MODIFICATION DESIGN INFORMATIOP I.
Background
The NRC, as part of a generic study, identified certain specific deficiencies in the design of the voltage regulator system of the motor generation sets, as follows:
(1)
There were potential undetectable single component failures which could adversely affect the operability of the reactor protection system; and (2) there is a postulated sequence of component malfunctions initiated by an earthquake which could adversely affect the operability of the reactor protection system.
In a NRC letter dated September 24, 1980, the Commission imposed the requirement that the power supply should be modified by the end of the next refueling outage and recommended a conceptual design utilized at Hatch.
Figure 1 provides a schematic description of the existing Reactor Protection System Power Supply - FitzPatrick has two identical supply busses.
II.
Modification Description Figure 2 provides a schematic description of the proposed modification.
The modification includes redundant protection circuitry which is environmentally and seismically qualified on each power source to the RPS busses.
I This modification will improve the reliability of operation of the Reactor Protection System to more closely meet the criterion of IEEE Standard 379-1977 "IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station IE Systems" and thus meet NRC requirements.
The modification includes a total of eight protective circuitry units, two in each power source in series, such that a single component failure would not adversely affect the operability of the Reactor Protective System.
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