ML19209B547

Forwards Info Re Potential Interaction Between Nonsafety Grade Sys & Safety Grade Sys in Response to NRC 790917 Request.Evaluation Has Not Identified Any Adverse Impact

ML19209B547
Person / Time
Site:	Oyster Creek
Issue date:	10/05/1979
From:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
To:	Office of Nuclear Reactor Regulation
References
TASK-07-04, TASK-7-4, TASK-RR NUDOCS 7910100097
Download: ML19209B547 (6)

Text

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Jersey Central Pcwer & Ught Company

. Madison Avenue at Punch Bowl Road Morristown. New Jerrey 07960 (201)455-8200 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20t55 .

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Interaction Between Non-Safety Grade Systems and Safety Grade Systems Your letter of September 17, 1979 airected us to provide within twenty days information on potential adverse impacts on our safety analyses and safety grade equipment from n_n-safety grade equipment subject to the environcental effects of high energy line breaks. The information that you requested is presented as follows:

Table 1 contains a list of systems for which it was determined that their failure or malfunction could not affect safety. These systems cannot adversely affect the operation of a safety system, the response of the reactor, or the containment of radioactive materials. Environmental effects on these systems were not reviewed and they are not included on the interaction matrix, Table 2.

Table 2 is the Environmental Interaction Matrix. Across the top of the matrix are listed high energy piping systems and general break localities. On the left hand side are listed non-safety systems which if affected by high energy line breaks could possibly affect the operation of a safety system, the response of tne reactor, or the containment of radioactive materials. The entries in the matrix are explained by the notes following the matrix.

The subject of high energy lin) break effects on safety - stems has already been addressed in Amendments 68 and 75 of the Oyster Crec facility Description and Safety Analysis Report (FDSAR) . Certain high energy systes inc1tried in those reports are not listed in the matrix. The Shutdown Cooling System, Core Spray System and Liquid Poison System, due to the very short periods during which they might contain high temperature or high pressure fluids, are not considered high energy systms under current criteria. Other high energy systems contain only high pressure but not high temnperature fluid and do not have the capability to produce other than local effects. Suca 1134 ^16 7 910100 M 7 Jersey Central Power & Ught Company is a Member of the General Public Utikhes Systern

ystems incltx3e the Control Rod Drive Hydraulic System, Reactor Vessel Head Cooling and the Condensate Pump Discharge. Other systens contain low pressure, high temperature fluids. Failures in any of these systems would impose only a mild transient on the plant and would not produce any adverse impacts that would prevent an orderly plant shutdown by the operators.

The evaluation attached to this letter has not identifind any adverse impact on safety actions or analysis conclusions which would incraase the consequences (peak cled temperature, containment pressure, torus water temperature, or radiological release) of any accidents analyzed in the FDSAR.

TM evaluation included walk-through of areas containing high energy lines for the identification of non-safety equipment potentially affected by an adverse enviroment. The locations of cables are still under review. Based on our work to date, no adverse interactions between cables and high energy systems are expected. If any are found, they will be reported.

In light of our findings and the material provided in Tdales 1 and 2 we feel that this provides your staff with the information necessary to make the determination that the cperating licensing for the Oyster Creek Nuclear Generatirq Station need not be modified, suspc Jed, or revoked.

Very truly yours, h

Ivan R. Finfr l

, Jr Vice Presioent STATE OF NEW JERSEY )

)

COUNIY OF MORRIS )

Sworn and subscribed to before me this n/ day of C 6 ~<.,

1979.

. A/ . i i w /A ,s c Notary Public V "l: . :

!:077 - / P L. : T '.E W KUEY f.'y C:,- L ,: n E - : Aug, li,1784 113s 17

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TABLE 1 SYSTEMS WHOSE FAILURE OR MALFUNCTION CANNOT AFFECT SAFETY Lighting Communicatiens Equipm?nt Drains Fuel H.i dling Equipment Fuel Pool Cooling 6 Cle;nup Off-gas Sampling Systems Computer Area Rsdiation Monitors (except RB 119' Level)

Process Radiation Monitors (except b6 Line tunnel and Off-gas line)

Cranes S bbnorails Environmental Monitoring Demineralized Water Potable Water Screen Wash Turbine and Generator Auxiliary Systems Vacuum Pumps Reactor Head Spray Drywell Cooling Core Spray 6 Containment Spray Pump Room Cooling Service Air Under Vessel Maintenance Equipment i134 ~1B

Page 1 of 3 TABLE 2 ENVIRON)fENTAL INTERACTION MATRIX .

Main Steam Line Feedwater LOCA Isolation Condenser Cleanup Tunnal Tunnel Affectc3 System Location DW 6 TB DW STB Lg SM RB RB Recirculation System -- -- -- -- -- -- -- -- --

- Pumps DN 2 4 2 4 2 2 4 4

- Valves 6 Operators DN 2 4  ? 4 2 2 4 4

- MG Sets RB 4 4 1 1 4 4 4 4

- NCC 6 Switchgear RB/TB 4 2 2 4 4 4 4

- Flow Control Sys. CR 4 4 4 4 4 4 4 4

- Control Inst. Trans. RB 4 4 4 4 4 4 4 4 Feedwater System -- -- -- - -- -- -- -- --

- Pumps TB 4 2 4 2 4 4 4 4

- Valves S Operators TB 4 2 4 2 4 4 4 4

- MCC 6 Switchgear TB 4 2 4 2 4 4 4 4

- Flow Control Sys. CR 4 4 4 4 4 4 4 4

- Flow Measurement TB 4 2 4 2 4 4 4 4

- Reactor Water Level Meas. DW/RB 2 4 2 4 2 2 4 4

- FW lleating TB 4 2 4 2 4 4 4 4

- Control Inst. Trans. RB/TB 4 2 4 2 4 4 4 4 Turbine Pressure Control -- -- -- -- -- -- -- -- --

- Bypass Valves TB 4 2 4 2 4 4 4 4

- Pressure Sensors TB 4 2 4 2 4 4 4 4

- Control System CR 4 4 4 4 4 4 4 4

- EllC TB 4 2 4 2 4 4 4 4

- Stop 6 Control Valves TB 4 2 4 2 4 4 4 4 Neutron bbnitoring -- -- -- -- -- -- -- -- --

- LPRMs G Cables DW/RB 2 4 2 4 2 2 4 4

- APRMs 6 Cables DW/RB 2 4 2 4 2 2 4 4

- RPIS 6 Rod Block Mon. DW/RB 2 4 2 4 2 2 4 4

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Reactor Protection -- -- -- -- -- -- -- -- --

- Turbine Scram TB 4 2 4 2 4 4  ? 4

- MG Set RB 4 4 4 4 4 4 4 4

~C Reactor hhnual Control RB/CR 4 4 4 4 4 4 4 4 Relief Valves DW/RB 3 4 .5 4 3 3 4 2 RBCCW DW/RB 2 4 2 4 2 2 4 4 Cleanup DW/RB 3 4 3 4 3 3 2

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. . Page 3 of 3 TABLE 2 NOTES 1 = Environmental induced malfunction may produce adverse response, i.e.,

increase in previously reported peak fuel clad temperature, contain-ment pressure, torus water temperature or radiological release.

2 = Environmental induced malfunction will not produce adverse response.

3 = System is qualified for adverse environment.

4 = System will not experience adverse environment.

Building Nomenclature DW - Dry Well P9 - Reactor Building TB - Turbine Building CR - Control Room Tunnel - Main Steam Line Tunnel 1139 '21

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