ML20081H103

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Text

{{#Wiki_filter:. g oo%q y" S-UNITED STATES g g NUCLEAR REGULATORY COMMISSION o 's WASHINGTON, D.C. 20666 4 001 i .....} A SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION I RELATED TO AMENDMENT NO.196 TO FACILITY OPERATING LICENSE NO. NPF-3 TOLED0 EDISON COMPANY ~ CENTERIOR SERVICE COMPANY 81 @ I THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DAVIS-BESSE NUCLEAR POWER-STATION. UNIT NO. 1 DOCKET NO. 50-346

1.0 INTRODUCTION

l By {{#if: 

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  | [[letter::{{#ask:from::[[site::{{#show:ML20081H103|?site|limit=1|link=none}}]]Issue date::December 6, 1994|limit=1|link=none|searchlabel=}}|letter dated December 6, 1994]]
  | {{#ask:from::Issue date::December 6, 1994|limit=0|searchlabel=letter dated December 6, 1994 }}
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| {{#if:{{#show:ML20081H103|?site|limit=1|link=none}}
  | {{#if:{{#ask:[[site::{{#show:ML20081H103|?site|limit=1|link=none}}]]Issue date::December 6, 1994!~Information Notice*!~Press Release*}}
    | [[letter::{{#ask:[[site::{{#show:ML20081H103|?site|limit=1|link=none}}]]Issue date::December 6, 1994!~Information Notice*!~Press Release*|limit=1|link=none|searchlabel=}}|letter dated December 6, 1994]]
    | letter dated December 6, 1994
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  | letter dated December 6, 1994
  }}

}}, the licensee requested an amendment to the Davis-Besse Nuclear Power Station (DBNPS), Unit 1, operating license to revise the plant Technical Specifications (TS). The proposed changes ~ involve TS 3/4.1.3.1, " Group Height - Safety and Regulating Rod Groups;" TS'3/4.1.3.2, " Group Height - Axial Power Shaping Rod Group;" TS 3/4.4.6.2, " Operational i Leakage;" TS 3/4.5.2, "ECCS Subsystems - Tavg equal to or greater than 280*F;" i TS 3/4.6.2.1, " Containment Spray System;" and TS 3/4.10.4, "Special Test Exceptions Shutdown Margin." All the proposed TS changes are compatible with DBNPS operating experience and are consistent with NRC guidance provided by Generic Letter (GL) 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation," or NUREG-1430, " Improved Standard Technical. Specifications for B&W Plants." 2.0 EVALUATION The proposed change to TS 4.1.3.1.2 for the Movable Control Assemblies " Group Height - Safety and Regulating Rod Groups," will relax testing requirements from at least once every 31 days to every 92 days. This change is in conformance with the recommendation of GL 93-05, Enclosure 1, Section 4.2.1. Additionally, the DBNPS reliability data for the Control Rod Drive Control System was reviewed and supports extending the surveillance frequency. Since there is no expected adverse effect on safety as a result of extending the surveillance interval, the staff, therefore, concludes that the proposed change is acceptable. The proposed change to Technical Specification 3/4.1.3.2 will delete Surveillance Requirement (SR) 4.1.3.2.2, that presently requires each Axial i Power Shaping Rod (APSR), that is not fully withdrawn, be moved every 31 days and that the movement be at least 2% to verify OPERABILITY. This requirement was deleted from Rev'-'on 0 of NUREG-1430. The APSRs have no safety function 9503240093 950321 i PDR ADOCK 05000346 P PDRi

_2_ to insert in order to mitigate any design basis accident. In fact, by the design of the system, these rods are prevented from moving on a reactor trip. SR 4.1.3.2.1, which is not changing, still requires determining the position of i each APSR at least 'once per 12 hours except when the asymmetric rod monitor is i inoperable and then at least once every 4 hours. According to the submittal, the DBNPS reliability data for the movement of APSRs was reviewed and supports the removal of this surveillance requirement from the TS. The staff, therefore, concludes that the proposed change is acceptable. The proposed change to TS 4.4.6.2, for " Operational Leakage," relaxes the requirement to leakage test RCS pressure isolation valves prior to entering MODE 2, whenever the plant has been in COLD SHUTDOWN for 72 hours to whenever the plant has been in COLD SHUTDOWN for 7 days. The proposed change is in conformance with GL 93-05, Enclosure 1, Section 6.1. The DBNPS reliability data for the Control Rod Drive Control System was reviewed and supports extending the 24-hour time period during which to perform the rod full insertion test to 7 days. The staff, therefore, concludes that the proposed change is acceptable. The proposed change to SR 4.5.2.c.2 for TS 4.5.2, "ECCS Subsystems - Tavg equal to or greater than 280 F," relaxes the inspection requirements for ensuring no debris in containment from "at the completion of each containment entry" to "at least once daily while work is ongoing and again during the final exit after completion of work (containment closeout) when CONTAINMENT INTEGRITY is established." The current DBNPS TS require a containment debris inspection during the final exit for containment closecut. This change does rot make substantial changes to the previous requirements, nor does it change the method i of performing the surveillance. However, this change will limit the ;stential for radiation dose to people performing containment inspections when cantainment integrity is established by limiting the inspection to those areas where work is being performed and ensuring those areas are inspected at least daily. Although the proposed change uses plant specific language, the change meets the intent of GL 93-05, Enclosure 1, Section 7.5. The staff, therefore, concludes that the proposed change is acceptable. TS 4.6.2.1.d, for the " Containment Spray System," relaxes the SR to perform an air or smoke flow test through the spray header a ' mzles from once per 5 years to once per 10 years. This proposed change m accordance with GL 93-05, Enclosure 1, Section 8.1. As discussed in NL..o-1366, " Improvements to Technical Specifications Surveillance Requirements," Section 8.1, industry experience has shown that the 3 instances where the test detected system problems, that the problems were attributable to plant construction. At the DBNPS, this surveillance test has been satisfactorily performed in the past. Because this system is not used during normal operation, there is no mechanism by which these nozzles could be rendered nonfunctional. The staff, therefore, concludes that the proposed change is acceptable. l TS 4.10.4.2 for "Special Test Exceptions Shutdown Margin" relaxes the SR interval for testing rod insertion capability prior to reducing the shutdown margin from 24 hours to 7 days. This proposed change is in accordance with GL 93-05, Enclosure 1, Section 12. The DBNPS reliability data for the Control Rod Drive Control System was reviewed and supports extending the 24-hour time period

. during which to perform the rod full insertion test to 7 days. Based on the review of each proposed change and determination that the proposed changes will not have an adverse effect on safety, the staff concludes that the proposed changes are acceptable and should be approved.

3.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Ohio State official was notified of the proposed issuance of the amendment. The State official had no comments.

4.0 ENVIRONMENTAL CONSIDERATION

This 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 staff has determined that the amendment involves no significant increase in the amounts, and no significant chan9e 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 (60 FR 8757). Accordingly, the 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 connection with the issuance of the amendment.

5.0 CONCLUSION

The staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the he:lth 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 Commission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributor: L. L. Gundrum Date: March 21, 1995}}

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