ML20214G032
| ML20214G032 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/14/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214F994 | List: |
| References | |
| NUDOCS 8611250529 | |
| Download: ML20214G032 (3) | |
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UNITED STATES 8"
NUCLEAR REGULATORY COMMISSION
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i SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDNENT N0.104TO FACILITY OPERATING LICENSE NO. DPR-51 l
ARKANSAS POWER AND LIGHT COMPANY ARKANSAS NUCLEAR ONE, UNIT NO. 1 i
DOCKET NO. 50-313 INTRODUCTION By letters dated July)18 and 31,1986, the Arkansas Power and Light Company (AP&Lorthelicensee requested amendments to the Technical Specifications (TSs) appeaded to Facility Operating License No. DPR-51 for Arkansas Nuclear One, Unit No. 1 (ANO-1). By letter dated October 17, 1986, the licensee
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provided clarifying information for the submittal dated July 31, 1986. The proposed amendments would (1) increase the setpoint for reactor trip on high pressure from 2300 psig to 2355 psig, (2) increase the anticipatory reactor trip (ART) on turbine trip anning threshold from 20% of full power to 45% of full power, and (3) correct several editorial errors. Specifically, the proposed amendments would change TS Figure 2.3-1, Table 2.3-1, 2.2 Bases, 2.3 Bases C, 3.5.1 Bases, TS 3.5.1.9.1, 3.5.1.9.2 and Table 3.5.1-1.
EVALUATION
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AN0-l's TSs currently have a value of 2300 psig for the high pressure trip setpoint, and a value of 20% of full power for the ART anning threshold.
These values were based on changes required by the NRC staff (Ref. 1),
5 subsequent to the accident at Three Mile Island Unit 2, to reduce i
challenges to and opening of the power operated relief valve (PORV).
In April 1986, we completed our review of the following two Babcock & Wilcox (B&W) topical reports related to AP&L's request: (1) " Justification for Raising Setpoint For Reactor Trip on High Presture," BAW-1890 September 1985 (Ref. 2); and (2) " Basis For Raising Arming Threshold For Anticipatory Reactor Trip on Turbine Trip," BAW-1893, October 1985 (Ref. 3). The results of i
i our review of the topical reports are contained in two Safety Evaluation l
Reports (Refs. 4 and 5).
In those Safety Evaluation Reports, we:
(1) reviewed the basis for the proposed changes; (2) reviewed B&W's method of analysis of 1
the effect of the proposed high pressure trip setpoint on PORV openings; (3) compared the results of Monte Carlo simulation for PORY openings with the NRC requirements contained 'in NUREG-0737 (Ref. 6); and (4) reviewed the results of B&W's analysis of the arming threshold for ART. The NRC requirements include:
(1) the PORV will open in less than 5% of all anticipated overpressure transients i
(Ref. 6 Item II.K 3.7); and (2) the probability of a small-break loss of j
coolant accident caused by a stuck-open PORV will be less than 0.001 per reactor-year (Ref. 6. Item II.K.3.2).
In the Safety Evaluation Reports, we concluded on a i
l generic basis that the proposed changes met the NRC requirements, and should benefit plants by potentially reducing the reactor trip frequency.
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- In regard to ANO-1, the licensee states in their supplemental response dated October 17, 1986, that the accidents analyzed in Chapter 14 of the Final Safety Analysis Report (FSAR) were based on the high pressure trip setpoint of 2355 psig (not the current setpoint of 2300 psig) and no credit for ART. The increase in the high pressure trip setpoint and the increase in arming threshold for ART will not increase the frequency of challenges to the main i
steam safety velves as compared to the initial plant design. Consequently, the accidents analyzed in the FSAR for ANO-1 bound the proposed TS changes.
We have reviewed the licensee's submittals and on the basis of the above, have determined that the proposed changes meet the applicable regulatory guidance and requirements and are, therefore, acceptable.
W6 have also reviewed AP&L's proposed changes to TS 3.5.1.9.1 and 3.5.1.9.2.
The purpose of these changes is to correct several editorial errors. The changes are appropriate and acceptable.
ENVIRONMENTAL CONSIDERATION This amendment involves changes in the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20.
We have determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Conunission has previously issued a proposed finding that this amendment involves no s
significant hazards consideration and there has been no public connent on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in ccnnection with the issuance of this amendment.
CONCLUSION 1
We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Comission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated: November 14, 1986 Principal Contributors:
E. Branagan G. Vissing 1
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REFERENCES i
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" Nuclear Incident at Three Mile Island - Supplement," IE Bulletin 79-058, April 21, 1979.
2.
" Justification for Raising Setpoint For Reactor Trip on High Pressure,"
BAW-1890, September 1985.
3.
" Basis For Raising Arming Threshold For Anticipatory Reactor Trip on Turbine Trip," BAW-1893, October 1985.
4.
Letter from D. M. Crutchfield, NRC to J. H. Taylor, Babcock and Wilcox Company, April 22, 1986.
5.
Letter from D. M. Crutchfield, NRC to J. H. Taylor, Babcock and Wilcox Company, April 25, 1986.
6.
" Clarification of TMI Action Plan Requirements," NUREG-0737, November 1980.
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