ML20148G493

Requests Addl Info Re Implementation of ATWS Rule Requirements,Including Provision of Electrical Functional Diagrams for ARI & RPT Sys from Sensors to Final Actuated Devices,By 880210

ML20148G493
Person / Time
Site:	Oyster Creek
Issue date:	01/19/1988
From:	Dromerick A Office of Nuclear Reactor Regulation
To:	Fielder P GENERAL PUBLIC UTILITIES CORP.
References
TAC-66126, NUDOCS 8801260520
Download: ML20148G493 (4)

Text

_ _ _ _ _ _

UAN 191989 Docket No. 50-219 DISTRIBUTION dancketJ11e# A. Drcmerick NRC & Local PDRs CGC-Bethesda

,, Mr. P. B. Fielder PDI-4 Reading E. Jordan

!Vice President and Director S. Varca J. Partlow Oyster Creek Nuclear Generating Station B. Boger ACRS (10)

Pest Office Eox 388 S. Norris Gray File Forked River, New Jersey 08731

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON ATHS REVIEW -

OYSTER CREEK NUCLEAR GEhERATING STATION (TAC NO. 66126)

The staff has reviewed the information provided by GPU Nuclear Corporation in letters dated Septen.ber 3, and December 30, 1987 concerning implementation of the ATNS rule requirements at the Oyster Creek Nuclear Generating Station.

Based on our review of this inforration, we find that additicnal infortation is required. The information r.eeded by the staff to conplete the evaluation is defir.ed in the enclosure. You are requested to respond to this request for additional infortation by February 10, 1988 in order to r.+et the scheduled con.pletion date.

The reporting ar.d/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, CMB clearance is not required under P.L.97-511.

Sincerely, W WW W Alexander W. Drecerick, Project Manager Project Directorate I-4 Divisicn of Reactor Projects I/II Division of Nuclear Reactor Regulatten

Enclosure:

As stated cc w/ enclosure:

See next page l

l l

l ck:bd z 01//7/P8 0 A /88 01/ 88 8801260520 880119 PDR ADOCK 05000219 P PDR 1

I n

l Mr. P. B. Fiedler Oyster Creek Nuclear Oyster Creek Nuclear Generating Station Generating Statien

~

" CC ' Resident Inspector l Ernest L. Blake, Jr.

Shaw, Pittman, Potts and Trowbridge e/o U.S. NRC 2300 N Street, NW Post Office Box 445 Washington, D.C. 20037 Forked River, New Jersey 08731 J.B. Libeman, Esquire Comissioner

( New Jersey Department of Energy l

Bishop, Libeman, Cook, et al .

1155 Avenue of the Americas 101 Comerce Street New York, New York 10036 Newark, New Jersey 07102 Mr. David M. Scott, Acting Chief Regional Administrator, Region I Bureau of Nuclear Engineering U.S. Nuclear Regulatory Comission Department of Environmental Protection 631 Park Avenue .

CN 411 - '

King of Prussia, Pennsy1Yania 19406 Trenton, New Jersey 08625 l

BWR Licensing Manager

, SPU Nuclear Corporation b 1 Upper Pond Road

r. Parsippany, New Jersey 07054 Deputy Attorney General State of New Jr;rsey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor -

Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 Licensing Manager Oyster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg. '

P. 0. Box 388 Forked River, New Jersey 08731

ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION ON ATWS REVIEW RELATED TO ALTERNATE ROD INJECTION (ARI) AND RECIRCULATION PUMP TRIP (RPT) SYSTEMS OYSTER CREEK NUCLEAR GENERATING STATION Provide the f ollowing design inf ormation as supporting documentation of your method of compliance with 10 CFR 50.62

1. Please identify, by number in the NEDE-31096-P Appendix A checklist, any items which the station will not be in full conf ormance with the ARI SER.

2. Provide the electrical functional i"agrams f or the ARI and RPT systems from the sensors to the final actuated devices.

2.1 Describe the manual initiation capabilities and the protection against inadvertent operation.

2.2 Verify that no manual bypass of the RPT system is available.

2.3 Identify if there will be positive position indication for the ARI valves and the location of this indication.

3. Provide the electrical one-line diagram to demonstrate the electrical independence between the ARI system and the Reactor Trip System (RTS), and describe the

! capability to perform the ARI function during the loss l -of-offsite power event.

3.1 Verify that the Reactor Recirculation Pump motor l generator drive motor breakers have trip coils which I are quallfled. Verify both trip coils are independent of the plant safety systems. Identify the criteria applied to the design of these trip coils.

3.2 Identify the separation criteria that is applied between the RE02 and RE0S instrument loop signals which are located in the Foxboro cabinets. What separation criteria will be applied to the redundant ECCS channels l

and redundant RTS channels identified in item 0 of your submit tal letter dated Sept 3,1987. Describe what is i meant by the terms "adequate air space separation" and l "a physical barrier (fire wrap) if necessary" in item 6 l of your submittal. Identify the availability for staff review the analysis for all potential failure modes (assurance that no failure will affect the safety functions of both ARI and RPS) for the common power supply to sensors RE02 and RE05 and their instrument channels. Verify that item (f) of Appendix B t o the SER of NEDE-31096-A has been considered and this information will be available for staff review.

_*2 l 3.3 Verify that the power source for the ARI control power, which is non-Class 1E, will be available af ter the s loss of off-site power. Identify the ultimate source of power for the loss of off-site power condition.

4. Describe the system design which permits the test / calibration and maintenance of the system logic while the plant is in power operation.

5. The ARI actuation setpoints have been indicated as not challenging the RPS scram settings; identify the settings and levels to be used for both RpS and ARI.

i 1

1

. _