View source for 1CAN088803, Application for Amend to License DPR-51,revising Variable Low Pressure Trip Setpoint for Reactor Protection Sys.Fee Paid

{{Adams
| number = ML20153F622
| issue date = 08/31/1988
| title = Application for Amend to License DPR-51,revising Variable Low Pressure Trip Setpoint for Reactor Protection Sys.Fee Paid
| author name = Campbell T
| author affiliation = ARKANSAS POWER &amp; LIGHT CO.
| addressee name = Calvo J
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM), NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000313
| license number = 
| contact person = 
| document report number = 1CAN088803, 1CAN88803, NUDOCS 8809070376
| package number = ML20153F626
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS &amp; PERMITS
| page count = 8
| project = 
| stage = Request
}}

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ARKANSAS POWER & LIGHT COMPANY CAPITOL TOWER BUILDING /P. O. BOX 551/LITTLE ROCK, ARKANSAS 72203/(501) 377 3525 T. GENE CAMPBELL                                                 August 31, 1988 Vice President . Nuclear ICAN088803 U. S. Nuclear Regulatory Conmission Document Control Desk Mail Station P1-137 Washington, D.C.         20555 Attn: Mr. Jose A. Calvo, Director Project Directorate IV l                        Division of Reactor Projects i
III, IV, Y and Special Projects

==SUBJECT:==
Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Reactor Protection System Trip Setpoint Technical Specification Change Request

==Dear Mr. Calvo:==

Attached for your review and approval are proposed Technical Specification changes revising the Variable Low Pressure Trip Setpoint of the ANO-1 Reactor Protection System (RPS). These Technical Specification changes are requested for support of Cycle 9 operation.
Our letter, dated July 20,1988(ICAN078803), submitted to you the Cycle 9 Reload Report and associated Technical Specification changes. AP&L has subsequentiv determined that the reload report analyses also support a change to the RPS Variable Low Pressure Trip Setpoint. The proposed chcnge will provide additional operating margin which will enhance the availability of ANO-1 by potentially reducing unnecessary reactor trips.
The revised RPS trip setpoint is based on the analyses performed for the Cycle 9 Reload Report, and the attached Technical Specification changes are consistent with those submitted with the reload report. AP&L consequently, suggests that the joint review of this change with the reload report and issuance of a single amendment would be the most effective use of NRC resources.
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August 31, 1988 AP&L har evaluated the proposed changes in accordance with 10CFR50.91(a)(3) using the criteria in 10CFR50.92(c) and has determined that these changes involve no significant hazards consideration. The bases for these determinations are included in the enclosed submittal. The circur. stances of this proposed amendment is not exigent or emergency. However, we do request your prompt review as our current projections are for an ANO-1 Cycle 9 startup on approximately October 30, 1988.
A copy of this amendment request and enclosure has been sent to Ms. Greta Dicus, Director, Division of Radiation Control and Emergency Management, Arkansas State Department of Health in accordance with 10CFR50.91(b)(1).
A check in the amount of $150.00 is included herewith as an application fee in accordance with 10CFR170.12(c).
Very truly yours, d 4?$v-S               v T. Gene Campbell TGC/1g Attachments / Enclosures cc:   Ms. Greta Dicus, Director Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street Little Rock, Arkansas 72201

STATE OF ARKANSAS                                )
                                                                      )          SS COUNTY OF PULASKI                                )
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 ICAN088803 and know the contents thereof; and that to the best of my knowledge, information and belief the statements in it are true.
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T. Gene Campbell SUBSCRIBED AND SNORN T0 before me, a Notary Public in and for the County and State above named, this 8/                                   day of _       /JI-          _,
1988.
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Notary Public My Commission Expires:
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9 ENCLOSURE PROPOSED TECHNICAL SPECIFICATION AND RESPECTIVE SAFETY ANALYSES IN THE MATTER OF AMENDING LICENSE NO. DPR-51 ARKANSAS POWER & LIGHT COMPANY ARKANSAS NUCLEAR ONE, UNIT 1 DOCKET NO. 50-313

