ML20091P671

Comments on Requested Mods to SEP Topic VI-7.A.3 Re ECCS Actuation Sys.Testing of Emergency Condenser Logic Trains & Related Components Already Required by Tech Specs.No Tech Spec Mod Required

ML20091P671
Person / Time
Site:	Oyster Creek
Issue date:	06/04/1984
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
TASK-06-07.A3, TASK-6-7.A3, TASK-RR NUDOCS 8406130135
Download: ML20091P671 (2)

Text

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GPU Nuclear Corporation Nuclear

',=:r388 Forked River.New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:

June 4, 1984 Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch #5 U.S.

Nuclear Regulatory Commission Washington, DC 20555

Subject:

Oyster Creek Nuclear Generating Station (OCNGS)

Docket No. 50-219 SEP Topic No. VI-7.A.3 Emergency Core Cooling System Actuation System During the integrated assessment of the SEP topics, the NRC staff requested that the Oyster Creek Technical Specifications be modified to include channel checks, functional testing, and calibration of the emergency condenser instrumant parameters.

The staff concluded that this modification is necessary because the emergency condenser is required to achieve plant shutdown for various accident scenarios or external events (e.g.,

hurricane induced flooding, tornado missile incident).

Our investigation indicates that the testing of the emergency condenser logic trains and associated components is already reghired by the existing Oyster Creek Technical Specifications.

Table 4.1.1 of the Technical Specifications requires test and calibration of the Low Low Reactor Water Level, Reactor High Pressure, High Condensate Flow, and High Steam Flow instrumentation (Items 4, 1, and 22).

These requirements are satisfied by procedures 610.3.005, " Core Spray System Instrument Channel Calibration and Test",

609.3.003, " Isolation Condenser, Automatic Acutuation Sensor Calibration and Test" and 609.3.002, " Isolation Condenser Isolation Test and Calibration."

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GPU Nuclear Corporation is a subsidiary of the General Pubhc Utihties Corporation 1 D L

s Mr. D:nnic M. Crutchfield, Cnief U.S.

Nuclear Rcgulatory Commission Page 2 Taole 4.1.2 item 9 of tne Technical Specifications requires a test of the Isolation Condenser Actuation and Isolation, (each trip circuit independently) during eacn refueling outage.

These requirements are satistied oy procedures 619.3.004

" Reactor Low Low Water Level Functional Tests" and again in 609.3.002.

Section 4.8 of the Tecnnical Specifications also requires Automatic Actuation and Functional Test of each isolation condenser loop during eacn refueling outage or following ma]or repair and additionally requires operability of motor operated valves once per month.

Tne valve operability test is satisfied by procedure 609.4.001 which can satisfy the manual start requirement.

Oyster Creek Reference Index which will De available before the startup of the next reactor cycle, will list Tecnnical Specitication surveillance requirements with applicable procedures and frequencies of tne surveillances.

Requirements of Tables 4.1.1, 4.1.2 and Section 4.8 of the Tecnnical Specifications will be accomplished oy tne applicaDie procedures referenced in tne Cross Reference Index.

Therefore, a modification of the existing Tecnnical Specifications concerning the testing of the emergency condenser logic trains is not considered necessary.

Very truly yours, P

B Vice President and Director Oyster Creek PBF/0178s cc: Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731