ML20206N500
| ML20206N500 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/12/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206N496 | List: |
| References | |
| NUDOCS 9905170244 | |
| Download: ML20206N500 (6) | |
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UNITED STATES y
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20066 4 001
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SAFETY EVALUAflON BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.m TO FACILITY OPERATING LICENSE NO. DPR-66
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DUQUESNE LIGHT COMPANY OHlO EDISON COMPANY PENNSYLVANIA POWER bOMPANY '
BEAVER VALLEY POWER STATION. UNIT NO.1 DOCKET NO. 50-334
1.0 INTRODUCTION
By letter dated January 17,1998, as supplemented by letters dated February 10,- 1998, November 9,1998, February 8,1999, and February 26,1999, the Duquesne Light Company (the licensee) submitted a request for changes to the Beaver Valley Power Station, Unit No.1 (BVPS-1) Updated Final Safety Analysis Report (UFSAR), Specifically, the requested changes to the BVPS-1 UFSAR reflect revisions to the control room radiological dose calculations for the Wasta Gas System Line Break (WGSLB) accident analysis. This revision is required in order to correct a mathematical error in the previous calculation. The February 10,1998, November 9,1998, February 8,1999, and February 26,1999, letters provided clarifying information that did not change the initial proposed no significant hazards consideration determination or expand the amendment request beyond the scope of the initial notice.
As a result of issues involving control room habitability, the licensee re-evaluated Beaver Valley Power Station, Unit Nos.1 and 2, control room dose calculations for Design Basis Accidents (DBAs) which credited isolation of the control room during the DBA. When analyses associated with the WGSLB were reviewed, an arithmetic error was discovered in the control room dose calculations for BVPS-1 which resulted in the associated values listed in the BVPS-1 UFSAR bemg incorrect.
The proposed action would authorize changes to the BVPS-1 UFSAR to reflect revision of the control room radiological dose calculations for the waste gas system line break analysis. The BVPS-1 UFSAR would be revised as follows: in Table 11.3-7, the reported Gamma (whole body) dose value would be revised from 0.0031 REM to less than 0.01 REM; the reported Beta dose value would be revised from 0.013 REM to less than 1.0 REM; and Table 14.2-8 would be revised to reflect the assump2as trist (1) the fraction of fuel with defects is one percent, and (2) the control room radiation monito,s will not initiate control room isolation, which were used in the reanalysis.
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H 4 ' 2.0 ' EVALUATION 2.1 Assessmentof RadiologicalConsequences The licensee performed an assessment of the radiological dose consequences of a WGSLB in
- support ofits request to modify the BVPS-1 UFSAR. The.NRC staff reviewed the licensee's UFSAR, amendment request, and letters associated with the proposed change. Using the
- input and assumptions given in these letters and the UFSAR, the NRC staff performed
- confirmatory calculations of the control room operators' whole body dose for the WGSLB. No assessment of offsite dose consequences was performed since the proposed change is the.
result of a correctum/ revision of the control room dose calculations for the WGSLB and does.
not impact offsite dose consequences. The parameters which were utilized in the Nuclear.
L Regulatory Commission (NRC) staff's assessment ar6 presented in the attached Tables 1'and
- 2. The radiological dose to the control room operators is given in Table 3.-
The results of the NRC staff's calculations described above were used to confirm the acceptability of the licensee's analysis methodology. Based on comparisons of results, the NRC staff finds the licensee's analysis to be acceptable.
2.2 Conclusion
- The NRC staff concludes, based upon the considerations above, that the proposed changes to the BVPS-1 UFSAR are acceptable. The NRC staff has determined that reasonable assurance exists, in the event of a postulated WGSLB, that the postulated control room.
operator doses would continue to be less than the criteria of 10 CFR Part 50, Appendix A, General Design Criteria 19.
3.0 STATE CONSULTATION
'In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
Pursuant to 10 CFR 51.21,51.32, and 51.35, an environmental assessment and finding of no significant impact have been prepared and published in the Federal Reaister on April 19,1999 (64 FR 19204). Accordingly, based upon the environmental assessment, the staff has determined that the issuance of this amendment will not have a significant effect on the quality of the human environment.
5.0 CONCLUSION
The Commission has 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, (2) such activities will be conducted in compliance with the
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' 4 Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Attachments: 1. Table 1, input Parameters for Beaver Valley Unit 1, Evaluation of Waste Gas System Line Break
- 2. Table 2, Source Term Parameters for Beaver Valley Unit 1, Evaluation of a Waste Gas System Line Break
- 3. Table 3, Calculated Dose for Beaver Valley Unit 1, Evaluation of Waste Gas System Line Break Principal Contributors: D. Collins W. M. Blumberg Date: Ny 12,1999
TABLE 1 INPUT PARAMETERS FOR BEAVER VALLEY UNIT 1 EVALUATION OF A WASTE GAS SYSTEM LINE BREAK Parameter Units Value Letdown flow rate gallons per min.
120 Time of release from broken line hour 1
Temperature of the degasifier degrees F 219 Control Room (CR) normal intake flow rate (pre-actuation) ft / min.
500 CR pressurization rate (bottles) ft'/ min.
O' CR unfiltered inleakage ft / min.
10 CR pressurization rate (Fans) ft / min.
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CR occupancy factor (0-24 hr) 1 CR occupancy factor (24 - 96 hr) 0.6 CR occupancy factor (96 - 720 hr) 0.4 CR 0 - 8 hr atmospheric dispersion factor sec/m 4.3E-03 I
CR volume ft 1.73E+05 l
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! No control room emergency ventilation is assumed.
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i TABLE 2 SOURCE TERM PARAMETERS FOR BEAVER VALLEY UNIT 1 EVALUATION OF A WASTE GAS SYSTEM LINE BREAK Nuclide Line Release Charcoal Delay Bed (Ci)
(Ci)
Kr-85m 52 3.0 Kr-85 290 106 Kr-87 33 3.8E-4 Kr-88 85 8.3E-1 Xe-133m 82 15 Xe-133 710 66 Xe-135m 30 0
Xe-135 85 18 Xe-138 18 0
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Attachnmt 2
l TABLE 3 CALCULATED DOSE FOR BEAVER VALLEY UNIT 1 WASTE GAS SYSTEM LINE BREAK Control Room Dose (Rem)
I Whole Body
- 0.005 10 CFR Part 50 Appendix A, GDC 19 Acceptance Criterion = 5 rem whole body J
l Attactrent 3