ML20214U428
| ML20214U428 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/25/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214U425 | List: |
| References | |
| TAC-61054, TAC-61280, TAC-61504, NUDOCS 8610010004 | |
| Download: ML20214U428 (3) | |
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UNITED STATES e
o NUCLEAR REGULATORY COMMISSION t,
y WASHINGTON, D. C. 20655
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.129 TO FACILITY OPERATING LICENSE N0. DPR-57 GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 DOCKET N0. 50-321
1.0 INTRODUCTION
By letter dated March 3,1986, Georgia Power Company, et al. (the licensee) proposed deletion of Table 3.7-1, " Primary Containment Isolation Valves, "
from the Hatch Unit 1 Technical Specifications. The table would be replaced with references to valve listings in applicable plant procedures.
Removal of component lists from Technical Specifications has been proposed as a generic change to the Standard Technical Specifications (STS) by the Atomic Industrial Forum and Owners Groups. Due to the significance of this proposal, the staft is in the process of developing generic guidelines for implementing this recommendation and updating the STS. Since this effort is not completed, the review of the proposed deletion of Table 3.7-1 will be delayed until completion of the generic effort.
Based on the staff's position, the licensee, in a letter dated April 15, 1986 for Hatch Unit 1, proposed changes which would update rather than delete valve listings in Table 3.7-1 and Table 3.7-4,
" Primary Containment Testable Isolation Valves." The following is the staff evaluation of the proposed TS updates.
2.0 EVALUATION Proposed Change 1:
To clarify its intent, the licensee proposes to change the title of Table 3.7-1 in Technical Specification for Hatch Unit 1, page 3.7-16, from Primary Containment Isolation Valves to Primary Containment Isolation valves Which Receive A7rimary Containment Isolation Signal.. This table is needed for the implementation of Technical Specification 4.7.D.1.a which requires the surveillance testing of operable isolation valves that are power operated and automatically initiated to be tested for simulated automatic initiation and the closure times specified in Table 3.7-1.
The proposed Table 3.7-1 contains only power operated Primary Containment Isolation Valves (PCIVs) which receive a containment isolation signal. This proposed change provides consistency within the Technical Specification and is, therefore, acceptable.
8610010004 860925 PDR ADOCK 05000321 P
2 Prope. sed Change 2:
This proposed change would delete reference to Table 3.7-1 from the Hatch Unit 1 Technical Specification 3.7.D.1.
The present Technical Specification requires operability of all PCIVs listed in Table 3.7-1.
Deletion of the reference to Table 3.7-1, as proposed, requires that all PCIVs shall be operable, including automatic PCIVs in Table 3.7-1 and non-automatic PCIVs. Since this proposed change is conservative, it is acceptable.
Proposed Change 3:
This proposed change is to delete check valves from Table 3.7-1 of the Hatch Unit 1 Technical Specification and add nine of them to Table 3.7-4.
The remaining two check valves are not Appendix J tested and are not included in lable 3.7-4.
Since the proposed Table 3.7-1 is for surveillance of automatic PCIVs which receive a primary containment isolation signal and the check valves are not in this category, it is acceptable to delete the check valves from Table 3./-1.
Proposed Change 4:
The proposed change is to include additional automatic PCIVs in Table 3.7-1.
Some of the additional valves have been included due to plant design changes, while others were not previously listed in Table 3.7-1 although they met the criteria for inclusion. Since this proposed change is conservative and will result in additional Technical Specification requirements, the proposed inclusion of additional valves in Table 3.7-1 is acceptable.
Proposed Change 5:
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The proposed change is editorial in nature.
It corrects the Technical Specification for Hatch Unit 1 to accurately reflect actual plant conditions and does not represent a change in PCIV operation or configuration. Since this change upgrades the accuracy of the Technical Specification, it is acceptable.
t Proposed Change 6:
This proposed change provides a listing in Table 3.7-4 of the Hatch Unit 1 Technical Specification of PCIVs subject to leak rate testing under the provisions of 10 CFR 50, Appendix J.
This proposed table differs from the present table by including corrections to erroneous listings, additions and deletions to valve listings, as well as changes to descriptive information and notes relevant to this table. This proposed change is acceptable since it corrects Table 3.7-4 to be consistent with a listing of PCIVs that require testing under 10 CFR 50 Appendix J.
Proposed Change 7:
This change provides a note to Table 3.7-4 to indicate the method of testing.
Since the method of testing meets applicable criteria per 10 CFR 50, Appendix J, the proposed change is acceptable.
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3 Proposed Change 8:,.
The proposed change adds 72 valves to Table 3.7-4 which are currently listed in plant leak rate test procedures. This proposed change is acceptable since it is conservative and provides consistency between the technical Specifications and plant leak rate test procedures.
Proposed Change 9:
This proposed change deletes 26 valves presently listed in Table 3.7-4 which do not require leak rate testing because the valves do not serve as the primary containment isolation boundary. This proposed change is acceptable since the deleted valves are not PCIVs and are not part of the primary isolation boundary.
On the basis of our evaluation, we conclude that the proposed changes which clarify and correct the Hatch Unit 1 Technical Specifications with respect to containment isolation valves are acceptable. While acceptable, the staff notes that the relevant portions of the Hatch Unit 1 Technical Specifications differ from Unit 2.
Since the licensee has proposed that Hatch be the lead plant for technical specifications improvement, these differences should be resolved during this review.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment changes a requirement with respect to installation or use of a facility component located within the restricted areas as defined in 10 CFR Part 20. The 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 should be no significant
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increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendirent involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categoricalexclusionsetforthin10CFR51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement nor environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
On the basis of the considerations discussed above, the staff has concluded 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 Comissior,'s regulations.
Principal Contributor:
F. Witt Dated: September 25, 1986