PROPOSED CHANGES The proposed amendment would change the Reactor Protection System (RPS)
Variable Low Pressure Trip Setpoint in ANO-1 Technical Specification 2.3.
Revised copies of the affected pages are included in this attachment.
The revised setpoint appears in Bases Section C, in Figure 2.3-1, and in Table 2.3-1. The third paragraph of Bases Section C has also been modified to present a more meaningful description of how the calibration and instrument errors associated with the setpoint are accounted for in the Safety Analysis. The change indicates that the safety analyses are based on the Pressure / Temperature Safety Limit of Technical Specification 2.1.1 which is error adjusted to develop the RPS trip setpoint.
Page 13 of Technical Specifications was also modified by the changes proposed in the Cycle 9 Reload Report submittal. Those changes were also included on page 13 of this submittal. The attached page 13, therefore, supersedes the corresponding page of the earlier submittal. The other two attached pages were not affected by the earlier submittal.
DISCUSSION The RPS Variable Low Pressure Trip, in conjunction with the Low Pressure and High Temperature Trips, prevent reactor operation with the Reactor Coolant System pressure and temperature conditions outside the core protection safety limit of Technical Specific.cion 2.1.1.                    This core protection safety limit provides a conservative margin to the pressure / temperature conditions at which departure from nucleate boiling (DNB) would occur. The limit provides a 95% probability at a 95% confidence factor that DNB will not occur during steady-state operation, normal operational transients, and anticipated transients.
The core protection safety limit of Technical Specification 2.1.1 has been revised to reflect the cycle specific analyses for Cycle 9. This proposed change was submitted earlier with the reload report. At the time of the analyses, the current RPS Variable Low Pressure Trip Setpoint was demonstrated to be conservative and no detailed setpoint calculations were performed. When the potential benefits of making a corresponding change to the RPS trip setpoint were realized, the additional calculations were initiated.
The revised RPS setpoint was derived by error adjusting the core protection safety limit which was used in the safety analyses for the Cycle 9 Reload Report. Therefore, the revised RPS trip setpoint is consistent with the Cycle 9 Reload Report analyses and conclusions. Changing the setpoint has no negative impact on the safe operation of ANO-1 for Cycle 9.

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DETERMINATION OF SIGNIFICANT HAZARDS Arkansas Power & Light Company has performed an arilysis of the proposed change in accordance with 10CFR50.91(a)(1) regard.ng no significant hazards consideration using the standards in 10CFR50.92(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 Cycle 9 Reload Report presented the results of an evaluation of accidents addressed in the ANO-1 SAR. The evaluation demonstrated that changes in the fuel cycle design and the corresponding proposed Technical Specification changes do not involve a significant increase in the probability or consequcnces of an accident previously evaluated. Since the safety limit of Technical Specification 2.1.1 provides the assumed RCS pressure and temperature operating limits for the evaluation of applicable steady state and transient conditions, the change to the RPS Variable Low Pressure Trip Setpoint does not affect these evaluations. Consequently, this chango does not involve a significant increase in the probability or consequence of an accident previously evaluated.
Criterion 2 - Does h t Create the Possibility of a New or Different Kind of Ac:ident from any Accident Previously Evaluated The proposed change would not create the possibility of a new or different kind of accident from any previously analyzed. The change is to an RPS setpoint only and will result in no significant change to the operation of the unit. Similar changes in the RPS Variable Low Pressure Trip Setpoint, resulting in increased operating margin have been reviewed and accepted by the NRC for ather B&W units.
Criterion 3 - Doas Not Involve a Significant Reduction in a Margin of Safety The proposed change does not involve a significar t reduction in a margin of safety. The RFS Variable low Pressure Trip prevents operation at pressure / temperature conditions beyond '.h3 core protection safety limit of Technical Specification 2.1.1. This softty limit provides the margin of safety to DNB which is not affected by this proposed setpoint change.
The Commission has provided guidance concerning the application of these standards by providing examples. Since this setpoint change is typically associated with changes supporting a fual cycle change and the related analyses, the proposed amendment is most closely encompassed by Example (iii):   "A change resi! ting from a core reloading, if no fuel assemblies significantly t.lfferent from those found previously acceptable to the NRC for a previous core at the facility in question are involved. This assumes j      that no significant changes are made to the acceptance criteria for the Technical Specifications, that the analytical methods used to demonstrate 7

i conformance with the Technical Specifications and regulations are not significantly changed, and the NRC has previously found such methods acceptable.
Therefore, based on the reasoning presented above and the previous                                                                      I discussion of amendment request, AP&L has determined that the requested changes do not involve a significant hazards consideration.                                                                             ,
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