ML20203B215
| ML20203B215 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/09/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20203B201 | List: |
| References | |
| NUDOCS 9802240228 | |
| Download: ML20203B215 (4) | |
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NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 3066H001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N05.211 CD 89 TO FACILITY OPERATING LICENSE NOS. DPR-66 AND NPF-73 DUQUESNE LIGHT COMPAN1 OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY BEAVER VALLEY POWER STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 5.0-334 AND 50-412
1.0 INTRODUCTION
By letters dated November 6, 1995, and March 11, 1996, as supplemented June 5, 1997, the Nguesne Light Company (the licensee) submitted a request for changes to the Beaver Valley Power Station, Unit Nos. I and 2 (BVPS-1 and BVPS-2), Technical Specifications (TSs). The requested changes would change:
1.
The reporting period of Action 36 of TS Table 3.3-6 of BVPS-1 and BVPS-2 3
from semi-annually to a, qually, for consistency with the current reporting interval for t.!fluents, 2.
The high alarm high setpoints of the BVPS-1 in-containment high range arearadjationmonitors(RM-RM-219A&B),from30R/hrto 1.5 x 10 R/hr, 3.
The high alarm high setpoints for the BVPS-2 in-containment high range area radiation monitors (2RM-RQ-206 and 207) from 3,290 to 20,000 R/hr, 4.
The alarm setpoints of the BVPS-1 noble gas effluent monitors (RM-VS-109 from 275 to 669 cpm; RM-VS-110 from 350 to 798 cpe; and RM-GW-109 from 18,000 to 183,000 cpm),and 5.
The alarm etpoints of the BVPS-2 containment purge exhaust monitors (2HVR-RQ 104 A & B) fram 3 times background to 0.00101 pC1/cc.
6.
Make minor editorial changes on TS Table 3.3-6 (both units),
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' The June 5,1997, letter provided clarifying information that did nct change the initial proposed no significant nazards consideration determination or expand the amendment request beyond the scope of the December 20, 1995, and April 10, 1996, Federal Reaister notices.
2.0 EVALUATION Item 1, the change in reporting frequency of Action 36 of TS Table 3.3-6 units) from semi-annually to annually would make this reporting frequency (both consistent with the reporting requirements proviously approved in License Amendment Nos. 188 (BVPS-1) and 70 (BVPS-2) but inadvertently not made in Action 36 during the processing of those amenoments. The proposed reporting frequency (annually) is consistent with current NRC requirements.
Therefore, this change is acceptable.
Items 2 and 3, the changes in the high alarm high setpoints for the in-containment area radiation monitors, are intended to make the high alarm high setpoints correspond to the Emergency Action Level (EAL) for a General Emergency based on radioactivity released into containment.
The current "VPS-1 and BVPS-2 EALs were approved by the NRC in At. gust 1994.
The NRC staff review confirms that the proposed setpoints are appropriate for the recommended 20-percent fuel damage which corresponds to a General Emergency EAL. Tine NRC staff notes that although these monitors are safety-related, they do not actuate any safety function nor interface with any other safety system. Therefore, the setpoint changes will not affect actual releases if an accident were to occur, nor will the changes impact releases during normal operations or occupational radiation exposure. These changes, therefore, are acceptable.
Item 4, the changes in the high alarm setpoints for three noble gas effluent monitors (actually three noble gas monitor components of the SPING system) are intended to make the alarm setpoints consistent with the current EAls. These high-range effluent monitors were required as a result of the TMI Lessons Learned effort [21 but no alarm setpoint was stipulated. The setpoint was established to call attention to releases to the environment that correspond to a General Emergency. No safety systems are actuated by these alarms.
In 1992, the NRC provided new guidance for EALs [1]. A principal change was the use of annual average meteorological dispersion for the dose calculations.
In August 1994, the BVPS-1 and BVPS-2 EALs were revised to meet the NRC guidance 1
and were approved by the NRC. Because the revised EALs have been approved and the proposed changes are consistent with the new EAls, the proposed changes are acceptable.
Item 5, the change in the alarm setpoints of the BVPS-2 containment purge exhaust monitors, is intended to raise the setpoints to a level which will avoid inadvertent alarms and, yet, will be low enough to enable the system to serve its intended purposes. The principal purpose of these monitors is to actuate containment isolation and, thereby, to minimize the offsite and control room doses that could result from a fuel handling accident inside containment. The licensee repnrts, and the NRC staff has verified, that the
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. proposed ritpoints are low enough to ensure that the rslavant criteria are met, i.e. the offsite doses would be kept well below the criterik of 10 CFR Part 100 and the doses in the control room would not exceed the limits of General Destgr. Criterion 19.
The secondary objective is to ensure, 'sith the system operational and containment isolated, instantaneout ' ' rates off site are below the 10 CFR Part 50, Appendix I criteria of 500 nrm. ' to the whole body and 3,000 aren to the skin. The licensee showed, and the n'RC staff verified, that the proposed setpoints are sufficiently low to meet this objective. The NRC ctaff concludes that the proposed setpoints are low enough to mest the accident mitigation criteria while being high enough to sub n antially reduce the frequency of inadvertent actuation of an engineered safety feature. These proposed changes to the technical specifications are acceptable.
The proposed editorial changes do not c Nnge the intent or the requirements of any of the TSs and are, therefore, acci.;, table.
3.0 STATE CONSULTATION
In accordance with the Comission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments. The State official had no coments.
i 4.0 ENVIRONMENTAL CONSIDERATIDff The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significent increase in the amounts, and no significant change in the types, of any effluents tht 1 may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Comission has prevbusly issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (60 FR 65677 and fil FR 15988). The amendments also relate to changes in recordkeeping, re)orting, or administrative procedures or requirements. Accordingly, tie amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (10).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
5.0 CONCLUSION
The Comission 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 conducteo in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the comon defense and security or to the health and safety of the public.
Principal Contributor:
C. Willis Date: February 9, 1998 l
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6.0 REFERENCES
1.
Emergency Planning and Preparedness for Nuclear Power Reactors, U.S.
i Nuclear Regulatory Commission, Regulatory Guide 1.101, Revision 3, August i
1992 2.
Clarification of TMI Action Plan Requirements, Nuclear Regulatory Commission Report NUREG-0737, November 1980 8
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