ML20211A676
| ML20211A676 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/10/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20211A671 | List: |
| References | |
| NUDOCS 9709240328 | |
| Download: ML20211A676 (6) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMIS810N 3
WASHINGTON, D.C. seseHeet Sg.....
j SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0. 205 LICENSE N05. DPR-66 l
DUQUESNE LIGHT COMPANY OHIO EDISDN COMPANY PENNSYLVANIA POWER COMPANY l
BEAVER VALLEY POWER STATION. UNIT No.1 DOCKET NO. 50-334 l
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_1.0 BT8000CTION By letter dated March 10,hanges to the Beaver Valley Power Station, Unit No.
1997, the Duquesne Light Company (the licensee) submitted a request for c 1, fBVPS-1) Technical Specifications (TSs). The requested changes would noddfy the TSs by reducing the reactor coolant system (RCS) specific activity limits in accordance with the Generic Letter (GL) g5-05 l oltage-Based Repair Corrosion. Cracking.ghouseSteamGeneratorTubesbyOutsldeDiamete Criteria for Westin Y The definition of DOSE EQUIVALENT I-131 would be replaced with the Improved Standard TS definition wording in the first sentence and an equation would be added based on dose conversion factors a
derived from the International Commission on Radiation Protection (ICRP ICRP-30. TS 3.4.8, Specific Activity, would be revised by reducing the EQUIVALENT I-131 limit from 1.0 #Ci/ gram to 0.35 pCi/ gram for the 48-hour limit and from 60 #Ci/ gram to 21 pC1/ gram for the maximum instantaneous limit.
Item 4.a in TS Table 4.4-12, Primary Coolant Specific Activity Sample ar.d Analysis Program, TS Figure 3.4-1, and the Bases for TS 3/4.4.8 would also be 4
modified to reflect the reduced DOSE EQUIVALENT I-131 limit.
2.0 EVALUATION The licensee performed an assessment of the radiological dose consequences of i
a main steam line break accident in support of its amendment request to reduce the RCS specific activity limits from 1.0 #C1/ gram to 0.35 pCi/ gram for the
'48-hour limit and from 60 #C1/ gram to 21 pC1/ gram for the maximum instantaneous limit (in accordance with Generic Letter g5-05.
Prior to this beendment request, BVPS-1 had been approved to operate based)upon a 4.5 gpa primary to secondary leak initiated by an accident-in the faulted steam generator and-.the TS allowable value for primary to recondary leakage from each intact steam generator of 150 gpd per steam generator. As part of this amendment request, the licensee is proposing to change the faulted steam generator leakage from 4.5 gpa to 11.75 gpe. The licensee'is also proposing to change the allowable activity levels of DOSE EQUIVALENT I-131 in the primary coolant from 1.0 pC1/ gram to 0.35 pCi/ gram for the 48-hour limit and from 60 #Ci/ gram to 21 pC1/ gram for the maximum instantaneous limit.
The c
9709240329 970910 PDR ADOCK 05000334 P
PDR 1
licensee found the radiological dose consequences acce) table, assumi allowable activity level of DOSE EQUIVALENT I-131 in t,1e secondary coo 0.1 #C1/ pam.
The NRC staff has independently calculated the doses resulting from a mai steam line break accident using the methodology associated with SRP 15 Appendix A.
The staff performed two separate assessments.
a pre-existing iodine spike activity level of 21 pC1/ gram of DOSE EQUIVALENTO l-131 and the other was based u)on an accident initiated iodine spike.
the accident initiated spike, t,1e staff assumed that the prtnary coolant For activity level was 0.35 pCl/ gram of DOSE EQUIVALENT l-131.
initiated an increase in the release rate of iodine from the fuel by a factor The accident of 500 over the release rate to maintain an activity level of 0.35 pC1/ gram o DOSE EQUIVALENT l-131 in primary coolant. For these two cases, the staff calculated doses for individuals located at the Exclusion Area Boundary and at the Low-Population Zone (LPZ). The control room operator's thyro d
dose was also calcJlated.
assessment are presented in Table 1.The parameters which were utilized in the staff's presented in Table 2.
