1CAN068809, Application for Amend to License DPR-51,changing Tech Specs Re Reactor Trip Breaker Design Mods,Per Generic Ltrs 83-28 & 85-10.Fee Paid

Application for Amend to License DPR-51,changing Tech Specs Re Reactor Trip Breaker Design Mods,Per Generic Ltrs 83-28 & 85-10.Fee Paid

ML20150A965
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/30/1988
From:	Tison Campbell ARKANSAS POWER & LIGHT CO.
To:	Calvo J NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation
Shared Package
ML20150A968	List: 1CAN068809, Application for Amend to License DPR-51,changing Tech Specs Re Reactor Trip Breaker Design Mods,Per Generic Ltrs 83-28 & 85-10.Fee Paid ML20150A981
References
1CAN068809, 1CAN68809, GL-83-28, GL-85-10, NUDOCS 8807110190
Download: ML20150A965 (7)

Text

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ARKANSAS POWER & LIGHT COMPANY CAPIT0L TOWER BUILDING /P. O. 80X 551/LITTLE ROCK. ARKANSAS 72203/(501) 377 3525 T. GENE CAMPBELL June 30, 1988 vice President - Nuclear ICAN068809 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Mr. Jose A. Calvo, Director Project Directorate IV Division of Reactor Projects III, IV, V and Special Projects

SUBJECT:

Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Technical Specification Change Request -

Control Rod Drive Trip Breaker

Dear Mr. Calvo:

The Arkansas Power and Light Company hereby rec, Jests an amendment to its Operating License DPR-51 for Arkansas Nuclear One - Unit 1 with the enclosed submittal of proposed changes to the Technical Specifications.

The proposed changes are made at the request of the U.S. Nuclear Regulatory Commission related to the reactor trip breaker design modifications (Generic Letters 83-28 and 85-10). The additional guidance contained in the request for additional information (RAI) from Mr. John F. Stolz (NRC) to Mr. T. Gene Campbell (AP&L), dated August 25, 1986 (1CNA088604), has been uti ized in preparing this submittal.

In accordance with 10CFR50.91(a)(1), AP&L has evaluated the proposed changes using the criteria in 10CFR50.92(c) and has determined that said changes involve no significant hazards considerations. The bases for this determination are attached. Also, in accordance with 10CFR50.91(b)(1) a copy of this amendment request with attachrnents has been sent to Ms. Greta Dicus, Director, Division of Radiation Control and Emergency Management, Arkansas Department of Health. j pO4' flf

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Mr. Jose A. Calvo June 30, 1988 A check in the amount of $150 is included herewith as an application fee in accordance with 10CFR170.12(c).

Very truly yours,

$ & M T. Gene Campbell TGC:lg Attachmentr cc: Ms. Greta Dicus, Director Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street Little Rock, AR 72205 i

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I, T. Gene Campbell, being duly sworn, subscribe to and say that I am Vice President, Nuclear for Arkansas Power & Light Company; that I have full authority to execute this oath;-that I have read the document numbered ICAN068809 and k1ow the contents thereof; and that to the-best of cy knowledge, information and belief the statements in it are true.

& f M T. Gene Campbe SUBSCRIBED AND SWORN T0 before me, a Notary Public in and for the County and State above named, this 3s* day of ,

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4 PROPOSED TECHNICAL SPECIFICATION CHANGE IN THE MATTER OF AMENDING LICENSE NUMBER OPR-51 ARKANSAS POWER AND LIGHT COMPANY ARKANSAS NUCLEAR ONE - UNIT 1 DOCKET NUMBER 50-313 t

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PROPOSED CHANGE A. Table 3.5.1-1 (Page 44a) is revised to add Functional Unit 13 (Electronic (SCR) Trip relay). Note 22 (Page 45g) is also added to apply if one or more of the Electronic (SCR) Trip relays in a channel is inoperable.

B. Table 3.5.1-1 (Page 44a) is revised to add Functional Unit 14 (Control Rod Drive Trip Breakers). Notes 23 and 24 (Page 45g) are added to apply if one of the channels is inoperable or if only one of the diverse trip features (undervoltage or shunt trip attachment) of the control rod drive trip breaker is inoperable, respectively.

C. Table 4.1-1 (Page 69) is revised to modify the "Remarks" column for the monthly surveillance test. This change requires that the test independently verify the operability of the undervoltage and shunt trip attachments.

