ML20235L436

Safety Evaluation Accepting Responses to Generic Ltr 83-28, Item 2.1 (Part 2), Vendor Interface Programs for Reactor Trip Sys Components

ML20235L436
Person / Time
Site:	Fort Calhoun
Issue date:	02/15/1989
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20235L429	List: ML20235L426 ML20235L436
References
GL-83-28, NUDOCS 8902270524
Download: ML20235L436 (2)

Text

. . - - _ - - - . _

a ps* * %9 4 g UMTED STATES E,*

O

• g,M v. ( l[c g

E NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

/

SAFETY EVALUATION BY THE_0FFICE OF MUCLEAR REACTOR REGULATION FORT CALHOUN STATION, UNIT 1 GENERIC LETTER 63-28, ITEM 2.1 (PART 2)

VENCCE INTERFACE PROGRAMS REACTOR TRIP SYSTEM C0f'PONENTS DOCKET NO. 50-285

1.0 INTRODUCTION

On Februery 25, 1983, bcth of the scran, circuit breakers et Ur.it 1 of the Salem i:cclear Poker Flant f ailed to open upon an automatic reactor trip signal from the reactor rrctectier u sten.. This incident was terminated tranually by the operatcr dcut 30 seconds tfter the initiation of the auton: etic trip signal.

The failure cf the circuit breakers was detero.inec to tc related te the sticling of the undcrsoltage trip attachment. Pricr to this incident, on

-February 2P,1983, at Unit I of the Selem Nuclear Power Plant, an auton.atic trip sigt.cl us generated haseo on ste.am generator low-low level during plant start-up. In this case, the reactor was tripped manually by the cperator almost coincidentally with the automatic trip.

Following these incider.ts, on February I6,1983, the NRC Executive Director for Opt.retions (ED0), directec the staff to investigate the report on the generic ir.plicctions cf thest. occurrences at Unit 1 of the Salcm Nuclear Power Plant.

The results of the staff's inquiry it.to the generic implications of these events are reported in t'UREG-1000, " Generic Implications of the ATWS Events at thc St!uilluclear Power Plant." As a result of this investigation, the Commission (NRC) requested (by Generic Letter 83-28 dated July 8, 1983) all licensees of operating reactors, applicants for an operatirg license, and holoers of construction permits to respond to generic issues raised by the analyses of these two ATWS events.

This report is an evaluation of the response submitted by Omaha Public Power District, the licensee for the Fort Calhoun Station Unit 1, for Item 2.1 (Part2)ofGenericLetter83-28. The actual documents reviewed, as part of this evaluation, are listed in the references et the end of this report.

Iten. 2.1 (Part 2) requires the licensee to confire that an interface has been established with the t'SSS vendor or with the vendors of ecch of the components of the Reactor Trip System which incluces:

c pericoic commuricttien between the licensee / applicant and the NSSS vendur or the vendors of each of the components of the Rcector Trip System, and o a system of positive feedback which confirms receipt by the licensee / applicant of trensmittels cf vendor technical information.

8902270524 890215 D PDR ADOCK 05000285 P PDC

% v 2.0 EVALUATION The licensee for Fort Calhoun Station Unit 1 provided responses to Generic Letter 83-28, item 2.1 (Part 2) in submittels dated November 4,1983, May 24, 1985 and September 1, 1987. The licensee stated that they have verified with the vendors of the reactor trip system that the information is the latest revision and applies to the components of the reactor trip system. The procedures used to perform maintenance and testing on those components have been reviewed to ensure they are current. In the third submittal the licensee stated that Fort Calhoun Station Administrative Standing Order G-62 was written to control vendor technical information which includes originally supplied vendor manuals and vendor supplied oddendums. The purpose of this procedure is to establish a continuing program to ensure and demonstrate that vendor technical information for the instElled RPS and other safety-relateo equipment is complete, current, accurate and controlled. The procedure details the steps to be iden to ensure proper receipt, evaluation, implementation and maintenance of vendor technical inforrration. As part of the establishment of the Vendor fianual Program, vendors have been contracted to update existing infortration. Also, the procedure will be reviewed and updated to reflect the need to perforr. periodic communication with venccrs of major components.

3.0 CONCLUSION

Based on our review of these responses, we find the licensee's stctements confirm that an acceptable vender interface program exists with the NSSS vendor for components that ere requireo for the successful performance cf the reactor trip function. This program neets the requirements of Item 2.1 (Part 2) of Generic Letter 83-28, and is, therefore, acceptable.

4.0 PEFERENCES

1. NRC Letter, D. G. Eisenhut to all Licensees of Operating Reactors, Applications for Operating Licenses, and Holders of Construction Permits,

" Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28)," July 8, 1983.

2. Letter, W. C. Jones, Omaha Public Power District to D. G. Eisenhut, November 4, 1983.

3. Letter, R. L. Andrews, Omaha Public Power District to J. R. Miller, NRC, May 24, 1985.

4. Letter, R. L. Andrews, Omaha Public Pcwer District to NRC, September 1987.

Principal Contributor: S. Rhow Dated: February 15, 1989

_______ .. ..