The doses calculated by the staff are The staff's calculations showed that the thyroid doses for the EA8 and LPZ would be less than the guidelines established by Standard Review Plan (S 15.1.5. Appendix A of NUREG-0800 The control room operator thyroid dose would be less than the guidelines of SRP 6.4 of NUREG-0800.
staff concluded that, based upon an acce)tance criterion of 300 rem thyroid at Therefore, the the EAB and LPZ for the pre-existing spi (e case and an acceptance criterion of 30 rem thyroid dose for the accident initiated spike case and for the control room operator dose assessments, a leak rate of 11.75 gpm is an acceptable limit for the maxin.um primary to secondary leakage initiated in the faulted steam cenerator by the main steam line break accident.
3.0
SUMMARY
The acceptance criteria guide' lines of SRP 15.1.5, A>pendix A are 300 rem thyroid at the EAB and LPZ for the pre-existing spi ce case and 30 rem thyroid for accident initiated spike case and for the control room operator dose NRC staff calculated doses for the proposed TS and B The
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. TABLE 1 INPUT PARAMETERS FOR BVPS-1 EVALUATION 0F MAIN STEAMLINE BREAK ACCIDENT 1.
Primary Coolant Concentration of 21 pCi/ gram of DOSE EQUIVALENT I-131 Pre-existino Soike Value (uci/aram) 1-131 =
16.23 1-132 -
5.66 1-133 -
26.09 I-134 -
3.50 1-135 =
13.55 2.
Volume of Primary Coolant and Secondary Coolant.
3 9,387 Primary Coolant Volume (ft )(*F Primary Coolant Temperature 577.0 3})
3,788 Secondary Coolant Steam Volume Secondary Coolant Liquid Volume t
2,080 Secondary Coolant Steam Temperature ('F) 'F) 516.8 Secondary Coolant Feedwater Temperature (
436.9 3.
TS Limits for DOSE EQUIVALENT I-131 in the Primary and Secondary Coolant.
Maximum Instantaneous DOSE EQUIVALENT l-131 Concentration (pC1/ gram) 21 Primary Coolant DOSE EQUIVALENT l-131 Concentration (pCi/ gram) 0.35 Secondary Coolant DOSE EQUIVALENT I-131 Concentration (pCi/ gram) 0.1 4.
TS Value for the Primary to Secondary Leak Rate.
Primary to secondary leak rate, maximum any SG (gpd) 150 Primary to secondary leak rate, total all SGs (gpd) 450 5.
Maximum Primary to Secondary leak Rate to the Faulted and Intact SGs.
Faulted SG (gpm) 11.75 Intact SGs (gpa/SG) 0.1 l
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4.
l o
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lodine Partition factor i
Faulted SG 1.0 Intact SG 0.01 7.
Steam Released to the Environment Faulted SG (0 - 30 minutes) 150,000 lbs Intact SGs (0 - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) 375.000 lbs Intact SGs (2 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />).
705.393 lbs
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8.
Letdown Flow Rate 60 gpm j
9.
Release Rate for 0.35 yC1/ gram of DOSE E0VIVALENT I-131 Release Rate (C1/hr) 500X Release Rate (C1/hr) i 1-131 2.79 1395
=
I-132 = 6.22 3110 1-133 6.87 3435 I-134 9.16 4580 1-135 - 6.64 3319
- 10. Atmospheric Dispersion Factors 3
sec/m EAB (0-2 hours) 1.30 x 103 LPZ (0 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) 1.30 x 10' Control Room (0 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) 2.42 x 10'3 11, Control Room Parameters 1
Filter Efficiency (*)
Volume (ft})
Air inta e filter 95 5
1.73x10 Makeup flow (cfm) 690 Recirculation Flow (cfm) 0-Unfiltered Inleakage (cfm) 10 Occupancy Factors 0 1 day 1.0 1-4: days:
0.6 4430 days 0.4 l
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. i Table 2 - THYR 0!D D0SES FROM BVPS-1 MAIN STEAM LINE BREAK ACCIDENT i
DOSE LOCATION.
Pre-Existing spike.
Accident-Initiated Spike **
(ree)-
(ren)
EAB 39.9*
20.9 LPZ 14.5*
22.7 Control Room **
28.6 27.2 Acceptance Criterior. - 300 rem thyroid
- Acceptance Criterion = 30 rem thyroid
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Pennsylvania State official was notiftai of the proposed issuance of the amendment.
The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has 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 Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (62 FR 24985). Accordingly, the amendment meets the eli ibility 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 eny ronmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded based on the considerations discussed above, that:
there is reasonable assurance that the health and safety of the public w(1)l not be endangered by operation in the proposed manner, (2) such il activities will be conducted in compliance with the 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.
Principal Contributor:
C. Hinson Date: September 10, 1997 9
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