D. Table 4.1-1 (Page 72d) is revised to add Channel Description 61 (Electronic (SCR) Trip relay) and require monthly channel functional testing.

DISCUSSION Item 4.3 of Generic Letter 83-23, "Required Actions based on Generic Implications of Salem ATWS Events," established the requirement for the automatic actuation of the shunt trip attachment for B&W plants. Item 4.4 of Generic Letter 83-23 specified that the appropriate surveillance and test requirements of the Technical Specifications be revised to include testing of the silicon controlled rectifiers (SCR) used to interrupt power to control rods.

The NRC issued a Safety Evaluation Report finding the design acceptable for the ANO-1 automatic actuation of the reactor trip breakers (RTB) shunt trip attachments, in correspondence from Mr. John F. Stolz (NRC) to Mr. John M.

Griffin (AP&L), dated January 24, 1984 (1CNA018402). Arkansas Power and Light implemented the shunt trip modifications associated with the reactor trip breaker (DCP83-1044A) during the ANO-1 mid-cycle outage in March 1984.

The shunt trip is operable from an automatic reactor protection signal and tested on a monthly basis (1CAN058405).

The NRC issued a Safety Evaluation Report (1CNA108605) finding the imprevements in the ANO-1 maintenance and test procedures relevant to the j SCRs acceptable as a result of AP&L's response to Item 4.4 of Generic

! Letter 83-23. Testing of the SCR circuit networks has been conducted on a

! monthly basis using the safety-related Reactor Protection System (RPS)

Monthly 'hannel Test procedures. By expanding the scope of this safety-related testing, the procedures were revised to also include degating of the SCRs. The electronic trip feature in the SCR circuit network is the I

method by which SCRs are degated. In respor to Generic Letter 85-10, AP&L

, proposes Technical Specification ch~ is th- und include the electronic l trip channels associated with the G uits in the maintenance and test requirements section of the AN0-1 lechnice' Spe,ifications and the Instrumentation Limiting Conditions for Operation (LCO).

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4 Generic Letter 85-10 found that proposed Technical Specifications should be submitted tr reflect appropriate LC0 and surveillance requirements consisting f independent testing of the shunt and undervoltage trip attachments, as_a result of the B&W generic design modifications. In response to Generic Letter 85-10, the BWOG in correspondence (ICAN198507) from Mr. J. Ted Enos, Chairman (BWOG/ATWS) to Mr. Hugh L. Thompson, Jr.

(NRC) dated October.9, 1985, requested a substitute LC0 action statement for the_0conee class design. In reply, the NRC provided an accaptable, revised action statement in correspondence from Mr. Frank Miraglia (NRC) to Mr. J.

Ted Enos (BWOG/ATWS), dated December 6, 1985. As a result of these pending issues being resolved, AP&L proposes changes to the AN0-1 nonstandard t Technical Specifications consistent with the request for additional information (RAI) from Mr. John F. Stolz (NRC) to Mr. T. Gene Campbell (AP&L) dated August 25, 1986 (1CNA088604).

DETERMINATION OF SIGNIFICANT HAZARDS Arkansas Power and Light Company has performed an analysis of the proposed change in accordance with 10CFR90.91(a)(1) regarding no significant hazards consideration, using the standards in 10CFR90.92(c).

A discussion of those standards as they relate to this amendment request follows:

Criterion 1 - Does not involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed change would not increase the proSability or consequences of any accident previously evaluated since the addition of limiting conditions for operation and surveillance requirements are made to conform with the Commission's generic requirements for reducing a potential ATWS event.

Criterion 2 - Does not create the possibility of a new or different kind of accident from any previously evaluated.

The proposed change would not create the possibility of a new or different kind of accident from any previously analyzed since the scope of the change does not establish a potential new accident precursor.

Criterion 3 - Does not involve a significant reduction in a margin of safety.

The proposed changes would not involve a significi.c reduction in the margin

( of safety, rather, it constitutes additional controls and surveillance requirements not presently ircluded in the Technical Specifications.

The Commission has provided guidance concerning the application of these standards by providing examples. The proposed amendment is most closely encompassed by Example (ii): a change that constitutes an additional limitation, restriction, or control not presently included in the Technical Specifications.

Therefore, based on the reasoning presented above and the previous discussion of the amendment request, AP&L has determined that the requested changes do not involve a significant hazards consideration.

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PROPOSED TECHNICAL SPECIFICATION CHANGES l

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